Published August 1995
| Version v1
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Hydrogen transport in the containment
Creators
Description
For the description of transport phenomena in water vapor/hydrogen mixtures released in nuclear meltdown accidents, an integrated analytical model is being developed for LWR containments. Thermal and mechanical loads due to recombination and combustion are to be calculable. The 3-dimensional GASFLOW code was taken over from LANL in exchange for HDR experimental results and Battelle BMC program results. (orig.)
Files
Additional details
Additional titles
- Original title (German)
- Wasserstofftransport im Containment
Publishing Information
- Imprint Title
- Karlsruhe Research Center, Nuclear Safety Research Project (PSF). Annual report 1994
- Imprint Pagination
- 433 p.
- Journal Page Range
- p. 1-18.
- ISSN
- 0947-8620
- Report number
- FZKA--5600
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- Germany
- INIS RN
- 28005585
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BWR TYPE REACTORS; COMPUTERIZED SIMULATION; CONTAINMENT; HYDROGEN; MELTDOWN; PWR TYPE REACTORS; THREE-DIMENSIONAL CALCULATIONS; VALIDATION
- Descriptors DEC
- ACCIDENTS; ELEMENTS; ENRICHED URANIUM REACTORS; NONMETALS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; SIMULATION; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Imprint:Forschungszentrum Karlsruhe, Projekt Nukleare Sicherheitsforschung. Jahrsbericht 1994.