Severe Accident Simulation of the Laguna Verde Nuclear Power Plant
The loss-of-coolant accident (LOCA) simulation in the boiling water reactor (BWR) of Laguna Verde Nuclear Power Plant (LVNPP) at 105% of rated power is analyzed in this work. The LVNPP model was developed using RELAP/SCDAPSIM code. The lack of cooling water after the LOCA gets to the LVNPP to meltin...
Saved in:
| Main Authors: | , , |
|---|---|
| Format: | Article |
| Language: | English |
| Published: |
Wiley
2012-01-01
|
| Series: | Science and Technology of Nuclear Installations |
| Online Access: | http://dx.doi.org/10.1155/2012/209420 |
| Tags: |
Add Tag
No Tags, Be the first to tag this record!
|
| _version_ | 1832558729470410752 |
|---|---|
| author | Gilberto Espinosa-Paredes Raúl Camargo-Camargo Alejandro Nuñez-Carrera |
| author_facet | Gilberto Espinosa-Paredes Raúl Camargo-Camargo Alejandro Nuñez-Carrera |
| author_sort | Gilberto Espinosa-Paredes |
| collection | DOAJ |
| description | The loss-of-coolant accident (LOCA) simulation in the boiling water reactor (BWR) of Laguna Verde Nuclear Power Plant (LVNPP) at 105% of rated power is analyzed in this work. The LVNPP model was developed using RELAP/SCDAPSIM code. The lack of cooling water after the LOCA gets to the LVNPP to melting of the core that exceeds the design basis of the nuclear power plant (NPP) sufficiently to cause failure of structures, materials, and systems that are needed to ensure proper cooling of the reactor core by normal means. Faced with a severe accident, the first response is to maintain the reactor core cooling by any means available, but in order to carry out such an attempt is necessary to understand fully the progression of core damage, since such action has effects that may be decisive in accident progression. The simulation considers a LOCA in the recirculation loop of the reactor with and without cooling water injection. During the progression of core damage, we analyze the cooling water injection at different times and the results show that there are significant differences in the level of core damage and hydrogen production, among other variables analyzed such as maximum surface temperature, fission products released, and debris bed height. |
| format | Article |
| id | doaj-art-68d6f9b9a6814dba982d6e9cf2089f11 |
| institution | Kabale University |
| issn | 1687-6075 1687-6083 |
| language | English |
| publishDate | 2012-01-01 |
| publisher | Wiley |
| record_format | Article |
| series | Science and Technology of Nuclear Installations |
| spelling | doaj-art-68d6f9b9a6814dba982d6e9cf2089f112025-02-03T01:31:39ZengWileyScience and Technology of Nuclear Installations1687-60751687-60832012-01-01201210.1155/2012/209420209420Severe Accident Simulation of the Laguna Verde Nuclear Power PlantGilberto Espinosa-Paredes0Raúl Camargo-Camargo1Alejandro Nuñez-Carrera2Área de Ingeniería en Recursos Energéticos, Universidad Autónoma Metropolitana-Iztapalapa, Avenida San Rafael Atlixco 186 Col. Vicentina, 09340 Mèxico City, DF, MexicoNuclear Safety Division, Comisión Nacional de Seguridad Nuclear y Salvaguardias, Doctor Barragán 779, Col. Narvarte, 03020 Mèxico City, DF, MexicoÁrea de Ingeniería en Recursos Energéticos, Universidad Autónoma Metropolitana-Iztapalapa, Avenida San Rafael Atlixco 186 Col. Vicentina, 09340 Mèxico City, DF, MexicoThe loss-of-coolant accident (LOCA) simulation in the boiling water reactor (BWR) of Laguna Verde Nuclear Power Plant (LVNPP) at 105% of rated power is analyzed in this work. The LVNPP model was developed using RELAP/SCDAPSIM code. The lack of cooling water after the LOCA gets to the LVNPP to melting of the core that exceeds the design basis of the nuclear power plant (NPP) sufficiently to cause failure of structures, materials, and systems that are needed to ensure proper cooling of the reactor core by normal means. Faced with a severe accident, the first response is to maintain the reactor core cooling by any means available, but in order to carry out such an attempt is necessary to understand fully the progression of core damage, since such action has effects that may be decisive in accident progression. The simulation considers a LOCA in the recirculation loop of the reactor with and without cooling water injection. During the progression of core damage, we analyze the cooling water injection at different times and the results show that there are significant differences in the level of core damage and hydrogen production, among other variables analyzed such as maximum surface temperature, fission products released, and debris bed height.http://dx.doi.org/10.1155/2012/209420 |
| spellingShingle | Gilberto Espinosa-Paredes Raúl Camargo-Camargo Alejandro Nuñez-Carrera Severe Accident Simulation of the Laguna Verde Nuclear Power Plant Science and Technology of Nuclear Installations |
| title | Severe Accident Simulation of the Laguna Verde Nuclear Power Plant |
| title_full | Severe Accident Simulation of the Laguna Verde Nuclear Power Plant |
| title_fullStr | Severe Accident Simulation of the Laguna Verde Nuclear Power Plant |
| title_full_unstemmed | Severe Accident Simulation of the Laguna Verde Nuclear Power Plant |
| title_short | Severe Accident Simulation of the Laguna Verde Nuclear Power Plant |
| title_sort | severe accident simulation of the laguna verde nuclear power plant |
| url | http://dx.doi.org/10.1155/2012/209420 |
| work_keys_str_mv | AT gilbertoespinosaparedes severeaccidentsimulationofthelagunaverdenuclearpowerplant AT raulcamargocamargo severeaccidentsimulationofthelagunaverdenuclearpowerplant AT alejandronunezcarrera severeaccidentsimulationofthelagunaverdenuclearpowerplant |