MIST final report
- 1. Babcock and Wilcox Co., Alliance, OH (United States)
Description
The multiloop integral system test (MIST) was part of a multiphase program started in 1983 to address small-break loss-of-coolant accidents (SBLOCAs) specific to Babcock ampersand Wilcox-designed plants. MIST was sponsored by the US Nuclear Regulatory Commission, the Babcock ampersand Wilcox Owners Group, the Electric Power Research Institute, and Babcock ampersand Wilcox. The unique features of the Babcock ampersand Wilcox design, specifically the hot leg U-bends and steam generators, prevented the use of existing integral system data or existing integral system facilities to addresss the thermal-hydraulic SBLOCA questions. MIST was specifically designed and constructed for this program, and an existing facility -- the once-through integral system (OTIS) -- was also used. Data from MIST and OTIS are used to benchmark the adequacy of system codes, such as RELAP5 and TRAC, for predicting abnormal plant transients. The MIST program is reported in eleven volumes; Volumes 2 through 8 pertain to groups of Phase 3 tests by type, Volume 9 presents inter-group comparisons. Volume 10 provides comparisons between the RELAP5 MOD2 calculations and MIST observations, and Volume 11 (with addendum) presents the later, Phase 4 tests. This is Volume 1 of the MIST final report, a summary of the entire MIST program. Major topics include: test advisory grop (TAG) issues; facility scaling and design; test matrix; observations; comparisons of RELAP5 calculations to MIST observations; and MIST versus the TAG issues. 11 refs., 29 figs., 9 tabs
Availability note (English)
Research Reports Center, PO Box 50490, Palo Alto, CA 94303.Additional details
Additional titles
- Subtitle (English)
- Volume 1, Summary
Publishing Information
- Imprint Pagination
- 171 p.
- Report number
- EPRI-NP--6480-Vol.1
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 23008750
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Numerical Data, Non-conventional Literature
- Descriptors DEI
- AFTER-HEAT REMOVAL; BWR TYPE REACTORS; EXPERIMENTAL DATA; HEAT TRANSFER; HIGH PRESSURE COOLANT INJECTIO; HYDRAULICS; LOSS OF COOLANT; PRESSURE DROP; PUMPS; PWR TYPE REACTORS; R CODES; REACTOR SAFETY; SCALE MODELS; SCALING LAWS; STEAM GENERATORS; T CODES; TEST FACILITIES; TRANSIENTS; TUBES
- Descriptors DEC
- ACCIDENTS; BOILERS; COMPUTER CODES; DATA; ECCS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; EQUIPMENT; INFORMATION; NUMERICAL DATA; POWER REACTORS; REACTOR ACCIDENTS; REACTOR PROTECTION SYSTEMS; REACTORS; REMOVAL; SAFETY; STRUCTURAL MODELS; THERMAL REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Funding organization
- Electric Power Research Inst., Palo Alto, CA (United States).