Analysis of High Conversion Critical Experiments
- Argonne National Lab. (ANL), Argonne, IL (United States)
Critical experiments performed in the ZPR-7 facility using Hi-C or BORAX-V fuel and light-water moderator are analyzed, The Hi-C fuel consisted of 3.04 w/o enriched UO2 pellets of 0.935 cm diameter, stacked to a height of 122 cm in either aluminum or stainless steel tubing. Experiments with BORAX-V fuel used UO2 pellets, which were 4.95 w/o enriched, 0.871 cm in diameter, and stacked 61 cm high in stainless steel tubing. All lattices analyzed consisted of fuel rods uniformly spaced in either square or triangular arrays. The H-to-U238 atom ratios in the cores varied from roughly 4.6 to 0.5 so that investigations extended far into the undermoderated region. Calculations of critical bucklings, reflector savings, and various microparameters are compared with experimental values. Agreement with experiment is in general reasonably good, except for the U238-to-U235 fission ratio.
- Research Organization:
- Argonne National Lab. (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-31-109-ENG-38
- NSA Number:
- NSA-21-040668
- OSTI ID:
- 4236738
- Report Number(s):
- ANL-7270
- Resource Relation:
- Other Information: UNCL. Orig. Receipt Date: 31-DEC-67
- Country of Publication:
- United States
- Language:
- English
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