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234-5 bank tank circulation studies

Description: In the Plutonium Reclamation Facility a critically-safe geometry of the processing vessels, combined with economical utilization of building space, has resulted in manifolded, vertical tanks for blending, receiving, holding, etc. The pumps attached to the bottom-outlet manifolds of the tanks are of a canned motor type. The extremely short life of these pumps (considerably below that expected even in severe abrasive and corrosive service) prompted a series of studies using glass tanks containing process solutions which, except for the associated radioactivity, duplicate plant process streams. Circulation, blending, and reaction characteristics of simulated process streams in glass duplicates of the 234-5 Bank Tanks TK-17, TK-27, and TK-37 revealed circulation patterns that result in intermittent cavitation within the canned motor transfer pumps. This cavitation, combined with the unavoidable corrosion and abrasion, rapidly destroys the pumps. The circulation patterns, under varying liquid levels as encountered in plant operation, cause single and dual phase transfer of the organic aqueous solutions to process colunans at different times, which results in flooding and erratic extraction efficencies. Reduction of cavitation and elimination of mixed phase transfer has been demonstrated by means of parallel controllable orifices in the external circulation lines. Elimination of cavitation and uniformity of mixing in the four separate vessels comprising the bank-tank assembly have also been demonstrated by means of changes in the inlet and outlet manifolds. The reduction of cavitation can be accomplished by changes in the system components remotely located from the tanks proper, i.e., in piping located in hoods. Complete elimination of cavitation and uniformity requires alteration of the tank headers and, while more desirable, also entails appreciable cost. (auth)
Date: April 30, 1974
Creator: Dunn, J.
Partner: UNT Libraries Government Documents Department

Generation of floor response spectra for mixed-oxide fuel fabrication plants

Description: Floor or amplified response spectra are generally used as input motion for seismic analysis of critical equipment and piping in nuclear power plants and related facilities. The floor spectra are normally the result of a time-history calculation of building response to ground shaking. However, alternate approximate methods have been suggested by both Kapur and Biggs. As part of a study for the Nuclear Regulatory Commission horizontal floor response spectra were generated and compared by all three methods. The dynamic analyses were performed on a model of the Westinghouse Recycle Fuels Plant Manufacturing Building (MOFFP). Input to the time-history calculations was a synthesized accelerogram whose response spectrum is similar to that in Regulatory Guide 1.60. The response spectrum of the synthetic ground motion was used as input to the Kapur and Biggs methods. Calculations were performed for both hard (3500 fps) and soft (1500 fps) foundation soils. Results of comparison of the three methods indicate that although the approximate methods could easily be made acceptable from a safety standpoint, they would be overly conservative. The time-history method will yield floor spectra which are less uncertain and less conservative for a relatively modest additional effort. (auth)
Date: October 1, 1975
Creator: Arthur, D.F.; Murray, R.C. & Tokarz, F.J.
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 safety analysis report for the irradiated fuels storage facility

Description: A fuel storage facility has been constructed at the Idaho Chemical Processing Plant to provide safe storage for spent fuel from two commercial HTGR's, Fort St. Vrain and Peach Bottom, and from the Rover nuclear rocket program. The new facility was built as an addition to the existing fuel storage basin building to make maximum use of existing facilities and equipment. The completed facility provides dry storage for one core of Peach Bottom fuel (804 elements), 1$sup 1$/$sub 2$ cores of Fort St. Vrain fuel (2200 elements), and the irradiated fuel from the 20 reactors in the Rover program. The facility is designed to permit future expansion at a minimum cost should additional storage space for graphite-type fuels be required. A thorough study of the potential hazards associated with the Irradiated Fuels Storage Facility has been completed, indicating that the facility is capable of withstanding all credible combinations of internal accidents and pertinent natural forces, including design basis natural phenomena of a 10,000 year flood, a 175-mph tornado, or an earthquake having a bedrock acceleration of 0.33 g and an amplification factor of 1.3, without a loss of integrity or a significant release of radioactive materials. The design basis accident (DBA) postulated for the facility is a complete loss of cooling air, even though the occurrence of this situation is extremely remote, considering the availability of backup and spare fans and emergency power. The occurrence of the DBA presents neither a radiation nor an activity release hazard. A loss of coolant has no effect upon the fuel or the facility other than resulting in a gradual and constant temperature increase of the stored fuel. The temperature increase is gradual enough that ample time (28 hours minimum) is available for corrective action before an arbitrarily imposed maximum fuel centerline temperature of ...
Date: January 1, 1976
Creator: Bingham, G.E. & Evans, T.K.
Partner: UNT Libraries Government Documents Department