O fator de Dancoff, em sua formulação clássica, corrige a corrente de nêutrons incidente na superfície de uma vareta combustível devido à presença das demais varetas da célula. Alternativamente, esse fator pode ser interpretado como a probabilidade de um nêutron oriundo de uma vareta de combustível entrar em outra vareta sem colidir no moderador ou no revestimento. Para combustíveis perfeitamente absorvedores essas definições são equivalentes. Entretanto, quando se assume a hipótese de absorção parcial no combustível, essa equivalência não se verifica. Então, os fatores de Dancoff devem ser determinados em termos de probabilidades de colisão. Ao longo dos últimos anos, vários trabalhos, usando ambas as definições, vêm relatando melhorias no cálculo dos fatores Dancoff. Neste trabalho, esses fatores são determinados através do método de probabilidades de colisão para células em geometria cluster com contorno externo quadrado, assumindo-se absorção total (Black Dancoff Factors) e parcial (Grey Dancoff Factors) no combustível. A validação dos resultados é feita através de comparações com a célula cilíndrica equivalente. O cálculo é realizado considerando-se reflexão especular, para a célula quadrada, e condição de contorno difusa (white) para a célula cilíndrica equivalente. Os resultados obtidos, com o aumento do tamanho das células, evidenciam o comportamento assintótico da solução. Além disso, são computados fatores de Dancoff para as células canadenses CANDU-37 e CANFLEX por ambas as metodologias de cálculo, direta e probabilística. Finalmente, os fatores de multiplicação efetivo, keff, para as células com contorno externo quadrado e a cilíndrica equivalente, são determinados e as diferenças registradas para os casos onde se assumem as hipóteses de absorção total e parcial. / In its classical formulation, the Dancoff factor for a perfectly absorbing fuel rod is defined as the relative reduction in the incurrent of resonance neutrons into the rod in the presence of neighboring rods, as compared to the incurrent into a single fuel rod immersed in an infinite moderator. Alternatively, this factor can be viewed as the probability that a neutron emerging from the surface of a fuel rod will enter another fuel rod without any collision in the moderator or cladding. For perfectly absorbing fuel these definitions are equivalent. In the last years, several works appeared in literature reporting improvements in the calculation of Dancoff factors, using both the classical and the collision probability definitions. In this work, we step further reporting Dancoff factors for perfectly absorbing (Black) and partially absorbing (Grey) fuel rods calculated by the collision probability method, in cluster cells with square outer boundaries. In order to validate the results, comparisons are made with the equivalent cylindricalized cell in hypothetical test cases. The calculation is performed considering specularly reflecting boundary conditions, for the square lattice, and diffusive reflecting boundary conditions, for the cylindrical geometry. The results show the expected asymptotic behavior of the solution with increasing cell sizes. In addition, Dancoff factors are computed for the Canadian cells CANDU-37 and CANFLEX by the Monte Carlo and Direct methods. Finally, the effective multiplication factors, keff, for these cells (cluster cell with square outer boundaries and the equivalent cylindricalized cell) are also computed, and the differences reported for the cases using the perfect and partial absorption assumptions.

O fator de Dancoff, em sua formulação clássica, corrige a corrente de nêutrons incidente na superfície de uma vareta combustível devido à presença das demais varetas da célula. Alternativamente, esse fator pode ser interpretado como a probabilidade de um nêutron oriundo de uma vareta de combustível entrar em outra vareta sem colidir no moderador ou no revestimento. Para combustíveis perfeitamente absorvedores essas definições são equivalentes. Entretanto, quando se assume a hipótese de absorção parcial no combustível, essa equivalência não se verifica. Então, os fatores de Dancoff devem ser determinados em termos de probabilidades de colisão. Ao longo dos últimos anos, vários trabalhos, usando ambas as definições, vêm relatando melhorias no cálculo dos fatores Dancoff. Neste trabalho, esses fatores são determinados através do método de probabilidades de colisão para células em geometria cluster com contorno externo quadrado, assumindo-se absorção total (Black Dancoff Factors) e parcial (Grey Dancoff Factors) no combustível. A validação dos resultados é feita através de comparações com a célula cilíndrica equivalente. O cálculo é realizado considerando-se reflexão especular, para a célula quadrada, e condição de contorno difusa (white) para a célula cilíndrica equivalente. Os resultados obtidos, com o aumento do tamanho das células, evidenciam o comportamento assintótico da solução. Além disso, são computados fatores de Dancoff para as células canadenses CANDU-37 e CANFLEX por ambas as metodologias de cálculo, direta e probabilística. Finalmente, os fatores de multiplicação efetivo, keff, para as células com contorno externo quadrado e a cilíndrica equivalente, são determinados e as diferenças registradas para os casos onde se assumem as hipóteses de absorção total e parcial. / In its classical formulation, the Dancoff factor for a perfectly absorbing fuel rod is defined as the relative reduction in the incurrent of resonance neutrons into the rod in the presence of neighboring rods, as compared to the incurrent into a single fuel rod immersed in an infinite moderator. Alternatively, this factor can be viewed as the probability that a neutron emerging from the surface of a fuel rod will enter another fuel rod without any collision in the moderator or cladding. For perfectly absorbing fuel these definitions are equivalent. In the last years, several works appeared in literature reporting improvements in the calculation of Dancoff factors, using both the classical and the collision probability definitions. In this work, we step further reporting Dancoff factors for perfectly absorbing (Black) and partially absorbing (Grey) fuel rods calculated by the collision probability method, in cluster cells with square outer boundaries. In order to validate the results, comparisons are made with the equivalent cylindricalized cell in hypothetical test cases. The calculation is performed considering specularly reflecting boundary conditions, for the square lattice, and diffusive reflecting boundary conditions, for the cylindrical geometry. The results show the expected asymptotic behavior of the solution with increasing cell sizes. In addition, Dancoff factors are computed for the Canadian cells CANDU-37 and CANFLEX by the Monte Carlo and Direct methods. Finally, the effective multiplication factors, keff, for these cells (cluster cell with square outer boundaries and the equivalent cylindricalized cell) are also computed, and the differences reported for the cases using the perfect and partial absorption assumptions.

O fator de Dancoff, em sua formulação clássica, corrige a corrente de nêutrons incidente na superfície de uma vareta combustível devido à presença das demais varetas da célula. Alternativamente, esse fator pode ser interpretado como a probabilidade de um nêutron oriundo de uma vareta de combustível entrar em outra vareta sem colidir no moderador ou no revestimento. Para combustíveis perfeitamente absorvedores essas definições são equivalentes. Entretanto, quando se assume a hipótese de absorção parcial no combustível, essa equivalência não se verifica. Então, os fatores de Dancoff devem ser determinados em termos de probabilidades de colisão. Ao longo dos últimos anos, vários trabalhos, usando ambas as definições, vêm relatando melhorias no cálculo dos fatores Dancoff. Neste trabalho, esses fatores são determinados através do método de probabilidades de colisão para células em geometria cluster com contorno externo quadrado, assumindo-se absorção total (Black Dancoff Factors) e parcial (Grey Dancoff Factors) no combustível. A validação dos resultados é feita através de comparações com a célula cilíndrica equivalente. O cálculo é realizado considerando-se reflexão especular, para a célula quadrada, e condição de contorno difusa (white) para a célula cilíndrica equivalente. Os resultados obtidos, com o aumento do tamanho das células, evidenciam o comportamento assintótico da solução. Além disso, são computados fatores de Dancoff para as células canadenses CANDU-37 e CANFLEX por ambas as metodologias de cálculo, direta e probabilística. Finalmente, os fatores de multiplicação efetivo, keff, para as células com contorno externo quadrado e a cilíndrica equivalente, são determinados e as diferenças registradas para os casos onde se assumem as hipóteses de absorção total e parcial. / In its classical formulation, the Dancoff factor for a perfectly absorbing fuel rod is defined as the relative reduction in the incurrent of resonance neutrons into the rod in the presence of neighboring rods, as compared to the incurrent into a single fuel rod immersed in an infinite moderator. Alternatively, this factor can be viewed as the probability that a neutron emerging from the surface of a fuel rod will enter another fuel rod without any collision in the moderator or cladding. For perfectly absorbing fuel these definitions are equivalent. In the last years, several works appeared in literature reporting improvements in the calculation of Dancoff factors, using both the classical and the collision probability definitions. In this work, we step further reporting Dancoff factors for perfectly absorbing (Black) and partially absorbing (Grey) fuel rods calculated by the collision probability method, in cluster cells with square outer boundaries. In order to validate the results, comparisons are made with the equivalent cylindricalized cell in hypothetical test cases. The calculation is performed considering specularly reflecting boundary conditions, for the square lattice, and diffusive reflecting boundary conditions, for the cylindrical geometry. The results show the expected asymptotic behavior of the solution with increasing cell sizes. In addition, Dancoff factors are computed for the Canadian cells CANDU-37 and CANFLEX by the Monte Carlo and Direct methods. Finally, the effective multiplication factors, keff, for these cells (cluster cell with square outer boundaries and the equivalent cylindricalized cell) are also computed, and the differences reported for the cases using the perfect and partial absorption assumptions.

The effect of water ingress in two pebble bed high temperature gas-cooled reactors i.e. the PBMR-200 MWthermal and the PBMR-400 MWthermal were simulated and compared using the VSOP 99/05 suite of codes. To investigate the effect of this event on reactivity, power profiles and thermal neutron flux profiles, the addition of partial steam vapour pressures in stages up to 400 bar into the primary circuit for the PBMR-400 and up to 300 bar for the PBMR- 200 was simulated for both reactors. During the simulation, three scenarios were simulated, i.e. water ingress into the core only, water ingress into the reflectors only and water ingress into both the core and reflectors. The induced reactivity change effects were compared for these reactors. An in-depth analysis was also carried out to study the mechanisms that drive the reactivity changes for each reactor caused by water ingress into the fuel core only, the riser tubes in the reflectors only and ingress into both the fuel core and the riser tubes in the reflectors. The knowledge gained of these mechanisms and effects was used in order to propose design changes aimed at mitigating the reactivity increases, caused by realistic water ingress scenarios. Past results from simulations of water ingress into Pebble Bed Reactors were used to validate and verify the present simulation approach and results. The reactivity increase results for both reactors were in agreement with the German HTR-Modul calculations. / Thesis (MSc (Engineering Sciences in Nuclear Engineering))--North-West University, Potchefstroom Campus, 2013

The effect of water ingress in two pebble bed high temperature gas-cooled reactors i.e. the PBMR-200 MWthermal and the PBMR-400 MWthermal were simulated and compared using the VSOP 99/05 suite of codes. To investigate the effect of this event on reactivity, power profiles and thermal neutron flux profiles, the addition of partial steam vapour pressures in stages up to 400 bar into the primary circuit for the PBMR-400 and up to 300 bar for the PBMR- 200 was simulated for both reactors. During the simulation, three scenarios were simulated, i.e. water ingress into the core only, water ingress into the reflectors only and water ingress into both the core and reflectors. The induced reactivity change effects were compared for these reactors. An in-depth analysis was also carried out to study the mechanisms that drive the reactivity changes for each reactor caused by water ingress into the fuel core only, the riser tubes in the reflectors only and ingress into both the fuel core and the riser tubes in the reflectors. The knowledge gained of these mechanisms and effects was used in order to propose design changes aimed at mitigating the reactivity increases, caused by realistic water ingress scenarios. Past results from simulations of water ingress into Pebble Bed Reactors were used to validate and verify the present simulation approach and results. The reactivity increase results for both reactors were in agreement with the German HTR-Modul calculations. / Thesis (MSc (Engineering Sciences in Nuclear Engineering))--North-West University, Potchefstroom Campus, 2013

This diploma thesis deals with storing the spent nuclear fuel and reviewing its safety. The theoretical part analyzes the processes taking place while the fuel is being used, such as fission, isotopic changes, fission gas release, cracking, swelling and densification of fuel pellet. The thesis is also focused on handling the spent fuel and on the way it makes from the reactor, through the spent fuel pool, the transportation, various kinds of storing, till the reprocessing and final deep geological repository. Furthermore, this part of the thesis briefly discusses computing code MCNP, its main characteristics, input files and using. The practical part of the work is focused on creating the model of the spent fuel pool located next to the nuclear reactor WWER 440/V213. This type was chosen, because it is the most used type of nuclear reactor in Czech Republic and Slovakia. With the help of the code MCNP, the multiplication factor of the main configurations of the fuel in the pool was calculated, and then the required safety regulations to ensure sufficient subcriticality, so its safety, were checked. Next, several analysis were performed using this model. These analyses were concerning the temperature of coolant, fuel and the use of various nuclear data libraries. In the future this model can be used to realize new analyses with new kinds of fuels, materials and data libraries.