Analysis of in-vessel hydrogen source term during severe accident induced by SB-LOCA
Creators
- 1. School of Mechanical and Power Engineering, Shanghai Jiaotong University, Shanghai (China)
Description
With an integral severe accident analysis computer code, severe accident sequences induced by small-break loss-of-coolant accident (SB-LOCA) in Daya Bay Nuclear Power Plant (900 MWe PWR NPP) are calculated. The impacts of different sizes and locations on the progression of accident and the generation of the in-vessel hydrogen source term are analyzed in this paper. The results are summarized as follows: A mass of in-vessel hydrogen source generates at oncoming and initial stage of core melting; The amount of in-vessel hydrogen source term is with obscure relation to the break size, and with many different sizes of breaks, the amount of in-vessel hydrogen source term distributes in a small area, and the average amount of the hydrogen production is about 500 kg; The location of break has a small impact on the generation of the hydrogen source term. (authors)
Additional details
Publishing Information
- Journal Title
- Nuclear Power Engineering
- Journal Volume
- 29
- Journal Issue
- 2
- Journal Page Range
- p. 88-91, 101
- ISSN
- 0258-0926
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 43075158
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- COMPUTER CODES; DAYA BAY-1 REACTOR; HYDROGEN; LOSS OF COOLANT; MASS; MELTING; NUCLEAR POWER PLANTS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR VESSELS; SOURCE TERMS
- Descriptors DEC
- ACCIDENTS; CONTAINERS; ELEMENTS; ENRICHED URANIUM REACTORS; NONMETALS; NUCLEAR FACILITIES; PHASE TRANSFORMATIONS; POWER PLANTS; POWER REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTORS; THERMAL POWER PLANTS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 7 figs., 2 tabs., 2 refs.