Method of pair exchange of fuel assemblies and its use in optimizing the energy distribution of water-cooled/water-moderated reactors

Journal Article · Sun Mar 01 00:00:00 EST 1987 · Sov. At. Energy (Engl. Transl.); (United States)

OSTI ID:5690181

Simonov, V D; Pavlov, V I; Perminov, A A; Pechikin, V A; Filimonov, P E; Yuskov, A M

The authors review various computer codes for determining the power distribution and optimizing the fueling procedure for water cooled and moderated reactors and assess their relative efficiencies in terms of computation time required. The algorithms take into account reactivity coefficients and neutron diffusion theory. A sensitivity analysis of the codes is given and steps are outlined for implementation of the codes for various reactor core configurations.

• OSTI ID: 5690181
• Journal Information: Sov. At. Energy (Engl. Transl.); (United States), Vol. 61:3; Other Information: Translated from At. Energ.; 61: No. 3, 166-169(Sep 1986)
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
COMPUTER CODES
COMPARATIVE EVALUATIONS
SENSITIVITY ANALYSIS
WATER COOLED REACTORS
COMPUTERIZED SIMULATION
POWER DISTRIBUTION
REACTOR FUELING
WATER MODERATED REACTORS
D CODES
EFFICIENCY
FUEL ASSEMBLIES
NEUTRON TRANSPORT THEORY
OPTIMIZATION
P CODES
REACTIVITY COEFFICIENTS
REACTOR KINETICS
REVIEWS
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WWER TYPE REACTORS
DOCUMENT TYPES
ENRICHED URANIUM REACTORS
KINETICS
PWR TYPE REACTORS
REACTORS
SIMULATION
THERMAL REACTORS
TRANSPORT THEORY
210100* - Power Reactors
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210200 - Power Reactors
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