The development of non-destructive assay (NDA) capabilities to directly measure the fissile content in spent fuel is needed to improve the timely detection of the diversion of significant quantities of fissile material. Currently, the International Atomic Energy Agency (IAEA) does not have effective NDA methods to verify spent fuel and recover continuity of knowledge in the event of a containment and surveillance systems failure. This issue has become increasingly critical with the worldwide expansion of nuclear power, adoption of enhanced safeguards criteria for spent fuel verification, and recent efforts by the IAEA to incorporate an integrated safeguards regime. In order to address these issues, the use of Self-Interrogation Neutron Resonance Densitometry (SINRD) has been developed to improve existing nuclear safeguards and material accountability measurements. The following characteristics of SINRD were analyzed: (1) ability to measure the fissile content in Light Water Reactors (LWR) fuel assemblies and (2) sensitivity and penetrability of SINRD to the removal of fuel pins from an assembly. The Monte Carlo Neutral Particle eXtended (MCNPX) transport code was used to simulate SINRD for different geometries. Experimental measurements were also performed with SINRD and were compared to MCNPX simulations of the experiment to verify the accuracy of the MCNPX model of SINRD. Based on the results from these simulations and measurements, we have concluded that SINRD provides a number of improvements over current IAEA verification methods. These improvements include: 1) SINRD provides absolute measurements of burnup independent of the operator’s declaration. 2) SINRD is sensitive to pin removal over the entire burnup range and can verify the diversion of 6% of fuel pins within 3σ from LWR spent LEU and MOX fuel. 3) SINRD is insensitive to the boron concentration and initial fuel enrichment and can therefore be used at multiple spent fuel storage facilities. 4) The calibration of SINRD at one reactor facility carries over to reactor sites in different countries because it uses the ratio of fission chambers (FCs) that are not facility dependent. 5) SINRD can distinguish fresh and 1-cycle spent MOX fuel from 3- and 4-cycles spent LEU fuel without using reactor burnup codes.

Os Ensaios Não Destrutivos (END), são aplicados em testes de qualidade de componentes e de máquinas. Estes elementos não teriam um bom desempenho se fossem concebidos alheios à qualidade do projeto, aos materiais envolvidos, aos processos de fabricação e à metodologia de inspeção e manutenção. Um alto nível de tecnologia é aplicado com um objetivo específico, ou seja, à garantia da qualidade dos componentes e do bom funcionamento dessas máquinas, seja na indústria e na geração e conversão de energia, incluindo a nuclear. A globalização nos diversos ramos da indústria leva a um aumento na quantidade de projetos e produtos contextualmente multinacionais. Surgem, as seguintes questões: como assegurar que os componentes e os processos utilizados se disponhem de alto índice na qualidade? Como otimizar os métodos e os rocessos de teste de materiais para assegurar a isenção de defeitos que possam afetar o esempenho dos componentes? As respostas para as questões se encontram notadamente na aplicação dos END. A análise de materiais complexos (não homogêneos) por meio de END requer um estudo detalhado dos sinais de resposta dos sensores. Um sistema de medidas e controle de processos não destrutivos usando radiação gama ou beta, em função do material a ser analisado foi desenvolvido. Esse sistema envolve: (a) Interface de entrada/saída (Hardware) e (b) Interface gráfica (Software). Na análise não destrutiva faz-se a comparação do sinal proveniente do sensor com um sinal preestabelecido (Set Point) ou sinal de referência, o qual é ajustado na Interface de entrada/saída. Após o processamento geral, o sistema tomará a decisão de rejeitar ou não o material analisado. A Interface de entrada/saída é implementada por um equipamento eletrônico constituído pelo MCS51, com a finalidade de fornecer um meio físico para troca de nformações, via de comunicação serial RS232, entre o sensor e o microcomputador . A Interface gráfica (programa computacional) foi escrita em linguagem C++ visual. / Nondestructive Assay (NDA) is applied to machines and components quality tests. These elements would not have a good performance if they were conceived without concern about the mechanical project quality, used materials, manufacture processes and inspection and maintenance methodology. There are constant developments in high level of technology with the objective of guaranteeing the components quality and the good functioning of these machines, in the mechanics, naval, aeronautical, petrochemical and steel industry, energy and nuclear generation as well. The globalization in the industry lines is a fact, leading to an increase in the multinational projects and products. The following questions arise: how to assure the high quality of components and processes? How to optimize the test methods to assure that the materials do not have defects affecting the performance of the components? The answers to the questions above are found in the application of NDA. The complex materials analysis (inhomogeneous) using NDA requires a detailed study of the sensors response signal. In this work, a measure and control system of non destructive processes was developed, using a radioactive source with a defined energy in function of the material to be analyzed. This system involves: (a) Interface of input/output (I/O) (the Hardware) and (b) graphical Interface (Software). In the non destructive analysis, it is made the comparison of the signal proceeding from the sensor with a signal preset (Set Point) or analogical signal of reference (Base Line), which is adjusted in the I/O Interface. Analyzed the signal, the system will make the decision: (a) to reject or (b) to accept the analyzed material. The I/O Interface is implemented by electronic equipment with a MCS51. The purpose of this interface is to supply conditions to exchange information, using serial RS232, between the sensor and the microcomputer. The graphical Interface (software) is written in visual C++ language.

Os Ensaios Não Destrutivos (END), são aplicados em testes de qualidade de componentes e de máquinas. Estes elementos não teriam um bom desempenho se fossem concebidos alheios à qualidade do projeto, aos materiais envolvidos, aos processos de fabricação e à metodologia de inspeção e manutenção. Um alto nível de tecnologia é aplicado com um objetivo específico, ou seja, à garantia da qualidade dos componentes e do bom funcionamento dessas máquinas, seja na indústria e na geração e conversão de energia, incluindo a nuclear. A globalização nos diversos ramos da indústria leva a um aumento na quantidade de projetos e produtos contextualmente multinacionais. Surgem, as seguintes questões: como assegurar que os componentes e os processos utilizados se disponhem de alto índice na qualidade? Como otimizar os métodos e os rocessos de teste de materiais para assegurar a isenção de defeitos que possam afetar o esempenho dos componentes? As respostas para as questões se encontram notadamente na aplicação dos END. A análise de materiais complexos (não homogêneos) por meio de END requer um estudo detalhado dos sinais de resposta dos sensores. Um sistema de medidas e controle de processos não destrutivos usando radiação gama ou beta, em função do material a ser analisado foi desenvolvido. Esse sistema envolve: (a) Interface de entrada/saída (Hardware) e (b) Interface gráfica (Software). Na análise não destrutiva faz-se a comparação do sinal proveniente do sensor com um sinal preestabelecido (Set Point) ou sinal de referência, o qual é ajustado na Interface de entrada/saída. Após o processamento geral, o sistema tomará a decisão de rejeitar ou não o material analisado. A Interface de entrada/saída é implementada por um equipamento eletrônico constituído pelo MCS51, com a finalidade de fornecer um meio físico para troca de nformações, via de comunicação serial RS232, entre o sensor e o microcomputador . A Interface gráfica (programa computacional) foi escrita em linguagem C++ visual. / Nondestructive Assay (NDA) is applied to machines and components quality tests. These elements would not have a good performance if they were conceived without concern about the mechanical project quality, used materials, manufacture processes and inspection and maintenance methodology. There are constant developments in high level of technology with the objective of guaranteeing the components quality and the good functioning of these machines, in the mechanics, naval, aeronautical, petrochemical and steel industry, energy and nuclear generation as well. The globalization in the industry lines is a fact, leading to an increase in the multinational projects and products. The following questions arise: how to assure the high quality of components and processes? How to optimize the test methods to assure that the materials do not have defects affecting the performance of the components? The answers to the questions above are found in the application of NDA. The complex materials analysis (inhomogeneous) using NDA requires a detailed study of the sensors response signal. In this work, a measure and control system of non destructive processes was developed, using a radioactive source with a defined energy in function of the material to be analyzed. This system involves: (a) Interface of input/output (I/O) (the Hardware) and (b) graphical Interface (Software). In the non destructive analysis, it is made the comparison of the signal proceeding from the sensor with a signal preset (Set Point) or analogical signal of reference (Base Line), which is adjusted in the I/O Interface. Analyzed the signal, the system will make the decision: (a) to reject or (b) to accept the analyzed material. The I/O Interface is implemented by electronic equipment with a MCS51. The purpose of this interface is to supply conditions to exchange information, using serial RS232, between the sensor and the microcomputer. The graphical Interface (software) is written in visual C++ language.

The safeguards verification of spent nuclear fuel is one of the major concern for the safeguards community, as this material represents about 80% of all material placed under safeguards.This PhD thesis described the development of two passive non-destructive assay (NDA) techniques: the Self-Indication Neutron Resonance Densitometry (SINRD) and the Partial Defect Tester (PDET).The NDA methods were investigated with Monte Carlo simulations and the benchmark experiments for SINRD were performed at the GELINA facility of JRC-IRMM in Geel, Belgium.The results for the SINRD technique showed promising results for the direct quantification of 239Pu in spent fuel, and both techniques gave encouraging results for the detection of partial defects. / Doctorat en Sciences de l'ingénieur et technologie / info:eu-repo/semantics/nonPublished

The large thermal cross section of cadmium makes it ideal for many practical applications where screening of thermal neutrons is desired. For example, in non-destructive assay techniques, or for astrophysical studies of the s-process. All such applications require precise knowledge of the neutron-capture cross section on cadmium. Although there are some data on neutron-capture cross sections particularly at thermal energies and at energies relevant for astrophysics, there is very little data at most other energies. Further, the evaluated cross sections from the ENDF and JENDL databases disagree at high energies. Therefore, there is a critical need for precise knowledge of the 114Cd(n, gamma)115Cd cross section over a large range of incident neutron energies. We performed a direct measurement of the neutron-capture cross section at the Los Alamos Neutron Science Center (LANSCE) using the Detector for Advanced Neutron Capture Experiments (DANCE). A highly enriched (∼$99%), 100 mg pressed metallic pellet sample of 114Cd was used to perform the neutron-capture measurements in the range of 1 eV to 300 keV using the white neutron source available at LANSCE. Additional neutron capture data were also taken on highly enriched samples of 112Cd and 113Cd to enable careful background subtraction of even the small contaminants found in the 114Cd sample. We used a large energy sum windows around the Q-value to circumvent any complication that may arise from populating the 180 keV isomeric (T1/2 = 44.56d) state in 115Cd.

A geological repository for spent nuclear fuel (SNF) and an associated encapsulation facility will be built in Sweden.  The encapsulation facility is planned to be in operation in 2025 and it will be the last place where verifying safeguards measurements of SNF can be performed. It is not clear what types of measurements that will be performed, because such requirements are not yet posed by national and international authorities and inspecting organizations. This report describes the objective and most recent results of a master thesis project, whereby a few existing non-destructive assay techniques for verifying SNF are selected for a review. The study focuses on the verifying ability of different techniques, or system of techniques in relation to the requirement that may be put on the future encapsulation plant. In addition, possible needs for future simulations and measurements are discussed. The work is done as a collaboration between Uppsala University in Sweden and Los Alamos National Laboratory in the USA.

Ensaio não destrutivo é uma ferramenta essencial quando um equipamento, dispositivo ou componente não pode ser submetido a procedimentos destrutivos ou invasivos devido a razões de segurança, alto custo ou outras restrições físicas ou logísticas. Dentro deste quadro radiografias por transmissão com raios gama e nêutrons térmicos são técnicas singulares para inspecionar um objeto e desvendar sua estrutura interna devido à capacidade de atravessar uma vasta gama de materiais utilizados na indústria. Grosso modo, raios gama são mais atenuados por materiais pesados enquanto nêutrons térmicos são mais atenuados por materiais mais leves, tornando-as ferramentas complementares. Este trabalho apresenta os resultados obtidos na inspeção de vários componentes mecânicos, através da radiografia por transmissão com nêutrons térmicos e raios gama. O fluxo de nêutrons térmicos de 4,46x105 n.cm-2.s-1 disponível no canal principal do reator de pesquisa Argonauta do Instituto de Engenharia Nuclear foi usado como fonte para as imagens radiográficas com nêutrons. Raios dekeV emitidos pelo 198Au, também produzido no reator, foram usados como fonte de radiação para radiografias . Imaging Plates, especificamente produzidos para operar com nêutrons térmicos ou com raios X, foram empregados como detectores e dispositivos de armazenamento e captação de imagens para cada uma dessas radiações. Esses dispositivos exibem varias vantagens quando comparados ao filme radiográfico convencional. Com efeito, além de maior sensibilidade e serem reutilizáveis não são necessários câmaras escuras e processamento químico para a revelação. Em vez disso, ele é lido por um feixe de laser que libera elétrons armadilhados na rede cristalina durante a exposição à radiação, fornecendo uma imagem final digital. O desempenho de ambos os sistemas de aquisição de imagens, assim constituído, foi avaliado com respeito à sensibilidade, resolução espacial, linearidade e range dinâmico, incluído uma comparação com sistemas radiográficos com nêutrons empregando filmes e folhas de gadolínio como conversor de nêutrons em partículas carregadas. Além desta caracterização, diversos equipamentos e componentes foram radiografados com ambos os sistemas visando-se avaliar suas capacidades de desvendar a estrutura interna desses objetos e detectar estruturas e estados anormais. Dentro desta abordagem, uma neutrongrafia detectou a presença de material cerâmico remanescente empregado como molde no processo de fabricação nos canais de refrigeração de uma aleta do estator de uma turbina tipo turbo-fan, que deveria estar livre desse material. O reostato danificado de um sensor de pressão automotivo, foi identificado por neutrongrafia, embora nesse caso a radiografia também conseguiu realizar essa tarefa com melhor resolução, corroborando assim as curvas de resolução espacial obtidas na caracterização dos dois sistemas. A homogeneidade da distribuição do material encapsulado em uma gaxeta explosiva de chumbo utilizada na indústria aeroespacial foi igualmente verificada por neutrongrafia porque esse metal é relativamente transparente para nêutrons, mas suficientemente opaco para o explosivo rico em hidrogênio. Diversos outros instrumentos e componentes tais como variômetro, altímetro, bússola aeronáutica, injetor automotivo de combustível, foto-camera, disco rígido de computador, motor de passo, conectores eletrônicos e projéteis foram radiografados com ambos os sistemas visando avaliar suas habilidades em desvendar diferentes peculiaridades em função do agente interrogador. / Non-destructive testing is an essential approach whenever a piece of equipment, device, or component should not be submitted to a destructive or invasive procedure due to safety reasons, high costs or other physical or logistics constraints. Within this frame, transmission radiography with gamma-rays and thermal neutrons are unique techniques to inspect an object and unveil its inner structure thanks to their capability to pass through a wide range of materials employed in the manufacturing industry. Roughly, as a rule of thumb, gamma-rays are more attenuated by heavy materials, while thermal neutrons are attenuated by the light ones, making them complementary tools. This work presents the results obtained in the inspection of several mechanical components through neutron and gamma-ray transmission radiography. The 4.46 x 105 n.cm-2.s-1 thermal neutron flux available at the main port of the Argonauta research reactor in Instituto de Engenharia Nuclear has been used as source for the neutron radiographic imaging. The 412 keV gamma-ray emitted by 198Au, also produced in that reactor, has been used as interrogation agent for the gamma radiography. Imaging Plates - IP specifically designed to operate with thermal neutrons or with X-rays have been employed as detectors and storage devices for each of these radiations. These devices exhibit several advantages with regard to the conventional radiographic film. Indeed, besides a higher sensitivity and reusability, a dark chamber and a cumbersome chemical processing is not required for the development. Instead, it is carried out by a laser beam which interrogates the electric state of the crystal lattices of the IP, yielding a final digital image. Performances of both Image Acquisition Systems so constituted have been evaluated with regard to sensitivity, spatial resolution, linearity and dynamic range, including a comparison with the neutron radiographic system employing films and a Gd foil as neutron-to-charged particle converter. Besides this characterization, several pieces of equipment, have been radiographed with both systems aiming at the evaluation of their capability to unveil the inner features of these components and to detect abnormal structures or states. Within this frame, a neutron radiography detected the presence of remaining ceramic material - employed as a mold during the manufacturing process - in the cooling channels of a turbo-fan stator blade, which should be free of it. Neutron and gamma-ray radiographs have also shown the damaged rheostat of an automotive pressure probe, but the last one exhibited a better spatial resolution corroborating thus the results obtained during the characterization of both systems. The homogeneity of distribution of the stuff encapsulated in an explosive lead-gasket used in the aero-space industry has also been verified by neutron radiography, for this metal is fairly transparent to neutrons but opaque enough to the hydrogen-bearing explosive material. A diversity of other instruments and components such as variometer, altimeter, aeronautical compass, automotive fuel injector, photo-camera, computer hard disk, step-motor, electronic connectors and bullets have been as well radiographed with both systems addressing their ability to unveil different features according to the type of the employed interrogating agente.

Ensaio não destrutivo é uma ferramenta essencial quando um equipamento, dispositivo ou componente não pode ser submetido a procedimentos destrutivos ou invasivos devido a razões de segurança, alto custo ou outras restrições físicas ou logísticas. Dentro deste quadro radiografias por transmissão com raios gama e nêutrons térmicos são técnicas singulares para inspecionar um objeto e desvendar sua estrutura interna devido à capacidade de atravessar uma vasta gama de materiais utilizados na indústria. Grosso modo, raios gama são mais atenuados por materiais pesados enquanto nêutrons térmicos são mais atenuados por materiais mais leves, tornando-as ferramentas complementares. Este trabalho apresenta os resultados obtidos na inspeção de vários componentes mecânicos, através da radiografia por transmissão com nêutrons térmicos e raios gama. O fluxo de nêutrons térmicos de 4,46x105 n.cm-2.s-1 disponível no canal principal do reator de pesquisa Argonauta do Instituto de Engenharia Nuclear foi usado como fonte para as imagens radiográficas com nêutrons. Raios dekeV emitidos pelo 198Au, também produzido no reator, foram usados como fonte de radiação para radiografias . Imaging Plates, especificamente produzidos para operar com nêutrons térmicos ou com raios X, foram empregados como detectores e dispositivos de armazenamento e captação de imagens para cada uma dessas radiações. Esses dispositivos exibem varias vantagens quando comparados ao filme radiográfico convencional. Com efeito, além de maior sensibilidade e serem reutilizáveis não são necessários câmaras escuras e processamento químico para a revelação. Em vez disso, ele é lido por um feixe de laser que libera elétrons armadilhados na rede cristalina durante a exposição à radiação, fornecendo uma imagem final digital. O desempenho de ambos os sistemas de aquisição de imagens, assim constituído, foi avaliado com respeito à sensibilidade, resolução espacial, linearidade e range dinâmico, incluído uma comparação com sistemas radiográficos com nêutrons empregando filmes e folhas de gadolínio como conversor de nêutrons em partículas carregadas. Além desta caracterização, diversos equipamentos e componentes foram radiografados com ambos os sistemas visando-se avaliar suas capacidades de desvendar a estrutura interna desses objetos e detectar estruturas e estados anormais. Dentro desta abordagem, uma neutrongrafia detectou a presença de material cerâmico remanescente empregado como molde no processo de fabricação nos canais de refrigeração de uma aleta do estator de uma turbina tipo turbo-fan, que deveria estar livre desse material. O reostato danificado de um sensor de pressão automotivo, foi identificado por neutrongrafia, embora nesse caso a radiografia também conseguiu realizar essa tarefa com melhor resolução, corroborando assim as curvas de resolução espacial obtidas na caracterização dos dois sistemas. A homogeneidade da distribuição do material encapsulado em uma gaxeta explosiva de chumbo utilizada na indústria aeroespacial foi igualmente verificada por neutrongrafia porque esse metal é relativamente transparente para nêutrons, mas suficientemente opaco para o explosivo rico em hidrogênio. Diversos outros instrumentos e componentes tais como variômetro, altímetro, bússola aeronáutica, injetor automotivo de combustível, foto-camera, disco rígido de computador, motor de passo, conectores eletrônicos e projéteis foram radiografados com ambos os sistemas visando avaliar suas habilidades em desvendar diferentes peculiaridades em função do agente interrogador. / Non-destructive testing is an essential approach whenever a piece of equipment, device, or component should not be submitted to a destructive or invasive procedure due to safety reasons, high costs or other physical or logistics constraints. Within this frame, transmission radiography with gamma-rays and thermal neutrons are unique techniques to inspect an object and unveil its inner structure thanks to their capability to pass through a wide range of materials employed in the manufacturing industry. Roughly, as a rule of thumb, gamma-rays are more attenuated by heavy materials, while thermal neutrons are attenuated by the light ones, making them complementary tools. This work presents the results obtained in the inspection of several mechanical components through neutron and gamma-ray transmission radiography. The 4.46 x 105 n.cm-2.s-1 thermal neutron flux available at the main port of the Argonauta research reactor in Instituto de Engenharia Nuclear has been used as source for the neutron radiographic imaging. The 412 keV gamma-ray emitted by 198Au, also produced in that reactor, has been used as interrogation agent for the gamma radiography. Imaging Plates - IP specifically designed to operate with thermal neutrons or with X-rays have been employed as detectors and storage devices for each of these radiations. These devices exhibit several advantages with regard to the conventional radiographic film. Indeed, besides a higher sensitivity and reusability, a dark chamber and a cumbersome chemical processing is not required for the development. Instead, it is carried out by a laser beam which interrogates the electric state of the crystal lattices of the IP, yielding a final digital image. Performances of both Image Acquisition Systems so constituted have been evaluated with regard to sensitivity, spatial resolution, linearity and dynamic range, including a comparison with the neutron radiographic system employing films and a Gd foil as neutron-to-charged particle converter. Besides this characterization, several pieces of equipment, have been radiographed with both systems aiming at the evaluation of their capability to unveil the inner features of these components and to detect abnormal structures or states. Within this frame, a neutron radiography detected the presence of remaining ceramic material - employed as a mold during the manufacturing process - in the cooling channels of a turbo-fan stator blade, which should be free of it. Neutron and gamma-ray radiographs have also shown the damaged rheostat of an automotive pressure probe, but the last one exhibited a better spatial resolution corroborating thus the results obtained during the characterization of both systems. The homogeneity of distribution of the stuff encapsulated in an explosive lead-gasket used in the aero-space industry has also been verified by neutron radiography, for this metal is fairly transparent to neutrons but opaque enough to the hydrogen-bearing explosive material. A diversity of other instruments and components such as variometer, altimeter, aeronautical compass, automotive fuel injector, photo-camera, computer hard disk, step-motor, electronic connectors and bullets have been as well radiographed with both systems addressing their ability to unveil different features according to the type of the employed interrogating agente.

京都大学 / 0048 / 新制・課程博士 / 博士(エネルギー科学) / 甲第18664号 / エネ博第309号 / 新制||エネ||63(附属図書館) / 31578 / 京都大学大学院エネルギー科学研究科エネルギー応用科学専攻 / (主査)教授 大垣 英明, 教授 白井 康之, 教授 松田 一成 / 学位規則第4条第1項該当 / Doctor of Energy Science / Kyoto University / DFAM

As nuclear energy grows in the United States and around the world, the expansion of the nuclear fuel cycle is inevitable. All currently deployed commercial reprocessing plants are based on the Plutonium - Uranium Extraction (PUREX) process. However, this process is not implemented in the U.S. for a variety of reasons, one being that it is considered by some as a proliferation risk. The 2001 Nuclear Energy Policy report recommended that the U.S. "develop reprocessing and treatment technologies that are cleaner, more efficient, less waste-intensive, and more proliferation-resistant." The Uranium Extraction (UREX+) reprocessing technique has been developed to reach these goals. However, in order for UREX+ to be considered for commercial implementation, a safeguards approach is needed to show that a commercially sized UREX+ facility can be safeguarded to current international standards. A detailed safeguards approach for a UREX+1a reprocessing facility has been developed. The approach includes the use of nuclear material accountancy (MA), containment and surveillance (C/S) and solution monitoring (SM). Facility information was developed for a hypothesized UREX+1a plant with a throughput of 1000 Metric Tons Heavy Metal (MTHM) per year. Safeguard goals and safeguard measures to be implemented were established. Diversion and acquisition pathways were considered; however, the analysis focuses mainly on diversion paths. The detection systems used in the design have the ability to provide near real-time measurement of special fissionable material in feed, process and product streams. Advanced front-end techniques for the quantification of fissile material in spent nuclear fuel were also considered. The economic and operator costs of these systems were not considered. The analysis shows that the implementation of these techniques result in significant improvements in the ability of the safeguards system to achieve the objective of timely detection of the diversion of a significant quantity of nuclear material from the UREX+1a reprocessing facility and to provide deterrence against such diversion by early detection.