NUCLEAR TECHNIQUES, Volume. 46, Issue 1, 010601(2023)
Critical safety analysis method of spent fuel solution system
Figures & Tables(10)
Fig. 2. Volume mixing operation when coupling neutronics with thermal-hydraulics / radiolysis gas
Fig. 5. Comparison of calculated results of fission rate for S2-300 experiment with different time step length
Fig. 6. Calculated results of fission rate and temperature for S2-300 experiment (color online)(a) The change of fission rate and temperature in the pulse duration, (b) The change of fission rate and temperature in the whole process
Fig. 7. Calculated results of reactivity and variation of solution system for S2-300 experiment
Table 1. Comparison on calculated keff of STACY problem
View tableView in ArticleTable 1. Comparison on calculated keff of STACY problem
keff 误差Error / 10-5 蒙卡程序 Monte Carlo code 0.999 80 — NECP-Hydra 0.999 66 -14
Table 2. Comparison on calculated neutron flux distribution of STACY problem
View tableView in ArticleTable 2. Comparison on calculated neutron flux distribution of STACY problem
程序Program 能群
Energy group
溶液分区通量
Distributed neutron flux in solution area / n·cm-2·s-1
蒙特卡罗程序
Monte Carlo code
1 8.953 20×10-2 1.439 90×10-1 1.414 48×10-1 7.617 25×10-2 6.927 32×10-2 1.112 82×10-1 1.095 87×10-1 5.956 68×10-2 3.645 34×10-2 5.825 81×10-2 5.749 10×10-2 3.197 74×10-2 2 9.104 06×10-2 1.434 08×10-1 1.409 48×10-1 7.444 57×10-2 7.029 00×10-2 1.110 32×10-1 1.092 43×10-1 5.826 82×10-2 3.694 98×10-2 5.816 49×10-2 5.729 14×10-2 3.139 46×10-2 3 9.066 44×10-2 1.437 66×10-1 1.411 14×10-1 7.497 01×10-2 7.006 13×10-2 1.111 12×10-1 1.093 59×10-1 5.861 73×10-2 3.669 91×10-2 5.796 70×10-2 5.715 79×10-2 3.140 31×10-2 4 8.822 74×10-2 1.438 11×10-1 1.411 90×10-1 7.347 63×10-2 6.804 80×10-2 1.112 11×10-1 1.094 47×10-1 5.762 37×10-2 3.687 82×10-2 5.989 44×10-2 5.906 72×10-2 3.217 90×10-2 Hydra-TD 1 8.893 49×10-2 1.430 69×10-1 1.409 08×10-1 7.633 48×10-2 -0.67a -0.64 -0.38 0.21 6.928 94×10-2 1.114 53×10-1 1.109 90×10-1 5.998 15×10-2 0.02 0.15 1.28 0.70 3.651 91×10-2 5.853 72×10-2 5.783 47×10-2 3.231 19×10-2 0.18 0.48 0.60 1.05 2 8.955 94×10-2 1.426 38×10-1 1.404 80×10-1 7.530 31×10-2 -1.22 -0.78 -0.45 0.44 6.978 08×10-2 1.111 12×10-1 1.109 57×10-1 5.920 75×10-2 -0.40 0.00 1.46 1.01 3.683 50×10-2 5.849 44×10-2 5.779 08×10-2 3.205 69×10-2 0.37 0.91 1.11 2.08 3 8.849 48×10-2 1.430 54×10-1 1.408 86×10-1 7.471 50×10-2 0.30 -0.53 -0.22 1.69 6.895 78×10-2 1.114 57×10-1 1.109 90×10-1 5.880 21×10-2 1.34 0.22 1.41 2.04 3.683 92×10-2 5.931 02×10-2 5.859 74×10-2 3.231 69×10-2 -0.11 -0.98 -0.80 0.43 4 8.614 65×10-2 1.428 87×10-1 1.407 19×10-1 7.390 26×10-2 -5.38 -0.36 -0.16 -0.73 6.713 29×10-2 1.113 35×10-1 1.109 77×10-1 5.823 73×10-2 -4.49 0.27 1.59 -0.05 3.674 54×10-2 6.055 55×10-2 5.983 02×10-2 3.290 58×10-2 -0.55 4.11 4.43 4.81
Table 3. Calculated power feature of S2-300 experiment
View tableView in ArticleTable 3. Calculated power feature of S2-300 experiment
实验值Experiment 计算值Calculated C/E 峰值裂变率Peak Fission rate / s-1 1.7×1016 2.08×1016 1.22 第一裂变峰总裂变次数Total fission count during first fission peak 4.2×1016 4.61×1016 1.10 峰值前裂变次数Fission count before peak 1.3×1016 1.28×1016 0.98 功率倍增时间Doubling time of power / s 0.130 0.125 0.96 功率峰出现时间Peak time/ s 9.5 9.17
Tools
Get Citation
Copy Citation Text
Huabei YIN, Yongping WANG, Junli GOU, Guoming LIU, Tiejun ZU, Wen YIN, Youqi ZHENG, Xianan DU. Critical safety analysis method of spent fuel solution system[J]. NUCLEAR TECHNIQUES, 2023, 46(1): 010601
Paper Information
Category: Research Articles
Received: Apr. 20, 2022
Accepted: --
Published Online: Feb. 17, 2023
The Author Email: WANG Yongping (wangyongping0627@xjtu.edu.cn)
© Copyright 2018-2021 | Chinese Laser Press.
All Rights Reserved 沪ICP备15018463号-20