RELAP5 Simulation of PKL Facility Experiments under Midloop Conditions
Nuclear power plant risk has to be quantified in full power and in other modes of operation. This latter situation corresponds to low power and shutdown modes of operation in which the residual heat removal (RHR) system is required to extract the heat generated in the core. These accidental sequence...
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| Main Authors: | , , , , |
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| Format: | Article |
| Language: | English |
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Wiley
2017-01-01
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| Series: | Science and Technology of Nuclear Installations |
| Online Access: | http://dx.doi.org/10.1155/2017/6140323 |
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| author | J. F. Villanueva S. Carlos F. Sanchez-Saez I. Martón S. Martorell |
| author_facet | J. F. Villanueva S. Carlos F. Sanchez-Saez I. Martón S. Martorell |
| author_sort | J. F. Villanueva |
| collection | DOAJ |
| description | Nuclear power plant risk has to be quantified in full power and in other modes of operation. This latter situation corresponds to low power and shutdown modes of operation in which the residual heat removal (RHR) system is required to extract the heat generated in the core. These accidental sequences are great contributors to the total plant risk. Thus, it is important to analyze the plant behavior to establish the accident mitigation measures required. In this way, PKL facility experimental series were undertaken to analyze the plant behavior in other modes of operation when the RHR is lost. In these experiments, the plant configurations were changed to analyze the influence of steam generators secondary side configurations, the temperature inside the pressurizer, and the inventory level on the plant behavior. Moreover, different accident management measures were proposed in each experiment to reach the conditions to restart the RHR. To understand the physical phenomena that takes place inside the reactor, the experiments are simulated with thermal-hydraulic codes, and this makes it possible to analyze the code capabilities to predict the plant behavior. This work presents the simulation results of four experiments included in PKL experimental series obtained using RELAP5/Mod3.3. |
| format | Article |
| id | doaj-art-32e8eb5fde5844f18b474b92565d4df4 |
| institution | Kabale University |
| issn | 1687-6075 1687-6083 |
| language | English |
| publishDate | 2017-01-01 |
| publisher | Wiley |
| record_format | Article |
| series | Science and Technology of Nuclear Installations |
| spelling | doaj-art-32e8eb5fde5844f18b474b92565d4df42025-02-03T06:01:21ZengWileyScience and Technology of Nuclear Installations1687-60751687-60832017-01-01201710.1155/2017/61403236140323RELAP5 Simulation of PKL Facility Experiments under Midloop ConditionsJ. F. Villanueva0S. Carlos1F. Sanchez-Saez2I. Martón3S. Martorell4Department of Chemical and Nuclear Engineering, Universitat Politècnica de València, Valencia, SpainDepartment of Chemical and Nuclear Engineering, Universitat Politècnica de València, Valencia, SpainDepartment of Chemical and Nuclear Engineering, Universitat Politècnica de València, Valencia, SpainDepartment of Chemical and Nuclear Engineering, Universitat Politècnica de València, Valencia, SpainDepartment of Chemical and Nuclear Engineering, Universitat Politècnica de València, Valencia, SpainNuclear power plant risk has to be quantified in full power and in other modes of operation. This latter situation corresponds to low power and shutdown modes of operation in which the residual heat removal (RHR) system is required to extract the heat generated in the core. These accidental sequences are great contributors to the total plant risk. Thus, it is important to analyze the plant behavior to establish the accident mitigation measures required. In this way, PKL facility experimental series were undertaken to analyze the plant behavior in other modes of operation when the RHR is lost. In these experiments, the plant configurations were changed to analyze the influence of steam generators secondary side configurations, the temperature inside the pressurizer, and the inventory level on the plant behavior. Moreover, different accident management measures were proposed in each experiment to reach the conditions to restart the RHR. To understand the physical phenomena that takes place inside the reactor, the experiments are simulated with thermal-hydraulic codes, and this makes it possible to analyze the code capabilities to predict the plant behavior. This work presents the simulation results of four experiments included in PKL experimental series obtained using RELAP5/Mod3.3.http://dx.doi.org/10.1155/2017/6140323 |
| spellingShingle | J. F. Villanueva S. Carlos F. Sanchez-Saez I. Martón S. Martorell RELAP5 Simulation of PKL Facility Experiments under Midloop Conditions Science and Technology of Nuclear Installations |
| title | RELAP5 Simulation of PKL Facility Experiments under Midloop Conditions |
| title_full | RELAP5 Simulation of PKL Facility Experiments under Midloop Conditions |
| title_fullStr | RELAP5 Simulation of PKL Facility Experiments under Midloop Conditions |
| title_full_unstemmed | RELAP5 Simulation of PKL Facility Experiments under Midloop Conditions |
| title_short | RELAP5 Simulation of PKL Facility Experiments under Midloop Conditions |
| title_sort | relap5 simulation of pkl facility experiments under midloop conditions |
| url | http://dx.doi.org/10.1155/2017/6140323 |
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