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

Description: 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: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Evaluation of environmental dosimetry models for applicability to possible radioactive waste repository discharges

Description: This report presents the results of a review of the available codes, for application to the National Waste Terminal Storage (NWTS) Program. Consideration was given to the types of radionuclides which may be of concern, the possible modes of release of these radionuclides and the various pathways by which members of the general public in the vicinity of a terminal storage facility may be exposed to the releases. Results reveal that the types and quantities of radioactive material requiring dispo… more
Date: September 1, 1977
Creator: Mauro, J. J.; Michlewicz, D. & Letizia, A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Effect of fuel recycling on radioactivity and thermal power of high-level wastes

Description: The radioactivity and thermal power of high-level and plutonium-bearing wastes from the nuclear fuel cycle have been calculated for the years 1975 to 2005 using the rate of generation of such wastes projected for the Generic Environmental Statement on Mixed Oxide Fuel (NUREG-0002). Three modes of fuel recycle are considered: (1) no recycle, (2) uranium recycle, and (3) prompt uranium and plutonium recycle. These cases are compared with a respect to radioactivity and thermal power of the generat… more
Date: October 1, 1977
Creator: Wachter, J.W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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ACORN: a computer program for plotting fault trees. [In FORTRAN for CDC Cyber 74]

Description: A description and user instructions are presented for ACORN, a FORTRAN computer program for drawing fault trees. ACORN analyzes the input logical structure of a fault tree and provides data for CalComp plot of the tree. AND, OR, and INHIBIT gates are permitted, and basic events are drawn as diamonds, circles, or houses. Each component (gate or basic event) can have a descriptive label within a rectangle attached to the top of its respective symbol. Tree logic is input as a set of FORTRAN statem… more
Date: November 1, 1977
Creator: Carter, J. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Long-term leaching of irradiated spent fuel

Description: Spent Light Water Reactor (LWR) fuel with burnups of 9, 28 and 54 MWd/kg U were leach tested at 25/sup 0/C in deionized water in a Paige apparatus. No discernible differences in leach rates were observed due to burnup. Additionally, the 28 MWd/kg U fuel was IAEA leach tested in five different leachants using the IAEA method. Deionized water gave the highest leach rates and a calcium chloride solution gave the lowest leach rates. An accelerated leaching period was observed during the Paige leach… more
Date: January 1, 1979
Creator: Katayama, Y. B. & Bradley, D. J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Metals and Ceramics Division. Annual progress report, ending June 30, 1980

Description: Research is reported concerning: (1) engineering materials, including materials compatibility, mechanical properties, nondestructive testing, pressure vessel technology, and welding and brazing; (2) fuels and processes consisting of ceramic technology, fuel cycle technology, fuels evaluation, fuel fabrication and metals processing; and (3) materials science which includes, ceramic studies, physical metallurgy properties, radiation effects and microstructural analysis, metastable and superconduc… more
Date: September 1, 1980
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Hot cell studies of tritium removal from and dissolution of an irradiated thoria fuel

Description: 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: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Nuclear fuel cycle facility accident analysis handbook

Description: 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: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Preliminary report on the promise of accelerator-driven natural-uranium-fueled light-water-moderated breeding power reactors

Description: A new concept for a power breeder reactor that consists of an accelerator-driven subcritical thermal fission system is proposed. In this system an accelerator provides a high-energy proton beam which interacts with a heavy-element target to produce, via spallation reactions, an intense source of neutrons. This source then drives a natural-uranium-fueled, light-water-moderated and -cooled subcritical blanket which both breeds new fuel and generates heat that can be converted to electrical power.… more
Date: July 1, 1977
Creator: Greenspan, E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Consolidated fuel reprocessing. Program progress report, April 1-June 30, 1980

Description: 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: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Uncertainty in the power distribution for a fast reactor burnup cycle

Description: Demonstration that advanced reactor designs satisfy safety and performance goals requires the analysis of uncertainties in calculated reactor characteristics. Two of the important performance characteristics of advanced liquid metal reactors (LMR) are the burnup reactivity swing and the local power peaking factor. Previous work reported a study of the uncertainty in the burnup reactivity swing attributable to nuclear data uncertainties for a typical advanced LMR design. The results are reported… more
Date: January 1, 1989
Creator: Downar, D.J.; Khalil, H. (Purdue Univ., Lafayette, IN (USA) & Argonne National Lab., IL (USA))
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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HTGR fuel recycle program. Quarterly progress report for the period ending November 30, 1977

Description: 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: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Actinide cross section program at ORELA

Description: The actinide cross section program at ORELA, the Oak Ridge Electron Linear Accelerator, is aimed at obtaining accurate neutron cross sections (primarily fission, capture, and total) for actinide nuclides which occur in fission reactors. Such cross sections, measured as a function of neutron energy over as wide a range of energies as feasible, comprise a data base that permits calculated predictions of the formation and removal of these nuclides in reactors. The present program is funded by the … more
Date: January 1, 1980
Creator: Dabbs, J. W. T.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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The ARIES-III D- sup 3 He tokamak reactor: Design-point determination and parametric studies

Description: The multi-institutional ARIES study has generated a conceptual design of another tokamak fusion reactor in a series that varies the assumed advances in technology and physics. The ARIES-3 design uses a D-{sup 3}He fuel cycle and requires advances in technology and physics for economical attractiveness. The optimal design was characterized through systems analyses for eventual conceptual engineering design. Results from the systems analysis are summarized, and a comparison with the high-field, D… more
Date: January 1, 1991
Creator: Bathke, C. G.; Werley, K. A.; Miller, R. L.; Krakowski, R. A. (Los Alamos National Lab., NM (United States)) & Santarius, J. F. (Wisconsin Univ., Madison, WI (United States))
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Effect of the self-pumped limiter concept on the tritium fuel cycle

Description: The self-pumped limiter concept for impurity control of the plasma of a fusion reactor has a major impact on the design of the tritium systems. To achieve a sustained burn, conventional limiters and divertors remove large quantities of unburnt tritium and deuterium from the plasma which must be then recycled using a plasma processing system. The self-pumped limiter which does not remove the hydrogen species, does not require any plasma processing equipment. The blanket system and the coolant pr… more
Date: January 1, 1988
Creator: Finn, P.A.; Sze, D.K. & Hassanein, A.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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System model for analysis of the mirror fusion-fission reactor

Description: This report describes a system model for the mirror fusion-fission reactor. In this model we include a reactor description as well as analyses of capital cost and blanket fuel management. In addition, we provide an economic analysis evaluating the cost of producing the two hybrid products, fissile fuel and electricity. We also furnish the results of a limited parametric analysis of the modeled reactor, illustrating the technological and economic implications of varying some important reactor de… more
Date: October 12, 1977
Creator: Bender, D.J. & Carlson, G.A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Operating and test experience of EBR-II

Description: EBR-2 has operated for 27 years, the longest for any Liquid Metal Reactor (LMR) power plant. During that time, much has been learned about successful LMR operation and design. The basic lesson is that conversatism in design can pay significant dividends in operating reliability. Furthermore, such conservatism need not mean high cost. The EBR-2 system emphasizes simplicity, minimizing the number of valves in the heat transport system, for example, and simplifying the primary heat-transport-syste… more
Date: January 1, 1991
Creator: Sackett, J. I.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Growth rates of breeder reactor fuel. Final report

Description: During the contract period, a consistent formalism for the definition of the growth rates (and thus the doubling time) of breeder reactor fuel has been developed. This formalism was then extended to symbiotic operation of breeder and converter reactors. Further, an estimation prescription for the growth rate has been developed which is based upon the breeding worth factors. The characteristics of this definition have been investigated, which led to an additional integral concept, the breeding b… more
Date: January 1, 1979
Creator: Ott, K O
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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FUEL CYCLE DEVELOPMENT PROGRAM. Quarterly Progress Report, January 1 to March 31, 1962

Description: The permanent shutdown of the Westinghouse Testing Reactor at the end of the quarter forced a revision in plans for programming the remainder of the irradiation of the two uninstrumented capsules whose testing was in progress. The minimum estimated burnup at this point, based on hot cell data obtained from the pilot capsule, was 13,100 MW-d/ton U. It was decided to continue the testing of only one capsule in another reactor until the original goal of 20,000 MW-d/ton U is reached. The irradiatio… more
Date: June 1, 1962
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Framework for fuel-cycle approaches to IAEA safeguards

Description: A framework is presented for comparing various safeguards verification approaches which have been proposed for consideration. Each inventory change, inventory, and material balance for each nuclear facility, reported by a state, may be verified. Verification approaches are compared by listing which of these reports would be verified and to what degree for each approach as they might be applied to a state with a closed fuel cycle. The comparison indicates that the extended-material-balance-area … more
Date: January 1, 1986
Creator: Fishbone, L.G. & Higinbotham, W.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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