Issues related to estimating potential radiological doses from treatment, storage, and disposal facilities handling waste containing trace amounts of radioactive material

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A simplified calculational model has been developed to permit a rapid, yet realistic, estimate of potential radiological doses to on-site workers and the off-site public from waste-handling operations at a treatment, storage, and disposal (TSD) facility. The waste-handling operations include transport, handling, storage, incineration, and landfilling of waste containing trace amounts of radioactive materials. The main objective of the model is to provide a radiological assessment methodology that can be used in a waste clearance strategy that addresses US Department of Energy mixed-waste moratorium issues. The model was developed on the basis of previous detailed studies of eight TSD facilities ... continued below

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10 p.

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Stevens, L.E.; Nimmagadda, M.; LePoire, D.; Chen, S.Y.; Ma, C.W.; Wheeler, T. et al. August 1, 1995.

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Description

A simplified calculational model has been developed to permit a rapid, yet realistic, estimate of potential radiological doses to on-site workers and the off-site public from waste-handling operations at a treatment, storage, and disposal (TSD) facility. The waste-handling operations include transport, handling, storage, incineration, and landfilling of waste containing trace amounts of radioactive materials. The main objective of the model is to provide a radiological assessment methodology that can be used in a waste clearance strategy that addresses US Department of Energy mixed-waste moratorium issues. The model was developed on the basis of previous detailed studies of eight TSD facilities and incorporates the essential features of such a facility. The model provides a simplified physical concept of the potential human exposure associated with the radioactive contents of the chemical wastes. Issues pertaining to the development of the model, as well as application and future use, are discussed. Specifically, these issues include physical model approximations, isotope selection, waste-handling operations, and selection of input parameters. Also, pathway and isotope selection criteria are discussed relative to the previous TSD sites studied. This model is being considered for additional development as a waste clearance strategy tool.

Physical Description

10 p.

Notes

INIS; OSTI as DE95015636

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  • ER `95: environmental remediation conference: committed to results, Denver, CO (United States), 13-18 Aug 1995

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  • Other: DE95015636
  • Report No.: ANL/EA/CP--86245
  • Report No.: CONF-950868--12
  • Grant Number: W-31109-ENG-38
  • Office of Scientific & Technical Information Report Number: 106508
  • Archival Resource Key: ark:/67531/metadc621560

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Office of Scientific & Technical Information Technical Reports

Reports, articles and other documents harvested from the Office of Scientific and Technical Information.

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  • August 1, 1995

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  • June 16, 2015, 7:43 a.m.

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  • Dec. 15, 2015, 6:07 p.m.

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Stevens, L.E.; Nimmagadda, M.; LePoire, D.; Chen, S.Y.; Ma, C.W.; Wheeler, T. et al. Issues related to estimating potential radiological doses from treatment, storage, and disposal facilities handling waste containing trace amounts of radioactive material, article, August 1, 1995; Illinois. (digital.library.unt.edu/ark:/67531/metadc621560/: accessed October 23, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.