Subcritical Limits for ²³³U Systems

Journal Article · Wed Oct 21 04:00:00 EDT 1981 · Nuclear Science and Engineering

DOI:https://doi.org/10.13182/NSE81-A19043· OSTI ID:786661

Clark, Hugh K. ^[1]

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1. Du Pont de Nemours (E.I.) and Co., Aiken, SC (United States). Savannah River Laboratory

As a contribution to the required quinquennial review of American National Standard for Nuclear Criticality Safety in Operations with Fissionable Materials Outside Reactors (ANSI N16.1-1975/ANS-8.1), limits for homogeneous ²³³U systems have been recalculated to confirm their sub-criticality or, where there were doubts, to propose more restrictive values. In addition, other limits were calculated to be proposed for inclusion, namely, limits for aqueous solutions of UO₂(NO₃)₂ and limits for uranium oxides. The same three methods of calculation were used as in similar work done recently for plutonium and ²³⁵U systems. The validity of each was established by correlation with the results of pertinent critical experiments. This report discusses this study.

• Research Organization: Du Pont de Nemours (E.I.) and Co., Aiken, SC (United States). Savannah River Laboratory
• Sponsoring Organization: USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
• DOE Contract Number: AC09-76SR00001
• OSTI ID: 786661
• Report Number(s): DP-MS-81-67
• Journal Information: Nuclear Science and Engineering, Journal Name: Nuclear Science and Engineering Journal Issue: 1 Vol. 79; ISSN 0029-5639
• Publisher: Taylor & Francis
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
97 MATHEMATICS AND COMPUTING
AQUEOUS SOLUTIONS
Aqueous Solutions
CRITICALITY
Criticality
Nuclear Criticality Safety Program (NCSP)
SAFETY ANALYSIS
Safety Analysis
URANIUM 233
URANIUM OXIDES
URANYL NITRATES
Uranium 233
Uranium Oxides
Uranyl Nitrates