EBR-II Wet Critical Experiments

Technical Report · Thu Oct 01 04:00:00 EDT 1964

DOI:https://doi.org/10.2172/4646860· OSTI ID:4646860

Kirn, F. S. ^[1]; Loewenstein, W. B. ^[2]

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

The Experimental Breeder Reactor-II (EBR-II) Wet Critical Experiments are one phase of a comprehensive, experimental, neutronic investigation associated with that reactor system. The Wet Critical Experiments are so designated to distinguish them from the previously conducted Dry Critical Experiments. The Wet Critical Experiments were conducted with sodium coolant in the reactor system, while the similar low-power investigations comprising the Dry Critical Experiments were performed with essentially no sodium coolant in the reactor system. Other pertinent, low-power, neutronic investigations include the detailed engineering mockup of EBR-II on the Zero Power Reactor-III (ZPR-III), as well as several related, but relatively clean, geometry systems that were also studied on ZPR-III. The next EBR-II neutronic studies comprise the Approach to Power. These studies will emphasize power dependent and long-term irradiation neutronics, as well as a few low-power investigations. The low-power investigations include measurements relating to the conversion ratio of the system based on fission rate distribution in core and blanket.

• Research Organization: Argonne National Laboratory (ANL), Argonne, IL (United States); Argonne National Laboratory (ANL), 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-19-021677
• OSTI ID: 4646860
• Report Number(s): ANL-6864
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
BREEDING
CONTROL ELEMENTS
CRITICALITY
Control Rods
EBR-2
Fission Ratio
INSTRUMENTS
LIQUID METAL COOLANT
MEASURED VALUES
NEUTRON SOURCES
Neutron Source
Nuclear Criticality Safety Program (NCSP)
OPERATION
POWER PLANTS
REACTIVITY
REACTORS
RODS
Reactivity
SODIUM
TEMPERATURE
TEMPERATURE COEFFICIENT