A study of RELAP5/MOD2 and RELAP5/MOD3 predictions of a small-break loss-of-coolant accident simulation conducted at the ROSA-IV Large-Scale Test Facility
Creators
- 1. EG and G Idaho, Inc., Idaho Falls, ID (United States)
- 2. Texas A and M Univ., College Station, TX (United States). Dept. of Nuclear Engineering
Description
The thermal-hydraulics simulation codes RELAP5/MOD2 and RELAP5/MOD3 are utilized to calculate the phenomena that occurred during a small-break loss-of-coolant accident (LOCA) simulation conducted at the ROSA-IV Large-Scale Test Facility. In this paper the RELAP5/MOD2 and RELAP5/MOD3 predictions are compared with each other and assessed against the experimental results. The overall conclusion is that both code versions predict trends well, but each differs in the prediction of the magnitude and timing of concurrences. Specific areas of difference include primary system pressure, differential pressure in the upper plenum, core liquid level depression and subsequent heatup, core void fraction profile, and the differential pressure in the steam generator inlet plenum. All but the last of these differences are related to the RELAP5/MOD3 prediction of excessive liquid holdup in the upper plenum during the first core liquid depression, which is believed to lead to the prediction of water trickling into the upper core volumes and providing a cooling mechanism not present during the experiment. The liquid holdup is believed to be the result of an overprediction of interphase drag at the junctions between the upper plenum volumes
Additional details
Publishing Information
- Journal Title
- Nuclear Technology
- Journal Volume
- 100
- Journal Issue
- 1
- Journal Page Range
- p. 111-124.
- ISSN
- 0029-5450
- CODEN
- NUTYBB
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 24023087
- Subject category
- S42: ENGINEERING; S99: GENERAL AND MISCELLANEOUS;
- Descriptors DEI
- FORECASTING; HEAT TRANSFER; LOSS OF COOLANT; M CODES; PRESSURE GRADIENTS; R CODES; REACTOR ACCIDENTS; REACTOR CORES; SIMULATION; STEAM GENERATORS; TEST FACILITIES; VOID FRACTION
- Descriptors DEC
- ACCIDENTS; BOILERS; COMPUTER CODES; ENERGY TRANSFER; REACTOR COMPONENTS; VAPOR GENERATORS