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UNIVERSITY OF BUCHAREST
FACULTY OF PHYSICS Guest
2024-11-22 1:49 |
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Conference: Bucharest University Faculty of Physics 2001 Meeting
Section: Nuclear and Elementary Particles Physics
Title:
MONTE CARLO CRITICALITY CALCULATIONS FOR
THE CANDU SPENT FUEL
Authors:
Cristina Alice Margeanu, Prof. Dr. Tatiana Angelescu
Affiliation:
Institute for Nuclear Research Pitesti,
P.O. Box 78, Pitesti, e-mail: malice@cc.nuclear.ro
Faculty of Physics, University of Bucharest,
P.O. Box MG12, Bucharest
E-mail
Keywords:
Abstract:
The major goal for the spent fuel storage follows to ensure the appropriate time range for deactivation and reduction of the spent nuclear fuel radioactivity. In these terms, a basic demand consist in maintaining the fuel bundles sheath integrity in order to eliminate the uncontrolled escape of fission products in the environment.
In order to perform a safety analysis criticality calculations are needed, that means determination of the neutron multiplication factor for the system.
In the paper, for criticality calculations the KENO VI 3D Monte Carlo code, integrated in SCALE programs package, was used. The neutron effective multiplication factor was calculated both in normal conditions and accidental scenarios for intermediate storage of the CANDU spent fuel bundles.
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