Coupled neutronic and thermal-hydraulic code benchmark activities at the International Nuclear Safety Center.
Conference
·
OSTI ID:10624
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
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