Emulation of neutron irradiation effects with protons: validation of principle

Was, Gary S.; Busby, Jeremy T.; Allen, Todd R.; Kenik, E.A.; Jensson, A; Bruemmer, S.M.; Gan, Jian; Edwards, Angela; Scott, Peter; Andreson, P.L

doi:10.1016/s0022-3115(01)00751-6

Cited by 289 publications

(164 citation statements)

References 24 publications

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“…The number density and mean size of Frank loops obtained for both iron and proton irradiated samples were in accordance with the values reported in neutron [10,18,38,39] and ion literature [18e23]. With increasing dose, a slight increase in average number density and diameter of Frank loops was observed in iron irradiated samples.…”

Section: Microstructuresupporting

confidence: 88%

Characterization of ion irradiation effects on the microstructure, hardness, deformation and crack initiation behavior of austenitic stainless steel:Heavy ions vs protons

Gupta

Hure

Tanguy

et al. 2018

Journal of Nuclear Materials

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OATAO is an open access repository that collects the work of Toulouse researchers and makes it freely available over the web where possible. This is an author-deposited version published in : http://oatao. Proton irradiation is generally used as a representative alternative of neutron irradiation to improve the current understanding of the mechanisms involved in IASCC. This study assesses the possibility of using heavy ions irradiation to evaluate IASCC mechanisms by comparing the irradiation induced modifications (in microstructure and mechanical properties) and cracking susceptibility of SA 304 L after both type of irradiations: Fe irradiation at 450 C and proton irradiation at 350 C. Irradiation-induced defects are characterized and quantified along with nano-hardness measurements, showing a correlation between irradiation hardening and density of Frank loops that is well captured by Orowan's formula. Both irradiations (iron and proton) increase the susceptibility of SA 304 L to intergranular cracking on subjection to Constant Extension Rate Tensile tests (CERT) in simulated nominal PWR primary water environment at 340 C. For these conditions, cracking susceptibility is found to be quantitatively similar for both irradiations, despite significant differences in hardening and degree of localization.

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Section: Microstructuresupporting

confidence: 88%

Characterization of ion irradiation effects on the microstructure, hardness, deformation and crack initiation behavior of austenitic stainless steel:Heavy ions vs protons

Gupta

Hure

Tanguy

et al. 2018

Journal of Nuclear Materials

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“…As a result, the material exhibits a substantial increase in yield stress (Fig. 2), reduction in ductility, swelling loss of corrosion resistance which may be damaging to the proper operation of the reactor [1][2][3][4][5][6][7]. For instance cracks were observed in bolts (Fig.…”

Section: State Of the Artmentioning

confidence: 99%

Using Microscopy to Help with the Understanding of Degradation Mechanisms Observed in Materials of Pressurized Water Reactors

Legras¹,

Volgin²,

Radiguet³

et al. 2017

JMSE-B

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Abstract:Even if temperature, pressure and chemistry of the cooling water are not very high and aggressive, materials used in PWRs (Pressurized Water Reactors) are exposed to different degradation mechanisms. One of the main goals of the research programs in this field is to develop physical model of the mechanisms down to the atomic scale. Such approach needs a clear description and understanding of the degradation mechanisms at the same small scale. This paper illustrates the benefits of different microscopies and of their last improvements up to the promising possibilities of monochromated and aberrations corrected TEM/STEM. A specific focus is placed on four different degradation mechanisms observed in austenitic stainless steel: irradiation ageing, corrosion fatigue, stress corrosion cracking and corrosion.

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“…Proton fluxes with an energy of 590 MeV are occasionally used to simulate the action of thermonuclear neutrons [17,18]. Special experiments [19] have demonstrated that radiation damage due to protons with the appropriate energy is identical to that of neutrons. However, the doses that cause identical effects differ slightly in value.…”

Section: Defects In Crystalline Solidsmentioning

confidence: 99%

Radiation Effects on the Components of Diagnostic Systems for a Thermonuclear Reactor: A Review

Gott

2005

Instrum Exp Tech

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The review is devoted to describing how irradiation with neutrons, fast particles, and γ rays affects components of the diagnostic equipment for a thermonuclear reactor. It is shown that the radiation environment inside a reactor and in the space around it has a significant (and sometimes crucial) effect on the diagnostic instruments. Unfortunately, the available data on radiation effects do not allow us to reliably estimate the resistance of a particular diagnostic component to radiation damage from neutrons, γ rays, and other particles. Specifically, the shortage of data on the effect of 14-MeV thermonuclear neutrons is a major problem. Therefore, the radiation testing of both the instruments' individual components of the instruments and diagnostic systems as a whole is in particular of paramount importance.

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Emulation of neutron irradiation effects with protons: validation of principle

Cited by 289 publications

References 24 publications

Characterization of ion irradiation effects on the microstructure, hardness, deformation and crack initiation behavior of austenitic stainless steel:Heavy ions vs protons

Characterization of ion irradiation effects on the microstructure, hardness, deformation and crack initiation behavior of austenitic stainless steel:Heavy ions vs protons

Using Microscopy to Help with the Understanding of Degradation Mechanisms Observed in Materials of Pressurized Water Reactors

Radiation Effects on the Components of Diagnostic Systems for a Thermonuclear Reactor: A Review

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