Hydrogen and steam distribution following a small-break LOCA in large dry containment

Jian DENG; Xuewu CAO

doi:10.1016/S1001-8042(07)60043-8

Your Location：

Home >

Browse articles >

Hydrogen and steam distribution following a small-break LOCA in large dry containment

MISCELLANEOUS | Updated：2021-01-29

- Hydrogen and steam distribution following a small-break LOCA in large dry containment
- Nuclear Science and Techniques Vol. 18, Issue 3, (2007)
- Affiliations：
  
  1.School of Nuclear Science and Engineering, Shanghai Jiaotong University, Shanghai 200240, China
- Author bio：
  
  E-mail: dengjian@sjtu.edu.cn
- Funds：
- DOI：10.1016/S1001-8042(07)60043-8
  CLC：
Scan for full text
Jian DENG, Xuewu CAO. Hydrogen and steam distribution following a small-break LOCA in large dry containment. [J]. Nuclear Science and Techniques 18(3):181-185(2007)
DOI：

Jian DENG, Xuewu CAO. Hydrogen and steam distribution following a small-break LOCA in large dry containment. [J]. Nuclear Science and Techniques 18(3):181-185(2007) DOI： 10.1016/S1001-8042(07)60043-8.

摘要

Abstract

The hydrogen deflagration is one of the major risk contributors to threaten the integrity of the containment in a nuclear power plant, and hydrogen control in the case of severe accidents is required by nuclear regulations. Based on the large dry containment model developed with the integral severe-accident analysis tool, a small-break loss-of-coolant-accident (LOCA) without HPI, LPI, AFW and containment sprays, leading to the core degradation and large hydrogen generation, is calculated. Hydrogen and steam distribution in containment compartments is investigated. The analysis results show that significant hydrogen deflagration risk exits in the reactor coolant pump (RCP) compartment and the cavity during the early period, if no actions are taken to mitigate the effects of hydrogen accumulation.

关键词

Keywords

Severe accidentSmall-break LOCALarge dry containmentHydrogen distribution

references

Alvares N J, Beason D G, Eidam G R, et al. Transactions of the American Nuclear Society, 1982, 43: 11-12.

Henrie J O, Postma A K. Transactions of the American Nuclear Society, 1982, 43: 12-13.

Sehgal B R. Nuclear Engineering and Design, 2001, 210: 79-94.

Koroll G W, Rohde J, Royen J. Proceedings of the OECD/NEA/CSNI Workshop on the Implementation of Hydrogen Mitigation Techniques, Manitoba, Canada, May 13-15, 1996.

Chen S, Liu X, Shi G. B, et al. Nuclear Power Engineering (in Chinese), 2006, 27(1): 13-17.

Fang L K, Chen S, Zhou Q F. Nuclear Power Engineering (in Chinese), 2006, 27(1): 18-22.

Lin J M, Jia B S, Liu B T. Nuclear Power Engineering (in Chinese), 2005, 25(3): 275-278.

Lin J M, Jia B S, Liu B T. Nuclear Power Engineering (in Chinese), 2005, 26(2): 114-120.

Bachellerie E, Arnould F, Auglaire M, et al. Nuclear Engineering and Design, 2003, 221: 151-165.

Views

Downloads

CSCD

Alert me when the article has been cited

Submit

Tools

Publicity Resources

A novel approach for radionuclide diffusion in the enclosed environment of a marine nuclear reactor during a severe accident

Moving particle semi-implicit simulation on the molten Wood’s metal downward relocation process

Simulation of hydrogen distribution and effect of engineering safety features (ESFs) on its mitigation in a WWER-1000 containment

Creep rupture assessment for Level-2 PSA of a 2-loop PWR: Accounting for phenomenological uncertainties

Numerical analysis of pressure load in a PWR cavity in an ex-vessel steam explosion

Related Author

No data

Related Institution

Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China

Shanghai Nuclear Engineering Research & Design Institute Co.LTD

Hunan Provincial Key Laboratory of Emergency Safety Technology and Equipment for Nuclear Facilities

School of Resource Environment and Safety Engineering, University of South China

Nuclear Physics and Biophysics Research Division, Physics Department, Faculty of Mathematics and Natural Science, Institut Teknologi Bandung, Jalan Ganesha 10

Address：Editorial Office of NST, 2019 Jialuo Road, Jiading, Shanghai 201800, China Postal code：201800
Email：nst@sinap.ac.cn
Technical support is provided by Beijing Founder electronics co., LTD 沪ICP备05005479号-1 京公网安备11010802024621
It is recommended to read the content of this site in Chrome&IE9+. Please switch to extreme mode in browser 360.
Cookies We use cookies to help provide and enhance our service and tailor content. By continuing, you agree to the use of cookies.

⁰