RELAP5-3D code validation for RBMK phenomena

Technical Report · Wed Sep 01 00:00:00 EDT 1999

DOI:https://doi.org/10.2172/752162· OSTI ID:752162

Fisher, J E

The RELAP5-3D thermal-hydraulic code was assessed against Japanese Safety Experiment Loop (SEL) and Heat Transfer Loop (HTL) tests. These tests were chosen because the phenomena present are applicable to analyses of Russian RBMK reactor designs. The assessment cases included parallel channel flow fluctuation tests at reduced and normal water levels, a channel inlet pipe rupture test, and a high power, density wave oscillation test. The results showed that RELAP5-3D has the capability to adequately represent these RBMK-related phenomena.

• Research Organization: Idaho National Lab. (INL), Idaho Falls, ID (United States)
• Sponsoring Organization: USDOE Office of Nonproliferation and National Security (NN) (US)
• DOE Contract Number: AC07-94ID13223
• OSTI ID: 752162
• Report Number(s): INEEL/EXT-99-00924; TRN: US0001358
• Resource Relation: Other Information: PBD: 1 Sep 1999
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE
R CODES
HEAT TRANSFER
HYDRAULICS
REACTOR SAFETY EXPERIMENTS
VALIDATION
LWGR TYPE REACTORS
REACTOR ACCIDENTS
THERMAL-HYDRAULIC
RBMK REACTOR
PARALLEL CHANNEL FLOW
WATER LEVELS
PIPE RUPTURE
HIGH POWER
RELAP5-3D
HIGH DENSITY