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NEA irradiation system ready to deploy at MITR
A new irradiation experimental system is ready for deployment. The rig, which is the focus of In-Core Real-Time Mechanical Testing of Structural Materials (INCREASE-I), an OECD Nuclear Energy Agency project, will be used to conduct stress-relaxation tests of stainless steel at the Massachusetts Institute of Technology Reactor (MITR), according to the OECD NEA.
G. Gervasini, F. Reiter
Fusion Science and Technology | Volume 27 | Number 2 | March 1995 | Pages 30-40
doi.org/10.13182/FST95-A11963802
Articles are hosted by Taylor and Francis Online.
Imperfectness of magnetic confinement in tokamak devices leads to interactions of plasma particles and radiation with the first walls and plasma facing components of fusion reactors. The most important processes are discussed. Special emphasis is given to the implantation and transport of hydrogen isotopes in solid materials.
One of the main concerns of hydrogen-material interaction is the determination of hydrogen recycling from the inner surface of the first wall, of hydrogen inventory in and hydrogen permeation through the wall of a fusion reactor. Numerical codes have been developed to calculate these properties. Hydrogen-material interaction parameters which are code input data are discussed. Some results of hydrogen isotopes inventory, recycling and permeation calculations in the next step fusion reactor ITER are presented, their accuracy is affected by the availability of data on trapping and surface processes.