Third international RETRAN conference: proceedings
Conference
·
OSTI ID:5962765
- ed.
The RETRAN computer code, developed by EPRI through its Contractor, Energy Incorporated (EI), is now being widely used by the international nuclear community for various types of safety analysis. In order to exchange information concerning the current use of the code by the various organizations, EPRI and EI jointly sponsored the Third International RETRAN Meeting in Las Vegas, Nevada, on April 9-11, 1984. The opening session featured a panel discussion on System Analysis for Plant Operations and Safety by representatives from NUSCO, NRC, EPRI, and UKAEA. During the three-day meeting, 39 technical papers were presented by the various participants. The papers can be generally classified as: RETRAN development, verification and analysis of non-LWR systems; RETRAN analysis of PWRs; and RETRAN analysis of BWRs. The entire text of the 39 papers is included in this special EPRI report.
- Research Organization:
- Electric Power Research Inst., Palo Alto, CA (USA)
- OSTI ID:
- 5962765
- Report Number(s):
- EPRI-NP-3803-SR; CONF-8404133-; ON: TI85920518
- Country of Publication:
- United States
- Language:
- English
Similar Records
Fourth International RETRAN Conference. Proceedings
Conference proceedings: second international RETRAN conference. [PWR; BWR]
Proceedings: Sixth international RETRAN conference. [RETRAN Computer Code]
Conference
·
Thu May 01 00:00:00 EDT 1986
·
OSTI ID:5692113
Conference proceedings: second international RETRAN conference. [PWR; BWR]
Conference
·
Thu Jul 01 00:00:00 EDT 1982
·
OSTI ID:6194426
Proceedings: Sixth international RETRAN conference. [RETRAN Computer Code]
Conference
·
Wed Aug 01 00:00:00 EDT 1990
·
OSTI ID:6665087
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
ABSTRACTS
ACCIDENTS
BWR TYPE REACTORS
COMPUTER CODES
DOCUMENT TYPES
ENERGY TRANSFER
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
LEADING ABSTRACT
LOSS OF COOLANT
MECHANICS
MEETINGS
OPERATION
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR OPERATION
REACTOR SAFETY
REACTOR START-UP
REACTORS
SAFETY
START-UP
SYSTEMS ANALYSIS
TRANSIENTS
WATER COOLED REACTORS
WATER MODERATED REACTORS
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
ABSTRACTS
ACCIDENTS
BWR TYPE REACTORS
COMPUTER CODES
DOCUMENT TYPES
ENERGY TRANSFER
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
LEADING ABSTRACT
LOSS OF COOLANT
MECHANICS
MEETINGS
OPERATION
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR OPERATION
REACTOR SAFETY
REACTOR START-UP
REACTORS
SAFETY
START-UP
SYSTEMS ANALYSIS
TRANSIENTS
WATER COOLED REACTORS
WATER MODERATED REACTORS