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Predicting fuel performance for SP-100 conditions

Description: This paper reports on methods for analyzing fuel designs proposed for the thermionic and thermoelectric concepts for SP-100 application. The proposed fuel design for the thermionic concept consisted of fully-enriched oxide fuel clad in chemical vapor deposition (CVD) tungsten, which also served as the emitter for the thermionic fuel element (TFE). The fuel density was 95% of theoretical with the linear heat rate flattened radially by removing fuel from the center of the fuel pellet. The fuel in… more
Date: January 1, 1985
Creator: Baars, R. E.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Cladding corrosion and hydriding in irradiated defected zircaloy fuel rods

Description: Twenty-one LWBR irradiation test rods containing ThO/sub 2/-UO/sub 2/ fuel and Zircaloy cladding with holes or cracks operated successfully. Zircaloy cladding corrosion on the inside and outside diameter surfaces and hydrogen pickup in the cladding were measured. The observed outer surface Zircaloy cladding corrosion oxide thicknesses of the test rods were similar to thicknesses measured for nondefected irradiation test rods. An analysis model, which was developed to calculate outer surface oxi… more
Date: August 1985
Creator: Clayton, J. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Results of recent reactor-material tests on dispersal of oxide fuel from a disrupted core

Description: The results of experimental investigations and related analyses are reported addressing the dispersal of molten oxide fuel from a disrupted core via various available pathways for the CRBR system. These investigations included the GAPFLOW tests in which pressure-driven and gravity drainage tests were performed using dispersal pathways mocking up the intersubassembly gaps, the CAMEL C6 and C7 tests in which molten fuel entered sodium-filled control assembly ducts under prototypic thermal-hydraul… more
Date: January 1, 1985
Creator: Spencer, B. W.; Wilson, R. J.; Vetter, D. L.; Erickson, E. G. & Dewey, G.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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High-Energy Neutron Spectroscopy on F-Electron Oxides

Description: Neutron inelastic scattering with the chopper spectrometers at IPNS has been used to measure, for the first time, the ground to excited crystal-field transitions in PrO/sub 2/ (130 meV), BaPrO/sub 3/ (255 meV), and UO/sub 2/ (approx.160 meV). From these measurements we deduce the values of V/sub 4/ = A/sub 4/ (r/sup 4/) and compare both the absolute values and their variation with theoretical estimates. In the case of UO/sub 2/ two peaks are seen, one at 155 and the other at 172 meV. This struc… more
Date: January 1, 1985
Creator: Kern, S.; Loong, C.K. & Lander, G.H.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Automated amperometric plutonium assay system

Description: The amperometric titration for plutonium assay has been used in the nuclear industry for over twenty years and has been in routine use at the Hanford Engineering Development Laboratory since 1976 for the analysis of plutonium oxide and mixed oxide fuel material for the Fast Flux Test Facility. It has proven itself to be an accurate and reliable method. The method may be used as a direct end point titration or an excess of titrant may be added and a back titration performed to aid in determinati… more
Date: January 1, 1985
Creator: Burt, M.C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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LMFBR source term experiments in the Fuel Aerosol Simulant Test (FAST) facility

Description: The transport of uranium dioxide (UO/sub 2/) aerosol through liquid sodium was studied in a series of ten experiments in the Fuel Aerosol Simulant Test (FAST) facility at Oak Ridge National Laboratory (ORNL). The experiments were designed to provide a mechanistic basis for evaluating the radiological source term associated with a postulated, energetic core disruptive accident (CDA) in a liquid metal fast breeder reactor (LMFBR). Aerosol was generated by capacitor discharge vaporization of UO/su… more
Date: January 1, 1985
Creator: Petrykowski, J.C. & Longest, A.W.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Fuel performance annual report for 1983. Volume 1

Description: This annual report, the sixth in a series, provides a brief description of fuel performance during 1983 in commercial nuclear power plants. Brief summaries of fuel design changes, fuel surveillance programs, fuel operating experience, fuel problems, high-burnup fuel experience, and items of general significance are provided. References to additional, more detailed information and related NRC evaluations are included.
Date: March 1, 1985
Creator: Bailey, W.J. & Dunenfeld, M.S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Chemical thermodynamic assessment of the Li-U-O system for possible space nuclear applications

Description: A thermochemical assessment of possible oxide fuel-lithium coolant interactions in conceptual 100-kW(e) space nuclear power reactors has been performed. Results of the evaluation indicate that in the event of a cladding breach the fuel and coolant will interact with extremely negative consequences. The lithium has the potential to reduce the fuel to metallic uranium. Differences in temperature within the coolant loop can drive oxygen and uranium transport processes.
Date: June 1, 1985
Creator: Besmann, T.M. & Cooper, R.H. Jr.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Analysis of reactor material experiments investigating oxide fuel crust stability and heat transfer in jet impingement flow

Description: An analysis is presented of the crust stability and heat transfer behavior in the CSTI-1, CSTI-3, and CWTI-11 reactor material experiments in which a jet of molten oxide fuel at approx. 160/sup 0/K above its freezing temperature was impinged normally upon stainless steel plates initially at 300 and 385 K. The major issue is the existence of nonexistence of a stable solidified layer of fuel, or crust, interstitial to the flowing hot fuel and the steel substrate, tending to insulate the steel fro… more
Date: January 1, 1985
Creator: Sienicki, J. J. & Spencer, B. W.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Corium quench in deep pool mixing experiments

Description: The results of two recent corium-water thermal interaction (CWTI) tests are described in which a stream of molten corium was poured into a deep pool of water in order to determine the mixing behavior, the corium-to-water heat transfer rates, and the characteristic sizes of the quenched debris. The corium composition was 60% UO/sub 2/, 16% ZrO/sub 2/, and 24% stainless steel by weight; its initial temperature was 3080 K, approx.160 K above the oxide phase liquidus temperature. The corium pour st… more
Date: January 1, 1985
Creator: Spencer, B. W.; McUmber, L.; Gregorash, D.; Aeschlimann, R. & Sienicki, J. J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Grain boundary sweeping and dissolution effects on fission product behavior under severe fuel damage accident conditions

Description: The theoretical FASTGRASS-VFP model has been used in the interpretation of fission gas, iodine, tellurium, and cesium release from severe-fuel-damage (SFD) tests performed in the PBF reactor in Idaho. A theory of grain boundary sweeping of gas bubbles, gas bubble behavior during fuel liquefaction (destruction of grain boundaries due to formation of a U-rich melt phase), and during U-Zr eutectic melting has been included within the FASTGRASS-VFP formalism. The grain-boundary-sweeping theory cons… more
Date: October 1, 1985
Creator: Rest, J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Flowsheets and source terms for radioactive waste projections

Description: Flowsheets and source terms used to generate radioactive waste projections in the Integrated Data Base (IDB) Program are given. Volumes of each waste type generated per unit product throughput have been determined for the following facilities: uranium mining, UF/sub 6/ conversion, uranium enrichment, fuel fabrication, boiling-water reactors (BWRs), pressurized-water reactors (PWRs), and fuel reprocessing. Source terms for DOE/defense wastes have been developed. Expected wastes from typical deco… more
Date: March 1, 1985
Creator: Forsberg, C.W. (comp.)
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Review of fracture properties of nuclear materials determined by Hertzian indentation

Description: A brief description of the determination of the surface fracture energy and the fracture toughness from a Hertzian indentation test is given. A number of theoretical and experimental problems are discussed. Results obtained on a variety of nuclear fuels and nuclear-waste-containment materials are reviewed and compared with values measured by other techniques. The Hertzian indentation test yields reliable fracture parameters.
Date: January 1, 1985
Creator: Routbort, J. & Matzke, H.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Potential behavior of depleted uranium penetrators under shipping and bulk storage accident conditions

Description: An investigation of the potential hazard from airborne releases of depleted uranium (DU) from the Army's M829 munitions was conducted at the Pacific Northwest Laboratory. The study included: (1) assessing the characteristics of DU oxide from an April 1983 burn test, (2) postulating conditions of specific accident situations, and (3) reviewing laboratory and theoretical studies of oxidation and airborne transport of DU from accidents. Results of the experimental measurements of the DU oxides wer… more
Date: March 1, 1985
Creator: Mishima, J.; Parkhurst, M.A. & Scherpelz, R.I.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Performance of Breached LMFBR Fuel Pins During Continued Operation

Description: Four EBR-II tests were used to scope the behavior of breached mixed-oxide pins. After release of stored fission gas, delayed-neutron signals were large and easily detected, although not readily correlated with exposed fuel area. No problems were met during reactor operation or fuel handling. Fuel-sodium reaction caused only narrow breaches which released minute amounts of fuel and fission products; the reaction product appeared dense and non-friable. These initial results indicated LMFBR oxide … more
Date: January 1, 1985
Creator: Lambert, J. D. B.; Strain, R. V.; Gross, K. C.; Hofman, G. L.; Colburn, R. P.; Adamson, M. G. et al.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Nuclear Waste Materials Characterization Center. Semiannual progress report, April 1985-September 1985

Description: Work continued on converting MCC Quality Assurance practices to comply with the national QA standard for nuclear facilities, ANSI/ASME NQA-1. Support was provided to the following: Office of Geologic Repositories; Salt Repository Project; Basalt Waste Isolation Project; Office of Defense Waste and Byproducts Management; Hanford Programs; Transportation Technology Center; and West Valley Demonstration Project. (LM)
Date: December 1, 1985
Creator: Mendel, J.E. (comp.)
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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D9 experiment: heat removal from stratified UO/sub 2/ debris

Description: The D9 experiment investigated the coolability of a shallow (77 mm), stratified urania bed in sodium. The bed was fission heated in the Annular Core Research Reactor (ACRR) at Sandia National Laboratories to simulate the effects of radioactive decay heating. It was the first stratified debris bed experiment to use an extended UO/sub 2/ particle size distribution (0.038 to 4.0 mm). Dryout occurred at powers ranging from 0.10 to 0.58 W/g, which was close to the incipient boiling power and before … more
Date: April 1, 1985
Creator: Ottinger, C A; Mitchell, G W; Lipinski, R J & Kelly, J E
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Reaction of water vapor with a clean liquid uranium surface

Description: To study the reaction of water vapor with uranium, we have exposed clean liquid uranium surfaces to H/sub 2/O under UHV conditions. We have measured the surface concentration of oxygen as a function of exposure, and determined the maximum attainable surface oxygen concentration X/sub 0//sup s/ as a function of temperature. We have used these measurements to estimate, close to the melting point, the solubility of oxygen (X/sub 0//sup b/, < 10/sup -4/) and its surface segregation coefficient ..be… more
Date: October 24, 1985
Creator: Siekhaus, W.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Thermal reactor design for a neutron scattering source facility

Description: The purpose of this paper is to present conclusions drawn from preliminary neutronic calculations and to present a possible reactor design configuration capable of meeting the above thermal flux level, flux location, and lifetime requirements. (JDB)
Date: January 1, 1985
Creator: Worley, B. A.; Difilippo, F. C. & Vondy, D. R.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Thermionic emission and work function of U and UO/sub 2/

Description: Thermionic emission measurements have been used to determine the work function (phi) of pure and oxidized uranium samples between 1100 and 1300/sup 0/K; Auger electron spectroscopy (AES) was used to verify the cleanliness and compositions of the samples. It was found that impurities present in ppM amounts in the bulk U segregated to the surface upon heating and had an appreciable effect on the zero-field emission currents as well as the slopes of the Schottkey curves obtained at various tempera… more
Date: February 1, 1985
Creator: McLean, W. & Chen, H. L.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Band structure of UO/sub 2/: an angle resolved and resonant photoemission study

Description: A detailed study of angle resolved photoemission of UO/sub 2/ <100> in the normal emission configuration is presented. The results are compared to a semirelativistic LAPW band calculation with the actual calculated empty bands used in the data reduction. Excellent agreement is found with calculations both for filled states as well as critical points in the empty states with no adjustment of bands. f-p hybridization is found at the leading edge of the valence band and not at the bottom of the va… more
Date: October 1, 1985
Creator: Arko, A. J.; Koelling, D. D.; Boring, A. M.; Ellis, W. P. & Cox, L. E.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Performance testing of refractory alloy-clad fuel elements for space reactors

Description: Two fast reactor irradiation tests, SP-1 and SP-2, provide a unique and self-consistent data set with which to evaluate the technical feasibility of potential fuel systems for the SP-100 space reactor. Fuel pins fabricated with leading cladding candidates (Nb-1Zr, PWC-11, and Mo-13Re) and fuel forms (UN and UO/sub 2/) are operated at temperatures typical of those expected in the SP-100 design. The first US fast reactor irradiated, refractory alloy clad fuel pins, from the SP-1 test, reached 1 a… more
Date: January 1, 1985
Creator: Dutt, D.S.; Cox, C.M.; Karnesky, R.A. & Millhollen, M.K.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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