Published January 1983
| Version v1
Report
ROSA-III Program for BWR LOCA/ECCS integral test
- 1. Japan Atomic Energy Research Inst., Tokai-mura, Ibaraki-ken
Description
The Japan Atomic Energy Research Institute (JAERI) initiated the Rig of Safety Assessment Number 3 (ROSA-III) program in 1978 to conduct an integral system effect test of a loss-of-coolant accident (LOCA) in a boiling water reactor (BWR) to study the fundamental thermal-hydraulic phenomena during a LOCA and the effectiveness of the emergency core cooling system (ECCS). The objectives of the ROAS-III program are: (1) to study the BWR LOCA scenario comprehensively varying the test conditions on the break, ECCS and other parameters; (2) to identify any problem area or unexpected phenomena in a BWR LOCA; and (3) to provide experimental data for the computer code assessment
Additional details
Publishing Information
- Imprint Title
- Tenth water reactor safety research information meeting: proceedings. Volume 1
- Journal Page Range
- p. 91-94d.
- Report number
- NUREG/CP--0041-Vol.1
Conference
- Title
- 10. water reactor safety research information conference.
- Dates
- 12-15 Oct 1982.
- Place
- Gaithersburg, MD (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 15049698
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BWR TYPE REACTORS; COMPUTER CODES; ECCS; HEAT TRANSFER; HYDRAULICS; JAERI; LOSS OF COOLANT; PRESSURE VESSELS; PRIMARY COOLANT CIRCUITS; REACTOR ACCIDENTS; REACTOR COOLING SYSTEMS; REACTOR SAFETY; RESEARCH PROGRAMS; SCALE MODELS; TESTING
- Descriptors DEC
- ACCIDENTS; CONTAINERS; COOLING SYSTEMS; ENERGY TRANSFER; JAPANESE ORGANIZATIONS; NATIONAL ORGANIZATIONS; REACTOR COMPONENTS; REACTOR PROTECTION SYSTEMS; REACTORS; SAFETY; STRUCTURAL MODELS; WATER COOLED REACTORS; WATER MODERATED REACTORS