Thorex Pilot Plant: Criticality Review of the Thorex Pilot Plant Using the Int-23 Process

Technical Report · Tue Jul 08 04:00:00 EDT 1958

DOI:https://doi.org/10.2172/4254138· OSTI ID:4254138

McDuffee, W. T. ^[1]; Yarbro, O. O. ^[1]

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1. Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)

The results of a criticality review of the ORNL Thorex pilot plant are presented for the condition where a low TBP (INT-23) flowsheet is used in recovering U-233 from irradiated thorium. Criticality control will be maintained by limiting the U-233 inventory in the solvent extraction system to less than 550g by means of stream-volume and U-233 material balances determined at 8 hr intervals. Equipment modification and improved operating procedures for safe plant operation are outlined.

• Research Organization: Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
• Sponsoring Organization: USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP); US Atomic Energy Commission (AEC)
• DOE Contract Number: W-7405-ENG-26
• NSA Number: NSA-13-010976
• OSTI ID: 4254138
• Report Number(s): CF-58-7-53
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
BUTYL PHOSPHATES
CONTROL
CRITICALITY
Criticality
DIAGRAMS
FABRICATION
INT-23
IRRADIATION
LIQUID FLOW
Liquid Flow
Nuclear Criticality Safety Program (NCSP)
OPERATION
ORNL
PILOT PLANT
QUANTITATIVE ANALYSIS
RECOVERY
REPROCESSING
SAFETY
SEPARATION PROCESSES
SOLVENT EXTRACTION
Safety
TBP
TESTING
THOREX PROCESS
THORIUM
Thorex
U-233
URANIUM 233
Uranium
Uranium 233
VOLUME
WASTE PROCESSING
WEIGHT