KINE--A one-dimensional dynamics program for pressurized water reactors with partial boiling in the core
Journal Article
·
· Nucl. Sci. Eng.; (United States)
OSTI ID:6987136
A short description of the reactor dynamics program KINE is given. The KINE code is a onedimensional code solving the time-dependent neutron diffusion equations in a two-group representation, taking into account six groups of delayed neutron precursors, one heating channel composed of fuel, canning, and a coolant region in which boiling may occur. Special attention is given to radial averaging of coolant density and fuel temperature in a core in which partial boiling can exist. The method of solution is a modified backward extrapolation procedure. Stationary starting conditions are achieved by adjustment of control rod position or liquid poison concentration.
- Research Organization:
- GKSS Forschungszentrum Geesthacht GmbH, Postfach 1160 2054 Geesthacht
- OSTI ID:
- 6987136
- Journal Information:
- Nucl. Sci. Eng.; (United States), Journal Name: Nucl. Sci. Eng.; (United States) Vol. 81:2; ISSN NSENA
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200* -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
BARYONS
BOILING
COMPUTER CALCULATIONS
COMPUTER CODES
CONTROL ELEMENTS
COOLING SYSTEMS
DELAYED NEUTRON PRECURSORS
DELAYED NEUTRONS
DENSITY
DIFFERENTIAL EQUATIONS
DIFFUSION
ELEMENTARY PARTICLES
ENERGY SYSTEMS
ENERGY TRANSFER
EQUATIONS
EXTRAPOLATION
FERMIONS
FISSION NEUTRONS
FLUID MECHANICS
HADRONS
HEAT TRANSFER
HYDRAULICS
ISOTOPES
K CODES
KINETICS
MATERIALS
MECHANICS
MULTIGROUP THEORY
NEUTRON DIFFUSION EQUATION
NEUTRON TRANSPORT THEORY
NEUTRONS
NUCLEAR POISONS
NUCLEONS
NUMERICAL SOLUTION
ONE-DIMENSIONAL CALCULATIONS
PHASE TRANSFORMATIONS
PHYSICAL PROPERTIES
POSITIONING
PRIMARY COOLANT CIRCUITS
PWR TYPE REACTORS
RADIOISOTOPES
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR CORES
REACTOR KINETICS
REACTOR KINETICS EQUATIONS
REACTOR MATERIALS
REACTORS
TIME DEPENDENCE
TRANSPORT THEORY
WATER COOLED REACTORS
WATER MODERATED REACTORS
210200* -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
BARYONS
BOILING
COMPUTER CALCULATIONS
COMPUTER CODES
CONTROL ELEMENTS
COOLING SYSTEMS
DELAYED NEUTRON PRECURSORS
DELAYED NEUTRONS
DENSITY
DIFFERENTIAL EQUATIONS
DIFFUSION
ELEMENTARY PARTICLES
ENERGY SYSTEMS
ENERGY TRANSFER
EQUATIONS
EXTRAPOLATION
FERMIONS
FISSION NEUTRONS
FLUID MECHANICS
HADRONS
HEAT TRANSFER
HYDRAULICS
ISOTOPES
K CODES
KINETICS
MATERIALS
MECHANICS
MULTIGROUP THEORY
NEUTRON DIFFUSION EQUATION
NEUTRON TRANSPORT THEORY
NEUTRONS
NUCLEAR POISONS
NUCLEONS
NUMERICAL SOLUTION
ONE-DIMENSIONAL CALCULATIONS
PHASE TRANSFORMATIONS
PHYSICAL PROPERTIES
POSITIONING
PRIMARY COOLANT CIRCUITS
PWR TYPE REACTORS
RADIOISOTOPES
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR CORES
REACTOR KINETICS
REACTOR KINETICS EQUATIONS
REACTOR MATERIALS
REACTORS
TIME DEPENDENCE
TRANSPORT THEORY
WATER COOLED REACTORS
WATER MODERATED REACTORS