US Light-Water Reactor spent fuel inventory-fissile distribution

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Those conducting waste management studies to reduce the potential for a nuclear criticality accident in a future geological repository must examine the quantities and distribution of fissile isotopes that are present in discharged boiling-water reactor (BWR) and pressurized-water reactor (PWR) spent nuclear fuel (SNF) scheduled for disposition. The major fissile isotopes present in LWR fuels that impact criticality safety are the nuclides, {sup 235}U, {sup 239}Pu, and {sup 24l}Pu. The sum of the quantities of these three nuclides, expressed as a percentage of the total amount of all U and Pu isotopes present in a batch of discharged fuel, determines ... continued below

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7 p.

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Ashline, R.C. & Forsberg, C.W. November 8, 1995.

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Description

Those conducting waste management studies to reduce the potential for a nuclear criticality accident in a future geological repository must examine the quantities and distribution of fissile isotopes that are present in discharged boiling-water reactor (BWR) and pressurized-water reactor (PWR) spent nuclear fuel (SNF) scheduled for disposition. The major fissile isotopes present in LWR fuels that impact criticality safety are the nuclides, {sup 235}U, {sup 239}Pu, and {sup 24l}Pu. The sum of the quantities of these three nuclides, expressed as a percentage of the total amount of all U and Pu isotopes present in a batch of discharged fuel, determines the final enrichment of the fuel batch under consideration. The final enrichment provides an approximate measure of the nuclear criticality potential. As the final enrichment increases, the mass, geometry, or administrative controls that must be in place to prevent nuclear criticality become more stringent. Below an enrichment of about 0.7%, however, criticality is no longer a concern because the infinite multiplication factor for any heterogeneous or homogeneous mixture of fuel and water, even under conditions of optimum moderation, is less than unity. The current study examines the distribution of the final enrichment of the LWR SNF which was discharged through December 31, 1993, and which currently resides in the fuel storage pools of the various utilities or in one of several AFR facilities.

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7 p.

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INIS; OSTI as DE96004934

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  • 7. annual international high-level radioactive waste management conference, Las Vegas, NV (United States), 29 Apr - 3 May 1996

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  • Other: DE96004934
  • Report No.: CONF-960421--4
  • Grant Number: AC05-84OR21400
  • Office of Scientific & Technical Information Report Number: 197840
  • Archival Resource Key: ark:/67531/metadc668431

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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.

Office of Scientific and Technical Information (OSTI) is the Department of Energy (DOE) office that collects, preserves, and disseminates DOE-sponsored research and development (R&D) results that are the outcomes of R&D projects or other funded activities at DOE labs and facilities nationwide and grantees at universities and other institutions.

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  • November 8, 1995

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  • June 29, 2015, 9:42 p.m.

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  • June 27, 2016, 3:04 p.m.

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Ashline, R.C. & Forsberg, C.W. US Light-Water Reactor spent fuel inventory-fissile distribution, article, November 8, 1995; Tennessee. (digital.library.unt.edu/ark:/67531/metadc668431/: accessed October 20, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.