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Title: Estimation of Dose from Potential Radionuclide Emissions from the Sample Preparation Laboratory at the Materials and Fuels Complex

Technical Report ·
DOI:https://doi.org/10.2172/1498266· OSTI ID:1498266

The Sample Preparation Laboratory (SPL) at the Materials and Fuels Complex will perform sample preparation, examination, and mechanical-property testing of highly irradiated materials. The purpose of this report is to document calculation of the estimated dose at public receptor locations from potential radionuclide releases to the atmosphere from SPL. Atmospheric dispersion and dose calculations were performed with the computer model CAP88-PC Version 4 in accordance with the requirements of Code of Federal Regulations (CFR), Title 40, “Protection of the Environment,” Part 61, “National Emission Standards for Hazardous Air Pollutants (NESHAPs),” Subpart H, “National Emission Standards for Emissions of Radionuclides Other than Radon from Department of Energy Facilities” (40 CFR 61, Subpart H 2010). Emission potentials were calculated based on the methodology in 40 CFR Part 61, Appendix D and additional guidance/approval by EPA Region 10 [see letter from Donald Dossett (EPA Region 10) to Tim Safford (DOE-ID), Oct 19, 2017 (CCN 241475)] for solid materials that undergo heating. Estimates of total effective dose are based on low-level chronic exposure. The potential maximum dose to a member of the public was calculated to be 0.02 mrem/year based on an estimated 16 g of the 30 kg source term (0.053%) being exposed to very high temperatures associated with electrical-discharge machining (EDM) and the remaining material heated to 100°C. Calculations show the maximum dose could be as high as 0.05 mrem/year if the remaining material were heated to 1400°C (i.e., the melting point of stainless steel). The potential maximum dose to a public receptor from emissions at SPL is not expected to exceed 0.1 mrem/year (1% of the standard) so long as the material impacted by EDM does not exceed 56 g (3.5 times the expected mass of 16 g and less than 0.2% of the total source term), and the remaining material is not heated to temperatures greater than 1400°C. It should be noted that credit for HEPA filtration does not impact the dose results because the dose is dominated by radionuclides that have exceeded their boiling point; thus, no credit for HEPA filtration may be applied to the emission factor.

Research Organization:
Idaho National Lab. (INL), Idaho Falls, ID (United States)
Sponsoring Organization:
USDOE
DOE Contract Number:
AC07-05ID14517
OSTI ID:
1498266
Report Number(s):
INL/MIS-18-51177-Rev000
Country of Publication:
United States
Language:
English