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UNIVERSITY OF BUCHAREST
FACULTY OF PHYSICS Guest
2024-11-22 2:11 |
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Conference: Bucharest University Faculty of Physics 2003 Meeting
Section: Nuclear and Elementary Particles Physics
Title:
Shielding Calculations for Spent CANDU Fuel Transport Cask
Authors:
Cristina Alice Mărgeanu, Prof. Dr. Tatiana Angelescu
Affiliation:
Institute for Nuclear Research Pitesti,
University of Bucharest
E-mail
Keywords:
Abstract:
CANDU spent fuel discharged from the reactor core contains Pu, so it must be stressed in two directions: tracing for the fuel reactivity in order to prevent critical mass formation and personnel protection during the spent fuel manipulation.
Shielding analyses, an essential component of the nuclear safety, take into account for the difficulties occurred during the manipulation, transport and storage of spent fuel bundles, both for personnel protection and impact on the environmental. The main objective here consists in estimations on radiation doses in order to reduce them under specified limitation values.
In order to perform the shielding calculations for the spent fuel transport cask three different codes were used: XSDOSE code and MORSE-SGC code, both incorporated in the SCALE4.4a system, and PELSHIE-3 code, respectively.
As source of radiation one spent standard CANDU fuel bundle was used. All the geometrical and material data, related to the transport cask, were considered according to the shipping cask type B model, whose prototype has been realized and tested in the Institute for Nuclear Research Pitesti.
The radial gamma dose rates estimated to the cask wall and in air, at different distances from the cask, are presented together with a comparison between the dose rates values obtained by all three recipes of shielding calculations.
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