Modeling Loss-of-Flow Accidents and Their Impact on Radiation Heat Transfer
Long-term high payload missions necessitate the need for nuclear space propulsion. The National Aeronautics and Space Administration (NASA) investigated several reactor designs from 1959 to 1973 in order to develop the Nuclear Engine for Rocket Vehicle Application (NERVA). Study of planned/unplanned...
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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/10.1155/2017/1345938 |
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| author | Jivan Khatry Fatih Aydogan |
| author_facet | Jivan Khatry Fatih Aydogan |
| author_sort | Jivan Khatry |
| collection | DOAJ |
| description | Long-term high payload missions necessitate the need for nuclear space propulsion. The National Aeronautics and Space Administration (NASA) investigated several reactor designs from 1959 to 1973 in order to develop the Nuclear Engine for Rocket Vehicle Application (NERVA). Study of planned/unplanned transients on nuclear thermal rockets is important due to the need for long-term missions. In this work, a system model based on RELAP5 is developed to simulate loss-of-flow accidents on the Pewee I test reactor. This paper investigates the radiation heat transfer between the fuel elements and the structures around it. In addition, the impact on the core fuel element temperature and average core pressure was also investigated. The following expected results were achieved: (i) greater than normal fuel element temperatures, (ii) fuel element temperatures exceeding the uranium carbide melting point, and (iii) average core pressure less than normal. Results show that the radiation heat transfer rate between fuel elements and cold surfaces increases with decreasing flow rate through the reactor system. However, radiation heat transfer decreases when there is a complete LOFA. When there is a complete LOFA, the peripheral coolant channels of the fuel elements handle most of the radiation heat transfer. A safety system needs to be designed to counteract the decay heat resulting from a post-LOFA reactor scram. |
| format | Article |
| id | doaj-art-ea3b0807120c4bb0ae6bf2caeea52b18 |
| 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-ea3b0807120c4bb0ae6bf2caeea52b182025-02-03T05:44:39ZengWileyScience and Technology of Nuclear Installations1687-60751687-60832017-01-01201710.1155/2017/13459381345938Modeling Loss-of-Flow Accidents and Their Impact on Radiation Heat TransferJivan Khatry0Fatih Aydogan1Center for Advanced Energy Studies (CAES), University of Idaho, 995 University Blvd., Idaho Falls, ID 83401, USACenter for Advanced Energy Studies (CAES), University of Idaho, 995 University Blvd., Idaho Falls, ID 83401, USALong-term high payload missions necessitate the need for nuclear space propulsion. The National Aeronautics and Space Administration (NASA) investigated several reactor designs from 1959 to 1973 in order to develop the Nuclear Engine for Rocket Vehicle Application (NERVA). Study of planned/unplanned transients on nuclear thermal rockets is important due to the need for long-term missions. In this work, a system model based on RELAP5 is developed to simulate loss-of-flow accidents on the Pewee I test reactor. This paper investigates the radiation heat transfer between the fuel elements and the structures around it. In addition, the impact on the core fuel element temperature and average core pressure was also investigated. The following expected results were achieved: (i) greater than normal fuel element temperatures, (ii) fuel element temperatures exceeding the uranium carbide melting point, and (iii) average core pressure less than normal. Results show that the radiation heat transfer rate between fuel elements and cold surfaces increases with decreasing flow rate through the reactor system. However, radiation heat transfer decreases when there is a complete LOFA. When there is a complete LOFA, the peripheral coolant channels of the fuel elements handle most of the radiation heat transfer. A safety system needs to be designed to counteract the decay heat resulting from a post-LOFA reactor scram.http://dx.doi.org/10.1155/2017/1345938 |
| spellingShingle | Jivan Khatry Fatih Aydogan Modeling Loss-of-Flow Accidents and Their Impact on Radiation Heat Transfer Science and Technology of Nuclear Installations |
| title | Modeling Loss-of-Flow Accidents and Their Impact on Radiation Heat Transfer |
| title_full | Modeling Loss-of-Flow Accidents and Their Impact on Radiation Heat Transfer |
| title_fullStr | Modeling Loss-of-Flow Accidents and Their Impact on Radiation Heat Transfer |
| title_full_unstemmed | Modeling Loss-of-Flow Accidents and Their Impact on Radiation Heat Transfer |
| title_short | Modeling Loss-of-Flow Accidents and Their Impact on Radiation Heat Transfer |
| title_sort | modeling loss of flow accidents and their impact on radiation heat transfer |
| url | http://dx.doi.org/10.1155/2017/1345938 |
| work_keys_str_mv | AT jivankhatry modelinglossofflowaccidentsandtheirimpactonradiationheattransfer AT fatihaydogan modelinglossofflowaccidentsandtheirimpactonradiationheattransfer |