Calculating fission product inventories in Peach Bottom FTE-4 fuel rods using the ORIGEN code
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.
- Research Organization:
- Oak Ridge National Lab., Tenn. (USA)
- DOE Contract Number:
- W-7405-ENG-26
- OSTI ID:
- 7129425
- Report Number(s):
- ORNL/TM-5691
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210300* -- Power Reactors
Nonbreeding
Graphite Moderated
CHEMICAL ANALYSIS
COMPUTER CALCULATIONS
COMPUTER CODES
ENRICHED URANIUM REACTORS
FISSION PRODUCTS
FUEL ELEMENTS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HELIUM COOLED REACTORS
HTGR TYPE REACTORS
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O CODES
PEACH BOTTOM-1 REACTOR
POWER REACTORS
QUANTITATIVE CHEMICAL ANALYSIS
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SPENT FUEL ELEMENTS
THERMAL REACTORS
210300* -- Power Reactors
Nonbreeding
Graphite Moderated
CHEMICAL ANALYSIS
COMPUTER CALCULATIONS
COMPUTER CODES
ENRICHED URANIUM REACTORS
FISSION PRODUCTS
FUEL ELEMENTS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HELIUM COOLED REACTORS
HTGR TYPE REACTORS
ISOTOPES
O CODES
PEACH BOTTOM-1 REACTOR
POWER REACTORS
QUANTITATIVE CHEMICAL ANALYSIS
RADIOACTIVE MATERIALS
REACTOR COMPONENTS
REACTORS
SPENT FUEL ELEMENTS
THERMAL REACTORS