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in subjects: "Austenitic Steels"

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Modeling of Microstructure Evolution in Austenitic Stainless Steels Irradiated Under Light Water Reactor Conditions

A model for the development of microstructure during irradiation in fast reactors has been adapted for light water reactor (LWR) irradiation conditions (275 {approximately} 325 C, up to {approximately}10 dpa). The original model was based on the rate-theory, and included descriptions of the evolution of both dislocation loops and cavities. The model was modified by introducing in-cascade interstitial clustering, a term to account for the dose dependence of this clustering, and mobility of inter… more

Date: November 30, 1998

Creator: Gan, J.; Stoller, R.E. & Was, G.S.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Irradiation creep at temperatures of 400 {degrees}C and below for application to near-term fusion devices

To study irradiation creep at 400{degrees}C and below, a series of six austenitic stainless steels and two ferritic alloys was irradiated sequentially in two research reactors where the neutron spectrum was tailored to produce a He production rate typical of a fusion device. Irradiation began in the Oak Ridge Research Reactor; and, after an atomic displacement level of 7.4 dpa, the specimens were moved to the High Flux Isotope Reactor for the remainder of the 19 dpa accumulated. Irradiation tem… more

Date: December 31, 1996

Creator: Grossbeck, M. L.; Gibson, L. T. & Mansur, L. K.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Technical progress report, March 1, 1991--December 12, 1991

During this period work was focussed on three major topics: (1) developing electropotential drop techniques to monitor the growth of part-through cracks; (2) developing combined micromechanical and finite element crack tip field models for failure assessment for ferritic and martensitic steels; (3) analysis and assessment of radiation-induced degradation of the mechanical properties of austenitic stainless steels pertinent to near term fusion machines. These activities are part of a broad effor… more

Date: February 1, 1996

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Technical progress summary for the period, March 1, 1992--January 1, 1993

During this period work has encompassed: (1) development of electropotential drop techniques to monitor the growth of cracks in steel specimens for a variety of specimen geometries; (2) micromechanical modeling of fracture using finite element calculations of crack and notch-tip stress and strain fields; (3) examining helium effects on radiation damage in austenitic and ferritic stainless steels; (4) analysis of the degradation of the mechanical properties of austenitic stainless steels for the… more

Date: February 1, 1996

Item Type: Report

Partner: UNT Libraries Government Documents Department

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The Properties and Weldability of Materials for Fusion Reactor Applications

Low-activation austenitic stainless steels have been suggested for applications within fusion reactors. The use of these nickel-free steels will help to reduce the radioactive waste management problem after service. one requirement for such steels is the ability to obtain sound welds for fabrication purposes. Thus, two austenitic Fe-Cr-Mn alloys were studied to characterize the welded microstructure and mechanical properties. The two steels investigated were a Russian steel (Fe-11.6Cr19.3Mn-0.1… more

Date: November 15, 1991

Creator: Chin, B. A.; Kee, C. K.; Wilcox, R. C. & Zinkle, S. J.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Manufacture of Alumina-Forming Austenitic Steel Alloys by Conventional Casting and Hot-Working Methods

Oak Ridge National Laboratory (ORNL) and Carpenter Technology Corporation (CarTech) participated in an in-kind cost share cooperative research and development agreement (CRADA) effort under the auspices of the Energy Efficiency and Renewable Energy (EERE) Technology Maturation Program to explore the feasibility for scale up of developmental ORNL alumina-forming austenitic (AFA) stainless steels by conventional casting and rolling techniques. CarTech successfully vacuum melted 301b heats of four… more

Date: March 10, 2009

Creator: Brady, M. P.; Yamamoto, Y. & Magee, J. H.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Assessment of Initial Test Conditions for Experiments to Assess Irradiation Assisted Stress Corrosion Cracking Mechanisms

Irradiation-assisted stress corrosion cracking is a key materials degradation issue in today s nuclear power reactor fleet and affects critical structural components within the reactor core. The effects of increased exposure to irradiation, stress, and/or coolant can substantially increase susceptibility to stress-corrosion cracking of austenitic steels in high-temperature water environments. . Despite 30 years of experience, the underlying mechanisms of IASCC are unknown. Extended service cond… more

Date: April 1, 2011

Creator: Busby, Jeremy T & Gussev, Maxim N

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Thermal stability of high temperature structural alloys

High temperature structural alloys were evaluated for suitability for long term operation at elevated temperatures. The effect of elevated temperature exposure on the microstructure and mechanical properties of a number of alloys was characterized. Fe-based alloys (330 stainless steel, 800H, and mechanically alloyed MA 956), and Ni-based alloys (Hastelloy X, Haynes 230, Alloy 718, and mechanically alloyed MA 758) were evaluated for room temperature tensile and impact toughness properties after … more

Date: March 1, 1999

Creator: Jordan, C. E.; Rasefske, R. K. & Castagna, A.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Fracture toughness of irradiated candidate materials for ITER first wall/blanket structures

Disk compact specimens of candidate materials for first wall/blanket structures in ITER have been irradiated to damage levels of about 3 dpa at nominal irradiation temperatures of either 90 or 250{degrees}C. These specimens have been tested over a temperature range from 20 to 250{degrees}C to determine J-integral values and tearing moduli. The results show that irradiation at these temperatures reduces the fracture toughness of austenitic stainless steels, but the toughness remains quite high. … more

Date: December 31, 1994

Creator: Alexander, D.J.; Pawel, J.E.; Grossbeck, M.L.; Rowcliffe, A.F. & Shiba, Kiyoyuki

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Advanced austenitic alloys for fossil power systems. CRADA final report

In 1993, a Cooperative Research and Development Agreement (CRADA) was undertaken between Oak Ridge National Laboratory and ABB Combustion Engineering t examine advanced alloys for fossil power systems. Specifically, the use of advanced austenitic stainless steels for superheater/reheater construction in supercritical boilers was examined. The strength of cold-worked austenitic stainless steels was reviewed and compared to the strength and ductility of advanced austenitic stainless steels. The a… more

Date: August 1, 1998

Creator: Swindeman, R. W.; Cole, N. C.; Canonico, D. A. & Henry, J. F.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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ABSTRACTS: Seventh annual conference on fossil energy materials

Objective of the Advanced Research and Technology Development materials program is to conduct R and D on materials for fossil energy applications (coal processing, coal liquefaction, gasification, heat engines and recovery, combustion systems, fuel cells). Research is aimed at better understanding of materials in fossil energy environments and development of new materials for improvement of plant operations and reliability. Abstracts are given of 37 papers on ceramics/composites, intermetallics… more

Date: June 1, 1993

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Report on thermal aging effects on tensile properties of ferritic-martensitic steels.

This report provides an update on the evaluation of thermal-aging induced degradation of tensile properties of advanced ferritic-martensitic steels. The report is the first deliverable (level 3) in FY11 (M3A11AN04030103), under the Work Package A-11AN040301, 'Advanced Alloy Testing' performed by Argonne National Laboratory, as part of Advanced Structural Materials Program for the Advanced Reactor Concepts. This work package supports the advanced structural materials development by providing ten… more

Date: May 10, 2012

Creator: Li, M.; Soppet, W. K.; Rink, D. L.; Listwan, J. T. & Natesan, K.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Metal cutting simulation of 4340 steel using an accurate mechanical description of meterial strength and fracture

Strength and fracture constitutive relationships containing strain rate dependence and thermal softening are important for accurate simulation of metal cutting. The mechanical behavior of a hardened 4340 steel was characterized using the von Mises yield function, the Mechanical Threshold Stress model and the Johnson- Cook fracture model. This constitutive description was implemented into the explicit Lagrangian FEM continuum-mechanics code EPIC, and orthogonal plane-strain metal cutting calcula… more

Date: September 1, 1996

Creator: Maudlin, P.J. & Stout, M.G.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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High-pressure tritium equipment

Some solutions to problems of compressing and containing tritium gas to 200 MPa at 700 K are discussed The principal emphasis is on commercial compressors and high-pressure equipment that can be modified easily by the researcher for safe use with tritium. Experience with metal belows and diaphragm compressors has been favorable. Selection of materials, fittings and gauges for high- pressure tritium work also is reviewed briefly.

Date: December 31, 1976

Creator: Coffin, D.O.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Recent developments in the study of phase stability of austenitic stainless steels and its relation to properties

Much work has been done over the years in alloy development of stainless steels and in the characterization of stainless steel microstructures and properties. However, in recent years there have been significant new advances made, and insights gained, into the physical metallurgy of these materials. In particular, advanced techniques have led to new information on the phase stability of stainless steels and the influence of the phase stability on mechanical properties. This paper will highlight… more

Date: December 31, 1995

Creator: Vitek, J.M. & David, S.A.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Buckling analysis of spent fuel basket

The basket for a spent fuel shipping cask is subjected to compressive stresses that may cause global instability of the basket assemblies or local buckling of the individual members. Adopting the common buckling design practice in which the stability capacity of the entire structure is based on the performance of the individual members of the assemblies, the typical spent fuel basket, which is composed of plates and tubular structural members, can be idealized as an assemblage of columns, beam-… more

Date: May 1, 1995

Creator: Lee, A.S. & Bumpas, S.E.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Fireside Corrosion in Oxy-fuel Combustion of Coal

Oxy-fuel combustion is burning a fuel in oxygen rather than air. The low nitrogen flue gas that results is relatively easy to capture CO{sub 2} from for reuse or sequestration. Corrosion issues associated with the environment change (replacement of much of the N{sub 2} with CO{sub 2} and higher sulfur levels) from air- to oxy-firing were examined. Alloys studied included model Fe-Cr alloys and commercial ferritic steels, austenitic steels, and nickel base superalloys. The corrosion behavior is … more

Date: May 20, 2012

Creator: Holcomb, G. R.; Tylczak, J.; Meier, G. H.; Lutz, B.; Jung, K.; Mu, N. et al.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Mechanical properties of four RSP stainless steel alloys

Four austenitic stainless steel alloys were processed by consolidating rapidly solidified gas atomized power using hot extrusion. These materials were characterized by measuring grain growth, hardness, tensile properties from 24 to 800{degrees}C, and creep-rupture at 600{degrees}C.

Date: December 1, 1996

Creator: Korth, G.E.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Modeling pitting corrosion damage of high-level radioactive-waste containers, with emphasis on the stochastic approach

Recent efforts to identify methods of modeling pitting corrosion damage of high-level radioactive-waste containers are described. The need to develop models that can provide information useful to higher level system performance assessment models is emphasized, and examples of how this could be accomplished are described. Work to date has focused upon physically-based phenomenological stochastic models of pit initiation and growth. These models may provide a way to distill information from mecha… more

Date: January 1, 1993

Creator: Henshall, G.A.; Halsey, W.G.; Clarke, W.L. & McCright, R.D.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Mechanical model for ductility loss

A mechanical model was constructed to probe into the mechanism of ductility loss. Fracture criterion based on critical localized deformation was undertaken. Two microstructure variables were considered in the model. Namely, the strength ratio of grain boundary affected area to the matrix, ..cap omega.., and the linear fraction, x, of grain boundary affected area. A parametrical study was carried out. The study shows that the ductility is very sensitive to those microstructure parameters. The fu… more

Date: February 11, 1980

Creator: Hu, W.L.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Irradiation-induced instability of MnS precipitates and its possible contribution to IASCC in light water reactors

Although a number of candidate mechanisms have been proposed to participate in the IASCC phenomenon, it is not clear at this time that all of the contributing mechanisms have been identified. A new mechanism was proposed by Garner and Greenwood as a potential contribution to IASCC that involves the radiation-induced release into solution of sulphur and other deleterious elements that are normally concentrated into MnS precipitates. The instability arises from the combined action of the transmut… more

Date: October 1, 1997

Creator: Garner, F. A.; Greenwood, L. R. & Chung, H. M.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Helium embrittlement model and program plan for weldability of ITER materials

This report presents a refined model of how helium embrittles irradiated stainless steel during welding. The model was developed based on experimental observations drawn from experience at the Savannah River Site and from an extensive literature search. The model shows how helium content, stress, and temperature interact to produce embrittlement. The model takes into account defect structure, time, and gradients in stress, temperature and composition. The report also proposes an experimental pr… more

Date: February 1, 1997

Creator: Louthan, M. R., Jr.; Kanne, W. R., Jr.; Tosten, M. H.; Rankin, D. T. & Cross, B. J.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Silicon`s role in determining swelling in neutron-irradiated Fe-Cr-Ni-Si alloys

Two silicon-modified alloy series, one based on Fe-15Cr-20Ni and another based on Fe-15Cr-25Ni were irradiated at target temperatures between 399 and 649{degree}C in EBR-II. The influence of silicon on swelling is more complex than previously envisioned and indicates that silicon plays two or more competing roles while in solution. Radiation-induced formation of {gamma}{prime} (Ni{sub 3}Si) precipitates is dependent on silicon and nickel content, as well as temperature. Precipitation of {gamma}… more

Date: November 1, 1991

Creator: Sekimura, N.; Garner, F. A. & Newkirk, J. W.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Aluminide Coatings for Power-Generation Applications

Aluminide coatings are of interest for many high temperature applications because of the possibility of improving the oxidation of structural alloys by forming a protective external alumina scale. In order to develop a comprehensive lifetime evaluation approach for aluminide coatings used in fossil energy systems, some of the important issues have been addressed in this report for aluminide coatings on Fe-based alloys (Task I) and on Ni-based alloys (Task II). In Task I, the oxidation behavior … more

Date: November 17, 2003

Creator: Zhang, Y

Item Type: Report

Partner: UNT Libraries Government Documents Department