2D/3D Program Work Summary Report (NUREG/IA-0126, GRS–100, MPR–1345)
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Publication Information
Date Published: June 1993
Edited by:
P. S. Damerell, J. W. Simons,
MPR Associates, Inc.
Prepared Jointly by:
Japan Atomic Energy Research Institute
Gesellschaft fuer Anlagen-und Reaktorsicherheit
Siemens AG, UB KWU
U.S. Nuclear Regulatory Commission
Los Alamos National Laboratory
MPR Associates, Inc.
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
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Abstract
The 2D/3D Program was carried out by Germany, Japan and the United States to investigate the thermal-hydraulics of a PWR large-break LOCA. A contributory approach was utilized in which each country contributed significant effort to the program and all three countries shared the research results. Germany constructed and operated the Upper Plenum Test Facility (UPTF), and Japan constructed and operated the Cylindrical Core Test Facility (CCTF) and the Slab Core Test Facility (SCTF). The US contribution consisted of provision of advanced instrumentation to each of the three test facilities, and assessment of the TRAC computer code against the test results. Evaluations of the test results were carried out in all three countries. This report summarizes the 2D/3D Program in terms of the contributing efforts of the participants.
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