Effects of spent fuel types on offsite consequences of hypothetical accidents

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Argonne National Laboratory (ANL) conducts experimental work on the development of waste forms suitable for several types of spent fuel at its facility on the Idaho National Engineering and Environmental Laboratory (INEEL) located 48 km West of Idaho Falls, ID. The objective of this paper is to compare the offsite radiological consequences of hypothetical accidents involving the various types of spent nuclear fuel handled in nonreactor nuclear facilities. The highest offsite total effective dose equivalents (TEDEs) are estimated at a receptor located about 5 km SSE of ANL facilities. Criticality safety considerations limit the amount of enriched uranium and plutonium ... continued below

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20 p.

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Courtney, J. C.; Dwight, C. C. & Lehto, M. A. February 18, 2000.

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  • Argonne National Laboratory
    Publisher Info: Argonne National Laboratory, Argonne, IL (United States)
    Place of Publication: Argonne, Illinois

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Argonne National Laboratory (ANL) conducts experimental work on the development of waste forms suitable for several types of spent fuel at its facility on the Idaho National Engineering and Environmental Laboratory (INEEL) located 48 km West of Idaho Falls, ID. The objective of this paper is to compare the offsite radiological consequences of hypothetical accidents involving the various types of spent nuclear fuel handled in nonreactor nuclear facilities. The highest offsite total effective dose equivalents (TEDEs) are estimated at a receptor located about 5 km SSE of ANL facilities. Criticality safety considerations limit the amount of enriched uranium and plutonium that could be at risk in any given scenario. Heat generated by decay of fission products and actinides does not limit the masses of spent fuel within any given operation because the minimum time elapsed since fissions occurred in any form is at least five years. At cooling times of this magnitude, fewer than ten radionuclides account for 99% of the projected TEDE at offsite receptors for any credible accident. Elimination of all but the most important nuclides allows rapid assessments of offsite doses with little loss of accuracy. Since the ARF (airborne release fraction), RF (respirable fraction), LPF (leak path fraction) and atmospheric dilution factor ({chi}/Q) can vary by orders of magnitude, it is not productive to consider nuclides that contribute less than a few percent of the total dose. Therefore, only {sup 134}Cs, {sup 137}Cs-{sup 137m}Ba, and the actinides significantly influence the offsite radiological consequences of severe accidents. Even using highly conservative assumptions in estimating radiological consequences, they remain well below current Department of Energy guidelines for highly unlikely accidents.

Physical Description

20 p.

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INIS; OSTI as DE00751924

Medium: P; Size: 20 pages

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  • Waste Management 2000 Conference, Tucson, AZ (US), 02/27/2000--03/02/2000

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  • Report No.: ANL/NT/CP-101144
  • Grant Number: W-31109-ENG-38
  • Office of Scientific & Technical Information Report Number: 751924
  • Archival Resource Key: ark:/67531/metadc712278

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  • February 18, 2000

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  • Sept. 12, 2015, 6:31 a.m.

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  • April 7, 2017, 7:12 p.m.

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Courtney, J. C.; Dwight, C. C. & Lehto, M. A. Effects of spent fuel types on offsite consequences of hypothetical accidents, article, February 18, 2000; Argonne, Illinois. (digital.library.unt.edu/ark:/67531/metadc712278/: accessed October 23, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.