Simulation of the Lower Head Boiling Water Reactor Vessel in a Severe Accident
The objective of this paper is the simulation and analysis of the BoilingWater Reactor (BWR) lower head during a severe accident. The COUPLE computer code was used in this work to model the heatup of the reactor core material that slumps in the lower head of the reactor pressure vessel. The predicti...
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/10.1155/2012/305405 |
| Tags: |
Add Tag
No Tags, Be the first to tag this record!
|
| _version_ | 1832552089252790272 |
|---|---|
| author | Alejandro Nuñez-Carrera Raúl Camargo-Camargo Gilberto Espinosa-Paredes Adrián López-García |
| author_facet | Alejandro Nuñez-Carrera Raúl Camargo-Camargo Gilberto Espinosa-Paredes Adrián López-García |
| author_sort | Alejandro Nuñez-Carrera |
| collection | DOAJ |
| description | The objective of this paper is the simulation and analysis of the BoilingWater Reactor (BWR) lower head during a severe accident. The COUPLE computer code was used in this work to model the heatup of the reactor core material that slumps in the lower head of the reactor pressure vessel. The prediction of the lower head failure is an important issue in the severe accidents field, due to the accident progression and the radiological consequences that are completely different with or without the failure of the Reactor Pressure Vessel (RPV). The release of molten material to the primary containment and the possibility of steam explosion may produce the failure of the primary containment with high radiological consequences. Then, it is important to have a detailed model in order to predict the behavior of the reactor vessel lower head in a severe accident. In this paper, a hypothetical simulation of a Loss of Coolant Accident (LOCA) with simultaneous loss of off-site power and without injection of cooling water is presented with the proposal to evaluate the temperature distribution and heatup of the lower part of the RPV. The SCDAPSIM/RELAP5 3.2 code was used to build the BWR model and conduct the numerical simulation. |
| format | Article |
| id | doaj-art-88cacf599cc1420ca827d5651302b56c |
| 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-88cacf599cc1420ca827d5651302b56c2025-02-03T05:59:36ZengWileyScience and Technology of Nuclear Installations1687-60751687-60832012-01-01201210.1155/2012/305405305405Simulation of the Lower Head Boiling Water Reactor Vessel in a Severe AccidentAlejandro Nuñez-Carrera0Raúl Camargo-Camargo1Gilberto Espinosa-Paredes2Adrián López-García3Comisión Nacional de Seguridad Nuclear y Salvaguardias, Dirección General Adjunta de Seguridad Nuclear, Doctor Barragán 779, Col. Narvarte, 03020 México DF, MexicoComisión Nacional de Seguridad Nuclear y Salvaguardias, Dirección General Adjunta de Seguridad Nuclear, Doctor Barragán 779, Col. Narvarte, 03020 México DF, MexicoÁrea de Ingeniería en Recursos Energéticos, Universidad Autónoma Metropolitana-Iztapalapa, Avenida San Rafael Atlixco 186, Col. Vicentina, 09340 México DF, MexicoComisión Nacional de Seguridad Nuclear y Salvaguardias, Dirección General Adjunta de Seguridad Nuclear, Doctor Barragán 779, Col. Narvarte, 03020 México DF, MexicoThe objective of this paper is the simulation and analysis of the BoilingWater Reactor (BWR) lower head during a severe accident. The COUPLE computer code was used in this work to model the heatup of the reactor core material that slumps in the lower head of the reactor pressure vessel. The prediction of the lower head failure is an important issue in the severe accidents field, due to the accident progression and the radiological consequences that are completely different with or without the failure of the Reactor Pressure Vessel (RPV). The release of molten material to the primary containment and the possibility of steam explosion may produce the failure of the primary containment with high radiological consequences. Then, it is important to have a detailed model in order to predict the behavior of the reactor vessel lower head in a severe accident. In this paper, a hypothetical simulation of a Loss of Coolant Accident (LOCA) with simultaneous loss of off-site power and without injection of cooling water is presented with the proposal to evaluate the temperature distribution and heatup of the lower part of the RPV. The SCDAPSIM/RELAP5 3.2 code was used to build the BWR model and conduct the numerical simulation.http://dx.doi.org/10.1155/2012/305405 |
| spellingShingle | Alejandro Nuñez-Carrera Raúl Camargo-Camargo Gilberto Espinosa-Paredes Adrián López-García Simulation of the Lower Head Boiling Water Reactor Vessel in a Severe Accident Science and Technology of Nuclear Installations |
| title | Simulation of the Lower Head Boiling Water Reactor Vessel in a Severe Accident |
| title_full | Simulation of the Lower Head Boiling Water Reactor Vessel in a Severe Accident |
| title_fullStr | Simulation of the Lower Head Boiling Water Reactor Vessel in a Severe Accident |
| title_full_unstemmed | Simulation of the Lower Head Boiling Water Reactor Vessel in a Severe Accident |
| title_short | Simulation of the Lower Head Boiling Water Reactor Vessel in a Severe Accident |
| title_sort | simulation of the lower head boiling water reactor vessel in a severe accident |
| url | http://dx.doi.org/10.1155/2012/305405 |
| work_keys_str_mv | AT alejandronunezcarrera simulationofthelowerheadboilingwaterreactorvesselinasevereaccident AT raulcamargocamargo simulationofthelowerheadboilingwaterreactorvesselinasevereaccident AT gilbertoespinosaparedes simulationofthelowerheadboilingwaterreactorvesselinasevereaccident AT adrianlopezgarcia simulationofthelowerheadboilingwaterreactorvesselinasevereaccident |