RELAP5 code development and assessment at the Savannah River Site

Conference · Tue Dec 31 04:00:00 EST 1991

OSTI ID:10130168

Dimenna, R A

Over the past year, the focus of RELAP5 use at the Savannah River Site has been on code applications to reactor accidents having a direct bearing on setting power limits, with a lesser emphasis on code development. In the applications task, RELAP5/MOD2.5 has been used to predict the thermal-hydraulic system response to large break loss of coolant accidents and to provide boundary conditions for a detailed fuel assembly code. This paper describes the significant phenomena affecting the ability of RELAP5 to perform the system calculations, the benchmarking work completed to validate the application of RELAP5 to Savannah River Site reactors, and the results of the system calculations. This paper will also describe the code and model development effort and will describe briefly certain significant gains.

• Research Organization: Westinghouse Savannah River Co., Aiken, SC (United States)
• Sponsoring Organization: USDOE, Washington, DC (United States)
• DOE Contract Number: AC09-89SR18035
• OSTI ID: 10130168
• Report Number(s): WSRC-MS--91-453; CONF-9111124--4; ON: DE92009568
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220900
42 ENGINEERING
420400
99 GENERAL AND MISCELLANEOUS
990200
BENCHMARKS
BOUNDARY CONDITIONS
DESIGN
FLOW MODELS
HEAT TRANSFER
HEAT TRANSFER AND FLUID FLOW
HYDRAULICS
LOSS OF COOLANT
MATHEMATICS AND COMPUTERS
R CODES
REACTOR ACCIDENTS
REACTOR SAFETY
SAVANNAH RIVER PLANT