RELAP5/MOD2.5 five-ring SRS reactor model for simulating L-reactor tests

Journal Article · Sat Dec 31 04:00:00 EST 1994 · Transactions of the American Nuclear Society

OSTI ID:76151

Paul, P K; Herman, D T; Gill, G L

A program was implemented as Savannah River site (SRS) to use the system code RELAP5 for K15.1 loss-of-coolant accident (LOCA) and loss-of-pumping accident (LOPA) reactor power limits calculations. The RELAP5 improvement program consolidated one system code and upgraded existing models. The existing SRS RELAP5 model was modified to have five rings for the plenum and tank models. To better model drained tank conditions, the bottom level was divided into two levels, making four levels for the tank. In addition, a new vacuum breaker model, new U-tube model, and modified blanket gas model were incorporated into the previous RELAP5 model. Benchmarking the complete model was performed against 1989 L-area test data before using RELAP5 for K15.1 limits calculations. The objective of these simulations was to show the applicability of RELAP5 to the flow instability phase of LOCA (LOCA-FI) and LOPA analyses. This paper presents the simulation results and comparisons with test data.

• OSTI ID: 76151
• Report Number(s): CONF-940602--
• Journal Information: Transactions of the American Nuclear Society, Journal Name: Transactions of the American Nuclear Society Vol. 70; ISSN 0003-018X; ISSN TANSAO
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
99 GENERAL AND MISCELLANEOUS
BENCHMARKS
CALCULATION METHODS
L REACTOR
LOSS OF COOLANT
R CODES
SIMULATION