12 Matching Results

Search Results

Advanced search parameters have been applied.
in subjects: "Steels 360106* -- Metals & Alloys-- Radiation Effects"  
Results: 1 - 12
open access

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.
Partner: UNT Libraries Government Documents Department
open access

Swelling in several commercial alloys irradiated to very high neutron fluence

Description: Swelling values have been obtained from a set of commercial alloys irradiated in EBR-II to a peak fluence of 2.5 x 10/sup 23/ n/cm/sup 2/ (E > 0.1 MeV) or approx. 125 dpa covering the range 400 to 650/sup 0/C. The alloys can be ranked for swelling resistance from highest to lowest as follows: the martensitic and ferritic alloys, the niobium based alloys, the precipitation strengthened iron and nickel based alloys, the molybdenum alloys and the austenitic alloys.
Date: January 1, 1983
Creator: Gelles, D. S. & Pintler, J. S.
Partner: UNT Libraries Government Documents Department
open access

Comparison of fracture behavior for low-swelling ferritic and austenitic alloys irradiated in the Fast Flux Test Facility (FFTF) to 180 DPA

Description: Fracture toughness testing was conducted to investigate the radiation embrittlement of high-nickel superalloys, modified austenitic steels and ferritic steels. These materials have been experimentally proven to possess excellent resistance to void swelling after high neutron exposures. In addition to swelling resistance, post-irradiation fracture resistance is another important criterion for reactor material selection. By means of fracture mechanics techniques the fracture behavior of those hig… more
Date: February 1, 1992
Creator: Huang, F.H.
Partner: UNT Libraries Government Documents Department
open access

Heavy Section Steel Technology Program. Irradiation effects on the fracture toughness of heavy section pressure vessel steels. Quarterly progress report for period ending August 31, 1975

Description: The recovery by postirradiation annealing of the irradiation produced shift in the fracture toughness transition of A533-B was investigated. Irradiation embrittlement was reduced by 40% after annealing at 600/sup 0/F for material that had been irradiated to approximately 2 x 10/sup 19/ n/cm/sup 2/ at 550/sup 0/F.
Date: September 1, 1975
Creator: Williams, J.A.
Partner: UNT Libraries Government Documents Department
open access

Impact of Advanced Microstructural Characterization Techniques on Modeling and Analysis of Radiation Damage

Description: The evolution of radiation-induced alterations of dimensional and mechanical properties has been shown to be a direct and often predictable consequence of radiation-induced microstructural changes. Recent advances in understanding of the nature and role of each microstructural component in determining the property of interest has led to a reappraisal of the type and priority of data needed for further model development. This paper presents an overview of the types of modeling and analysis activ… more
Date: January 1, 1980
Creator: Garner, F. A. & Odette, G. R.
Partner: UNT Libraries Government Documents Department
open access

Detection of radiation-induced changes in electrochemical properties of austenitic stainless steels using miniaturized specimens and the single-loop electrochemical potentiokinetic reactivation method

Description: Single-loop electrochemical potentiokinetic reactivation testing of miniaturized (TEM) specimens can provide reliable data comparable to data obtained with larger specimens. Significant changes in electrochemical properties (increased reactivation current and Flade potential) were detected for PCA and type 316 stainless steels irradiated at 200--420[degrees]C up to 7--9 dpa. Irradiations in the FFTF Materials Open Test Assembly and in the Oak Ridge Research Reactor are reported on. 45 figs., 5 … more
Date: January 1, 1993
Creator: Inazumi, T.; Bell, G.E.C.; Kenik, E.A. & Kiuchi, K.
Partner: UNT Libraries Government Documents Department
open access

Materials data in support of LMFBR core design. [Irradiation swelling and creep; 20 percent C. W. 316 ss; material development]

Description: The properties of the most intense interest for LMFBR are irradiation-induced swelling and creep. The behavior of 20 percent cold-worked Type 316 stainless steel under irradiation is discussed. Knowledge of irradiation creep and research programs are reviewed in some depth. Programs for the development of improved materials for LMFBR duct and cladding applications are now underway. 50 fig. (DLC)
Date: unknown
Creator: Straalsund, J. L.
Partner: UNT Libraries Government Documents Department
open access

Use of pressurized eccentric tubes to study the effect of hydrostatic stress on swelling

Description: A technique for measuring the effect of hydrostatic stress on radiation-induced swelling is presented. This technique is based on the nonuniform hydrostatic stress that arises when an eccentric tube (a tube with inner and outer surfaces having dissimilar centers of revolution) is internally pressurized. The elastic analyses of the thin- and thick-walled eccentric tube are given. The elastic stress state is allowed to relax plastically, based on a constitutive law for deformation during neutron … more
Date: May 1, 1977
Creator: Wolfer, W. G. & Reiley, T. C.
Partner: UNT Libraries Government Documents Department
open access

Evaluation of ferritic alloy Fe-2-1/4Cr-1Mo after neutron irradiation - irradiation creep and swelling

Description: Irradiation creep and swelling measurements are reported for Fe-2-1/4Cr-1Mo after irradiation by fast neutrons over the temperature range 390 to 560/sup 0/C. Diameter change measurements on thin walled pressurized tubes in a bainitic condition and density change measurements on rods in a nonstandard condition were made following irradiation in the Experimental Breeder Reactor II. The irradiation creep specimens were irradiated to a fluence of 5.7 x 10/sup 22/ n/cm/sup 2/ (E > 0.1 MeV) or 30 dpa… more
Date: October 1, 1983
Creator: Gelles, D. S. & Puigh, R. J.
Partner: UNT Libraries Government Documents Department
open access

Evaluation of ferritic alloy Fe-2-1/4Cr-1Mo after neutron irradiation - microstructure development

Description: Microstructural examinations are reported for nine specimen conditions of 2-1/4Cr-1Mo steel which had been irradiated by fast neutrons over the temperature range 390 to 510/sup 0/C. Two heats of material were involved, each with a different preirradiation heat treatment, one irradiated to a peak fluence of 5.1 x 10/sup 22/ n/cm/sup 2/ (E > 0.1 MeV) or 24 dpa and the other to 2.4 x 10/sup 23/ n/cm/sup 2/ (E > 0.1 MeV) or 116 dpa. Void swelling is found following irradiation at 400/sup 0/C in bot… more
Date: May 1, 1984
Creator: Gelles, D. S.
Partner: UNT Libraries Government Documents Department
open access

DT fusion neutron irradiation of LLL 316 stainless steel and SLL silica samples

Description: The DT fusion neutron irradiation of six LLL 316 stainless steel samples and 24 SLL pure silica samples is described. The sample position, beam-on time, and neutron dose record are given. The maximum neutron fluence on any sample was 1.52 x 10/sup 17/ neutrons/cm/sup 2/.
Date: March 31, 1977
Creator: MacLean, S. C.
Partner: UNT Libraries Government Documents Department
open access

Proton induced swelling in Type 316 stainless steel

Description: Annealed Type 316 stainless steel was irradiated by 140-keV protons at 625/sup 0/C in vacuum (approximately 1 x 10/sup -8/ Torr) to study its swelling behavior. The maximum fluence used in the investigation, 2 x 10/sup 20/ protons/cm/sup 2/, created a peak damage of 590 dpa (displacements per atom) based on 25 eV as the displacement threshold. The swellings integrated along the entire proton range were obtained from the measurements of the step-heights at the junction of the irradiated and unir… more
Date: February 1, 1977
Creator: Srivastava, A. K.
Partner: UNT Libraries Government Documents Department
Back to Top of Screen