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Assessment of light water reactor fuel damage during a reactivity initiated accident

Description: This paper presents an assessment of LWR fuel damage during a reactivity initiated accident and comments on the adequacy of the present USNRC design requirements. Results from early SPERT tests are reviewed and compared with results from recent computer simulations and PBF tests. A progression of fuel rod and cladding damage events is presented. High strain rate deformation of relatively cool irradiated cladding early in the transient may result in fracture at a radial average peak fuel enthalp… more
Date: January 1, 1980
Creator: MacDonald, P. E.; Seiffert, S. L.; Martinson, Z. R.; McCardell, R. K.; Owen, D. E. & Fukuda, S. K.
Partner: UNT Libraries Government Documents Department
open access

Low strain diameter expansion of internally pressurized Zircaloy-4 tubing at high temperatures

Description: Tests of closed-end, internally pressurized, Zircaloy-4 tubing specimens were utilized to develop low strain creep characteristics as a function of time at temperatures in the range of 1475/sup 0/F to 2000/sup 0/F (802/sup 0/C to 1093/sup 0/C) and hoop stresses in the range of 250 to 2500 psi for use in loss-of-coolant accident (LOCA) analyses. The strain rate above the start of the alpha to beta phase transformation region, approximately 1490/sup 0/F (810/sup 0/C), was found to be sensitive to… more
Date: March 1978
Creator: White, L.S. & Busby, C.C.
Partner: UNT Libraries Government Documents Department
open access

Thermal transport properties of niobium and some niobium base alloys from 80 to 1600/sup 0/K

Description: The electrical resistivities and absolute Seebeck coefficients of 99.8 at. % niobium with a RRR of 36, Nb-4.8 at. % W, Nb-5 at. % Mo, Nb-10 at. % Mo, and Nb-2.4 at. % Mo-2.4 at. % Zr were measured from 80 to 1600/sup 0/K, and the thermal conductivities of the niobium and Nb-5 at. % W were measured from 80 to 1300/sup 0/K. A technique is described for measuring the electrical resistivity and Seebeck coefficient of a specimen during radial heat flow measurements of the thermal conductivity. The t… more
Date: January 1, 1980
Creator: Moore, J. P.; Graves, R. S. & Williams, R. K.
Partner: UNT Libraries Government Documents Department
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Optimization of film synthesized rare earth transition metal permanent magnet systems

Description: Progress is reported in three areas: high coercivity Sm-Fe-Ti-V, Sm-Fe-Zr, and two element Sm-Fe Sm{sub 5}(Fe,T){sub 17} type crystalline phases; ThMn{sub 12} type pseudobinary SmFe{sub 12-x}T{sub x}(0{le}{times}{le}1.5); and sputter process control for the synthesis of precisely textured rare earth-transition metal magnetic films. (DLC)
Date: January 1, 1992
Creator: Cadieu, F.J.
Partner: UNT Libraries Government Documents Department
open access

Susceptibility of unirradiated recrystallized Zircaloy-4 tubing to stress corrosion cracking

Description: Stress corrosion cracking (SCC) in unirradiated recrystallized Zircaloy-4 internally pressurized tubing specimens in atmospheres containing iodine vapor, cesium, or combinations of iodine and cesium is evaluated experimentally in terms of the effects of internal surface flaw morphology, iodine and cesium concentrations, tubing hydrogen content, test temperature, and test atmosphere water vapor content on the time to failure. The iodine vapor SCC data are analyzed in the framework of a fracture … more
Date: December 1977
Creator: Polan, N. W. & Tucker, R. P.
Partner: UNT Libraries Government Documents Department
open access

Nuclear materials research progress reports for 1979

Description: Research is presented concerning iodide stress corrosion cracking of zircaloy, self-diffusion of oxygen in hypostoichiometric urania, surface chemistry of epitaxial silicon deposition by thermal cracking of silane, kinetics of laser pulse vaporization of UO/sub 2/, gas laser model for laser induced evaporation, solubility of hydrogen in uranium dioxide, thermal gradient migration of metallic inclusions in UO/sub 2/, molecular beam studies of atomic hydrogen reduction of oxides, and thermal grad… more
Date: December 1, 1979
Creator: Olander, D.R.
Partner: UNT Libraries Government Documents Department
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Management of waste cladding hulls. Part II. An assessment of zirconium pyrophoricity and recommendations for handling waste hulls

Description: 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
Partner: UNT Libraries Government Documents Department
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Compact nuclear power systems based on particle bed reactors

Description: Compact, low cost nuclear power systems with an extremely low radioactive inventory are described. These systems use the Particle Bed Reactor (PBR), in which HTGR particle fuel is contained in packed beds that are changed daily. The small diameter particle fuel (500 ..mu..m) is directly cooled utilizing the large heat transfer area available (7.8 m/sup 2//liter), thus allowing high bed power densities (MW/liter).
Date: January 1, 1986
Creator: Horn, F. L.; Powell, J. R.; Steinberg, M. & Takahashi, H.
Partner: UNT Libraries Government Documents Department
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Phase stability in Be-Nb and Be-Nb-Zr intermetallics

Description: Sputter deposition of Be-Nb alloys at low temperature (30{degrees}C) produces an amorphous phase for compositions >5 at.% Nb. A metastable crystalline phase which can be considered a highly faulted form of the Be{sub 12}Nb occurs at higher deposition temperatures or by low-temperature annealing of the amorphous phase. Because of structural similarities, this metastable phase is a precursor to the formation of either Be{sub 12}Nb or Be{sub 17}Nb{sub 2} upon high temperature annealing. There was … more
Date: September 1, 1991
Creator: Brimhall, J.L.; Charlot, L.A. & Bruemmer, S.M.
Partner: UNT Libraries Government Documents Department
open access

Load relaxation studies of zircaloy-4

Description: The results of the present work have shown (1) the load relaxation data of Zircaloy-4 in the temperature range of 200/sup 0/C to 385/sup 0/C can be represented by the phenomenological model based on Hart's plastic equation of state; (2) the room temperature load relaxation data reflect the effects of deformation twinning; (3) at higher temperatures the load relaxation data suggest the contribution of grain boundary sliding; and (4) the effects of strain aging can be identified based on the load… more
Date: January 1, 1976
Creator: Huang, F. H.; Sabol, G. P.; McDonald, S. G. & Li, C. Y.
Partner: UNT Libraries Government Documents Department
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Accurate determination of the parameters of the 292. 4-eV resonance of /sup 91/Zr and the 301. 1-eV resonance of /sup 96/Zr

Description: High-resolution transmission measurements of zirconium metal samples have been carried out at ORELA using the 80-m flight path and an improved /sup 6/Li-glass scintillation neutron detector. Four different thicknesses of the pure zirconium metal and one sample of zircaloy were used in four separate experiments. The transmission data for these samples were measured at room temperature, and one sample was cooled to liquid nitrogen temperature. These data were analyzed using the multilevel R-matri… more
Date: January 1, 1985
Creator: Salah, M.M.; Harvey, J.A.; Hill, N.W.; Hussein, A.Z. & Perey, F.G.
Partner: UNT Libraries Government Documents Department
open access

Cladding creepdown under compression. [BWR; PWR]

Description: Light-water power reactors use Zircaloy tubing as cladding to contain the UO/sub 2/ fuel pellets. In-service operating conditions impose an external hydrostatic force on the cladding, causing it to creep down into eventual contact with the fuel. Knowledge of the rate of such creepdown is of great importance to modelers of fuel element performance. An experimental system was devised for studying creepdown that meets several severe requirements by providing (1) correct stress state, (2) multiple … more
Date: November 9, 1977
Creator: Hobson, D.O.
Partner: UNT Libraries Government Documents Department
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Boundary effects on Zircaloy-4 cladding deformation in LOCA simulation tests. [PWR; BWR]

Description: Deformation behavior of Zircaloy-4 cladding under simulated loss-of-coolant accident (LOCA) conditions is being investigated in the Multirod Burst Test (MRBT) program in single rod and multirod tests. In these tests, internally-pressurized unirradiated Zircaloy-4 tubes containing internal electrical heaters are heated to failure in a low-pressure, superheated-steam environment (200 < Re < 800). The results provide a data base for evaluating deformation and blockage models employed with design-b… more
Date: January 1, 1982
Creator: Longest, A.W.; Chapman, R.H. & Crowley, J.L.
Partner: UNT Libraries Government Documents Department
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ORNL irradiation creep facility

Description: A machine was developed at ORNL to measure the rates of elongation observed under irradiation in stressed materials. The source of radiation is a beam of 60 MeV alpha particles from the Oak Ridge Isochronous Cyclotron (ORIC). This choice allows experiments to be performed which simulate the effects of fast neutrons. A brief review of irradiation creep and experimental constraints associated with each measurement technique is given. Factors are presented which lead to the experimental choices ma… more
Date: September 1, 1980
Creator: Reiley, T. C.; Auble, R. L.; Beckers, R. M.; Bloom, E. E.; Duncan, M. G.; Saltmarsh, M. J. et al.
Partner: UNT Libraries Government Documents Department
open access

Analysis of the ballooning deformation of an internally pressurized thin-wall tube during fast thermal transients

Description: A large-strain time-dependent thermoplastic analysis has been developed for the ballooning deformation of a thin-wall tube subjected to internal pressure, axial loading, and fast thermal transients. This deformation initiates with the onset of plastic instability in the material, the onset being determined by a plastic-instability criterion for strain-rate sensitive materials. The interaction among the local ballooning geometry, the state of stress, and the plastic flow process was considered, … more
Date: January 1, 1977
Creator: Lin, E.I.H.
Partner: UNT Libraries Government Documents Department
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Creep strength of niobium alloys, Nb-1%Zr and PWC-11

Description: A study is being conducted at NASA Lewis Research Center to determine the feasibility of using a carbide particle strengthened Nb-1% Zr base alloy to meet the anticipated temperature and creep resistance requirements of proposed near term space power systems. In order to provide information to aid in the determination of the suitability of the PWC-11 alloy as an alternative to Nb-1% Zr in space power systems this study investigated (1) the long-time high-vacuum creep behavior of the PWC-11 mate… more
Date: January 1, 1990
Creator: Titran, R.H.
Partner: UNT Libraries Government Documents Department
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SSMS near surface analysis of B in irradiated Zircaloy-2: ion implantation standards as a calibration technique

Description: Purpose of this study was to determine the amount of /sup 10/B contamination on the surface of Zircaloy-2 clad irradiated fuel elements that had been stored in an aqueous solution containing 5000 wt. ppM enriched B. SMSS indicated that the contamination was less than 0.06 ..mu..g/cm/sup 2/. (DLC)
Date: January 1, 1980
Creator: Christie, W. H.; Carter, J. A.; Eby, R. E.; Landau, L. & Musick, W. R.
Partner: UNT Libraries Government Documents Department
open access

Irradiation performance of metallic fuels

Description: Argonne National Laboratory has been working for the past five years to develop and demonstrate the Integral Fast Reactor (IFR) concept. The concept involves a closed system for fast-reactor power generation and on-site fuel reprocessing, both designed specifically around the use of metallic fuel. The Experimental Breeder Reactor-II (EBR-II) has used metallic fuel for all of its 25-year life. In 1985, tests were begun to examine the irradiation performance of advanced-design metallic fuel syste… more
Date: January 1, 1989
Creator: Pahl, R. G.; Lahm, C. E.; Porter, D. L.; Batte, G. L.; Hofman, G. L. (Argonne National Lab., Idaho Falls, ID (USA) & Argonne National Lab., IL (USA))
Partner: UNT Libraries Government Documents Department
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Metallurgy of continuous filamentary A15 superconductors

Description: The early history of the bronze process is recapitulated and modifications to the process which have since followed are described. The metallurgical principles, which are involved in the process, are described including the kinetics of the compound growth, the effects of additives on the growth, etc. The superconducting properties of these compounds are also discussed. The influence of metallurgical variables on the superconducting properties is discussed in detail. In discussing the supercondu… more
Date: January 1, 1980
Creator: Suenaga, M
Partner: UNT Libraries Government Documents Department
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Assessment of molten debris freezing in a severe RIA in-pile test. [PWR; BWR]

Description: An understanding of the freezing of molten debris on cold core structures following a hypothetical core meltdown accident in a light water reactor (LWR) is of importance to reactor safety analysis. The purpose of the present investigation was to analyze the transient freezing of the molten debris produced in a severe reactivity initiated accident (RIA) scoping test, designated RIA-ST-4, which was performed in the Power Burst Facility and simulated a BWR control rod drop accident. In the RIA-ST-… more
Date: January 1, 1980
Creator: El-Genk, Mohamed S. & Moore, Richard L.
Partner: UNT Libraries Government Documents Department
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LWR Fuel Rod Behavior Observed During Postulated Accident Conditions: A Comparison of FRAP-T Calculated and PBF Experimental Results

Description: Light water reactor (LWR) fuel rod behavior during transient experiments conducted in the Power Burst Facility is reviewed. The experiments examined simulated hypothetical reactivity initiated accidents (RIA) and power-cooling-mismatch (PCM) events. Fuel rod behavior calculated by the Fuel Rod Analysis Program-Transient (FRAP-T) is compared with the test data. Important physical phenomena observed during the tests and not presently incorporated into the FRAP-T code are: (a) fuel swelling in the… more
Date: January 1, 1980
Creator: Charyulu, M. K.; Hobbins, R. R. & MacDonald, P. E.
Partner: UNT Libraries Government Documents Department
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Tracer diffusion of /sup 60/Co and /sup 63/Ni in amorphous NiZr alloy

Description: Tracer diffusion of /sup 60/Co and /sup 63/Ni in equiatomic amorphous NiZr alloy in the temperature range between 486 and 641/sup 0/K can be described by: D/sub Co/sup */ = 3.7 x 10/sup -7/ exp(-(135 +- 14) kJ mole/sup -1//RT) m/sup 2//sec and D/sub Ni//sup */ = 1.7 x 10/sup -7/ exp(-(140 +- 9) kJ mole/sup -1//RT) m/sup 2//sec. The values of D/sub Ni//sup */ are in reasonable agreement with those measured by the Rutherford backscattering technique. The measured diffusivities were independent of… more
Date: January 1, 1987
Creator: Hoshino, K.; Averback, R. S.; Hahn, H. & Rothman, S. J.
Partner: UNT Libraries Government Documents Department
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