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in subjects: "Reprocessing"

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Thorium fuel cycles for LWRs: fuel diversion assessments and recycle requirements

A number of fuel cycles have been proposed for evaluation in the nonproliferation alternative systems assessment program. Among these systems are light water reactors (LWR) operating on the thorium-uranium cycle or the plutonium-thorium cycle either inside or outside energy centers. These proposals support the President's nuclear power policy of accelerating research into alternative fuel cycles that do not permit direct access to materials usable for nuclear weapons but still retain the benefi… more

Date: January 1, 1978

Creator: Carter, W. L.; Rainey, R. H. & Johnson, D. R.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Plutonium scrap recovery at Savannah River: Past, present, and vision of the future

As a result of the changing requirement, plus environmental and regulatory commitments, SRP now has essentially completed its paradigm shift. SRP has been transformed from primarily a reprocessor of irradiated uranium targets to primarily a reprocessor of non-specification plutonium. This is the mission which will carry SRP into the 21st Century. Accomplishment of the defined goals for the three-pronged RandD program will achieve several objectives: exploit new processes for recovering low-grad… more

Date: January 1, 1988

Creator: Gray, Leonard W.; Gray, John H.; Blancett, Allen L.; Lower, William M. & Rudisill, Tracy S.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Hot cell studies of tritium removal from and dissolution of an irradiated thoria fuel

Tritium removal and dissolution studies on an irradiated thoria-based fuel were conducted in the High Level Caves at the Savannah River Laboratory (SRL). The objectives of these studies were to define the effects of key process-related parameters on tritium evolution and subsequent dissolution. The test program at SRL determined the effects on tritium removal of particle size, heating temperature, oxidation, and agitation. ThO/sub 2//UO/sub 2/ (95%/5%) fuel from the Elk River Reactor, irradiate… more

Date: January 1, 1980

Creator: Pickett, J.B.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Nuclear fuel cycle facility accident analysis handbook

The Accident Analysis Handbook (AAH) covers four generic facilities: fuel manufacturing, fuel reprocessing, waste storage/solidification, and spent fuel storage; and six accident types: fire, explosion, tornado, criticality, spill, and equipment failure. These are the accident types considered to make major contributions to the radiological risk from accidents in nuclear fuel cycle facility operations. The AAH will enable the user to calculate source term releases from accident scenarios manual… more

Date: unknown

Creator: Ayer, J. E.; Clark, A. T.; Loysen, P.; Ballinger, M. Y.; Mishima, J.; Owczarski, P. C. et al.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Consolidated fuel reprocessing. Program progress report, April 1-June 30, 1980

This progress report is compiled from major contributions from three programs: (1) the Advanced Fuel Recycle Program at ORNL; (2) the Converter Fuel Reprocessing Program at Savannah River Laboratory; and (3) the reprocessing components of the HTGR Fuel Recycle Program, primarily at General Atomic and ORNL. The coverage is generally overview in nature; experimental details and data are limited.

Date: September 1, 1980

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

HTGR fuel recycle program. Quarterly progress report for the period ending November 30, 1977

The work reported includes the development of unit processes and equipment for reprocessing of High-Temperature Gas-Cooled Reactor (HTGR) fuel, the design and development of an integrated pilot line to demonstrate the head end of HTGR reprocessing using unirradiated fuel materials, and design work in support of Hot Engineering Tests (HET). Work is also described on trade-off studies concerning the required design of facilities and equipment for the large-scale recycle of HTGR fuels in order to … more

Date: December 1, 1977

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Rockwell Hanford Operations' 1978 radiological improvement program

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.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

SM-1A PROJECT--TECHNICAL MANUAL: CHEMISTRY

A manual is given of the equipment and procedures used in the Army Reactor (SM-1A) to control the water purity and makeup. In addition to a description of the primary purification control system, a discussion is presented of the water chemistry control procedures for the auxiliary systems (e.g., the spent-fuel pit, the shield tank, and the waste disposal system). (T.F.H.)

Date: September 29, 1960

Creator: Chupak, J.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Potential of pyroprocessing for partitioning purex wastes

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.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Technical Division quarterly progress report, October 1--December 31, 1977. [Fuel cycle research and development; special materials production]

Results are presented on the fluidized-bed calcination of simulated radioactive waste from the reprocessing of spent commercial nuclear fuel and on the removal of actinide elements from the waste prior to calcination. Other programs include the development of storage technology for /sup 85/Kr waste; and the behavior of volatile radionuclides during the combustion of HTGR graphite-based fuel. The long-term management of defense waste from the ICPP covers post-calcination treatment of ICPP calcin… more

Date: February 1, 1978

Creator: Slansky, C.M. (ed.)

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Actinide partitioning and transmutation program. Progress report, July 1--September 30, 1977

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.)

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Comparative assessment of nuclear fuel cycles. Light-water reactor once-through, classical fast breeder reactor, and symbiotic fast breeder reactor cycles

The object of the Alternative Nuclear Fuel Cycle Study is to perform comparative assessments of nuclear power systems. There are two important features of this study. First, this evaluation attempts to encompass the complete, integrated fuel cycle from mining of uranium ore to disposal of waste rather than isolated components. Second, it compares several aspects of each cycle - energy use, economics, technological status, proliferation, public safety, and commercial potential - instead of conce… more

Date: June 1, 1980

Creator: Hardie, R.W.; Barrett, R.J. & Freiwald, J.G.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Treatment of high-level wastes from the IFR fuel cycle

The Integral Fast Reactor (IFR) is being developed as a future commercial power source that promises to have important advantages over present reactors, including improved resource conservation and waste management. The spent metal alloy fuels from an IFR will be processed in an electrochemical cell operating at 500{degree}C with a molten chloride salt electrolyte and cadmium metal anode. After the actinides have been recovered from several batches of core and blanket fuels, the salt cadmium in… more

Date: January 1, 1992

Creator: Johnson, T. R.; Lewis, M. A.; Newman, A. E. & Laidler, J. J.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Remotex: a new concept for efficient remote operation and maintenance in nuclear fuel reprocessing. [Hot Experimental Facility (HEF)]

Remotex is a concept of remote operation and maintenance that utilizes advanced manipulator design to improve plant operating efficiency, reduce personnel exposure, and improve safeguards and diversion resistance. It is a concept developed over the past two years in the conceptual design of the Hot Experimental Facility (HEF), a mechanically intense pilot plant facility designed to demonstrate reprocessng technology for early US breeder demonstration reactors. The Remotex concept is directly ap… more

Date: January 1, 1980

Creator: Feldman, M.J. & White, J.R.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Voloxidation studies with UO/sub 2/ reactor fuels

Voloxidation was studied experimentally in small-scale laboratory tests with irradiated UO/sub 2/ reactor fuels. The present study developed new data on the effects on the voloxidation reaction of hull length, oxygen concentration, temperature, agitation, fuel density, and fuel type and burnup. The reaction was studied by measuring weight gains, yields of U/sub 3/O/sub 8/, product densities and particle-size distributions, reaction rates, tritium release, and behavior of other off-gases (/sup 1… more

Date: January 1, 1980

Creator: Stone, J A

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Consolidated fuel-reprocessing program. Progress report, April 1-June 30, 1982

Highlights of progress accomplished during the quarter ending June 30, 1982 are summarized. Discussion is presented under the headings: Process development; Laboratory R and D; Engineering research; Engineering systems; Integrated equipment test facility operation; Instrument development; and HTGR fuel reprocessing.

Date: September 1, 1982

Creator: Burch, W D

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Voloxidation and dissolution of irradiated plutonium recycle fuels

Voloxidation removed > 99.4% of the tritium in the fuels tested (LWR recycled fuels containing /sup 239/Pu). Voloxidation increased the amount of insoluble residue by roughly a factor of two. Voloxidation increased the amount of plutonium in the insoluble residue by factors of 4 to 5. Voloxidation made the insoluble plutonium much harder to dissolve.

Date: January 1, 1980

Creator: Cadieux, J.R. & Stone, J.A.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Management of waste cladding hulls. Part II. An assessment of zirconium pyrophoricity and recommendations for handling waste hulls

This report reviews experience and research related to the pyrophoricity of zirconium and zirconium alloys. The results of recent investigations of the behavior of Zircaloy and some observations of industrial handling and treatment of Zircaloy tubing and scrap are also discussed. A model for the management of waste Zircaloy cladding hulls from light water reactor fuel reprocessing is offered, based on an evaluation of the reviewed information. It is concluded that waste Zircaloy cladding hulls … more

Date: November 1, 1977

Creator: Kullen, B J; Levitz, N M & Steindler, M J

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

HTGR fuel recycle program. Quarterly progress report for the period ending August 31, 1977

Date: September 1, 1977

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

ACFAC: a cash flow analysis code for estimating product price from an industrial operation

A computer code is presented which uses a discountted cash flow methodology to obtain an average product price for an industtrial process. The general discounted cash flow method is discussed. Special code options include multiple treatments of interest during construction and other preoperational costs, investment tax credits, and different methods for tax depreciation of capital assets. Two options for allocating the cost of plant decommissioning are available. The FORTRAN code listing and th… more

Date: April 1, 1980

Creator: Delene, J.G.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Nuclear proliferation and civilian nuclear power. Report of the Nonproliferation Alternative Systems Assessment Program. Volume III. Resources and fuel cycle facilities

The ability of uranium supply and the rest of the nuclear fuel cycle to meet the demand for nuclear power is an important consideration in future domestic and international planning. Accordingly, the purpose of this assessment is to evaluate the adequacy of potential supply for various nuclear resources and fuel cycle facilities in the United States and in the world outside centrally planned economy areas (WOCA). Although major emphasis was placed on uranium supply and demand, material resource… more

Date: June 1, 1980

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Nuclear proliferation and civilian nuclear power. Report of the Nonproliferation Alternative Systems Assessment Program. Volume I. Program summary

This report summarizes the Nonproliferation Alternative Systems Assessment Program (NASAP): its background, its studies, and its results. The introductory chapter traces the growth of the issue of nuclear weapons proliferation and the organization and objectives of NASAP. Chapter 2 summarizes the program's assessments, findings, and recommendations. Each of Volumes II-VII reports on an individual assessment (Volumn II: Proliferation Resistance; Volume III: Resources and Fuel Cycle Facilities; V… more

Date: June 1, 1980

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Nuclear proliferation and civilian nuclear power. Report of the Nonproliferation Alternative Systems Assessment Program. Volume V. Economics and systems analysis

This NASAP assessment considers the economics of alternative nuclear reactor and fuel-cycle systems in the light of possible patterns of uranium supply and energy demand, as well as the economic implications of improvng the proliferation resistance of the various systems. The assessment focuses on the costs of alternative nuclear technologies and the possible timing of their implementation, based on their economic attractiveness.

Date: June 1, 1980

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Alternate fuel cycle technologies. Quarterly report, April--June 1977

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

Item Type: Report

Partner: UNT Libraries Government Documents Department