OECD/NEA Main Steam Line Break PWR Benchmark Simulation by TRACE/S3K Coupled Code
NURETH-14 - 2011 September 25-30


Presented at:
NURETH-14
2011 September 25-30
Location:
Toronto, Canada
Session Title:
B13-4 Development, Assessment and Applications of TRACE

Authors:
Konstantin Nikitin (Paul Scherrer Institut)
Annalisa Manera (Paul Scherrer Institut)
Hakim Ferroukhi (Paul Scherrer Institut)
Jerry Judd (Studsvik Scandpower, Inc.)
Gerardo M. Grandi (Studsvik, Idaho Falls)
  

Abstract

A coupling between the TRACE system thermal-hydraulics code and the SIMULATE-3K

(S3K) three-dimensional reactor kinetics code has been developed in a collaboration between

the Paul Scherrer Institut (PSI) and Studsvik. In order to verify the coupling scheme and the

coupled code capabilities with regards to plant transients, the OECD/NEA Main Steam Line

Break PWR benchmark was simulated with the coupled TRACE/S3K code. The core/plant

system data were taken from the benchmark specifications, while the nuclear data were

generated with the Studsvik’s lattice code CASMO-4 and the core analysis code

SIMULATE-3. The TRACE/S3K results were compared with the published results obtained

by the 17 participants of the benchmark. The comparison shows that the TRACE/S3K code

reproduces satisfactory the main transient parameters, namely, the power and reactivity

history, steam generator inventory, and pressure response.

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