Evaluation of Doses to an Individual from a Contaminated Area with Radioactive Material
Creators
- 1. Nuclear and Radiological Regulatory Authority (ENRRA), Cairo (Egypt)
Description
Nuclear facilities require characterization and documentation of planning and decision-making for decontamination and decommissioning (D and D) projects. These projects illustrate residual radioactivity levels at their sites, to determine whether radiologically contaminated building sand structures can be free released for a specific land residential or industrial use. The aim of this work is to evaluate the potential radiological dose incurred by a worker who works in a radiochemistry laboratory contaminated with residual radioactive material using RESRAD-BUILD computer code. The hypothetical worker is assumed to perform laboratory activities for one year. Clean-up scenario is considered for hypothetical sources of (60 Co, 90 Sr and 13'7 Cs) contaminated materials. Implementation of the RESRAD-BUILD shows the impacts of occupancy scenarios in terms of potential dosages of receptors. The results from the exposure to a human receptor from the radioactive contamination at the be ginning was 1.08 E-05 mSv/year and reduced to 8.65 E-06 after one year. The results can help for site-specific analysis and getting derived concentration guide line Levels (DCGLs) for building surfaces
Additional details
Publishing Information
- Journal Title
- Arab Journal of Nuclear Sciences and Applications
- Journal Volume
- 50
- Journal Issue
- 2
- Journal Page Range
- p. 250-257
- ISSN
- 1110-0451
- CODEN
- AJNADV
INIS
- Country of Publication
- Egypt
- Country of Input or Organization
- Egypt
- INIS RN
- 48044360
- Subject category
- S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES;
- Descriptors DEI
- AIR FLOW; BUILDINGS; CONTAMINATION; NUCLEAR FACILITIES; RADIOACTIVE MATERIALS; RADIOCHEMISTRY; RECEPTORS
- Descriptors DEC
- CHEMISTRY; FLUID FLOW; GAS FLOW; MATERIALS; MEMBRANE PROTEINS; ORGANIC COMPOUNDS; PROTEINS