THE VOID COEFFICIENT IN AN ENRICHED, WATER REACTOR
Journal Article
·
· Nuclear Sci. and Eng.
OSTI ID:4830991
An experimental and analytical study of the void coefficient of reactivity in the Ford Nuclear Reactor (a fully enriched, swimming pool type) was made. A stream of air bubbles was used to introduce voids. Out-of-pile calibration of the air flow system was necessary to account for variation in bubble rise velocity with average air concentration. This method is extremely simple except for the calibration procedure. With the results presented, the void coefficients of other reactors with similar fuel elements (18 plate, BSR type) can be measured without the necessity for recalibration. For the calculation of uniformly distributed void coefficients, relatively simple two- group diffusion theory is shown to be accurate provided the variation of leakage in all three dimensions is taken into account. This variation of leakage is computed by the use of a buckling iterative procedure. Second order effects, such as the variation of effective thermal neutron temperature and disadvantage factor, may be neglected. For the calculation of localized void effects, the buckling iteration method is inaccurate due to the nonseparability of axial and radial flux. distribution in this small core. To improve the accuracy an extension of this method to several region iteration is suggested. The principal value of this type of calculation is the short computer time required. (auth)
- Research Organization:
- Univ. of Michigan, Ann Arbor
- NSA Number:
- NSA-16-018629
- OSTI ID:
- 4830991
- Journal Information:
- Nuclear Sci. and Eng., Journal Name: Nuclear Sci. and Eng. Vol. Vol: 12
- Country of Publication:
- Country unknown/Code not available
- Language:
- English
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Sat Dec 31 23:00:00 EST 1983
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·
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Related Subjects
BUBBLES
BUCKLING
DIFFERENTIAL EQUATIONS
DIFFUSION
DISTRIBUTION
EQUATIONS
FNR
GAS FLOW
GROUP THEORY
LOSSES
MEASURED VALUES
NEUTRON FLUX
NEUTRONS
PROGRAMMING
REACTIVITY
REACTOR CORE
REACTOR TECHNOLOGY
REACTORS
RESEARCH REACTORS
SWIMMING POOL
TEMPERATURE
VARIATIONS
VELOCITY
WATER COOLANT
WATER MODERATOR
ZONES
BUCKLING
DIFFERENTIAL EQUATIONS
DIFFUSION
DISTRIBUTION
EQUATIONS
FNR
GAS FLOW
GROUP THEORY
LOSSES
MEASURED VALUES
NEUTRON FLUX
NEUTRONS
PROGRAMMING
REACTIVITY
REACTOR CORE
REACTOR TECHNOLOGY
REACTORS
RESEARCH REACTORS
SWIMMING POOL
TEMPERATURE
VARIATIONS
VELOCITY
WATER COOLANT
WATER MODERATOR
ZONES