Published 1997
| Version v1
Book
Model experiments BERDA describing the impact of molten core material against a PWR vessel head
Creators
- 1. Institut fuer Reaktorsicherheit, Karlsruhe (Germany)
Description
The experiments investigate mechanical effects of a postulated in-vessel steam explosion. The geometry including the liquid slug and the vessel head is scaled down 1:10. Six tests are reported, two tests with a slug of lead spheres, one test with a solid projectile, and three tests with slugs of liquid metal. The results indicate that for slugs of lead spheres and liquid metal the impact forces are reduced to about one quarter of the force caused by a solid projectile. In those tests where the load carrying capacity was approached, maximum strains of more than 30 % were obtained. 6 refs., 7 figs
Additional details
Publishing Information
- Publisher
- American Nuclear Society, Inc.
- Imprint Place
- La Grange Park, IL (United States)
- Imprint Title
- Proceedings of the international topical meeting on advanced reactors safety: Volume 2
- Imprint Pagination
- 715 p.
- Journal Page Range
- p. 1219-1226.
Conference
- Title
- American Nuclear Society (ANS) international meeting on advanced reactors safety.
- Acronym
- ARS '97
- Dates
- 1-5 Jun 1997.
- Place
- Orlando, FL (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 29021604
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CORIUM; DEFORMATION; IMPACT TESTS; KINETIC ENERGY; MELTDOWN; PRESSURE VESSELS; PWR TYPE REACTORS; STRAINS
- Descriptors DEC
- ACCIDENTS; CONTAINERS; ENERGY; ENRICHED URANIUM REACTORS; MATERIALS TESTING; MECHANICAL TESTS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-970607--Vol.2.