Analysis of Radiation Doses from Operation of Postulated Commercial Spent Fuel Transportation Systems

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Description

This report contains a system study of estimated radiation doses to the public and workers resulting from the transport of spent fuel from commercial nuclear power reactors to a geologic repository. The report contains a detailed breakdown of activities and a description of time/distance/dose-rate estimates for each activity within the system. Collective doses are estimated for each of the major activities at the reactor site, in transit, and at the repository receiving facility. Annual individual doses to the maximally exposed individuals or groups of individuals are also estimated. A total of 17 alternatives and subalternatives to the postulated reference transportation … continued below

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318 p.; ill.

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Schneider, K. J.; Hostick, C. J.; Ross, W. A.; Peterson, R. W.; Smith, R. I.; Stiles, D. L. et al. November 1, 1987.

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Description

This report contains a system study of estimated radiation doses to the public and workers resulting from the transport of spent fuel from commercial nuclear power reactors to a geologic repository. The report contains a detailed breakdown of activities and a description of time/distance/dose-rate estimates for each activity within the system. Collective doses are estimated for each of the major activities at the reactor site, in transit, and at the repository receiving facility. Annual individual doses to the maximally exposed individuals or groups of individuals are also estimated. A total of 17 alternatives and subalternatives to the postulated reference transportation system are identified, conceptualized, and their dose-reduction potentials and costs estimated. Resulting ratios of ..delta..cost/..delta..collective system dose for each alternative relative to the postulated reference transportation system are given. Most of the alternatives evaluated are estimated to provide both cost and dose reductions. Major reductions in transportation system dose and cost are estimated to result from using higher-capacity rail and truck casks, and particularly when replacing legalweight truck casks with ''advanced design'' overweight truck casks. The greatest annual dose reduction to the highest exposed individual workers (i.e., at the repository) is estimated to be achieved by using remote handling equipment for the cask handling operations at the repository. Additional shielding is also effective in reducing doses to both radiation workers at the reactor and repository and to transport workers. 69 refs., 36 figs., 156 tabs.

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318 p.; ill.

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NTIS, PC 13.

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  • Other Information: Includes 6 sheets of 24x reduction microfiche

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  • November 1, 1987

Added to The UNT Digital Library

  • Jan. 22, 2018, 7:23 a.m.

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  • Nov. 4, 2020, 8:11 a.m.

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Schneider, K. J.; Hostick, C. J.; Ross, W. A.; Peterson, R. W.; Smith, R. I.; Stiles, D. L. et al. Analysis of Radiation Doses from Operation of Postulated Commercial Spent Fuel Transportation Systems, report, November 1, 1987; United States. (https://digital.library.unt.edu/ark:/67531/metadc1058345/: accessed May 30, 2024), University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.

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