D retention behavior in the CLF-1 steel after D ion irradiation and D plasma exposure.

• D was introduced into the CLF-1 steel using D ion irradiation, D plasma exposure in PREFACE and EAST separately. • D retention and release behavior of the CLF-1 steel was examined using TDS. • Different D retention and release behavior of the CLF-1 steel irradiated in three conditions were showed. Deuterium (D) retention behavior in a reduced activation ferritic/martensitic (RAFM) steel (CLF-1) is measured by thermal desorption spectrometry (TDS) after irradiation by D ion in an ion beam facility, exposure to D plasma in a linear ECR plasma generator, and exposure to D plasmas in the EAST tokamak separately. The D release behavior of the CLF-1 steel under the three-different D implantation condition is compared. Results indicate that D release behavior in the CLF-1 steel after the tokamak exposure experiments differs significantly from those after laboratory D ion implantation experiments or D plasma exposure experiments in a linear ECR plasma generator. This demonstrates that using low temperature plasmas in laboratory facilities alone is not sufficient in the study of hydrogen isotope retention behavior in a realistic tokamak environment. In order to simulate the plasma and material interaction in tokamak more felicitously, more work need to do to improve the linear plasma generator at present. Possible explanations have been proposed to explain the different D release behavior in the CLF-1 steel after D implantation in three different environment. [ABSTRACT FROM AUTHOR]