西安脉冲堆燃耗对反应性引入瞬态行为的影响研究

张信一; 王立鹏; 王永平; 江新标; 银华北; 何彬; 李达; 张良; 姜夺玉; 胡田亮

doi:10.13832/j.jnpe.2023.05.0030

西安脉冲堆燃耗对反应性引入瞬态行为的影响研究

doi: 10.13832/j.jnpe.2023.05.0030

张信一^{1, 2,},
王立鹏²,
王永平³,
江新标²,
银华北³,
何彬¹,
李达²,
张良²,
姜夺玉^{1, 2},
胡田亮²

1.
火箭军工程大学，西安，710025
2.
西北核技术研究所，西安，710024
3.
西安交通大学，西安，710049

详细信息

作者简介:
张信一（1987—），男，博士研究生，现主要从事反应堆数值模拟与安全评估方面的研究，E-mail: zhangxy87@foxmail.com

中图分类号: TL323
计量
- 文章访问数: 164
- HTML全文浏览量: 49
- PDF下载量: 92
- 被引次数: 0
出版历程
- 收稿日期: 2022-11-18
- 修回日期: 2023-02-20
- 刊出日期: 2023-10-13

Influence of Depletion on Reactivity Insertion Transients for Xi’an Pulsed Reactor

1.
Rocket Force University of Engineering, Xi’an, 710025, China
2.
Northwest Institute of Nuclear Technology, Xi’an, 710024, China
3.
Xi’an Jiaotong University, Xi’an, 710049, China

摘要

摘要: 研究了一种精确模拟反应堆燃耗相关瞬态行为的新方法。基于三维物理热工耦合的堆芯瞬态计算程序，与采用微观燃耗的三维精确燃耗计算程序相耦合，针对西安脉冲堆控制棒移动过程，分析了不同燃耗深度下由于反应性引入的不同形式和大小而引起的堆芯功率和燃料温度等参数的瞬态特性。进行了堆芯脉冲功率响应对反应性引入量的敏感性分析，研究了堆芯动态参数的变化机理。数值结果表明：随着燃耗的加深，脉冲堆芯布置时脉冲功率有减小的趋势，而堆芯稳态布置时脉冲功率明显增大，达到脉冲功率峰值的时间有所提前。
- 瞬态 /
- 燃耗 /
- 动态参数 /
- 耦合
Abstract: In this paper, a new method is presented to accurately simulate the transient behavior of reactor burnup. The core transient calculation code based on three-dimensional physical and thermal coupling is coupled with the three-dimensional precise micro burnup calculation code. According to the control rod movement process of Xi'an Pulsed Reactor (XAPR), the transient characteristics of different parameters such as core power and fuel temperature due to the different form and magnitude of reactivity insertion at different burnup depth are analyzed. The sensitivity of core pulse power response to reactivity insertion is analyzed, and the change mechanism of core dynamic parameters is studied. The numerical results show that with the burnup of nuclear fuel, the peak pulse power tends to decrease when the core is arranged with pulse state, while the peak pulse power increases obviously with the steady state core arrangement, and the time to reach the peak pulse power is advanced.
- Transient /
- Burnup /
- Dynamic parameters /
- Coupling

HTML全文

图 1 不同堆芯部件的等效模型

Figure 1. Equivalent Models for Different Core Components

下载: 全尺寸图片幻灯片

图 2 功率分布计算值与参考值偏差

Figure 2. Deviation between Calculated and Referenced Power Distribution

下载: 全尺寸图片幻灯片

图 3 DAISY建立的XAPR模型（真空边界）

Figure 3. XAPR Model Established by DAISY (Vacuum Boundary)　　　　　　

下载: 全尺寸图片幻灯片

图 4 冷却剂流道模型

Figure 4. Model for Coolant Flow Channel

下载: 全尺寸图片幻灯片

图 5 耦合计算流程图

Figure 5. Flow Chart of Coupling Calculation

下载: 全尺寸图片幻灯片

图 6 不同燃耗深度时²³⁵U核素的微观反应截面

fission—裂变反应；1 b—10⁻²⁴ cm⁻²；EFPD—等效满功率天

Figure 6. Micro-reaction Cross Section of ²³⁵U at Different Burnups　　　　　　　

下载: 全尺寸图片幻灯片

图 7 不同燃耗深度时¹H核素的微观反应截面

Figure 7. Micro-reaction Cross Section of ¹H at Different Burnups　　　　　　　

下载: 全尺寸图片幻灯片

图 8 D5和G14燃料棒不同高度处²³⁵U消耗计算结果与实验值对比

Figure 8. Comparison of Calculation Results and Experimental Values of ²³⁵U Consumption of D5 and G14 Fuel Rods at Different Heights

下载: 全尺寸图片幻灯片

图 9 XAPR引入不同反应性时功率曲线与实验值对比　　　　　　

Figure 9. Comparison between Calculated and Experimental Power Curves with Different Reactivity Insertion of XAPR

下载: 全尺寸图片幻灯片

图 10 脉冲堆芯布置时脉冲功率随燃耗变化曲线

Figure 10. Pulse Power Change Curve with Burnup under Pulse Core Distribution

下载: 全尺寸图片幻灯片

图 11 脉冲堆芯布置时动态参数随燃耗变化曲线

Figure 11. Dynamic Parameter Change Curve with Burnup under Pulse Core Distribution

下载: 全尺寸图片幻灯片

图 12 稳态堆芯布置时脉冲功率随燃耗变化曲线

Figure 12. Pulse Power Change Curve with Burnup under Steady State Core Distribution

下载: 全尺寸图片幻灯片

图 13 稳态堆芯布置时燃料温度变化曲线

Figure 13. Fuel Temperature Curve under Steady State Core Distribution　　　　　　

下载: 全尺寸图片幻灯片

图 14 稳态堆芯布置时动态参数随燃耗变化曲线

Figure 14. Dynamic Parameters Change Curve with Burnup under Steady State Core Distribution

下载: 全尺寸图片幻灯片

图 15 2种堆芯布置的中子能谱对比

Figure 15. Comparison of Neutron Energy Spectrum between Two Core Arrangements

下载: 全尺寸图片幻灯片

表 1 瞬发中子能群结构

Table 1. Prompt Neutron Energy Group Structure

瞬发中子能群编号	中子能量上界 /eV
1	10⁷
2	5.00×10⁵
3	9.118×10³
4	4.00
5	0.625
6	0.14
7	0.058

下载: 导出CSV

表 2 缓发中子相对份额和衰减常数

Table 2. Relative Fraction and Decay Constant of Delayed Neutrons

缓发中子能群编号	缓发中子相对份额/%	缓发中子衰减常数/s⁻¹
1	3.20	0.0125
2	16.64	0.0318
3	16.13	0.1094
4	45.96	0.3170
5	13.35	1.3540
6	4.72	8.6364

下载: 导出CSV

表 3 不同控制棒位置和价值堆芯临界计算k_eff与参考值对比　　　　　

Table 3. Comparison of Core Criticality Calculated and Referenced k_eff with Different Control Rod Positions

控制棒位置	k_eff		偏差/%
控制棒位置	计算值	参考值	偏差/%
D控制棒全插	0.99479	0.99725	−0.25
D控制棒全提	1.02502	1.02584	−0.08

下载: 导出CSV

表 4 XAPR引入不同反应性时脉冲参数与实验值对比

Table 4. Comparison between Calculated and Experimental Pulse Parameters with Different Reactivity Insertion of XAPR

引入反应性 /$	堆芯布置方式	脉冲峰功率/MW		脉冲峰功率偏差 / %	脉冲半高宽/ms		脉冲半高宽偏差 / %
引入反应性 /$	堆芯布置方式	计算值	实验值	脉冲峰功率偏差 / %	计算值	实验值	脉冲半高宽偏差 / %
0.95	脉冲堆芯	1.43	1.5	−4.67	3485.0	3716	−6.22
1.11	脉冲堆芯	12.12	13.2	−8.18	167.8	154.8	8.40
2.0	脉冲堆芯	601.61	636.5	−5.48	16.5	17.58	−6.14
3.45	脉冲堆芯	4157.92	4301.3	−3.33	7.15	7.214	0.88
1.14	稳态堆芯	14.30	13.8	3.60	272.5	296.4	−8.06

下载: 导出CSV

表 5 引入反应性的量变化1%时，脉冲峰功率和半高宽的变化量

Table 5. Sensitivity of Pulse Peak Power and FWHM with Reactivity Insertion Change of 1%

引入反应性 /$	堆芯布置方式	脉冲峰功率变化量 /%	半高宽变化量 /%
0.95	脉冲堆芯	6.54	8.08
1.11	脉冲堆芯	13.23	10.56
2.0	脉冲堆芯	4.08	2.15
3.45	脉冲堆芯	1.80	3.12×10⁻⁴
1.14	稳态堆芯	12.60	9.60

下载: 导出CSV

表 6 中子消失的途径和平均时间

Table 6. Path and Average Time for Neutron Disappearance

中子消失途径	泄漏	俘获	裂变
平均消失时间 /s	9.132×10⁻⁵	1.208×10⁻⁴	4.473×10⁻⁵
中子份额（0 EFPD）/%	0.32	58.17	41.51
中子份额（120 EFPD）/%	0.31	60.40	39.29

下载: 导出CSV

参考文献(13)

[1]	ZUO H Z. The uranium-zirconium hydride pulsed reactor and its use in science and technology[J]. Nuclear Engineering and Design, 1997, 168(1-3): 305-311. doi: 10.1016/S0029-5493(96)01324-6
[2]	BADRUN N H, ALTAF M H, CHOWDHURY M T. Transient behavior studies of TRIGA core for variations in reactor kinetics[J]. Annals of Nuclear Energy, 2015, 85: 394-397. doi: 10.1016/j.anucene.2015.04.035
[3]	FERRARO D, GARCÍA M, VALTAVIRTA V, et al. Serpent/SUBCHANFLOW pin-by-pin coupled transient calculations for a PWR minicore[J]. Annals of Nuclear Energy, 2020, 137: 107090. doi: 10.1016/j.anucene.2019.107090
[4]	TRAN V P, NGUYEN K C, HARTANTO D, et al. Development of a PARCS/Serpent model for neutronics analysis of the Dalat nuclear research reactor[J]. Nuclear Science and Techniques, 2021, 32(2): 15. doi: 10.1007/s41365-021-00855-5
[5]	MINHAT M S, SUBHA N A M, HASSAN F, et al. Profiling and analysis of control rod speed design on core power control for TRIGA reactor[J]. Progress in Nuclear Energy, 2020, 128: 103481. doi: 10.1016/j.pnucene.2020.103481
[6]	LIU Q J, NICHITA E. Position-dependent delayed-neutron fractions for IQS calculations and application to PHWR kinetics calculations[J]. Nuclear Engineering and Design, 2018, 339: 150-158. doi: 10.1016/j.nucengdes.2018.08.028
[7]	HOSSEINI S A, VOSOUGHI N, GHOFRANI M B, et al. Calculation, measurement and sensitivity analysis of kinetic parameters of Tehran Research Reactor[J]. Annals of Nuclear Energy, 2010, 37(4): 463-470. doi: 10.1016/j.anucene.2010.01.018
[8]	HE M T, WU H C, ZHENG Y Q, et al. Beam transient analyses of accelerator driven subcritical reactors based on neutron transport method[J]. Nuclear Engineering and Design, 2015, 295: 489-499. doi: 10.1016/j.nucengdes.2015.10.021
[9]	ZHANG X Y, JIANG X B, ZHENG Y Q, et al. Three-dimensional transient analysis of Xi’an pulsed reactor by the coupled neutronics and thermal-hydraulics code[J]. Annals of Nuclear Energy, 2022, 175: 109254. doi: 10.1016/j.anucene.2022.109254
[10]	CHEN J, LIU Z Y, ZHAO C, et al. A new high-fidelity neutronics code NECP-X[J]. Annals of Nuclear Energy, 2018, 116: 417-428. doi: 10.1016/j.anucene.2018.02.049
[11]	王立鹏,张信一,江新标,等. 西安脉冲堆燃料元件精细燃耗分布的蒙特卡罗方法研究[J]. 原子能科学技术,2018, 52(10): 1756-1761. doi: 10.7538/yzk.2018.youxian.0028
[12]	HE M T, WU H C, CAO L Z, et al. Time-dependent, three dimensional nodal transport code development based on unstructured mesh[C]//2014 22nd International Conference on Nuclear Engineering. Prague: ASME, 2014.
[13]	张文首,阿景烨,陈达,等. 西安脉冲堆燃料元件燃耗无损实验测量[J]. 核动力工程,2009, 30(3): 30-34.