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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.
C. Boffito, A. Conte, G. Gasparini
Fusion Science and Technology | Volume 27 | Number 2 | March 1995 | Pages 69-74
doi.org/10.13182/FST95-A11963807
Articles are hosted by Taylor and Francis Online.
The dissociation of tritiated water and the recovery of tritium is an important issue for the future thermonuclear fusion device.
Various solutions have been prospected including chemical dissociation on active beds.
The results of H2O sorption tests performed on different possible candidate alloys, by means of vacuum microbalance tecnique at a pressure of some hundreds Pa and at temperatures ranging from 300 to 400°C, are presented. From these tests a ternary Zr-Mn-Fe alloy appears to have promising features, combining good dissociation characteristics for H2O with low hydrogen pick-up.
The basic properties of this material are discussed, including structural aspects and sorption characteristics vs. other gases.