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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.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Repair Welding of Fusion Reactor Components

Description: Recent experimental investigations indicate that the repair welding of irradiated materials containing greater than 1 to 2.5 appm helium leads to catastrophic cracking in the heat affected zone of the weld. The high temperatures and cooling tensile stresses which occur during the welding process lead to enhanced helium bubble growth in the heat affected zone region, resulting in catastrophic cracking upon cooling. An investigation is proposed which seeks to determine the effect of stress state … more
Date: May 20, 1992
Creator: Chin, Bryan A.
Item Type: Refine your search to only Report
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.
Item Type: Refine your search to only Report
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.
Item Type: Refine your search to only Report
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.
Item Type: Refine your search to only Article
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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Silicon mass transfer in sodium loops and the resulting/thermal hydraulic effects. [LMFBR]

Description: The element silicon in the surface of new, 300 series stainless steel has been shown to rapidly dissolve in sodium above 525/sup 0/C. It deposits in slightly cooler regions as a crystalline compound with sodium and oxygen. In tests, the deposits have caused increases in hydraulic friction factor (hence, increased pressure loss) of up to 300% at Reynolds Numbers of 14/sup 4/ to 10/sup 5/.Also, they have contributed to local losses of heat transfer rate to 1/10 the original value, at a Reynolds N… more
Date: February 1, 1980
Creator: Yunker, W.H.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Interaction of xenon light with the surface of 304 stainless steel

Description: Laser amplifier frames fabricated from Type 304 stainless steel are known to cause damage to glass lenses by ejecting particles which are deposited on the lenses. High energy pulses of xenon light interact with the steel surface to produce damage sites. Heat treatment and surface cleaning procedures greatly affect the surface stability of the steel and influence contamination generated by the steel. It is believed that inclusions and/or carbides play a role, and the size of damage sites observe… more
Date: February 14, 1978
Creator: Krenzer, R. W.
Item Type: Refine your search to only Report
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.
Item Type: Refine your search to only Article
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.
Item Type: Refine your search to only Report
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.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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THE HEAT CAPACITY OF BERYLLIUM CARBIDE POWDER IN STAINLESS STEEL CAPSULES AS A FUNCTION OF TEMPERATURE (400-1800 F)

Description: The mean heat capacity of a sample of powdered beryllium carbide, a possible moderator material for a nuclear reactor, was determined as a function of temperature. A thin-walled stainless steel capsule containing the material was heated in an electric furnace and dropped into a water calorimeter. The following linear equation for mean heat capacity over the temperature range 50 f C-T f C as a function of temperature, T, was derived from the data by the method of least squares: C/sub p/ = 0.299 … more
Date: April 20, 1949
Creator: Powers, H.; Kostigen, T. & Trice, J.B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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An assessment of the effects of radiation on permanent magnet material in the ALS (Advanced Light Source) insertion devices

Description: Electrons that are lost from the beam during normal operation of a synchrotron radiation source and during a beam dump at the end of a run produce both ionizing radiation and neutrons. This radiation has the potential for damaging sensitive materials, in particular those that need to be very close to the beam. The wigglers and undulators for the Advanced Light Source (ALS) at LBL will use magnetic materials such as the very high performance neodymium-iron-boron, which will be as close as 1 cm a… more
Date: August 1, 1989
Creator: Hassenzahl, W. V.; Jenkins, T. M.; Namito, Y.; Nelson, W. R. & Swanson, W. P.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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CRBRP reactor system shield design and impact of new materials irradiation damage data

Description: Structural materials radiation damage data have received considerable attention in the design of LMFBR permanent reactor structures. A recent FFTF/CRBRP structural materials irradiation experiment, conducted as part of the national program plan for irradiation effects on mechanical properties of LMFBR out-of-core structural materials, has found engineering application in setting energy-dependent neutron exposure limits of irradiated structures. This paper describes the impact of the new irradia… more
Date: January 1, 1980
Creator: Wrights, G.N.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Liquid metal corrosion considerations in alloy development

Description: Liquid metal corrosion can be an important consideration in developing alloys for fusion and fast breeder reactors and other applications. Because of the many different forms of liquid metal corrosion (dissolution, alloying, carbon transfer, etc.), alloy optimization based on corrosion resistance depends on a number of factors such as the application temperatures, the particular liquid metal, and the level and nature of impurities in the liquid and solid metals. The present paper reviews the va… more
Date: January 1, 1984
Creator: Tortorelli, P. F. & DeVan, J. H.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Study of particle rebound characteristics and material erosion at high temperature

Description: In this research an investigation was conducted to study the ash particle rebound characteristics and the associated erosion behavior of alloys and coatings which are widely used in gas and steam turbines. A three-component LDV system was used to measure the restitution parameters of 15 micron mean diameter coal ash particles impacting superalloys and coating at different angles. The presented results show the variation of the particle restitution ratios with the impingement angle for the coate… more
Date: April 1, 1992
Creator: Tabakoff, W.; Hamed, A.; Metwally, A. & Yeuan, J. (Cincinnati Univ., OH (United States). Dept. of Aerospace Engineering and Engineering Mechanics)
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Scale effects in sliding friction: An experimental study

Description: Solid friction is considered by some to be a fundamental property of two contacting materials, while others consider it to be a property of the larger tribosystem in which the materials are contained. A set of sliding friction experiments were designed to investigate the hypothesis that the unlubricated sliding friction between two materials is indeed a tribosystems-related property and that the relative influence of the materials properties or those of the machine on friction varies from one s… more
Date: July 24, 1991
Creator: Blau, P.J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Study of the corrosion rate behavior of ion implanted Fe-based alloys

Description: We report on some studies we have made of the time evolution of the corrosion behavior of ion implanted samples of pure iron, medium carbon steel, and 18-8 Cr-Ni stainless steel. Ti, Cr, Ni, Cu, Mo and Yb were implanted at mean ion energies near 100 keV and at doses up to 1 {times} 10{sup 17} cm{sup {minus}2} using a Mevva metal ion implantation facility. A novel feature of this experiment was the simultaneous implantation with several different implanted species. The implanted samples were imm… more
Date: June 1, 1991
Creator: Weiping, Cai; Wei, Tian; Wu Run (Wuhan Iron and Steel Univ., HB (China)); Godechot, X. & Brown, I. (Lawrence Berkeley Lab., CA (United States))
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Remote reactor repair: GTA (gas tungsten Arc) weld cracking caused by entrapped helium

Description: A repair patch was welded to the wall of a nuclear reactor tank using remotely controlled thirty-foot long robot arms. Further repair was halted when gas tungsten arc (GTA) welds joining type 304L stainless steel patches to the 304 stainless steel wall developed toe cracks in the heat-affected zone (HAZ). The role of helium in cracking was investigated using material with entrapped helium from tritium decay. As a result of this investigation, and of an extensive array of diagnostic tests perfor… more
Date: January 1, 1988
Creator: Kanne, W. R., Jr.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Investigation of stainless steel clad fuel rod failures and fuel performance in the Connecticut Yankee Reactor. Final report

Description: Significant levels of fuel rod failures were observed in the batch 8 fuel assemblies of the Connecticut Yankee reactor. Failure of 304 stainless steel cladding in a PWR environment was not expected. Therefore a detailed poolside and hot cell examination program was conducted to determine the cause of failure and identify differences between batch 8 fuel and previous batches which had operated without failures. Hot cell work conducted consisted of detailed nondestructive and destructive examinat… more
Date: November 1, 1981
Creator: Pasupathi, V. & Klingensmith, R. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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