Effect of water injection on hydrogen generation during severe accident in PWR

被引:0
作者
TAO Jun CAO Xuewu School of Mechanical and Power Engineering Shanghai Jiao Tong University Shanghai China [200240 ]
机构
关键词
Pressurized water reactor (PWR); Severe accident; Core damage state; Depressurization; Water injection; Hydrogen generation; Steam starvation;
D O I
10.13538/j.1001-8042/nst.20.312-316
中图分类号
TL421.1 [];
学科分类号
082703 ;
摘要
Effect of water injection on hydrogen generation during severe accident in a 1000 MWe pressurized water reactor was studied. The analyses were carried out with different water injection rates at different core damage stages. The core can be quenched and accident progression can be terminated by water injection at the time before cohesive core debris is formed at lower core region. Hydrogen generation rate decreases with water injection into the core at the peak core temperature of 1700 K, because the core is quenched and reflooded quickly. The water injection at the peak core temperature of 1900 K, the hydrogen generation rate increases at low injection rates of the water, as the core is quenched slowly and the core remains in uncovered condition at high temperatures for a longer time than the situation of high injection rate. At peak core temperature of 2100–2300 K, the Hydrogen generation rate increases by water injection because of the steam serving to the high temperature steam-starved core. Hydrogen generation rate increases significantly after water injection into the core at peak core temperature of 2500 K because of the steam serving to the relocating Zr-U-O mixture. Almost no hydrogen generation can be seen in base case after formation of the molten pool at the lower core region. However, hydrogen is generated if water is injected into the molten pool, because steam serves to the crust supporting the molten pool. Reactor coolant system (RCS) depressurization by opening power operated relief valves has important effect on hydrogen generation. Special attention should be paid to hydrogen generation enhancement caused by RCS depressurization.
引用
收藏
页码:312 / 316
页数:5
相关论文
共 50 条
[21]   Vessel Failure Analysis of a Boiling Water Reactor During a Severe Accident [J].
Wang, H. D. ;
Chen, Y. L. ;
Villanueva, W. .
FRONTIERS IN ENERGY RESEARCH, 2022, 10
[22]   NATURAL CIRCULATION AND CREEP DAMAGE ANALYSES OF SEVERE ACCIDENT FOR A TYPICAL PWR PLANT [J].
Kawabata, Osamu ;
Ogino, Masao .
PROCEEDINGS OF THE 17TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, VOL 2, 2009, :395-402
[23]   Severe accident analysis induced by secondary pipeline break in a small modular PWR [J].
Bi, Xiaolong ;
Chen, Jie ;
Sun, Peiwei ;
Wei, Xinyu .
NUCLEAR ENGINEERING AND TECHNOLOGY, 2024, 56 (10) :4263-4279
[24]   Example of PWR Severe Accident Sensitivity and Uncertainty Analyses Using MELCOR Code [J].
Malicki, M. ;
Lind, T. .
NUCLEAR TECHNOLOGY, 2025,
[25]   Uncertainty Quantification Using the MAAP5 Code of In-Vessel Hydrogen Generation in a Severe Accident at an Advanced Boiling Water Reactor [J].
Wang, Te-Chuan ;
Lee, Min .
NUCLEAR TECHNOLOGY, 2020, 206 (03) :414-427
[26]   PRELIMINARY ANALYSIS OF EFFECT OF THE INTENTIONAL DEPRESSURIZATION ON FISSION PRODUCT BEHAVIOR DURING TMLB' SEVERE ACCIDENT [J].
Huang Gaofeng ;
Tong Lili ;
Cao Xuewu .
PROCEEDINGS OF THE 17TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, VOL 2, 2009, :421-425
[27]   Analysis of primary side bleed and feed actions for severe accident management following total loss of feed water in a Swedish PWR [J].
Zhao, Nan ;
Ma, Weimin ;
Bechta, Sevostian .
ANNALS OF NUCLEAR ENERGY, 2022, 167
[28]   REVIEW ON WATER RADIOLYSIS IN THE FUKUSHIMA DAIICHI ACCIDENT - POTENTIAL CAUSE OF HYDROGEN GENERATION AND EXPLOSION [J].
Saji, Genn .
PROCEEDINGS OF THE 22ND INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING - 2014, VOL 1, 2014,
[29]   Core cooling in pressurized-water reactor during water injection [J].
TAO Jun LI Jingxi TONG Lili CAO Xuewu School of Mechanical EngineeringShanghai Jiao Tong UniversityShanghai China .
Nuclear Science and Techniques, 2011, 22 (01) :60-64
[30]   Research on severe accident diagnosis method based on PCA and DT for a small modular PWR [J].
Bi, Xiaolong ;
Sun, Peiwei ;
Wei, Xinyu .
NUCLEAR ENGINEERING AND DESIGN, 2025, 442