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in subjects: "Chromium Alloys"

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TCT hybrid preconceptual blanket design studies

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: Report

Partner: UNT Libraries Government Documents Department

open access

Repair Welding of Fusion Reactor Components

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: Report

Partner: UNT Libraries Government Documents Department

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Coal Technology Program. Progress report for November 1977

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

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Investigation of joining techniques for advanced austenitic alloys

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: Report

Partner: UNT Libraries Government Documents Department

open access

Elastic and Plastic Strains and the Stress Corrosion Cracking of Austenitic Stainless Steels. Progress Report, April 30, 1977--December 30, 1977

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: Report

Partner: UNT Libraries Government Documents Department

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Radiation-induced segregation in HT-9 martensitic steel

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.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Deposition and removal of radioactive isotopes from LMFBR components

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: Article

Partner: UNT Libraries Government Documents Department

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Hydrogen embrittlement of austenitic stainless steels

No Description Available.

Date: January 1, 1974

Creator: Louthan, M. R. Jr.; Rawl, D. E. Jr.; Donovan, J. A. & Holmes, W. G.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

High-temperature oxidation and corrosion of materials program

Research progress is reported in the behavior of metals and alloys in gas mixtures at high temperature, corrosion mechanisms in complex environments of low oxidizing potential, hot corrosion of nickel-base alloys at intermediate temperatures, corrosion of solid sulfate deposits, adherence of Al/sub 2/O/sub 3/ oxide films, oxidation behavior of a two-phase alloy Fe-44% Cu, and formation of subscales of varying composition. (FS)

Date: March 1, 1980

Creator: Whittle, D.P.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

PNL technical review of pressurized thermal-shock issues. [PWR]

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: Report

Partner: UNT Libraries Government Documents Department

open access

Evaluation of weldments in Type 21-6-9 stainless steel for Compact Ignition Tokamak structural applications: Phase 1

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.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Influence of compositional modifications on the corrosion of iron aluminides of molten nitrate salts

The corrosion of iron-aluminum alloys by molten nitrate salt as a function of aluminum, chromium, and other minor elements has been studied as part of an alloy design effort aimed at the development of a strong, ductile, corrosion-resistant FeAl type of aluminide. Short- term weight change data were used to examine the compositional dependence of the corrosion processes that occurred upon exposure of iron aluminides to highly oxidizing nitrate salts of 650{degrees}C. Corrosion resistance was fo… more

Date: January 1, 1991

Creator: Tortorelli, P. F. & Bishop, P. S.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Method for fabricating a seal between a ceramic and a metal alloy

A method of fabricating a seal between a ceramic and an alloy comprising the steps of prefiring the alloy in an atmosphere with a very low partial pressure of oxygen, firing the assembled alloy and ceramic in air, and gradually cooling the fired assembly to avoid the formation of thermal stress in the ceramic. The method forms a bond between the alloy and the ceramic capable of withstanding the environment of a pressurized water reactor and suitable for use in an electrical conductivity sensiti… more

Date: July 24, 1981

Creator: Kelsey, P.V. Jr. & Siegel, W.T.

Item Type: Patent

Partner: UNT Libraries Government Documents Department

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Silicon mass transfer in sodium loops and the resulting/thermal hydraulic effects. [LMFBR]

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: Article

Partner: UNT Libraries Government Documents Department

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Interaction of xenon light with the surface of 304 stainless steel

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: Report

Partner: UNT Libraries Government Documents Department

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Sodium compatibility of HT-9 and Fe-9Cr-1Mo steels

Ferritic steels have been receiving significant attention for possible use as steam generator tubing, and as alternate structural materials for liquid-metal heat-transport systems in commercial fast reactors, fusion reactors, etc. The materials are chosen on the basis of their high thermal conductivity, resistance to stress-corrosion-cracking in aqueous and steam environments, favorable fabricability and fairly low cost. These steels are available in several classes based on the microstructure … more

Date: November 1, 1985

Creator: Anantatmula, R. P. & Brehm, W. F.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Microstructural and solidification cracking evaluation of electron beam welds in 304L

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: Article

Partner: UNT Libraries Government Documents Department

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Flash hydropyrolysis of coal. Quarterly report No. 2, April 1--June 30, 1977

With the combination of low hydrogen to coal ratio, high coal feed rate and larger total quantity of coal fed, considerable liquid product is being condensed and collected. Experimental runs conducted at 750/sup 0/C and 800/sup 0/C at pressures up to 3000 psi of hydrogen show overall hydrocarbon yields and particularly gaseous hydrocarbon yields to increase with pressure to approximately 60 percent at 3000 psi. At 750/sup 0/C approximately one third (20 percent) of this yield is in the form of … more

Date: July 1, 1977

Creator: Fallon, P

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Transport and deposition of activation products in a helium cooled fusion power plant

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: Report

Partner: UNT Libraries Government Documents Department

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Growth rate of dislocation loop in Fe-Ni-Cr alloy under Kr sup + ion and electron irradiation

In order to examine the effect of irradiating particle species on the growth rate of radiation-induced dislocation loops, a solution-annealed Fe-25Ni-15Cr-0.02C alloy was irradiated at 723 K first by 1.5 MeV Kr{sup +} ions for 2520 sec, then by 1.5 MeV Kr{sup +} ions and 1.0 MeV electrons simultaneously for 780 sec, and finally by 1.0 MeV electrons for 780 sec with the HVEM-Tandem Facility in Argonne National Laboratory. The calculated damage rate by 1.5 MeV Kr{sup +} ions was 5.8 {times} 10{su… more

Date: October 1, 1991

Creator: Kimoto, T. (National Research Inst. for Metals, Tsukuba, Ibaraki (Japan)); Allen, C.W. & Rehn, L.E. (Argonne National Lab., IL (United States))

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Design and operation of small-scale glass melters for immobilizing radioactive waste

A small-scale (3-kg), joule-heated, continuous melter has been designed to study vitrification of Savannah River Plant radioactive waste. The first melter built has been in nonradioactive service for nearly three years. This melter had Inconel 690 electrodes and uses Monofrax K-3 for the contact refractory. Several problems seem in this melter have had an impact on the design of a full-scale system. Problems include uncontrolled electric currents passing through the throat, and formation of a s… more

Date: January 1, 1980

Creator: Plodinec, M.J. & Chismar, P.H.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Advanced Gas Cooled Nuclear Reactor Materials Evaluation and Development Program. Progress report, January 1, 1980-March 31, 1980

Results are presented of work performed on the Advanced Gas-Cooled Nuclear Reactor Materials Evaluation and Development Program. The objectives of this program are to evaluate candidate alloys for Very High Temperature Reactor (VHTR) Nuclear Process Heat (NPH) and Direct Cycle Helium Turbine (DCHT) applications, in terms of the effect of simulated reactor primary coolant (helium containing small amounts of various other gases), high temperatures, and long time exposures, on the mechanical prope… more

Date: June 25, 1980

Item Type: 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

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: Article

Partner: UNT Libraries Government Documents Department

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Combined electrochemical/surface science investigations of Pt/Cr alloy electrodes

Chromium addition improves the performance of carbon-supported Pt electrodes for oxygen reduction in phosphoric acid fuel cells. To clarify the role of chromium and its chemical nature at the electrode surface, we have performed a combined electrochemical/surface science investigation of a series of bulk Pt/sub x/Cr/sub (1-x)/ alloys (0 less than or equal to x less than or equal to 1). In this paper we report the surface characterization of the starting electrodes by XPS, electrochemical result… more

Date: January 1, 1985

Creator: Daube, K. A.; Paffett, M. T.; Gottesfeld, S. & Campbell, C. T.

Item Type: Article

Partner: UNT Libraries Government Documents Department