Proceedings of the 1992 Topical Meeting on Advances in Reactor Physics. Volume 1
Conference
·
OSTI ID:10130448
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.
- Research Organization:
- Westinghouse Savannah River Co., Aiken, SC (United States)
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP); American Nuclear Society (ANS), La Grange Park, IL (United States); Atomic Energy Society of Japan (AESJ), Tokyo (Japan)
- DOE Contract Number:
- AC09-89SR18035
- OSTI ID:
- 10130448
- Report Number(s):
- CONF-920308--Vol.1; ON: DE92009520
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210000
220100
220600
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
96 KNOWLEDGE MANAGEMENT AND PRESERVATION
97 MATHEMATICS AND COMPUTING
990200
BENCHMARKS
BWR TYPE REACTORS
COMPUTER CODES
Code Benchmarks and Validation
Core Computational Systems
Criticality Safety and Applications and Waste
FISSION PRODUCT RELEASE
FUEL CYCLE
FUEL MANAGEMENT
Fuel Management
HTGR TYPE REACTORS
LEADING ABSTRACT
LMFBR TYPE REACTORS
MATHEMATICS AND COMPUTERS
MEETINGS
NEUTRON TRANSPORT
NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS
Nodal Methods for Diffusion Theory
Nuclear Criticality Safety Program (NCSP)
Nuclear Data
POWER DISTRIBUTION
PRODUCTION REACTORS
PWR TYPE REACTORS
Proceedings
RADIOACTIVE WASTES
REACTIVITY
REACTOR CORES
REACTOR FUELING
REACTOR KINETICS
REACTOR PHYSICS
REACTOR SAFETY
RESEARCH
TEST
TRAINING
PRODUCTION
IRRADIATION
MATERIALS TESTING REACTORS
Safety Aspects of Heavy Water Reactors
Space-Time Core Kinetics
THEORY AND CALCULATION
VALIDATION
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210000
220100
220600
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
96 KNOWLEDGE MANAGEMENT AND PRESERVATION
97 MATHEMATICS AND COMPUTING
990200
BENCHMARKS
BWR TYPE REACTORS
COMPUTER CODES
Code Benchmarks and Validation
Core Computational Systems
Criticality Safety and Applications and Waste
FISSION PRODUCT RELEASE
FUEL CYCLE
FUEL MANAGEMENT
Fuel Management
HTGR TYPE REACTORS
LEADING ABSTRACT
LMFBR TYPE REACTORS
MATHEMATICS AND COMPUTERS
MEETINGS
NEUTRON TRANSPORT
NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS
Nodal Methods for Diffusion Theory
Nuclear Criticality Safety Program (NCSP)
Nuclear Data
POWER DISTRIBUTION
PRODUCTION REACTORS
PWR TYPE REACTORS
Proceedings
RADIOACTIVE WASTES
REACTIVITY
REACTOR CORES
REACTOR FUELING
REACTOR KINETICS
REACTOR PHYSICS
REACTOR SAFETY
RESEARCH
TEST
TRAINING
PRODUCTION
IRRADIATION
MATERIALS TESTING REACTORS
Safety Aspects of Heavy Water Reactors
Space-Time Core Kinetics
THEORY AND CALCULATION
VALIDATION