Abstract: The micronucleus assay is an important technique used to evaluate genotoxic damage of chemical or physical agents (as ionizing radiations) on cells, based on quantification of cells bearing micronuclei, which are fragments derived from damage (breakage) of the DNA. Currently, this technique was updated to an automated approach that relies on plasma membrane dissolution to analyze fluorescent dye-labelled nuclei and micronuclei by flow cytometry. Cell suspensions were irradiated in PBS by a ⁶⁰Co source in doses between 0 and 16Gy, and incubated by 48h. Cell membranes were lysed in the presence of SYTOX Green and EMA dyes, so EMA-stained nuclei could be discriminated as from dead cells, and nuclei and micronuclei could be quantified. Amounts of micronuclei (percent of events) in the samples, were found to be proportional to radiation doses, and could be fitted to a linear-quadratic model (R² = 0.993). Only higher doses (8 and 16Gy) and positive control could induce relevant increases in micronucleus amounts. The incorporation EMA showed an increase in irradiated cells. Midto high doses (4, 8 and 16Gy) induced reduction of cell proliferation. Experiments showed the suitability of the technique to replace traditional microscopy analysis in evaluation of the effects of ionizing radiations on cells, with possibility to use in biological dosimetry.

Palavras-Chave: cell flow systems; cell membranes; cell nuclei; cell proliferation; cho cells; cobalt 60; dosimetry; radiation effects

CARVALHO, LUMA R. de; BONFIM, LETICIA; VIEIRA, DANIEL P. Use of 2-color flow cytometry to assess radiationinduced geotoxic damage on cho-ki cells. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 22-27, 2017, Belo Horizonte, MG. Proceedings... Rio de Janeiro, RJ: Associação Brasileira de Energia Nuclear, 2017. Disponível em: http://repositorio.ipen.br/handle/123456789/28296. Acesso em: $DATA.

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Abstract: Since 2001 the Nuclear and Energy Research Institute (IPEN/CNEN-SP, Brazil) has produced about 2.5 mCi/mAh of 123I weekly using a manual irradiation system fully developed by its researchers. Ultrapure 123I has been produced and distributed to hospitals and clinics where several diagnostic imaging procedures are done for thyroid, brain and cardiovascular functions. Due to the short half-life and emission of low-energy photons, this radioisotope becomes suitable for diagnosis in children. Currently IPEN researchers are involved in the development of a new fully automated irradiation system dedicated to 123I routine production employing enriched xenon gas (124Xe) as the target material. This new system consists of a target port, a water and a helium cooling system, a cryogenic system, an electric power system, a control and process monitoring unit composed of a supervisory software connected to a Programmable Logic Controller (PLC) via personal computer. In this new concept, there is no need for human interference during radioisotope production, reducing the possibility of eventual failures or incidents involving radioactive material. In this way, with this new system, a specific yield of approximately 3.5 mCi/mAh per irradiation is expected and this will meet a large part of the national demand for this important radioisotope. In the present work will be presented all the technical and constructive aspects of this new system as well as the results obtained in the irradiation of tests.

Palavras-Chave: automation; cyclotrons; iodine 123; irradiation devices; isotope production; performance testing; remote control; xenon 124

LAPOLLI, ANDRE L.; BARCELLOS, HENRIQUE; MATSUDA, HYLTON; SUMIYA, LUIZ C. do A.; JUNQUEIRA, FERNANDO de C. A new 124Xe irradiation system for 123I routine production at the 30 MeV IPEN-CNEN/SP cyclotron. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 22-27, 2017, Belo Horizonte, MG. Proceedings... Rio de Janeiro, RJ: Associação Brasileira de Energia Nuclear, 2017. Disponível em: http://repositorio.ipen.br/handle/123456789/28294. Acesso em: $DATA.

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Abstract: Edible films and coatings have received considerable attention in recent years for their advantages over synthetic films for edible packaging materials. Chia seeds (Salvia hispanica L.) have functional and important nutritional values: protein content (15–25%), fats (30–33%), carbohydrates (26–41%), dietary fiber (18–30%), and ash (4-5%). It also contains a high amount of vitamins, minerals, and antioxidants. Mucilage of chia, a natural exudates from chia seeds, is mainly composed of xylose, glucose and glucuronic acid forming a branched polysaccharide. In the present preliminary work whole chia seeds were irradiated in a 60Co source Gammacell 220 (AECL) with doses of 0, 5 and 10 kGy, dose rate about 0.8 kGy h-1. The irradiated seeds were crushed and soaked in an aqueous solution (6% w/w) together with glycerol (1% w/w), under magnetic stirring for 15 minutes at room temperature and poured into casting plates. The plates were placed in an oven with forced air circulation at 35 °C for at least 20 h. Water uptake, moisture, solubility and water activity of the films were established. The most expressive result was a decrease in water uptake with the increase of the radiation dose. Solubility remained almost unaffected by radiation in doses of 5kGy and moisture analysis showed also a decrease with dose.

Palavras-Chave: cobalt 60; films; polysaccharides; radiation doses; radiation effects; seeds; uptake; water

CHIERENTIN, GABRIEL S.; TEIXEIRA, BRUNA S.; MASTRO, NELIDA L. DEL. The effect of gamma radiation on chia (Salvia hispanica L.) edible film. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 22-27, 2017, Belo Horizonte, MG. Proceedings... Rio de Janeiro, RJ: Associação Brasileira de Energia Nuclear, 2017. Disponível em: http://repositorio.ipen.br/handle/123456789/28292. Acesso em: $DATA.

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Abstract: The HTGR ( High Temperature Gas-cooled Reactor) is a 4th generation nuclear reactor and is fuelled by a mixture of graphite and fuel-bearing microspheres. There are two competitive designs of this reactor type: The German “pebble bed” mode, which is a system that uses spherical fuel elements, containing a graphite-and-fuel mixture coated in a graphite shell; and the American version, whose fuel is loaded into precisely located graphite hexagonal prisms that interlock to create the core of the vessel. In both variants, the coolant consists of helium pressurised. The HTGR system operates most efficiently with the thorium fuel cycle, however, so relatively little development has been carried out in this country on that cycle for HTGRs. In the Nuclear Engineering Centre of IPEN (Instituto de Pesquisas Energéticas e Nucleares), a study group is being formed linked to thorium reactors, whose proposal is to investigate reactors using thorium for 233U production and rejects burning. The present work intends to show the use of thorium in HTGRs, their advantages and disadvantages and its feasibility.

Palavras-Chave: fuel cycle; htgr type reactors; nuclear fuels; pebble bed reactors; reactor safety; thermal efficiency; thorium

GUIMARAES, CLAUDIO Q.; STEFANI, GIOVANNI L. de; SANTOS, THIAGO A. dos. Use of thorium for high temperature gas-cooled reactors. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 22-27, 2017, Belo Horizonte, MG. Proceedings... Rio de Janeiro, RJ: Associação Brasileira de Energia Nuclear, 2017. Disponível em: http://repositorio.ipen.br/handle/123456789/28290. Acesso em: $DATA.

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Abstract: Lithium is a material of great interest in the world, it is found in different minerals on Earth's crust (spodumene, lepidolite, amblygonite and petalite) also in salt pans. This element belongs to alkaline group and has two natural isotopes: Li-6 and Li-7. In the nuclear field, lithium isotopes are used for different purposes. The Li-6 is applied in the production of energy, because its section of shock is larger than the other isotope. The Li-7 regulates the pH in refrigerant material in the primary circuits of the Pressurized Water Nuclear Reactor (PWR). In nuclear reactor, lithium is used as a heat transfer due its boiling temperature (1342°C), making it an excellent thermal conductor. However, to reach all these applications, lithium must have high purity (> 99%). The main processes to reach a high purity level of lithium employee a combination of solvent extraction and ion exchange process, to obtain its salts or ending with chemical electrolysis of its chlorides to obtain its pure metal. This work presents a review of new applications of Lithium in Nuclear Energy and its purification and enrichment processes.

Palavras-Chave: brines; impurities; ion exchange; lithium 6; lithium 7; nuclear energy; solvent extraction

OLIVEIRA, GLAUCIA A.C. de; BUSTILLOS, JOSE O.V.; FERREIRA, JOAO C.; BERGAMASCHI, VANDERLEI S.; MORAES, RAFAELI M. de; GIMENEZ, MAISE P.; MIYAMOTO, FLAVIA K.; SENEDA, JOSE A. Applications of lithium in nuclear energy. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 22-27, 2017, Belo Horizonte, MG. Proceedings... Rio de Janeiro, RJ: Associação Brasileira de Energia Nuclear, 2017. Disponível em: http://repositorio.ipen.br/handle/123456789/28288. Acesso em: $DATA.

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Abstract: Optimization of nuclear fuel for use in pressurized water reactors can be achieved by obtaining higher burnups. This, however, requires the excess reactivity caused by increasing the fuel's enrichment to be taken into account, which can be done by introducing burnable absorbers into the UO2 fuel pellets themselves. Some of the rare earth elements have thermal and mechanical properties that make them appropriate for use inside the reactor. In order to characterize the microstructure of erbium-doped UO2 fuel, sintered UO2-Er2O3 pellets were prepared, with Er2O3 content ranging from 1:0 to 9:8wt%, and analyzed by X-ray di raction to determine whether the composite formed solid solutions and, if so, evaluate the lattice parameter as a function of erbia concentration. While XRD analysis showed the Er2O3 completely dissolved in the UO2 powder, it also evidenced the emergence of a second uorite-type phase, whose phase fraction increases and lattice parameter decreases with increasing erbia concentration. Analysis of the di raction patterns showed this emerging phase has the same crystalline structure as the host lattice, but with a smaller lattice parameter, and a smaller domain size. These results are compatible with the phenomenon of defect segregation, which consists in the formation of microdomains with a higher concentration of defects.

Palavras-Chave: crystal-phase transformations; doped materials; erbium; erbium; fuel pellets; lattice parameters; nanostructures; nuclear fuels; optimization; uranium dioxide

SANSONE, ALBERTO E.S.; RIELLA, HUMBERTO G.; CARVALHO, ELITA F.U. de. Characterization of crystalline phases of (U,Er)O2 pellets by X-ray diffraction. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 22-27, 2017, Belo Horizonte, MG. Proceedings... Rio de Janeiro, RJ: Associação Brasileira de Energia Nuclear, 2017. Disponível em: http://repositorio.ipen.br/handle/123456789/28286. Acesso em: $DATA.

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Abstract: The experiment aimed to verify if seeds of cotton of variety FiberMax FM 993, irradiated with the doses of 0 (test); 25; 50; 75; 100 Gy can induce the production increase in cotton culture. For all treatments with irradiation, was used a source of cobalt-60, type Gammacell 220. After the irradiation, the seeds were planted in the experimental field of the Department of Plant Production ESALQ-USP, Piracicaba-SP. The experimental design was randomized blocks with four replications and 60 g of seed were used for each repetition, the rows were 5m and the spacing of 0.90m, using randomized blocks and rows of edging. After planting the final height and productivity were evaluated. The obtained data were statistically analyzed in the Tukey test at 5% level of probability. From the results obtained, it was concluded that the dose of 50Gy was the one that induced a greater production of cotton.

Palavras-Chave: augmentation; cobalt 60; cotton; dose rates; experimental data; germination; productivity; radiation effects; seeds

ARAUJO, ANA L.; ARTHUR, PAULA B.; FRANCO, CAMILO F. de O.; ARTHUR, VALTER. Effects of the irradiation in seeds of cotton. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 22-27, 2017, Belo Horizonte, MG. Proceedings... Rio de Janeiro, RJ: Associação Brasileira de Energia Nuclear, 2017. Disponível em: http://repositorio.ipen.br/handle/123456789/28284. Acesso em: $DATA.

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Abstract: The 99Mo/99mTc generator is widely used in nuclear medicine and it consists of a glass column containing Teflon® strips and alumina in which 99Mo produced by 235U fission is adsorbed. The 99mTcO4- eluate shall meet the sterile and pyrogen free conditions for injectable radiopharmaceuticals as determined by the Good Manufacturing Practices. The purpose of this study was to evaluate the feasibility of using gamma radiation in the sterilization of the 99Mo/99mTc generator column and the influence on the elution efficiency. Alumina-containing columns were irradiated with 10, 15, 25 and 50 kGy absorbed doses. Alumina samples and control (non-irradiated) were submitted to X-ray diffraction and the combined use of scanning electron microscopy and elemental analysis. Teflon® samples were evaluated by thermogravimetry (TGA) and differential scanning calorimetry (DSC). X-ray diffractograms and micrographies with elemental analysis showed no significant changes in the crystalline structure of the alumina because it was stable α-Al2O3. TGA demonstrated that higher doses showed changes in lower temperatures and times than the control material. For DSC the higher the absorbed dose, the greater the polymer chain breakage and crosslinking in the material. The generator system without radioactivity was set up with the irradiated columns and the eluates demonstrated to be sterile and pyrogen free. The effects of different absorbed doses on the generator column, although some reported changes in the materials, demonstrated that the sterilization of the columns by irradiation with gamma rays as an alternative to wet heat sterilization is feasible from a technical and financial point of view.

Palavras-Chave: absorbed radiation doses; aluminium oxides; calorimetry; cobalt 60; feasibility studies; molybdenum 99; radioisotope generators; sterilization; technetium 99; thermal gravimetric analysis

FUKUMORI, NEUZA T.O.; MENGATTI, JAIR; MATSUDA, MARGARETH M.N. Evaluation of 99Mo/99mTc generator columns after irradiation with different absorbed doses. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 22-27, 2017, Belo Horizonte, MG. Proceedings... Rio de Janeiro, RJ: Associação Brasileira de Energia Nuclear, 2017. Disponível em: http://repositorio.ipen.br/handle/123456789/28282. Acesso em: $DATA.

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Abstract: Ionizing radiation has been used as an important treatment and diagnostic method for several diseases. Optical techniques provides an efficient clinical diagnostic to support an accurate evaluation of the interaction of radiation with molecules. Fourier-transform infrared spectroscopy coupled with attenuated total reflectance (ATR-FTIR) is a label-free and nondestructive optical technique that can recognize functional groups in biological samples. In this work, 30 fragments of bone were collected from bovine femur diaphysis. Samples were cut and polished until 1 cm x 1 cm x 1 mm, which were then stored properly in the refrigerated environment. Samples irradiation was performed with a Cobalt-60 Gammacell Irradiator source at doses of 0.1 kGy, 1 kGy, whereas the fragments exposed to dose of 15 kGy was irradiated in a multipurpose irradiator of Cobalt-60. Spectral data was submitted to principal component analysis followed by linear discriminant analysis. Multivariate analysis was performed with Principal component analysis(PCA) followed by Linear Discriminant Analysis(LDA) using MATLAB R2015a software (The Mathworks Inc., Natick, MA, USA). We demonstrated the feasibility of using ATR-FTIR spectroscopy associated with PCA-LDA multivariate technique to evaluate the molecular changes in bone matrix caused by different doses: 0.1 kGy, 1 kGy and 15 kGy. These alterations between the groups are mainly reported in phosphate region. Our results open up new possibilities for protein monitoring relating to dose responses.

Palavras-Chave: cattle; cobalt 60; femur; fourier transformation; infrared spectra; ionizing radiations; multivariate analysis; radiation dose ranges; radiation doses; radiation effects

CASTRO, PEDRO A.A. de; DIAS, DERLY A.; ZEZELL, DENISE M. Characterization of ionizing radiation effects on bone using Fourier Transform Infrared Spectroscopy and multivariate analysis of spectra. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 22-27, 2017, Belo Horizonte, MG. Proceedings... Rio de Janeiro, RJ: Associação Brasileira de Energia Nuclear, 2017. Disponível em: http://repositorio.ipen.br/handle/123456789/28278. Acesso em: $DATA.

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Abstract: This paper describes the Monte Carlo simulation, using MCNP4C, of a multichannel third generation tomography system containing a two radioactive sources, 192I (316.5 – 468 KeV) and 137Cs (662 KeV), and a set of fifteen NaI(Tl) detectors, with dimensions of 1 inch diameter and 2 inches thick, in fan beam geometry, positioned diametrically opposite. Each detector moves 10 steps of 0,24o, totalizing 150 virtual detectors per projection, and then the system rotate 2 degrees. The Monte Carlo simulation was performed to evaluate the viability of this configuration. For this, a multiphase phantom containing polymethyl methacralate (PMMA ((  1.19 g/cm3)), iron ( 7.874 g/cm3), aluminum (  2.6989 g/cm3) and air (  1.20479E-03 g/cm3) was simulated. The simulated number of histories was 1.1E+09 per projection and the tally used were the F8, which gives the pulse height of each detector. The data obtained by the simulation was used to reconstruct the simulated phantom using the statistical iterative Maximum Likelihood Estimation Method Technique (ML-EM) algorithm. Each detector provides a gamma spectrum of the sources, and a pulse height analyzer (PHA) of 10% on the 316.5 KeV and 662 KeV photopeaks was performed. This technique provides two reconstructed images of the simulated phantom. The reconstructed images provided high spatial resolution, and it is supposed that the temporal resolution (spending time for one complete revolution) is about 2.5 hours.

Palavras-Chave: cesium 137; computerized simulation; computerized tomography; configuration; iridium 192; monte carlo method; nai detectors; phantoms; spatial resolution

VELO, A.F.; ALVAREZ, A.G.; CARVALHO, D.V.S.; FERNANDEZ, V.; SOMESSARI, S.; SPRENGER, F.F.; HAMADA, M.M.; MESQUITA, C.H. A third generation tomography system with fifteen detectors and a gamma-ray source in fan beam geometry simulated by Monte Carlo Method. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 22-27, 2017, Belo Horizonte, MG. Proceedings... Rio de Janeiro, RJ: Associação Brasileira de Energia Nuclear, 2017. Disponível em: http://repositorio.ipen.br/handle/123456789/28276. Acesso em: $DATA.

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Abstract: Because of the increase in the demand for the calibration of neutron detectors, there is a need for new calibration services. In this context, the Calibration Laboratory of Instituto de Pesquisas Energéticas e Nucleares (IPEN), São Paulo, which already offers calibration services of radiation detectors with standard X, gamma, beta and alpha beams, has recently projected a new test laboratory for neutron detectors. This work evaluated the contribution of dispersed neutron radiation in this laboratory, using the cone shadow method and a Bonner sphere spectrometer to take the measurements at a distance of 100 cm from the neutron source. The dosimetric quantities Ḣ*(10) and Ḣp(10) were obtained at the laboratory, allowing the calibration of detectors.

Palavras-Chave: neutron sources; calibration; neutron activation analysis; neutron detectors; radiation scattering analysis; bonner sphere spectrometers; americium 241; shadow effect; brazilian cnen

ALVARENGA, TALLYSON S.; FREITAS, BRUNO M.; FONSECA, EVALDO S.; PEREIRA, WALSAN W.; CALDAS, LINDA V.E. Determination of the scattered radiation at the neutron calibration laboratory of IPEN using the shadow cone method. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 22-27, 2017, Belo Horizonte, MG. Proceedings... Rio de Janeiro, RJ: Associação Brasileira de Energia Nuclear, 2017. Disponível em: http://repositorio.ipen.br/handle/123456789/28274. Acesso em: $DATA.

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Abstract: In the development of a thermal neutron detector using a square photodiode and a thin boron film, a radioactive calibration source with the same geometry was needed. An americium-243 standard source was produced by electrodeposition aiming at the calibration of a PIN-type silicon photodiode with a detection area of 10 x 10 mm2. To produce the samples two tests were performed. In the first test, a square stainless steel plate (10 x 10 mm2) was fixed on the surface of the conventional plate, which was removed after deposition. To reduce the loss of activity of the source, in the second test nail polish was applied on the silver plate leaving only an area of 10 x 10 mm2 without varnish coating. Once the electrodeposition process was completed, the activity concentration measurement was performed by alpha particle spectrometry. The first method presented a lower activity when compared to the total activity of Am-243 added initially. For the second method, the total activity was concetrated in the exposed square region (without nail polish).The results showed that it is possible to obtain a square geometry source; furthermore, the surrounding nail polish was not contaminated by 243Am. The comparison of these two approaches indicated that the second method was more efficient as it was possible to concentrate all the americium activity in the delimitated square area.

Palavras-Chave: americium 243; boron; calibration; electrodeposition; neutron detectors; photodiodes; brazilian cnen; silicon; square configuration; stainless steels; thermal neutrons; thin films

COSTA, PRISCILA; GERALDO, BIANCA; RAELE, MARCUS P.; MARUMO, JULIO T.; VICENTE, ROBERTO; ZAHN, GUILHERME S.; GENEZINI, FREDERICO A. Production of a square geometry americium standard source for use with photodiodes. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 22-27, 2017, Belo Horizonte, MG. Proceedings... Rio de Janeiro, RJ: Associação Brasileira de Energia Nuclear, 2017. Disponível em: http://repositorio.ipen.br/handle/123456789/28272. Acesso em: $DATA.

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Abstract: A low-cost amplifier for Hamamatsu S3590-09 PIN photodiode to be used in alfa detection is presented. This amplifier consists basically of two circuits: a pulse preamplifier and a shaper-driver. The PIN photodiode is reverse-biased and connected to a charge preamplifier input. Incident alpha particles generate a small current pulse in the photodiode. The integrating circuit of the low noise preamplifier transforms current pulse into a voltage pulse with amplitude proportional to the charge carried by the current pulse. The shaper-driver consists of a differentiator and an integrator and is responsible for filtering and further amplifying the preamplifier signal, generating a NIM-compatible energy pulse. The performance of the set photodiode-amplifier was successively tested through the use of a 243Am radioactive source. The low-cost photodiode amplifier was designed and constructed at IPEN - CNEN/SP using national components and expertise.

Palavras-Chave: alpha detection; alpha spectrometers; americium 243; amplifiers; performance; photodiodes; brazilian cnen; radiation monitoring

DOMIENIKAN, CLAUDIO; COSTA, PRISCILA; GENEZINI, FREDERICO A.; ZAHN, GUILHERME S. Low-cost amplifier for alpha detection with photodiode. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 22-27, 2017, Belo Horizonte, MG. Proceedings... Rio de Janeiro, RJ: Associação Brasileira de Energia Nuclear, 2017. Disponível em: http://repositorio.ipen.br/handle/123456789/28270. Acesso em: $DATA.

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Abstract: Neutron activation analysis and gamma-ray spectrometry was used to determine 238U, 226Ra, 228Ra, 210Pb, 232Th and 40K contents in feed pulverized coal, bottom ash, fly ash from cyclone and baghouse filters, zeolites synthesized from the ashes and two different soil samples. All the samples used in the study was collected at Figueira thermoelectric power plant, located in the city of Figueira, Paraná State, which coal presents a significant amount of uranium concentration. The natural radionuclide concentrations in pulverized coal were 4216 Bq kg–1 for 238U, 180 Bq kg–1 for 226Ra, 27 Bq kg–1 for 228Ra, 28 Bq kg–1 for 232Th and 192 Bq kg–1 for 40K. The ashes fraction presented concentrations ranging from 683.5 to 1479 Bq kg–1 for 238U, from 484 to 1086 Bq kg–1 for 226Ra, from 291 to 1891 Bq kg–1 for 210Pb, from 67 to 111 Bq kg–1for 228Ra, from 80 to 87 Bq kg–1 for 232Th and from 489 to 718 Bq kg–1 for 40K. Similar ranges were observed for zeolites. The activity concentration of 238U was higher than worldwide average concentration for all samples. The concentration of the uranium series found in the ashes were lower than the values observed in similar studies carried out 10 years ago and under the limit adopted by the Brazilian guideline (CNEN-NN-4.01). Nevertheless, the concentrations of this specific area are higher than others coal mines and thermoelectric power plants in and out of Brazil, so it is advisable to evaluate the environmental impact of the installation.

Palavras-Chave: baghouses; coal; concentration ratio; contamination; fly ash; natural radioactivity; soils; thermoelectricity; zeolites

FUNGARO, DENISE A.; SILVA, PAULO S.C. da; CAMPELLO, FELIPE A.; MIRANDA, CAIO da S.; IZIDORO, JULIANA de C. Evaluation of radionuclide contamination of soil, coal ash and zeolitic materials from figueira thermoelectric power plant. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 22-27, 2017, Belo Horizonte, MG. Proceedings... Rio de Janeiro, RJ: Associação Brasileira de Energia Nuclear, 2017. Disponível em: http://repositorio.ipen.br/handle/123456789/28268. Acesso em: $DATA.

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Abstract: The indiscriminate use of phosphate fertilizers causes adverse effects on biota, mainly due to the contaminants present in the rocks used in their manufacture. Among these contaminants, stand out the Rare Earth Elements (REEs) because of the significant increase in the use in several technological areas, such as in vehicle catalysts and also in fertilizer enrichment. In order to evaluate the levels of La, Sm, Nd, Yb and Lu by the Instrumental Neutron Activation Analysis (INAA), the present study aims to survey the ETRs in agricultural soils in Pernambuco/Brazil. For this study, 120 soil samples with a depth of 20 cm were collected in the main vegetable producing regions of the Metropolitan Region of Recife (RMR), evaluating organic and conventional crops with and without influenced by automotive vehicles. The results obtained when compared to the Netherlands reference values defined by the National Institute of Health and Environment (RIVM). The results were higher in all points for La (35 mg.kg-¹ at 85 mg.kg-¹) Yb, (4 mg.kg-¹ at 11 mg.kg-¹) and Lu (0.3 mg.kg-¹ at 0.7 mg.kg-¹ at 4 mg.kg-¹). For Nd (9 mg.kg-¹ at 137 mg.kg-¹) the concentrations were above the values reported by RIVM in 4 points. Comparing the types of crops evaluated with the literature, the results are found was above for all elements analyzed. It may be related to the increase in the use of phosphate fertilizers. However, in environments using smaller amounts of additives, the results were also significant and the more detailed studies are needed to evaluate other possible contamination pathways.

Palavras-Chave: activity levels; agriculture; crops; ecological concentration; elements; irradiation; neutron activation analysis; rare earths; soils; thermal neutrons; vehicles

FRANÇA, FERNANDA C.S.S.; TICIANELLI, REGINA B.; MOREIRA, EDSON G.; GENEZINI, FREDERICO A.; ALBUQUERQUE, ADRIANA M. de A.; SILVEIRA, PATRICIA B. da; BARBOSA, JONNAS T. de L.; ALMEIDA, AMANDA C. de; HONORATO, ELIANE V.; HAZIN, CLOVIS A. Determination of REEs in agricultural soils of pernambuco by the neutron activation technique. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 22-27, 2017, Belo Horizonte, MG. Proceedings... Rio de Janeiro, RJ: Associação Brasileira de Energia Nuclear, 2017. Disponível em: http://repositorio.ipen.br/handle/123456789/28266. Acesso em: $DATA.

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Abstract: São Paulo is one of the most populated cities in the world, with about 20 million inhabitants in its metropolitan area, more than 12 million motor vehicles and intense industrial activity. Given its importance as a major urban center in South America and the lack of information concerning urban dust composition, the present study aimed to determine rare earth elements (REEs), U and Th mass fractions in tunnel dust, collected in the Jânio Quadros Tunnel, and to assess their possible sources. The study of REEs distribution in urban environments has become of interest over the last decades, due to the increasing industrial use of these elements. The REEs, that are as common as the most familiar metals, are found in metallurgical additives, fluid cracking catalysts and automobile converter catalysts, among other applications. In this study, which employed Instrumental Neutron Activation Analysis (INAA) as analytical technique, the mass fractions of eight REEs were determined and normalized to the chondrite concentration values. The results showed that major concentrations were found for light REEs, following the sequence Ce > La > Nd > Sm > Yb > Eu > Tb > Lu. The pattern of the results pointed to a natural origin for these elements. Regarding U and Th concentrations, the results varied between 1.0 – 9.4 μg g-1 and 3.3 – 35.9 μg g-1, respectively. Since there is almost no information about the concentration of these elements in this kind of matrix in São Paulo city, these data are important to support further investigations.

Palavras-Chave: chondrites; concentration ratio; dusts; neutron activation analysis; rare earths; thorium; tunnels; uranium; urban areas

NORY, RENATA M.; FIGUEIREDO, ANA M.G. Rare earth elements, U and Th in tunnel dusts of São Paulo City, Brazil. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 22-27, 2017, Belo Horizonte, MG. Proceedings... Rio de Janeiro, RJ: Associação Brasileira de Energia Nuclear, 2017. Disponível em: http://repositorio.ipen.br/handle/123456789/28264. Acesso em: $DATA.

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Abstract: In the present study the preliminary results for 2 sediment cores from the Itupararanga Reservoir are presented. Instrumental neutron activation analysis was also applied to the sediment samples to determine the total concentration of some metal, trace and rare earth elements. The results obtained were compared to the reference values NASC (North American Shale Composite). The enrichment factor (EF) was applied to the results obtained by using NASC (North American Shale Composite) and the concentration values of the last layer of this profile as reference values for sediment contamination index assessment. The EF calculated with the NASC values presented enrichment for As, Ce, Fe, La, Th and U in the two profiles Nd, Sm Hf and Tb, only present enrichment in the 2nd campaign. However, with respect to the base of the profile there was no element with enrichment. For semi metal As and for metals Cr and Zn the concentration values were compared to the oriented values from Environmental Canada (TEL and PEL). As and Cr presented values between TEL and PEL and Zn, values below TEL. The distribution pattern of light and heavy REEs was also verified in relation to the normatization of PAAS (Pos Archean Australian Shale).

Palavras-Chave: calibration standards; comparative evaluations; concentration ratio; elements; environmental impacts; sediments; trace amounts; water pollution; water reservoirs

SILVA, SHARLLENY A.; HENRIQUE, HELOISE A.R.; FAVARO, DEBORAH I.T. Metal, trace and rare earth element assessment in a sedimentary profile from Itupararanga Reservoir, São Paulo State, Brazil, by NAA. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 22-27, 2017, Belo Horizonte, MG. Proceedings... Rio de Janeiro, RJ: Associação Brasileira de Energia Nuclear, 2017. Disponível em: http://repositorio.ipen.br/handle/123456789/28262. Acesso em: $DATA.

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Abstract: It has been reported that the formation and stabilization of coastal dune fields in Brazil have a dependence on the climate changes and Relative Sea Level (RSL) variations. A few topics regarding the morphodynamics of coastal aeolian systems in Brazil can be the RSL variations in the Holocene and weather conditions. In this work, a dune field known as “Dama Branca”, located in the town of Cabo Frio, Rio de Janeiro, has been studied to understand its formation and stabilization. Dating by trapped charge dating techniques as Optically Stimulated Luminescence (OSL) using the Single Aliquot Regenerative protocol (SAR), help us to understand the formation and dynamics of aeolian systems in Brazil. Samples from a dune were collected from different heights and points for dating. The results obtained by OSL-SAR showed that ages decrease as the height from the dune base increase and older samples are found in deeper horizontal positions. The ages for the base of the studied dunes indicated that its stabilization occurred during the recess of the sea level.

Palavras-Chave: age estimation; climatic change; equivalent radiation doses; luminescence; morphology; natural radioactivity; quartz; sand; sea level; sediments

CARMO, LUCAS S. do; WATANABE, SHIGUEO; DEWITT, REGINA. OSL-SAR dating of sediments from brazilian aeolian system: Dama Branca, Rio De Janeiro, morphodynamic study. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 22-27, 2017, Belo Horizonte, MG. Proceedings... Rio de Janeiro, RJ: Associação Brasileira de Energia Nuclear, 2017. Disponível em: http://repositorio.ipen.br/handle/123456789/28260. Acesso em: $DATA.

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Abstract: In the last decades tree barks have become a very common bioindicator of air pollution because of its several advantages over other bioindicators. In the present study, tree barks were collected from different sites of Metropolitan Region of São Paulo (MRSP) and from two control sites far away from MRSP. The barks were analyzed by neutron activation analysis (NAA) for determinations of As, Br, Ca, Cl, Co, Cr, Cs, Fe, K, La, Mg, Mn, Ni, Rb, Sb, Sc, V and Zn and for Cd, Cu and Pb by graphite furnace absorption spectrometry (GF AAS). Results obtained for samples collected in different sampling sites in the MRSP presented wide variability due to the different pollutants levels that each tree was exposed to. High concentrations of Cd, Pb, Sb and Zn were obtained in tree barks sampled close to high vehicular traffic. The principal components analysis (PCA) applied a identify four possible emission sources, soil resuspension plus vehicular emission, industrial, marine aerosols as well as the tree bark structure itself. The enrichment factor (EF) results indicated that all the elements originated from anthropic sources, with the exception of Cs. The cluster analyses indicated no significant differences between MRSP and control sites were observed with regards to characteristics of element emissions, probably due to the control sites are located also in urban areas. The results of certified reference material analyses indicated that NAA and GF AAS provided reliable data for element concentrations with standardized differences, |Z score| < 2.

Palavras-Chave: absorption spectroscopy; air pollution; bark; cluster analysis; concentration ratio; ecological concentration; elements; graphite; particulates; trees

SANTOS, ELIANE C.; SAIKI, MITIKO. Air pollution assessment using tree barks as biomonitors. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 22-27, 2017, Belo Horizonte, MG. Proceedings... Rio de Janeiro, RJ: Associação Brasileira de Energia Nuclear, 2017. Disponível em: http://repositorio.ipen.br/handle/123456789/28258. Acesso em: $DATA.

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Abstract: The study of pollutants with organic and inorganic characteristics in groundwater and surface waters of a given region is an important tool in the assessment of pollution. Endocrine interferers are synthetic or natural chemicals that have the ability to act on the endocrine system of humans and animals by mimetizing natural hormones and may produce adverse effects on organisms, even in low concentrations (μg or ng.L-1). Anthropic activities are the major source of input of endocrine disruptors into the environment. The Brazilian government has a project to construct a multipurpose reactor, Brazilian Multipurpose Reactor (RMB), at the Iperó city, to improve the nuclear research Brazilian capacity. The object of this research in to analyze 14 organic compounds that may be present in the groundwater and surface waters of the RMB installation area. This is an unprecedented and extremely important study for the evaluated region; since it will provide guidance on the degree of contamination of the local waters before the construction begins. The study will also make it possible to verify if the construction of the RMB will offer environmental issues to the place. For the determination of the compounds of interest, a developed and validated analytical method was used. This methodology consists of the concentration of the samples by solid phase extraction (SPE) followed by quantification by gas chromatography coupled to the mass spectrometry detector (GC/MS). The water column particulate was also evaluated by ultrasonic extraction, followed by quantification by GC/MS. The results reveal that some of the compounds were found and it was due to anthropic activities in the vicinity of the regions. By initial analysis it was possible verify river that cross the RMB area present values below 0.05 μg L-1.

Palavras-Chave: surface waters; environmental impacts; gas chromatography; ground water; mass spectroscopy; organic compounds; particulates; research reactors

SILVA, LARISSA L.; MARTINS, ELAINE A.J.; COTRIM, MARYCEL E.B.; PIRES, MARIA A.F. Evaluation of organic endocrine disruptors in water at Brazilian Multipurpose Reactor – RMB instalation area. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 22-27, 2017, Belo Horizonte, MG. Proceedings... Rio de Janeiro, RJ: Associação Brasileira de Energia Nuclear, 2017. Disponível em: http://repositorio.ipen.br/handle/123456789/28256. Acesso em: $DATA.

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Abstract: Taiaçupeba reservoir, located in the state of São Paulo, Brazil, belongs to Producer System of Alto Tietê (Sistema Produtor Alto Tietê) and it is responsible for water supply for about 3.1million of people. The water quality of a reservoir is very important, but this is reduced by the increase of environmental degradation of the soil around the reservoir and its different uses. The study of soil profiles and sediment cores is an important tool for understanding the geophysical and geochemical aspects of an aquatic ecosystem. The objective of this work was to present the natural radionuclides 238U, 226Ra, 210Pb, 232Th, 228Th, 228Ra and 40K activity concentrations and also the inorganic chemical characterization of four soil profiles and four sediment cores collected in the area of influence area of Taiaçupeba reservoir. The analytical techniques, gamma spectrometry and instrumental neutron activation analysis were used in the determination. In the soil profiles the highest activity concentrations were obtained for the radionuclides 40K and 228Th and the lowest for 210Pb; in the sediment cores the highest activity concentrations were obtained for the radionuclide 210Pb and the lowest for 226Ra and 228Ra. For the inorganic chemical characterization the highest values obtained were for Na, As and Sb; in a sediment core a very high concentration was obtained for the element Zn indicating a probable accumulation of this element inside the reservoir; enrichment factor was used to evaluate a possible anthropic contamination in the soil and sediment at the margins of Taiacupeba reservoir.

Palavras-Chave: geochemical surveys; concentration ratio; geophysical surveys; natural radioactivity; radioecological concentration; sediments; soils; thorium 232; uranium 238; water reservoirs

SOUZA, J.M.; DAMATTO, S.R.; LEONARDO, L.; SURKOV, A.M.; SILVA, A.R.; MADUAR, M.F.; GONÇALVES, P.N. Natural radionuclides from U-238 and TH-232 series and inorganic chemical characterization of soil profiles and sediment cores of the Taiaçupeba Reservoir, São Paulo, Brazil. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 22-27, 2017, Belo Horizonte, MG. Proceedings... Rio de Janeiro, RJ: Associação Brasileira de Energia Nuclear, 2017. Disponível em: http://repositorio.ipen.br/handle/123456789/28254. Acesso em: $DATA.

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Abstract: Concentration and distribution of trace and rare earth elements in bottom sediment samples collected in the Billings System (including Rio Grande and Guarapiranga Reservoirs) were assessed by using Instrumental Neutron Activation (INAA). To evaluate the sources of anthropogenic contamination the enrichment factor (FE) and the geoacumulation index (IGeo) were calculated using NASC and Guarapiranga Park Soil as Reference Values. Results were compared to the concentration guideline values established by CCME (Canadian Council of Ministers of the Environment) environmental agency for As, Cr and Zn, and values in other published studies. Most points exceeded TEL values and, in some points, PEL values for these elements, indicating poor sediment quality in these reservoirs. In general terms, the elements As, Cr, Sb and Zn through EF and IGeo calculations present enrichment at all points analyzed, in both collection campaigns, except for the Rio Grande Reservoir points. The region where the reservoirs are located receive untreated sewage as well as pollution from urban occupation, industrial and mining activities, making it difficult to accurately identify the pollution sources. This study found higher concentrations of the elements analyzed in the Billings Reservoir, indicating a greater contamination level in relation to the other reservoirs.

Palavras-Chave: concentration ratio; contamination; distribution; elements; environmental quality; particle size; sediments; trace amounts; water reservoirs

SILVA, LARISSA S.; FERREIRA, FRANCISCO J.; FAVARO, DEBORAH I.T. Distribution and concentration evaluation of trace and rare earth elements in sediment samples of the billings and Guarapiranga Reservoir Systems. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 22-27, 2017, Belo Horizonte, MG. Proceedings... Rio de Janeiro, RJ: Associação Brasileira de Energia Nuclear, 2017. Disponível em: http://repositorio.ipen.br/handle/123456789/28250. Acesso em: $DATA.

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Abstract: In this work, the scripting capabilities of Genie-2000 were used to develop a software that automatically analyses all spectrum les in either Ortec's CHN or Canberra's MCA or CNF formats in a folder, generating two output les: a print-ready text le (.DAT) and a Comma-Separated Values (.CSV) le which can be easily imported in any major spreadsheet software. This software, named CAX (\Convert and Analyse for eXcel"), uses Genie-2000's functions to import spectrum les into Genie's native CNF format and analyze the converted spectra. The software can also, if requested, import energy and FWHM calibrations from a stored calibrated spectrum. The print-ready output le (.DAT) is generated by Genie-2000 using a customized script, and the CSV le is generated by a custom-built DAT2CSV software which generates a CSV le that complies to the Brazilian standards, with commas as a decimal indicator and semicolons as eld separators. This software is already used in the daily routines in IPEN's Neutron Activation Laboratory, greatly reducing the time required for sample analyses, as well as reducing the possibility of transcription errors.

Palavras-Chave: automation; c codes; calibration; g codes; gamma radiation; brazilian cnen; gamma spectra; neutron activation analysis; performance

ZAHN, GUILHERME S.; GENEZINI, FREDERICO A. CAX a software for automated spectrum analysis. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 22-27, 2017, Belo Horizonte, MG. Proceedings... Rio de Janeiro, RJ: Associação Brasileira de Energia Nuclear, 2017. Disponível em: http://repositorio.ipen.br/handle/123456789/28248. Acesso em: $DATA.

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Abstract: The determination of silicon (Si), total uranium (U) and impurities in uranium-silicide (U3Si2) samples by wavelength dispersion X-ray fluorescence technique (WDXRF) has been already validated and is currently implemented at IPEN’s X-Ray Fluorescence Laboratory (IPEN-CNEN/SP) in São Paulo, Brazil. Sample preparation requires the use of approximately 3 g of H3BO3 as sample holder and 1.8 g of U3Si2. However, because boron is a neutron absorber, this procedure precludes U3Si2 sample’s recovery, which, in time, considering routinely analysis, may account for significant unusable uranium waste. An estimated average of 15 samples per month are expected to be analyzed by WDXRF, resulting in approx. 320 g of U3Si2 that wouldn’t return to the nuclear fuel cycle. This not only impacts in production losses, but generates another problem: radioactive waste management. The purpose of this paper is to present the mathematical models that may be applied for the correction of systematic errors when H3BO3 sample holder is substituted by cellulose-acetate {[C6H7O2(OH)3-m(OOCCH3)m], m = 0~3}, thus enabling U3Si2 sample’s recovery. The results demonstrate that the adopted mathematical model is statistically satisfactory, allowing the optimization of the procedure.

Palavras-Chave: acetates; boric acid; boron 10; corrections; errors; impurities; mathematical models; optimization; quantitative chemical analysis; sample preparation; uranium silicides

SCAPIN, MARCOS A.; GUILHEN, SABINE N.; AZEVEDO, LUCIANA C. de; COTRIM, MARYCEL E.B.; PIRES, MARIA A.F. Application of bias correction methods to improve U3Si2 sample preparation for quantitative analysis by WDXRF. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 22-27, 2017, Belo Horizonte, MG. Proceedings... Rio de Janeiro, RJ: Associação Brasileira de Energia Nuclear, 2017. Disponível em: http://repositorio.ipen.br/handle/123456789/28246. Acesso em: $DATA.

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Abstract: Thorium is a naturally occurring radioactive element that is widely distributed in the crust of the Earth. This element is very common in mineral formations in regions with high levels of natural radioactivity, therefore, its determination in environmental samples is important. Thorium isotopes (228Th, 230Th, and 232Th) were determined in a reference material, the IAEA Soil 327 sample, to validate the two methods employed using different resins. The initial preparation with acid dissolution is the same to both, in the first is used anion exchange resin (DOWEX 1x2) and electrodeposition in silver planchets. And in the second method is used a specific chromatographic resin (TEVA) and cerium fluoride microprecipitation. At the end both analysis are quantified by alpha spectrometry. The two methods the results obtained were satisfactory for the reference material used, with relative error of less than 4% for 228Th, 230Th, and 232Th. The main differences found between them were spectrums resolutions, time and cost of analysis.

Palavras-Chave: alpha spectroscopy; calibration standards; cerium fluorides; comparative evaluations; electrodeposition; precipitation; resins; thorium isotopes

ROSA, MYCHELLE M.L.; TADDEI, MARIA H.T.; CHEBERLE, LUAN T.V.; SILVA, PAULO S.C.; MAIHARA, VERA A. A comparative study using differents resins to determine thorium isotopes. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 22-27, 2017, Belo Horizonte, MG. Proceedings... Rio de Janeiro, RJ: Associação Brasileira de Energia Nuclear, 2017. Disponível em: http://repositorio.ipen.br/handle/123456789/28244. Acesso em: $DATA.

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Abstract: The objective of the work is to evaluate the mercury exposure of children living in an artisanal gold mining area and in a control area, without mining. A cross-sectional study was conducted with children living in the municipalities of Chapada de Natividade and Porto Nacional, in the State of Tocantins, where hair samples were collected for laboratorial analysis of mercury concentrations, comparing between municipalities, gender, monthly fish consumption, profession of parents and the presence of amalgam in dental restorations. The hair samples were analyzed by the methods of neutron activation analysis and also by means of the DMA (Direct Mercury Analyzer) equipment, in the last case being a partnership with CETESB. There was no evidence of mercury-related diseases in the studied children. The mean concentration of mercury in children in Chapada de Natividade was significantly higher than in Porto Nacional. Children exposed to artisanal gold mining areas have higher concentrations of mercury than children living in non- artisanal gold mining areas. There was no significant relationship between mercury concentrations and gender, monthly fish consumption, parental profession and amalgam presence in dental restorations. The results suggest that the children living in an area exposed to mining experience greater environmental exposure to mercury, regardless of their eating habits or gender.

Palavras-Chave: children; concentration ratio; cross sections; ecological concentration; gold; hair; mercury; mining; neutron activation analysis

MENDES, SEYNA U.R.; VASCONCELLOS, MARINA B.A.; CATHARINO, MARILIA G.M.; QUINAGLIA, GILSON A.; HELD, BARBARA. Evaluation of mercury levels in hair of children resident in artisanal gold mining area in the city of Chapada de Natividade-Tocantins. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 22-27, 2017, Belo Horizonte, MG. Proceedings... Rio de Janeiro, RJ: Associação Brasileira de Energia Nuclear, 2017. Disponível em: http://repositorio.ipen.br/handle/123456789/28242. Acesso em: $DATA.

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Abstract: There are various methods of neutron activation analysis, one of these is the k0 Method for quantitative reactor Neutron Activation Analysis (NAA). The k0-NAA procedure is nowadays widely used in numerous laboratories performing NAA all over the world. Among these reactions, 186W(n, )187W can be considered important because it can be used for a W concentration measurements. The irradiations were performed at position 24A, near the core of the IEA-R1 4.5 MW swimming-pool nuclear research reactor of the Instituto de Pesquisas Energéticas e Nucleares (IPEN-CNEN/SP – Nuclear and Energy Research Institute), in São Paulo, Brazil. Two irradiations were carried out in sequence, using two sets of samples: the first with a cadmium cover around the samples and the second without, in a total of three data sets with and without Cd cover performed in 2014 and 2015. The activity measurements were carried out in an HPGe gamma-ray spectrometer. Standard sources of 152Eu, 133Ba, 60Co and 137Cs supplied by the IAEA were used in order to obtain the HPGe gamma-ray peak efficiency as a function of the energy. The covariance matrix methodology was applied to all uncertainties involved. The preliminary values of k0 for 186W(n, )187W reaction for the gamma transition energy of 479.53 keV was 3.17x10-2(5), for 618.77 keV was 9.08x10-3(15) and for 685.77 keV was 3.88x10-2(6). These preliminary values for k0 have been compared with the literature.

Palavras-Chave: activity levels; cadmium; data covariances; high-purity ge detectors; neutron activation analysis; tungsten 186

BARROS, LIVIA F.; DIAS, MAURO S.; KOSKINAS, MARINA F.; YAMAZAKI, IONE M.; SEMMLER, RENATO. Preliminary measurements of k0 values for W-186. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 22-27, 2017, Belo Horizonte, MG. Proceedings... Rio de Janeiro, RJ: Associação Brasileira de Energia Nuclear, 2017. Disponível em: http://repositorio.ipen.br/handle/123456789/28240. Acesso em: $DATA.

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Abstract: The minimum sample intake for which a reference material remains homogeneous is one of the parameters that must be estimated in the homogeneity assessment study of reference materials. In this work, Instrumental Neutron Activation Analysis was used to evaluate this quantity in a bovine kidney candidate reference material. The mass fractions of 9 inorganic constituents were determined in subsamples between 1 and 2 mg in order to estimate the relative homogeneity factor (HE) and the minimum sample mass to achieve 5% and 10% precision on a 95% confidence level. Results obtained for HE in all the analyzed elements were satisfactory. The estimated minimum sample intake was between 2 mg and 40 mg, depending on the element.

Palavras-Chave: calibration standards; cattle; high-purity ge detectors; homogenates; intake; kidneys

CASTRO, LILIANA; MOREIRA, EDSON G.; VASCONCELLOS, MARINA B.A. Micro-homogeneity evaluation of a bovine kidney candidate reference material. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 22-27, 2017, Belo Horizonte, MG. Proceedings... Rio de Janeiro, RJ: Associação Brasileira de Energia Nuclear, 2017. Disponível em: http://repositorio.ipen.br/handle/123456789/28238. Acesso em: $DATA.

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Abstract: We have prepared the Hafnium Oxide (HfO2) nanoparticles (NPs) doped with 5% at. of silicon (Si) using the sol-gel chemical method. Nuclear quadrupole interactions at Hf sites were investigated by perturbed γ–γ angular correlations (PAC) spectroscopy using 181Ta as probe nuclei. This method is based on the hyperfine interactions between the nuclear moments of the probe nuclei with extra-nuclear magnetic fields or electric field gradients (EFGs). In the case of quadrupolar electric interactions, experimental measurements give the quadrupole frequency Q with respective distribution () as well the asymmetry parameter  of of of the EFG. The hyperfine parameters were measured within the range from 200°C to 900°C. The structural and morphological characterization of the samples were carried out by X-ray diffraction and scanning electron microscopy (SEM) with electron back scattering diffraction (EBSD). PAC results show a major site fraction of probe nuclei, that was assigned to the monoclinic phase of HfO2, with approximately 60% population, which increases when the temperature of heat treatment increases. The XRD results showed a single phase with the expected monoclinic structure for the as-prepared samples indicating that Si atoms are at substitutional Hf sites.

Palavras-Chave: doped materials; hafnium oxides; nanoparticles; perturbed angular correlation; quadrupoles; silicon; sol-gel process; tantalum 181; temperature dependence

SALES, TATIANE S.N.; CARBONARI, ARTUR W. Effect of silicon doping in HFO2 nanoparticles from an atomic view. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 22-27, 2017, Belo Horizonte, MG. Proceedings... Rio de Janeiro, RJ: Associação Brasileira de Energia Nuclear, 2017. Disponível em: http://repositorio.ipen.br/handle/123456789/28236. Acesso em: $DATA.

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Abstract: The response of the commercial XRA-24 PIN photodiode (5.76 mm2 active area) for clinical electron beam dosimetry covering the range of 8-12 MeV was investigated. Within this energy range, the charge generated in the diode’s sensitive volume is linearly dependent on the absorbed dose up to 320 cGy. However, charge sensitivity coefficients evidenced that the dose response of the diode is slightly dependent on the electron beam energy. Indeed, the diode’s energy dependence was within 8.5% for 8-12MeV electron beams. On the other hand, it was also observed an excellent repeatability of these results with a variation coefficient (VC) lower than 0.4%, which is within the 1% tolerance limit recommended by the AAPM TG-62. Furthermore, the agreement between the percentage depth dose profiles (PDD) gathered with the diode and the ionization chamber allowed achieving the electron beam quality within 1% of that obtained with the ionization chamber. Based on these results, the photodiode XRA-24 can be a reliable and inexpensive alternative for electron beams dosimetry.

Palavras-Chave: depth dose distributions; electron beams; energy dependence; feasibility studies; ionization chambers; mev range 01-10; photodiodes; silicon diodes

NASCIMENTO, CRISTINA R.; ASFORA, VIVIANE K.; BARROS, VINICIUS S.M.; GONÇALVES, JOSEMARY A.C.; ANDRADE, LUCAS F.R.; KHOURY, HELEN J.; BUENO, CARMEN C. Feasibility studies of using thin entrance window photodiodes for clinical electron beam dosimetry. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 22-27, 2017, Belo Horizonte, MG. Proceedings... Rio de Janeiro, RJ: Associação Brasileira de Energia Nuclear, 2017. Disponível em: http://repositorio.ipen.br/handle/123456789/28234. Acesso em: $DATA.

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Abstract: The pencil-type ionization chamber widely used in computed tomography (CT) dosimetry, is a measuring instrument that has a cylindrical shape and provides uniform response independent of the angle of incidence of ionizing radiation. Calibration and measurements performed with the pencil-type ionization chamber are done in terms of Kerma product in air-length (Pk,l) and values are given in Gy.cm. To obtain the values of (Pk,l) during clinical measurements, the readings performed with the ionization chamber are multiplied by the calibration coefficient (Nk,l) and the correction factor C for quality (Kq) which are given in Calibration certificates of the chambers. The application of the correction factor for radiation quality Kq is done as a function of the effective energy of the beam that is determined by the Half Value layer (HVL) calculation. In order to estimate the HVL values in this work, a Tandem system made up of cylindrical aluminum and PMMA absorber layers was used as a low cost and easy to apply method. From the Tandem curve, it was possible to construct the calibration curve and obtain the appropriate Kq to the beam of the computed tomography equipment studied.

Palavras-Chave: calibration; computerized tomography; corrections; dosimetry; ionization chambers; kerma; layers; pmma; quality assurance

FONTES, LADYJANE P.; POTIENS, MARIA da P.A. Application of the correction factor for radiation quality Kq in dosimetry with pencil-type ionization chambers using a tandem system. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 22-27, 2017, Belo Horizonte, MG. Proceedings... Rio de Janeiro, RJ: Associação Brasileira de Energia Nuclear, 2017. Disponível em: http://repositorio.ipen.br/handle/123456789/28232. Acesso em: $DATA.

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Abstract: This paper is a preliminary study on the use of reactor IPEN/MB-01 as standard radiation source for mixed field dosimetry studies. As a first step on this attempt, simulations and experiments, evaluating the neutron and gamma field distributions, were performed and compared. TLDs are widely employed in dose measurements and the TLD 100 / TLD 700 pair conforms with ICRU recommendations for mixed field dosimetry. In this study, TLD irradiations were performed in the IPEN/MB-01 nuclear reactor. IPEN/MB-01 reactor is zero power reactor widely used to perform reactor physics experiments. Its neutron flux distribution is well known for a variety of reactor core configurations. However, the photon fluxes are unknown. A series of experiments with TLD 100 and TLD 700 were performed for two different core configurations (rectangular and cylindrical with a central flux trap). Simulations with MCNP5 for these two configurations were also done, and neutron and gamma fluxes distributions along the core were computed. The responses of TLD 100 and TLD 700 were compared with simulated fluxes and showing a good agreement between them. This paper presents the results of the experiments done so far given the status of the study under way in order to couple IPEN/MB-01 and TLD 100 / 700 pair into a mixed field calibration methodology.

Palavras-Chave: calibration standards; computerized simulation; dosimetry; monte carlo method; neutron flux; reactor cores; thermoluminescent dosemeters; validation

CAVALIERI, TASSIO A.; SIQUEIRA, PAULO T.D.; YORIYAZ, HELIO. Reactor IPEN/MB-01 dosimetry using TLDs. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 22-27, 2017, Belo Horizonte, MG. Proceedings... Rio de Janeiro, RJ: Associação Brasileira de Energia Nuclear, 2017. Disponível em: http://repositorio.ipen.br/handle/123456789/28230. Acesso em: $DATA.

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Abstract: In vivo dosimetry is an essential tool for quality assurance programs, being a procedure commonly performed with thermoluminescent dosimeters (TLDs) or diodes. However, a type of dosimeter that has increasing popularity in recent years is the metal-oxide-semiconductor field effect transistor (MOSFET) detector. MOSFET dosimeters fulfill all the necessary characteristics to realize in vivo dosimetry since it has a small size, good precision and feasibility of measurement, as well as easy handling. Nevertheless, its true differential is to allow reading of the dose in real time, enabling immediate intervention in the correction of physical parameters deviations and anticipation of small anatomical changes in a patient during treatment. In order for MOSFET dosimeter to be better accepted in clinical routine, information reporting performance should be available frequently. For this reason, this work proposes to verify reproducibility and angular dependence of a standard sensitivity MOSFET dosimeter (TN-502RD-H) for Cs-137 and Co-60 sources. Experimental data were satisfactory and MOSFET dosimeter presented a reproducibility of 3.3% and 2.7% (1 SD) for Cs-137 and Co-60 sources, respectively. In addition, an angular dependence of up to 6.1% and 16.3% for both radioactive sources, respectively. It is conclusive that MOSFET dosimeter TN-502RD-H has satisfactory reproducibility and a considerable angular dependence, mainly for the Co-60 source. This means that although precise measurements, special attention must be taken for applications in certain anatomical regions in a patient.

Palavras-Chave: cesium 137; cobalt 60; dosemeters; dosimetry; experimental data; in vivo; mosfet; performance

SOUZA, CLAYTON H.; SHORTO, JULIAN M.B.; SIQUEIRA, PAULO T.D.; NUNES, MAIRA G.; SILVA JUNIOR, IREMAR A.; YORIYAZ, HELIO. Verification of angular dependence in mosfet detector. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 22-27, 2017, Belo Horizonte, MG. Proceedings... Rio de Janeiro, RJ: Associação Brasileira de Energia Nuclear, 2017. Disponível em: http://repositorio.ipen.br/handle/123456789/28228. Acesso em: $DATA.

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Abstract: Tobacco products contain significant concentrations of natural radionuclides from 238U and 232Th series. The consumption of these products increases the internal dose of radiation due to the inhalation of the natural radionuclides. Studies from literature emphasize that tobacco products have measurable concentrations of 210Po and 210Pb, and may contribute significantly to the increase of internal radiation dose and a large number of lung cancer in smokers. The objectives of this work were to determine the concentrations (Bq/kg) of the radionuclides 226Ra, 228Ra, 210Pb and 210Po and calculate the internal doses of radiation due to the consumption of these products. In the present work 71 samples were analyzed, consisting of cigars, unflavored and flavored cigarettes, straw cigarettes, cigars and roll smoke. The samples were purchased in Brazilian popular commercial establishments. The analytical techniques employed were the gross alpha and beta measurement after radiochemical separation for the radionuclides 226Ra, 228Ra, 210Pb and alpha spectrometry for 210Po. The internal radiation doses were calculated with the activity concentrations determined and using the ICRP Publication 119 dose coefficients. An annual consumption of 3,650 kg of tobacco products was considered. The inhalation rates of each radionuclide followed the rates of the current literature. The estimated mean annual dose varied from 76 to 263μSv/y for the tobacco product studied in this work.

Palavras-Chave: absorbed radiation doses; activity levels; alpha decay; alpha spectroscopy; beta decay; concentration ratio; inhalation; natural radioactivity; thorium 232; tobacco products; uranium 238

OLIVEIRA, ALINE S.G.R. de; DAMATTO, SANDRA R. Natural radioactivity and estimated dose in brazilian tobacco products. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 22-27, 2017, Belo Horizonte, MG. Proceedings... Rio de Janeiro, RJ: Associação Brasileira de Energia Nuclear, 2017. Disponível em: http://repositorio.ipen.br/handle/123456789/28226. Acesso em: $DATA.

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Abstract: The objective of the work was to evaluate the effect of gamma radiation on (Cucurbita moschata) processed minimally. The zucchinis were acquired in of Horticulture Department of the ESALQ/ USP, Piracicaba, SP. Brazil, and taken to the laboratory of Food Irradiation of CENA/USP, where they were washed in running water, peeled and cut in cubes. The squash cubes were dipped in a solution of sodium hypochlorite 15ml/L for 4 minutes and kept in plastic box (polypropylene). They were irradiated with doses of: 0 (control), 1.0 and 2.0 kGy, in a source of Cobalt-60, type Gammacell-220 with a dose rate of 0.666 kGy/h, and stored in temperature of 5ºC. After 1, 3 and 7 days of irradiation were realized analyses of: color (factors L, a, b), pH, Brix and acidity. By obtained results conclude that there is not statistics difference between the treatments processed by irradiation and the control. Therefore the dose of 2.0 kGy can be used to reduce the level of microbial load without affects the physical chemical characteristics of minimally processed zucchini.

Palavras-Chave: cobalt 60; color; dose rates; fruits; ph value; radiation effects; radicidation

SILVA, LUCIA C.A.S.; ARTHUR, PAULA B.; PIRES, JULIANA A.; HARDER, MARCIA N.C.; FRANCO, SUELY S.H.; C. FILHO, JORGE; ARTHUR, VALTER. Gamma radiation in the conservation Cucurbita moschata processed minimally. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 22-27, 2017, Belo Horizonte, MG. Proceedings... Rio de Janeiro, RJ: Associação Brasileira de Energia Nuclear, 2017. Disponível em: http://repositorio.ipen.br/handle/123456789/28222. Acesso em: $DATA.

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Abstract: Food irradiation is approved for use in more than 60 countries for applications and purposes in a wide variety of foods, being an effective and safe method for preservation and long-term storage. 2-Alkylcyclobutanones (2-ACBs) are the only known radiolytic products generated from foods that contain fatty acids (Triglycerides) when irradiated. The acids analyzed in this study are palmitic and stearic, which when irradiated form 2-Dodecylcyclobutanones (2-dDCB) and 2-Tetradecylcyclobutanone (2-tDCB). Part of the 2-ACBs ingested is excreted through feces and part is deposited in adipose tissues. In vitro studies so far have been only in colon cells. The work used a human hepatoma cell line (HepG2) since the accumulation of fat in this organ is quite common. Micronucleus test was selected to evaluate possible genotoxic effects of 2-dDCB and 2-tDCB compounds when exposed to high concentrations (447, 1422 and 2235 μM) for 4 and 24 hours. Tests were performed in quadriplicates using flow cytometric analysis. None detectable genotoxic damage was observed after 4 hours of exposure to the compounds, and cytotoxic effects were only significant at the highest concentration (2235 μM) of 2-dDCB. After 24 hours of exposure, slight genotoxic damage was observed at all concentrations evaluated, and cytotoxic effects were only present when exposed to compound 2-tDCB. Although there is a genotoxic and cytotoxic effect in some of the situations tested, the two compounds predominantly induced proliferation reduction effects of this hepatic tumor cell line.

Palavras-Chave: cell flow systems; dodecyl radicals; food processing; hepatomas; hexadecanoic acid; in vitro; irradiation; octadecanoic acid; radiation effects; toxicity

BARBEZAN, ANGELICA B.; SANTOS, CARLA J.B.; CARVALHO, LUMA R.; VIEIRA, DANIEL P.; SANTELLI, GLAUCIA M.M.; VILLAVICENCIO, ANNA L.C.H. Flow cytometry based micronucleus assay for evaluation of genotoxic potential of 2-ACBs in hepatic cells HepG2. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 22-27, 2017, Belo Horizonte, MG. Proceedings... Rio de Janeiro, RJ: Associação Brasileira de Energia Nuclear, 2017. Disponível em: http://repositorio.ipen.br/handle/123456789/28220. Acesso em: $DATA.

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Abstract: Goji-berry is fruit native from China, found on a red berry form and keeps an excellent source of antioxidants, such as carotenoids. The consumption of goji-berry is growing on the Brazilian commerce. To allow the commercialization of this foods its necessary of these foods are free of contaminants agents which may cause damages to the consumers health. For this warranty it’s required of this method does not harm the food properties and quality. For this check was made the study using goji-berry. Irradiation is one of the methods that improves the safety and extends the shelf life of some foods. Food irradiation is a technology process of exposing a particular food to a controlled dose of ionizing radiation. This study aimed compares the effects of ionizing radiation processing on physical properties of color and texture in goji-berries at different irradiation doses. Samples were bought on the retail market in the city of São Paulo and processed by ionizing radiation on Nuclear and Energy Research Institute (IPEN/CNEN-SP) at doses of 2.5; 5.0; 7.5; 10.0 kGy and the control group. Then the samples were followed by color and texture analyses. The color assay's results showed that the irradiation process decreased red and yellow pigments. On the other hand, the sample’s luminosity increased after being processed by ionizing radiation. On the texture assay was verified a decrease of the fruit compressive force, turning the fruit more softened.

Palavras-Chave: color; fruits; ionizing radiations; radiation doses; radiation effects; texture

SILVA, PAMELA G. da; KOIKE, AMANDA C.R.; RODRIGUES, FLAVIO T.; VILLAVICENCIO, ANNA L.C.H. Analysis of physical properties of color and texture in Goji-Berry processed by ionizing radiation. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 22-27, 2017, Belo Horizonte, MG. Proceedings... Rio de Janeiro, RJ: Associação Brasileira de Energia Nuclear, 2017. Disponível em: http://repositorio.ipen.br/handle/123456789/28218. Acesso em: $DATA.

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Abstract: The characterization of edible tissues of fishes consumed by humans is very important for determination of several toxic and potentially toxic elements, ensuring the food safety. The Instrumental Neutron Activation Analysis (INAA) comparative method allows the determination of several of these elements, as well as others, for example of nutritional character. This study is part of the International Atomic Energy Agency (IAEA) technical cooperation project of Latin America and Caribbean countries to ensure the quality of food and biomonitoring of contaminants in molluscs and fishes. Ten specimens of 5 of the most consumed fish in São Paulo city: whitemouth croaker (Micropogonias Furnieri), smooth weakfish (Cynoscion learchus), common snook (Centropomus undecimalis), Brazilian sardine (Sardinella brasiliensis) and bluefish (Pomatomus Saltatrix) were analyzed. Complete procedures for analysis, which includes purchase in the largest warehouse in Latin America, transport to the laboratory, storage, freeze-drying, milling, weighting and others preparations of the subsamples, and the short irradiation parameters for the determination of Br, Cl, K, Mn and Na are reported. Results obtained for macro and microelements are presented and are in agreement with analysis of oyster tissue and mussel tissue certified reference materials under the same irradiation conditions, with z-score values ranging from -3.0 to 2.2.

Palavras-Chave: contamination; cooperation; fishes; high-purity ge detectors; neutron flux; quality assurance; quality management; radioisotopes; toxicity

TAPPIZ, BRUNO; MOREIRA, EDSON G. Neutron activation analysis characterization procedures for fish consumed at São Paulo City. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 22-27, 2017, Belo Horizonte, MG. Proceedings... Rio de Janeiro, RJ: Associação Brasileira de Energia Nuclear, 2017. Disponível em: http://repositorio.ipen.br/handle/123456789/28216. Acesso em: $DATA.

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Abstract: The material studied in this work was flooded in the city of São Luiz do Paraitinga, SP, Brazil on January 2010 during a record flood suffered by the river that pass through the region. The documentary collection belonging to the City Hall underwent emergency drying and recovery treatments including irradiation with gamma rays to the destruction of various cellulosic fungi. Seven record books with many pages in blank and presenting severe fungal and mold infestation were provided by the Public Archive of the State of São Paulo, in charge of the damaged official documents, as samples for the present investigation on the effects of gamma radiation in the recovery and preservation of paper supported collections that are victims of biological contamination. This study represents a very rare possibility of working with a real object of actual use, which suffered a real disaster, and not with material prepared in laboratory and subjected to a forged flood situation.

Palavras-Chave: absorption spectroscopy; cobalt 60; decontamination; fungi; paper; preservation; radiation effects

AUADA, FERNANDA M.; BARDI, MARCELO A.G.; MACHADO, LUCI D.B. Application of gamma radiation for recovery of papers infected by fungi: case study about São Luiz do Paraitinga. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 22-27, 2017, Belo Horizonte, MG. Proceedings... Rio de Janeiro, RJ: Associação Brasileira de Energia Nuclear, 2017. Disponível em: http://repositorio.ipen.br/handle/123456789/28214. Acesso em: $DATA.

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Abstract: The analyzes carried out in this work aims to contribute to the discussion about the ceramic objects founded in Monte Castelo’s sambaqui located at south-west Amazonia. The first study accomplished by Miller in 1980 suggests that this archaeological site is inserted in the old contexts of production of ceramics in the Amazon. Until today, there are not any physical and chemical analysis studies in this ceramics and this kind of studies may help archaeological studies performed at the sambaqui. With this purpose, this work presents a preliminary study of chemical characterization of eighty-seven ceramic samples using the Neutron Activation Analysis (NAA). The analyzed elements were: As, K, La, Lu, Na, Nd, Sm, U, Yb, Ce, Co, Cr, Cs, Eu, Fe, Hf, Rb, Sc, Ta, Tb, Th. With the purpose to study the similarity/dissimilarity between the samples cluster and discriminant analysis were used. The results showed the existence of three different chemical groups that are in agreement with the archaeological studies made by Miller which found a sequence of cultural development, with three main occupational components whose dating ranging from 8.400 to 4.000 b.P. In this way, the results of this work are in agreement with miller's studies and suggest Bacabal’s phase as the oldest ceramist culture in the Southwest of the Amazon.

Palavras-Chave: archaeological sites; archaeological specimens; ceramics; chemical analysis; elements; thermal neutrons

CARVALHO, PATRICIA R.; MUNITA, CASIMIRO S.; NEVES, EDUARDO G.; ZIMPEL, CARLOS A. Chemical characterization of ancient pottery from the South-West Amazonia using neutron activation analysis. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 22-27, 2017, Belo Horizonte, MG. Proceedings... Rio de Janeiro, RJ: Associação Brasileira de Energia Nuclear, 2017. Disponível em: http://repositorio.ipen.br/handle/123456789/28212. Acesso em: $DATA.

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Abstract: At the Instituto de Pesquisa Energéticas e Nucleares (IPEN), the Centro de Combustível Nuclear (CCN) is responsible for manufacturing fuels for the IEA-R1 reactor and, possibly, the multipurpose reactor fuels. In order to meet the demand for both reactors, the CCN developed a new plant. The production process of the fuel generates several types of effluents - containing uranium or not - being solid, liquid and gaseous with varied physical and chemical characteristics. The objective of this work is to follow the nuclear fuel production process and to identify, quantify and characterize the effluents, especially the liquid ones, to later elaborate a plan of management of these and eventually dispose in a responsible way in the environment.

Palavras-Chave: environmental impacts; liquid wastes; nuclear fuels; production; radioactive effluents; radioactive waste management

SAKAI, MAYARA C.C.B.; RIELLA, HUMBERTO G.; CARVALHO, ELITA F.U. de. Quantification of effluents in the production of nuclear fuel. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 22-27, 2017, Belo Horizonte, MG. Proceedings... Rio de Janeiro, RJ: Associação Brasileira de Energia Nuclear, 2017. Disponível em: http://repositorio.ipen.br/handle/123456789/28210. Acesso em: $DATA.

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Abstract: The malicious use of radioactive material could be devastating, particularly in the case of a nuclear explosive device, it could be unpredictably disruptive resulting in the dispersal of radioactive material, like it was in the Fukushima Daiichi Nuclear Power Plant disaster. Physical Protection System (PPS) plays an important role in ensuring that individuals, organizations and institutions remain vigilant and that sustained measures are taken to prevent and combat the threat of sabotage or of using radioactive material for malicious acts. PPS is an integrated system of people, equipment and procedures used to protect nuclear facilities and radioactive sources against threat, theft or sabotage. In the operator's perspective, this paper study factors influencing the performance of a PPS in a nuclear facility suggesting ways to increase the system effectiveness. The human factor, the physical and the psychological work environment has a large impact on how personnel perform their work and comply with nuclear security requirements. Apathy and corporatism are two human behaviors that collaborate negatively and make decrease the effectiveness of any PPS. Job satisfaction reduces the probability that personnel will become less reliable and/or obstructive in extreme cases an insider threat. Managers must recognize individual and group needs and the relationship among personnel so that they may motivate personnel by creating a supportive working environment that reduces workplace stress. An effective PPS can result in a significant increase in the effectiveness of the security of radioactive material and associated facilities.

Palavras-Chave: emergency plans; human factors; nuclear facilities; performance; physical protection; physical protection devices; radiation protection; safety culture; vulnerability

VAZ, ANTONIO C.A.; CONTI, THADEU N. Increasing the effectiveness of the physical protection system on a nuclear facility. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 22-27, 2017, Belo Horizonte, MG. Proceedings... Rio de Janeiro, RJ: Associação Brasileira de Energia Nuclear, 2017. Disponível em: http://repositorio.ipen.br/handle/123456789/28208. Acesso em: $DATA.

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Abstract: The use of parallel plate-type fuel assemblies is common in nuclear research reactors. One of the main problems of this fuel element configuration is the hydraulic instability of the plates caused by the high flow velocities. The current work is focused on the hydrodynamic characterization of coolant channels typical of a flat-plate fuel element, using a numerical model developed with the commercial code ANSYS CFX. Numerical results are compared to accurate analytical solutions, considering two turbulence models and three different fluid meshes. For this study, the results demonstrated that the most suitable turbulence model is the k- model. The discretization error is estimated using the Grid Convergence Index method. Despite its simplicity, this model generates precise flow predictions.

Palavras-Chave: a codes; analytical solution; computerized simulation; coolants; finite difference method; fuel assemblies; fuel elements; hydrodynamics; instability; turbulent flow

MANTECON, JAVIER G.; MATTAR NETO, MIGUEL. Simplified CFD model of coolant channels typical of a plate-type fuel element: an exhaustive verification of the simulations. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 22-27, 2017, Belo Horizonte, MG. Proceedings... Rio de Janeiro, RJ: Associação Brasileira de Energia Nuclear, 2017. Disponível em: http://repositorio.ipen.br/handle/123456789/28206. Acesso em: $DATA.

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Abstract: The fuel elements of a MTR (Material Testing Reactor) type nuclear reactor are mostly composed of aluminumcoated fuel plates containing the core of uranium silica (U3Si2) dispersed in an aluminum matrix. These plates have a thickness of the order of millimeters and are much longer in relation to their thickness. They are arranged in parallel in the assembly of the fuel element to form channels between them a few millimeters in thickness, through which there is a flow of the coolant. This configuration, combined with the need for a flow at high flow rates to ensure the cooling of the fuel element in operation, may create problems of mechanical failure of fuel plate due to the vibration induced by the flow in the channels. In the case of critical velocity excessive permanent deflections of the plates can cause blockage of the flow channel in the reactor core and lead to overheating in the plates. For this study an experimental bench capable of high volume flows and a test section that simulates a plate-like fuel element with three cooling channels were developed. The dimensions of the test section were based on the dimensions of the Fuel Element of the Brazilian Multipurpose Reactor (RMB), whose project is being coordinated by the National Commission of Nuclear Energy (CNEN). The experiments performed attained the objective of reaching Miller's critical velocity condition. The critical velocity was reached with 14.5 m/s leading to the consequent plastic deformation of the flow channel plates.

Palavras-Chave: critical velocity; deformation; experimental data; fluid flow; fuel assemblies; fuel plates; mtr reactor; nuclear fuels; reactor cores

CASTRO, ALFREDO J.A.; SCURO, NIKOLAS L.; ANDRADE, DELVONEI A. Experimental investigation of critical velocity in a parallel plate research reactor fuel assembly. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 22-27, 2017, Belo Horizonte, MG. Proceedings... Rio de Janeiro, RJ: Associação Brasileira de Energia Nuclear, 2017. Disponível em: http://repositorio.ipen.br/handle/123456789/28204. Acesso em: $DATA.

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Abstract: Charpy specimen reconstitution is widely used around the world as a tool to enhance or supplement surveillance programs of nuclear reactor pressure vessels. The reconstitution technique consists in the incorporation of a small piece from a previously tested specimen into a compound specimen, allowing to increase the number of tests. This is especially important if the available materials is restricted and fracture mechanics parameter have to be determined. The reconstitution technique must fulfill some demands, among them tests results like the original standard specimens and the loaded material of the insert must not be influenced by the welding and machining procedure. It is known that reconstitution of Charpy specimens may affect the impact energy in a consequence of the constraint of plastic deformation by the hardened weldment and HAZ. This paper reviews some recent advances of the reconstitution technique and its applications.

Palavras-Chave: charpy test; decomposition; heat affected zone; inspection; neutron fluence; pressure vessels; reactors; steels; welding

ANDRADE, ARNALDO H.P.; LOBO, RAQUEL M.; MIRANDA, CARLOS A.J. Recent advances on charpy specimen reconstitution techniques. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 22-27, 2017, Belo Horizonte, MG. Proceedings... Rio de Janeiro, RJ: Associação Brasileira de Energia Nuclear, 2017. Disponível em: http://repositorio.ipen.br/handle/123456789/28202. Acesso em: $DATA.

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