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UNIVERSITY OF BUCHAREST
FACULTY OF PHYSICS Guest
2024-11-23 17:56 |
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Conference: Bucharest University Faculty of Physics 2002 Meeting
Section: Nuclear and Elementary Particles Physics
Title:
Monte Carlo Method Application to
Shielding Calculations
Authors:
Cristina Alice Mărgeanu*, Prof. Dr. Tatiana Angelescu**
Affiliation:
* Institute for Nuclear Research Pitești, P.O. Box 78, Pitesti
** University of Bucharest, P.O. Box MG-12, Magurele, 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.
The basic tasks accomplished by the shielding calculations in a nuclear safety analysis consist in dose rates calculations in order to prevent any risks both for personnel protection and impact on the environment during the spent fuel manipulation, transport and storage.
To perform photon dose rates calculations the Monte Carlo MORSE-SGC code incorporated in SAS4 sequence from SCALE system was used.
The paper objective was to obtain the photon dose rates to the spent fuel transport cask wall, both in radial and axial directions.
As source of radiation one spent 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.
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