基于栅元嵌套网格的停堆剂量率方法初步验证及应用

郑征; 夏春梅; 梅其良; 解均涵; 史涛; 高静; 王梦琪

doi:10.11884/HPLPB202537.250009

基于栅元嵌套网格的停堆剂量率方法初步验证及应用

doi: 10.11884/HPLPB202537.250009

上海核工程研究设计院股份有限公司，上海 200233

基金项目: 国家重点研发计划项目(2022YFB1902800)

详细信息

作者简介:
郑　征，zhengzheng@snerdi.com.cn

通讯作者:
王梦琪，wangmengqi@snerdi.com.cn。

中图分类号: TL328
计量
- 文章访问数: 8
- HTML全文浏览量: 7
- PDF下载量: 0
- 被引次数: 0
出版历程
- 收稿日期: 2025-01-09
- 修回日期: 2025-07-08
- 录用日期: 2025-06-27
- 网络出版日期: 2025-07-18

Preliminary validation and application of shutdown dose rate calculation method based on cell-in-mesh

Shanghai Nuclear Engineering Research and Design Institute Co, Ltd, Shanghai 200233, China

摘要

摘要: 停堆剂量率计算分析是核反应堆辐射安全的重要内容。为了分析车载微型移动核电源的停堆剂量率，研究了基于栅元嵌套网格的停堆剂量率计算方法。该方法在严格两步法的计算框架下，对活化光子源的抽样方法进行了改进。通过构建几何简单的包围盒，抽样得到源栅元内的粒子分布，从而提高了抽样效率和精度。在国际热核聚变实验堆(ITER)停堆剂量率基准题中进行了验证，该方法与参考解符合较好。基于该方法开展了兆瓦级车载微型移动核电源Megapower的停堆剂量率分析，计算结果表明热管贯穿端剂量率水平相对较高。该方法可用于反应堆停堆剂量率的计算分析，能够准确评估结构材料活化源及其产生的剂量率，对于反应堆屏蔽设计、维修计划的制定以及退役具有重要的参考意义。
- 停堆剂量率 /
- 严格两步法 /
- 源粒子抽样 /
- ITER基准题 /
- Megapower
Abstract: Shutdown dose rate calculation and analysis is an important aspect of radiation safety for nuclear reactors. To analyze shutdown dose rate of vehicle-mounted micro-mobile nuclear power sources, this paper investigates a shutdown dose rate calculation method based on cell-in-mesh. Within the framework of the rigorous two-step method, improvements were made to the sampling method for activated photon sources. By constructing geometrically simple bounding boxes and sampling the particle distribution within the source cell, both sampling efficiency and accuracy were enhanced. This method was validated against the International Thermonuclear Experimental Reactor (ITER) shutdown dose rate benchmark problem, showing good agreement with reference solutions. Based on this method, a shutdown dose rate analysis was conducted for the megawatt-level vehicle-mounted micro-mobile nuclear power source Megapower, revealing that the dose rate level at the end of the heat pipe is relatively high. This method can be used for the calculation and analysis of reactor shutdown dose rates, accurately assessing structural material activation sources and their generated dose rates. It has significant reference value for reactor shielding design, maintenance planning, and decommissioning.
- shutdown dose rate /
- rigorous two-step method /
- source particle sample /
- ITER benchmark /
- Megapower

HTML全文

图 1 基于栅元嵌套网格的停堆剂量率计算方法流程图

Figure 1. Flowchart of shutdown dose rate calculation method based on cell-in-mesh

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图 2 栅元嵌套网格源粒子抽样示意图

Figure 2. Schema of source particle sample based on cell-in-mesh

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图 3 ITER停堆剂量率基准题几何模型

Figure 3. ITER shutdown dose rate benchmark geometry

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图 4 ITER停堆剂量率计算结果

Figure 4. ITER shutdown dose rate calculation results

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图 5 Megapower微型核反应堆几何模型示意图

Figure 5. Schema of Megapower micro-reactor geometry

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图 6 Megapower停堆后剂量率分布示意图

Figure 6. Schema of Megapower shutdown dose rate

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表 1 ITER停堆剂量率基准题材料信息

Table 1. ITER shutdown dose rate benchmark material compositions

nuclide	nuclide fraction		nuclide	nuclide fraction
nuclide	steel and water mixture	steel	nuclide	steel and water mixture	steel
H	1.46E-01	−	Mn	1.42E-02	1.82E-02
B	4.02E-05	5.14E-05	Fe	5.03E-01	6.44E-01
C	8.14E-04	1.04E-03	Co	3.68E-04	4.71E-04
N	2.17E-03	2.78E-03	Ni	9.06E-02	1.16E-01
O	7.29E-02	6.95E-05	Cu	2.05E-03	2.62E-03
Al	8.04E-04	1.03E-03	Zr	9.52E-06	1.22E-05
Si	7.73E-03	9.89E-03	Nb	4.67E-05	5.98E-05
P	3.50E-04	4.48E-04	Mo	1.13E-02	1.45E-02
S	1.02E-04	1.30E-04	Sn	7.31E-06	9.36E-06
K	5.55E-06	7.10E-06	Ta	2.40E-05	3.07E-05
Ti	1.36E-03	1.74E-03	W	2.36E-06	3.02E-06
V	3.41E-05	4.36E-05	Pb	1.68E-06	2.14E-06
Cr	1.46E-01	1.87E-01	Bi	1.66E-06	2.13E-06

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表 2 ITER停堆剂量率基准题辐照历史

Table 2. ITER shutdown dose rate benchmark irradiation history

neutron source/(n/s)	time	repetition
1.0714E+17	2 y	1
8.25E+17	10 y	1
0	0.667 y	1
1.6607E+18	1.33 y	1
0	3920s	1
2.0E+19	400s	17
0	3920s	17
2.8E+19	400s	3
0	3920s	3
2.8E+19	400s	1
0	10⁶s	1

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