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氟盐冷却高温堆主冷却剂系统16N源项分析

Analysis of 16N Source Term in Primary Coolant System of FHR

    摘要
  • 摘要: 基于SCALE6.1程序包中的三维蒙特卡罗输运程序KENO-Ⅵ对氟盐冷却高温堆（FHR）堆芯中子能谱进行计算，利用Mathematica程序建立了16N源项在主冷却剂系统内的流动模型，对FHR的主冷却剂系统16N源项进行定量分析，对不同流速情况下主冷却剂系统不同区域16N源强分布进行研究。结果表明：当冷却剂体积流量大于4.15×102 cm3•s-1、小于4.15×106 cm3•s-1时，流动效应对主冷却剂系统内16N源项浓度分布影响显著，在FHR的设计基准流量（4.15×104 cm3•s-1）情况下，堆芯中16N源项占总16N源项的76.98%，上腔室为18.89%，其余区域放射性活度占16N总量的4.13%。所建立分析方法及结论可为FHR的工程设计、辐射防护设计及源项的精确分析等提供参考。

     

    Abstract: Neutron spectrum of fluoride salt cooled high temperature reactor (FHR) was calculated by 3D Monte Carlo transport program KENO-Ⅵ in SCALE6.1 software package. The flow model of the 16N source term in the primary coolant system was established using Mathematica code. The 16N source term in the primary coolant was quantitatively analyzed and the distribution of 16N source term in different regions of the primary coolant at different flow velocities was analyzed. The results show that 16N source term concentration is obviously affected when the flow rate is greater than 4.15×102 cm3•s-1 and less than 4.15×106 cm3•s-1. In the case of design velocity of FHR, the 16N source term in core accounts for 76.98% of the total 16N source term, the 16N source term in upper chamber accounts for 18.89%, and the rest accounts for 4.13%. The analysis method and conclusion can provide some references for the engineering design of FHR, the design of radiation protection and the accurate analysis of source terms.

     

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