GASP7; one-dimensional burnup power distribution search. [UNIVAC1108; FORTRAN IV]
Technical Report
·
OSTI ID:6484793
GASP7 calculates the one-dimensional distribution of fissile and fertile materials in a nuclear reactor which will yield any desired power distribution during the burnup history of the reactor core. A poison and poison distribution search for a desired multiplication and minimum power distribution perturbation can also be performed.UNIVAC1108; FORTRAN IV; EXEC2; 65K UNIVAC1108 or 1107 and 3 tapes (input, output, system).
- Research Organization:
- General Atomic Co., San Diego, CA (USA)
- OSTI ID:
- 6484793
- Report Number(s):
- ANL/NESC-319; ON: DE83048319
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
654003* -- Radiation & Shielding Physics-- Neutron Interactions with Matter
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
COMPUTER CODES
DIFFERENTIAL EQUATIONS
EQUATIONS
G CODES
ITERATIVE METHODS
MULTIGROUP THEORY
NEUTRON DIFFUSION EQUATION
NEUTRON TRANSPORT THEORY
ONE-DIMENSIONAL CALCULATIONS
POISONING
POWER DISTRIBUTION
TRANSPORT THEORY
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
COMPUTER CODES
DIFFERENTIAL EQUATIONS
EQUATIONS
G CODES
ITERATIVE METHODS
MULTIGROUP THEORY
NEUTRON DIFFUSION EQUATION
NEUTRON TRANSPORT THEORY
ONE-DIMENSIONAL CALCULATIONS
POISONING
POWER DISTRIBUTION
TRANSPORT THEORY