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Description of Purex Plant Process

Description: A brief summary, with reference literature for details, of pertinent and important process flowsheet conditions which are in use in the Purex Process is presented. (auth)
Date: April 30, 1959
Creator: Irish, E. R.
Partner: UNT Libraries Government Documents Department

PUREX Plant deactivation function analysis report

Description: The document contains the functions, function definitions, function interfaces, function interface definitions, Input Computer Automated Manufacturing Definition (IDEFO) diagrams, and a function hierarchy chart that describe what needs to be performed to deactivate PUREX.
Date: September 1, 1995
Creator: Lund, D.P. & Group, PUREX Working
Partner: UNT Libraries Government Documents Department

PUREX Storage Tunnels waste analysis plan. Revision 1

Description: Washington Administrative Code 173-303-300 requires that a facility develop and follow a written waste analysis plan which describes the procedures that will be followed to ensure that its dangerous waste is managed properly. This document covers the activities at the PUREX Storage Tunnels used to characterize and designate waste that is generated within the PUREX Plant, as well as waste received from other on-site sources.
Date: November 1, 1995
Creator: Stephenson, M.J.
Partner: UNT Libraries Government Documents Department

PUREX storage tunnels waste analysis plan

Description: Washington Administrative Code 173-303-300 requires that a facility develop and follow a written waste analysis plan which describes the procedures that will be followed to ensure that its dangerous waste is managed properly. This document covers the activities at the PUREX Storage Tunnels used to characterize and designate waste that is generated within the PUREX plant, as well as waste received from other on-site sources
Date: October 16, 1995
Creator: Haas, C.R.
Partner: UNT Libraries Government Documents Department

GRADED PLATE CARTRIDGE FOR PUREX A-TYPE EXTRACTION COLUMN

Description: Graded nonuniform cartridges are described which have plates with larger holes, greater free area, and/or greater plate spacing. These plates were developed and specified for the Purex Plant A-type columns. Use of the cartridges eliminated cyclic local flooding and increased the complete flooding frequency by 10 and 25 cycles/min at volume velocities of 530 and 1060 gal/hr/ sq ft, respectively, and exhibited satisfactory extraction efficiency over a wide range of frequencies and throughputs. (auth)
Date: March 20, 1957
Creator: Geier, R.G. & Hesson, G.M.
Partner: UNT Libraries Government Documents Department

PUREX PULSE COLUMN STUDIES-1960

Description: A series of pilot plant runs was conducted to define new cartridges for increasing the capacity in the Purex 1 Bx, 2A, lC and 2E columns and eliminate plastic cartridge failures in the HA column scrub section, the HS column and the 2A column. The most favorable designs are presented and data from the various runs are included. (J.R.D.)
Date: February 22, 1961
Creator: Jansen, G. & Richardson, G.L.
Partner: UNT Libraries Government Documents Department

Laser-enhanced chemical reactions and the liquid state. II. Possible applications to nuclear fuel reprocessing

Description: Laser photochemistry is surveyed as a possible improvement upon the Purex process for reprocessing spent nuclear fuel. Most of the components of spent nuclear fuel are photochemically active, and lasers can be used to selectively excite individual chemical species. The great variety of chemical species present and the degree of separation that must be achieved present difficulties in reprocessing. Lasers may be able to improve the necessary separations by photochemical reaction or effects on rates and equilibria of reactions. (auth)
Date: January 1, 1976
Creator: DePoorter, G. L. & Rofer-DePoorter, C. K.
Partner: UNT Libraries Government Documents Department

Process specifications and standards for the 1970 thorium campaign in the Purex Plant

Description: The process specifications and standards for thorium processing operations in the Purex Plant are presented. These specifications represent currently known limits within which plant processing conditions must be maintained to meet defined product requirements safely and with minimum effect on equipment service life. These specifications cover the general areas of feed, essential materials, and chemical hazards. (LK)
Date: June 30, 1970
Creator: Van der Cook, R.E. & Ritter, G.L.
Partner: UNT Libraries Government Documents Department

Criticality prevention specifications thorium--uranium-233 separations in the Purex Plant

Description: The specifications in this document define the limits or restrictions required to maintain an acceptably low probability of the occurrence of a nuclear chain reaction in the Purex Plant while processing irradiated thoria targets. These criticality prevention specifications do not stipulate the system, procedures, or mechanisms to permit operation within the limits or restrictions. (LK)
Date: June 1, 1970
Creator: Matheison, W.E.; Oberg, G.C. & Ritter, G.L.
Partner: UNT Libraries Government Documents Department

FINAL CYCLE PLUTONIUM RECOVERY BY AMINE EXTRACTION

Description: The flowsheet visualized from development work thus far for final plutonium recovery and purification will accept as feed a Purex partition stream without feed adjustment beyond the usual reoxidation. Extraction with trilaurylamine at approximately 0.3M appears suitable for 20 to 60 g Pu/liter product from 0.5 to 2 g Pu/liter feed. Scrubbing with either ((2 M or))2 M HNO/ sub 3/ is possible. Acetic acid is at present the first choice for stripping agent, with oil-soluble and aqueous-soluble organic reductants as alternates. (auth)
Date: May 24, 1961
Creator: Coleman, C.F.
Partner: UNT Libraries Government Documents Department

PUREX PROCESS FOR PLUTONIUM AND URANIUM RECOVERY

Description: Labcratory data which indicate that the recovery of Pu and U and decontamination from fission products are feasible in a solvent extraction process using tributyl phosphate are given. The procedure consists of extracting Pu(IV) and U with 15% TBP--85% Varsol using 5.0 N HNO/sub 3/ as a salting agent. (J.R.D.)
Date: October 1, 1949
Creator: Lanham, W.B. & Runion, T.C.
Partner: UNT Libraries Government Documents Department