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Sunday, May 17, 2020 | History

2 edition of Effect of neutron irradiation on fatigue crack propagation in Type 316 stainless steel at 649C̊ found in the catalog.

Effect of neutron irradiation on fatigue crack propagation in Type 316 stainless steel at 649C̊

D. J. Michel

Effect of neutron irradiation on fatigue crack propagation in Type 316 stainless steel at 649C̊

by D. J. Michel

  • 204 Want to read
  • 21 Currently reading

Published by Naval Research Laboratory in Washington, D.C .
Written in English

    Subjects:
  • Neutron irradiation.,
  • Steel, Stainless -- Fatigue.

  • Edition Notes

    StatementD.J. Michel and H.H. Smith.
    SeriesNRL memorandum report -- 3936.
    ContributionsSmith, H. H., Naval Research Laboratory (U.S.). Thermostructural Materials Branch.
    The Physical Object
    Paginationiii, 12 p. :
    Number of Pages12
    ID Numbers
    Open LibraryOL17824757M

    Rotating bending fatigue tests of Ti added extra low carbon steel with no strain ageing were carried out. The results obtained are as follows; 1) At the stress of the fatigue limit, fatigue cracks did not propagate when N (number of repetitions) reaches 10 was confirmed to the extent of N=8×10 7 in this experiment. That the strain ageing plays an important role in fatigue is well . steel [] and to corrosion fatigue [], with some of them focused on th e role of the microstructure with respect to the degree of cold drawing on the fatigue life. But few papers are dedicated to fatigue crack propagation and fatigue threshold [], most studies being conducted on wires having a di ameter of about 5 to 10 mm [].

    Abstract The effects of fast reactor irradiation at temperatures of ~ ° C and ~ ° C on the fracture toughness and associated strength changes, induced in solution treated Type stainless steel have been characterised using instrumented impact test procedures. Fig. 2. This type of the specimen is referred to as the epoxy-bonded copper film. Moreover, the reference specim en of base itself was also prepared for the purpose of com paring with epoxy-bonded copper film in electric resistance change du ring fatigue crack propagation. Fatigue testing. Fatigue testing was performed using a servo-hydraulic.

    Hardening behavior induced by neutron irradiation at various temperatures ( to K) is characterized in terms of the variations in athermal stress and activation energy for plasticity controlled by precipitation or solid solution, and kink-pair formation with the content and type of impurities. In P-doped alloys, neutron irradiation below. Fatigue-crack growth tests were conducted at temperatures of 75 F (24 C), F ( C), F ( C) and F ( C); the results for base metal specimens are shown in Figs. , and for weldment specimens in Figs. The results for specimens (material 'a'Heavy Section Steel Technology Program Plate No.


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Effect of neutron irradiation on fatigue crack propagation in Type 316 stainless steel at 649C̊ by D. J. Michel Download PDF EPUB FB2

Get this from a library. Effect of neutron irradiation on fatigue crack propagation in Type stainless steel at C̊. [D J Michel; H H Smith; Naval Research Laboratory (U.S.). Thermostructural Materials Branch.]. The fast cycling fatigue crack propagation characteristics of type steel and weld metal have been investigated at °C after irradiation to − × 10 20 n/cm 2 (E > 1 MeV) and × 10 21 n/cm 2 (E > 1 MeV)at the same temperature.

With mill-annealed type steel, modest decreases in the rates of crack propagation were observed for both dose levels considered, Cited by: 3. Journal of Nuclear Materials () North-Holland Publishing Company CRACK PROPAGATION CHARACTERISTICS IN NEUTRON IRRADIATED TYPE STAINLESS STEEL MICROSPECIMENS R.D.

GERKE and W.A. JESSER Department of Materials Science, Thornlon Halt, University of Virginia, Charlottescille, VA l, USA In order to better relate the Cited by: 3. Specimens of Types and and Sandvik 12R72 stainless steels were irradiated in Experimental Breeder Reactor-II (EBR-II) to a fluence of × 10 22 neutrons (n)/cm 2 (E > MeV) at and °C.

Three different specimen configurations were used: small sheet tension specimens, small right circular cylinders for immersion-density measurements, and thin foils. Abstract. It has been revealed that the neutron irradiation of ultrafine-grained (UFG) 08Kh18N10T steel after severe plastic deformation (SPD) does not lead to the appearance of defects of radiation origin up to a fluence of 2 × 10 20 n/cm 2 (~ dpa) and that the strength properties of the material are retained after irradiation.

At the same time, this irradiation Cited by: 4. Fatigue crack growth rates in an irradiated stainless steel were obtained at a load cycling frequency of Hz with hold times of 1, 10, and 50 s and at 60 Hz at test temperatures ranging from to K.

Specimens were prepared from wrapper tube material, which was irradiated to a fluence level of 4 × 10 26 n/m 2 (E ⩾ MeV) at K in a fast breeder reactor (JOYO).Author: S Jitsukawa, A Umino, I Takahashi, S Iida, M Adachi, K Suzuki, A Hishinuma.

A systematic review has been established by Murakami et al. [19] regarding the H effect on the fatigue crack propagation in steels. Hydrogen-assisted fatigue crack growth in ferritic steels. The high-cycle fatigue behavior of type low-carbon, nitrogen-added (LN) stainless steel (SS), the prime-candidate target-container material for the spallation neutron source (SNS), was.

The neutron irradiation effects on the fracture toughness of the austenitic chromium-nickel 18CrNi-Ti steel and the weld metal irradiated in a BOR reactor are studied. The fracture toughness of the steel is found as a function of the orientation of a fracture surface with respect to the rolling by: 2.

Effect of neutron radiation exposure was investigated in various ferritic steels with the main emphasis being the effects of thermal neutrons on radiation hardening. Pure iron of varied grain sizes was also used for characterizing the grain size effects on the source hardening before and after neutron irradiation.

While many steels are considered in the overall study, the Cited by: 4. Effects of temperature and frequency on fatigue crack growth in 18% Cr ferritic stainless steel Kamel Makhlouf and J.W.

Jones The fatigue crack growth behaviour of a ferritic stainless steel has been investigated as a function of test temperature, thermal exposure and frequency at intermediate growth rates.

Fatigue crack propagation, metastable austenitic stainless steel, crack closure INTRODUCTION AISI LN stainless steel is one of the materials that fulfill the exigencies of the automotive sector for the development of components that can be used to lead to weight reductions [1].

Christine Sarazin-Baudoux et al. / Procedia Engineering () – (a) (b) Fig (a) Fatigue crack propagation in high vacuum da/dN vs 'K and 'K eff; (b) comparison of intrinsic fatigue crack propagation in high vacuum for the studied steel and three high strength steels [9].

In Fig. 1b are plotted the effective crac propagation data in a da/dN vs k 'K. The fatigue crack propagation behavior of type A steel will be examined as a function of specimen thickness, mean stress at both low and high crack growth rates, specimen orientation with respect to the rolling direction, and in the presence of weldments.

In the latter case, fatigue crack propagation studies will be performedAuthor: R. Hertzberg, H. Nordberg. Martensitic high carbon high strength SAE bearing steel is one of the main alloys used for rolling contact applications when high wear and fatigue resistance are required.

Refining the microstructure of steel improves its mechanical properties (e.g. toughness). In this work SAE specimens were exposed to repeated induction heating process and rotation bending Cited by: Irradiation-assisted stress corrosion cracking (IASCC) is a significant materials issue for the light water reactor (LWR) industry and may also pose a problem for fusion power reactors that will use water as coolant.

A new metallurgical process is proposed that involves the radiation-induced release into solution of minor impurity elements not usually thought to participate in IASCC.

Cited by: 5. This research has involved studies of fatigue crack initiation as well as fatigue crack propagation. Principal findings have been that subsurface fatigue cracks can be initiated in forgings of this titanium alloy when the alpha-phase size is of the order of 10 micron, a size which can be present in large forgings.

stainless steel up to necking point. A very good agreement is found between newly calibrated tensile curves and the measurements. 1 INTRODUCTION Severe irradiation conditions in nuclear reactors may limit the operational life of internal struc-tural components supporting the reactor core. Neutron irradiation of austenitic stainless steels that.

Crack propagation experiments under constant stress intensity conditions were performed on SEN specimen of a high-alloyed steel. The experiments were accompanied by thermo elastic stimulated lock-in thermography investigations.

The experiments showed that the crack propagation rate decreases with increasing crack length. Concurrent an increase in the Cited by: 4. DETECTION OF FATIGUE CRACK PROPAGATION IN STEEL USING MAGNETIC MEASUREMENTS Y. Bi and D. Jiles Center for Nondestructive Evaluation Iowa State University Ames, IA 11 INTRODUCTION For structural components which are exposed to cyclic stresses, fatigue damage could lead to a catastrophic failure.

The effects of stress ratio and frequency on the fatigue crack propagation of glass phenolic composite have been dis­ cussed in the present investigation. The fatigue crack growth rates at three stress ratios ofand have been studied with the first set of specimens whereas the effect of frequency has been studied with the second.EFFECT OF BORON CONCENTRATION ON FATIGUE CRACK PROPAGATION RESISTANCE AND LOW CYCLE FATIGUE PROPERTIES OF INCONEL L.

Xiao1, D.L. Chen2 and M.C. Chaturvedi1 1Department of Mechanical and Industrial Engineering, University of Manitoba, Winnipeg, Manitoba R3T 5V6, Canada.for fatigue design of cold-formed steel sections. 1. tion of the axial fatigue behaviour of cold-formed steel members.

However, a large body on the type of steel material, low temperatures can be beneficial or detrimental or have a little influence on the total fatigue life of a component.

: Dimos Polyzois, Glenn Morris, S. K Hassan.