Research on Direct Transport Calculation Method Based on Numerical Nuclear Reactor Physics Code SHARK

Zhao Chen; Zhao Wenbo; Zhang Hongbo; Wang Bo; Chen Zhang; Peng Xingjie; Gong Zhaohu; Zeng Wei; Li Qing

doi:10.13832/j.jnpe.2023.04.0033

Volume 44 Issue 4

Aug. 2023

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Article Navigation > Nuclear Power Engineering > 2023 > 44(4): 33-40

Zhao Chen, Zhao Wenbo, Zhang Hongbo, Wang Bo, Chen Zhang, Peng Xingjie, Gong Zhaohu, Zeng Wei, Li Qing. Research on Direct Transport Calculation Method Based on Numerical Nuclear Reactor Physics Code SHARK[J]. Nuclear Power Engineering, 2023, 44(4): 33-40. doi: 10.13832/j.jnpe.2023.04.0033

Citation:

Zhao Chen, Zhao Wenbo, Zhang Hongbo, Wang Bo, Chen Zhang, Peng Xingjie, Gong Zhaohu, Zeng Wei, Li Qing. Research on Direct Transport Calculation Method Based on Numerical Nuclear Reactor Physics Code SHARK[J]. Nuclear Power Engineering, 2023, 44(4): 33-40. doi: 10.13832/j.jnpe.2023.04.0033

Citation:

Zhao Chen, Zhao Wenbo, Zhang Hongbo, Wang Bo, Chen Zhang, Peng Xingjie, Gong Zhaohu, Zeng Wei, Li Qing. Research on Direct Transport Calculation Method Based on Numerical Nuclear Reactor Physics Code SHARK[J]. Nuclear Power Engineering, 2023, 44(4): 33-40. doi: 10.13832/j.jnpe.2023.04.0033

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Research on Direct Transport Calculation Method Based on Numerical Nuclear Reactor Physics Code SHARK

doi: 10.13832/j.jnpe.2023.04.0033

Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu, 610213, China

Received Date: 2022-10-08
Rev Recd Date: 2022-12-05
Publish Date: 2023-08-15

Abstract

Abstract

In order to establish the next-generation reactor physics calculation method based on the numerical nuclear reactor technology and realize high-fidelity modeling, high-resolution and high-precision calculation, the research of direct transport method was conducted based on the numerical nuclear reactor physics code SHARK, and 2D/1D and quasi-3D MOC methods were built and compared. Based on the large-scale parallel acceleration technology of domain decomposition and coarse mesh finite difference (CMFD), the whole reactor direct transport calculation was realized for the pin-type and plate-type cores. Compared with Monte-Carlo reference results, eigenvalue differences were less than 100pcm (1pcm=10^–5) and maximum pin/plate powers were less than 3%. Numerical results showed the good accuracy of SHARK in the direct transport calculation, and can be apllied in multi-application scenarios of pin-type and plate-type cores.
- Numerical nuclear reactor,
- 2D/1D method,
- Quasi-3D MOC method,
- SHARK

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References(18)

References

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