Objectives and prospects for low-activation materials

Butterworth, G.J.

doi:10.1016/0022-3115(91)90028-6

Cited by 17 publications

(4 citation statements)

References 3 publications

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“…The main principle adopted to reduce the amount of activation in a material is by substitution of elements that are particularly susceptible to activation, with chemically similar elements with a lower susceptibility to activation [1,2,7,16,22,[32][33][34]. As mentioned in section 2 ECF/ICF gives a comprehensive model for identification of such elements and quantifying their response towards the radiological quantities.…”

Section: Materials Optimization Formalization Based On Multiple Radio...mentioning

confidence: 99%

“…One of the major challenges for the design and construction of fusion reactors is the development and qualification of materials to withstand complex loading conditions which include high thermal and mechanical strains along with nuclear responses produced in the material by the incident fusion neutrons [1][2][3][4][5]. These high-energy (up to 14.1 MeV) and high flux (up to 1.0 × 10 15 n cm −2 ) neutrons produced in fusion reaction would irradiate the materials that make up the reactor vessel and its sub-systems.…”

Section: Introductionmentioning

confidence: 99%

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Composition optimization strategy based on multiple radiological responses for materials in spatially and temporally varying neutron fields

Kanth¹,

Tadepalli²,

Subhash³

2018

Nucl. Fusion

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Structural materials present in and around any fusion device will face stringent conditions due to the high-energy and high-flux neutrons emitted from the fusion plasma. These neutrons can cause induced radioactivity, gas production, energetic knock out atoms, atomic displacement and decay heat in these materials. This would have a significant life-limiting impact on the materials and would also cause biological hazards and radioactive waste. Hence designing low activation materials for fusion devices is warranted. This paper presents a novel tool for quantification of radiological responses in terms of the elements present in the initial material composition. Such a framework would help in the identification and optimization of the fraction of most dangerous elements/isotopes from the material composition. In practical scenarios, the material encounters a large spatial and temporal variation of neutron fluxes. This problem has been effectively treated in the present work using a multi-parameter optimization scheme. The scheme optimizes the material composition (elemental or isotopic) based on various nuclear responses and there spatial and temporal variations within the user-defined constraints. This scheme is further included in the multi-point activation code ACTYS-1-GO. The tool provides a comprehensive picture of the material response during neutron irradiation and after shutdown, enabling the assessment of structural integrity of components in a fusion device. As an aide to the material optimization process, this paper also introduces a visual representation of the evaluated information like quantification of radiological responses produced by the parent elements/isotopes in a material. This has been implemented through a series of spectrum independent and spectrum-dependent diagrams called the radiation response diagrams. These diagrams show the variation of contributing parents toward the radiological responses as a function of cooling time. Such a graph could be very useful as a first approximation for material design.

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Section: Materials Optimization Formalization Based On Multiple Radio...mentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Composition optimization strategy based on multiple radiological responses for materials in spatially and temporally varying neutron fields

Kanth¹,

Tadepalli²,

Subhash³

2018

Nucl. Fusion

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“…In the present study RAFM steel is used, which is the chosen material for the first wall of the fusion reactor test blanket module in ITER, which is supposed to retain adequate mechanical properties under intense neutron irradiation (~14.1 MeV energy) and high thermo-mechanical loads during reactor operation [9][10][11]. The flow behaviour of this material under high strain rates is extremely important towards structural integrity of this component.…”

Section: Methodsmentioning

confidence: 99%

Assessment of Deformation Field during High Strain Rate Tensile Tests of RAFM Steel Using DIC Technique

Krishnan

Baranwal

Moitra

et al. 2014

Procedia Engineering

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Towards developing a constitutive model for describing the flow and fracture behaviour of engineering materials under higher strain rates, studying the deformation fields in uniform and localized deformation regime using the high strain rate tensile tests is of technical importance. To this end, high strain rate tensile tests have been carried out on flat tensile specimen of reduced activation ferritic-martensitic (RAFM) steel at different loading rates varying from 5 m/s to 14 m/s. The strain fields at uniform and localized deformation regime have been mapped by Digital Image Correlation (DIC) technique. For carrying out the DIC, high speed images of the specimen surface have been captured in-situ by high speed camera, synchronized with the loaddisplacement data acquisition system. The stress-strain fields thus obtained in this study would be an appropriate input to numerical analysis to characterize the flow and fracture behaviour of RAFM steels.

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“…For this purpose, the Reduced Activation Ferritic Martensitic (RAFM) steel with alloying elements of W, Ta and V is the chosen material in order to overcome residual radioactivity, generally encountered in conventional ferritic-martensitic steels originating from the long-lived transmutation nuclides of Mo, Nb, Ni, N, B, Cu, Co, Ti etc [4][5][6]. For evaluating DBTT under quasi-static loading situations, the reference temperature (T 0 ) approach, as described in ASTM E 1921-10 [7], is a well-recognised approach.…”

Section: Introductionmentioning

confidence: 99%

A Study of Fracture Mechanisms in RAFM Steel in the Ductile to Brittle Transition Temperature Regime

Moitra

Dasgupta

Sathyanarayanan

et al. 2014

Procedia Engineering

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The fracture behaviour of a Reduced Activation Ferritic Martensitic Steel (RAFM) has been studied within the Ductile to Brittle Transition Temperature (DBTT) regime. The DBTT has been determined by ASTM E 1921 based reference temperature approach under dynamic loading condition. The dynamic reference temperature (T 0 dy ) was found to be − 33.8 °C. The fracture mechanism has been studied by extracting TEM specimens precisely at the crack initiation sites using focused ion beam (FIB) technique in a high resolution dual beam scanning electron microscope. Detailed analytical TEM studies revealed that the morphology of carbides play a crucial role in the initiation of a crack. The larger ellipsoidal carbides, which were found to be Crrich, have been found to be responsible for dislocation piles ups. The shorter edge of these ellipsoidal carbides are areas of high stress concentration and were found to initiate cracks by decohesion of the particle-matrix interface. On the contrary, the iron rich carbides have been found to be smaller, more spherical, and thus less effective in blocking dislocation movement and therefore formation of pile ups. The results, which reveal an important mechanism towards crack initiation in ferritic-martensitic steels, will be presented in detail.

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Objectives and prospects for low-activation materials

Cited by 17 publications

References 3 publications

Composition optimization strategy based on multiple radiological responses for materials in spatially and temporally varying neutron fields

Composition optimization strategy based on multiple radiological responses for materials in spatially and temporally varying neutron fields

Assessment of Deformation Field during High Strain Rate Tensile Tests of RAFM Steel Using DIC Technique

A Study of Fracture Mechanisms in RAFM Steel in the Ductile to Brittle Transition Temperature Regime

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