Calculating fission product inventories in Peach Bottom FTE-4 fuel rods using the ORIGEN code

Davis, W Jr; Kee, C W; Vaughen, V C.A.; Tobias, M L

doi:10.2172/7129425

Title: Calculating fission product inventories in Peach Bottom FTE-4 fuel rods using the ORIGEN code

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Abstract

Nondestructive gamma-ray analyses (NDA) for fission products and mass-spectrometric analyses for five uranium isotopes in two samples of fuel removed from the Peach Bottom reactor have been compared with corresponding quantities calculated from reactor operating data using the ORIGEN code to form the basis for material balance calculations in head-end reprocessing steps. Satisfactory agreement between ORIGEN results and measured uranium isotopic distributions as found with the standard ORIGEN inputs. Many fission products of interest, including /sup 89/Sr, /sup 91/Y, /sup 95/Zr, /sup 95/Nb, /sup 103/Ru, /sup 106/Ru, /sup 127/Te*, /sup 129/Te*, /sup 131/I, /sup 134/Cs, and /sup 144/Ce, have half-lives that are less than about 2 years. Comparisons of ORIGEN calculations and NDA values for /sup 95/Zr, /sup 106/Ru, /sup 125/Sb, /sup 134/Cs, /sup 144/Ce, and /sup 154/Eu demonstrated the need to include realistic reactor operating data, including shutdown times, in the ORIGEN input parameters.

Authors:: Davis, W Jr; Kee, C W; Vaughen, V C.A.; Tobias, M L

Publication Date:: Tue Jun 01 00:00:00 EDT 1976

Research Org.:: Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

OSTI Identifier:: 7129425

Report Number(s):: ORNL/TM-5691
TRN: 77-005633

DOE Contract Number:: W-7405-ENG-26

Resource Type:: Technical Report

Country of Publication:: United States

Language:: English

Subject:: 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; PEACH BOTTOM-1 REACTOR; SPENT FUEL ELEMENTS; COMPUTER CALCULATIONS; FISSION PRODUCTS; O CODES; QUANTITATIVE CHEMICAL ANALYSIS; CHEMICAL ANALYSIS; COMPUTER CODES; ENRICHED URANIUM REACTORS; FUEL ELEMENTS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HELIUM COOLED REACTORS; HTGR TYPE REACTORS; ISOTOPES; POWER REACTORS; RADIOACTIVE MATERIALS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; 210300* - Power Reactors, Nonbreeding, Graphite Moderated

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                    Davis, W Jr, Kee, C W, Vaughen, V C.A., and Tobias, M L. Calculating fission product inventories in Peach Bottom FTE-4 fuel rods using the ORIGEN code.  United States: N. p., 1976. 
        Web.  doi:10.2172/7129425.

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                    Davis, W Jr, Kee, C W, Vaughen, V C.A., & Tobias, M L. Calculating fission product inventories in Peach Bottom FTE-4 fuel rods using the ORIGEN code.  United States.  https://doi.org/10.2172/7129425

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                    Davis, W Jr, Kee, C W, Vaughen, V C.A., and Tobias, M L. 1976.  
        "Calculating fission product inventories in Peach Bottom FTE-4 fuel rods using the ORIGEN code".  United States.  https://doi.org/10.2172/7129425.  https://www.osti.gov/servlets/purl/7129425.

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@article{osti_7129425,

  title        = {Calculating fission product inventories in Peach Bottom FTE-4 fuel rods using the ORIGEN code},

  author       = {Davis, W Jr and Kee, C W and Vaughen, V C.A. and Tobias, M L},

  abstractNote = {Nondestructive gamma-ray analyses (NDA) for fission products and mass-spectrometric analyses for five uranium isotopes in two samples of fuel removed from the Peach Bottom reactor have been compared with corresponding quantities calculated from reactor operating data using the ORIGEN code to form the basis for material balance calculations in head-end reprocessing steps. Satisfactory agreement between ORIGEN results and measured uranium isotopic distributions as found with the standard ORIGEN inputs. Many fission products of interest, including /sup 89/Sr, /sup 91/Y, /sup 95/Zr, /sup 95/Nb, /sup 103/Ru, /sup 106/Ru, /sup 127/Te*, /sup 129/Te*, /sup 131/I, /sup 134/Cs, and /sup 144/Ce, have half-lives that are less than about 2 years. Comparisons of ORIGEN calculations and NDA values for /sup 95/Zr, /sup 106/Ru, /sup 125/Sb, /sup 134/Cs, /sup 144/Ce, and /sup 154/Eu demonstrated the need to include realistic reactor operating data, including shutdown times, in the ORIGEN input parameters.},

  doi          = {10.2172/7129425},

  url          = {https://www.osti.gov/biblio/7129425},
  journal      = {},
number       = ,

  volume       = ,

  place        = {United States},

  year         = {Tue Jun 01 00:00:00 EDT 1976},

  month        = {Tue Jun 01 00:00:00 EDT 1976}

}

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