Published 1986
| Version v1
Book
Significant safety research results of the REBEKA program on fuel behavior in a LOCA
Creators
- 1. Kernforschungszentrum Karlsruhe, Institut fur Reaktorbauelemente, Postfach 3640, 7500 Karlsruhe 1
Description
The dominant effects which ensure core coolability of a PWR during refill and reflood of a LOCA are described on the basis of the REBEKA test results. Topics considered in this paper include reactor safety experiments, fuel elements, reactor cores, and reactor cooling systems
Additional details
Publishing Information
- Publisher
- American Nuclear Society.
- Imprint Place
- La Grange Park, IL (USA)
- ISBN
- 0-89448-121-5
- Imprint Title
- Proceedings of the international ANS/ENS topical meeting on thermal reactor safety
- Journal Page Range
- p. XXIX4.1-XXIX4.7.
Conference
- Title
- International ANS/ENS topical meeting on thermal reactor safety.
- Dates
- 2-6 Feb 1986.
- Place
- San Diego, CA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 18080582
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S99: GENERAL AND MISCELLANEOUS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COOLING; FUEL ELEMENTS; LOSS OF COOLANT; PWR TYPE REACTORS; R CODES; REACTOR COOLING SYSTEMS; REACTOR CORES; REACTOR SAFETY EXPERIMENTS
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; COOLING SYSTEMS; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS