Results and implications of the EBR-II inherent safety demonstration tests
Creators
- 1. Argonne National Lab., IL (USA)
Description
On April 3, 1986 two milestone tests were conducted in EBR-II. The first test was a loss of flow without scram and the second was a loss of heat sink without scram. Both tests were initiated from 100% power and in both tests the reactor was shut down passively-by natural processes, principally thermal expansion-without automatic scram, operator intervention, or the help of special in-core devices. The temperature transients during the tests were mild, as predicted, and there was no damage to the core or reactor plant structures. In a general sense, therefore, the tests plus supporting analysis demonstrated the feasibility of inherent passive shutdown for undercooling accidents in metal-fueled LMRs. The results provide a technical basis for future experiments in EBR-II to demonstrate inherent safety for transient overpower accidents and to provide additional data for validation of computer codes used for design and safety analysis of inherently safe reactor plants
Additional details
Publishing Information
- Publisher
- Societe Francaise d'Energie Nucleaire.
- Imprint Place
- Paris (France)
- Imprint Title
- Advances in Reactor Physics, Mathematics and Computation. Volume 2
- Imprint Pagination
- 597 p.
- Journal Page Range
- p. 921-936.
Conference
- Title
- International Topical Meeting on Advances in Reactor Physics, Mathematics and Computation.
- Dates
- 27-30 Apr 1987.
- Place
- Paris (France).
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 22060953
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- EBR-2 REACTOR; FLUID FLOW; LOSS OF FLOW; N CODES; POWER DISTRIBUTION; REACTIVITY; REACTOR SAFETY EXPERIMENTS; SAFETY ANALYSIS; TIME DEPENDENCE
- Descriptors DEC
- ACCIDENTS; BREEDER REACTORS; COMPUTER CODES; DISTRIBUTION; EPITHERMAL REACTORS; EXPERIMENTAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; LIQUID METAL COOLED REACTORS; LMFBR TYPE REACTORS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; RESEARCH AND TEST REACTORS; SODIUM COOLED REACTORS; SPATIAL DISTRIBUTION
Optional Information
- Contract/Grant/Project number
- Contract W-31-109-Eng-38