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UNIVERSITY OF BUCHAREST
FACULTY OF PHYSICS Guest
2024-11-22 2:09 |
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Conference: Bucharest University Faculty of Physics 2007 Meeting
Section: Nuclear and Elementary Particles Physics
Title:
Radiation doses assessment in some operational scenarios
for radioactive waste disposal in a near surface repository,
by using monte carlo methodology
Authors:
Cristina Alice Margeanu, Petre Ilie, Sorin Margeanu, Tatiana Angelescu *
Affiliation:
Institute for Nuclear Research Pitesti,PO.Box-78, 115400-Pitesti, Romania
*Faculty of Physics, University of Bucharest, PO.Box MG-12, Bucharest, Romania
E-mail
malice@scn.ro
Keywords:
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.
The paper goal is to apply Monte Carlo methodology to radiological impact estimation for some scenarios characterizing the near surface repository operational phase.
Two operational scenarios were considered, namely: a normal operation scenario (workers exposure to external irradiation due to the stored waste packages) and an abnormal operation scenario (workers exposure to external irradiation due to the dropping and crushing of a waste package during storage into the disposal cell).
The waste is immobilized in a concrete matrix, packaged in a 400 l standard metallic drum or a 290 l fiber reinforced-concrete container (CBF), and 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.
For both scenarios, the paper follows to estimate, by means of Monte Carlo MORSE-SGC shielding code, the radiation doses collected by the operator sitting in the crane cab and transporting the waste package, and, also, by the workers sitting on the ground level in the disposal cell and operating the waste package, due to the external exposure.
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