An investigation of post-irradiation examination facility for fusion blanket materials

This report describes the concept of the post-irradiation examination (PIE) facility for fusion blanket materials, and results of an investigation on the experimental facility for tritium breeding related materials, which will be built for materials tests as the first step of arrangement of the PIE facility. In the framework of the fusion blanket development program related the International Thermonuclear Experimental Reactor (ITER), an in-pile test using the Japan Materials Test Reactor (JMTR), designated the in-pile functional test of the partial ITER test module, has been planned in order to study the functions of the breeding blanket under neutron irradiation, such as tritium generation and recovery properties and nuclear and thermal properties. It is essential to dismantle the irradiated assembly and to execute property tests of the irradiated specimens, such as measurement of the residual tritium inventory. There is, however, no facility in the Japan Atomic Energy Research Institute (JAERI), nor in all Japan, where PIE is possible for specimens with tritium of more than 37 MBq (1000 Ci) and γ-source without sealing. Also there is not facility in abroad where systematic PIE can be made. In addition, it is anticipated that a large amount of expense is needed to construct a new PIE facility with these kinds of functions. Therefore, the present report summarizes a model case of main items and contents to be examined concretely for the arrangement, assuming reconstruction of an existing facility, namely the Radioisotope Application and Development Laboratory in Oarai Research Establishment of JAERI. In this investigation, reduction of construction fee has been pursued, and it has been planned to concentrate in the newly reconstructed facility the blanket-related PIE equipments which are scattered in the JMTR Hot Laboratory, in order to promote efficient research and development. (author)