Spent Fuel Shipping, Reprocessing, and Recycle Fabrication in the HTGR Fuel Cycle

Conference · Sun Sep 16 00:00:00 EDT 1973

OSTI ID:4419225

Brooks, L. H. ^[1]; Davis, C. R. ^[1]; Peterman, D. D. ^[1]; Spaeth, M. E. ^[1]

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1. Gulf General Atomic, Inc., San Diego, CA (United States)

The High Temperature Gas Cooled Reactor (HTGR) fuel recycle operation is described. The description includes the HTGR spent fuel shipping system and the proposed method of reprocessing the spent fuel to recover the bred ²³³U and ²³⁵U. The process for refabricating the recovered fuel into recycle fuel is also discussed.

• Research Organization: Gulf General Atomic, Inc., San Diego, CA (United States)
• Sponsoring Organization: USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP); US Atomic Energy Commission (AEC)
• DOE Contract Number: AT(04-3)-167
• NSA Number: NSA-29-003147
• OSTI ID: 4419225
• Report Number(s): GULF-GA-A--12272; CONF-730918--2
• Country of Publication: United States
• Language: English

Related Subjects

*FUEL ELEMENTS-- FABRICATION
*HTGR TYPE REACTORS-- FUEL CYCLE
*SPENT FUEL ELEMENTS-- TRANSPORT
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
Coated Particles
Fuel Particles
Fuel Shipping Cask Structure
High Temperature Gas Cooled Reactor (HTGR) Fuel Recycle Operation
Nuclear Criticality Safety Program (NCSP)
Refabrication Process
Shipping System
Solvent Extraction Process
Spent Fuel