Engineering studies on pot calcination for ultimate disposal of nuclear waste from the TBP-25, DAREX, and PUREX processes. Part I. The system evaluation

Technical Report · Mon Sep 23 04:00:00 EDT 1963

DOI:https://doi.org/10.2172/6892265· OSTI ID:6892265

Hancher, C W; Suddath, J C; Whatley, M E

Experience with the operation of an experimental engineering-development pot-calcination facility, including two types of evaporators with associated control systems and a calciner pot up to 8 in. in diameter and 90 in. high, formed the basis for the recommendation of equipment and operating procedures for the hot-pilot-plant phase of the waste-calcination program. The performance of each component in the system is discussed. The evolutionary justification is given for choices of equipment and operational techniques which are recommended. The pot calcination process reduces radioactive liquid waste solutions to calcined solids, which are permanently stored in the calcination pot. It can handle wastes of a variety of fuel processes. Rehandling and packaging of the calcined solids are not required since the pot used for the final evaporation and calcination serves as the permanent storage vessel. The prolonged high temperature in the pot decreases nitrate in the solids to less than 500 ppM under ordinary conditions, leading to greater stability during storage. Ingredients for improving the physical or thermal properties of the solids or for fixation of isotopes can be incorporated in the system if desired. Performance information is presented for equipment and system behavior based on engineering scale studies of simulated waste from Purex, Darex, and TBP-25 plants. Two flowsheets (batch evaporation and continuous) were demonstrated satisfactorily after trial and error modification of the equipment and control systems. Average rates of 5 gal/hr were processed in the evaporator-calciner complex for all three types of waste 'reverse arrowbased on 40 gal/ton, Purex waste; 45 g Al/liter, TBP-25 waste; and 38 g Fe/liter, Darex waste).

• Research Organization: Oak Ridge National Lab., TN (USA)
• DOE Contract Number: W-7405-ENG-26
• OSTI ID: 6892265
• Report Number(s): ORNL-3277
• Country of Publication: United States
• Language: English

Related Subjects

052001* -- Nuclear Fuels-- Waste Processing
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
CALCINATION
CHEMICAL REACTIONS
DAREX PROCESS
DECOMPOSITION
DESIGN
DIAGRAMS
EQUIPMENT
FLOWSHEETS
MANAGEMENT
NITRATES
NITROGEN COMPOUNDS
OXYGEN COMPOUNDS
PERFORMANCE TESTING
PHASE TRANSFORMATIONS
PROCESSING
PUREX PROCESS
PYROLYSIS
RADIOACTIVE WASTE PROCESSING
REPROCESSING
SEPARATION PROCESSES
SOLIDIFICATION
TESTING
THERMOCHEMICAL PROCESSES
WASTE MANAGEMENT
WASTE PROCESSING