CFD Application to Hydrogen Risk Analysis and PAR Qualification
Creators
Description
A three dimensional computation fluid dynamics (CFD) code, GASFLOW, is applied to analyze the hydrogen risk for Qinshan‐II nuclear power plant (NPP). In this paper, the effect of spray modes on hydrogen risk in the containment during a large break loss of coolant accident (LBLOCA) is analyzed by selecting three different spray strategies, that is, without spray, with direct spray and with both direct and recirculation spray. A strong effect of spray modes on hydrogen distribution is observed. However, the efficiency of the passive auto‐catalytic recombiners (PAR) is not substantially affected by spray modes. The hydrogen risk is significantly increased by the direct spray, while the recirculation spray has minor effect on it. In order to simulate more precisely the processes involved in the PAR operation, a new PAR model is developed using CFD approach. The validation shows that the results obtained by the model agree well with the experimental results.
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10.1155_2009_213981.pdf
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Additional details
Identifiers
- DOI
- 10.1155/2009/213981;
- Crossref Funder ID
- 10.13039/501100012166;
Publishing Information
- Journal Title
- Science and Technology of Nuclear Installations
- Journal Volume
- 2009
- Journal Issue
- 1
- ISSN
- 1687-6075
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- A CODES; CALCULATION METHODS; COMPUTER CALCULATIONS; COMPUTERIZED SIMULATION; CONTAINMENT; FLUID MECHANICS; HYDROGEN; LBLOCA; NUCLEAR POWER PLANTS; QINSHAN-1 REACTOR; QINSHAN-2-1 REACTOR; QINSHAN-3-1 REACTOR; RECOMBINERS; RISK ASSESSMENT; SAFETY INJECTION; VALIDATION
- Descriptors DEC
- ACCIDENTS; CANDU TYPE REACTORS; COMPUTER CODES; ELEMENTS; ENRICHED URANIUM REACTORS; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; LOSS OF COOLANT; MECHANICS; NONMETALS; NUCLEAR FACILITIES; PHWR TYPE REACTORS; POWER PLANTS; POWER REACTORS; PRESSURE TUBE REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTORS; SIMULATION; TESTING; THERMAL POWER PLANTS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Copyright
- © Author(s)
- Contract/Grant/Project number
- 2007CB209800
- Notes
- Record automatically processed
- Funding organization
- National Basic Research Program of China