Seventh international RETRAN conference: Proceedings

Conference · Sat Feb 01 04:00:00 EST 1992

OSTI ID:5346879

Agee, L J ^[1]

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1. ed.

The RETRAN computer code, developed by EPRI through its Contractors, EI International, Inc. (EI) and Computer Simulation and Analysis, Inc. (CSA), is now widely used by the international nuclear community for various types of safety analyses. In order to exchange information concerning the current use of the code by the various organizations, EPRI and CSA sponsored the Seventh International RETRAN meeting in New Orleans, Louisiana on September 15--18, 1991. The opening session featured a panel discussion on Future Analysis Requirements and Methods for Reactor Licensing Operations'' by representatives of the US Fuel Vendors (i.e., ABB-CE, Seimens, B W, GE, and W) as well as review of RETRAN activities during 1990 and 1991. During the three-day meeting, technical papers were presented by the various participants. The papers can be generally classified as: RETRAN-03 development, verification and validation; RETRAN-02 analysis of PWRs; RETRAN-02 analysis of BWRs; and VIPRE-01 and VIPRE-02 codes and application. The individual papers have been cataloged separately.

• Research Organization: Electric Power Research Inst., Palo Alto, CA (United States)
• Sponsoring Organization: Electric Power Research Inst., Palo Alto, CA (United States)
• OSTI ID: 5346879
• Report Number(s): EPRI-TR-100361; CONF-9109388--
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
99 GENERAL AND MISCELLANEOUS
990200 -- Mathematics & Computers
ABSTRACTS
ACCIDENTS
BWR TYPE REACTORS
COMPUTER CODES
COOLING SYSTEMS
DOCUMENT TYPES
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
EVALUATION
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
LEADING ABSTRACT
LICENSING
LOSS OF COOLANT
MECHANICS
MEETINGS
POWER REACTORS
PWR TYPE REACTORS
R CODES
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR LICENSING
REACTOR SAFETY
REACTORS
RELIABILITY
SAFETY
SAFETY ANALYSIS
THERMAL REACTORS
TRANSIENTS
V CODES
WATER COOLED REACTORS
WATER MODERATED REACTORS