... Title : Evaluation of Commercial Production A533-B Steel Plates and Weld Deposits with Extra-Low Copper Content for ... Report Date : OCT 1977. ...
DTIC Science & Technology
... improved steel production (current practice). ... VESSELS, NUCLEAR REACTORS, RADIATION ... METALLOGRAPHY FISSION REACTOR MATERIALS. ...
... Title : Effect of Thermal Ageing on the ... of PWR Pressure Vessel Steels and Weldments,. ... The materials investigated include A533B plate and A508 ...
... 3) special A533-B steel heat for ... PRESSURE VESSELS, THERMAL STABILITY, MARAGING ... SENSITIVITY, EMBRITTLEMENT, STEEL, RESPONSE ...
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...
National Technical Information Service (NTIS)
... 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. ...
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...
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...
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...
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 ...
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 ...
Energy Citations Database
... Title : Indentation Loading Studies of Acoustic Emission from Temper and Hydrogen Embrittled A533B Steel,. Corporate Author : ...
... 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. ...
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, ...
DOE Information Bridge
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....
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 ...
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 ...
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 ...
NASA Astrophysics Data System (ADS)
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
... 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...
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 ...
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 ...
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, ...
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. ...
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 ...
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 ...
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 ...
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 ...
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-...
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 (...
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...
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)
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 ...
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 ...
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 A508 Class 3 ...
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 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 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 ...
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 ...
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 ...
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 ...
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 ...
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 suitable experimental ...
Eleven wide-plate crack-arrest tests have been completed to date, seven utilizing specimens fabricated from A533B class 1 material (WP-1 series), and four fabricated from a low upper-shelf base material (WP-2 series). With the exception of one test in the WP-1 series and two tests in the WP-2 series which utilized ...
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. ...
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 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 irradiation to significant ...
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-edge notched specimen that was subjected to a linear thermal ...
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 ...
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 A533-B weld ...
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 ...
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 ...
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 ...
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 ...
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, ...
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 sensitivity is judged on ...
... 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 ...
... method for evaluating the quality of hull plate steel on ... Descriptors : (*STEEL, NOTCH SENSITIVITY), (*SHIP PLATES, STEEL), SHIP HULLS ...
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 alloys, and a ...
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 ...
Thermal fatigue tests were performed on the following materials: gun steel; 4340 steel; chromium plated gun steel; gun steel plated with a composite plate of chromium over alumina dispersion hardened cobalt; 4340 steel ...
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 constraint at the ...
