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Compatibility testing of vitrified waste forms

Description: An experimental program to evaluate candidate metals for use in the fabrication of canisters for long-term storage of vitrified radioactive wastes is described. The long-term compatibility of the candidate metal both with the contained vitrified radioactive waste and with the external environments expected in possible final storage locations will be determined. These tests involve heating combinations of waste forms and canister metals in intimate contact for up to 50,000 hr to accelerate any r… more
Date: March 6, 1978
Creator: Rankin, W.N.
Partner: UNT Libraries Government Documents Department
open access

TCT hybrid preconceptual blanket design studies

Description: The conceptual design of a tokamak fusion-fission (hybrid) reactor, which produces electric power and fissile material, has been performed in a cooperative effort between Princeton's Plasma Physics Laboratory (PPPL) and Battelle's Pacific Northwest Laboratories (PNL). PPPL, who had overall project lead responsibility, designed the fusion driver system. Its core consists of a tokamak plasma maintained in the two-component torus (TCT) mode by both D and T beams and having a single null poloidal d… more
Date: January 1, 1978
Creator: Aase, D. T.; Bampton, M. C. C.; Doherty, T. J.; Leonard, B. R.; McCann, R. A.; Newman, D. F. et al.
Partner: UNT Libraries Government Documents Department
open access

Discussion: ''toughness variations during the tempering of a plain carbon martensitic steel'' by J. E. King, R. F. Smith and J. F. Knott. Retained austenite and transgranular tempered martensite embrittlement

Description: Discussion is presented to substantiate, clarify and reinterpret some of the results of the above authors for the existence and origin of tempered martensite embrittlement (TME) in relation to retained austenite, with reference to the experimental steels worked at LBL for the past several years.
Date: June 1, 1977
Creator: Rao, B.V.N. & Thomas, G.
Partner: UNT Libraries Government Documents Department
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Phosphate-bonded glass cements for geothermal wells. Final report

Description: Calcium aluminosilicate glasses were found to react with phosphoric acid in three ways depending upon silica content. Above 55% SiO/sub 2/ they are insoluble while below 50% they dissolve readily. The transition compositions release calcium and aluminum ions and a silica gel phase replaces the glass. Activation energies in the order of 10 kcal/mole are associated with the dissolution. Equilibrium studies in the systems CaO-P/sub 2/O/sub 5/-H/sub 2/O, Al/sub 2/O/sub 3/-P/sub 2/O/sub 5/-H/sub 2/O… more
Date: September 1, 1979
Creator: Rockett, T.J.
Partner: UNT Libraries Government Documents Department
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Integrity of PWR pressure vessels during overcooling accidents

Description: The reactor pressure vessel in a pressurized water reactor is normally subjected to temperatures and pressures that preclude propagation of sharp, crack-like defects that might exist in the wall of the vessel. However, there is a class of postulated accidents, referred to as overcooling accidents, that can subject the pressure vessel to severe thermal shock while the pressure is substantial. As a result of such accidents vessels containing high concentrations of copper and nickel, which enhance… more
Date: January 1, 1982
Creator: Cheverton, R.D.; Iskander, S.K. & Whitman, G.D.
Partner: UNT Libraries Government Documents Department
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Coal Technology Program. Progress report for November 1977

Description: A block of Pittsburgh seam bituminous coal and a block of Wyodak subbituminous coal were pyrolyzed under reducing gas in support of in situ gasification. Information from previously completed block pyrolysis of bituminous coal under an argon atmosphere show that differences in evolved gas result from differences in heating rates. Compared to block pyrolysis at 0.3 C/sup 0//min, block pyrolysis at 3 C/sup 0//min produces less gas but gas with a higher heating value, yielding a higher overall pyr… more
Date: January 1, 1978
Partner: UNT Libraries Government Documents Department
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Investigation of joining techniques for advanced austenitic alloys

Description: Modified Alloys 316 and 800H, designed for high temperature service, have been developed at Oak Ridge National Laboratory. Assessment of the weldability of the advanced austenitic alloys has been conducted at the University of Tennessee. Four aspects of weldability of the advanced austenitic alloys were included in the investigation.
Date: May 1, 1991
Creator: Lundin, C. D.; Qiao, C. Y. P.; Kikuchi, Y.; Shi, C. & Gill, T. P. S.
Partner: UNT Libraries Government Documents Department
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Elastic and Plastic Strains and the Stress Corrosion Cracking of Austenitic Stainless Steels. Progress Report, April 30, 1977--December 30, 1977

Description: A newly developed test environment based on NaCl, Na/sub 2/SO/sub 4/, and HCl has provided some insight to several aspects of SCC in a transformable austenitic stainless steel. Current vs. time curves indicated the presence of the formation of a ''protective'' film which drastically reduced the anodic current leading to failure. This film, not indicated by the polarization curves, is subject to highly localized damage such as pitting. Thus, although it allows only very small corrosion currents,… more
Date: January 1, 1978
Creator: Troiano, A. R.
Partner: UNT Libraries Government Documents Department
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Radiation-induced segregation in HT-9 martensitic steel

Description: Miniature notched-bar specimens of normalized and tempered HT-9 were neutron irradiated to approx.13 dpa and broken at liquid nitrogen temperatures in a UHV chamber. Fracture surfaces were analyzed using scanning Auger electron spectroscopy. Following irradiation at 410/sup 0/C, the fracture surface contained a small number of large relatively smooth facets, which are thought to be prior austenite grain boundaries. Strong segregation of Ni, Cr, Si, and P was detected at these surfaces, the rema… more
Date: January 1, 1986
Creator: Clausing, R.E.; Heatherly, L.; Faulkner, R.G.; Rowcliffe, A.F. & Farrell, K.
Partner: UNT Libraries Government Documents Department
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Deposition and removal of radioactive isotopes from LMFBR components

Description: The development of an analytical model to describe the production, transport and eventual removal of radioactive materials in the primary sodium of LMFBR's is a continuing Sodium Technology activity sponsored by the Department of Energy. This paper describes studies directed toward obtaining an understanding of the deposition from sodium of fuel cladding activated corrosion products onto stainless steel alloys and the effect of their diffusion into the base metal on the process required to deco… more
Date: January 1, 1980
Creator: Hill, E. F.; Lutton, J. M. & Maffei, H. P.
Partner: UNT Libraries Government Documents Department
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Radiolytic Effects on Ion Exchangers During the Storage of Radioactive Wastes

Description: Radiolytic effects on ion exchangers are being recognized as a significant problem in the processing and storage of high-specific-activity radioactive waste forms. Two major literature surveys and a series of scoping experiments conducted during this investigation indicate that radiation decomposition of ion exchange materials has the potential for a variety of undesirable consequences. These include the ready dispersion of adsorbed radionuclides to the environment, corrosion and pressurization… more
Date: January 1, 1982
Creator: Pillay, K. K. S. & Palau, G. L.
Partner: UNT Libraries Government Documents Department
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PNL technical review of pressurized thermal-shock issues. [PWR]

Description: Pacific Northwest Laboratory (PNL) was asked to develop and recommend a regulatory position that the Nuclear Regulatory Commission (NRC) should adopt regarding the ability of reactor pressure vessels to withstand the effects of pressurized thermal shock (PTS). Licensees of eight pressurized water reactors provided NRC with estimates of remaining effective full power years before corrective actions would be required to prevent an unsafe operating condition. PNL reviewed these responses and the r… more
Date: July 1, 1982
Creator: Pedersen, L. T.; Apley, W. J.; Bian, S. H.; Defferding, L. J.; Morgenstern, M. H.; Pelto, P. J. et al.
Partner: UNT Libraries Government Documents Department
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Evaluation of weldments in Type 21-6-9 stainless steel for Compact Ignition Tokamak structural applications: Phase 1

Description: Primary design considerations for the Compact Ignition Tokamak toroidal field-coil cases are yield strength and toughness in the temperature range from 77 to 300 K. Type 21-6-9 stainless steel, also still known by its original Armco Steel Company trade name Nitronic 40, is the proposed alloy for this application. It has high yield strength and usually adequate base metal toughness, but weldments in thick sections have not been adequately characterized in terms of mechanical properties or hot-cr… more
Date: June 1, 1991
Creator: Alexander, D. J.; Goodwin, G. M. & Bloom, E. E.
Partner: UNT Libraries Government Documents Department
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Microstructural and solidification cracking evaluation of electron beam welds in 304L

Description: Weld hot cracking of stainless steels is a major materials-related problem in the welding industry. This present investigation evaluates the crack susceptibility of highly-constrained EB welds made in materials whose DeLong ferrite potentials range from zero to nine FN. In addition, the effect of piece part strength level on cracking is examined. This study has revealed that these deep penetration EB welds have regions that solidify as primary austenite, even when the DeLong ferrite potential i… more
Date: January 1, 1991
Creator: Sturgill, P.L.; Campbell, R.D. & Henningsen, J.L.
Partner: UNT Libraries Government Documents Department
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Transport and deposition of activation products in a helium cooled fusion power plant

Description: The transport and deposition of neutron activation products in a helium cooled tokamak fusion power plant are investigated. Stainless steel is used as coolant channel material for a helium/steam system. The important gamma emitting nuclides /sup 56/Mn, /sup 54/Mn, /sup 57/Co, /sup 58/Co, /sup 60/Co, /sup 51/Cr, and /sup 99/Mo are considered. The dominant release mechanism identified is direct daughter recoil emission from (n,x) type reactions. Corrosion and evaporation are discussed. The radion… more
Date: September 1, 1980
Creator: Bickford, W.E.
Partner: UNT Libraries Government Documents Department
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Investigation of cooling coil corrosion in storage tanks for radioactive waste

Description: The high frequency of cooling coil leaks observed in high-heat waste storage tanks soon after sludge removal operations is attributed to pitting, according to laboratory corrosion studies. Experiments show that the most likely series of events leading to coil leakage is (1) excessive dilution of basic nitrite in the supernate, (2) initiation of attack in crevices due to oxygen depletion cells, and (3) acceleration of the attack by sulfate dissolved from the sludge. When sludge was slurried with… more
Date: January 1, 1978
Creator: Ondrejcin, R.S.
Partner: UNT Libraries Government Documents Department
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Material Considerations in the Design of a Bulk Shield for the Fusion Engineering Device

Description: The FED bulk shield provides protection from high-energy neutrons and gamma rays and removes nuclear heat generated. Bulk shield optimization calculations were conducted using the Los Alamos ONEDANT discrete ordinates and the General Atomic PATH point kernel codes. Six candidate steel alloys were considered.
Date: January 1, 1981
Creator: Kirchner, J. & Engholm, B. A.
Partner: UNT Libraries Government Documents Department
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Fossil Energy Advanced Research and Technology Development (AR TD) Materials Program semiannual progress report for the period ending September 30, 1991

Description: The objective of the Fossil Energy Advanced Research and Technology Development Materials Program is to conduct research and development on materials for fossil energy applications with a focus on the longer-term and generic needs of the various fossil fuel technologies. The Program includes research aimed toward a better understanding of materials behavior in fossil energy environments and the development of new materials capable of substantial enhancement of plant operations and reliability. … more
Date: April 1, 1992
Creator: Judkins, R.R. & Cole, N.C. (comps.)
Partner: UNT Libraries Government Documents Department
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A numerical study of Rayleigh-Taylor instability in aluminum and steel plates

Description: The SCRAM code is applied to the study of Rayleigh-Taylor instability in metal plates, and comparisons of these computer results are made with experimental data for 1100-O aluminum, 6061-T6 aluminum and 304 stainless steel. Various models for the pressure, temperature, and strain-rate dependencies of the flow stress are compared in the computer calculations. The coefficients that are required in these models to give good agreement with the experimental results are generally close to values that… more
Date: March 1, 1988
Creator: Daly, B.J.
Partner: UNT Libraries Government Documents Department
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Assessment of lamellar tearing

Description: Information on lamellar tearing is summarized and related to proposed ASME Code requirements. Lamellar tearing is characterized as a complex phenomenon related to poor short transverse ductility and through-thickness strain. The material, welding, and design variables that affect lamellar tearing are shown to be complex and interrelated. The commonly reported tests for assessing material susceptibility are described, with the controversy over their validity being carefully detailed. Although th… more
Date: March 1, 1978
Creator: McEnerney, J.W.
Partner: UNT Libraries Government Documents Department
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Energy use in Japan and the United States

Description: This comparative study was undertaken to explain in part the per capita differential between the two countries. In the introduction, the ratios of energy per capita and energy per dollar of Gross Domestic Product (GDP) are presented. The exchange rates utilized to convert GDP to a common currency are discussed in detail. Brief sections on the energy supply and electric generation situation in Japan are included for background information, followed by the body of the report devoted to the energy… more
Date: August 1, 1977
Creator: Doernberg, A
Partner: UNT Libraries Government Documents Department
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Spin forming development

Description: Bendix product applications require the capability of fabricating heavy gage, high strength materials. Five commercial sources have been identified that have the capability of spin forming metal thicknesses greater than 9.5 mm and four equiment manufacturers produce machines with this capability. Twelve assemblies selected as candidates for spin forming applications require spin forming of titanium, 250 maraging steel, 17-4 pH stainless steel, Nitronic 40 steel, 304 L stainless steel, and 6061 … more
Date: May 1, 1982
Creator: Gates, W.G.
Partner: UNT Libraries Government Documents Department
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LWR-PV damage estimate methodology

Description: A credible estimate of the pressure vessel lifetime due to neutron-induced embrittlement is studied. The first step toward this goal is the accurate prediction of fluence and neutron energy spectrum at the pressure vessel. This, in turn, is obtained from least squares unfolding techniques of dosimetry measurements at a surveillance position, transport calculations, and a translation of information obtained at the surveillance position to the damage position. Including a prototypic neutron field… more
Date: January 1, 1980
Creator: Wagschal, J.J.; Maerker, R.E. & Broadhead, B.L.
Partner: UNT Libraries Government Documents Department
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