Development and verification of fuel assembly bowing model in software package PCM
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摘要: 燃料组件在反应堆内受压紧力等作用会发生弯曲，该弯曲会显著改变反应堆局部位置的中子慢化。基于中广核核设计软件包PCM中的组件中子截面计算软件PINE和堆芯核设计软件COCO，开发了专门的燃料组件弯曲模型，以分析燃料组件弯曲对堆芯局部功率分布的影响，并和蒙特卡罗软件JMCT做了对比验证计算。计算结果表明，PCM软件包燃料组件弯曲模型的计算结果与JMCT吻合良好，该软件包可以用于燃料组件弯曲的分析计算。燃料组件的弯曲对于堆芯的局部功率分布有显著的影响，需要在设计中予以特别关注。Abstract: The fuel assemblies bow with different stresses in the PWR reactor core and this phenomenon can significantly affect the local neutron moderation in the reactor core. Based on the CGN’s in-house software package PCM, which is composed of the fuel assembly neutron cross section software PINE and the core design software COCO, this study developed a specific model for fuel assembly bowing to analyze the impact on local power distribution, and compared the results with that of the Monto Carlo code JMCT. The study shows that the results of fuel assembly bowing model in PCM have good consistency with those of JMCT, and that PCM is valid in fuel assembly bowing analysis. The fuel assembly bowing has a significant impact on core local power distribution. This phenomenon shall be specially considered in the PWR reactor design.
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Key words:
- fuel assembly bowing /
- core power distribution /
- PCM /
- water gap /
- neutron cross section
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图 5 正常水隙下K03位置组件左上角1/4区域燃料棒功率分布对比
Figure 5. Fuel rod power distribution at K03 under normal water gap
(a) the first value in the square is the calculation results from COCO and the second value is from JMCT;(b) shows the difference defined as (JMCT - COCO)/COCO
图 6 水隙增大后K03位置组件左上角1/4区域燃料棒功率分布对比
Figure 6. Fuel rod power distribution at K03 under increased water gap
(a) the first value in the square is the calculation results from COCO and the second value is from JMCT; (b) shows the difference defined as (JMCT - COCO)/COCO
表 1 燃料组件主要参数
Table 1. Fuel assembly main parameters
enrichment/% assembly configuration normal water gap/mm increased water gap/mm 4.45 17×17 0.76 3.80 
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表 2 燃料组件均匀化中子截面的比较
Table 2. Homogeneous neutron cross section of fuel assembly
fast group
transport cross
section/cm−1thermal group
transport cross
section/cm−1fast group
absorption cross
section/cm−1thermal group
absorption cross
section/cm−1fast group
fission cross
section/cm−1thermal group
fission cross
section/cm−1case 1 2.37744×10−1 8.80051×10−1 9.99930×10−3 1.04927×10−1 3.24601×10−3 7.22189×10−2 Case 2 2.35261×10−1 9.07776×10−1 9.48205×10−3 9.92312×10−2 3.06870×10−3 6.71697×10−2 case 3 2.36489×10−1 8.94271×10−1 9.73666×10−3 1.02015×10−1 3.15638×10−3 6.96360×10−2 results from Eq.(2) 2.36460×10−1 8.94392×10−1 9.73174×10−3 1.01981×10−1 3.15429×10−3 6.96071×10−2 difference 0.012% −0.014% 0.051% 0.034% 0.066% 0.042%
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