ANL Pre Analysis of the SHEBA/CERES Experiment

Technical Report · Thu Nov 11 00:00:00 EST 1999

DOI:https://doi.org/10.2172/757501· OSTI ID:757501

Palmiotti, G. ^[1]; Smith, M. ^[2]; Klann, R. ^[1]; Fujita, E. ^[1]; Imel, G. ^[1]

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1. Argonne National Lab. (ANL), Argonne, IL (United States)
2. Univ. of Missouri, Rolla, MO (United States)

The French and British nuclear programs have prepared a series of natural uranium oxide fuel samples spiked with small amounts of the individual fission products which makeup a large fraction of the total neutron absorption by fission products in spent nuclear fuel. Both programs have utilized these samples in experimental reactors and have inferred the worth of the individual fission products. These results have been used to validate the cross sections used in criticality safety calculations. These measurements constitute a major element in support of spent fuel burnup credit in these countries.

• Research Organization: Argonne National Lab. (ANL), Argonne, IL (United States)
• Sponsoring Organization: USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP); USDOE Office of Civilian Radioactive Waste Management (RW)
• DOE Contract Number: W-31-109-ENG-38
• OSTI ID: 757501
• Report Number(s): ANL-FRA-2000-1; TRN: US0100308
• Resource Relation: Other Information: PBD: 5 May 2000
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
ANL
CROSS SECTIONS
EXPERIMENTAL REACTORS
FISSION PRODUCTS
NATURAL URANIUM
NUCLEAR FUELS
SPENT FUELS
Nuclear Criticality Safety Program (NCSP)
Fission Products
Nuclear Fuel
Null Reactivity
Oscillation Measurements
Critical Assembly