Rack design analyses for loading Pu-glass cans in Can-in-Canister demonstration. Revision 1
Description
The Can in Canister (CIC) demonstration program is designed to demonstrate a concept for immobilization of surplus plutonium (Pu). This program will include special cold (non-radioactive) runs in the Defense Waste Processing Facility (DWPF) of the Savannah River Site (SRS) within a schedule window before the start of radioactive operations. Two steel racks were designed to hold eight cans and twenty cans of surrogate Pu glass. The loaded rack will be inserted into a 24-inch OD (outer diameter) DWPF canister pre-cut at the top. After the top of the canister is re-welded, the assembly will be transported to S-Area ready for filling with surrogate high level waste glass. The ultimate requirement for the rack design is that the cans of surrogate Pu glass held by the racks should not interfere with the surrogate high level glass stream during filling. Therefore, acceptance criteria for lifting and transport conditions require that the racks maintain their as designed (built) shapes when they are placed in S-Area for filling. During filling, the racks must maintain their load carrying capacity against collapse mainly due to the softening of material tensile properties at the very high temperatures. Stress analyses of racks loaded with surrogate Pu glass cans were performed as part of the CIC program to ensure that these acceptance criteria are met. This report will describe the materials of construction of the racks in Section 2. The stress analysis methodology which includes the modeling and acceptance criteria is detailed in Section 3. Results are reported in Section 4 and are discussed in Section 5
Availability note (English)
MF available from INIS under the Report Number; Also available from OSTI as DE97000438; NTIS; US Govt. Printing Office Dep.
Files
Additional details
Publishing Information
- Imprint Pagination
- 20 p.
- Report number
- WSRC-TR--95-0430-Rev.1
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 28013657
- Subject category
- S42: ENGINEERING; S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES;
- Descriptors DEI
- CONTAINERS; DESIGN; INCONEL ALLOYS; MATERIALS HANDLING; MECHANICAL PROPERTIES; PLUTONIUM; RADIOACTIVE WASTE PROCESSING; STAINLESS STEEL-304; STRESS ANALYSIS; SUPPORTS; TRANSPORT; VITRIFICATION; WASTE FORMS
- Descriptors DEC
- ACTINIDES; ALLOYS; AUSTENITIC STEELS; CARBON ADDITIONS; CHROMIUM ALLOYS; CHROMIUM-NICKEL STEELS; CORROSION RESISTANT ALLOYS; ELEMENTS; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; HIGH ALLOY STEELS; IRON ALLOYS; IRON BASE ALLOYS; MANAGEMENT; MATERIALS; MECHANICAL STRUCTURES; METALS; NICKEL ALLOYS; NICKEL BASE ALLOYS; STAINLESS STEELS; STEEL-CR19NI10; STEELS; TRANSITION ELEMENT ALLOYS; TRANSURANIUM ELEMENTS; WASTE MANAGEMENT; WASTE PROCESSING; WASTES
Optional Information
- Contract/Grant/Project number
- Contract AC09-89SR18035
- Funding organization
- USDOE, Washington, DC (United States).