Coupled neutronic and thermal-hydraulic code benchmark activities at the International Nuclear Safety Center.

Conference · Wed Jul 29 00:00:00 EDT 1998

OSTI ID:10624

Podlazov, L N

Two realistic benchmark problems are defined and used to assess the performance of coupled thermal-hydraulic and neutronic codes used in simulating dynamic processes in VVER-1000 and RBMK reactor systems. One of the problems simulates a design basis accident involving the ejection of three control and protection system rods from a VVER-1000 reactor. The other is based on a postulated rod withdrawal from an operating RBMK reactor. Preliminary results calculated by various codes are compared. While these results show significant differences, the intercomparisons performed so far provide a basis for further evaluation of code limitations and modeling assumptions.

• Research Organization: Argonne National Lab., IL (US)
• Sponsoring Organization: US Department of Energy (US)
• DOE Contract Number: W-31109-ENG-38
• OSTI ID: 10624
• Report Number(s): ANL/RA/CP-95538; TRN: US0103638
• Resource Relation: Conference: American Nuclear Society, International Conference on the Physics of Nuclear Science and Technology, Long Island, NY (US), 10/05/1998--10/08/1998; Other Information: PBD: 29 Jul 1998
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
BENCHMARKS
DESIGN BASIS ACCIDENTS
EVALUATION
PERFORMANCE
THERMODYNAMICS
HYDRAULICS
REACTOR KINETICS
WWER-5 REACTOR
LWGR TYPE REACTORS
COMPUTER CODES
ROD EJECTION ACCIDENTS