Pebble-Bed High-Temperature Gas-Cooled Reactor Burnup Uncertainty Analysis Based on Fine Burnup History and Fine Burnup Chains

被引:0
|
作者
Cui M. [1 ]
Guo J. [1 ]
Wang Y. [1 ]
Liu B. [1 ]
Kong B. [1 ]
Zhu K. [1 ]
Li F. [1 ]
机构
[1] Key Laboratory of Advanced Reactor Engineering and Safety of Ministry of Education, Collaborative Innovation Center of Advanced Nuclear Energy Technology, Institute of Nuclear and New Energy Technology, Tsinghua University, Beijing
来源
关键词
Burnup uncertainty analysis; Fine burnup calculation; NUIT; PB-HTGR;
D O I
10.13832/j.jnpe.2023.02.0009
中图分类号
学科分类号
摘要
The fuel element burnup history becomes extremely complex as a result of the multipass of the fuel pebble through the reactor core in fuel management of the pebble-bed high-temperature gas-cooled reactor (PB-HTGR). The core physical design program VSOP of PB-HTGR can provide a fine burnup history of fuel elements, but it involves only a small number of burn-up chains and nuclide species. The burnup calculation program NUIT developed independently by Tsinghua University can realize fine burnup calculation and contains complete burnup chain and nuclide information, but it cannot track the fine burnup history. In this paper, we will develop the fine burnup calculation function of PB-HTGR based on NUIT and the fine burnup history of PB-HTGR provided by VSOP, build a burnup analysis process with fine burnup history simulation and fine burnup chain nuclides and realize a burnup uncertainty analysis function. On this basis, the contribution of fission yield uncertainty to the burnup calculation contribution of PB-HTGR is studied, and the results are compared with the VSOP calculation results. The calculation and analysis results show that the fine burnup calculation results based on NUIT and the burnup calculation results based on VSOP are mutually verified, and more nuclide information can be obtained. Such calculation results can be used as a basis for the decay heat uncertainty study of PB-HTGR. © 2023 Yuan Zi Neng Chuban She. All rights reserved.
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页码:9 / 14
页数:5
相关论文
共 8 条
  • [1] (2021)
  • [2] RUTTEN H J., (99/05) Computer code system for reactor physics and fuel cycle simulation, (2005)
  • [3] GUO J, WANG Y Z, ZHANG H, Et al., Challenges and progress of uncertainty analysis for the pebble-bed high-temperature gas-cooled reactor, Progress in Nuclear Energy, 138, (2021)
  • [4] WANG Y Z, CUI M L, GUO J, Et al., Lognormal-based sampling for fission product yields uncertainty propagation in pebble-bed HTGR, Science and Technology of Nuclear Installations, 2020, (2020)
  • [5] REARDEN B T, JESSEE M A., SCALE code system: TN 37831-6283, (2016)
  • [6] (2021)
  • [7] 12, 1, (2021)
  • [8] ZU T J, LU Z R, HAN F L, Et al., Uncertainty analysis of infinite multiplication factor and nuclide number density based on the UAM-PWR benchmark with respect to cross sections, fission yields and decay half-life, Annals of Nuclear Energy, 165, (2022)