Equation of low-cycle fatigue of irradiated steel 0Kh16N15M3B

Skripnik, Yu. D.; Kosov, B. D.

doi:10.1007/bf00767042

Cited by 2 publications

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“…The standard method [13] does in principle include creep and neutron irradiation but it is very conservative and disregards the influence of strain rate in a loading cycle on the fatigue resistance. The method put forward in [6,10,11] allows for the influence of irradiation on the fatigue fracture resistance but gives no consideration to creep in a loading cycle. The method [6,7] takes into account neutron irradiation and creep only for the case where a unilateral creep strain accumulation is the prevailing damage mechanism.…”

Section: Discussionmentioning

confidence: 99%

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A method for predicting fracture resistance of material in cyclic loading under viscoelastoplastic deformation and neutron irradiation conditions

et al. 2008

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We analyze the available methods for prediction of fatigue fracture resistance, which allow for material creep in a deformation cycle and neutron irradiation. Benefits and drawbacks of the available methods are discussed. We present a new method for the fatigue fracture strength prediction, which suffers no disadvantages inherent to the well-known methods. The proposed method has been verified on austenitic steels tested at elevated temperatures.Keywords: fatigue fracture resistance, creep, neutron flux level.Introduction. Various parts of a fast neutron reactor plant operate in a wide temperature range -from 220 to 580°C. Moreover, some of them are subjected to intensive neutron irradiation. During the reactor transient modes, such as reactor going-up, shutdown cooling, fast emergency protection conditions, the temperature distribution in structural elements is highly nonuniform, resulting in thermal stresses and strains. The transient processes, when repeated many times, may lead to fatigue damage. Since the structural elements operate at temperatures above the temperature threshold of creep, damage should be considered as a case of interplay between fatigue and creep. The problem becomes even more complicated as this process is accompanied by an intensive neutron irradiation of the structural elements, which contributes to a considerable deterioration of ductility and creep rupture strength of material. The static strength and ductility characteristics of a material correlate with its resistance to fatigue fracture; therefore, neutron irradiation has a significant effect on the cyclic strength of the material.The objective of the present work has been to review the currently available methods and to further develop them to enable prediction of fracture resistance in cyclic loading under viscoelastoplastic deformation and neutron irradiation conditions. 1. Current Status. Let us discuss the currently available methods for predicting fatigue damage in a material under creep and neutron irradiation conditions.In [1][2][3][4], the researchers used a so called strain range partitioning method which essentially consists in dividing the damage into components induced by the time-dependent and time-independent strains. Generally, alternating inelastic deformation is split into the four components: a) plastic tensile strain followed by plastic compression strain Δε pp ;

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Section: Discussionmentioning

confidence: 99%

“…if if (10) Thus, Eq. (8) in combination with (9), (10), and (7) makes it possible to predict fatigue fracture resistance including the creep effects and strain rate in cyclic loading under irradiation conditions.…”

Section: General Principles Of Plotting Fatigue Curvesmentioning

confidence: 94%

A method for predicting fracture resistance of material in cyclic loading under viscoelastoplastic deformation and neutron irradiation conditions

et al. 2008

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“…Using these coordinates, as shown in [13], experimental points for no-hold-time tests are reduced, irrespective of fluence, to a single straight line both for non-irradiated and irradiated materials: Experimental data reproduced in the above specified coordinates are given in Fig. 8.…”

Section: Fatigue Lifementioning

confidence: 99%

“…Pre-loading fluence Fo and loading fluence FN may be adopted as irradiation parameters at constant intensity of the neutron flux. When the no-hold-time life of irradiated steel was estimated in [13], no account was taken of the difference between the parameters Fo and F, . It was justified by the fact that maximum duration of an experiment under trianglecycle reversed straining made up several hours, and therefore the value of fluence accumulated in the course of loading was negligible.…”

Section: (8)mentioning

confidence: 99%

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IN‐REACTOR LOW‐CYCLE FATIGUE OF TYPE 0Kh16N15M3B STAINLESS STEEL

Kiselevsky¹,

Kharitonov²

1984

Fatigue Fract Eng Mat Struct

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An investigation has been carried out on austenitic stainless steel OKh16N15M3B under normal conditions and also to neutron irradiation of 6.8 x 10I6 nm-2 s-' ( E 0. I MeV) intensity. Thin-walled torsion cylindrical specimens were tested in straincontrolled fully reversed loading mode at 923 K. Various ranges of strain, pre-loading fluences and half-cycle hold times (1, 5 and 30min) were applied. Neutron irradiation was found to result in hardening of the steel, stimulating cyclic stress relaxation and a reduction in cyclic life. When acting together, neutron irradiation and static loads cause a more significant reduction in the number of cycles to failure than if summed up as independent factors. Application of a kinetic failure criterion based on a damage parameter enables an estimation to be made of the limiting state of the steel under high-temperature cyclic loading with hold periods. NOMENCLATUREFr = failure fluence Fa = pre-loading fluence FN = F1 -Fa = loading fluence (fluence accumulated under loading) N / = number of cycles to failure n = cycle number T = temperature t = time t , = cycle period to = cycle period in no-hold-time tests t H = hold time td = t,/tO = dimensionless cycle period v = loading frequency y = shear strain y, = creep strain y p = plastic strain y , = total strain Ay = strain range Af = corrected strain range cr,, = yield stress cru = ultimate strength T = shear stress T,, = maximum stress in a cycle r^ = stress measured from the point of unloading AT = stress range AT" = stress decrease during hold time 6 =tensile elongation to fracture o = damage o, = static damage w f = fatigue damage I// = reduction of area; in tension A T~/ T~ = the degree of stress relaxation A,

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Equation of low-cycle fatigue of irradiated steel 0Kh16N15M3B

Cited by 2 publications

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A method for predicting fracture resistance of material in cyclic loading under viscoelastoplastic deformation and neutron irradiation conditions

A method for predicting fracture resistance of material in cyclic loading under viscoelastoplastic deformation and neutron irradiation conditions

IN‐REACTOR LOW‐CYCLE FATIGUE OF TYPE 0Kh16N15M3B STAINLESS STEEL

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