Proceedings: Sixth international RETRAN conference. [RETRAN Computer Code]

Conference · Wed Aug 01 04:00:00 EDT 1990

OSTI ID:6665087

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 sponsored the Sixth International RETRAN meeting in Washington, DC on September 17--20, 1989. The opening session featured a panel discussion on Licensing Issues of the Nineties'' by representatives from NUMARC, Wolf Creek, and Entergy Services, Inc. as well as a review of RETRAN activities during 1988 and 1989. During the three-day meeting, 28 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; and RETRAN-02 analysis of BWRs. The entire text of all of the papers is included in this special EPRI report. In addition, these proceedings contain the text of seven technical reports presented at a poster session. Each individual paper has been cataloged separately.

• Research Organization: Electric Power Research Inst., Palo Alto, CA (USA)
• Sponsoring Organization: EPRI
• OSTI ID: 6665087
• Report Number(s): EPRI-NP-6949; CONF-8909248--
• 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
COMPUTERIZED SIMULATION
DOCUMENT TYPES
ENERGY TRANSFER
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
LEADING ABSTRACT
LICENSING
MECHANICS
MEETINGS
PROCEEDINGS
PWR TYPE REACTORS
R CODES
REACTOR ACCIDENTS
REACTOR LICENSING
REACTOR SAFETY
REACTORS
SAFETY
SIMULATION
TRANSIENTS
WATER COOLED REACTORS
WATER MODERATED REACTORS