[en] The MANET-I martensitic 10.6% Cr type of steel was developed as a potential structural material for the first wall and the blanket of a fusion device within the framework of the Nuclear Fusion Project. An extensive irradiation program (FRUST/SIENA) was elaborated to study the influence of radiation upon the Charpy impact characteristics. In addition to unirradiated reference specimens, 87 irradiated subsize Charpy specimens (3 x 4 x 27 mm³) were examined under eight different heat treatments at irradiation temperatures between 287 degrees C and 475 degrees C and exposure doses of 5 dpa to 15 dpa. On the basis of the numerous test results and their interpretation it is possible to describe radiation induced material embrittlement, and, consequently, the deterioration of the Charpy impact properties. The description is limited, on the one hand, by the variations in the test results and, on the other hand, by the gaps in the test matrix. Therefore, additional investigations, especially in the low irradiation temperature and low dose regimes will be the subject of further ongoing work

[en] Problems of the permeation of hydrogen and tritium through heat exchangers for HTGR reactors and for steam/methane reforming processes in which nuclear heat is used, are discussed. An experimental facility is described which was designed to investigate hydrogen permeability through materials of interest at the high temperature involved under process conditions and results of the tests are presented. Plans are also discussed for determination of permeation of tritium, produced in the HTR, into the chemical products. (U.K.)

[en] The Tritium Laboratory Karlsruhe began operations with gram amounts of tritium in March 1995. Since then, the experimental facilities CAPRICE and PETRA have been routinely in operation. New experimental activities include the analysis of tritium in first wall materials of fusion devices and the development of methods for the detritiation of graphite and carbon fibre composite tiles. The experience gained with Tritium Retention Systems, with the Tritium Transfer System, with portable uranium getter beds and in this context with tritium accountancy is reported. The incorporation of a new Pd packed column into the Isotope Separation System, the increase in storage capacity of the Tritium Storage System, the improvements of the analytical instrumentation and some repair activities are also described. (authors)

[en] An overview is given of the tritium technology activities carried out in the European national laboratories associated with the European Fusion Programme and in the European Joint Research Center. The relationship of these activities to the Next European Torus (NET) design priorities is discussed, and the current status of the research is summarised. Future developments, required for NET, which will be addressed in the definition of the next 5-year programme are also presented