A comparison of RELAP5 and TRAC LOCA (loss-of-coolant accident) calculations for the K-14. 1 charge at SRS (Savannah River Site)

Technical Report · Tue Aug 01 04:00:00 EDT 1989

DOI:https://doi.org/10.2172/7175249· OSTI ID:7175249

Davis, C B

Calculations of a loss-of-coolant accident (LOCA) in K-Reactor at the Savannah River Site (SRS) were performed using the RELAP5 computer code. The results of the RELAP5 calculation were then compared with a TRAC calculation previously performed by Savannah River Laboratory. The calculations represented the early (flow instability) portion of a LOCA initiated by a double-ended quillotine break in the plenum inlet piping in K-Reactor. A RELAP5 model of K-Reactor was developed to perform the calculations. The model represented all six external loops and represented the reactor vessel in a three-dimensional manner. The RELAP5 and TRAC results were compared to illustrate and understand differences and similarities between calculations performed with independent computer codes and input models. The variation between the independent calculations provided an indication of the uncertainty in the calculated results with both codes. Results of the comparison were generally favorable as differences between the calculated results for the water plenum and tank bottom pressures were generally less than the values currently assumed in Savannah River's FLOWTRAN uncertainty studies. 23 refs., 24 figs., 2 tabs.

• Research Organization: EG and G Idaho, Inc., Idaho Falls, ID (USA)
• Sponsoring Organization: DOE/NE
• DOE Contract Number: AC07-76ID01570
• OSTI ID: 7175249
• Report Number(s): EGG-EAST-8608; ON: DE90010923
• Country of Publication: United States
• Language: English

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ACCIDENTS
COMPARATIVE EVALUATIONS
COMPUTER CALCULATIONS
COMPUTER CODES
COOLING SYSTEMS
ENERGY SYSTEMS
ENERGY TRANSFER
FLUID MECHANICS
HEAT EXCHANGERS
HEAT TRANSFER
HEAVY WATER MODERATED REACTORS
HYDRAULICS
K REACTOR
LOSS OF COOLANT
MECHANICS
PRODUCTION REACTORS
PUMPS
R CODES
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR SAFETY
REACTORS
SAFETY
SENSITIVITY ANALYSIS
SPECIAL PRODUCTION REACTORS
T CODES