Addendum to the Report on High Conversion Critical Experiments

Technical Report · Thu Aug 01 04:00:00 EDT 1968

DOI:https://doi.org/10.2172/4819403· OSTI ID:4819403

Plumlee, K. E. ^[1]

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1. Argonne National Lab. (ANL), Argonne, IL (United States)

This addendum presents revised results for the conversion-ratio, measurements reported in ANL-7203. All the results have been revised downward, by net relative reductions of ~4-15%. The revision is necessary because of the application of a more appropriate method of data analysis than originally used. The improved analysis adjusts accurately for the epicadmium flux component in graphite thermal columns, which affected the reference irradiations used for normalization of these measurements. The revised results for initial conversion ratios range from 0.44 ± 0.01 to 1.25 ± 0.04 for H:U²³⁸ atom ratios of 4.16 down to 0.50 (which is a subcritical composition), using 3.04 w/o enrichment UO₂ fuel and H₂O moderator and reflector. the UO₂ pellet diameter was 0.935 cm, and an average of 853.3 g was contained as a 121.9-cm-length column in each fuel element. The cladding was 1.06-cm-OD stainless steel with 0.05-cm wall thickness.

• Research Organization: Argonne National Laboratory (ANL), Argonne, IL (United States)
• Sponsoring Organization: USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP); US Atomic Energy Commission (AEC)
• DOE Contract Number: W-31109-ENG-38
• NSA Number: NSA-23-013583
• OSTI ID: 4819403
• Report Number(s): ANL-7203(Add.)
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
ANALYSIS
BURNUP
CONFIGURATION
CONVERSION
Conversion Ratio
EFFICIENCY
EQUATIONS
ERRORS
Epicadmium
FUEL CANS
FUEL ELEMENTS
Neutron Flux
Nuclear Criticality Safety Program (NCSP)
PELLETS
PERFORMANCE
STAINLESS STEELS
UO2
URANIUM DIOXIDE
WATER MODERATOR