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Study of the Feasibility of Aqueous Recovery of Spent Fuels. Part 3. Calculated Distribution of Fission Product Nuclides.

Description: Calculation of evaluation of the mass and the activity of each fission product nuclide present in the spent fuel of a 500 Mw reactor operating on a 42 day cycle, at the time of removal from the reactor and as a function of time thereafter.
Date: June 1954
Creator: Nehemias, John V.; Dennis, Ralph C. & Ambo, Eugene
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Reprocessing of Homogeneous Beryllium-Base Reactor Fuel : a Suggested Scheme for the Selective Aqueous Dissolution of the Matrix

Description: The matrix of a dilute homogeneous H.T.G.C. reactor fuel employing metallic beryllium as a moderator can be selectively dissolved by a caustic soda solution containing salicylate ion. At least 99 percent of the uranium and thorium can be recovered as insoluble solids, but in the case of irradiated material the uranium loss might be higher. Some decontamination of the resulting beryllium solution from fission products and Pa233 can also be obtained. A tentative chemical flowsheet is proposed on … more
Date: August 1962
Creator: Farrell, M. S. & Temple, R. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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West Valley transfer cart control system design description. Environmental Restoration and Waste Management Program

Description: Detail design of the control system for the West Valley Nuclear Services Vitrification Facility transfer cart has been completed by Oak Ridge National Laboratory. This report documents the requirements and describes the detail design of that equipment and control software. Copies of significant design documents including analysis and testing reports and design drawings are included in the Appendixes.
Date: January 1, 1993
Creator: Bradley, E. C.; Crutcher, R. I.; Halliwell, J. W.; Hileman, M. S.; Moore, M. R.; Nodine, R. N. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Radiant-heat spray-calcination process for the solid fixation of radioactive waste. Part 1, Non-radioactive pilot unit

Description: The fixation of radioactive waste in a stable solid media by means of calcination of these aqueous solutions has been the subject of considerable-effort throughout the U. S. Atomic Energy Commission and by atomic energy organizations in other countries. Several methods of doing this on a continuous or semi-continuous basis have been devised, and a fev have been demonstrated to be feasible for the handling of non-radioactive, or low-activity, simulated wastes. Notable among methods currently und… more
Date: November 14, 1960
Creator: Allemann, R. T. & Johnson, B. M. Jr.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Pyrochemical processing of DOE spent nuclear fuel

Description: A compact, efficient method for conditioning spent nuclear fuel is under development. This method, known as pyrochemical processing, or {open_quotes}pyroprocessing,{close_quotes} provides a separation of fission products from the actinide elements present in spent fuel and further separates pure uranium from the transuranic elements. The process can facilitate the timely and environmentally-sound treatment of the highly diverse collection of spent fuel currently in the inventory of the United S… more
Date: February 1, 1995
Creator: Laidler, J. J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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PFP up-right lift UL-20/26 manlifts

Description: This Technical Evaluation of Equipment Maintenance (TEEM) is provided principally to document vendor suggested maintenance requirements and deviations from vendor suggested requirements, and provide documentation to support PM procedures. As additional maintenance activities are identified, they will be documented in later revisions. This TEEM is applicable to four single-person manlifts. The report documents preventive maintenance evaluations, semi-annual checks, safety rules before the use of… more
Date: November 9, 1994
Creator: Morley, J. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Interim operation of the Purex 241-A Waste Tank Farm Condensate Disposal Facility

Description: This letter presents recommendations for the interim operation of the Purex 241-A Waste Tank Farm Condensate Disposal Facility and outlines briefly the status of design studies either progress or to be initiated in the near future to overcome its shortcomings.
Date: September 14, 1956
Creator: Michels, L. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Change of scope relocation of Purex cooling water swamp project CA-683

Description: It has been proposed that facilities be provided which can be used to divert the Purex cooling water from the facilities already proposed on this project to a depression within the 540 ft. elevation contour at approximate plant coordinates 34,300 N, 40200 W. These facilities are in addition to the change of scope referred to in reference (1). The purpose of these new facilities is to forma hydrologic dam as part of the ground water table which would aid in the confining of contamination and/or … more
Date: October 26, 1956
Creator: Wood, V. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Signal transmission techniques for large-scale nuclear fuel reprocessing applications

Description: The RCE is currently developing a prototypic microwave-based signal transmission system for reprocessing cell applications. This system, being developed for use in the Advanced Integrated Maintenance System (AIMS), will operate in the 10-GHz frequency range. Provisions are being made for five real-time video channels, three bidirectional data channels at one megabaud data rate each, and two audio channels. The basic utility of the concept has been proven in a laboratory demonstration using gall… more
Date: January 1, 1985
Creator: Herndon, J. N. & Bible, D. W.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Review of thermodynamic and kinetic data for the molten-tin process

Description: This report gives a brief description of the Molten Tin Process for nuclear fuel reprocessing, and summarizes the available data on thermodynamics and kinetics that pertain to the process. The two main reactions of concern in the process are illustrated by: MO/sub 2/(s) + 2C(in Sn sol'n) ..-->.. M(in Sn sol'n) + 2CO(g), and M(in Sn sol'n) + 1/2 N/sub 2/(g) ..-->.. MN(s), where M represents U or some other element in an oxide fuel. It is especially important for the Molten Tin Process to have in… more
Date: August 6, 1979
Creator: Krikorian, O.H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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ERDA light water reactor fuel

Description: The Energy Research and Development Administration is funding a program to assist the closing of the back-end of the light water reactor fuel cycle. The program uses resources of industrial and academic groups and those of technology laboratories throughout the ERDA complex. The ERDA Division of Waste Management, Production, and Reprocessing has the responsibility for overall program management, and the Savannah River Operations Office is responsible for field management and program implementat… more
Date: January 1, 1976
Creator: Meyer, L. H.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Advanced Safeguards Approaches for New Reprocessing Facilities

Description: U.S. efforts to promote the international expansion of nuclear energy through the Global Nuclear Energy Partnership (GNEP) will result in a dramatic expansion of nuclear fuel cycle facilities in the United States. New demonstration facilities, such as the Advanced Fuel Cycle Facility (AFCF), the Advanced Burner Reactor (ABR), and the Consolidated Fuel Treatment Center (CFTC) will use advanced nuclear and chemical process technologies that must incorporate increased proliferation resistance to e… more
Date: June 24, 2007
Creator: Durst, Philip C.; Therios, Ike; Bean, Robert; Dougan, A.; Boyer, Brian; Wallace, Richard et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Seismic (SSE) evaluation for the 291Z stack at the Hanford Site -- Addition of environmental monitoring penetrations

Description: The purpose of this 291Z stack analysis is to determine the structural effects of chipping additional holes into the stacks concrete walls. The proposed holes are for new environmental monitoring sample probes to be installed at three different elevations. The approximate elevations proposed at this time are 50 ft, 135 ft and 175 ft. There will be four holes required at each of the elevations to support two sample probes extending across the diameter of the stack. A structural sensitivity study… more
Date: August 31, 1994
Creator: Baxter, J. T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Plant-scale anodic dissolution of unirradiated IFR fuel pins

Description: This report discusses anodic dissolution which is a major operation in the pyrometallurgical process for recycling spent metal fuels from the Integral Fast Reactor (IFR), an advanced reactor design developed at Argonne National Laboratory. This process involves electrorefining the heavy metals (uranium and plutonium) from chopped, steel-clad fuel segments. The heavy metals are electrotransported from anodic dissolution baskets to solid and liquid cathodes in a molten salt electrolyte (LiCl-KCI)… more
Date: September 1, 1993
Creator: Gay, E. C.; Tomczuk, Z. & Miller, W. E.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Experimental results: Pilot plant calcine dissolution and liquid feed stability

Description: The dissolution of simulated Idaho Chemical Processing Plant pilot plant calcines, containing none of the radioactive actinides, lanthanides or fission products, was examined to evaluate the solubility of calcine matrix materials in acidic media. This study was a necessary precursor to dissolution and optimization experiments with actual radionuclide-containing calcines. The importance of temperature, nitric acid concentration, ratio of acid volume to calcine mass, and time on the amount, as a … more
Date: February 1, 1995
Creator: Herbst, R. S.; Fryer, D. S.; Brewer, K. N.; Johnson, C. K. & Todd, T.A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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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… more
Date: April 30, 1974
Creator: Dunn, J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Proposed Purex Phase II expansion program

Description: This letter dated March 8, 1957 summarizes the results of preliminary studies on the stepwise expansion of Purex facilities to the ultimate rate of 4.0 capacity factor, using a two-cycle flow-sheet. Briefly, it was suggested that Purex be expanded to the intermediate capacity of 3.5 capacity factor using available FY-1958 funds insofar as possible; decision to expand Purex to 4.0 capacity factor, could have been deferred for subsequent budgetary consideration.
Date: March 8, 1957
Creator: Michels, L. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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