Multiloop integral system test (MIST): Test Group 34, Steam generator tube rupture
Creators
- 1. Babcock and Wilcox Co., Lynchburg, VA (USA). Nuclear Power Div.
Description
The multiloop integral system test (MIST) is part of a multiphase program started in 1983 to address small-break loss-of-coolant accidents (SBLOCAs) specific to Babcock and Wilcox designed plants. MIST is sponsored by the US Nuclear Regulatory Commission, the Babcock ampersand Wilcox Owners Group, the Electric Power Research Institute, and Babcock and Wilcox. The unique features of the Babcock and Wilcox design, specifically the hot leg U-bends and steam generators, prevented the use of existing integral system data or existing integral facilities to address the thermal-hydraulic SBLOCA questions. MIST and two other supporting facilities were specifically designed and constructed for this program, and an existing facility--the Once Through Integral System (OTIS)--was also used. Data from MIST and the other facilities will be used to benchmark the adequacy of system codes, such as RELAP5 and TRAC, for predicting abnormal plant transients. The MIST program is reported in 11 volumes. The program is summarized in Volume 1; Volumes 2 through 8 describes groups of tests by test type; Volume 9 presents inter-group comparisons; Volume 10 provides comparisons between the calculations of RELAP5/MOD2 and MIST observations, and Volume 11 presents the later Phase 4 tests. This Volume 6 pertains to Test Group 34, Steam Generator Tube Rupture. The specifications, conduct, observations, and results of these tests are described. 6 refs., 189 figs., 16 tabs
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS, PC E13/MF E02 - GPO as TI90001686; OSTI; INIS.
Files
Additional details
Additional titles
- Subtitle (English)
- Final report: Volume 6
Publishing Information
- Imprint Pagination
- 340 p.
- Report number
- NUREG/CR--5395-Vol.6
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 21019349
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Progress Report
- Descriptors DEI
- COMPUTERIZED SIMULATION; FLUID FLOW; HEAT TRANSFER; HYDRAULICS; LOSS OF COOLANT; MITIGATION; PROGRESS REPORT; PWR TYPE REACTORS; R CODES; REACTOR CONTROL SYSTEMS; REACTOR COOLING SYSTEMS; REACTOR SAFETY; RUPTURES; STEAM GENERATORS; TEST FACILITIES; TESTING; TRANSIENTS; TUBES
- Descriptors DEC
- ACCIDENTS; BOILERS; COMPUTER CODES; CONTROL SYSTEMS; COOLING SYSTEMS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FAILURES; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; SAFETY; SIMULATION; THERMAL REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- This report contains 5 microfiche supplements.
- Secondary number(s)
- EPRI-NP--6480-Vol.6; BAW--2065.