Actions for Criticality Experiments with Subcritical Clusters of 2.35 Wt% and 4.31 Wt% 235U Enriched U02 Rods in Water with Uranium or Lead Reflecting Walls Undermoderated Water-to-Fuel Volume Ratio of 1.6 [electronic resource].

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Criticality Experiments with Subcritical Clusters of 2.35 Wt% and 4.31 Wt% 235U Enriched U02 Rods in Water with Uranium or Lead Reflecting Walls Undermoderated Water-to-Fuel Volume Ratio of 1.6 [electronic resource].

Published
Richland, Wash. : Pacific Northwest National Laboratory (U.S.), 1981.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
Additional Creators
Pacific Northwest National Laboratory (U.S.) and United States. Department of Energy. Office of Scientific and Technical Information
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Summary
A series of criticality experiments with undermoderated (1.6 water-to-fuel volume ratio) 2.35 wt% and 4.31 wt% ²³⁵U enriched UO₂ rods in water were performed to provide data on the reactivity effects of lead and depleted uranium reflecting walls. This data furnishes well defined benchmarks for use in validating calculational techniques employed in analyzing fuel shipping and storage systems having lead or uranium biological shields. For each fuel enrichment, the critical separation between three subcritical fuel clusters was observed to increase as either 77mm thick depleted uranium or 102mm thick lead reflecting walls were moved towards the fuel. A maximum critical separation was observed for both the lead and the depleted uranium reflecting walls with a water gap between the fuel clusters and the reflecting walls. For both fuel enrichments, this optimum water gap was about 25mm for the depleted uranium walls and about lOmm for the lead walls.
Report Numbers
E 1.99:pnl-3926 vol. 2
pnl-3926 vol. 2
Subject(s)
Note
Published through SciTech Connect.
12/01/1981.
"pnl-3926 vol. 2"
Bierman, S. R.; Durst, B. M.; Clayton, E. D.
Office of Nuclear Regulatory Research
Funding Information
DE-AC06-76RL01830
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