The IAEA ICSP on Numerical Benchmarks for Multiphysics Simulation of Pressurized Heavy Water Reactor Transients was initiated in 2016 to facilitate the development of a set of open access, standardized, numerical test problems for postulated accident scenarios in a CANDU styled Reactor. The test problems include a loss of coolant accident resulting from an inlet header break, a loss of flow accident caused by a single pump trip, and a loss of regulation accident due to inadvertently withdrawn adjusters. The Benchmark was split into phases, which included stand-alone physics and thermal-hydraulics transients, coupled steady state simulations, and coupled transients. This thesis documents the results that were generated through an original TRACE/PARCS coupling methodology that was developed specifically for this work. There is a strong emphasis on development methods and step by step verification throughout the thesis, to provide a framework for future research in this area. In addition to the Benchmark results, additional studies on propagation of fundamental nuclear data uncertainty, and sensitivity analysis of coupled transients are reported in this thesis. Two Phenomena and Key Parameter Identification and Ranking Tables were generated for the loss of coolant accident scenario, to provide feedback to the Benchmark Team, and to add to the body of work on uncertainty/sensitivity analysis of CANDU style reactors. Some important results from the uncertainty analysis work relate to changes in the uncertainty of figures of merit such as integrated core power, and peak core power magnitude and time, between small and large break loss of coolant accidents. The analysis shows that the mean and standard deviation of the integrated core power and maximum integrated channel power, are very close between a 30% header break and a 60% header break, despite the peak core power being much larger in the 60% break case. Furthermore, it shows that there is a trade off between the uncertainty in the time of the peak core power, and the magnitude of the peak core power, with smaller breaks showing a smaller standard deviation in the magnitude of the peak core power, but a larger standard deviation in when this power is reached during the transient, and vice versa for larger breaks. From the results of the sensitivity analysis study, this thesis concludes that parameters related to coolant void reactivity and shutoff rod timing and effectiveness have the largest impact on loss of coolant accident progressions, while parameters that can have a large impact in other transients or reactor designs, such as fuel temperature reactivity feedback and control device incremental cross sections, are less important. / Thesis / Master of Science (MSc) / This thesis documents McMaster’s contribution to an International Atomic Energy Agency Benchmark on Pressurized Heavy Water Reactors that closely resemble the CANDU design. The Benchmark focus is on coupling of thermal-hydraulics and neutron physics codes, and simulation of postulated accident scenarios. This thesis contains some select results from the Benchmark, comparing the results generated by McMaster to other participants. This thesis also documents additional work that was performed to propagate fundamental nuclear data uncertainty through the coupled transient calculations and obtain an estimate of the uncertainty in key figures of merit. This work was beyond the scope of the Benchmark and is a unique contribution to the open literature. Finally, sensitivity studies were performed on one of the accident scenarios defined in the Benchmark, the loss of coolant accident, to determine which input parameters have the largest contribution to the variability of key figures of merit.

O Laboratório de Análise por Ativação com Nêutrons (LAN-IPEN) vem analisando amostras geológicas, tais como rochas, solos e sedimentos, há vários anos, empregando o método de análise por ativação com nêutrons comparativa, visando estudos geoquímicos e ambientais. Este trabalho apresenta os resultados obtidos na implementação do método de padronização k0-INAA no LANIPEN, para a análise de amostras geológicas, utilizando o programa k0-IAEA, fornecido pela Agência Internacional de Energia Atômica (IAEA). A razão do fluxo de nêutrons térmico-epitérmico f e o fator &alpha; da distribuição de fluxo de nêutrons epitérmicos do reator IEA-R1 do IPEN foram determinados na estação pneumática de irradiação, e em uma posição de irradiação selecionada, para irradiações curtas e longas, respectivamente. Para obter esses fatores, foi utilizado o chamado método bare triple-monitor com 197Au-96Zr-94Zr. Para avaliar a exatidão e precisão do método, foram analisados os materiais geológicos de referência basalto JB-1 (GSJ) e BE-N (IWG-GIT), andesito AGV-1 (USGS), granito GS-N (ANRT), SOIL-7 (IAEA) e sedimento Buffalo River Sediment (NIST BRS-8704), que representam diferentes matrizes geológicas. Os resultados obtidos para até 30 elementos concordaram com os valores recomendados, com erros relativos (bias) menores que 10%, exceto no caso do Zn no AGV-1 (11,4%) e Mg no GS-N (13,4%). Os critérios estatísticos z-score, zeta-score e U-score foram aplicados para avaliação dos resultados. Pelo critério do z-score, os resultados obtidos puderam ser considerados satisfatórios (z<2), com exceção dos resultados obtidos para Mg no GS-N e no JB-1, e para Yb no Soil-7. O critério estatístico zeta-score se mostrou o mais restritivo, obtendo-se resultados questionáveis (2 < zeta < 3) para Mg no BE-N, Mn no GS-N e Yb no Soil-7, e resultados insatisfatórios (zeta>3) para Mn no BE-N, Mg, Ce e La no GS-N, Mg no JB-1, e Th e Eu no Buffalo River Sediment. Os valores de U-score mostraram que todos os resultados, com exceção do valor para Mg no JB-1, estão dentro de um intervalo de confiança de 95% (se for considerado 1,96 o valor limite para o Uteste para um nível de probabilidade de 95%). Estes resultados indicam excelentes possibilidades para o uso deste método paramétrico no LAN-IPEN para a análise de amostras geológicas em estudos geoquímicos e ambientais. / The Neutron Activation Analysis Laboratory (LAN-IPEN) has been analysing geological samples such as rocks, soils and sediments, for many years with the INAA comparative method, for geochemical and environmental research. This study presents the results obtained in the implementation of the k0-standardization method at LANIPEN, for geological sample analysis, by using the program k0- IAEA, provided by the International Atomic Energy Agency (IAEA). The thermal to epithermal flux ratio f and the shape factor &alpha; of the epithermal flux distribution of the IPEN IEA-R1 nuclear reactor were determined for the pneumatic irradiation facility and one selected irradiation position, for short and long irradiations, respectively. To obtain these factors, the bare triple-monitor method with 197Au- 96Zr-94Zr was used. In order to validate the methodology, the geological reference materials basalts JB-1 (GSJ) and BE-N (IWG-GIT), andesite AGV-1 (USGS), granite GS-N (ANRT), SOIL-7 (IAEA) and sediment Buffalo River Sediment (NISTBRS-8704), which represent different geological matrices, were analysed. The concentration results obtained agreed with assigned values, with bias less than 10% except for Zn in AGV-1 (11.4%) and Mg in GS-N (13.4%). Three different scores were used to evaluate the results: z-score, zeta-score and Uscore. The z-score showed that the results can be considered satisfactory (z<2), except for Mg in GS-N and JB-1, and for Yb in Soil-7. Zeta-score was the most restrictive criterion, indicating questionable results (2 < zeta < 3) for Mg in BE-N, Mn in GS-N and Yb in Soil-7, and unsatisfactory results (zeta>3) for Mn in BE-N, Mg, Ce and La in GS-N, Mg in JB-1, and Th and Eu in Buffalo River Sediment. The U-score test showed that all results, except Mg in JB-1, were within 95% confidence interval. These results indicate excellent possibilities of using this parametric method at the LAN-IPEN for geological samples analysis in geochemical and environmental studies.

O Laboratório de Análise por Ativação com Nêutrons (LAN-IPEN) vem analisando amostras geológicas, tais como rochas, solos e sedimentos, há vários anos, empregando o método de análise por ativação com nêutrons comparativa, visando estudos geoquímicos e ambientais. Este trabalho apresenta os resultados obtidos na implementação do método de padronização k0-INAA no LANIPEN, para a análise de amostras geológicas, utilizando o programa k0-IAEA, fornecido pela Agência Internacional de Energia Atômica (IAEA). A razão do fluxo de nêutrons térmico-epitérmico f e o fator &alpha; da distribuição de fluxo de nêutrons epitérmicos do reator IEA-R1 do IPEN foram determinados na estação pneumática de irradiação, e em uma posição de irradiação selecionada, para irradiações curtas e longas, respectivamente. Para obter esses fatores, foi utilizado o chamado método bare triple-monitor com 197Au-96Zr-94Zr. Para avaliar a exatidão e precisão do método, foram analisados os materiais geológicos de referência basalto JB-1 (GSJ) e BE-N (IWG-GIT), andesito AGV-1 (USGS), granito GS-N (ANRT), SOIL-7 (IAEA) e sedimento Buffalo River Sediment (NIST BRS-8704), que representam diferentes matrizes geológicas. Os resultados obtidos para até 30 elementos concordaram com os valores recomendados, com erros relativos (bias) menores que 10%, exceto no caso do Zn no AGV-1 (11,4%) e Mg no GS-N (13,4%). Os critérios estatísticos z-score, zeta-score e U-score foram aplicados para avaliação dos resultados. Pelo critério do z-score, os resultados obtidos puderam ser considerados satisfatórios (z<2), com exceção dos resultados obtidos para Mg no GS-N e no JB-1, e para Yb no Soil-7. O critério estatístico zeta-score se mostrou o mais restritivo, obtendo-se resultados questionáveis (2 < zeta < 3) para Mg no BE-N, Mn no GS-N e Yb no Soil-7, e resultados insatisfatórios (zeta>3) para Mn no BE-N, Mg, Ce e La no GS-N, Mg no JB-1, e Th e Eu no Buffalo River Sediment. Os valores de U-score mostraram que todos os resultados, com exceção do valor para Mg no JB-1, estão dentro de um intervalo de confiança de 95% (se for considerado 1,96 o valor limite para o Uteste para um nível de probabilidade de 95%). Estes resultados indicam excelentes possibilidades para o uso deste método paramétrico no LAN-IPEN para a análise de amostras geológicas em estudos geoquímicos e ambientais. / The Neutron Activation Analysis Laboratory (LAN-IPEN) has been analysing geological samples such as rocks, soils and sediments, for many years with the INAA comparative method, for geochemical and environmental research. This study presents the results obtained in the implementation of the k0-standardization method at LANIPEN, for geological sample analysis, by using the program k0- IAEA, provided by the International Atomic Energy Agency (IAEA). The thermal to epithermal flux ratio f and the shape factor &alpha; of the epithermal flux distribution of the IPEN IEA-R1 nuclear reactor were determined for the pneumatic irradiation facility and one selected irradiation position, for short and long irradiations, respectively. To obtain these factors, the bare triple-monitor method with 197Au- 96Zr-94Zr was used. In order to validate the methodology, the geological reference materials basalts JB-1 (GSJ) and BE-N (IWG-GIT), andesite AGV-1 (USGS), granite GS-N (ANRT), SOIL-7 (IAEA) and sediment Buffalo River Sediment (NISTBRS-8704), which represent different geological matrices, were analysed. The concentration results obtained agreed with assigned values, with bias less than 10% except for Zn in AGV-1 (11.4%) and Mg in GS-N (13.4%). Three different scores were used to evaluate the results: z-score, zeta-score and Uscore. The z-score showed that the results can be considered satisfactory (z<2), except for Mg in GS-N and JB-1, and for Yb in Soil-7. Zeta-score was the most restrictive criterion, indicating questionable results (2 < zeta < 3) for Mg in BE-N, Mn in GS-N and Yb in Soil-7, and unsatisfactory results (zeta>3) for Mn in BE-N, Mg, Ce and La in GS-N, Mg in JB-1, and Th and Eu in Buffalo River Sediment. The U-score test showed that all results, except Mg in JB-1, were within 95% confidence interval. These results indicate excellent possibilities of using this parametric method at the LAN-IPEN for geological samples analysis in geochemical and environmental studies.

The safety and safety work on OKG, Oskarshamns Kraftgrupp, is supervised by SKI, Swedish nuclear power inspectorate. The task of SKI is to inspect that the nuclear power plants of Sweden runs in a safe way. The proprietor of the permit who runs nuclear power plants has the responsibility to maintain the required safety to run a plant. SKI publishes a number of statue books that OKG has to meet to be able to run the plants. SKI recommends in SKIFS 2 004:1, that OKG work with the safety requirements of IAEA. IAEA, International Atomic Energy Agency is a worldwide cooperation in the nuclear industry. The purpose with the thesis is to do a gap-analysis between the management system of OKG and GS-R-3, a safety standard of IAEA, furthermore basis to work with possible gaps will be brought up. The expected result is to find possibilities for improvements in the management system of the organization. The methods used in the thesis are literature studies, interviews and classification. An assessment has been made, if the management system of OKG meets the safety standard GSR- 3 of IAEA. The assessment is based on information in documents from the management system of the company and information that had been brought up by interviews with experts in different areas. The interviews have been a complement when the documents not were clear enough. For some of the possibilities to improve that was found, basis to work with these areas was brought up from IAEA and WANO. WANO, the World Association of Nuclear Operators, is an organization with the purpose to increase safety end reliability in the nuclear industry, by increasing communication, exchanging information and comparison between the nuclear power plants around the world. The requirements were divided in to three classes, those requirements that were met by the management system, those who were partly met and those that were not at all met. Finally 64 % was assessed being met, 29 % partly met and 7 % not met at all by the management system of OKG. The conclusion drawn is that there are a number of possibilities to improve the management system of OKG to be able to meet the IAEA GS-R-3. The major areas to work with is grading of documents, working with processes, assessing the organization, handling nonconformances, working with improvements and feedback from experience. / <p>Uppsatsnivå: D</p>

The thesis of is to strengthen the capacity building of nuclear safety and disaster prevention all over the world from a preventive perspective, and to ensure zero probability of any nuclear disaster in the world. In the face of threat from skyrocketing fossil fuel prices and the pressure of GHG emission reduction, nuclear power generation, with its advantages on low carbon emission, has been valued once again. More and more countries have taken positive and active attitudes toward nuclear power generation, facilitating the development of it or adopting nuclear energy as a potential alternative energy option in the future. Through information sharing, knowledge dissemination and cross-organizational collaboration aim at assisting enery country in their capacity building of nuclear safety and nuclear disaster prevention, and to promote conformity of enery operation towards nuclear safety and disaster prevention. Thus we should seek to help to promote every country¡¦s public education and communication of nuclear safety and to contribute to energy security and sustainable development in the world.

Iran’s nuclear program continues to present a major challenge to U.S. policy. At the core of this challenge is one fundamental question: Is Iran attempting to build a nuclear weapon? Objective analysis reveals that Iran’s dependence on oil and natural gas provides sufficient economic merit for Iran to pursue a peaceful nuclear program; without nuclear power to meet rising domestic energy needs, Iran’s economy will suffer. Though the economic justification is valid, the security of Iran and the survival of its regime are overarching; acts of foreign interference in Iran’s affairs have fueled the regime’s quest for a nuclear weapon. For this reason, U.S. administrations since the 1979 revolution have striven to derail Iran’s nuclear program through policies of containment, isolation, and denial of nuclear technology. Considering the current standoff between Iran and the U.S., we must ask another key question: How effective have U.S. policies been? The answer is simple; Iran has made significant progress in its nuclear program. Sanctions, political pressure, and threats proved no obstacle to Iran; worse still, ignoring IAEA and other’s reports that found no convincing evidence that Iran is building nuclear weapons damaged U.S. efforts significantly. Iran’s progress makes it clear that U.S. policies have failed, and its strategies must be discarded in favor of a new approach. This research implicates that a non-confrontational engagement policy, which acknowledges Iran’s needs to build a peaceful nuclear program will provide President Obama and the U.S. the highest probability of preventing Iran from acquiring nuclear weapons.

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Made available in DSpace on 2014-10-09T12:52:05Z (GMT). No. of bitstreams: 0 / Made available in DSpace on 2014-10-09T13:57:44Z (GMT). No. of bitstreams: 0 / A fim de implementar o novo código de prática da Agência Internacional de Energia Atômica (AIEA) no Brasil, o Laboratório de Calibração de Instrumentos (LCI/IPEN) está realizando calibrações em termos de kerma no ar e em termos de dose absorvida na água, em feixes de 60Co. As razões ND,w/NK obtidas são comparadas com valores da literatura, obtendo-se concordância satisfatória. As diferenças entre os valores das razões CK (ND,w/NK) obtidas no presente trabalho e os valores da literatura são devidas a vários fatores. Estes fatores podem ser as variações entre as câmaras, que devem ser objeto de diferenças nas incertezas estimadas pelos PSDLs, e as diferenças nos padrões utilizados por cada Instituto de Metrologia Nacional (NMI) ou Laboratório de Dosimetria. No entanto, se forem conhecidas as razões entre cada NMI e o BIPM, para os padrões de kerma no ar e de dose absorvida na água, é possível a normalização das razões CK medidas para as razões equivalentes ao BIPM. Todos os resultados de razões CK obtidos foram convertidos para as razões equivalentes ao BIPM para facilitar a comparação. Neste trabalho é discutida a utilização da razão CK como parâmetro de controle de qualidade na verificação de resultados das calibrações rotineiras. Para avaliação dos procedimentos de calibração adotados no LCI, foram realizados testes de estabilidade a longo prazo com as câmaras de ionização padrões. Além disso, foi criado um banco de dados para armazenamento dos dados de calibração, com o objetivo de melhorar a qualidade do procedimento de calibração. / Dissertação (Mestrado) / IPEN/D / Instituto de Pesquisas Energeticas e Nucleares - IPEN/CNEN-SP