International Code Assessment and Applications Program: Summary of Code Assessment Studies Concerning RELAP5/MOD2, RELAP5/MOD3, and TRAC–B (NUREG/IA-0128, EGG-EAST-8719)
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Date Published: December 1993
R. R. Schultz
Idaho National Engineering Laboratory
EG & G Idaho, Inc.
Idaho Falls, ID 83415
Prepared as part of:
Arrangement on Research Participation and Technical Exchange between
the Federal Minister for Research and Technology of the Federal Republic of Germany
(BMFT) and the Japan Atomic Energy Research Institute (JAERI) and the United States Nuclear
Regulatory Commission (USNRC) in a Coordinated Analytical and Experimental Study
of the Thermo-hydraulic Behavior of Emergency Core Coolant during the Refill and Reflood
Phase of a Loss-of-Coolant Accident in a Pressurized Water Reactor (the 2D/3D Program).
Office of Nuclear Regulatory Research
U.S. Nuclear Regulatory Commission
Washington, DC 20555-0001
Members of the International Code Assessment Program (ICAP) have assessed the U.S. Nuclear Regulatory Commission (USNRC) advanced thermal-hydraulic codes over the past few years in a concerted effort to identify deficiencies, to define user guidelines, and to determine the state of each code. The results of sixty-two code assessment reviews, conducted at INEL, are summarized. Code deficiencies are discussed and user recommended nodalizations investigated during the course of conducting the assessment studies and reviews are listed. All the work that is summarized was done using the RELAP5/MOD2, RELAP5/MOD3, and TRAC-B codes.