A CALCULATION OF RESONANCE ESCAPE PROBABILITY BY MONTE CARLO METHODS
Technical Report
·
OSTI ID:4279929
A Monte Carlo program written for the IBM 704 to calculate the resonaece escape probability (p) is described, and the results of several calculations are given. The program was designed for studying the temperature variation of p in the Calder Hall lattice consisting of a square array of natural uranium rods lying the centers of cylindrical gas channels through a graphite moderator. In order to study the temperature effect it was found necessary to cover resonances up to 5 kev. The reduced neutron widths for these were sampled from the Porter- Thomas distribution, the spacing and gamma -widths being assumed consstant and the same as for the lower resonances. The spatial distribution and the energy distribution of the absorptions are also obtained from the calculations. The former is obtained less accurately than the rest of the results, but is possible to get from it some idea of whether the surface or the volume temperature of the fuel rods of most important in determining the temperature coefficient. One or two devices incorporated in the program to increase the efficiency of the Monte Carlo method are described and their merits discussed. (auth)
- Research Organization:
- Atomic Energy Research Establishment, Harwell, Berks, Eng.
- NSA Number:
- NSA-13-007079
- OSTI ID:
- 4279929
- Report Number(s):
- A/CONF.15/P/19
- Country of Publication:
- Country unknown/Code not available
- Language:
- English
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Related Subjects
ABSORPTION
ANGULAR DISTRIBUTION
CALDER HALL
CAPTURE
COMPUTERS
CONFIGURATION
COOLANT LOOPS
DECAY
EFFICIENCY
ENERGY LEVELS
EQUATIONS
ERRORS
FUEL ELEMENTS
GAMMA RADIATION
GAS COOLANT
GRAPHITE MODERATOR
IBM 704
INTERACTIONS
MONTE CARLO METHOD
NATURAL URANIUM FUEL
NEUTRON FLUX
NUMERICALS
PROGRAMMING
REACTOR CORE
REACTORS
RESONANCE
RESONANCE ESCAPE PROBABILITY
RESONANCE NEUTRONS
RODS
SPECTRAL SHIFT
STATISTICS
TEMPERATURE
VARIATIONS
ZONES
ANGULAR DISTRIBUTION
CALDER HALL
CAPTURE
COMPUTERS
CONFIGURATION
COOLANT LOOPS
DECAY
EFFICIENCY
ENERGY LEVELS
EQUATIONS
ERRORS
FUEL ELEMENTS
GAMMA RADIATION
GAS COOLANT
GRAPHITE MODERATOR
IBM 704
INTERACTIONS
MONTE CARLO METHOD
NATURAL URANIUM FUEL
NEUTRON FLUX
NUMERICALS
PROGRAMMING
REACTOR CORE
REACTORS
RESONANCE
RESONANCE ESCAPE PROBABILITY
RESONANCE NEUTRONS
RODS
SPECTRAL SHIFT
STATISTICS
TEMPERATURE
VARIATIONS
ZONES