Estimating Public Dose Along Hypothetical Spent Nuclear Fuel Transportation Routes
Creators
- 1. Oak Ridge National Laboratory Bethel Valley Road, Oak Ridge, Tenn., 37831, United States (United States)
Description
In the future, it will be necessary to transport large quantities of spent nuclear fuel (SNF) from nuclear power plant sites to an interim storage facility (ISF) or a repository when such a facility is available. Because it is impossible to shield all of the radiation from this material, the general public will receive a very small, but quantifiable, dose from this transportation campaign. This paper describes the estimated collective effective radiation dose to the public due to SNF shipments under routine conditions and compares the estimated dose figures to the natural background radiation dose. To determine the estimated collective effective dose to the public, this analysis uses the US Department of Energy's (DOE) Stakeholder Tool for Assessing Radioactive Transportation (START), a geographic information system (GIS) routing tool, and a set of unit dose factors (UDFs) which were developed to calculate the estimated dose to the public along transportation routes. The estimated doses of radiation to which the public would be exposed during shipments of SNF is expected to be a consideration, along with many other factors, when making routing decisions. In all cases studied in this paper, estimated doses to the public will be orders of magnitude lower than the natural background radiation dose and will meet all US federal regulatory requirements for radiation dose/exposure to members of the public. The sample routes analyzed in this paper are expected to be representative of future SNF shipment routes in terms of length and mode of transportation, although they do not represent actual routes or destinations. This paper considers four routes from two shutdown reactor sites to two destinations. It must be noted that the specified origin sites are not necessarily the first sites under consideration for a de-inventory process. Further, the destination sites reviewed in this report are only to illustrate estimated dose figures along different routes and should not be taken as potential sites for an ISF or repository. For illustrative purposes only, the shortest distance rail route was found between each origin and destination point, and the collective effective dose to the public from the SNF cask was estimated along each route. This paper is not intended to make recommendations for routing decisions, but rather is intended to inform further discussion about the transportation of SNF and other radioactive materials
Additional details
Publishing Information
- Journal Title
- Transactions of the American Nuclear Society
- Journal Volume
- 116
- Journal Page Range
- p. 229-232
- ISSN
- 0003-018X
Conference
- Title
- 2017 Annual Meeting of the American Nuclear Society
- Dates
- 11-15 Jun 2017
- Place
- San Francisco, CA (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 52087774
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BACKGROUND RADIATION; EFFECTIVE RADIATION DOSES; GEOGRAPHIC INFORMATION SYSTEMS; NUCLEAR POWER PLANTS; RADIATION PROTECTION; RADIOACTIVE MATERIALS; REACTOR SHUTDOWN; REACTOR SITES; RECOMMENDATIONS; ROUTING; SHIELDS; SPENT FUEL CASKS; SPENT FUELS; STORAGE FACILITIES; WASTE STORAGE; WASTE TRANSPORTATION
- Descriptors DEC
- CASKS; CONTAINERS; DOSES; ENERGY SOURCES; FUELS; INFORMATION SYSTEMS; MANAGEMENT; MATERIALS; NUCLEAR FACILITIES; NUCLEAR FUELS; POWER PLANTS; RADIATION DOSES; RADIATIONS; REACTOR LIFE CYCLE; REACTOR MATERIALS; SHUTDOWN; STORAGE; THERMAL POWER PLANTS; WASTE MANAGEMENT
Optional Information
- Notes
- 6 refs.; available from American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (US)