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Rockwell Hanford Operations' 1978 radiological improvement program

Description: This document describes the radiological improvement program (RIP) to be undertaken by Rockwell Hanford Operations during calendar year 1978. Actions taken in each facility to reduce exposure and to implement the Company's policy to conduct operations in a manner that assures radiation exposures to employees are maintained at the lowest levels reasonably achievable.
Date: December 30, 1977
Creator: Cunningham, D. S.
Partner: UNT Libraries Government Documents Department
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Potential of pyroprocessing for partitioning purex wastes

Description: The processes are extremely compact. The process reagents are highly resistant to radiation damage and, therefore, can be used to handle short-cooled, highly concentrated waste with negligible degradation. Most reagents can be recycled back through the process many times, thereby minimizing the generation of waste products, and also reducing the process cost. Fission-product wastes are discharged from the process as concentrated, solid wastes, typically in a metal matrix suitable for permanent … more
Date: July 23, 1980
Creator: Coops, M. S. & Sisson, D. H.
Partner: UNT Libraries Government Documents Department
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Actinide partitioning and transmutation program. Progress report, July 1--September 30, 1977

Description: In Purex process modifications, two cold runs with mixer-settlers were made on the extraction and stripping of ruthenium and zirconium without the presence of uranium. Efforts in actinide recovery from solids were directed toward the determination of dissolution parameters in various reagents for /sup 241/Am and /sup 239/Pu oxide mixtures, /sup 233/U oxide, /sup 237/Np oxide, /sup 244/Cm oxide, /sup 232/Th oxide, and PuO/sub 2/. Studies in americium-curium recovery with OPIX (oxalate precipitat… more
Date: February 1, 1978
Creator: Tedder, D.W. & Blomeke, J.O. (comps.)
Partner: UNT Libraries Government Documents Department
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Alternate fuel cycle technologies. Quarterly report, April--June 1977

Description: This quarterly report describes studies to provide information needed to close the back end of the commercial light-water reactor (LWR) fuel cycle. These efforts are directed primarily at reprocessing and recycle of uranium and plutonium from spent LWR fuel. Research is reported in the following categories: environmental studies, fuel receipt, head-end processes, purex process, waste management, safeguards (dose rate for extraction streams), and general support.
Date: September 1, 1977
Partner: UNT Libraries Government Documents Department
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Actinide Partitioning and Transmutation Program. Progress report, April 1--June 30, 1977

Description: Experimental work on the 16 tasks comprising the Actinide Partitioning and Transmutation Program was continued. Summaries of work are given on Purex Process modifications, actinide recovery, Am-Cm recovery, radiation effects on ion exchangers, LMFBR transmutation studies, thermal reactor transmutation studies, fuel cycle studies, and partitioning-transmutation evaluation. (JRD)
Date: October 1, 1977
Creator: Tedder, D. W. & Blomeke, J. O.
Partner: UNT Libraries Government Documents Department
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Plutonium(IV) hydrous polymer chemistry

Description: The hydrous polymer chemistry of Pu(IV) in aqueous nitric acid solutions has been a subject of considerable interest for several years. This interest stems mainly from the fact that most nuclear fuel reprocessing schemes based on the Purex process can be hampered by the occurrence of polymer. As a result, an understanding and control of the parameters that affect polymer formation during reprocessing are studied. 2 refs.
Date: January 1, 1985
Creator: Toth, L.M. & Dodson, K.E.
Partner: UNT Libraries Government Documents Department
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Improved laboratory assays of Pu and U for SRP purification and finishing processes

Description: Significant improvements have been made in routine assay techniques for uranium and plutonium as part of an effort to improve accountability at the Savannah River Plant (SRP). Emphasis was placed on input/output accountability points and key physical inventory tanks associated with purification and finishing processes. Improvements were made in existing assay methods; new methods were implemented; and the application of these methods was greatly expanded. Prior to assays, samples were validated… more
Date: January 1, 1986
Creator: Holland, M K & Dorsett, R S
Partner: UNT Libraries Government Documents Department
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Rheological evaluation of simulated neutralized current acid waste - transuranics

Description: At the Hanford Plutonium and Uranium Extraction Plant (PUREX), in Richland, Washington, plutonium and uranium products are recovered from irradiated fuel by a solvent extraction process. A byproduct of this process is an aqueous waste stream that contains fission products. This waste stream, called current acid waste (CAW), is chemically neutralized and stored in double shell tanks (DSTs) on the Hanford Site. This neutralized current acid waste (NCAW) will be transported by pipe to B-Plant, a p… more
Date: September 1, 1986
Creator: Fow, C.L.; McCarthy, D.; Thornton, G.T.; Scott, P.A. & Bray, L.A.
Partner: UNT Libraries Government Documents Department
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Efficiency of contactors

Description: The Savannah River Plant has two separations plants that began Purex operations in 1954 and 1955 with pump-mix mixer-settlers as contactors to process nuclear fuels. The only changes to the extraction equipment were replacement of most of the mixer-settlers in one plant with larger units in 1959, and the further replacement of the large 1A bank with a bank of rapid-contact centrifugal contactors in 1966. Improved performance of the old units has become highly desirable, and an experimental prog… more
Date: January 1, 1986
Creator: Orth, D A; Graham, F R & Holt, D L
Partner: UNT Libraries Government Documents Department
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Institutional arrangements for the reduction of proliferation risks formulation, evaluation, and implementation of institutional concepts

Description: The purpose of this study was to: (1) identify alternative institutional arrangements applicable to the sensitive steps in the back-end of the fuel cycle that might reduce their associated proliferation risks; and (2) assess their advantages and disadvantages from the standpoint of nonproliferation effectiveness and political, economic, and operational acceptability. The concept of international or multinational custody of sensitive materials and facilities was found to offer a high degree of p… more
Date: December 1, 1979
Creator: Kratzer, M.B.; Wonder, E.F.; Gray, J.E.; Shantzis, S.B.; Sievering, N.F.; Paige, H.W. et al.
Partner: UNT Libraries Government Documents Department
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Purex process operation and performance: 1970 thoria campaign

Description: The Hanford Purex Plant has demonstrated suitability for reprocessing irradiated thoria (ThO/sub 2/) target elements on a campaign basis. A 1965 process test and major production campaigns conducted in 1966 and 1970 recovered nitrate solution form products totaling approximately 565 tons of thorium and 820 kilograms of /sup 233/U. The overall recoveries for the 1970 campaign based on reactor input data were 94.9 percent for thorium and 95.2 percent for uranium. The primary function of the Hanfo… more
Date: February 1, 1978
Creator: Walser, R.L.
Partner: UNT Libraries Government Documents Department
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NO/sub x/ emissions from Hanford nuclear fuels reprocessing plants

Description: Operation of the existing Hanford nuclear fuel reprocessing facilities will increase the release of nitrogen oxides (NO/sub x/) to the atmosphere over present emission rates. Stack emissions from two reprocessing facilities, one waste storage facility and two coal burning power plants will contain increased concentrations of NO/sub x/. The opacity of the reprocessing facilities' emissions is predicted to periodically exceed the State and local opacity limit of twenty percent. Past measurem… more
Date: September 15, 1978
Creator: Pajunen, A. L. & Dirkes, R. L.
Partner: UNT Libraries Government Documents Department
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Purex process

Description: The following aspects of the Purex Process are discussed: head end dissolution, first solvent extraction cycle, second plutonium solvent extraction cycle, second uranium solvent extraction cycle, solvent recovery systems, primary recovery column for high activity waste, low activity waste, laboratory waste evaporation, vessel vent system, airflow and filtration, acid recovery unit, fume recovery, and discharges to seepage basin. (LK)
Date: January 1, 1977
Creator: Starks, J.B.
Partner: UNT Libraries Government Documents Department
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Recovery of plutonium from molten salt extraction residues

Description: Savannah River Laboratory (SRL), Savannah River Plant (SRP), and Rocky Flats Plant (RFP) are jointly developing a process to recover plutonium from molten salt extraction residues. These NaCl, KCl, MgCl/sub 2/ residues, which are generated in the pyrochemical extraction of /sup 241/Am from aged plutonium metal, contain up to 25 wt % dissolved PUCl/sub 3/ and up to 2 wt % AmCl/sub 3/. The objective is to develop a process to convert these residues to plutonium metal product and discardable waste… more
Date: January 1, 1983
Creator: Gray, L.W. & Holcomb, H.P.
Partner: UNT Libraries Government Documents Department
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Trace elements retained in washed nuclear fuel reprocessing solvents

Description: Analysis of purified TBP extractant from solvent extraction processes at Savannah River Plant showed several stable elements and several long-lived radioisotopes. Stable elements Al, Na, Br, Ce, Hg, and Sm are found in trace quantities in the solvent. The only stable metallic element consistently found in the solvent was Al, with a concentration which varies from about 30 ppM to about 10 ppM. The halogens Br and Cl appear to be found in the solvent systems as organo halides. Radionuclides found… more
Date: September 1, 1979
Creator: Gray, L.W. & MacMurdo, K.W.
Partner: UNT Libraries Government Documents Department
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Coprocessing solvent-extraction flowsheet studies for LWR and FBR fuels

Description: Coprocessing solvent extraction studies using irradiated LWR and FBR fuels have indicated the need for an efficient feed clarification. A potentially useful filtration method for fulfilling this need has been demonstrated. Conditions necessary for the satisfactory use of unstabilized hydroxylamine nitrate (HAN) or nitrous acid as the reducing agent for Pu(IV) during reductive stripping operations have been defined. Both partial partitioning and total costripping operations have been demonstrate… more
Date: January 1, 1982
Creator: Collins, E. D.; Benker, D. E.; Bigelow, J. E.; Chattin, F. R.; King, L. J.; Lloyd, M. H. et al.
Partner: UNT Libraries Government Documents Department
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Purex diluent degradation

Description: The chemical degradation of normal paraffin hydrocarbon (NPH) diluents both in the pure state and mixed with 30% tributyl phosphate (TBP) was investigated in a series of experiments. The results show that degradation of NPH in the TBP-NPH-HNO/sub 3/ system is consistent with the active chemical agent being a radical-like nitrogen dioxide (NO/sub 2/) molecule, not HNO/sub 3/ as such. Spectrophotometric, gas chromatographic, mass spectrographic, and titrimetric methods were used to identify the d… more
Date: February 1, 1984
Creator: Tallent, O. K.; Mailen, J. C. & Pannell, K. D.
Partner: UNT Libraries Government Documents Department
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Laboratory studies on the evolution of iodine-129 during Purex-uranium metal dissolution

Description: The path of iodine from the Purex dissolver was determined during fuel dissolution using /sup 125/I tracer. Laboratory-scale equipment qualification studies were completed using sections of nonirradiated uranium N-reactor fuel elements. A proof-of-principle dissolution study was completed at the end of FY 1979 in the PNL hot cells using wafers of irradiated N-reactor fuel. The findings include the following: the laboratory-scale dissolver/downdraft condenser was designed at a factor of 5 x 10/s… more
Date: March 1, 1980
Creator: Bray, L.A.
Partner: UNT Libraries Government Documents Department
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Chemical Engineering Division Fuel Cycle Programs: October--December 1976. [Encapaulation in a metal matrix]

Description: Fuel-cycle studies reported for this period include pyrochemical separation of plutonium and americium oxides from contaminated materials of construction such as steel. The actinides are partitioned to a high degree into slags that are contacted by the molten metal. Studies of advanced solvent extraction techniques focussed on the development of centrifugal contactors for use in Purex processes. A miniature contactor is to be used for performance studies applicable to larger units. Review of li… more
Date: January 1, 1977
Creator: Steindler, M. J.; Ader, M.; Bernstein, G.; Flynn, K.; Gerding, T.; Jardine, L. et al.
Partner: UNT Libraries Government Documents Department
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Secondary cleanup of Idaho Chemical Processing Plant solvent

Description: Solvent from the Idaho Chemical Processing Plant (ICPP) (operated by Westinghouse Idaho Nuclear Company, Inc.) has been tested to determine the ability of activated alumina to remove secondary degradation products - those degradation products which are not removed by scrubbing with sodium carbonate.
Date: January 1, 1985
Creator: Mailen, J. C.
Partner: UNT Libraries Government Documents Department
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In-process inventory estimation for pulsed columns and mixer-settlers

Description: Nuclear materials accounting and control in fuels reprocessing plants can be improved by near-real-time estimation of the nuclear materials inventory in solvent-extraction contactors. Techniques are being developed for the estimation of the in-process inventory in contactors. These techniques are derived from recent developments in chemical modeling of contactor systems, on-line measurements for materials accounting and control of the Purex process, and computer-based data acquisition and analy… more
Date: 1980~
Creator: Cobb, D. D.; Burkhart, L. E. & Beyerlein, A. L.
Partner: UNT Libraries Government Documents Department
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Creep and cycling tests: thermal properties of Hanford concretes. [79 to 1175/sup 0/F]

Description: Four tests were conducted to determine thermal properties of concrete core material from the Purex Building at Hanford, Washington, and from concrete cast at the Portland Cement Association. Specific heat, thermal conductivity, and thermal diffusivity were measured as functions of temperature from 79 to 1175F.
Date: March 1, 1979
Creator: Gillen, M.
Partner: UNT Libraries Government Documents Department
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