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in subjects: "Chromium-Nickel Steels"

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Compatibility testing of vitrified waste forms

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: Article

Partner: UNT Libraries Government Documents Department

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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

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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

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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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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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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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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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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CRBRP reactor system shield design and impact of new materials irradiation damage data

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: Article

Partner: UNT Libraries Government Documents Department

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Liquid metal corrosion considerations in alloy development

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: Article

Partner: UNT Libraries Government Documents Department

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Electroless nickel and ion-plated protective coatings for silvered glass mirrors

A preliminary examination of two methods of protecting second surface silvered glass mirrors from environmental degradation is presented. One method employed silver mirrors overcoated with Al, Ni, 304 stainless steel, Cr, or an Al/Cu alloy prepared by ion-plating. The other method used conventional wet process silver mirrors protected with a thin electroless nickel coating. No attempt was made to optimize the coatings for either method. These experimental mirrors were compared with conventional… more

Date: April 1, 1982

Creator: Lind, M. A.; Chaudiere, D. A.; Dake, L. S. & Stewart, T. L.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Remote reactor repair: GTA (gas tungsten Arc) weld cracking caused by entrapped helium

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: 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

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: Report

Partner: UNT Libraries Government Documents Department

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Postirradiation cladding strength under biaxial loading with an increasing temperature ramp. [LMFBR]

The flow behavior of unirradiated 20% cold worked AISI 316 tubing during constant pressure, increasing temperature tests was modeled with a constitutive relation approach; strain below approximately 0.2% came predominantly from an anelastic portion of the model while higher strains were predominantly plastic. The flow of cladding sections from irradiated fuel pins was largely restricted to the strain region attributed to anelastic deformation due to reduced ductility compared to unirradiated tu… more

Date: April 1, 1980

Creator: Duncan, D. R. & Hunter, C. W.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Comparison of Calculated and Experimental Neutron Attenuation and Streaming Data for Fusion Reactor Design

Integral experiments that measure the neutron and gamma-ray energy spectra resulting from the attenuation of approx. 14 MeV T(D,n)/sup 4/He reaction neutrons in laminated slabs of stainless steel type 304, borated polyethylene, and a tungsten alloy (Hevimet) and from neutrons streaming through a 30-cm-diameter iron duct (L/D = 3) imbedded in a concrete shield have been performed at the Oak Ridge National Laboratory. The facility, NE-213 liquid scintillator detector system, and experimental tech… more

Date: January 1, 1980

Creator: Santoro, R. T.; Alsmiller, R. G., Jr.; Barnes, J. M. & Chapman, G. T.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Controlled powder morphology experiments in megabar 304 stainless steel compaction

Experiments with controlled morphology including shape, size, and size distribution were made on 304L stainless steel powders. These experiments involved not only the powder variables but pressure variables of 0.08 to 1.0 Mbar. Also included are measured container strain on the material ranging from 1.5% to 26%. Using a new strain controllable design it was possible to seperate and control, independently, strain and pressure. Results indicate that powder morphology, size distribution, packing d… more

Date: January 1, 1985

Creator: Staudhammer, K.P. & Johnson, K.A.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Localized corrosion and stress corrosion cracking behavior of austenitic stainless steel weldments containing retained ferrite. Annual progress report, June 1, 1977--March 31, 1978

Localized corrosion (pitting) experiments have been performed on single-phase austenitic 304 stainless steels and on duplex 304 steels containing 6 to 8% retained delta ferrite as a result of rapid solidification (welding). Experimental variables included thermomechanical treatment, solution pH, chloride concentration and solution temperature.

Date: March 1, 1978

Creator: Savage, W. F. & Duquette, D. J.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Effects of nominal and crack-tip strain rate on IGSCC susceptibility in CERT tests

Constant extension rate tests have been performed on sensitized Type 316 stainless steel in oxygenated water (8 ppM O/sub 2/) containing chloride ion impurities (0.5 ppM) over a range of strain rates from 10/sup -5/ to 2 x 10/sup -7/ s/sup -1/. The susceptibility to IGSCC (as quantified by parameters such as crack length at failure) increases with a decrease in strain rate. A model consistent with the observed and postulated crack growth behavior and with a fracture criterion is presented and u… more

Date: September 1, 1983

Creator: Maiya, P.S. & Shack, W.J.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Nuclear performance calculations for the ELMO Bumpy Torus Reactor (EBTR) reference design

The nuclear performance of the ELMO Bumpy Torus Reactor reference design has been calculated using the one-dimensional discrete ordinates code ANISN and the latest available ENDF/B-IV transport cross-section data and nuclear response functions. The calculated results include estimates of the spatial and integral heating rate with emphasis on the recovery of fusion neutron energy in the blanket assembly and minimization of the energy deposition rates in the cryogenic magnet coil assemblies. The … more

Date: December 1, 1977

Creator: Santoro, R. T. & Barnes, J. M.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Tritium permeability of structural materials and surface effects on permeation rates

Tritium management in any system always will include containment such that tritium release rates will be less than established limits and also will be as low as practical. The well known properties of hydrogen to permeate through most materials make the complete containment of tritium an impossible task. However, tritium release rates from a given system can be minimized by two primary efforts. First is the selection of a compatible containment material which frequently also will be the structu… more

Date: January 1, 1980

Creator: Bell, J T; Redman, J D & Bittner, H F

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Fatigue and environmentally assisted cracking in light water reactors

Fatigue and stress corrosion cracking (SCC) for low-alloy steel used in piping and in steam generator and reactor pressure vessels have been investigated. Fatigue data were obtained on medium-sulfur-content A533-Gr B and A106-Gr B steels in high-purity (HP) deoxygenated water, in simulated pressurized water reactor water, and in air. Analytical studies focused on the behavior of carbon steels in boiling water reactor (BWR) environments. Crack-growth rates of composite fracture-mechanics specime… more

Date: March 1, 1992

Creator: Kassner, T.F.; Ruther, W.E.; Chung, H.M.; Hicks, P.D.; Hins, A.G.; Park, J.Y. et al.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Application of ultrasonic waves to assess grain structure in cast stainless steel

Although the ASME code requires the inspection of cast stainless steel (CSS) piping in nuclear reactors, it has not been possible to demonstrate unambiguously that current inspection techniques are adequate. Ultrasonic inspection is difficult because the microstructure of CSS can vary considerably, from elastically isotropic with equiaxed, relatively small grains to elastically anisotropic with a columnar grain structure to a combination of the two. For the near term, improvements that may incr… more

Date: April 1, 1985

Creator: Kupperman, D.S.; Reimann, K.J. & Abrego-Lopez, J.

Item Type: Article

Partner: UNT Libraries Government Documents Department