Simulation of the primary-secondary leak experiment of IAEA'S third standard problem exercise using the RELAP5/MOD2 and RELAP5/MOD3 computer codes
Journal Article
·
· Nuclear Technology; (United States)
OSTI ID:5508770
- Texas A and M Univ., Dept. of Nuclear Engineering, College Station, TX (US)
The International Atomic Energy Agency's third standard problem exercise (SPE-3) is simulated with the RELAP5/MOD2 and RELAP5/MOD3 computer codes. The SPE-3 consists of the simulation of the transient resulting from an 11.9% break in the hot collector of the steam generator (primary-secondary leak) of the PMK-NVH test facility. The predicted scenario is compared with the experimental data. Generally, a reasonable agreement between the code predictions and experimental data is obtained. One important calculated parameter that demonstrates deviation for the data is the break mass flow rate. The RELAP5/MOD3 predictions did not display significant differences. This paper is a part of an international effort for codes/benchmarks.
- OSTI ID:
- 5508770
- Journal Information:
- Nuclear Technology; (United States), Journal Name: Nuclear Technology; (United States) Vol. 96:2; ISSN NUTYB; ISSN 0029-5450
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220200 -- Nuclear Reactor Technology-- Components & Accessories
220400 -- Nuclear Reactor Technology-- Control Systems
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
CALCULATION METHODS
COMPUTER CODES
COOPERATION
DATA
EXPERIMENTAL DATA
IAEA SAFEGUARDS
INFORMATION
INTERNATIONAL COOPERATION
LEAK TESTING
LOSS OF COOLANT
NUMERICAL DATA
R CODES
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR SAFETY
REACTOR SAFETY EXPERIMENTS
SAFEGUARDS
SAFETY
SAFETY ANALYSIS
SAFETY STANDARDS
STANDARDS
TEST FACILITIES
TESTING
220200 -- Nuclear Reactor Technology-- Components & Accessories
220400 -- Nuclear Reactor Technology-- Control Systems
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
CALCULATION METHODS
COMPUTER CODES
COOPERATION
DATA
EXPERIMENTAL DATA
IAEA SAFEGUARDS
INFORMATION
INTERNATIONAL COOPERATION
LEAK TESTING
LOSS OF COOLANT
NUMERICAL DATA
R CODES
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR SAFETY
REACTOR SAFETY EXPERIMENTS
SAFEGUARDS
SAFETY
SAFETY ANALYSIS
SAFETY STANDARDS
STANDARDS
TEST FACILITIES
TESTING