Critical Studies of a Fast Reactor Core Containing Depleted Uranium and Sodium as Diluents (ZPR- III Assembly 36)

Technical Report · Mon Jan 01 04:00:00 EST 1962

DOI:https://doi.org/10.2172/4801472· OSTI ID:4801472

Gasidlo, J. M. ^[1]; Long, J. K. ^[1]; McVean, R. L. ^[1]

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1. Argonne National Lab., Idaho Falls, ID (United States)

Critical studies were performed with a metallic, fast reactor core designed to investigate the effects of replacing highly absorbing U²³⁸ diluent with high-scattering, low-absorbing sodium diluent. The fuel was 15.7 w/o enriched U²³⁵ and the core contained 18.2 v/o sodium and 12.68 v/o stainless steel. The experimental program was designed to measure the effect of the material replacement on spectral indices, which consisted of the standard fission ratios, foil irradiations, and a large number of central reactivity coefficients. Other measurements included the Rossi-α radial fission traverses, and edge reactivity worths of a few samples.

• Research Organization: Argonne National Laboratory, Idaho Falls, ID (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-16-011186
• OSTI ID: 4801472
• Report Number(s): ANL-6494
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
ABSORPTION
BURNUP
CAPTURE
CONFIGURATION
CRITICALITY
DISTRIBUTION
ENRICHMENT
FAST FISSION FACTOR
FAST NEUTRONS
FOILS
FUELS
Fission Ratio
IRRADIATION
MASS
MATERIALS TESTING
MEASURED VALUES
NEUTRON FLUX
Nuclear Criticality Safety Program (NCSP)
PLANNING
POWER PLANTS
REACTIVITY
REACTOR CORE
Radial Fission
Rossi-Alpha
SCATTERING
SODIUM
SPECTRA
STAINLESS STEELS
Spectral Indices
THERMAL FISSION FACTOR
THERMAL UTILIZATION
TRANSIENTS
U235
U238
URANIUM
URANIUM 235
URANIUM 238
VARIATIONS
ZONES