Calculated K-Effectives Using ENDF/B-V Data for U + Pu Solution Critical Experiments

Conference · Sun Nov 29 00:00:00 EST 1981

OSTI ID:5562805

Primm, III, R. T. ^[1]; Mincey, J. F. ^[1]

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1. Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)

Effective multiplication factors for 12 critical experiments have been calculated using multigroup cross sections derived from the ENDF/B-V library. All 12 experiments contained mixed plutonium and uranium nitrate solutions. The range of hydrogen-to-fissile plutonium atom ratios spanned by these experiments was 200 to 2200. A comparison with K-effectives calculated with ENDF/B-IV data is presented.

• Research Organization: Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
• Sponsoring Organization: USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP); USDOE Office of Nuclear Fuel Cycle
• DOE Contract Number: W-7405-ENG-26
• OSTI ID: 5562805
• Report Number(s): CONF-811103-82; ON: DE82006815; TRN: 82-007780
• Resource Relation: Conference: ANS Winter Meeting, San Francisco, CA, USA, , 29 Nov - 4 Dec 1981
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
97 MATHEMATICS AND COMPUTING
PLUTONIUM NITRATES
CRITICALITY
URANIUM NITRATES
CROSS SECTIONS
EXPERIMENTAL DATA
HYDROGEN
MULTIGROUP THEORY
MULTIPLICATION FACTORS
NEUTRON REACTIONS
SOLUTIONS
ACTINIDE COMPOUNDS
BARYON REACTIONS
DATA
DISPERSIONS
ELEMENTS
HADRON REACTIONS
INFORMATION
MIXTURES
NEUTRON TRANSPORT THEORY
NITRATES
NITROGEN COMPOUNDS
NONMETALS
NUCLEAR REACTIONS
NUCLEON REACTIONS
NUMERICAL DATA
OXYGEN COMPOUNDS
PLUTONIUM COMPOUNDS
TRANSPORT THEORY
TRANSURANIUM COMPOUNDS
URANIUM COMPOUNDS
Nuclear Criticality Safety Program (NCSP)
Evaluated Nuclear Data File (ENDF)
Plutonium and Uranium Nitrate Solutions
KENO-IV
Flux Spectra
Cross Section Libraries
Hydrogen-to-Fissile Plutonium Ratios
050800* - Nuclear Fuels- Spent Fuels Reprocessing