Abstract: The Nuclear and Energy Research Institute (IPEN CNEN / SP), through the Research Reactor Center (CERPq), conducts several studies using Instrumental Neutron Activation Analysis (INAA) in its Activation Analysis Laboratory (LAN). The present study performed a critical analysis of the way Certified Reference Materials (CRM) are used to assess accuracy in LAN activities, from a statistical point of view. With the wide dissemination and application of metrological concepts, the use of regulatory standards (ABNT and INMETRO) became increasingly necessary. The literature defines several approaches to the statistical principles for the use of the obtained values. CRMs are used to assess the accuracy of analytical methods, being essential for trueness assessment. There are a few ways to quantify trueness, and this can be done by percent relative error and z score, determining the trend of the analytical method, which is defined as the estimation of a systematic error. The use of z scores is interesting in evaluating the quality of analytical methods, as it is less subject to the influence of the concentration value. Theses and dissertations developed at LAN were selected as the object of study and the calculations were performed using the concepts presented to verify the data treatment, at a 95% confidence level, presenting satisfactory results.

Palavras-Chave: accuracy; calibration standards; data; data analysis; neutron activation analysis; quality assurance; statistical data; statistical models

LIMA, GEAN B. de; KAISER, THIAGO J. S.; MOREIRA, EDSON G. Z-score, a tool for quality assurance of analytical results in neutron activation analysis. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 21-25, 2019, Santos, SP. Proceedings... Rio de Janeiro: Associação Brasileira de Energia Nuclear, 2019. p. 478-485. Disponível em: http://repositorio.ipen.br/handle/123456789/30390. Acesso em: $DATA.

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Abstract: The aim of this paper is to provide students, educators, and the general public with a virtual tool for learning about the peaceful use of nuclear technology and its importance to humanity. Using new technologies available in the market such as smartphones, software for the development of electronic games, virtual reality glasses, among others, we will virtually reproduce the facilities of the IEA-R1 nuclear research reactor, allowing anyone to perform a virtual and interactive visit to these facilities in a safe and didactic way. The use of virtual reality glasses and applications has been shown to be adequate in relation to the objectives proposed here.

Palavras-Chave: computer codes; computerized simulation; data visualization; educational tools; iear-1 reactor; mobile phones; real time systems; training

SILVA, LEANDRO G.M. e; SABUNDJIAN, GAIANE. Virtual visit to nuclear research reactor IEA-R1. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 21-25, 2019, Santos, SP. Proceedings... Rio de Janeiro: Associação Brasileira de Energia Nuclear, 2019. p. 4839-4846. Disponível em: http://repositorio.ipen.br/handle/123456789/30702. Acesso em: $DATA.

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Abstract: In an open pool type reactor, the pool water inventory should act as a heat sink to provide emergency reactor core cooling. In the Brazilian Multipurpose Reactor – RMB, to avoid the loss of pool water inventory, all the Core Cooling System (CCS) lines penetrate at the pool top, far above the reactor core level. However, as most of CCS equipment and lines are located below the reactor core level, in the case of a Loss of Coolant Accident (LOCA), a large amount of pool water could be lost drained by siphon effect. To avoid RMB research reactor core discovering in the case of a LOCA, siphon breakers, that allow CCS line air intake, are installed in the CCS lines in order to stop the reactor pool draining due to siphon effect. As siphon breakers are important passive safety devices, their effectiveness should be verified. Several previous numerical and experimental studies about siphon break effect were found in the literature. Some of them comment about the effectiveness of the siphon breakers based on their air intake area. Others state that one-dimensional thermo-hydraulic system codes such as RELAP5 code would fail when modeling the siphon break effect. This work shows the RELAP5/MOD3.3 code capability in modeling the siphon break effect. A nodalization for RELAP5/MOD3.3 code of a Siphon Breaker Test Facility located at POSTECH University in Korea was developed. Experiments considering several siphon breakers device intake areas were simulated. A very good agreement between numerical and experimental results was obtained. As siphon breakers intake areas decrease, the siphon breaker effectiveness also decreases and more water is drained from the reactor pool. For smaller siphon breaker intake areas, RELAP5/MOD3.3 code showed conservative results, overestimating the reactor pool water losses.

Palavras-Chave: computerized simulation; loss of coolant; pipes; pool type reactors; r codes; reactor cores; ruptures; safety analysis; tanks; test facilities; test facilities; validation; void fraction

BELCHIOR JUNIOR, ANTONIO; SOARES, HUMBERTO V.; FREITAS, ROBERTO L. Validation of the RELAP5 code for the simulation of the Siphon Break effect in pool type research reactors. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 21-25, 2019, Santos, SP. Proceedings... Rio de Janeiro: Associação Brasileira de Energia Nuclear, 2019. p. 5383-5392. Disponível em: http://repositorio.ipen.br/handle/123456789/30722. Acesso em: $DATA.

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Abstract: A maioria dos países enfrenta grandes desafios para controlar e organizar a geração e a disposição dos resíduos sólidos urbanos. Milhões de toneladas desses resíduos são gerados anualmente pela população e pelas indústrias. A eliminação destes resíduos sólidos é um problema mundial crescente. Os materiais poliméricos (plásticos e borrachas) compreendem uma proporção cada vez maior de resíduos industriais que entram em aterros sanitários e ambientais. Devido à capacidade da radiação ionizante alterar a estrutura e as propriedades dos materiais poliméricos, e o fato de que ela é aplicável a todos os tipos de polímeros, a irradiação é promissora para tratar do problema de resíduos poliméricos. O objetivo deste trabalho foi utilizar a radiação gama proveniente de uma fonte de 60Co para reciclar o poli(tetrafluoroetileno) (PTFE) que é um polímero de difícil decomposição quando descartado no meio ambiente. Aparas industriais deste polímero foram selecionadas e submetidas ao processo de moagem. Posteriormente, as amostras foram submetidas ao processo de irradiação com uma dose de 200 kGy. Após a irradiação o material obtido foi micronizado obtendo-se um pó muito fino de PTFE o qual foi classificado de acordo com os tamanhos de partículas com características especiais para diferentes possibilidades de utilização industrial (aditivos para tintas, massas lubrificantes, óleos e como carga em polímero para diminuir o coeficiente de atrito).

Palavras-Chave: cobalt 60; grinding; ionizing radiations; particle size; polytetrafluoroethylene; recycling; scrap

SOUZA, ERIC W. de; VIEIRA, JOSE M.; SILVA, LEONARDO G. de A. e. Uso da radiação ionizante na reciclagem de poli (tetrafluoroetileno) (PTFE). In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 21-25, 2019, Santos, SP. Proceedings... Rio de Janeiro: Associação Brasileira de Energia Nuclear, 2019. p. 3167-3171. Disponível em: http://repositorio.ipen.br/handle/123456789/30672. Acesso em: $DATA.

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Abstract: Cyanobacteria blooms have been observed in the aquatic systems in different continents, frequently with the production of cyanotoxins that negatively alter water potability. This work provides a small review of the state of the art of the use of advanced oxidation processes in the degradation of cyanobacteria and their toxins. It is divided into 3 major sections: the first part focuses on cyanobacteria and the mechanisms of production related to the environmental conditions. The second part we exposed the guidance values of the evaluation in drinking water for the control of cyanotoxins worldwide, and Brazil regulations. In the third and last part, we present some studies about the use of the advanced oxidation processes for the inhibition and degradation of cyanotoxins, focuses on ionizing radiation: gamma-ray and electron beam irradiation. In conclusion, the ionizing radiation is an efficient and economically viable alternative on the remediation of areas contaminated by cyanobacteria blooms and their toxins, mainly in the reservoirs destined to the water treatment and supply. As well, some suggestions are provided for additional studies about the use of this technology for the treatment of drinking water.

Palavras-Chave: algae; bacteria; comparative evaluations; drinking water; ecosystems; environmental effects; gamma radiation; ionizing radiations; radiation doses; toxicity; toxins

SILVA, THALITA T.; BORRELY, SUELI I. Use of ionizing radiation for the inhibition and removal of cyanotoxins in the water: a review. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 21-25, 2019, Santos, SP. Proceedings... Rio de Janeiro: Associação Brasileira de Energia Nuclear, 2019. p. 690-699. Disponível em: http://repositorio.ipen.br/handle/123456789/30503. Acesso em: $DATA.

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Abstract: Uranium can exist in the water as a result of soil leaching or technological processes (mining and processing of phosphate minerals to fertilizer production). The INAA (instrumental neutron activation analysis) usually is used to determination of trace elements through the conversion of stable nuclei to another via nuclear reactions. The present work used INAA method for determination of U in water samples. The goals are validate a methodology to determine U in water samples, apply this methodology and determinate the physical chemical parameters pH, total solids and alkalinity in tap waters samples. The validation was stablished based on varying the irradiation and counting times. A-one-liter sample with 87 g of U was prepared from the standard solution of U 1000 mg L􀀀1 (SPEX CERTIPREP). From this prepared solution was taken ten samples of 100 mL each. After complete evaporation at 100oC in hot plate and at 60oC in infrared lamp, the ten samples were irradiated in the IEA-R1 nuclear research reactor. Two samples from di erent regions were collected for determination of pH, total solids, alkalinity and U concentration.

Palavras-Chave: acid neutralizing capacity; concentration ratio; elements; iear-1 reactor; irradiation; neutron activation analysis; ph value; solids; trace amounts; uranium; water

SOUZA, LUCAS S.G. de; SILVA, PAULO S.C. da. Uranium determination in tap water by INAA. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 21-25, 2019, Santos, SP. Proceedings... Rio de Janeiro: Associação Brasileira de Energia Nuclear, 2019. p. 594-601. Disponível em: http://repositorio.ipen.br/handle/123456789/30412. Acesso em: $DATA.

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Abstract: O uso do laser no processamento de materiais é uma área de pesquisa em ascensão, sendo que o mesmo tem sido utilizado em processos avançados de fabricação e em tratamentos superficiais. Quanto aos tratamentos superficiais, destaca-se o de endurecimento seletivo, que provoca o aumento de dureza da superfície do material da peça, possibilitando a redução do desgaste e aumento no tempo de vida do componente. Nesse sentido, o objetivo do trabalho foi avaliar a influência de alguns parâmetros de aplicação do laser pulsado de Nd:YAG na alteração sub-superficial de uma amostra de aço-rápido sinterizado (HSS/PM). Para tanto, foi realizada a preparação metalográfica da seção transversal da amostra atacada pelo laser, para em seguida realizar as caracterizações por microscopia óptica e eletrônica de varredura, mecânica através do ensaio de microdureza Vickers e física para a identificação das fases formadas através da difração de raios-X (DRX). A análise dos resultados mostrou que os parâmetros do laser influenciaram significativamente na profundidade da alteração sub-superficial, da mesma forma que promoveram variação de dureza, provavelmente, devido a formação de martensita e carbonetos detectadas em DRX.

Palavras-Chave: lasers; hardness; steels; microhardness

BERGAMASCHI, VITOR; CARNEIRO, MARCELO B.; ROSSI, WAGNER de; NEVES, MAURICIO D.M. Tratamento térmico de endurecimento por laser pulsado de Nd:YAG em aço-rápido. In: CONGRESSO BRASILEIRO DE ENGENHARIA DE FABRICAÇÃO, 10., 5-7 de agosto, 2019, São Carlos, SP. Anais... Rio de Janeiro, RJ: Associação Brasileira de Engenharia e Ciências Mecânicas, 2019. Disponível em: http://repositorio.ipen.br/handle/123456789/31068. Acesso em: $DATA.

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Abstract: In the present study, sediment cores were collected in the Graminha (Caconde) water supply reservoir in Feb/2015 (points 1 and 3) and Aug/2015 (points 1 and 4) sampling campaigns. The four sediment cores with different depths were cut every 2.5 cm, yielding 36, 21, 33 and 37 slices of sediments, respectively, that were individually analyzed by INAA (Instrumental Neutron Activation Analysis). This analytical technique was used to quantify the elements: As, Ba, Br, Co, Cr, Cs, Fe, Hf, Rb, Sb, Sc, Ta, Zn, U and Th. The validation of precision of the methodolody was made by analyzing certified reference material. The concentration values obtained for As, Cr and Zn were compared with TEL and PEL oriented values established by the CCME (Canada) and adopted by CETESB for sediment quality evaluation. None of the sediment cores analyzed surpassed the PEL value for these elements. Sediment samples from points 2 and 3 presented the worst sediment quality but were still classified as good quality for sediments. The enrichment factor (EF) and Geoacumulation Index (IGeo) tools used for contamination level assessment were used for all sediment cores and mostly presented enrichment on As and U. The results from concentrations, EF and IGeo showed a significant increase mostly below 30 cm of depth in every core. Statistical analyses were applied to the elemental concentration values for better interpretation of the results.

Palavras-Chave: elements; evaluation; metals; neutron activation analysis; sampling; sediments; trace amounts; water reservoirs; brazil

JUNQUEIRA, LUCAS S.; SILVA, SHARLLENY A.; FRANKLIN, ROBSON L.; FAVARO, DEBORAH I.T. Trace element assessment in sediment cores from Graminha reservoir, São Paulo State, by INAA. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 21-25, 2019, Santos, SP. Proceedings... Rio de Janeiro: Associação Brasileira de Energia Nuclear, 2019. p. 505-520. Disponível em: http://repositorio.ipen.br/handle/123456789/30393. Acesso em: $DATA.

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Abstract: The textile industry uses expressive amount of water during the production and generate effluents that contain residuals of dyes, surfactants, peroxides, acids and salts, and toxicity. In addition, the textile effluents are commonly colored, because the dyes used in fibers dyeing usually have low fixation and high solubility. Many of the mentioned products are not easily removed, requiring additional treatment steps. Advanced Oxidative Processes, such as electron beam irradiantion (EBI), can be a good alternative to reduction of organic pollutants from effluents. Therefore, studies on these contaminants in aquatic environment are important for assessing their impacts on ecosystems and water quality. The objective of this study was to evaluate the toxicity of textile effluents treated with EBI. The doses of 2.5 kGy and 5.0 kGy were used. The toxicity assays were performed with Daphnia similis organisms, exposed to samples during 48 hours, and the results expressed by EC50 (median effective concentration). For the textile effluent, EC 50% values ranged from: 2.95 ±0.13 (raw effluent) until 20.90 ±1.48 (irradiated effluent, at 5kGy). The EBI treatment was effective for toxicity reduction, with efficiency higher than 60% (2.5 kGy) and 80% (5.0 kGy). The study of organic and inorganic contaminants, presents in these effluents, demonstred EC 50 values below 5%. These results demonstrate high toxicity of contaminants from textile effluents for aquatic organisms (D. similis, cladocera). Similar data was observed for the raw effluent. These values are relevant for thinking radiation as a possible technology for such a type of effluent.

Palavras-Chave: chemical effluents; decontamination; electron beams; environment; industrial wastes; irradiation; liquid wastes; pollutants; textile industry; textiles; toxicity; water quality

GARCIA, VANESSA S.G.; BOIANI, NATHALIA F.; ROSA, JORGE M; BORRELY, SUELI I. Toxicity of textile effluents treated by electron beam technology. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 21-25, 2019, Santos, SP. Proceedings... Rio de Janeiro: Associação Brasileira de Energia Nuclear, 2019. p. 735-742. Disponível em: http://repositorio.ipen.br/handle/123456789/30512. Acesso em: $DATA.

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Abstract: Chia seeds (Salvia hispanica L.) is a good source of oil, protein, dietary fiber, minerals and polyphenolic compounds. In order to study the influence of the processing methods on the content of phenolic compounds, the objective of this work was to evaluate the effect of gamma radiation, doses 0-20 kGy, on the total phenolic compounds extracted from chia seeds. Seeds were first defatted and extracts produced with proper solvents. Total phenolic content was determined according to Folin-Ciocalteu’s method and the extraction solvents applied were ethanol 100%, ethanol 70%, ethanol 50%, methanol 100%, methanol 70% and methanol 50%. When using ethanol 100%, ethanol 70 %, ethanol 50%, methanol 100% and methanol 70%, the extraction yield was independent of the absorbed dose. With methanol 50%, the irradiation process affected positively the total phenolic yield from of chia seeds. In general, the absorbed dose as well as the nature of the solvent affected the extraction yield, although in a limited manner.

Palavras-Chave: antioxidants; cobalt 60; dose rates; food processing; gamma radiation; irradiation; radiation dose units; radiation effects; seeds

CHIERENTIN, GABRIEL S.; TEIXEIRA, BRUNA S.; DEL MASTRO, NELIDA L. Total phenolic compounds of irradiated chia seeds. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 21-25, 2019, Santos, SP. Proceedings... Rio de Janeiro: Associação Brasileira de Energia Nuclear, 2019. p. 2102-2106. Disponível em: http://repositorio.ipen.br/handle/123456789/30607. Acesso em: $DATA.

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