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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.
J. Manuel Perlado, Eduardo Alonso, Kunioki Mima, Sadao Nakai
Fusion Science and Technology | Volume 30 | Number 3 | December 1996 | Pages 1304-1308
Power Plant Design and Technology | doi.org/10.13182/FST96-A11963128
Articles are hosted by Taylor and Francis Online.
The Inertial Fusion Reactor KOYO, proposed by ILE Osaka was completed in its first phase study in 1992, and recent updates including new features have been released up to now. It is based on potentially key achievements in Inertial Fusion Energy (IFE) physics: development to achieve required laser efficiency, implosion stability and gain, pellet fabrication, chamber maintenance, engineering feasibilities, and cost of electricity.
Neutron (target) emission profiles are reported assuming direct drive compressed targets (500 g.cm-3), which have been described with different approaches in stationary transport models. A full three-dimensional description of the reactor has been used to perform the neutronic analysis. Neutron spectra and flucnecs are calculated, and compared with previous one-dimensional results showing the differences in using both approaches. Some figures indicating the neutron flux expected through deep penetrations impinging on the final optics are also presented, representing its coincidence at long distances with the uncollided flux.
The reported consequences are those related to the activation of the materials: shallow land burial (SLB) and recycling. Those radiological responses have been studied for the SiC tubes (components of the blanket), graphite (reflector), and ferritic steel HT-9 (structural wall).