... Title : Effect of Thermal Ageing on the ... of PWR Pressure Vessel Steels and Weldments,. ... The materials investigated include A533B plate and A508 ...
DTIC Science & Technology
... Title : Evaluation of Commercial Production A533-B Steel Plates and Weld Deposits with Extra-Low Copper Content for ... Report Date : OCT 1977. ...
... 3) special A533-B steel heat for ... PRESSURE VESSELS, THERMAL STABILITY, MARAGING ... SENSITIVITY, EMBRITTLEMENT, STEEL, RESPONSE ...
... Title : Reactor Pressure Vessel Steels ASTM A533B and A508 Cl.2: Crack Opening ... Personal Author(s) : Pelli,R. ; Kemppainen,M. ; Toeroenen,K. ...
... FOR GENERATING AE HAS BEEN USED TO PRODUCE REPEATABLE SIGNALS IN TEMPER AND HYDROGEN EMBRITTLED A533B STEEL. ...
This report presents the description of the research programme concerning the reactor pressure vessel steels ASTM A533B A533B and A508 Cl.2. The main aim of the programme is to gather and create adequate information needed in national efforts devoted to ...
National Technical Information Service (NTIS)
After exposure to low and intermediate fluence neutron irradiation, a variety of reactor pressure vessel (RPV) steels, including A533B-type surveillance specimens, Gundremmigen KRB-A ex-service plate, and test reactor irradiated materials, have been analy...
... Title : Indentation Loading Studies of Acoustic Emission from Temper and Hydrogen Embrittled A533B Steel,. Corporate Author : ...
... improved steel production (current practice). ... VESSELS, NUCLEAR REACTORS, RADIATION ... METALLOGRAPHY FISSION REACTOR MATERIALS. ...
... Fatigue Crack Growth in Coarse-Grained, Martensitic A533B Pressure Vessel Steel,. ... one-step-temper-embrittlement', when tempered at 290 ...
... temperature. Strain aging is found at 200 C for A508 but at 288 C for A533B, connected with a Portevin-Le Chatelier effect. ...
This report presents the impact and drop-weight test results of reactor pressure vessel steels ASTM A533B and A508 Cl.2 conducted at the Technical Research Centre of Finland. The ductility of the steels was studied after varying austenitizing and temperin...
Corrosion fatigue crack growth tests have been performed on three pressure vessel steels, A533-B, Ducol W30 and a C-Mn steel, in simulated water reactor environments at ambient temperature and pressure. A533-B and Ducol W30 had a ...
In order to predict the stress reduction during stress relief heat treatment in welded joints of the pressure vessel steel A533B, uniaxial stress relaxation as well as creep tests have been performed. The specimens were isothermally stress relaxed between...
In order to predict the stress reduction during stress relief heat treatment in welded joints of the pressure vessel steel A533B, uniaxial stress relaxation as well as creep tests have been performed for base and weld metal. The specimens were isothermall...
Stress corrosion of the pressure vessel steel A-533-B can be induced by accelerated laboratory tests in oxygenous water at high temperature. Cracking has occurred in water with 8 ppm O sub 2 but not in water with less than 10 ppB O sub 2 . High load durin...
The susceptibility of the reactor pressure vessel steels A533B and A508 cl.2 to strain ageing has been studied using conventional tensile and impact testing of prestrained and aged specimens. The results show a modest susceptibility, seen as an increase i...
This report presents the tensile test results of steels ASTM A533B and A508 Cl.2 obtained in connection with a programme initiated to gather and create information needed for the assessment of the structural integrity of the reactor pressure vessels. The ...
This report describes the heat treatment programmes utilized in connection with a research programme concerning the reactor pressure vessel steels ASTM A533B and A508 Cl.2. (Atomindex citation 10:444562)
This report describes the crack opening displacement (COD) test results for the steels ASTM A533B and A508 C1.2 obtained in connection with a program initiated to gather and create information concerning the manufacturing variables, e.g. heat treatment, n...
Computations have been made of the relaxation of residual stresses in a thick walled tube under conditions corresponding to commercial stress relief heat treatment of the nuclear reactor pressure vessel steel A533B. The distribution of residual stresses w...
The aim with this work was to compare strain data obtained using the film-or camera method and the diffractometer method for residual stress measurement by X-ray diffraction. The measurements were carried out on a weldment of pressure vessel steel A533-B....
A-533-B steel. PHASE VII. CYCLIC CRACKGROWTHIN HYIO0 STEEL IN ...... for Inconel 718 exposed to 34.5 _/m 2 (SO00 psi) hydrogen at ambient temper- ...
NASA Website
... I tempered (Q&T) steel [50] in Figure 9. In this case ... Some of the e' values (A36, A537, A533B, 1020, and low-carbon 3 steels) were obtained by ...
Post weld heat treatments of thick-section A533B steel for nuclear pressure vessels are discussed with reference to the ASME code. The discussion is in the form of a lecture and summarized by noting that the ASME code, in particular Section III, Division ...
... have been performed on three pressure vessel steels, A533-B, Ducol W30 and a C-Mn steel, in simulated water reactor environments at ambient ...
... Quenched and tempered Mn-Mo-Ni steel (ASTM A533B Class 2) and normalized and tempered 2.25Cr-1Mo steel (ASTM A387 Class 2 Grade 22 ...
irradiated A533B pressure vessel steel weld has been characterized by atom probe field-ion microscopy. Many vessel steel weld metal by Burke et a1.[2s41 In this paper, an atom probe field-ion microscopy OF IRRADIATED A533B PRESSURE ...
E-print Network
The report describes progress in the following areas: (a) fatigue crack propagation in reactor pressure vessel steels in an air environment, (b) dynamic fracture toughness of 1-in. (25-mm) and precracked Charpy-V bend specimens under impact loading, (c) postirradiation notch ductility and properties recovery in reactor vessel steels, (d) factors ...
Energy Citations Database
... Developed from federally funded research, testing and training programs; updated annually. ... OF A212-B, A302-B, A533-B, AND A543-1 STEEL. ...
The report covers research for the period 1 November 1969-31 January 1970, includes: (1) demonstration of improved radiation embrittlement resistance in commercial scale melt of Type A533-B pressure vessel steel, (2) an outline of the effects of fast reac...
... their chemical composition, (2) influence of prior temper embrittlement on ... response of Ni-Cr-Mo steel, (3) relative ... of a 7-1/2-in.-thick A533-B Class I ...
... Accession Number : ADD120584. Title : Effects of Specimen Geometry on the J(sub I)-R Curve for ASTM A533B Steel,. Corporate ...
... the effect of different heat-treatment practices on ... S orientations of ASTM A533B steel were examined ... interfaces debond due to thermal stresses set ...
... funded research, testing and training programs; updated ... A-36, A516, A537; ASTM ALLOY STEEL GRADES A533-B, A542, A543; AND OTHER ...
... Abstract : The effects of long term thermal aging treatments on notched ... commercially produced PWR pressure vessel steels, A533B Class 1 ...
This report describes the crack opening displacement (COD) test results for the steels ASTM A533B and A508 C1.2 obtained in connection with a program initiated to gather and create information concerning the manufacturing variables, e.g. heat treatment, needed in the assessment of the structural integrity of ...
Tensile testing has been performed at three different strain rates (2,4times10 exp -2 , 2,4times10 exp -3 , 2,4times10 exp -4 s exp -1 ) in the temperature range 20-375degreeC on a quenched-and-tempered nuclear-reactor pressure-vessel steel, A533 B. The a...
This report presents results obtained during the first year of a research program to investigate important metallurgical parameters that control the reactions of hydrogen with carbides in steels. Preliminary work included a detailed literature review of th phenomenon of decarburization and methane bubble formation in steels and a ...
This report describes research progress for Fiscal Year 1979 in a continuing program to characterize material properties performance with respect to structural integrity of light water reactor pressure boundary components. Progress under fracture mechanics investigations includes the first J-R curves from irradiated ...
The dose dependence of true stress parameters has been investigated for nuclear structural materials: A533B pressure vessel steels, modified 9Cr 1Mo and 9Cr 2WVTa ferritic martensitic steels, 316 and 316LN stainless steels, and Zircaloy-4. After ...
NASA Astrophysics Data System (ADS)
This ENEA Data-Base regards mechanical properties, chemical composition and heat treatments of nuclear pressure vessel materials: type A533-B, A302-B, A508 steel plates and forgings, submerged arc welds and HAZ before and after nuclear irradiation. Irradi...
Unirradiated and irradiated (5.3 -- 5.7 x 10/sup 19/n/cm/sup 2/, E> 1.0 MeV) A533-B class 1 steel was fatigue cycled in air at 1 cpm and 75 and 550 deg F. Results, compared with data for 600 cpm, indicate that there is no effect of cyclic frequency in unirradiated material, . although in the irradiated ...
The effects of long term thermal ageing treatments on notched impact fracture properties has been studied in two commercially produced PWR pressure vessel steels, A533B Class 1 and A508 Class 3. Heat treatments of up to 10,000h duration at temperatures be...
... toughness with specimen thickness for A533-B at-750 ... A533B Class 1 Steel 407 559 207 0.3 0.12 ... 4340 Steel (3990C Temper) 1468 1538 207 0.3 ...
Four unirradiated A533B pressure vessel steels in the form of small three-point-bend (TPB) specimens were precracked for fracture toughness testing. Crack growth rates, obtained from eight specimens of each type of steel, were measured and Paris law const...
Three pressure vessel steels of type A508 class 3/A533B class 1, containing varying copper and phosphorus contents, have been examined by a Positron Annihilation technique before and after irradiation to doses of (approximately) 1 x 10 sup 23 n m sup -2 (...
Exploratory assessments were made of the Charpy-V notch ductility characteristics of heavy section A533-B and A533-C steel plate and submerged arc weldments following neutron irradiation at 550F. The experimental evaluations were performed largely with co...
The effects of thermal ageing of fatigue crack growth behavior have been evaluated in three experimental melts of ASTM A533B MnMoNi steel containing differing amounts of copper and phosphorus. Tests have been conducted under vacuum and in a high purity, l...
After exposure to low and intermediate fluence neutron irradiation, a variety of reactor pressure vessel (RPV) steels, including A533B-type surveillance specimens, Gundremmigen KRB-A ex-service plate, and test reactor irradiated materials, have been analyzed in the atom probe field-ion microscope (APFIM). With this ...
DOE Information Bridge
This investigation employed laboratory melts of pressure vessel steels (A 533-B or A 302-B base) to probe suspect interactions between copper impurities and manganese, molybdenum, chromium and nickel alloying as influencing elevated temperature, radiation sensitivity development. Radiation ...
A533B-1 are used in the construction of coal conversion vessels and were furnished .... heat treatment than to carbon content although more data is needed before any ... 1010 STEEL. 400 TORR. IA-N) b= 0.365 Cm. a = 0.239 Cm. ...
Mechanical properties of nine heats of manual arc welded A533B-1 steel are reported. The specific tests are: tensile, Charpy V-notch, and static compact and dynamic one-inch and four-inch fracture toughness results. (GHT)
Stress corrosion cracking (SCC) studies were conducted in two commonly used pressure vessel steels: A533 Grade B Class 1 (A533-B-1) plate and an equivalent A508 Class 2 (A508-2) forging. The purpose of these studies was to determine the response of the ma...
The results of a number of experiments dealing with fatigue crack propagation in irradiated reactor pressure-vessel steels are reviewed. The steels included ASTM alloys A302B, A533B, A508-2, and A543, as well as weldments in A543 steel. Fluences and irradiation conditions ...
Experience with ASTM A533-B steel and the HSST program are described; ASTM A543 is seen as the material for pressure vessel fabrication. Nuclear applications and problems of stainless steels are also discussed. Various other material selection topics are discussed: RTGR materials, core ...
... Accession Number : AD0180659. Title : Radiation Resistant Weld Metal for Fabricating A533-B Nuclear Reactor Vessels. Corporate Author : ...
... Accession Number : ADD117706. Title : Kinetics of Void Development in Fracturing A533B Tensile Bars,. Corporate Author : ...
The fission-track etching technique was used to determine the B microdistribution in an ASTM A533B steel weldment. B segregates on gamma grain boundaries in the heat-affected zone; the B content is 12 ppM in the deposit and l ppM in the base metal. The effect of the B segregation on the radiation ...
An important aspect of the Light Water Reactor-Pressure Vessel-Surveillance Dosimetry Improvement Program is the Hanford Engineering Development Laboratory effort to develop and test trend curve exposure parameter data. Progress in these trend curve-data correlation analysis activities at HEDL is described. The exposure parameters of primary interest are those associated with the production of ...
This paper is concerned with the recent study of determining fatigue damage on medium strength A533B nuclear reactor pressure vessel steel by magnetic nondestructive testing methods. Because of the nature of fatigue, which always begins with surface damage, it was found that the Barkhausen noise measurement, a ...
The principal objectives are: (a) to characterize the dynamic fracture toughness of three heats of nuclear pressure vessel steel, namely, 6-in. A302-B plate, 8-in. A533-B Class 1 plate, and 9-in. A508 Class 2 forging; and (b) to develop techniques for the interpretation and analysis of notched, three-point bend ...
A new methodology is proposed to correlate the upper shelf energy (USE) of full size and subsize Charpy specimens of a nuclear reactor pressure vessel plate material, ASTM type A 533 Grade B (A533B) having a low USE (USE 1 MeV) by 78 {degree}, 83{degree}, and 70{degree}C for full, half, and third size specimens, respectively. These ...
Steel plates and weld deposits exhibiting relatively low Charpy-V C sub v upper-shelf energy levels in the preirradiation condition are present in certain older reactor pressure vessels. Because the postirradiation notch ductility behavior of such materials is not well understood, a series of investigations has been undertaken for representative ...
Neutron irradiation is known to cause embrittlement of iron-based materials; in the nuclear industry, this effect can be detrimental for reactor pressure vessel steels. In this paper, we investigate the variations of the magnetic hysteretic behavior due to neutron irradiation, for four materials, i.e. nominally pure Fe, Fe-0.1 wt% Cu and Fe-0.3 wt%Cu model ...
The arc stud welding process was used to produce new, full size Charpy V-notch impact specimens from halves of Charpy specimens which had been previously tested. The apparatus was developed such that it could be used not only for unirradiated specimens, but also so that it could be adapted for in-cell use to produce new reconstituted specimens of irradiated material. The materials studied are of ...
The objective of this work was to investigate the relationship between the micromechanisms of ductile crack growth, the microstructural constituent phases present in nuclear pressure vessel steel, and the observed fracture behavior as determined by impact and fracture mechanics tests. Results from a microstructural and mechanical property comparison of an ...
The Heavy Section Steel Technology Program (HSST) at Oak Ridge National Laboratory (ORNL) is investigating the influence of flaw depth on the fracture toughness of reactor pressure vessel (RPV) steel. Recently, it has been shown that, in notched beam testing, shallow cracks tend to exhibit an elevated toughness as a result of a loss of ...
Post weld heat treatments of thick-section A533B steel for nuclear pressure vessels are discussed with reference to the ASME code. The discussion is in the form of a lecture and summarized by noting that the ASME code, in particular Section III, Division 1, imposes a post weld heat treatment requirement on pressure ...
The research program of the NRL Metallurgy Division, Reactor Materials Branch, involves a broad study of the effects of nuclear radiation upon materials. The report includes: (1) status and recent observations of AEC-CE-NRL cooperative program on improved (radiation resistant) A533-B steel plates and weldments; (2) ...
Metals that can sustain plastic deformation homogeneously throughout their bulk tend to be tough and malleable. Often, however, if a metal has been hardened it will no longer deform uniformly. Instead, the deformation occurs in narrow bands on a microscopic scale wherein stresses and strains become concentrated in localized zones. This strain localization degrades the mechanical properties of the ...
This paper addresses the mechanisms of cleavage fracture in the pressure-vessel steel A533B. Microstructures of single bainite microstructures exhibit a higher propensity for brittle cleavage fracture than do those of auto-tempered martensites. The K{sub 1c} values of mixed microstructures are determined by the ...
The 550 deg F irradiation response characteristics of several NiCrMo steel plates, forgings, and weldments were evaluated. Primary objectives were to explore variable radiation-embrittlement tendencies and to assess notch ductility performance relative to that of the MnMoNi steel (ASTM Type ...
Pre and postirradiation fatigue crack growth rates in A302-B, A533-B, and A543 steel plate and in two A543 welds (submerged arc and electroslag) were determined at 550$sup 0$F in air. The fracture mechanics approach was used to analyze the experimental data. Neutron irradiation at 585$sup 0$F to 2.5 x ...
This report describes progress in a continuing program to characterize material properties performance with respect to structural integrity of light water reactor pressure boundary components. Progress under fracture mechanics highlights J-R curve trends from low upper shelf A533-B weld deposits irradiated under the HSST program. ...
Specimens from 33 heats of three types of nuclear pressure vessel steel were heat treated to produce a simulated weld HAZ microstructure and tested to determine their resistance to stress relief cracking (SRC). The method employed a special jig in which notched specimens were loaded in 3-point bending to a fixed displacement and then heated to 610/sup 0/C for 6 h in a ...
Irradiation embrittlement in nuclear reactor pressure vessel steels results from the formation of a high number density of nanometer sized copper rich precipitates and sub-nanometer defect-solute clusters. We present positron annihilation spectroscopy (PAS) results to characterize the compositions and magnetic character of these defects in model ...
The operation of some early-generation light water reactors may be limited by the irradiation-induced embrittlement of their reactor vessels. Additional nondestructive methods of measuring the actual embrittlement are desirable to support limits placed on the operation of these vessels. Previous studies have indicated that the increase in microhardness with irradiation may correlate with shifts in ...
A model to describe the change in the inelastic and fracture properties of reactor pressure vessel steels due to neutron irradiation in the ductile region (i.e., irradiation embrittlement) is developed. First, constitutive equations for unirradiated elastic-viscoplastic-damaged materials are developed within the framework of the irreversible thermodynamics theory. To take into ...
Atom probe field-ion microscopy has been used to characterize the microstructure of a neutron-irradiated A533B pressure vessel steel weld. The atomic spatial resolution of this technique permits a complete structural and chemical description of the ultra-fine features that control the mechanical properties to be ...
The work described in this paper is part of a continuing program to produce well-characterized data for use in the development of models for the prediction of irradiation shift in pressurized water reactor steels. Results are presented for around 50 batches of Charpy specimens, irradiated either in the DIDO or PLUTO heavy water, or in the HERALD light water, research reactors, ...
A comparison between the BCL one-dimensional and two-dimensional dynamic fracture models was made using experimental crack propagation results from a transparant plastic as a basis for the comparison. Both models gave essentially the same results in good agreement with experiment with regard to the important features of the fracture events, e.g. length of crack jump, and the variation in the ...
Results of a program seeking (i) dynamic analyses of crack arrest in thermally stressed nuclear pressure vessels, (ii) standardization of a laboratory test method for measuring the crack arrest toughness, and (iii) a crack arrest toughness data base for unirradiated and irradiated nuclear steels and weldments are described. Dynamic finite difference analyses of fast fracture ...
Sixteen wide-plate crack-arrest tests have been completed, ten utilizing specimens fabricated from A533B class 1 material and six fabricated from a low-upper-shelf base material. Each test utilized a single-edge notched specimen that was subjected to a linear thermal gradient along the plane of crack propagation. Test results exhibit ...
Stress corrosion cracking (SCC) studies were conducted in two commonly used pressure vessel steels: A533 Grade B Class 1 (A533-B-1) plate and an equivalent A508 Class 2 (A508-2) forging. The purpose of these studies was to determine the response of the materials in simulated pressurized water reactor environment. ...
Previous work by the authors described a micromechanics fracture model to correct measured J sub c-values for the mechanistic effects of large-scale yielding. This new work extends the model to also include the influence of ductile crack extension prior to cleavage. Ductile crack extensions of 10-15 times the initial crack tip opening displacement at initiation are considered in plane-strain, ...
... ton A533-B demonstration melt; (3) examination of microstructures of Inconel 718, Incoloy 800, PH13-8Mo, Mo and Nb after irradiation in EBR-II; (4 ...
A study has been made of the effects of prior hydrogen attack damage on fatigue crack propagation behavior in commercial pressure vessel steels. Quenched and tempered Mn-Mo-Ni steel (ASTM A533B Class 2) and normalized and tempered 2.25Cr-1Mo steel (ASTM A387 Class 2 Grade ...
Experimental studies demonstrate a significant effect of specimen size, a/W ratio and prior ductile tearing on cleavage fracture toughness values (J{sub c}) measured in the ductile-to-brittle transition region of ferritic materials. In the lower-transition region, cleavage fracture often occurs under conditions of large-scale yielding but without prior ductile crack extension. The increased ...
Some recent studies of material response have identified an issue that crosses over and blurs the boundary between ASME Boiler and Pressure Vessel Code Section III Subsection NB and Subsection NH. For very long design lives, the effects of creep show up at lower and lower temperature as the design life increases. Although true for the temperature at which the allowable stress is governed by creep ...
Irradiation embrittlement in nuclear reactor pressure vessel steels results from the hardening by a high number density of nanometer scale features. In steels with more than ?0.10% Cu, the dominant features are often Cu-rich precipitates typically alloyed with Mn, Ni and Si. At low-Cu and low-to-intermediate Ni levels, so-called matrix hardening features ...
The precracked Charpy single-edge notched bend, SE(B), specimen (PCC) is the most likely specimen type to be used for determination of the reference temperature, T0, with reactor pressure vessel (RPV) surveillance specimens. Unfortunately, for many RPV steels, significant differences have been observed between the T0 temperature for the PCC specimen and that obtained from the ...
A508 Gr 4N has improved fracture toughness because of the addition of 3% nickel, compared to typical low alloy steels which have less than 1% nickel. However, there is an expectation in much of the recent literature, based mostly on low-alloy steels with nickel below 1%, that irradiation embrittlement will increase with increasing nickel (Ni) content. In ...
The objective of this work was to provide experimental heat transfer boundary condition and reactor pressure vessel (RPV) section thermal response data that can be used to benchmark computer codes that simulate thermal annealing of RPVS. This specific protect was designed to provide the Electric Power Research Institute (EPRI) with experimental data that could be used to support the development of ...
Fifteen wide-plate crack-arrest tests have been completed to date, ten utilizing specimens fabricated from A533B class 1 material (WP-1 and WP-CE series), and five fabricated from a low upper-shelf base material (WP-2 series). Each test utilized a single-...
... Abstract : To investigate the properties of carbon steel with a ferrite + cementite + martensite structure; we investigated unalloyed carbon steels ...
... Accession Number : ADD132623. Title : Investigation of the Hydrogen Embrittlement of Steels for Hydrogen Steel Cylinders and Pressure Vessels,. ...
An investigation of the plastic fracture process to improve tensile strength in high strength steels
NASA Technical Reports Server (NTRS)
... INVESTIGATION OF FRICTION AND WEAR OF STEELS, A HARD ALLOY, AND POLYMER MATERIALS AT LOW TEMPERATURES By: Ye.. ...
... Title : Ultrasonic NDT of Bridge Steel and Weathering Steel Bridge Investigation in ... weathering steel on the inspected twelve Idaho bridges is found ...
... method for evaluating the quality of hull plate steel on ... Descriptors : (*STEEL, NOTCH SENSITIVITY), (*SHIP PLATES, STEEL), SHIP HULLS ...
... STAINLESS STEELS, THE CONTROLLING FACTORS FOR TOUGHNESS OF HIGH CHROMIUM FERRITIC STEELS WERE INVESTIGATED, AND ...
... RUBBER COATINGS, COMPOSITE MATERIALS, STEEL, STAINLESS STEEL, BRONZE, BRASS, POLYVINYL CHLORIDE, HALOCARBON ...
... Abstract : THE CLIMAX MOLYBDENUM COMPANY HAS INVESTIGATED THE PROPERTIES OF FERRITIC STEELS WITH A LOW ...
... Accession Number : ADA950721. Title : Investigation of the Effect of Cerium as an Addition to Steel. Descriptive Note : Informal status rept.,. ...
... Title : Investigation of Stress Corrosion Cracking of Austenitic Steels in Acid Chloride Solutions at Low Temperatures. Descriptive ...
... Accession Number : ADD344725. Title : Investigating Pipeline Steel Inhomogeneity with Magnetic Barkhausen Noise and Magnetic Flux Leakage,. ...
... Accession Number : ADD115951. Title : INVESTIGATIONS ON CHROMIUM IN STAINLESS STEEL WELDING FUMES,. Corporate Author : ...
... Accession Number : AD0639619. Title : INVESTIGATION OF RESIDUAL STRESSES IN STEEL WELDMENTS. Descriptive Note : Final rept. ...
... Title : INVESTIGATION OF PERFORMANCE OF SEMIKILLED CARBON STEEL ABS CLASS B AND RIMMED STEEL ABS CLASS A UNDER ...
... Accession Number : AD0636304. Title : INVESTIGATION OF FRACTURED STEEL PLATES REMOVED FROM WELDED SHIPS. ...
... Accession Number : AD0636290. Title : INVESTIGATION OF FRACTURED STEEL PLATES REMOVED FROM WELDED SHIPS. ...
... Title : Investigation of Stress Corrosion Cracking in Mild Steel, Stainless Steel and Brass by Stress Relaxation Technique,. Corporate Author : ...
... L.,. INVESTIGATION OF WELDABILITY jm OF HOT-WORK TOOL STEELS C**4 ... INVESTIGATION OF WELDABILITY OF HOT-WORK TOOL STEELS ...
... Title : Investigation of the Relationship Between Carbon and Sulphur Segregation and the Drawability of High Carbon Steel Rod,. ...
... Accession Number : ADA950908. Title : Investigation of Significant Properties and Characteristics of Cold Worked Steel. ...
... Accession Number : ADA950907. Title : Investigation of Significant Properties and Characteristics of Cold Worked Steel. ...
... Title : INVESTIGATION OF THE PRECIPITATION OF VANADIUM CARBIDE IN AUSTENITIC STEEL,. Corporate Author : ...
... Title : INVESTIGATION OF THE FAILURE IN TENSION OF AN ALUMINUM ALLOY REINFORCED WITH STEEL WIRE,. Corporate Author : ...
... Title : INVESTIGATION OF SOLIDIFICATION OF HIGH STRENGTH STEEL CASTINGS UNDER SIMULATED PRODUCTION CONDITIONS. ...
... INVESTIGATION OF RESONANT BEAM AND ULTRASONIC METHODS FOR THE EVALUATION OF SINTERED POWDER STEEL COMPACTS. ...
... Title : INVESTIGATION OF NONDESTRUCTIVE TESTING TECHNIQUES FOR DETECTING CORROSION OF STEEL UNDER INSULATION. ...
... Title : INVESTIGATION OF CRACKING PROBLEM IN ELECTRON BEAM WELDING HIGH ALLOY STEEL,. Corporate Author : ...
... INVESTIGATING THE DISTRIBUTION AND ORIENTATION OF STAINLESS STEEL FIBRE-FILLED POLYPROPYLENE COMPOSITES WITH EDDY ...
... Title : EXPERIMENTAL INVESTIGATION OF SOME ELECTROMAGNETIC CHARACTERISTICS OF THE CORROSION PRODUCTS OF STEEL. ...
... Title : An Investigation of the Relaxation of Static Stresses in Chromium- Nickel Steel Specimens in Cyclic Loading. Descriptive ...
... Title : AN INVESTIGATION ON THERMAL AND MECHANICAL STABILITY OF MOLD MATERIALS FOR STEEL CASTINGS. ...
... Accession Number : AD0175393. Title : AN INVESTIGATION OF VIBRATIONAL STRESS RELIEF IN STEEL. Corporate Author : ...
... Title : AN INVESTIGATION OF THE MECHANICAL PROPERTIES AND MICROSTRUCTURES OF 18NI(250) MARAGING STEEL WELDMENTS. ...
... Title : AN INVESTIGATION OF THE EFFECTS OF CERTAIN LUBRICANTS IN REDUCING FRETTING CORROSION OF CERTAIN STEELS. ...
... Title : A PRELIMINARY INVESTIGATION OF HART'S MODEL IN HYDROGEN EMBRITTLEMENT IN MARAGING STEELS,. Corporate Author : ...
... Title : A Fractographic Investigation of Explosively Fragmented Silicon-Manganese Steels by Scanning Electron Microscopy. ...
The capability to conduct dynamic tensile testing of sheet steels was established and the influence of strain rate on strengthening mechanisms in sheet steels was investigated in this work. Several different automotive sheet steels were studied, including...
... These * mi crostructural changes were similar to those observed in both 3140 and plain carbon steels by other investigators. ...
... These microstructural changes were similar to those observed in both 3140 and plain carbon steels by other investigators. ...
... sodium-steel interface are derived. Under loop conditions only chromite can be formed. Stainless steel samples were investigated ...
... This paper lists some of the data of investigations dealing with the effect of organisms of mncrofoulinp on the corrosion of steel in the Black Sea. ...
Investigation determined whether irradiated pressure-vessel steels 4340 and 212-B are susceptible to
... Pagination or Media Count : 52. ... steels were produced with compositional variations in the content of titanium, nitorgen, vanadium, boron, calcium ...
... bars to the rotary bending test. At the same time, the efficiency of anodic protection was examined. With all four steels, the ...
... EP-33 is investigated. The hydrogen content in the steel changes with pressure according to Sievert's law. It is suggested ...
... The 20%-nickel maraging steel and the "high-titanium" 18%-nickel ... OF 18%-NICKEL MARAGING STEEL WITH "HIGH TITANIUM" ...
... Abstract : There is a general consensus in industry that the corrosion of steel piles driven into undisturbed soils is insignificant and as a result ...
This research on steel diaphragms was undertaken at the Langley Memorial Aeronautical Laboratory, as
... the Invest'gation of Stress Corrosion Cracking of High Strength Steels for the ... in three alloys: 18% nickel maraging steel, a low-alloy martensitic steel ...
... Five metallic materials of construction are included in the program: 304 stainless steel; A-286 (aged) steel, 17 4-PH (aged) stainless steel; Inconel ...
... Five metallic materials of construction are included in the program: 304 stainless steel, A-286 (aged) steel, 17-4 (aged) stainless steel, Inconel 718 ...
... Title : Laser Welding of Ship Steel. Descriptive Note : Final rept. ... Abstract : An expertimental laser welding investigation was conducted on ship steel. ...
... Abstract : In producing various welded joints of the type pearlitic steel-corrosion resistant steel or pearliltic steel-anticorrosion melt-on, the ...
The article investigates the effect of the parameters of heat treatment on the grain structure of maraging steels. A regime of heat treatment is suggested that ensures sufficiently high impact toughness of these steels.
The present research program was designed to investigate the influence of crystallographic texture on the mechanical strength of steel plates subjected to various loading conditions including ballistic impact. The steels of interest are 5% Ni martenistic ...
... Title : Corrosion of Electroless Nickel-Coated Steel. ... Abstract : The corrosion behavior of electroless nickel-coated steel has been investigated. ...
... Abstract : This communication gives the results of an investigation of the corrosion resistance of carbon steel St3, chromium steels (08Kh13, 2Kh13 ...
... properties of D6-AC tool steel and H-11 HSLA steel which had been aus- ... As the two sheets burn, they fracture the glass. ... The steel anvil ...
... HEAT TREATMENT INVESTIGATION OF 4330 VANADIUM-MODIFIED STEEL ... HEAT IREATMENT INVESTIGATION OF 4330 VANADIUM- ...
This investigation was conducted in order to assess the impact of the steel safeguard measures on differing segments of the U.S. manufacturing sector and to focus on steel products subject to the President's safeguard measures. This report (Volume III in ...
... Title : XPS Investigation on AISI 420 Stainless Steel Corrosion in Oil and Gas Well Environments,. Descriptive Note : Journal Article,. ...
... Accession Number : ADD127118. Title : XPS Investigation of Stainless Steel Surfaces Heated in Aqueous Media,. Corporate Author : ...
... Accession Number : ADD139055. Title : Structural and Physicomechanical Investigations of Steel Wire 12Kh18N10T After Electroplastic Drawing,. ...
... Title : Resume of Investigations on Steels for High-Temperature, High-Pressure Applications 1963-1965. Descriptive Note : Resume. ...
... Title : Microscopic Investigation of Interface Corrosion of Steel-Aluminum Explosively Bonded Material Exposed to Periodic Sea Water Spray. ...
... Accession Number : ADA951090. Title : Investigation of Properties of Nickel-Silicon Steels Made by the International Nickel Company. ...
... Title : Investigation of Precipitation Behaviors of Maraging Steels of Fe-18%Ni-Co-Mo-Ti Series by Measurement of Electrical Resistivity,. ...
Zinc embrittlement in the welding and heat treatment of stainless steel, high tensile steel, and mild steel was investigated. On welding galvanized steels or steels coated with zinc rich primer, the zinc melts and weld cracking may occur. Susceptability t...
Simulation of Dimensional Changes in Steel Casting Shouzhu (Hans) Ou and Christoph Beckermann Pattern allowances in casting of steel are predicted using the casting simulation software MAGMASOFT to predict dimensional changes occurring during solidification and cooling of a steel casting
Experiments designed to investigate the effects of increasing the size of steel cylinders on their fragmentation behavior were carried out using medium-carbon steel (CS1050) in both the annealed and the hardened and tempered conditions. Another steel (AIS...
A potential method of quantitative analysis of high-strength steels by x-ray fluorescence was investigated. A technique for measuring composition is described in the report. Tool steel, stainless steel, and high temperature alloys of widely varying compos...
Contents: Present state of the art in welding aluminum and its alloys to steel; Study of the interaction of aluminum with iron and steel during heating; Investigating the heat propagation process in an aluminum/steel joint; The formation of intermetallic ...
The paper investigates the values of coefficient of friction in cold rolling steel strip for a number of lubricants prepared by the Ploiesti Crude Oil Processing Technological Design and Research Institute for use by the Galati Steel Mill Combine's steel ...
The effect of metallic coatings and zinc rich primers on the performance of finishing systems for automotive steel was investigated. Galvanized and aluminized type steels and zinc rich primer steels were coated with specification finishing systems and exp...
The effects of phosphorus and nickel on the cold shortness of 0.50% carbon steel were studied. The impact ductility of carbon, phosphorus carbon, and nickel alloyed steel at various temperatures and the microstructure of nickel alloyed steel were investigated. (R.V.J.)
The fundamentals of localized corrosion are briefly discussed, and the literature concerning corrosion of carbon steel in aqueous environments, in particular the stress-corrosion cracking of carbon steels, is reviewed. The behavior of high strength steels...
The corrosion of carbon steel in water at 250C with small amounts of oxygen has been studied in a boiling, out-of-pile loop made of carbon steel. In addition to the steel specimens activated iron was used in order to faciliate the investigation of corrosi...
A study was conducted on the corrosion behavior of an AerMet 100 steel and a 300M steel. This study included investigations of stress corrosion cracking (SCC), immersion corrosion, salt spray corrosion, and humidity corrosion of both steels. For the SCC i...
In 1987, the Steel Construction Institute (SCI) commenced a study to investigate 'Generic Steel Designs for Tidal Power Barrages'. The purpose of the study was to perform generic designs for steel caissons, to allow evaluation of their potential over the ...
