Neutronic calculation of safety parameters for the RP-0 and RP-10 nuclear reactors
Theoretical safety calculations were done with proved codes utilized by the staff of the RERTR program in the HEU to LEU core conversions. The studies were designed to evaluate the reactivity coefficients and kinetics parameters of the reactor involved in the evolution of peak power transients by re...
| Authors: | ; ; |
|---|---|
| Format: | Article |
| Publication date: | 2002 |
| Country: | Perú |
| Institution: | IPEN |
| Repository: | IPEN-Institucional |
| Language: | English |
| OAI Identifier: | oai:repositorio.ipen.gob.pe:20.500.13054/168 |
| Online Access: | https://hdl.handle.net/20.500.13054/168 |
| Access Level: | Open access |
| Keyword: | Reactor RP-10 Reactor RP-0 Análisis de seguridad Cálculos por ordenadores Método de Monte Carlo |
| _version_ | 1878411393210777600 |
|---|---|
| author | Deen, James R. |
| author2 | Lázaro, Gerardo Woodruff, William L. |
| author2_role | author author |
| author_browse | Deen, James R. Lázaro, Gerardo Woodruff, William L. |
| author_facet | Deen, James R. Lázaro, Gerardo Woodruff, William L. |
| author_role | author |
| bitstream_url_str_mv | https://repositorio.ipen.gob.pe/bitstream/20.500.13054/168/1/Pag.%206-10%20-%20ICT%201998-2001.pdf https://repositorio.ipen.gob.pe/bitstream/20.500.13054/168/2/license.txt https://repositorio.ipen.gob.pe/bitstream/20.500.13054/168/3/Pag.%206-10%20-%20ICT%201998-2001.pdf.txt https://repositorio.ipen.gob.pe/bitstream/20.500.13054/168/4/Pag.%206-10%20-%20ICT%201998-2001.pdf.jpg |
| collection | IPEN-Institucional |
| description | Theoretical safety calculations were done with proved codes utilized by the staff of the RERTR program in the HEU to LEU core conversions. The studies were designed to evaluate the reactivity coefficients and kinetics parameters of the reactor involved in the evolution of peak power transients by reactivity insertion accidents. It was done to show the trend of these reactivity coefficients as a function of the core size and fuel depletion for RP10 cores. It was useful to get a better understanding of the progression of the reactivity insertion transients monitoring the critical thermal hydraulic parameters to avoid core damage. To confirm the accuracy of these studies the results were compared with experimental data of the SPERT I reactors. The microscopic cross section calculations were condensed to 15 broad groups using the WIMSD4M[1] code for all the isotopes from eight different regions that model seven different assemblies. The Supercell, multiplate and homogenized options were used to represent the different assemblies in the reactor. For diffusion theory calculations the DIF3D[2] code was used in planar geometry with input axial buckling to simulate axial leakage. To Benchmark the designed models used in the cross sections generation and the DIF3D designed model, the VIM[3] Monte Carlo code was used. The RECOEFF[4] code was used to calculate the reactivity coefficients. |
| eu_rights_str_mv | openAccess |
| format | article |
| id | PE_603e134fe2d3f171a66f139df5bdb708 |
| institution | IPEN |
| instname_str | Instituto Peruano de Energía Nuclear |
| language | eng |
| network_acronym_str | PE |
| network_name_str | Perú |
| oai_identifier_str | oai:repositorio.ipen.gob.pe:20.500.13054/168 |
| publishDate | 2002 |
| publishDateSort | 2002 |
| publisher | Lima PE |
| publisherStr | Lima PE |
| reponame_str | IPEN-Institucional |
| spelling | Neutronic calculation of safety parameters for the RP-0 and RP-10 nuclear reactors Cálculo neutrónico de parámetros de seguridad de los reactores RP-10 y RP-0 Deen, James R. Lázaro, Gerardo Woodruff, William L. Reactor RP-10 Reactor RP-0 Análisis de seguridad Cálculos por ordenadores Método de Monte Carlo Theoretical safety calculations were done with proved codes utilized by the staff of the RERTR program in the HEU to LEU core conversions. The studies were designed to evaluate the reactivity coefficients and kinetics parameters of the reactor involved in the evolution of peak power transients by reactivity insertion accidents. It was done to show the trend of these reactivity coefficients as a function of the core size and fuel depletion for RP10 cores. It was useful to get a better understanding of the progression of the reactivity insertion transients monitoring the critical thermal hydraulic parameters to avoid core damage. To confirm the accuracy of these studies the results were compared with experimental data of the SPERT I reactors. The microscopic cross section calculations were condensed to 15 broad groups using the WIMSD4M[1] code for all the isotopes from eight different regions that model seven different assemblies. The Supercell, multiplate and homogenized options were used to represent the different assemblies in the reactor. For diffusion theory calculations the DIF3D[2] code was used in planar geometry with input axial buckling to simulate axial leakage. To Benchmark the designed models used in the cross sections generation and the DIF3D designed model, the VIM[3] Monte Carlo code was used. The RECOEFF[4] code was used to calculate the reactivity coefficients. Instituto Peruano de Energía Nuclear Lima PE Lázaro G, Deen JR, Woodruff WL. Neutronic calculation of safety parameters for the RP-0 and RP-10 nuclear reactors. Instituto Peruano de Energía Nuclear. Informe Científico Tecnológico. 1998-2001;:6-10. 1684-1662 https://hdl.handle.net/20.500.13054/168 |
| spellingShingle | Neutronic calculation of safety parameters for the RP-0 and RP-10 nuclear reactors Deen, James R. Reactor RP-10 Reactor RP-0 Análisis de seguridad Cálculos por ordenadores Método de Monte Carlo |
| title | Neutronic calculation of safety parameters for the RP-0 and RP-10 nuclear reactors |
| title_full | Neutronic calculation of safety parameters for the RP-0 and RP-10 nuclear reactors |
| title_fullStr | Neutronic calculation of safety parameters for the RP-0 and RP-10 nuclear reactors |
| title_full_unstemmed | Neutronic calculation of safety parameters for the RP-0 and RP-10 nuclear reactors |
| title_short | Neutronic calculation of safety parameters for the RP-0 and RP-10 nuclear reactors |
| title_sort | Neutronic calculation of safety parameters for the RP-0 and RP-10 nuclear reactors |
| topic | Reactor RP-10 Reactor RP-0 Análisis de seguridad Cálculos por ordenadores Método de Monte Carlo |
| topic_facet | Reactor RP-10 Reactor RP-0 Análisis de seguridad Cálculos por ordenadores Método de Monte Carlo |
| url | https://hdl.handle.net/20.500.13054/168 |