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基于OpenMC的离岸固定式铅堆的物理设计分析

Physical Design Analysis of Offshore Stationary Lead Reactor Based on OpenMC

  • 摘要: 海上核能平台具有运行成本低、能源供给可靠和环境友好等特点,可以为海洋油气资源开发、工作人员生活保障等提供稳定可靠的能源。离岸固定式铅堆平台针对我国海洋稳定供能的需求,旨在提出一种电功率达到20 MW,寿期40年且全寿期不换料的反应堆概念设计方案。使用CAR-3600基准题,对开源蒙特卡罗程序OpenMC的燃耗模块在铅基快堆中的适用性进行了验证。对比了OpenMC程序和MCNP程序关于离岸固定式铅堆堆芯的计算结果,分析了使用不同核数据库的OpenMC程序计算结果差异,并探讨了可能原因。研究结果表明:OpenMC程序的燃耗模块在快堆中是适用的的。OpenMC和MCNP程序计算结果接近,通过不同计算软件对离岸固定式铅堆的设计方案进行了对比验证。模拟同时发现, 由于235U和238U俘获截面的差异,ENDF/B-VIII.0库和JEFF-3.3库得到的全寿期反应性波动偏大,全寿期反应性差异超过了 1 \; \的设计目标,后续还需对方案进行进一步的优化,缩小燃耗反应性波动。

     

    Abstract: The offshore nuclear energy platform, characterized by low operating costs, reliable energy supply, and environmental friendliness, can provide stable and reliable energy for the development of offshore oil and gas resources and the livelihood support of personnel. The offshore fixed lead-cooled reactor platform, addressing the demand for stable energy supply in China's maritime regions, aims to propose a conceptual design for a reactor with an electrical power output of 20 MW, a service life of 40 years, and no need for replacement of materials throughout its entire lifespan. This paper uses the CAR-3600 benchmark and validates the applicability of the burnup module of the open-source Monte Carlo program OpenMC in a lead-cooled fast reactor. A comparison of the calculation results for the offshore fixed lead-cooled reactor core between the OpenMC and MCNP programs is conducted, analyzing the differences in results obtained using different nuclear databases in the OpenMC program and exploring possible reasons for these differences. The research results indicate that the burnup module of the OpenMC program is applicable in fast reactors. The calculation results of OpenMC and MCNP programs are close, and a comparative validation of the design scheme for the offshore fixed lead-cooled reactor is carried out using different simulation software. The simulation also reveals that due to differences in capture cross-sections of 235U and 238U, the reactivity fluctuations obtained from the ENDF/B-VIII.0 library and the JEFF-3.3 library are larger than the design target of 1\; \, requiring further optimization of the scheme to reduce burnup reactivity fluctuations.

     

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