Results of recent NUPEC hydrogen related tests
Creators
Description
Nuclear Power Engineering Center (NUPEC) started NUPEC Containment Integrity project entitled Proving Test on the Reliability for Reactor Containment Vessel in June, 1987. Based on the test results, computer codes are verified and as the result of analysis and evaluation by the computer codes, containment integrity is to be confirmed. This paper indicates the results of hydrogen mixing and distribution test and hydrogen burning test. A comparison of the NUPEC data with previously performed FITS test data at SNL is presented in terms of the peak combustion pressure normalized with respect to the initial pressure. The NUPEC data are in good agreement with the FITS data which were obtained at the lower hydrogen concentration condition. New data bases have been added in the higher hydrogen concentration by the NUPEC data
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Additional details
Publishing Information
- Imprint Title
- Transactions of the nineteenth water reactor safety information meeting
- Imprint Pagination
- 220 p.
- Journal Page Range
- p. 4.9.
- Report number
- NUREG/CP--0118
Conference
- Title
- 19. Nuclear Regulatory Commission (NRC) water reactor safety information meeting.
- Dates
- 28-30 Oct 1991.
- Place
- Bethesda, MD (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 23059431
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BWR TYPE REACTORS; COMBUSTION; COMPUTER CODES; COMPUTERIZED SIMULATION; CONTAINMENT SPRAY SYSTEMS; CONTAINMENT SYSTEMS; EXPLOSIONS; HYDROGEN; JAPAN; JAPANESE ORGANIZATIONS; MITIGATION; NITROGEN; PWR TYPE REACTORS; REACTOR CORE DISRUPTION; REACTOR SAFETY; REACTOR SAFETY EXPERIMENTS; RELIABILITY; STEAM; VERIFICATION
- Descriptors DEC
- ACCIDENTS; ASIA; CHEMICAL REACTIONS; CONTAINMENT; DEVELOPED COUNTRIES; ELEMENTS; ENGINEERED SAFETY SYSTEMS; ENRICHED URANIUM REACTORS; NATIONAL ORGANIZATIONS; NONMETALS; OXIDATION; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; SAFETY; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-911079--.