基于MOSASAUR程序的中子-光子输运堆芯释热率计算方法研究

胡馗; 马续波; 王连杰; 张斌; 赵晨; 张腾; 陈义学

doi:10.13832/j.jnpe.2024.03.0037

基于MOSASAUR程序的中子-光子输运堆芯释热率计算方法研究

doi: 10.13832/j.jnpe.2024.03.0037

胡馗^1,,
马续波^1, ,,
王连杰²,
张斌²,
赵晨²,
张腾¹,
陈义学¹

1.
华北电力大学核科学与工程学院，北京，102206
2.
中国核动力研究设计院核反应堆系统设计技术重点实验室，成都，610213

基金项目: 国家自然科学基金资助项目（11875128、12075228）

详细信息

作者简介:
胡　馗（1997—），男，博士研究生，现主要从事中子-光子耦合输运计算方法研究，E-mail: hk@ncepu.edu.cn

通讯作者:
马续波，E-mail: maxb@ncepu.edu.cn

中图分类号: TL32
计量
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- 被引次数: 0
出版历程
- 收稿日期: 2023-06-12
- 修回日期: 2023-07-16
- 刊出日期: 2024-06-13

Research on the Neutron-photon Transport and Heat Calculation Method Based on MOSASAUR Code

1.
School of Nuclear Science and Engineering, North China Electric Power University, Beijing, 102206, China
2.
Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu, 610213, China

摘要

摘要: 为了准确计算快堆堆芯中所有裂变材料与非裂变材料释热，并精细考虑中子、光子、电子在堆芯中的能量沉积，以提高快堆堆芯释热率计算精度。本文基于确定论两步法研究并实现了中子-光子输运堆芯释热率计算方法，通过求解裂变源中子输运方程和固定源光子输运方程得到中子和光子注量率，基于比释动能（KERMA）因子方法计算瞬发中子和瞬发光子释热率，利用比例因子方法计算缓发光子产生矩阵，在MOSASAUR程序内通过内耦合方式实现了快堆中子-光子输运和堆芯释热率计算。计算铅铋快堆RBEC-M基准题的功率分布并与蒙特卡罗程序计算结果进行对比，燃料组件总功率相对偏差在±4%以内，非燃料组件总功率相对偏差在±10%以内，所有组件光子功率相对偏差在±10%以内。因此，本文研究的中子-光子输运堆芯释热率计算方法对快堆堆芯释热计算具有较高精度。
- 中子-光子输运 /
- 比释动能（KERMA）因子 /
- 快堆 /
- 缓发光子 /
- 高阶光子输运
Abstract: To accurately calculate the heat released by all fissile and non-fissile materials in the fast reactor core, with a meticulous consideration of energy deposition by neutrons, photons, and electrons within the core, so as to enhance the precision of heat generation calculations, this paper, based on the deterministic two-step method, explores and implements a neutron-photon coupled transport calculation method. By solving the fission-source neutron transport equation and the fixed-source photon transport equation, the neutron and photon flux are obtained. Prompt neutron and prompt photon heat generation rates are calculated using the KERMA factor method. The delayed photon production matrix is computed using the scaling factor method. A self-coupling method in the MOSASAUR code is employed to achieve neutron-photon transport and heat generation calculations within the fast reactor core. The power distribution of the lead-bismuth fast reactor RBEC-M benchmark is compared with the results from Monte Carlo code. The relative deviations of total power are within ±4% for fuel assemblies, within ±10% for non-fuel assemblies, and within ±10% for all assemblies' photon power. Therefore, the neutron-photon transport and heat calculation method studied in this article has a high level of accuracy for the fast reactor cores.
- Neutron-photon transport /
- KERMA factor /
- Fast reactor /
- Delayed gamma /
- High-order photon transport

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图 1 中子-光子输运及堆芯释热计算流程

Figure 1. Calculation Flow of Neutron-Photon Transport and Core Heat Generation

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图 2 RBEC-M 1/6 堆芯构成

Figure 2. 1/6 Core of RBEC-M

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图 3 RBEC-M归一化中子和光子注量率

Figure 3. Normalized Neutron and Photon Flux of RBEC-M

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图 4 RBEC-M各类组件功率组成

Figure 4. Power Composition of RBEC-M Components

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图 5 RBEC-M各类组件功率占比

Figure 5. Power Proportion of RBEC-M Components

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图 6 利用²³⁵U和²³⁹Pu缓发电子能量计算得到的缓发电子功率与F7:N计算结果对比

Figure 6. Comparation of the Delayed Beta Power Calculated Using ²³⁵U and ²³⁹Pu with the Computed Results of F7:N

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图 7 利用改进后的平均缓发电子能量计算得到的缓发电子功率对比

Figure 7. Delayed Beta Power Comparision Using Improved Average Delayed Beta Energy

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图 8 RBEC-M光子功率相对偏差

Figure 8. Relative Deviation of Photon Power of RBEC-M

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图 9 RBEC-M中子功率相对偏差

Figure 9. Relative Deviation of Neutron Power of RBEC-M

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图 10 RBEC-M总功率对比

Figure 10. Relative Deviation of Total Power of RBEC-M

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表 1 RBEC-M裂变核素参数

Table 1. Parameters of Fissionable Nuclides of RBEC-M

类型	核素种类
类型	²³⁵U	²³⁸U	²³⁸Pu	²³⁹Pu	²⁴⁰Pu	²⁴¹Pu	²⁴²Pu	²⁴¹Am
缓发光子能量/MeV	6.50	8.48	5.12	5.31	6.62	6.40	6.83	5.51
缓发电子能量/MeV	6.33	8.25	5.26	5.17	6.49	6.58	7.48	5.62
裂变能量/MeV	180.57	181.04	189.98	188.42	186.36	188.99	188.47	190.83
堆芯1区裂变率比例/%	0.93	10.79	0.90	68.63	4.98	12.96	0.70	0.10
堆芯2区裂变率比例/%	0.92	11.01	0.90	68.54	4.99	12.83	0.70	0.10
堆芯3区裂变率比例/%	0.92	11.60	0.89	68.07	4.90	12.83	0.69	0.10
增殖区裂变率比例/%	7.60	92.40

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表 2 各类组件缓发光子和缓发电子平均能量

Table 2. Average Energy of Delayed Gamma and Delayed Beta of Core Components

能量	组件类型
能量	堆芯1区	堆芯2区	堆芯3区	增殖区
缓发光子平均能量/MeV	5.88	5.88	5.90	8.33
缓发电子平均能量/MeV	5.78	5.78	5.80	8.10

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表 3 功率构成计算结果

Table 3. Calculation Results for Power Components

功率类型	蒙特卡罗程序计算值/MW	MOCO 计算值/MW	相对偏差/%
中子功率	765.08	769.1	0.53
光子功率	109.7	104.8	–4.47
瞬发光子能量	84.05	82.33	–2.05
缓发电子能量	25.19	26.37	4.68
缓发光子能量	25.68	22.49	–12.42

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