irradiation tests of several steels

irradiation tests of several steels
JIS G3101 SS400

Grain Boundary Composition and Irradiation-Assisted Stress

Abstract.Scanning transmission electron microscopy (STEM) analyses,in-reactor swelling mandrel tests,and laboratory constant extension rate tensile (CERT) tests were conducted on nine custom type 348 (UNS S34800) stainless steel (SS) alloys in an attempt to correlate grain boundary composition with irradiation-assisted stress corrosion cracking (IASCC) resistance.sp.info Microstructure Characterization of Oxide Dispersion Cr inclusions.The cause was determined to be the combined effects of the heterogeneity of the matrix Cr composition (presence of metallic Cr inclusions) and the high-temperature environment in the BOR-60 irradiation test.3,4) In this study,the high-temperature thermal aging tests of pre-mix process 9Cr-ODS steels were carried out tosp.info (PDF) Post-Irradiation Tensile Behavior and Residual Post-Irradiation Tensile Behavior and Residual Activity of Several Ferritic/Martensitic and Austenitic Steels Irradiated in Osiris Reactor at 325°C up to 9 dpasp.info Comparison of Irradiation Creep and Swelling of an Comparative irradiation of identically constructed creep tubes in the Fast Flux Test Facility (FFTF) and the Prototypic Fast Reactor (PFR) shows that differences in irradiation conditions arising from both reactor operation and the design of the irradiation vehicle can have a significant impact on the void swelling and irradiation creep of austenitic stainless steels.

The effects of irradiation,annealing and reirradiation on

Request PDF The effects of irradiation,annealing and reirradiation on RPV steels An atom probe tomography microstructural characterization has been performed on an A533B pressure vessel steelsp.info Evaluation of Irradiation Embrittlement of A508 Gr 4N and Jun 17,2002·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.sp.info A SANS investigation of the irradiation-enhanced α-α Feb 01,2003·In the case of the low Cr content F82H steel irradiated 2.9 dpa at 325 °C,where α ' phase does not form,a small irradiation-induced SANS intensity is detected,which is probably due to point defect clusters.The α ' precipitates contribute significantly to the irradiation-induced hardening of 9-12 wt% Cr content steels.sp.info Evaluation of Irradiation Embrittlement of A508 Gr 4N and This trend also occurs for low copper A533B and A302B plate material.The irradiation temperature dependence of more embrittlement in A508 Gr 4N is nearly the same as other low copper low-alloy steels tested over a wide range of temperatures.

Post-irradiation annealing behavior of microstructure and ...

In this study, the microstructural changes caused by neutron irradiation have been characterized in A508 Grade (Gr) 4N-type steels (similar to 3.5% Ni) using a variety of state-of-the-art ...sp.info Microstructural Aspects of Irradiation Damage in A508 Gr ...In this study, the microstructural changes caused by neutron irradiation have been characterized in A508 Grade (Gr) 4N-type steels (∼3.5% Ni) using a variety of state-of-the-art analytical techniques including 3D-Atom Probe Field-Ion Microscopy and Small Angle Neutron Scattering, along with post-irradiation annealing studies combining Positron Annihilation Lineshape Analysis and hardness measurements.sp.info Low Temperature Irradiation Embrittlement of Reactor @article{osti_1212342,title = {Low Temperature Irradiation Embrittlement of Reactor Pressure Vessel Steels},author = {Wang,Jy-An John},abstractNote = {The embrittlement trend curve development project for HFIR reactor pressure vessel (RPV) steels was carried out with three major tasks.Which are (1) data collection to match that used in HFIR steel embrittlement trend published in 1994sp.info Surface Modification by Zr+ Ion Beam Irradiation of Cyclic tension and alternating bending tests of 12Cr1MoV and 30CrMnSiNi2 steels specimens in as–supplied state and after surface irradiation by Zr+ ion beam have been carried out.Distinctions in formation of strain induced relief,as well as cracking pattern of modified surface layer are illustrated by methods of optical microscopy and interferential profilometry.

Irradiation damage behavior of low alloy steel wrought and

A study was undertaken to evaluate the irradiation damage response of several different types of low alloy steel vintage type ASTM A302 Grade B (A302B) plates and welds containing different Ni and Cu concentrations,3.5% Ni steels similar to ASTM A508 Class 4,welds containing about 1% Ni (similar to type 105S),and 3.5% Ni steels with ``superclean`` composition.sp.info Effect of Annealing on Microstructures and Hardening of occurred and irradiation hardening completely disappeared in V-3Fe-4Ti-0.1Si.No signif icant recovery of irradiation hardening could be observed in the irradiated specimens after post-irradiation annealing at 500 °C for 2 h [ 12].The research of irradiation damage of recovery by post-irradiation annealing of EUROFER base steels showed thatsp.info Ferritic/Martensitic Steel - an overview ScienceDirect Effect of irradiation temperature Fig.15(a) shows the irradiation temperature dependence of irradiation embrittlement in various RAFM steels and conventional ferritic steels.171 The shift in DBTT (ΔDBTT) is smaller when increasing the irradiation temperature,and reach almost zero at around 400°C.The irradiation hardening is responsible for the irradiation embrittlement up to thesp.info Microstructural Aspects of Irradiation Damage in A508 Gr A study was undertaken to evaluate the irradiation damage response of several different types of low alloy steel vintage type ASTM A302 Grade B (A302B) plates and welds containing different Ni and Cu concentrations,3.5% Ni steels similar to ASTM A508 Class 4,welds containing about 1% Ni (similar to type 105S),and 3.5% Ni steels with

Microstructural evolution and hardening effect of

Sep 15,2020·The 12Cr2W2Mn ferritic/martensitic(F/M) steel was irradiated by 6 MeV Au ions at room temperature (RT) and 400 °C to the peak irradiation doses of 25 dpa and 54 dpa.XRD,nanoindentation and TEM tests were carried out to investigate the microstructural evolution and hardening effect of 12Cr2W2Mn F/M steels.sp.info Irradiation Effects on Ferritic / Martensitic Steels The irradiation was performed in the MISTRAL (Multipurpose Irradiation System for Testing of Reactor Alloys) irradiation rig of the BR2 reactor at 200°C up to a dose of 4.5dpa,in flowing water,and without tailoring spectrum.In Table 3 the results obtained from each type of test for the investigated materials are given.sp.info Cited by 1Publish Year 1992Author G.L.Hash,J.R.Schwank,M.R.Shaneyfelt,K.L.Hughes,M.P.Connors,J.W.Swonger,N.W.van Vonno,RHigh Level Gamma and Neutron Irradiation of Silica Optical In the final objective of elaborating an optical sensor of dimensional change in a nuclear testing reactor,we present extreme high level irradiation tests,up to 1.3 1020 nfastsp.info Author M.G.Burke,R.J.Stofanak,J.M.Hyde,C.A.English,W.L.ServerPublish Year 2002Microstructural Aspects of Irradiation Damage in A508 Gr In this study,the microstructural changes caused by neutron irradiation have been characterized in A508 Grade (Gr) 4N-type steels (∼3.5% Ni) using a variety of state-of-the-art analytical techniques including 3D-Atom Probe Field-Ion Microscopy and Small Angle Neutron Scattering,along with post-irradiation annealing studies combining Positron Annihilation Lineshape Analysis and hardness measurements.

Tensile behavior of dual-phase titanium alloys under

Similar mechanical tests weremade on an α-like Ti-4Al-2V [15] in comparison with Ti-6Al-4V [16],for neutron irradiation up to about 0.4dpa.Ti-4Al-2V also retained strain hardening capability and uniform elonga tion did not drop below 2.5%.oAt a higher temperature (550 C),very high irradiation data with neutron up to 37 dpa issp.info (PDF) Post-Irradiation Tensile Behavior and Residual ...Post-Irradiation Tensile Behavior and Residual Activity of Several Ferritic/Martensitic and Austenitic Steels Irradiated in Osiris Reactor at 325°C up to 9 dpasp.info charpy impact toughness Topics by Science.govFracture toughness and Charpy impact properties of several RAFMS before and after irradiation in HFIR.NASA Astrophysics Data System (ADS) Sokolov,M.A.; Tanigawa,H.; Odette,G.R.; Shiba,K.; Klueh,R.L.2007-08-01.As part of the development of candidate reduced-activation ferritic steels for fusion applications,several steels,namely F82H,9Cr-2WVTa steels and F82H weld metal,are beingsp.info Microstructural Aspects of Irradiation Damage in A508 Gr @article{osti_835565,title = {Microstructural Aspects of Irradiation Damage in A508 Gr 4N Forging Steel Composition and Flux Effects},author = {Burke,M G and Stofanak,R J and Hyde,J M and English,C A and Server,W L},abstractNote = {Neutron irradiation can promote significant changes in the microstructure and associated mechanical properties of low alloy steels.

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