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NEA irradiation system ready to deploy at MITR
A new irradiation experimental system is ready for deployment. The rig, which is the focus of In-Core Real-Time Mechanical Testing of Structural Materials (INCREASE-I), an OECD Nuclear Energy Agency project, will be used to conduct stress-relaxation tests of stainless steel at the Massachusetts Institute of Technology Reactor (MITR), according to the OECD NEA.
David Murdoch
Fusion Science and Technology | Volume 27 | Number 2 | March 1995 | Pages 1-7
doi.org/10.13182/FST95-A11963797
Articles are hosted by Taylor and Francis Online.
The design concepts and machine operating parameters which are now emerging for ITER demand novel fuel cycle system designs. The requirement that the torus vacuum system and the fuelling system be installed inside the cryostat imposes a range of stringent environmental constraints. The high divertor pressure which is characteristic of the ITER-EDA involves the development of completely new pumping concepts, and the lower specific tritium inventories now targetted will impact the design of systems and components throughout the fuel cycle.
The new design input parameters are reviewed in the paper, and a range of advanced pumping concepts proposed as candidates for the ITER torus vacuum duty are outlined. The R & D programme priorities as outlined by the ITER-JCT and as presently implemented by the EC Home Team are reviewed.
The status of the design for the SEAFP (Safety and Environmental Aspects of Fusion Power) studies is outlined, and the essential differences from ITER are described. The key R & D issues associated with the SEAFP fuel cycle design are listed.