Proceedings of the 1992 Topical Meeting on Advances in Reactor Physics
Conference
·
OSTI ID:10130459
This document, Volume 2, 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: Transport Theory; Fast Reactors; Plant Analyzers; Integral Experiments/Measurements & Analysis; Core Computational Systems; Reactor Physics; Monte Carlo; Safety Aspects of Heavy Water Reactors; and Space-Time Core Kinetics. The individual reports have been cataloged separately.
- Research Organization:
- Savannah River Site (SRS), Aiken, SC (United States)
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP); American Nuclear Society Savannah River Section, Reactor Physics Division, and Mathematics and Computations Division; Atomic Energy Society of Japan (AESJ)
- DOE Contract Number:
- AC09-89SR18035
- OSTI ID:
- 10130459
- Report Number(s):
- CONF-920308--Vol.2; ON: DE92009763
- Country of Publication:
- United States
- Language:
- English
Similar Records
Proceedings of the 1992 topical meeting on advances in reactor physics
Proceedings of the 1992 Topical Meeting on Advances in Reactor Physics. Volume 1
Proceedings of the topical meeting on reactor physics and safety: Sessions 11-16. Volume 2
Conference
·
Tue Dec 31 23:00:00 EST 1991
·
OSTI ID:5842522
Proceedings of the 1992 Topical Meeting on Advances in Reactor Physics. Volume 1
Conference
·
Sat Mar 07 23:00:00 EST 1992
·
OSTI ID:10130448
Proceedings of the topical meeting on reactor physics and safety: Sessions 11-16. Volume 2
Conference
·
Fri Aug 01 00:00:00 EDT 1986
·
OSTI ID:5292068
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210000
22 GENERAL STUDIES OF NUCLEAR REACTORS
220100
220400
220600
96 KNOWLEDGE MANAGEMENT AND PRESERVATION
97 MATHEMATICS AND COMPUTING
990200
BWR TYPE REACTORS
COMPUTER CODES
CONTROL SYSTEMS
Core Computational Systems
Fast Reactors
Integral Experiments/Measurements & Analysis
LEADING ABSTRACT
LMFBR TYPE REACTORS
MATHEMATICS AND COMPUTERS
MEETINGS
MONTE CARLO METHOD
Monte Carlo
NESDPS Office of Nuclear Energy Space and Defense Power Systems
NEURAL NETWORKS
NEUTRON TRANSPORT
NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS
Nuclear Criticality Safety Program (NCSP)
PRODUCTION REACTORS
PWR TYPE REACTORS
Plant Analyzers
REACTIVITY
REACTOR CONTROL SYSTEMS
REACTOR CORES
REACTOR KINETICS
REACTOR MONITORING SYSTEMS
REACTOR PHYSICS
REACTOR SAFETY
RESEARCH
TEST
TRAINING
PRODUCTION
IRRADIATION
MATERIALS TESTING REACTORS
Reactor Physics
SPACE POWER REACTORS
Safety Aspects of Heavy Water Reactors
Space-Time Core Kinetics
THEORY AND CALCULATION
TRANSIENTS
TRANSPORT THEORY
Transport Theory
210000
22 GENERAL STUDIES OF NUCLEAR REACTORS
220100
220400
220600
96 KNOWLEDGE MANAGEMENT AND PRESERVATION
97 MATHEMATICS AND COMPUTING
990200
BWR TYPE REACTORS
COMPUTER CODES
CONTROL SYSTEMS
Core Computational Systems
Fast Reactors
Integral Experiments/Measurements & Analysis
LEADING ABSTRACT
LMFBR TYPE REACTORS
MATHEMATICS AND COMPUTERS
MEETINGS
MONTE CARLO METHOD
Monte Carlo
NESDPS Office of Nuclear Energy Space and Defense Power Systems
NEURAL NETWORKS
NEUTRON TRANSPORT
NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS
Nuclear Criticality Safety Program (NCSP)
PRODUCTION REACTORS
PWR TYPE REACTORS
Plant Analyzers
REACTIVITY
REACTOR CONTROL SYSTEMS
REACTOR CORES
REACTOR KINETICS
REACTOR MONITORING SYSTEMS
REACTOR PHYSICS
REACTOR SAFETY
RESEARCH
TEST
TRAINING
PRODUCTION
IRRADIATION
MATERIALS TESTING REACTORS
Reactor Physics
SPACE POWER REACTORS
Safety Aspects of Heavy Water Reactors
Space-Time Core Kinetics
THEORY AND CALCULATION
TRANSIENTS
TRANSPORT THEORY
Transport Theory