Deriving formula to simulate the radiological behavior during LOCA in open pool type reactor
This study aims to model the radiological consequences that result from loss of coolant accident in open pool research reactor of 22 MW power. The loss of coolant accident results from rupture in the cooling systems of the reactor and consequently results in decreasing the water level in the reactor...
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| Language: | English |
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Brazilian Radiation Protection Society (Sociedade Brasileira de Proteção Radiológica, SBPR)
2022-02-01
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| Series: | Brazilian Journal of Radiation Sciences |
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| Online Access: | https://bjrs.org.br/revista/index.php/REVISTA/article/view/1723 |
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| author | Amr Abdelhady |
| author_facet | Amr Abdelhady |
| author_sort | Amr Abdelhady |
| collection | DOAJ |
| description | This study aims to model the radiological consequences that result from loss of coolant accident in open pool research reactor of 22 MW power. The loss of coolant accident results from rupture in the cooling systems of the reactor and consequently results in decreasing the water level in the reactor pool. Decreasing the water level, that represents the shielding material above the reactor core, results in increasing the dose rate in the top region in the reactor pool as well as the reactor building. LOCA normally results in shutting down the reactor due to the radioprotection system provided in the upper region of the reactor pool. A failure in shutdown systems of the reactor during LOCA is rare but expected and it represents the worst case. So, evaluating LOCA from the radiological point of view must be investigated for the safe shutdown mode as well as the failure of shutdown case. The study also includes occurring LOCA for shutdown reactor taking the decay time into consideration.
ORIGEN-S module from scale system was used to estimate the delayed neutrons and gamma rays from the core for the shutdown mode. KENO-VI module from Scale system was used to estimate the prompt neutrons and gamma rays generated from the core for the failure case. Then, MAVRIC/Scale module was used to estimate the dose rate at the top point of the reactor pool for the two cases during LOCA.
Studying the dose rate during LOCA aims to determine the water level that verifies the radiological safety limit at the top point of the reactor pool for the two cases. The calculations introduced a relationship between the water level that verifies the permissible radiological limit (WL) and the decay time (DT) in the range between 0 to 30 d. |
| format | Article |
| id | doaj-art-7653d5dfd20e46e4ab5324053d6154b0 |
| institution | DOAJ |
| issn | 2319-0612 |
| language | English |
| publishDate | 2022-02-01 |
| publisher | Brazilian Radiation Protection Society (Sociedade Brasileira de Proteção Radiológica, SBPR) |
| record_format | Article |
| series | Brazilian Journal of Radiation Sciences |
| spelling | doaj-art-7653d5dfd20e46e4ab5324053d6154b02025-08-20T03:13:11ZengBrazilian Radiation Protection Society (Sociedade Brasileira de Proteção Radiológica, SBPR)Brazilian Journal of Radiation Sciences2319-06122022-02-0110110.15392/bjrs.v10i1.17231344Deriving formula to simulate the radiological behavior during LOCA in open pool type reactorAmr Abdelhady0Reactors dept., Nuclear research center, Egyptian atomic energy authorityThis study aims to model the radiological consequences that result from loss of coolant accident in open pool research reactor of 22 MW power. The loss of coolant accident results from rupture in the cooling systems of the reactor and consequently results in decreasing the water level in the reactor pool. Decreasing the water level, that represents the shielding material above the reactor core, results in increasing the dose rate in the top region in the reactor pool as well as the reactor building. LOCA normally results in shutting down the reactor due to the radioprotection system provided in the upper region of the reactor pool. A failure in shutdown systems of the reactor during LOCA is rare but expected and it represents the worst case. So, evaluating LOCA from the radiological point of view must be investigated for the safe shutdown mode as well as the failure of shutdown case. The study also includes occurring LOCA for shutdown reactor taking the decay time into consideration. ORIGEN-S module from scale system was used to estimate the delayed neutrons and gamma rays from the core for the shutdown mode. KENO-VI module from Scale system was used to estimate the prompt neutrons and gamma rays generated from the core for the failure case. Then, MAVRIC/Scale module was used to estimate the dose rate at the top point of the reactor pool for the two cases during LOCA. Studying the dose rate during LOCA aims to determine the water level that verifies the radiological safety limit at the top point of the reactor pool for the two cases. The calculations introduced a relationship between the water level that verifies the permissible radiological limit (WL) and the decay time (DT) in the range between 0 to 30 d.https://bjrs.org.br/revista/index.php/REVISTA/article/view/1723locaopen pool reactorkeno-vi codeorigen-s codemavric coderadiation dose rate. |
| spellingShingle | Amr Abdelhady Deriving formula to simulate the radiological behavior during LOCA in open pool type reactor Brazilian Journal of Radiation Sciences loca open pool reactor keno-vi code origen-s code mavric code radiation dose rate. |
| title | Deriving formula to simulate the radiological behavior during LOCA in open pool type reactor |
| title_full | Deriving formula to simulate the radiological behavior during LOCA in open pool type reactor |
| title_fullStr | Deriving formula to simulate the radiological behavior during LOCA in open pool type reactor |
| title_full_unstemmed | Deriving formula to simulate the radiological behavior during LOCA in open pool type reactor |
| title_short | Deriving formula to simulate the radiological behavior during LOCA in open pool type reactor |
| title_sort | deriving formula to simulate the radiological behavior during loca in open pool type reactor |
| topic | loca open pool reactor keno-vi code origen-s code mavric code radiation dose rate. |
| url | https://bjrs.org.br/revista/index.php/REVISTA/article/view/1723 |
| work_keys_str_mv | AT amrabdelhady derivingformulatosimulatetheradiologicalbehaviorduringlocainopenpooltypereactor |