Temperature Response of the HTR-10 during the Power Ascension Test
The 10 MW High Temperature Gas-Cooled Reactor-Test Module (HTR-10) is the first High Temperature Gas-Cooled Reactor in China. With the objective of raising the reactor power from 30% to 100% rated power, the power ascension test was planned and performed in January 2003. The test results verified th...
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| Format: | Article |
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Wiley
2015-01-01
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| Series: | Science and Technology of Nuclear Installations |
| Online Access: | http://dx.doi.org/10.1155/2015/302648 |
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| author | Fubing Chen Yujie Dong Zuoyi Zhang |
| author_facet | Fubing Chen Yujie Dong Zuoyi Zhang |
| author_sort | Fubing Chen |
| collection | DOAJ |
| description | The 10 MW High Temperature Gas-Cooled Reactor-Test Module (HTR-10) is the first High Temperature Gas-Cooled Reactor in China. With the objective of raising the reactor power from 30% to 100% rated power, the power ascension test was planned and performed in January 2003. The test results verified the practicability and validity of the HTR-10 power regulation methods.
In this study, the power ascension process is preliminarily simulated using the THERMIX code. The code satisfactorily reproduces the reactor transient parameters, including the reactor power, the primary helium pressure, and the primary helium outlet temperature. Reactor internals temperatures are also calculated and compared with the test values recorded by a number of thermocouples. THERMIX correctly simulates the temperature variation tendency for different measuring points, with good to fair agreement between the calculated temperatures and the measured ones. Based on the comparison results, the THERMIX simulation capability for the HTR-10 dynamic characteristics during the power ascension process can be demonstrated. With respect to the reactor safety features, it is of utmost importance that the maximum fuel center temperature during the test process is always much lower than the fuel temperature limit of 1620°C. |
| format | Article |
| id | doaj-art-92e5bd30333b4febbf0e47bce66ab3b6 |
| institution | Kabale University |
| issn | 1687-6075 1687-6083 |
| language | English |
| publishDate | 2015-01-01 |
| publisher | Wiley |
| record_format | Article |
| series | Science and Technology of Nuclear Installations |
| spelling | doaj-art-92e5bd30333b4febbf0e47bce66ab3b62025-02-03T05:46:34ZengWileyScience and Technology of Nuclear Installations1687-60751687-60832015-01-01201510.1155/2015/302648302648Temperature Response of the HTR-10 during the Power Ascension TestFubing Chen0Yujie Dong1Zuoyi Zhang2Institute of Nuclear and New Energy Technology, Tsinghua University, Collaborative Innovation Center of Advanced Nuclear Energy Technology, Key Laboratory of Advanced Reactor Engineering and Safety, Ministry of Education, Beijing 100084, ChinaInstitute of Nuclear and New Energy Technology, Tsinghua University, Collaborative Innovation Center of Advanced Nuclear Energy Technology, Key Laboratory of Advanced Reactor Engineering and Safety, Ministry of Education, Beijing 100084, ChinaInstitute of Nuclear and New Energy Technology, Tsinghua University, Collaborative Innovation Center of Advanced Nuclear Energy Technology, Key Laboratory of Advanced Reactor Engineering and Safety, Ministry of Education, Beijing 100084, ChinaThe 10 MW High Temperature Gas-Cooled Reactor-Test Module (HTR-10) is the first High Temperature Gas-Cooled Reactor in China. With the objective of raising the reactor power from 30% to 100% rated power, the power ascension test was planned and performed in January 2003. The test results verified the practicability and validity of the HTR-10 power regulation methods. In this study, the power ascension process is preliminarily simulated using the THERMIX code. The code satisfactorily reproduces the reactor transient parameters, including the reactor power, the primary helium pressure, and the primary helium outlet temperature. Reactor internals temperatures are also calculated and compared with the test values recorded by a number of thermocouples. THERMIX correctly simulates the temperature variation tendency for different measuring points, with good to fair agreement between the calculated temperatures and the measured ones. Based on the comparison results, the THERMIX simulation capability for the HTR-10 dynamic characteristics during the power ascension process can be demonstrated. With respect to the reactor safety features, it is of utmost importance that the maximum fuel center temperature during the test process is always much lower than the fuel temperature limit of 1620°C.http://dx.doi.org/10.1155/2015/302648 |
| spellingShingle | Fubing Chen Yujie Dong Zuoyi Zhang Temperature Response of the HTR-10 during the Power Ascension Test Science and Technology of Nuclear Installations |
| title | Temperature Response of the HTR-10 during the Power Ascension Test |
| title_full | Temperature Response of the HTR-10 during the Power Ascension Test |
| title_fullStr | Temperature Response of the HTR-10 during the Power Ascension Test |
| title_full_unstemmed | Temperature Response of the HTR-10 during the Power Ascension Test |
| title_short | Temperature Response of the HTR-10 during the Power Ascension Test |
| title_sort | temperature response of the htr 10 during the power ascension test |
| url | http://dx.doi.org/10.1155/2015/302648 |
| work_keys_str_mv | AT fubingchen temperatureresponseofthehtr10duringthepowerascensiontest AT yujiedong temperatureresponseofthehtr10duringthepowerascensiontest AT zuoyizhang temperatureresponseofthehtr10duringthepowerascensiontest |