Proceedings of the 1992 topical meeting on advances in reactor physics
Conference
·
OSTI ID:5842522
This document, Volume 1, presents proceedings of the 1992 Topical Meeting on Advances in Reactor Physics on March 8--11, 1992 at Charleston, SC. Session topics were as follows: Code Benchmarks and Validation; Fuel Management; Nodal Methods for Diffusion Theory; Criticality Safety and Applications and Waste; Core Computational Systems; Nuclear Data; Safety Aspects of Heavy Water Reactors; and Space-Time Core Kinetics. The individual papers have been cataloged separately. (FI)
- Research Organization:
- Westinghouse Savannah River Co., Aiken, SC (United States)
- Sponsoring Organization:
- DOE; ANS; AESJA; USDOE, Washington, DC (United States); American Nuclear Society, La Grange Park, IL (United States); Atomic Energy Society of Japan, Tokyo (Japan)
- DOE Contract Number:
- AC09-89SR18035
- OSTI ID:
- 5842522
- Report Number(s):
- CONF-920308-Vol.1; ON: DE92009520
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210000 -- Nuclear Power Plants
22 GENERAL STUDIES OF NUCLEAR REACTORS
220100* -- Nuclear Reactor Technology-- Theory & Calculation
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
99 GENERAL AND MISCELLANEOUS
990200 -- Mathematics & Computers
ABSTRACTS
BENCHMARKS
BREEDER REACTORS
BWR TYPE REACTORS
COMPUTER CODES
DOCUMENT TYPES
ENRICHED URANIUM REACTORS
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FISSION PRODUCT RELEASE
FUEL CYCLE
FUEL MANAGEMENT
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HTGR TYPE REACTORS
KINETICS
LEADING ABSTRACT
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MATERIALS
MEETINGS
NEUTRAL-PARTICLE TRANSPORT
NEUTRON TRANSPORT
PHYSICS
POWER DISTRIBUTION
POWER REACTORS
PRODUCTION REACTORS
PWR TYPE REACTORS
RADIATION TRANSPORT
RADIOACTIVE MATERIALS
RADIOACTIVE WASTES
REACTIVITY
REACTOR COMPONENTS
REACTOR CORES
REACTOR FUELING
REACTOR KINETICS
REACTOR PHYSICS
REACTOR SAFETY
REACTORS
SAFETY
TESTING
THERMAL REACTORS
VALIDATION
WASTES
WATER COOLED REACTORS
WATER MODERATED REACTORS
210000 -- Nuclear Power Plants
22 GENERAL STUDIES OF NUCLEAR REACTORS
220100* -- Nuclear Reactor Technology-- Theory & Calculation
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
99 GENERAL AND MISCELLANEOUS
990200 -- Mathematics & Computers
ABSTRACTS
BENCHMARKS
BREEDER REACTORS
BWR TYPE REACTORS
COMPUTER CODES
DOCUMENT TYPES
ENRICHED URANIUM REACTORS
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FISSION PRODUCT RELEASE
FUEL CYCLE
FUEL MANAGEMENT
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HTGR TYPE REACTORS
KINETICS
LEADING ABSTRACT
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MATERIALS
MEETINGS
NEUTRAL-PARTICLE TRANSPORT
NEUTRON TRANSPORT
PHYSICS
POWER DISTRIBUTION
POWER REACTORS
PRODUCTION REACTORS
PWR TYPE REACTORS
RADIATION TRANSPORT
RADIOACTIVE MATERIALS
RADIOACTIVE WASTES
REACTIVITY
REACTOR COMPONENTS
REACTOR CORES
REACTOR FUELING
REACTOR KINETICS
REACTOR PHYSICS
REACTOR SAFETY
REACTORS
SAFETY
TESTING
THERMAL REACTORS
VALIDATION
WASTES
WATER COOLED REACTORS
WATER MODERATED REACTORS