| Autor: |
Khakim, Azizul, Margiyanto, Dwi, Utari, Utari |
| Předmět: |
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| Zdroj: |
AIP Conference Proceedings; 2023, Vol. 2893 Issue 1, p1-9, 9p |
| Abstrakt: |
The use of extensive graphite material as moderator, reflector, and regulating rod in thermal MSR often limits the operational life of the reactor due to graphite material integrity. The graphite material is challenged by fast neutron exposure during its service. Therefore, neutron fluence analysis on graphite material of TMSR-500 (ThorCon) was simulated with MCNP6 code. Neutron fluence calculations on the TMSR-500 were carried out with a nominal power of 557 MWt. The reactor operates at a temperature of around 977 K. The analysis is intended to identify the spot and estimate the maximum exposure to high-energy neutron fluence (>0.1 MeV) on the graphite material of TMSR-500 during four years of operation. The maximum fast neutron fluence (E> 0.1 MeV) in the graphite moderator of TMSR-500 is found to be 1.506×1022 n.cm−2 during four years of operation. Damage to graphite material could occur due to radiation exposure caused by high energy neutrons (E> 0.1 MeV) when it exceeds the recommended limit of neutron fluence 4.0×1022 n.cm−2. Thus, the fast neutron fluence exposure to the graphite moderator of TMSR-500 during 4 years of operation is well below the maximum acceptable limit. [ABSTRACT FROM AUTHOR] |
| Databáze: |
Complementary Index |
| Externí odkaz: |
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