Neutron/Gamma Radial Shielding Design of Main Vessel in a Small Modular Molten Salt Reactor

IF 0.5 Q4 NUCLEAR SCIENCE & TECHNOLOGY Journal of Nuclear Engineering and Radiation Science Pub Date : 2023-02-22 DOI:10.3390/jne4010017
Haiyan Yu, Guifeng Zhu, Y. Zou, Rui Yan, Yafen Liu, Xuzhong Kang, Ye Dai
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Abstract

The SM-MSR (small modular molten salt reactor) has a good prospect for development with regards to combining the superiority of the molten salt reactor and modularization technologies, showing the advantages of safety, reliability, low economic cost and flexibility of site selection. However, because its internal structural parts are not easily replaced, and the outer shielding structure is limited, the lifespan of the reactor vessel and its in-reactor shielding design needs to be addressed. In order to find an optimal shielding model with both high fuel efficiency and strong radiation shielding capability, five different design schemes were proposed in this work, which varied in thickness and boron concentration in inner-shielding materials. The neutron/gamma flux and DPA (displacements per atom)/helium production rates were evaluated to obtain an appropriate scheme. Several beneficial results were obtained. Considering the above factors and the actual manufacturing process, 20 cm-thick boron graphite with a 5 wt% Boron-10 concentration combined with a 1 cm-thick Hastelloy barrel was chosen as the in-reactor shielding structure. Outside the reactor, the neutron flux was reduced to 8.33 × 1010 cm−2 s−1, and the gamma flux was decreased to 1.13 × 1011 cm−2 s−1. The vessel/barrel material could maintain a lifespan of more than 10 years, while the burnup depth was 6.25% lower than that of a model without inner-shielding. The conclusions of this research can provide important references for the shielding design and parameter selections of small molten salt reactors in the future.
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小型模块化熔盐堆主容器中子/射线屏蔽设计
SM-MSR(小型模块化熔盐堆)将熔盐堆的优势与模块化技术相结合,具有良好的发展前景,具有安全可靠、经济成本低、选址灵活等优点。然而,由于其内部结构部件不易更换,且外部屏蔽结构有限,因此需要解决反应堆容器的使用寿命和堆内屏蔽设计问题。为了寻找一种既具有高燃油效率又具有强辐射屏蔽能力的最佳屏蔽模型,本文根据屏蔽材料的厚度和硼浓度的不同,提出了5种不同的设计方案。对中子/伽马通量和DPA(每原子位移)/氦产率进行了评估,以获得合适的方案。获得了一些有益的结果。考虑到上述因素和实际制造工艺,选择了硼-10浓度为5 wt%的20 cm厚硼石墨和1 cm厚哈氏合金筒体作为堆内屏蔽结构。在反应堆外,中子通量降低到8.33 × 1010 cm−2 s−1,伽马通量降低到1.13 × 1011 cm−2 s−1。容器/桶材料寿命维持在10年以上,燃耗深度比无内屏蔽模型低6.25%。研究结论可为今后小型熔盐堆的屏蔽设计和参数选择提供重要参考。
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来源期刊
CiteScore
1.30
自引率
0.00%
发文量
56
期刊介绍: The Journal of Nuclear Engineering and Radiation Science is ASME’s latest title within the energy sector. The publication is for specialists in the nuclear/power engineering areas of industry, academia, and government.
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