S. Von Tiedemann D Collins M. Gilbert I. Kodeli
Predictions of material activity in commercial fusion conditions predominantly rely on computational methods, due to a lack of data on long-term e ects of high-energy neutron irradiation on structural steels. Consequently, this could result in a bias due to uncertainties in nu…
Preprint PublishedSehila M. Gonzalez de Vicente Nicholas A. Smith Laila El-Guebaly Sergio Ciattaglia Luigi Di Pace Mark Gilbert Robert Mandoki Sandrine Rosanvallon Youji Someya Kenji Tobita David Torcy
In the absence of official standards and guidelines for nuclear fusion plants, fusion designers adopted, as far as possible, well-established standards for fission-based nuclear power plants (NPPs). This often implies interpretation and/or extrapolation, due to differences in structures, systems and components, materials, safety mitigation systems,…
Preprint PublishedD.J.M. King A.J. Knowles D. Bowden M.R. Wenman S. Capp M. Gorley J. Shimwell L. Packer M.R. Gilbert A. Harte
This Review considers current Zr alloys and opportunities for advanced zirconium alloys to meet the demands of a structural material in fusion reactors. Zr based materials in the breeder blanket offer the potential to increase the tritium breeding ratio above that of Fe, Si and V based materials. Current commercial Zr alloys might be considered …
Preprint PublishedL. W. Packer P. Batistoni S. C. Bradnam S. Conroy M. Fabbri Z. Ghani M. R. Gilbert S. Jednorog E. Laszynska D. Leichtle I. Lengar M. Majerle J. W. Mietelski C. R.Nobs O. Ogorodnikova M. Pillon M. I. Savva I. E. Stamatelatos T. Vasilopoulou R. Villari A. Wojcik-Gargula R. Worrall JET Contributors
Understanding the effects of neutron irradiation of materials is one of the outstanding issues in the development of fusion technologies. The impact of this work derives from the opportunity, for the first time in a tokamak operating with a D-T plasma, to deliver experimental results which directly link to the nuclear characteristics of real sample…
Preprint PublishedL. Reali M. Boleininger M. R. Gilbert S. L. Dudarev
Using the notion of eigenstrain produced by the defects formed in a material exposed to high energy neutron irradiation, we develop a method for computing macroscopic elastic stress and strain arising in components of a fusion power plant during operation. In a microstructurally isotropic material, the primary cause of macroscopic elastic stress an…
Preprint PublishedMegha Sanjeev Mark R. Gilbert Samuel T. Murphy
The high anisotropy in the thermal conductivity of lithium metatitanate, Li2TiO3, is shown using the classical simulation method of Molecular Dynamics (MD). The thermal conductivity along the z-direction is markedly lower than that in x and y. This characteristic could be exploited to favourably adjus…
Preprint PurchaseElena V. Rosa Adame Andrius Aleksa Mark R. Gilbert Martin Cuddy Tristan Calvet Zsolt Vizvary Nicolas Mantel Francesco Maviglia Jeong Ha You
A development plan for validation of functional principles is defined to support the challenges of mock-up manufacturing and testing. It is aimed to develop the process and infrastructure for qualifying fusion components for the limiters in the European DEMO. The limiters are components that define the plasma boundary by direct contact during norma…
PreprintA. Litnovsky I. Duran J.W. Coenen Yu. Gasparyan M.R. Gilbert E. Hollmann Ch. Linsmeier S. Nogami C.H. Skinner S. Zinkle
The chapter is devoted to materials used in controlled fusion facilities. Material solutions for magnetic confinement fusion devices and inertial confinement fusion facilities are described. Fusion materials have to preserve their performance often under extremely harsh conditions characterized by intensive particle fluxes, high levels of neutron i…
PurchaseYichen Qian Mark Gilbert Lucile Dezerald David Cereceda
Tungsten and tungsten alloys are being considered as leading candidates for structural and functional materials in future fusion energy devices. The most attractive properties of tungsten for the design of magnetic and inertial fusion energy reactors are its high melting point, high thermal conductivity, low sputtering yield and low long-term dispo…
Preprint PublishedA. Litnovsky F. Klein X. Tan J. Schmitz J. W. Coenen C. Linsmeier J. Gonzalez-Julian M. Bram I. Povstugar T. Morgan Y. M. Gasparyan A. Suchkov D. Bachurina D. Nguyen-Manh M. Gilbert D. Sobieraj J. S. Wróbel P. Bittner A. Reuban
Self-passivating Metal Alloys with Reduced Thermo-oxidation (SMART) are under development for the primary application as plasma-facing materials of the first wall in a fusion DEMOnstration power plant (DEMO). SMART materials must combine the suppressed oxidation in case of an accident and an acceptable plasma performance during the regular operatio…
Preprint Published