Study on Neutronic/Thermal-Mechanical Coupling Calculation Method for Fast-neutron Pulse Reactor with Metallic Nuclear Fuel

Guo Shuwei; Chen ZhenPing; Jiang Xinbiao; Li Da; Zhang Xinyi; Wang Lipeng; Hu Tianliang; Xie Jinsen; Yu Tao

doi:10.13832/j.jnpe.2022.04.0031

Volume 43 Issue 4

Aug. 2022

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Guo Shuwei, Chen ZhenPing, Jiang Xinbiao, Li Da, Zhang Xinyi, Wang Lipeng, Hu Tianliang, Xie Jinsen, Yu Tao. Study on Neutronic/Thermal-Mechanical Coupling Calculation Method for Fast-neutron Pulse Reactor with Metallic Nuclear Fuel[J]. Nuclear Power Engineering, 2022, 43(4): 31-37. doi: 10.13832/j.jnpe.2022.04.0031

Citation:

Guo Shuwei, Chen ZhenPing, Jiang Xinbiao, Li Da, Zhang Xinyi, Wang Lipeng, Hu Tianliang, Xie Jinsen, Yu Tao. Study on Neutronic/Thermal-Mechanical Coupling Calculation Method for Fast-neutron Pulse Reactor with Metallic Nuclear Fuel[J]. Nuclear Power Engineering, 2022, 43(4): 31-37. doi: 10.13832/j.jnpe.2022.04.0031

Citation:

Guo Shuwei, Chen ZhenPing, Jiang Xinbiao, Li Da, Zhang Xinyi, Wang Lipeng, Hu Tianliang, Xie Jinsen, Yu Tao. Study on Neutronic/Thermal-Mechanical Coupling Calculation Method for Fast-neutron Pulse Reactor with Metallic Nuclear Fuel[J]. Nuclear Power Engineering, 2022, 43(4): 31-37. doi: 10.13832/j.jnpe.2022.04.0031

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Study on Neutronic/Thermal-Mechanical Coupling Calculation Method for Fast-neutron Pulse Reactor with Metallic Nuclear Fuel

doi: 10.13832/j.jnpe.2022.04.0031

1.
School of Nuclear Science and Technology, University of South China, Hengyang, Hunan, 421001, China
2.
Northwest Institute of Nuclear Technology State Key Laboratory of Intense Pulsed Radiation Simulation and Effect, Xi’an, 710024, China

Received Date: 2021-08-19
Accepted Date: 2021-11-17
Rev Recd Date: 2021-11-17

Available Online: 2022-08-12

Publish Date: 2022-08-04

Abstract

Abstract

In order to ensure the operational safety of the fast-neutron pulse reactor and prevent the supercritical pulse from causing physical damage to the material, it is necessary to simulate and analyze the pulse operating conditions of the fast-neutron pulse reactor. In this study, for the fast-neutron pulse reactor with metallic nuclear fuel, the neutronic/thermal-mechanical coupling calculation and analysis of Godiva-I pulse reactor are carried out based on the point reactor dynamics method, Monte Carlo method and finite element mechanics method. The calculation results show that the reactivity temperature coefficient and fission rate are in good agreement with the experimental values, and the reactivity, temperature rise, surface displacement and surface stress are consistent with the actual situation. Therefore, the "neutronic/thermal-mechanical" coupling calculation method established in this paper can be applied to the analysis and calculation of the fast-neutron pulse reactor with metallic nuclear fuel, and has certain reliability.
- Pulse reactor,
- Neutronic/thermal-mechanical coupling,
- ANSYS,
- Transient analysis

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References(17)

References

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