基于Bamboo-C软件的压水堆核电厂次临界刻棒方法研究及验证

李载鹏; 白家赫; 万承辉; 房何; 潘泽飞; 吴宏春

doi:10.13832/j.jnpe.2024.06.0022

基于Bamboo-C软件的压水堆核电厂次临界刻棒方法研究及验证

doi: 10.13832/j.jnpe.2024.06.0022

李载鹏^1,,
白家赫²,
万承辉^2, ,,
房何^{1, 2},
潘泽飞¹,
吴宏春²

1.
江苏核电有限公司，江苏连云港，222042
2.
西安交通大学核科学与技术学院，西安，710049

基金项目: 国家重点研发计划（2022YFB1902600）

详细信息

作者简介:
李载鹏（1982—），男，高级工程师，现主要从事核反应堆物理及燃料管理研究，E-mail: lizpa@cnnp.com.cn

通讯作者:
万承辉，E-mail: wan.ch@mail.xjtu.edu.cn

中图分类号: TL329
计量
- 文章访问数: 19
- HTML全文浏览量: 5
- PDF下载量: 3
- 被引次数: 0
出版历程
- 收稿日期: 2023-12-15
- 修回日期: 2024-01-23
- 刊出日期: 2024-12-17

Research and Verification of Subcritical Rod Worth Measurement Method for PWRs Based on Bamboo-C Code

Li Zaipeng^1
,,
Bai Jiahe²,
Wan Chenghui^{2
, ,},
Fang He^{1, 2},
Pan Zefei¹,
Wu Hongchun²

1.
Jiangsu Nuclear Power Co., Ltd., Lianyungang, Jiangsu, 222042, China
2.
School of Nuclear Science and Technology, Xi’an Jiaotong University, Xi’an, 710049, China

摘要

摘要: 控制棒价值测量是核电厂核设计验证的重要内容，传统上普遍需要在零功率物理试验中单独设置一段时间，通过硼测法、换棒法或动态刻棒方法实现控制棒价值测量，导致零功率物理试验时间较长，经济性较低。因此，本文提出了三维中子源增殖方法，基于提棒达临界过程中源量程探测器的实测数据以及Bamboo-C软件的三维堆芯数值模拟，实现次临界反应性的测量，进而获得控制棒价值。整个过程直接依赖于现有的提棒达临界规程，具有优异的工程应用能力，能够显著提高核电厂的经济性。采用田湾核电站M310机组某个循环提棒达临界过程的实测数据对本文提出的方法进行验证，验证结果表明，绝大部分的控制棒价值测量值均能够满足±10%的工程验证准则，验证效果较好，证明本文提出的方法具有工程应用的研究价值。
- 次临界刻棒 /
- 三维中子源增殖方法 /
- 源量程探测器 /
- 提棒达临界 /
- 控制棒价值
Abstract: The measurement of control rod worth is very important for the validation of nuclear design. Conventionally, the control rod worth measurement is carried out through the boron-dilution method, the rod-swap method, or the dynamic rod worth measurement method. These conventional methods lead to the fact that the zero power physics test occupies too long time. Therefore, this paper proposes the three-dimensional neutron source multiplication method. This method can achieve the measurement of subcriticality as well as control rod worth based on the measured source-range detector signals during the rod withdrawal process and the simulation results by Bamboo-C code. The whole flowchart relies on the current procedure of rod withdrawal process. This method has excellent engineering application ability and can significantly improve the economy of nuclear power plants. The measurement data during the rod withdrawal process in the M310-type reactor of Tianwan NPP is adopted for the verification of the proposed method. Most measured results of control rod worth can meet the engineering acceptance criteria (±10%), which proves that the method proposed in this paper has research value in engineering application.
- Subcritical rod worth measurement /
- Three-dimensional neutron source multiplication method /
- Source-range detector /
- Rod withdrawal process /
- Control rod worth

HTML全文

图 1 基于三维中子源增殖方法的次临界刻棒流程

Figure 1. Flowchart of Subcritical Rod Worth Measurement Based on Improved Neutron Source Multiplication Method

下载: 全尺寸图片幻灯片

图 2 Sb-Be中子源的布置

Figure 2. Configuration of Sb-Be Neutron Source

下载: 全尺寸图片幻灯片

图 3 源量程探测器布置图

Figure 3. Layout of Source-range Detector

下载: 全尺寸图片幻灯片

图 4 停堆棒组移出顺序

Figure 4. Withdrawal Sequence of Shutdown Control Rods

下载: 全尺寸图片幻灯片

图 5 功率调节棒组和R棒组移出顺序

Figure 5. Withdrawal Sequence of Power Adjustment and R Control Rods

下载: 全尺寸图片幻灯片

图 6 停堆棒组移出时源量程探测器计数率

Figure 6. Source-range Detector Count Rates during Withdrawal Process of Shutdown Control Rods

下载: 全尺寸图片幻灯片

图 7 功率调节和R棒组移出时源量程探测器计数率

Figure 7. Source-range Detector Count Rates during Withdrawal Process of Power Adjustment and R Control Rods

下载: 全尺寸图片幻灯片

图 8 源量程探测器计数率对比结果

Figure 8. Comparison of Source-Range Detector Count Rates

下载: 全尺寸图片幻灯片

表 1 次临界状态的总体信息

Table 1. General Information of Subcritical States

状态点	控制棒棒位/步									SR1计数率/s⁻¹	SR2计数率/s⁻¹
状态点	N2	N1	G2	G1	R	SA	SB	SC	SD	SR1计数率/s⁻¹	SR2计数率/s⁻¹
①	5	5	5	5	5	5	5	5	5	695	668
②	5	5	5	5	5	225	5	5	5	713	675
③	5	5	5	5	5	225	225	5	5	958	904
④	5	5	5	5	5	225	225	225	5	957	902
⑤	5	5	5	5	5	225	225	225	225	957	908
⑥	225	120	5	5	5	225	225	225	225	1132	1079
⑦	225	225	135	10	5	225	225	225	225	1173	1115
⑧	225	225	225	110	5	225	225	225	225	1234	1171
⑨	225	225	225	225	5	225	225	225	225	1252	1188
⑩	225	225	225	225	150	225	225	225	225	2321	2221

下载: 导出CSV

表 2 次临界反应性结果

Table 2. Subcriticality Results

状态点	理论值/pcm	实测值/pcm		误差/pcm		相对误差/%
状态点	理论值/pcm	SR1	SR2	SR1	SR2	SR1	SR2
①	12699	12707	12708	8	9	0.1	0.1
②	11687	11525	11730	−161	44	−1.4	0.4
③	9443	9573	9699	130	257	1.4	2.7
④	8804	8957	9084	153	280	1.7	3.2
⑤	7998	8195	8265	197	267	2.5	3.3
⑥	6676	6805	6829	130	153	1.9	2.3
⑦	5573	5653	5689	80	115	1.4	2.1
⑧	4956	5010	5049	54	93	1.1	1.9
⑨	4649	4676	4714	27	64	0.6	1.4
1pcm=10⁻⁵

下载: 导出CSV

表 3 源量程探测器SR1和SR2分别测量的控制棒价值

Table 3. Control Rod Worth Measured by SR1 or SR2

控制棒	理论值/pcm	实测值/pcm		误差/pcm		相对误差/%
控制棒	理论值/pcm	SR1	SR2	SR1	SR2	SR1	SR2
SA	1012	1182	977	170	−35	16.8	−3.5
SB	2244	1952	2029	−292	−215	−13	−9.5
SC	639	616	615	−23	−24	−3.6	−3.8
SD	806	762	820	−44	14	−5.5	1.7
N2+部分N1	1322	1389	1436	67	114	5.1	8.6
部分N1+部分G2+部分G1	1102	1152	1141	49	39	4.5	3.5
部分G2+部分G1	617	644	639	27	22	4.3	3.6
部分G1	307	333	336	26	29	8.6	9.4
部分R	516	543	580	27	64	5.3	12.5
功率调节棒组	3348	3518	3552	170	204	5.1	6.1

下载: 导出CSV

表 4 源量程探测器SR1和SR2测量的控制棒价值平均值

Table 4. Control Rod Worth Measured by Both SR1 and SR2

控制棒	理论值/pcm	实测值/pcm	误差/pcm	相对误差/%
SA	1012	1079.5	67.5	6.7
SB	2244	1991.5	−252.5	−11.3
SC	639	615.5	−23.5	−3.7
SD	806	790.5	−15.5	−1.9
N2+部分N1	1322	1412.5	90.5	6.8
部分N1+部分G2+部分G1	1102	1146	44	4.0
部分G2+部分G1	617	641.5	24.5	4.0
部分G1	307	334.5	27.5	9.0
部分R	516	561.5	45.5	8.8
功率调节棒组	3348	3534.5	186.5	5.6

下载: 导出CSV

参考文献(14)

[1]	CHAO Y A, CHAPMAN D M, HILL D J, et al. Dynamic rod worth measurement[J]. Nuclear Technology, 2000, 132(3): 403-412. doi: 10.13182/NT00-A3153
[2]	WAN C H, BAI J H, HUANG Z P, et al. Effects research of multiple-cycle nuclide-number-density distributions on dynamic rod worth measurement[J]. Nuclear Engineering and Design, 2022, 400: 112061. doi: 10.1016/j.nucengdes.2022.112061
[3]	BAI J H, WAN C H, LI Y Z, et al. Research of dynamic rod worth measurement technique based on the pin-by-pin response function[J]. Annals of Nuclear Energy, 2023, 193: 110039. doi: 10.1016/j.anucene.2023.110039
[4]	代前进,张佶翱,詹勇杰,等. 压水反应堆达临界的外推修正[J]. 核动力工程,2010, 31(6): 93-95,101.
[5]	陈效先,王璠,周琦,等. 启明星Ⅱ号中子吸收体反应性价值测量[J]. 原子能科学技术,2020, 54(2): 302-306. doi: 10.7538/yzk.2019.youxian.0065
[6]	PERSSON C M, FOKAU A, SERAFIMOVICH I, et al. Pulsed neutron source measurements in the subcritical ADS experiment YALINA-Booster[J]. Annals of Nuclear Energy, 2008, 35(12): 2357-2364. doi: 10.1016/j.anucene.2008.07.011
[7]	刘东海,张巍,章秩烽,等. 跳源法测量启明星Ⅱ号反应堆次临界度[J]. 核电子学与探测技术,2019, 39(1): 1-4. doi: 10.3969/j.issn.0258-0934.2019.01.001
[8]	张潇湘. 基于逆动态法的次临界系统次临界度重构方法研究[D]. 合肥: 中国科学技术大学,2017.
[9]	SZIEBERTH M, KLUJBER G, KLOOSTERMAN J L, et al. Measurement of multiple α-modes at the Delphi subcritical assembly by neutron noise techniques[J]. Annals of Nuclear Energy, 2015, 75: 146-157. doi: 10.1016/j.anucene.2014.07.018
[10]	LEE E K, PARK D H, CHOI H. Experimental determination of subcriticality at subcritical PWRs in Korea[J]. Annals of Nuclear Energy, 2010, 37(11): 1601-1608. doi: 10.1016/j.anucene.2010.06.022
[11]	AHN J G, CHO N Z, KUH J E. Generation of spatial weighting functions for ex-core detectors by adjoint transport calculation[J]. Nuclear Technology, 1993, 103(1): 114-121. doi: 10.13182/NT93-A34834
[12]	XU L F, SHEN H Y, WEI J X, et al. Study of the PWR ex-core detector response simulation based on the 3D S_N method[J]. Annals of Nuclear Energy, 2020, 139: 107223. doi: 10.1016/j.anucene.2019.107223
[13]	WANG Y P, ZHENG Y Q, XU L F, et al. NECP-hydra: a high-performance parallel S_N code for core-analysis and shielding calculation[J]. Nuclear Engineering and Design, 2020, 366: 110711. doi: 10.1016/j.nucengdes.2020.110711
[14]	万承辉,李云召,郑友琦,等. 压水堆燃料管理软件Bamboo-C研发及工业确认[J]. 核动力工程,2021, 42(5): 15-22.