Stiffness confinement method for solving nuclear reactor kinetics equations
Thesis/Dissertation
·
OSTI ID:6224978
The point kinetics equations are stiff, coupled differential equations. This stiffness problem in reactor kinetics is overcome by the stiffness confinement method (SCM) for solving the kinetic equations. The idea is based on the observation that the stiffness characteristic is present only in the time response of the prompt neutron density, but not in that of the delayed neutron precursors. A method is, therefore, devised to have the stiffness decoupled from the differential equations for the precursors and confined to the one for the prompt neutrons, which can be analytically solved. Numerical examples of applying the method to a variety of problems confirm that the step size of time increment can be greatly increased and the computing time much saved as compared to other conventional methods. The effects of including temperature feedback into the formulism of (SCM), and extending (SCM) from the point kinetics model to space-time kinetics, are qualitatively examined. The theory is of general validity and involves no approximation other than the discretization of the time variable.
- Research Organization:
- Carnegie-Mellon Univ., Pittsburgh, PA (USA)
- OSTI ID:
- 6224978
- Country of Publication:
- United States
- Language:
- English
Similar Records
A resolution of the stiffness problem of reactor kinetics
Using dynamic frequencies for overcoming the stiffness of the neutronic space-time kinetic calculations
Solving stiff differential equations with the method of patches
Journal Article
·
Wed May 01 00:00:00 EDT 1985
· Nucl. Sci. Eng.; (United States)
·
OSTI ID:5056944
Using dynamic frequencies for overcoming the stiffness of the neutronic space-time kinetic calculations
Conference
·
Thu Dec 31 23:00:00 EST 1992
· Transactions of the American Nuclear Society; (United States)
·
OSTI ID:6022971
Solving stiff differential equations with the method of patches
Journal Article
·
Mon Aug 10 00:00:00 EDT 1998
· Journal of Computational Physics
·
OSTI ID:653494
Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220100* -- Nuclear Reactor Technology-- Theory & Calculation
BARYONS
DELAYED NEUTRONS
ELEMENTARY PARTICLES
EQUATIONS
FERMIONS
FISSION NEUTRONS
HADRONS
NEUTRON DENSITY
NEUTRONS
NUCLEONS
NUMERICAL SOLUTION
PROMPT NEUTRONS
REACTOR KINETICS EQUATIONS
TEMPERATURE EFFECTS
220100* -- Nuclear Reactor Technology-- Theory & Calculation
BARYONS
DELAYED NEUTRONS
ELEMENTARY PARTICLES
EQUATIONS
FERMIONS
FISSION NEUTRONS
HADRONS
NEUTRON DENSITY
NEUTRONS
NUCLEONS
NUMERICAL SOLUTION
PROMPT NEUTRONS
REACTOR KINETICS EQUATIONS
TEMPERATURE EFFECTS