＜正＞Plasma-facing materials（PFMs） in fusion reactors are exposed to high flux deuterium/tritium plasma and 14 MeV *** such as vacancies,voids and dislocations formed by irradiation of high energy neutrons act as s...
＜正＞Plasma-facing materials（PFMs） in fusion reactors are exposed to high flux deuterium/tritium plasma and 14 MeV *** such as vacancies,voids and dislocations formed by irradiation of high energy neutrons act as strong trapping sites of hydrogen isotopes and raise tritium retention in ***,quantitative understanding of the effects of neutron irradiation on tritium retention is important for safety assesment of fusion *** this purpose,the authors have tried to develop techniques to measure tritium concentration in neutron-irradiated *** concentration in materials is commonly examined by measuring intensity of-rays from tritium and/or that of X-rays induced ***-irradiated
作者：
K.ZhangM.ShimadaT.OtsukaP.CalderoniY.OyaM.SokolovJ.P.SharpeM.MatsuyamaY.HatanoHydrogen Isotope Research Center
University of ToyamaToyama930-8555Japan Fusion Safety ProgramIdaho National LaboratoryIdaho FallsID83415USA Interdisciplinary Graduate School of Engineering and ScienceKyushu UniversityFukuoka 812-8581Japan Radioscience Research LaboratoryFaculty of ScienceShizuoka UniversityShizuoka422-8529JAPAN Oak Ridge National LaboratoriesOak RidgeTN37831USA
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