Critical Studies of a Dilute Fast Reactor Core (ZPR-III Assembly 31)

Technical Report · Sun Oct 01 04:00:00 EDT 1961

DOI:https://doi.org/10.2172/4822638· OSTI ID:4822638

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 on a dilute, metallic, fast reactor core. The fuel was 38.6% enriched uranium and reduced-density aluminum was used to simulate sodium coolant. The measured critical mass was 463 kg of U²³⁵ in a 425-liter core. The main part of the experimental program consisted of measurements of the standard fission ratios, a number of central reactivity coefficients, and the prompt neutron lifetime. An additional series of experiments were performed to obtain the worths of aluminum, aluminum oxide, and sodium at various radial positions in the core.

• 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-16-000931
• OSTI ID: 4822638
• Report Number(s): ANL-6338
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
ALUMINUM
ALUMINUM OXIDES
COOLANTS
CRITICALITY
Critical Mass
DENSITY
ENRICHMENT
FAST NEUTRONS
FISSION
FUELS
Fission Ratio
LIFETIME
MASS
MEASURED VALUES
METALS
Neutron Lifetime
Nuclear Criticality Safety Program (NCSP)
PROMPT NEUTRONS
REACTIVITY
REACTORS
Radial Worth
SODIUM
SOLUTIONS
URANIUM