随机球床模拟方法对氟盐冷却高温堆中子学参数的影响分析

Effect of Random Pebble Bed Model on FHR Neutronics Characteristic

  • 摘要: 氟盐冷却高温堆(FHR)采用氟盐冷却球形燃料元件,其中子物理计算面临双重不均匀性问题:燃料球在堆芯内的随机排布和包覆燃料颗粒在燃料球中的随机排布。此问题是该堆型设计中面临的主要挑战之一。本文基于MCNP程序和固态燃料钍基熔盐堆(TMSR-SF1)模型完成了不同燃料球床与燃料球描述对关键中子学参数(如keff、堆芯能谱、控制棒价值和温度系数等)的影响分析。燃料球床描述使用随机序列添加(RSA)方法建立了随机球床模型与体心立方(BCC)结构的等效规则模型。包覆燃料颗粒描述则基于简立方(SC)等效模型利用MCNP程序中的URAN卡实现随机扰动。结果表明,包覆燃料颗粒随机分布的影响远小于燃料球随机分布的影响;尽管具有相同的总堆积密度,等效规则模型相比于随机球床模型会增加堆芯中子的泄漏,低估冷态满装载反应性约0.5%,高估控制棒价值约5%。

     

    Abstract: The fluoride salt-cooled high-temperature reactor (FHR) uses fluoride salt to cool fuel pebbles, which leads to the double heterogeneity in neutronic calculation including the random distribution of pebbles in the reactor and TRISO particles in the pebble. That is one of the special challenges in FHR design. Based on MCNP code and the solid-fueled thorium molten salt reactor (TMSR-SF1) model, the effects of different pebbles and pebble bed models used in criticality calculations on key parameters were analyzed, such as keff, neutron spectrum, control rod worth and temperature coefficients. The structure of pebble bed was explored by the random sequential addition (RSA) method and an equivalent body centered cubic (BCC) model with the same packing density. The distribution of TRISO particles was realized by an equivalent simple cubic (SC) model and the random perturbation implemented by the URAN card in MCNP code. The results show that the effect of the random distribution of TRISO particles is negligible compared to the random distribution of pebbles and the regular model causes more leakage than the random model, which leads to undervalue the cold state reactivity about 0.5% and overestimate the control rod worth about 5%.

     

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