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HTGR fuels and core development program. Quarterly progress report for the period ending November 30, 1976. [Graphite and fuel irradiations; fission product release]

Description: The work reported includes studies of reactions between core materials and coolant impurities, basic fission product transport mechanisms, core graphite development and testing, the development and testing of recyclable fuel systems, and physics and fuel management studies. Materials studies include irradiation capsule tests of both fuel and graphite. Experimental procedures and results are discussed and the data are presented in tables, graphs, and photographs.
Date: December 27, 1976
Partner: UNT Libraries Government Documents Department

HTGR fuels and core development program. Quarterly progress report for the period ending February 28, 1977. [Graphite and fuel irradiation; fission product release]

Description: The work reported includes studies of reactions between core materials and coolant impurities, basic fission product transport mechanisms, core graphite development and testing, and development and testing of recyclable fuel systems, and physics and fuel management studies. Materials studies include irradiation capsule tests of both fuel and graphite.
Date: March 1, 1977
Partner: UNT Libraries Government Documents Department

HTGR fuels and core development program. Quarterly progress report for the period ending May 31, 1976. [Graphite and fuels irradiation; fission product release]

Description: The work reported includes studies of reactions between core materials and coolant impurities, basic fission product transport mechanisms, core graphite development and testing, the development and testing of recyclable fuel systems, and physics and fuel management studies. Materials studies include irradiation capsule tests of both fuel and graphite. Experimental procedures and results are discussed and the data are presented in tables, graphs, and photographs.
Date: June 30, 1976
Partner: UNT Libraries Government Documents Department

Determination of fission product and heavy metals inventories in FTE-4 fuel rods by a grind-burn-leach flowsheet

Description: Experiments using High-Temperature Gas-Cooled Reactor (HTGR) fuel material, TRISO-coated (2.75 Th/U)C/sub 2/--TRISO-coated ThC/sub 2/ and TRISO-coated UO/sub 2/--BISO-coated ThO/sub 2/, were performed in Building 4507 (the High-Level Chemical Development Facility) to determine the inventory and transport behavior of fission products and heavy metals from a grind-burn-leach process flowsheet. In addition, values calculated by the ORNL Isotope Generation and Depletion Code (ORIGEN, a computer program used for predicting quantities of activation products, actinides, and fission products from irradiation data and nuclear data libraries) are compared with values derived by chemical analyses (CA) and those measured by a gamma-scan nondestructive analytical (NDA) technique. Reasonable agreement was obtained between ORIGEN and NDA results for one of the tests, but the values obtained by chemical analysis were lower than either of the two other sets of values. With the exception of /sup 234/U, isotopic uranium values determined by chemical analysis (mass spectrometry) agreed within 15 percent of the ORIGEN prediction.
Date: July 1, 1977
Creator: Fitzgerald, C. L.; Vaughen, V. C. A. & Lamb, C. E.
Partner: UNT Libraries Government Documents Department

Thorium utilization program. Quarterly progress report for the period ending November 30, 1975. [Fuel element crushing, solids handling, fluidized bed combustion, aqueous separations, solvent extraction, systems design and drafting, alternative head-end reprocessing, and fuel recycle systems analysis]

Description: The development program for HTGR fuel reprocessing continues to emphasize the design and construction of a prototype head-end line. Design work on the multistage crushing system, the primary and secondary fluidized bed burners, the pneumatic transfer systems, and the ancillary fixtures for semiremote assembly and disassembly is essentially complete. Fabrication and receipt of all major components is under way, and auxiliary instrumentation and support systems are being installed. Studies of flow characteristics of granular solids in pneumatic transfer systems are continuing and data are being collected for use in design of systems for solids handling. Experimental work on the 20-cm primary fluidized bed burner verified the fines recycle operating mode in runs of greater than 24 hr. Twelve leaching runs were performed during the quarter using crushed, burned-back TRISO coated ThC/sub 2/ particles and burned-back BISO coated sol gel ThO/sub 2/ particles to examine the effect of varying the Thorex-to-thoria ratio to give product solutions ranging from 0.25M to 1M in thorium. Only minor effects were observed and reference values for facility operations were specified. Two-stage leaching runs with burned-back ThC/sub 2/ indicate there are no measurable differences in total dissolution time as compared to single-stage leaching. Bench-scale tests on oxidation of HTGR fuel boron carbide at 900/sup 0/C indicates that most if not all of the carbide will be converted to boron oxide in the fluidized bed burner. Eight solvent extraction runs were completed during the quarter. These runs represented the first cycle and second uranium cycle of the acid-Thorex flowsheet. A detailed calculation of spent fuel compositions by fuel block and particle type is being performed for better definition of process streams in a fuel reprocessing facility.
Date: December 31, 1975
Partner: UNT Libraries Government Documents Department

HTGR fuels and core development program. Quarterly progress report for period ending February 29, 1976. [Graphite and fuel irradiation; fission product release]

Description: The work reported includes studies of reactions between core materials and coolant impurities, basic fission product transport mechanisms, core graphite development and testing, the development and testing of recyclable fuel systems, and physics and fuel management studies. Materials studies include irradiation capsule tests of both fuel and graphite. Experimental procedures and results are discussed and the data are presented in tables, graphs, and photographs.
Date: March 31, 1976
Partner: UNT Libraries Government Documents Department

Fuel cycle cost studies: fabrication, reprocessing, and refabrication of LWR, SSCR, HWR, LMFBR, and HTGR fuels

Description: The comparative analysis of power generation costs for the various reactor cycles that is being performed in the Nonproliferation Alternative Systems Assessment Program (NASAP) and the International Nuclear Fuel Cycle Evaluation (INFCE) requires that the costs associated with processing of fuel materials for use in these cycles be estimated. The study described here provided unit cost estimates for the fabrication, reprocessing, and refabrication of a variety of fuels for several reactor systems. We examined in detail the facility requirements and operations to estimate capital and operating costs. Unit processing cost determinations were based on a cash flow analysis technique in which income from sales over the life of each facility was equated to the total capital and operating expenses of that facility plus a specified return on equity investment. The effects of plant capacities were determined by application of scaling factors to individual components of the reference plant costs. Capital and operating costs were estimated for 21 reactor and fuel cycle combinations. Based on these estimates, unit costs were determined for fabrication, reprocessing, and refabrication of the fuels. In each instance, the effect of plant capacities on unit costs associated with the processing of fuels was determined. All costs were based on mature industries, and first-of-a-kind costs were not included. Unit cost determinations were based on three financing techniques, which included government financing, typical industrial financing, and high-risk industrial financing. The unit costs recommended for the comparative analysis of power generation costs are those associaated with the economic assumptions of a typical industry.
Date: March 1, 1979
Creator: Olsen, A.R.; Judkins, R.R.; Carter, W.L. & Delene, J.G.
Partner: UNT Libraries Government Documents Department

High-temperature gas-cooled reactor fuel recycle development. Annual progress report for period ending September 30, 1977

Description: The status of the following tasks is reported: program management, studies and analysis, fuel processing, refabrication development, in-plant waste treatment, research general support, and major facilities including HTGR recycle reference facility, hot engineering test facility and cold prototype test facility-refabrication. (JRD)
Date: September 1, 1978
Creator: Lotts, A.L. & Kasten, P.R.
Partner: UNT Libraries Government Documents Department

Gas-cooled reactor programs. High-temperature gas-cooled reactor base-technology program progress report for July 1, 1975--December 31, 1976

Description: Progress is reported in the following areas: prestressed concrete pressure vessel development, structural materials, fission product technology, kernel migration and irradiated fuel chemistry, coolant chemistry (steam-graphite reactions), fuel qualification, and characterization and standardization of graphite.
Date: November 1, 1977
Creator: Homan, F. J. & Kasten, P. R.
Partner: UNT Libraries Government Documents Department

Selected studies in HTGR reprocessing development. [KA2C process]

Description: Recent work at ORNL on hot cell studies, off-gas cleanup, and waste handling is reviewed. The work includes small-scale burning tests with irradiated fuels to study fission product release, development of the KALC process for the removal of /sup 85/Kr from a CO/sub 2/ stream, preliminary work on a nonfluidized bed burner, solvent extraction studies including computer modeling, characterization of reprocessing wastes, and initiation of a development program for the fixation of /sup 14/C as CaCO/sub 3/. (auth)
Date: March 1, 1976
Creator: Notz, K. J.
Partner: UNT Libraries Government Documents Department

High-temperature gas-cooled reactor base-technology program. Progress report, January 1, 1974--June 30, 1975

Description: Progress is reported in the following areas: PCRV development, studies on structural materials, fission product technology studies, kernel migration and irradiated fuel chemistry, coolant chemistry (steam-graphite reactions), fuel qualification, and characterization and standardization of graphite.
Date: November 1, 1976
Creator: Coobs, J. H. & Kasten, P. R.
Partner: UNT Libraries Government Documents Department