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UNIVERSITY OF BUCHAREST
FACULTY OF PHYSICS Guest
2024-11-22 2:07 |
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Conference: Bucharest University Faculty of Physics 2006 Meeting
Section: Nuclear and Elementary Particles Physics
Title:
Radiation doses estimation in an abnormal operational scenario for radioactive waste disposal in vaults,
by using monte carlo methodology
Authors:
Cristina Alice Margeanu, Petre Ilie
Affiliation:
INSTITUTE FOR NUCLEAR RESEARCH PITESTI
E-mail
malice@scn.ro
Keywords:
near surface disposal, waste package, operational scenario, external exposure, radiation dose
Abstract:
All human activities involving actual or potential exposure to ionizing radiation, including radioactive waste management, require implementation of measures for protection of human and the environment. Radioactive waste must be managed safely, according to internationally agreed safety standards.
Near surface disposal is an option used by many countries for the disposal of radioactive waste containing mainly short lived radionuclides and low concentrations of long lived radionuclides. This disposal option requires design and operational measures to be provided for the human health and the environment protection, both during disposal facility operation and following its closure.
A scenario characterizing a near surface disposal safety analysis during the operational phase was considered: dropping and crushing of a waste package to be disposed into a vault during unloading.
The considered scenario is possible in operating a vault; it corresponds to an abnormal situation. Exposure to workers will be principally due to direct irradiation and especially in case of damage of the waste package during repository operation. Vaults are generally operated in open air and the dilution volume is important, hence inhalation will be low.
The waste is immobilized in a concrete matrix and packaged in a 220 l standard metallic drum. The radioactive waste package was modeled as a uniform radiation source, consistent with radioactive waste management national regulations. After the waste package dropping and crushing on the ground, the concrete and the biological shielding are supposed to be destroyed and the waste spreads on a 1 m2 area.
The paper follows to estimate the radiation doses collected by an operator sitting in the crane cab and operating the waste package, and, also, by a worker sitting on the ground level in the vault, due to the external exposure. For the estimations, the Monte Carlo MORSE-SGC shielding code will be used.
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