Counterpart tests of SBLOCA on the effect of break location with the ATLAS. DVI nozzle versus cold-leg breaks
- 1. Korea Atomic Energy Research Inst., Daejeon (Korea, Republic of)
Description
Results from two integral effect tests were compared to discuss the effect of break location between the direct vessel injection (DVI) nozzle and cold leg during the small-break loss of coolant accident (SBLOCA) scenario. One is the SB-DVI-09 test for a 6-inch (50% break area of a DVI nozzle) DVI line break and the other is the SB-CL-06 test for an equivalent break size of cold leg. Both counterpart tests were performed with the same control logic and initial/boundary conditions except for different break locations of the DVI line and cold leg. Experimental results showed that the maximum heater surface temperature increased more with the broken DVI nozzle (SB-DVI-09) than with the broken cold leg (SB-CL-06) due to the delayed and simultaneous occurrence of the loop seal clearing and the momentary decrease in the collapsed water level in the core region. (author)
Availability note (English)
Available from http://dx.doi.org/10.3327/jnst.48.1319Additional details
Identifiers
- DOI
- 10.3327/jnst.48.1319;
Publishing Information
- Journal Title
- Journal of Nuclear Science and Technology (Tokyo)
- Journal Volume
- 48
- Journal Issue
- 10
- Journal Page Range
- p. 1319-1326
- ISSN
- 0022-3131
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 43027358
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- COMPARATIVE EVALUATIONS; COOLANT LOOPS; HYPOTHETICAL ACCIDENTS; INJECTION; LOSS OF COOLANT; NOZZLES; PWR TYPE REACTORS; REACTOR ACCIDENT SIMULATION; REACTOR SAFETY; RUPTURES; TEST FACILITIES; THERMAL HYDRAULICS
- Descriptors DEC
- ACCIDENTS; COOLING SYSTEMS; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; EVALUATION; FAILURES; FLUID MECHANICS; HYDRAULICS; INTAKE; MECHANICS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; SAFETY; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 13 refs., 9 figs., 4 tabs.