Research on Few Group Cross-Section Generation Method For Fast Reactor Based on Monte Carlo Code
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摘要: 为了提高快堆中子学分析精度,解决传统确定论方法制作快堆少群截面面临的复杂共振问题,基于组件均匀化-堆芯输运计算两步法,从各向异性散射、能群结构、泄漏修正等方面,开展了采用蒙特卡洛程序制作堆芯输运计算所需的组件均匀化少群截面的方法研究。数值结果表明:采用蒙特卡洛程序制作快堆少群截面,可以很好地处理中等质量核素的共振效应;采用1阶散射截面或者输运修正后的少群截面可以有效考虑各向异性散射的影响;少群截面的能群数目减小会导致堆芯有效增殖因子(keff)减小;泄漏修正会导致堆芯keff增大。采用蒙特卡洛程序制作快堆少群截面,堆芯输运得到的keff偏差小于100pcm(1pcm=10−5),功率分布偏差小于2%。Abstract: In order to improve the accuracy of neutronics analysis for fast reactors and solve the complex resonance problem faced by traditional deterministic method in making few group cross-sections of fast reactors, this paper, based on the two-step method of assembly homogenization-core transport calculation, studies the method of assembly homogenized few group cross-section by using the Monte Carlo code from the aspects of anisotropic scattering, energy group structure and leakage correction. The numerical results show that the resonance effect of medium-mass nuclides can be well treated in the fast reactor few group cross-section generation based on the Monte Carlo code; the effects of anisotropic scattering can be effectively considered with 1-order scattering cross-section or transport modified few group section. Core effective multiplication factor ( keff ) may decrease due to the decrease in the number of energy groups of few group cross-section; core keff may increase due to the leakage correction. When Monte Carlo code is used in few group cross-sections generation of fast reactor, the keff deviation of core transport is less than 100 pcm (1pcm=10−5), and the power distribution deviation is less than 2%.
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Key words:
- Few group cross-section generation /
- Monte Carlo /
- Core transport /
- Fast reactor
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表 1 MET-1000堆芯主要参数
Table 1. Main Parameters of MET-1000
参数名 参数值 燃料 (U,Pu)Zr 活性区高度/cm 85.82 组件中心距/cm 16.2471 组件壁厚度/cm 0.3966 包壳外半径/cm 0.3857 包壳内半径/cm 0.3236 燃料棒半径/cm 0.3236 结构材料 HT-9钢 冷却剂温度/K 705 结构材料温度/K 705 燃料温度/K 807 表 2 粒子数对堆芯keff的影响
Table 2. Influence of Particle Number on Core keff
算例编号 每代粒子数/万 活跃代数/代 keff 计算偏差/pcm 1 50 1000 1.03530 −19 2 50 1500 1.03584 33 3 200 2000 1.03653 99 参考解 1.03550 1pcm=10−5 表 3 各向异性散射对堆芯keff的影响
Table 3. Influence of Anisotropic Scattering on Core keff
算例 keff 计算偏差/pcm 参考解 1.0355 MOCS 0阶 1.07744 3970 MOCS 1阶 1.02351 −1165 MOCS输运修正 1.02653 −870 Serpent 0阶 1.06844 3132 Serpent 1阶 1.03549 −1 Serpent输运修正 1.03653 99 表 4 不同能群下堆芯keff计算结果对比
Table 4. Comparison of Calculation Results of Core keff for Different Energy Groups
算例 keff 计算偏差/pcm 参考解 1.03550 111g-24g 1.03652 98 47g-24g 1.03653 99 24g-24g 1.03653 99 111g-9g 1.03590 39 47g-9g 1.03589 38 24g-9g 1.03589 38 表 5 泄漏效应对堆芯keff的影响
Table 5. Influence of Leakage Effect on Core keff
算例 keff 计算偏差/pcm 泄漏修正影响/pcm 参考解 1.03550 111g-24g 1.03652 98 218 111g-24g-B1 1.03878 316 47g-24g 1.03653 99 161 47g-24g-B1 1.03820 260 111g-9g 1.03590 39 936 111g-9g-B1 1.04565 975 47g-9g 1.03589 38 875 47g-9g-B1 1.04500 913 24g-9g 1.03589 38 701 24g-9g-B1 1.04318 739 -
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