Published 1978
| Version v1
Report
Restricted
LMFBR safety and sodium boiling
Description
Within the U.S. Fast Breeder Reactor Safety R and D Work Breakdown Structure for Line of Assurance 2, Limit Core Damage, the influence of sodium boiling upon the progression and termination of accidents is being studied in loss of flow, transient overpower, loss of piping integrity, loss of shutdown heat removal system and local fault situations. The pertinent analytical and experimental results of this research to date are surveyed and compared with the requirements for demonstrating the effectiveness of this line of assurance. A discussion of specific technical issues concerned with sodium boiling and the need for future development work is also presented
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS., PC A02/MF A01.
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Restricted
The record is publicly accessible, but files are restricted to users with access.
Additional details
Publishing Information
- Imprint Pagination
- 13 p.
- Report number
- CONF-781022--41
Conference
- Title
- ENS/ANS international topical meeting on nuclear power reactor safety.
- Dates
- 16 - 19 Oct 1978.
- Place
- Brussels, Belgium.
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 10461221
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AFTER-HEAT REMOVAL; ATWS; BOILING; COMPUTER CODES; FAILURES; FLOW BLOCKAGE; LMFBR TYPE REACTORS; LOSS OF FLOW; MOCKUP; REACTOR SAFETY; SODIUM; TRANSIENTS
- Descriptors DEC
- ACCIDENTS; ALKALI METALS; BREEDER REACTORS; DESIGN BASIS ACCIDENTS; ELEMENTS; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; LIQUID METAL COOLED REACTORS; METALS; PHASE TRANSFORMATIONS; REACTOR ACCIDENTS; REACTORS; SAFETY; STRUCTURAL MODELS