Effect of atomic-pile radiation on the elastic modulus of an austenitic steel

Charlesby, A.; Hancock, Nicholas; Sansom, H.C.

doi:10.1016/0891-3919(54)90026-1

Cited by 5 publications

(8 citation statements)

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“…Any trend in the production of CF 4 from PTFE was obscured by the large scatter; the G -values were in the range 0.004 to 0.009 for doses up to 1.84×10 22 ev/g, which are lower on the average than Charlesby’s values [ 18 ] and do not seem to fit his dose-dependence formula requiring a regular linear increase from G =0 initially to G =0.050 at 1×10 21 ev/g. At very high doses agreement might improve.…”

Section: Resultsmentioning

confidence: 99%

“…The initial G -value for evolution of F-in aqueous alkali and air was near 0.6 or 1.7 in different studies. A weight loss proportional to the square of the radiation dose was found by Charlesby [ 18 ] when diffusion effects were eliminated. If the weight loss was principally CF 4 , the G (CF 4 ) should increase proportionally with dose.…”

Section: Products Of Irradiationmentioning

confidence: 99%

“…The observed changes of mechanical properties are, (1) a very early increase in impact strength at 3×10 20 ev/g [ 2 ], (2) a loss of most elongation somewhere in the range 0.5–5×10 20 ev/g [ 2 , 46 ], (3) a loss of tensile strength, which may occur early or not be important until past 30×10 20 ev/g [ 8 , 46 ], and finally (4) a disintegration of large pieces beginning around 300×10 20 ev/g [ 18 ]. Thin pieces are more resistant to disintegration.…”

Section: Products Of Irradiationmentioning

confidence: 99%

“…Volatile and ionic products sometimes show a dependence upon thickness [ 4 , 18 ] or upon storage after irradiation [ 4 ], which is attributed to slow diffusion. In the present study these effects were small because of the powdered form of the sample and the long storage before analysis.…”

Section: Products Of Irradiationmentioning

confidence: 99%

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Gamma irradiation of fluorocarbon polymers

Florin¹,

Wall²

1961

J. RES. NATL. BUR. STAN. SECT. A.

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Several ~uorocarbon polym~rs ~ere irradiated with Co60 gamma radiation at doses up to 10 22 ev/g. ~he polymers studIed Included polytetrafiuoroethylene, polytrifiuoroethylene, polychlorotrIfiuoroethy.len~, a copoly.mer of tetrafiuoroethylene with hexafiuoropropylene, and several rubbery vInylIdene fiuorIde copolymers. G-values were measured for volatile p~oducts, for free radica.ls ~etected by electron spin reso~ance, and, in the case of polychlorotrIfiuoroethylene, for SClSSIOns. The course of degradatIOn or crosslinking was followed by zero-strength-time .and tensile-strength measurements. It was found that for poly tetrafiuoroethylene and Its hexafiuoropropylene copolymer the presence of air-accelerated scission drastically. The mechanism of the radiation-induced changes is discussed in terms of freeradical intermediates.

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Section: Resultsmentioning

confidence: 99%

Section: Products Of Irradiationmentioning

confidence: 99%

Section: Products Of Irradiationmentioning

confidence: 99%

Section: Products Of Irradiationmentioning

confidence: 99%

See 2 more Smart Citations

Gamma irradiation of fluorocarbon polymers

Florin¹,

Wall²

1961

J. RES. NATL. BUR. STAN. SECT. A.

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“…The thermoelastic parameter of Wong et al is given by

k = ((), α - \frac{1}{E^{2}} \frac{\partial E}{\partial T} σ_{m}) {(ρ_{o} C_{ε})}^{- 1}

where α is the coefficient of thermal expansion, E is the modulus of elasticity, T is the absolute temperature, σ m is the mean stress, ρ o is the material density, and C ε is the heat capacity at constant strain. Early studies by Charlesby et al on the change in elastic modulus of austenitic steels with exposure to radiation found a change of no more than 0.3%. The density will change if irradiation swelling is significant; however, at the low level of damage used in this study, volumetric changes due to swelling are unlikely.…”

Section: Experimental Methodsmentioning

confidence: 99%

Observations of fatigue crack behaviour in proton‐irradiated 304 stainless steel

Spencer

Patterson

2019

Fatigue Fract Eng Mat Struct

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Thermoelastic stress analysis (TSA) has been used to monitor fatigue crack growth in compact tension (CT) specimens, made from 304 grade austenitic stainless steel, that have been subject to proton irradiation. Several specimens had a 10 × 10 mm area ahead of a 1‐mm precrack irradiated with a 1.6 MeV proton beam up to 0.216C to 0.648C of accumulated charge prior to fatigue testing. Subsequently, specimens were loaded sinusoidally at 20 Hz with an R ratio of 0.5, and TSA data were collected both at the loading frequency and its second harmonic. Irradiation appears to cause an increase in the fatigue life, with a reduction in crack growth rate observed in the irradiated specimens compared with the unirradiated control specimens. Irradiation damage caused a moderately linear change in both the parameters of the Paris law with accumulated charge from the irradiation.

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Radiation Effects in Steel

Porter¹

1960

Materials in Nuclear Applications

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As early as 1942 it was recognized that high-energy neutrons would have the ability to disrupt the crystal lattice of metals through which they might pass and that this disruption might lead to serious changes in the mechanical and physical properties of structural materials used in the construction of nuclear reactors. Since that time studies of these “radiation effects” have been conducted by solid stale physicists and by reactor development engineers working at or in conjunction with the various atomic energy installations. This paper is a survey of the published literature on the effect of neutron radiation on the mechanical properties of steels. On theoretical grounds and on the basis of fundamental experiments it is postulaled that clusters of radiation-produced vacancies or interstitials, by interacting with dislocations already present and additional dislocations produced during plastic deformation, are primarily responsible for the increased strength and decreased ductility of irradiated metals. From a tabulation of the existing information on the effect of neutron radiation on the mechanical properties of carbon, alloy, and stainless steels, it appears that relationships between the changes in properties and neulron exposure can be defined. These relationships indicate that steels behave in general as a class of material and are affected by neutron radiation in a similar manner so that the effects of a given neutron exposure can usually be predicted within rallier general limits. Normally, a large proportion of the radiation-produced crystal lattice defects responsible for the changes in mechanical properties in steels can be removed by heating in the range 550 to 900 F. Likewise, irradiation at temperatures above 500 F usually results in less damage than irradiation at lower temperatures, presumably because of concurrent thermal annealing of the damaged regions. Under certain conditions, radiation may accelerate phase transformation or aging phenomena, and changes in mechanical properties as a result of such secondary effects may not be removed by the annealing treatments at 550 to 900 F. It is important to recognize that the above generalizations are based on results which show considerable scatter and that there is information available which indicates that such factors as grain size, microstructure, composition, and steel cleanliness can influence the magnitude of the radiation effect.

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Effect of atomic-pile radiation on the elastic modulus of an austenitic steel

Cited by 5 publications

References 0 publications

Gamma irradiation of fluorocarbon polymers

Gamma irradiation of fluorocarbon polymers

Observations of fatigue crack behaviour in proton‐irradiated 304 stainless steel

Radiation Effects in Steel

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