Extending the utility of a radioactive material package

Conference · Thu Jun 04 00:00:00 EDT 2015

OSTI ID:1204360

Abramczyk, G. ^[1]; Nathan, S. ^[2]; Loftin, B. ^[1]; Bellamy, S. ^[1]

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1. Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL). Savannah River Nuclear Solutions
2. Savannah River Site (SRS), Aiken, SC (United States). Savannah River Nuclear Solutions

Once a package has been certified for the transportation of DOT Hazard Class 7 – Radioactive Material in compliance with the requirements of 10 CFR 71, it is often most economical to extend its utility through the addition of content-specific configuration control features or the addition of shielding materials. The SRNL Model 9977 Package’s authorization was expanded from its original single to twenty contents in this manner; and most recently, the 9977 was evaluated for a high-gamma source content. This paper discusses the need for and the proposed shielding modifications to the package for extending the utility of the package for this purpose.

• Research Organization: Savannah River Site (SRS), Aiken, SC (United States)
• Sponsoring Organization: USDOE
• DOE Contract Number: DE-AC09-08SR22470
• OSTI ID: 1204360
• Report Number(s): SRNS-STI-2015-00290
• Resource Relation: Conference: Institute of Nuclear Materials Management - Annual Meeting
• Country of Publication: United States
• Language: English

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