JMCT与子通道程序耦合方法研究及验证

刘鹏; 史敦福; 李康; 邓力

doi:10.11884/HPLPB201830.170252

JMCT与子通道程序耦合方法研究及验证

doi: 10.11884/HPLPB201830.170252

刘鹏^1,,
史敦福¹,
李康¹,
邓力^{1, 2}

1.
中物院高性能数值模拟软件中心, 北京 100088
2.
北京应用物理与计算数学研究所, 北京 100092

基金项目:

能源局重大专项子项 2015ZX06002008

国防科工局国防基础科研计划项目 C1520110002

国家磁约束核聚变能源研究专项 2015GB108002

NSFC-广东联合基金(第二期)超级计算科学应用专项 U1501501

详细信息

作者简介:
刘鹏(1989-)，男，博士，从事核热耦合研究；liu_p07@163.com

中图分类号: TL32
计量
- 文章访问数: 1256
- HTML全文浏览量: 328
- PDF下载量: 167
- 被引次数: 0
出版历程
- 收稿日期: 2017-06-21
- 修回日期: 2017-09-21
- 刊出日期: 2018-01-15

Researchand validation on coupling method of JMCT and subchannel code

Liu Peng^1
,,
Shi Dunfu¹,
Li Kang¹,
Deng Li^{1, 2}

1.
CAEP Software Center for High Performance Numerical Simulation, Beijing 100088, China
2.
Institute of Applied Physics and Computational Mathematics, Beijing 100092, China

摘要

摘要: 蒙特卡罗与热工水力的耦合计算是目前反应堆数值模拟的重要研究方向，在蒙特卡罗方法连续能量点截面的基础上结合热工程序的温度反馈，反应堆中子计算的准确性得到大幅提高。为了提高计算精度，堆芯模型分辨率也需进一步提高，相比于组件均匀化模型，pin-by-pin的建模方式能够获得更好的结果。利用蒙特卡罗程序JMCT与子通道程序COBRA-EN实现了蒙特卡罗-热工的内耦合，内耦合方式通过内存进行数据传递，其计算效率及安全性均优于外耦合方法。随后利用NURISP项目迷你堆的pin-by-pin模型对耦合程序进行验证。计算结果与同类耦合程序相似，验证了程序的准确性。同时，对耦合过程的收敛性问题进行了初步分析。
- JMCT /
- 子通道 /
- 蒙特卡罗-热工耦合 /
- pin-by-pin
Abstract: Monte Carlo is a statistical method widely used in solving particle transport problems. A Monte Carlo code has the advantages of much flexible geometry and high fidelity. Taking advantage of this, reactor core analysis can be solved with high fidelity, although much computing cost is needed. With the feedback of a thermal hydraulic code, the core in hot full power condition on steady state can be computed by a Monte Carlo code. In this paper, JMCT, a Monte Carlo code, and COBRA-EN, a subchannel code, are coupled through the method of internal coupling. Picard iteration is used between neutron transport calculation and thermal-hydraulic calculation. The HFP steady-state calculation in a mini-core benchmark in NURISP project is used to validate the coupling code. The result agrees with that of SERPENT2/SUBCHANFLOW and TRIPOLI/SUBCHANFLOW, verifying the accuracy of this code.
- JMCT /
- COBRA-EN /
- internal coupling /
- pin-by-pin

HTML全文

图 1 耦合程序流程图

Figure 1. Coupling scheme of JCMT and COBRA-EN

下载: 全尺寸图片幻灯片

图 2 迷你堆模型示意图

Figure 2. Geometry of minicore model

下载: 全尺寸图片幻灯片

图 3 迷你堆计算模型

Figure 3. Computation models of minicore

下载: 全尺寸图片幻灯片

图 4 有效增殖系数k_eff随迭代次数的收敛情况

Figure 4. k_eff in the iteration steps

下载: 全尺寸图片幻灯片

图 5 迷你堆的功率分布

Figure 5. Power distributions in minicore

下载: 全尺寸图片幻灯片

表 1 迷你堆HFP工况的物理热工参数

Table 1. HFP parameters of minicore

height of fuel pins /cm	assembly width /cm	assembly arrangement	power /mW	mass flow rate /(kg·s^-1)	inlet temperature /K	pressure /MPa	boron concentration /ppm
365.76	21.42	17×17	100	82.12	560	15.4	200

下载: 导出CSV

表 2 收敛比例与粒子数和统计代数的关系

Table 2. Convergence ratio of power in different tracking neutrons and batches

neutrons per batch	number of batches	convergence ratio/%
1×10⁵	1000	30.94
2×10⁵	1000	42.26
4×10⁵	1000	54.44
6×10⁵	1000	61.63
8×10⁵	1000	70.51
10×10⁵	1000	73.50
6×10⁵	1500	73.23
6×10⁵	2000	83.39
6×10⁵	3000	88.25

下载: 导出CSV

参考文献(8)

[1]	Kelly D J, Aviles B N, Herman B R. MC21 analysis of the MIT PWR benchmark: hot zero power results[C]//Proceedings of the International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, 2962-2977.
[2]	Sjenitzer B L, Hoogenboom J E, Escalante J J, et al. Coupling of dynamic Monte Carlo with thermal-hydraulic feedback[J]. Annals of Nuclear Energy, 2015: 27-39. https://www.sciencedirect.com/science/article/pii/S0306454914004903
[3]	Daeubler M, Ivanov A, Sjenitzer B L, et al. High-fidelity coupled Monte Carlo neutron transport and thermal-hydraulic simulations using Serpent 2/SUBCHANFLOW[J]. Annals of Nuclear Energy, 2015: 352-375. https://www.sciencedirect.com/science/article/pii/S0306454915001747
[4]	Liu S, Liang J, Wu Q, et al. BEAVRS full core burnup calculation in hot full power condition by RMC code[J]. Annals of Nuclear Energy, 2017, 101: 434-446. https://www.sciencedirect.com/science/article/pii/S0306454916304959
[5]	刘仕昌, 吴屈, 郭娟娟, 等. BEAVRS基准题热态满功率计算研究[C]//2016年反应堆物理会议, 2016. Liu Shichang, Wu Qu, Guo Juanjuan, et al. Whole core calculations of [5] BEAVRS benchmark in hot full power condition//CORPHY-2016, 2016
[6]	李刚, 邓力, 张宝印, 等. BEAVRS基准模型热零功率状态的JMCT分析[J]. 物理学报, 2016, 65: 052801. doi: 10.7498/aps.65.052801 Li Gang, Deng Li, Zhang Baoyin, et al. JMCT Monte Carlo analysis of BEAVRS benchmark: hot zero power results. Acta Physica Sinica, 2016, 65: 052801 doi: 10.7498/aps.65.052801
[7]	Kozlowski T, Downar T J. OECD/NEA and U.S. NRC PWR MOX/UO₂ core transient benchmark—final report[R]. OECD Nuclear Energy Agency/Nuclear Science Committee. 2007.
[8]	Kozlowski T, Downar T J. OECD/NEA and U.S. NRC PWR MOX/UO₂ core transient benchmark[R]. OECD Nuclear Energy Agency/Nuclear Science Committee. 2003.