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Critical Studies of a 440-Liter Fast-Reactor Core Fueled with Uranium Enriched to 17 Percent (ZPR-3 Assembly 41)

Technical Report ·
DOI:https://doi.org/10.2172/4711925· OSTI ID:4711925

ZPR-3 Assembly 41 was a cylindrical fast-reactor system composed of a dilute uranium core surrounded by a thick, depleted-uranium blanket. The fuel, a five-to-one mixture of 238U and 235U, amounted to 35 vol % of the core, and this was diluted with 18 vol % aluminum, 14 vol % steel, and 33 vol % void. A critical mass of 494 kg of 235U was measured for this composition. Basic physics experiments included measurements of spectral indices, material reactivity coefficients, and flux profiles. The worths of steel and aluminum as reflectors, relative to uranium, were investigated in radial and axial blanket regions. Studies were carried out to determine the relative merits of three breeder-blanket concepts: an EBR-II-type blanket (with 40 vol % uranium, 40 vol % sodium, 20 vol % steel); a UC type blanket (with 20 vol % uranium, 20 vol % carbon, 40 vol % sodium, and 20 vol % steel); and a two-zone blanket with an inner zone of an EBR-II-type blanket and an outer zone containing graphite instead of uranium. Worths of boron carbide near the core in two blanket types were measured to evaluate a rotary-control-rod concept for fast rectors. This report contains experimental details and the results of all measurements.

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-26-006325
OSTI ID:
4711925
Report Number(s):
ANL-6732
Country of Publication:
United States
Language:
English