V.A. Pozharov

Bio: V.A. Pozharov is an academic researcher from Kurchatov Institute. The author has contributed to research in topics: Divertor & Tokamak. The author has an hindex of 2, co-authored 2 publications receiving 23 citations.

Chapter 9: ITER contributions for Demo plasma development

Abstract: The chapter summarizes the physics issues of the demonstration toroidal fusion power plant (Demo) that can be addressed by ITER operation. These include burning plasma specific issues, i.e. energetic particle behaviour and plasma self-heating effects, and a broader class of power-plant scale physics issues that cannot be fully resolved in present experiments. A critical issue for Demo is whether MHD and energetic particle modes driven by fast particles will become unstable and affect plasma performance. Self-heating effects are expected to be especially important for control of steady-state plasmas with internal transport barriers (ITBs) and high bootstrap current fractions. Experimental data from ITER will improve strongly the physics basis of projections to Demo of major plasma parameters such as the energy confinement time, beta and density limits, edge pedestal temperature and density, and thermal loads on in-vessel components caused by ELMs and disruptions. ITER will also serve as a test bed for fusion technology studies, such as power plant plasma diagnostics, heating and current drive systems, plasma facing components, divertor and blanket modules. Finally, ITER is expected to provide benefits for the understanding of burning plasma behaviour in other magnetic confinement schemes.

Vanadium Alloys for Fusion Blanket Applications

Abstract: Vanadium alloys are attractive candidate structural materials for breeding blanket of fusion reactors because of their low activation properties and high temperature strength. Studies on various blanket designs are being carried out using vanadium alloys as structural materials and liquid lithium or molten salt Flibe as breeding and coolant materials. Recently significant progress in fabrication technology has been made for vanadium alloys through a program of producing large ingots of high purity V-4Cr-4Ti (NIFS-HEATs). Fundamental understandings on the effects of interstitial impurities (C, N, O) on mechanical properties, radiation effects on microstructure and mechanical properties, corrosion and compatibility in various environments were enhanced. New promising candidates were identified for the MHD insulator coating. Among the remaining critical issues are the effects of transmutant helium on mechanical properties and development of long life MHD coating. Development of vanadium alloys will he carried out in coordination with IFMIF and ITER-TBM schedules as essential tools for verification of their performance in fusion blanket environments.

Vanadium for Nuclear Systems

Abstract: Vanadium alloys are recognized as attractive candidate materials for the structural component of fusion reactors because of their low activation properties, high thermal stress factors, and radiation resistance V–4Cr–4Ti has been regarded as the leading candidate composition Recent Japanese, US, Russian, and Chinese fusion programs largely enhanced the fabrication technology of vanadium alloys Also, fundamental understandings of the effects of interstitial impurities (C, N, O) on mechanical properties, radiation effects on microstructure and mechanical properties, and compatibility in various environments were advanced recently The effects of neutron irradiation with transmutant helium on mechanical properties and irradiation/thermal creep performance are among the major remaining issues