Conditional Release of Steel From Decommissioning in a Form of Reinforced Concrete

Pritrsky, Jozef; Brodňan, Miroslav; Nečas, Vladimı́r

doi:10.1115/icem2011-59058

Cited by 2 publications

(1 citation statement)

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“…• the dust concentration the air • the time spent in the dust plume • the breathing rate • the dose factor for inhalation [8] Our conservative assumptions were that the worker spent working time 2000 h/y in the dust plume for variant without optimization (800 h/y with optimization variant), rubble initial activity 1000 Bq for all radionuclides, assumed dust concentration was 1E-06 kg/m 3 and breathing rate 1.2 m 3 /h. Derived clearance levels for inhalation exposure pathway are given in Table 7 and Table 8.…”

Section: Inhalation Exposure Pathwaymentioning

confidence: 99%

Conditional clearance of radioactive demolition waste in motorway scenario

Novak¹,

Pritrsky²,

Daniska

et al. 2014

Progress in Nuclear Science and Technology

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The paper describes the model application of conditional clearance radioactive demolition waste arising from decommissioning of nuclear power plants and the calculation of individual effective dose absorbed during construction and operation stage of motorway. Large quantities of materials with very low level radioactivity may occur during the decommissioning of NPPs after the end of its lifetime or after a nuclear accident. Part of the decommissioning waste consists of the contaminated demolition waste, which is necessary to be processed and stored on a designated storage sites or disposed. The construction of such stores or repositories requires significant financial and material resources. Possible solving of this issue is conditional clearance of very low level radioactive waste and its reuse in construction of roads, where they are incorporated for 50 to 100 years. This period is necessary for natural radioactive decay of radionuclides to the levels applicable for unconditional clearance. The foundation of a road represents a significant potential for recycling of concrete rubble from the decommissioning. Calculation of external exposure was performed by means of VISIPLAN 3D ALARA, internal exposure due to inhalation was calculated by AMBER 5.4. The outputs of calculations are the individual effective dose absorbed during working activities from all relevant exposure pathways. Final results include clearance levels -specific mass activities of demolition waste designated for clearance.

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Section: Inhalation Exposure Pathwaymentioning

confidence: 99%