Published 2006 | Version v1
Book

Verification of the coupled 3-D neutronics and thermal-hydraulic code SKETCH-INS/TRAC-P

  • 1. Japan Nuclear Energy Safety Organization JNES, Kamiya-cho, MT Bldg., 4-3-20, Tranomon, Minato-ku, Tokyo 105-0001 (Japan)

Description

In order to analyze the complex transients with coupled interactions between core behavior and plant dynamics, the three-dimensional neutronics code SKETCH-INS was coupled with the thermal-hydraulic code TRAC-P. The capability SKETCH-INS code was verified against the 3-D transient benchmark problem. The capability of the coupled code SKETCH-INS/TRAC-P was verified against the NEACRP 3-D LWR core transient benchmark and OECD MSLB benchmark problems. The results of analyses were in reasonable agreement with the reference and different codes results of benchmarks. This paper provides the outline of the coupled code SKETCH-INS/TRAC-P and the results of benchmarks. (authors)

Additional details

Publishing Information

Publisher
American Nuclear Society - ANS
Imprint Place
La Grange Park (United States)
ISBN
0-89448-697-7
Imprint Pagination
10 p.

Conference

Title
American Nuclear Society's Topical Meeting on Reactor Physics - Advances in Nuclear Analysis and Simulation
Acronym
PHYSOR-2006
Dates
10-14 Sep 2006
Place
Vancouver, BC (Canada)

Optional Information

Notes
10 refs.