Critical Experiments in PuO2-UO2-H2O Lattices
- Pacific Northwest National Laboratory (PNNL), Richland, WA (United States)
A series of critical experiments has been performed in the Plutonium Recycle Critical Facility (PRCF) using half-inch diameter U02-2 wt% PuO2 fuel rods moderated with H2O. The fuel rods are 36 inches long, 0.508 inches in diameter, covered with a Zircaloy-2 sleeve 0.030 inches thick, and each rod contains an average of 1128 g of UO2-PuO2 mixture. The rods were loaded in a hexagonal lattice with a pitch of 0.85 inches which corresponds to a moderator-to-oxide volume ratio of 1.83.
- Research Organization:
- Pacific Northwest National Laboratory (PNNL), Richland, WA (United States)
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP); US Atomic Energy Commission (AEC)
- DOE Contract Number:
- AT(45-1)-1830
- OSTI ID:
- 1987624
- Report Number(s):
- BNWL--400
- Country of Publication:
- United States
- Language:
- English
Similar Records
Critical Experiments in H2O-Moderated Assemblies Containing UO2-2 wt.% PuO2 Fuel Rods
Subcritical Measurements with UO2-2 wt.% PuO2 Fuel
Critical Experiments with the UO2-2 wt.% PuO2 Batch Core in the PRTR
Technical Report
·
Sun Dec 31 23:00:00 EST 1967
·
OSTI ID:1988760
Subcritical Measurements with UO2-2 wt.% PuO2 Fuel
Technical Report
·
Sun Dec 31 23:00:00 EST 1967
·
OSTI ID:1988759
Critical Experiments with the UO2-2 wt.% PuO2 Batch Core in the PRTR
Technical Report
·
Sun Jan 31 19:00:00 EST 1971
·
OSTI ID:4071718