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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.
Satoshi Sato, Koichi Maki, Hideyuki Takatsu, Yasushi Seki
Fusion Science and Technology | Volume 30 | Number 3 | December 1996 | Pages 1076-1080
Neutronics Experiments and Analyses | doi.org/10.13182/FST96-A11963093
Articles are hosted by Taylor and Francis Online.
Shielding analyses for toroidal field coils (TFCs) around the exhaust duct in a nuclear fusion experimental reactor have been performed by two-dimensional discrete ordinate method, and their peak nuclear responses were evaluated. From the results, it was found that the duct wall of about 410 mm thickness was required incase of no shield structure behind the divertor in ordsr to satisfy the radiation limits of TFCs. Taking overestimation due to the analysis model simulating the exhaust duct with a toroidally continuos opening into account, nuclear responses may possibly be lower than the radiation limits by 300 mm thick duct wall. By providing a 480 mm thick shield with 140 mm wide slits behind the divertor, nuclear responses were reduced to about 1/20, and they were equal to or lower than the radiation limits for 200 mm thick duct wall. Also, taking overestimation, nuclear responses may possibly be more than six times lower than the radiation limits for 200 mm thick duct wall.