Methodology of the Experiments to Study Lithium CPS Interaction with Deuterium Under Conditions Of Reactor Irradiation

Problems of plasma-facing materials degradation and in-vessel element destructions, tritium accumulation and plasma pollution can be overcome by the use of liquid metals with low atomic number. The best candidate as a material for divertor receiving plates and other in-vessel devices is lithium. Liquid lithium advantages as a plasma facing material have been confirmed by a large number of the experiments at the plasma-physical facilities being operated worldwide

Application of hydrogen permeation method in reactor experiments on investigation of hydrogen isotope interaction with structural materials

The relevance of the study is caused by the necessity to develop methodical and instrumental bases for researching hydrogen isotope interaction with different materials under reactor irradiation. The main aim of the study is to develop and to test the technique on determining hydrogen isotope interaction parameters with structural materials under reactor irradiation; to carry out the estimates and experiments confirming the possibility of using the technique. The methods used in the study: thermophysical, neutron calculations methods of ampoule devices and method of hydrogen permeation were used. The results: The paper introduces the principle concepts of material reactor investigation technique using the hydrogen permeation method, estimates of the technique applicability and the results of its application at the reactor experiments with structural materials, such as steel SS316L (N)-IG, vanadium alloy V4Cr4Ti and copper bronze CuCrZr

Methodology of the Experiments to Study Lithium CPS Interaction with Deuterium Under Conditions Of Reactor Irradiation

Problems of plasma-facing materials degradation and in-vessel element destructions, tritium accumulation and plasma pollution can be overcome by the use of liquid metals with low atomic number. The best candidate as a material for divertor receiving plates and other in-vessel devices is lithium. Liquid lithium advantages as a plasma facing material have been confirmed by a large number of the experiments at the plasma-physical facilities being operated worldwide