Analysis of two small break loss-of-coolant experiments in the BETHSY facility using RELAP5/MOD3
- EG and G Idaho, Inc., Idaho Falls, ID (United States)
- Korea Atomic Energy Research Inst., Daebuk (Korea, Republic of)
Small break loss-of-coolant accident (SBLOCA) data were recorded during tests 9.lb and 6.2 TC in the Boucle d`Etudes Thermohydrouliques Systeme (BETHSY) facility at the Centre d`Etudes Nucleares de Grenoble (CENG) complex in Grenoble, France. The data from test 9.lb form the basis for the International Standard Problem number 27 (ISP-27). For each test the primary system depressurization, break flow rate, core heat-up, and effect of operator actions were analyzed. Based on the test 9.lb/ISP-27 and 6.2 TC data, an assessment study of the RELAP5/MOD3 version 7 code was performed which included a study of the above phenomena along with countercurrent flow limitation and vapor pull-through. The code provided a reasonable simulation of the various phenomena which occurred during the tests.
- Research Organization:
- EG and G Idaho, Inc., Idaho Falls, ID (United States)
- Sponsoring Organization:
- Nuclear Regulatory Commission, Washington, DC (United States)
- DOE Contract Number:
- AC07-76ID01570
- OSTI ID:
- 10172846
- Report Number(s):
- EGG-NE--10353; ON: DE92019689
- Country of Publication:
- United States
- Language:
- English
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Assessment of RELAP5/MOD3 Version 7 based on the BETHSY Test 6.2 TC
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22 GENERAL STUDIES OF NUCLEAR REACTORS
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99 GENERAL AND MISCELLANEOUS
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COMPUTER CALCULATIONS
COMPUTERIZED SIMULATION
DEPRESSURIZATION
FLOW RATE
HEAT TRANSFER
HUMAN FACTORS
HYDRAULICS
LOSS OF COOLANT
MATHEMATICS AND COMPUTERS
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
NONBOILING WATER COOLED
PWR TYPE REACTORS
R CODES
REACTOR SAFETY
SCALE MODELS