Proceedings of an international conference on numerical methods in nuclear engineering
Conference
·
OSTI ID:7090319
This book presents the papers given at a conference on reactor kinetics calculations and neutron transport theory. Topics considered at the conference included computer codes for thermohydraulic analysis of reactor components, PWR transient analysis, neutronics calculations, the neutron diffusion equation, homogenization techniques in reactor lattices, core thermohydraulics, subchannel analysis, risk assessment, heat transfer during loss of coolant accidents, core physics, turbulent flow in rod bundles, fuel behavior, reactor core disruption calculations, and a computer-aided design package for designing multivariable control systems.
- OSTI ID:
- 7090319
- Report Number(s):
- CONF-830932-
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220100* -- Nuclear Reactor Technology-- Theory & Calculation
654003 -- Radiation & Shielding Physics-- Neutron Interactions with Matter
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
ABSTRACTS
ACCIDENTS
COMPUTER CODES
COMPUTER-AIDED DESIGN
CONTROL SYSTEMS
DIFFERENTIAL EQUATIONS
DOCUMENT TYPES
ENERGY TRANSFER
EQUATIONS
FLUID MECHANICS
HEAT TRANSFER
HOMOGENIZATION METHODS
HYDRAULICS
KINETICS
LEADING ABSTRACT
LOSS OF COOLANT
MECHANICS
MEETINGS
NEUTRON DIFFUSION EQUATION
NEUTRON FLUX
NEUTRON TRANSPORT THEORY
PWR TYPE REACTORS
RADIATION FLUX
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CONTROL SYSTEMS
REACTOR CORE DISRUPTION
REACTOR CORES
REACTOR KINETICS
REACTOR LATTICE PARAMETERS
REACTORS
RISK ASSESSMENT
ROD BUNDLES
THERMODYNAMICS
TRANSPORT THEORY
WATER COOLED REACTORS
WATER MODERATED REACTORS
220100* -- Nuclear Reactor Technology-- Theory & Calculation
654003 -- Radiation & Shielding Physics-- Neutron Interactions with Matter
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
ABSTRACTS
ACCIDENTS
COMPUTER CODES
COMPUTER-AIDED DESIGN
CONTROL SYSTEMS
DIFFERENTIAL EQUATIONS
DOCUMENT TYPES
ENERGY TRANSFER
EQUATIONS
FLUID MECHANICS
HEAT TRANSFER
HOMOGENIZATION METHODS
HYDRAULICS
KINETICS
LEADING ABSTRACT
LOSS OF COOLANT
MECHANICS
MEETINGS
NEUTRON DIFFUSION EQUATION
NEUTRON FLUX
NEUTRON TRANSPORT THEORY
PWR TYPE REACTORS
RADIATION FLUX
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CONTROL SYSTEMS
REACTOR CORE DISRUPTION
REACTOR CORES
REACTOR KINETICS
REACTOR LATTICE PARAMETERS
REACTORS
RISK ASSESSMENT
ROD BUNDLES
THERMODYNAMICS
TRANSPORT THEORY
WATER COOLED REACTORS
WATER MODERATED REACTORS