Internal Corrosion Analysis of Model 9975 Packaging Containing Pu or PuO{sub 2} During Shipping and Storage

Technical Report · Tue Mar 23 00:00:00 EST 1999

DOI:https://doi.org/10.2172/5015· OSTI ID:5015

Vormelker, P

The Materials Consultation Group of SRTC has completed an internal corrosion analysis of the Model 9975 packaging assembly containing either Pu or PuO2 for storage in K Reactor under ambient conditions for a period of 12 years. The 12-year storage period includes two years for shipping and up to ten years for storage.

• Research Organization: Savannah River Site (SRS), Aiken, SC (United States)
• Sponsoring Organization: US Department of Energy (US)
• DOE Contract Number: AC09-96SR18500
• OSTI ID: 5015
• Report Number(s): WSRC-TR-99-00030; TRN: US0101636
• Resource Relation: Other Information: PBD: 23 Mar 1999
• Country of Publication: United States
• Language: English

Related Subjects

12 MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
CORROSION PRODUCTS
CHEMICAL ANALYSIS
PACKAGING
RADIOACTIVE WASTE STORAGE
PLUTONIUM
PLUTONIUM OXIDES
CONTAINERS
WASTE TRANSPORTATION