基于RMC的微观截面参数化

冯致远; 李凯文; 骆浩; 王侃

doi:10.11884/HPLPB202234.210309

基于RMC的微观截面参数化

doi: 10.11884/HPLPB202234.210309

清华大学工程物理系，北京 100084

基金项目: 国家自然科学基金项目（11775127）；科技部重点研发计划（ 2020YFB1901700）

详细信息

作者简介:
冯致远，fengzy17@mails.tsinghua.edu.cn

中图分类号: TL32
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- 被引次数: 0
出版历程
- 收稿日期: 2021-07-22
- 修回日期: 2021-09-06
- 网络出版日期: 2021-10-14
- 刊出日期: 2022-01-11

Micro cross-section parameterization based on RMC code

Department of Engineering Physics, Tsinghua University, Beijing 100084, China

摘要

摘要: 为了进行堆芯计算，需要通过组件计算提前构建少群截面参数库。传统确定论的组件截面参数化方法针对宏观截面进行截面参数化，但这种方式不仅需要考虑多种物理状态参数，而且需要考虑历史效应对截面的影响。提出了基于核素微观截面的蒙卡程序参数化方法，该方法可以消除燃耗历史的影响，且考虑的物理状态仅为燃耗深度以及材料温度。利用蒙卡程序产生组件截面参数库耦合堆芯程序进行堆芯计算，首先用蒙卡程序同时统计对应状态点下的核素密度以及核素少群微观截面，再利用核素微观截面进而获得宏观截面进行后续堆芯计算。为了验证方法正确性，构造了一个自定义的压水堆模型，计算结果与连续能量蒙卡计算结果符合良好。
- 截面参数化 /
- RMC /
- 少群微观截面 /
- 燃耗深度 /
- 有效增殖因子
Abstract: To perform realistic core calculations, few-group neutron cross-sections library by functions of burn-up and thermal hydraulics parameters should be prepared in advance. Traditional deterministic parameterization process is based on the macro cross-section. However, this method should consider the historical effect of some physical states, which increases the number of calculation branches. Thus, this paper proposes a new parameterization process based on the micro cross-section of nuclide. This method effectively eliminates the historical impact. Therefore, only burn-up and material temperature need to be considered. The calculation process is performed by RMC code. Firstly, all of material nuclides micro cross-section and nuclides density is calculated. Then, macro cross-section is obtained by the micro cross-section lib. To test the method accuracy, a self-design pressurized water reactor model is built. The test results agree well with the reference results calculated by RMC full core calculation.
- cross-section parameterization /
- RMC /
- few-group micro cross-section /
- burn-up /
- effective multiplication factor

HTML全文

图 1 Python计算流程图

Figure 1. Multi-physical conditions calculation process

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图 2 可燃毒物组件

Figure 2. Burnable poison assembly geometry

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图 3 堆芯径向布置图

Figure 3. Radial model of core

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图 4 550 K燃耗点数据对比

Figure 4. Comparison of multigroup RMC and continues energy RMC under 550 K

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图 5 0.05 MWD/KgHM的功率分布相对偏差

Figure 5. Relative difference in radial power distribution under 0.05 MWD/tHM burnup

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图 6 2.5 MWD/KgHM的功率分布相对偏差

Figure 6. Relative difference in radial power distribution under 2.5 MWD/tHM burnup

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图 7 11.5 MWD/KgHM的功率分布相对偏差

Figure 7. Relative difference in radial power distribution under 11.5 MWD/tHM burnup

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表 1 燃耗设置

Table 1. Setting of burnup

step	time/day	burnup（MWD/kgHM）
0	0.00	0.00
1	1.44	0.05
2	2.88	0.10
3	5.76	0.20
4	8.64	0.30
5	14.41	0.50
6	21.61	0.75
7	28.81	1.00
8	43.22	1.50
9	72.03	2.50
10	100.85	3.50
11	129.66	4.50
12	158.47	5.50
13	187.29	6.50
14	216.10	7.50
15	244.91	8.50
16	273.73	9.50
17	302.54	10.50
18	331.35	11.50

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表 2 550 K燃耗点k_eff数据对比

Table 2. Comparison of k_eff of multigroup RMC and continues energy RMC under 550 K

step RMC	Continuous energy	multi-group	relative error /pcm
0	1.179881	1.178647	123.4
1	1.149456	1.149575	11.9
2	1.166661	1.16565	101.1
3	1.165531	1.164513	101.8
4	1.164228	1.163652	57.6
5	1.162347	1.161281	106.6
6	1.16069	1.160169	52.1
7	1.159095	1.157965	113
8	1.156514	1.154763	175.1
9	1.14495	1.144422	52.8
10	1.13964	1.138056	158.4
11	1.135396	1.134719	67.7
12	1.130832	1.130409	42.3
13	1.126472	1.12633	14.2
14	1.122124	1.121316	80.8
15	1.117846	1.117473	37.3
16	1.113375	1.112881	49.4
17	1.108662	1.109897	123.5
18	1.104564	1.104411	15.3

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参考文献(8)

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