Additional nuclear criticality safety calculations for small-diameter containers
This report documents additional criticality safety analysis calculations for small diameter containers, which were originally documented in Reference 1. The results in Reference 1 indicated that some of the small diameter containers did not meet the criteria established for criticality safety at the Portsmouth facility (K{sub eff} +2{sigma}<.95) when modeled under various contingency assumptions of reflection and moderation. The calculations performed in this report reexamine those cases which did not meet the criticality safety criteria. In some cases, unnecessary conservatism is removed, and in other cases mass or assay limits are established for use with the respective containers.
- Research Organization:
- Portsmouth Gaseous Diffusion Plant, OH (United States)
- Sponsoring Organization:
- USDOE, Washington, DC (United States)
- DOE Contract Number:
- AC05-76OR00001
- OSTI ID:
- 211600
- Report Number(s):
- POEF-SH-43; ON: DE96007357; TRN: 96:010429
- Resource Relation:
- Other Information: PBD: Jan 1996
- Country of Publication:
- United States
- Language:
- English
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