Methods and Results for the MSLB NEA Benchmark Using SIMTRAN and RELAP-5

Conference · Sun Jun 17 00:00:00 EDT 2001

OSTI ID:784579

Aragones, Jose M; Ahnert, Carol; Cabellos, Oscar; Garcia-Herranz, Nuria

This work discusses the methods developed in a three-dimensional (3-D) pressurized water reactor (PWR) SIMTRAN Core Dynamics code and its coupling to the RELAP-5 system code for general transient and safety analysis, as well as its demonstration application to the Nuclear Energy Agency/Organization for Economic Cooperation and Development (NEA/OECD) Benchmark on Main Steam Line Break (MSLB). The results for the steady states and the transients proposed for exercise 2 of the MSLB Benchmark, the guided core transient analysis, show small deviations from the mean results of other participants, especially for core average parameters. For exercise 3, the full system transient, the agreement is quite good for both integral and local parameters.

• Research Organization: Universidad Politecnica de Madrid, Madrid (ES)
• Sponsoring Organization: Consejo de Seguridad Nuclear (ES) (US)
• OSTI ID: 784579
• Report Number(s): NONE; ISSN 0003-018X; CODEN TANSAO; ISSN 0003-018X; CODEN TANSAO
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BENCHMARKS
LOSS OF COOLANT
PWR TYPE REACTORS
R CODES
REACTOR CORES
S CODES
SAFETY ANALYSIS
STEAM LINES
TRANSIENTS