严重事故工况下反应堆热工水力参数对源项释放行为影响研究

您当前的位置：

首页 >

文章列表页 >

严重事故工况下反应堆热工水力参数对源项释放行为影响研究

更新时间：2025-07-09

- 严重事故工况下反应堆热工水力参数对源项释放行为影响研究
- Issue 3, Pages: 25-37(2024)
- 作者机构：
  
  1. 西安交通大学能源与动力工程学院
  2. 西安交通大学动力工程多相流国家重点实验室
- 作者简介：
- 基金信息：
- DOI：
  CLC： TL364.4;TL33
- Published：2024
- 稿件说明：
移动端阅览
[J]. 2024, (3): 25-37.
DOI：

[J]. 2024, (3): 25-37. DOI：

摘要

为了进一步研究反应堆严重事故进程中热工参数对源项释放的影响，识别对其影响较大的物理过程，从而进一步改进和发展数值模型以提高计算精度降低不确定性，以第三代压水堆为对象，利用一体化严重事故分析程序ISAA对大破口失水事故导致的严重事故开展了数值分析研究，并基于Wilks公式利用自主开发的不确定性程序代码SAUP对17个热工参数进行了拉丁超立方抽样(LHS)执行批量计算，对目标输出(FoM)即氢气与裂变产物的释放进行了不确定性与敏感性分析。结果表明：在热工参数的不确定性范围内，氧化产氢以及裂变产物的释放呈现正态分布且存在较大的不确定带，包壳氧化层的失效温度、堆芯碎片尺寸以及碎片孔隙率对高挥发性裂变产物的释放有较为显著的相关性。该研究有助于理解反应堆严重事故中热工参数与源项之间的复杂联系，同时对核电厂安全系统的设计以及严重事故的预防与缓解具有参考意义。

Abstract

关键词

Keywords

references

Malicki Mateusz,Lind Terttaliisa.Parametric MELCOR 2.2 sensitivity and uncertainty study with a focus on aerosols based on Phébus test FPT1[J].Progress in Nuclear Energy,2023.

Gao Pengcheng,Yang Hao,Zhang Bin,SHAN Jianqiang.Development of PWR lower head failure model for severe accident analysis[J].Nuclear Engineering and Design,2023.

Li Jishen,Zhang Bin.Influence of active and passive equipment for advanced pressurized water reactor on thermal hydraulic and source term behavior in severe accidents[J].Energy Storage and Saving,2023.

Wang Wanhong,Ma Weimin.Bootstrapped artificial neural network model for uncertainty analysis in MELCOR simulation of severe accident[J].Progress in Nuclear Energy,2023.

Choi Wonjun,Ahn Kwang-Il,Kim Sung Joong.Effect of mitigation strategies in the severe accident uncertainty analysis of the OPR1000 short-term station blackout accident[J].Nuclear Engineering and Technology,2022.

Wang Wanhong,Chen Yangli,Ma Weimin.Application of uncertainty analysis methods to MELCOR simulation of postulated severe accidents in a Nordic BWR[J].Nuclear Engineering and Design,2022.

Ahn Kwang-Il,Park Soo-Yong.Best-practice severe accident uncertainty and sensitivity analysis for a short-term SBO sequence of a reference PWR using MAAP5[J].Annals of Nuclear Energy,2022.

Li Xiaoyu,Li Chuhao,Hu Yang,Yu Yongqi,Zeng Wenjie,Wu Haibiao.Uncertainty quantification of the power control system of a small PWR with coolant temperature perturbation[J].Nuclear Engineering and Technology,2022.

Šadek Siniša,Grgić Davor,Allison Chris,PerezFerragut Marina.Uncertainty Study of the In-Vessel Phase of a Severe Accident in a Pressurized Water Reactor[J].Energies,2022.

Elsalamouny Noura,Kaliatka Tadas.Uncertainty Quantification of the PHEBUS FPT-1 Test Modelling Results[J].Energies,2021.

Liu Yinuo,Jiang Qingfeng,Yang Chao,Zeng Wenjie,Cai Manbo.Uncertainty analysis of reactivity feedback coefficient for LFR core power control system during reactivity insertion accident[J].Annals of Nuclear Energy,2021.

Zhao Nan,Chen Yangli,Ma Weimin,Bechta Sevostian,Isaksson Patrick.A nodal sensitivity study of MELCOR simulation for severe accidents in a pressurized water reactor[J].Annals of Nuclear Energy,2021.

Tiborcz Livia,Hollands Thorsten.Uncertainty and sensitivity analysis of the Phébus FPT3 test[J].Nuclear Engineering and Design,2021.

Darnowski Piotr,Mazgaj Piotr,Włostowski Mateusz.Uncertainty and Sensitivity Analysis of the In-Vessel Hydrogen Generation for Gen-III PWR and Phebus FPT-1 with MELCOR 2.2[J].Energies,2021.

Gharari R.,Kazeminejad H.,Mataji Kojouri N.,Hedayat A.,Hassan Vand M..Application of a severe accident code to the sensitivity and uncertainty analysis of hydrogen production in the WWER1000/V446[J].Annals of Nuclear Energy,2021.

F. Sanchez-Saez,A.I. Sánchez,J.F. Villanueva,S. Carlos,S. Martorell.Uncertainty analysis of a large break loss of coolant accident in a pressurized water reactor using non-parametric methods[J].Reliability Engineering and System Safety,2018.

Seokwon Whang,Hyun Sun Park,Kiyofumi Moriyama,Kukhee Lim,Young Jin Cho,Moo Hwan Kim.Uncertainty analysis of in-vessel retention in a high power reactor during severe accident[J].Nuclear Engineering and Design,2017.

Siniša Šadek,Davor Grgić,Zdenko Šimić.Application of ASTEC, MELCOR, and MAAP Computer Codes for Thermal Hydraulic Analysis of a PWR Containment Equipped with the PCFV and PAR Systems[J].Science and Technology of Nuclear Installations,2017.

K. Chevalier-Jabet,F. Cousin,L. Cantrel,C. Séropian.Source term assessment with ASTEC and associated uncertainty analysis using SUNSET tool[J].Nuclear Engineering and Design,2014.

Kwang-Il Ahn,Sun-Hee Park,Hee-Dong Kim,Hyun Sun Park.The plant-specific uncertainty analysis for an ex-vessel steam explosion-induced pressure load using a TEXAS–SAUNA coupled system[J].Nuclear Engineering and Design,2012.

M. Perez,F. Reventos,L. Batet,A. Guba,I. Tóth,T. Mieusset,P. Bazin,A. de Crécy,S. Borisov,T. Skorek,H. Glaeser,J. Joucla,P. Probst,A. Ui,B.D. Chung,D.Y. Oh,R. Pernica,M. Kyncl,J. Macek,A. Manera,J. Freixa,A. Petruzzi,F. D’Auria,A. Del Nevo.Uncertainty and sensitivity analysis of a LBLOCA in a PWR Nuclear Power Plant: Results of the Phase V of the BEMUSE programme[J].Nuclear Engineering and Design,2011.

Wilks S. S..Statistical Prediction with Special Reference to the Problem of Tolerance Limits[J].The Annals of Mathematical Statistics,1942(4).

李玉,楚武利,姬田园.叶片安装角偏差对动叶性能影响的不确定性研究[J].西安交通大学学报,2023(04).

姬成,黄兆骞,席光.离心叶轮非轴对称轮盘面气动敏感性分析[J].西安交通大学学报,2023(02).

杨皓,张斌,高鹏程,唐绍伟,单建强.反应堆压力容器下封头热蠕变模型的开发及在OLHF实验分析中的应用[J].核技术,2022(08).

张恒,刘雷,刘立军.非均匀入流对CAP1400核主泵内流及性能的影响研究[J].西安交通大学学报,2023(02).

袁璐,曹学武.核电厂严重事故下氢气源项的不确定性分析[J].原子能科学技术,2021(11).

别朝红,潘超琼,陈叶,李芙蓉.能源转型下新能源电力系统概率风险评估[J].西安交通大学学报,2021(07).

黄明,李军,李志刚,宋立明.动叶凹槽状叶顶气膜冷却有效度和气动性能不确定性量化研究[J].西安交通大学学报,2021(05).

Omid Noori-kalkhoran,Najmeh Jafari-ouregani,Massimiliano Gei,Rohollah Ahangari.Simulation of hydrogen distribution and effect of Engineering Safety Features (ESFs) on its mitigation in a WWER-1000 containment[J].Nuclear Science and Techniques,2019(06).

Sh.Sheykhi,S.Talebi,M.Soroush,E.Masoumi.Thermal-hydraulic and stress analysis of AP1000 reactor containment during LOCA in dry cooling mode[J].Nuclear Science and Techniques,2017(06).

苟军利,单建强,胡宏伟,曹建华,沈永刚.先进安注箱热工水力特性研究[J].西安交通大学学报,2015(11).

Views

下载量

CSCD

Alert me when the article has been cited

提交

Tools

Publicity Resources

CO2-H2O双循环燃煤发电系统仿真研究

高压环境下高炉煤气化学反应机理敏感性分析及机理简化

Electrothermal Coupling Research on the Evolutionary Law of Anti-Corona Performance for High-Altitude Air-Cooled Generators

A Structure-Semantics-Residual Collaborative Image Compression Framework：Towards Privacy Protection and High-Fidelity Reconstruction

Study on the Thermodynamic Properties in the Anomalous Region of Supercritical Water

Related Author

冯雪佳

陈敏

吴君

王春国

王顺森

杨诏

李祥晟

Related Institution

武汉第二船舶设计研究所

西安交通大学叶轮机械研究所

⁰