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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.
S.K. Sood, K.M. Kalyanam
Fusion Science and Technology | Volume 27 | Number 2 | March 1995 | Pages 79-84
doi.org/10.13182/FST95-A11963809
Articles are hosted by Taylor and Francis Online.
Tritiated water represents a source of occupational exposure and environmental emissions for fusion and fission reactors. Fusion reactors must operate within stringent radionuclide emission limits.
A range of tritiated water concentrations can be generated in fusion reactors, mostly in the form of tritiated light water. In contrast, tritium removal plants have been built in Canada and France to remove tritium from heavy water moderated fission reactors.
Various isotope separation processes have been developed to remove tritium from light and heavy water. Appropriate process selection depends, amongst other items, on whether tritium is to be removed from light or heavy water, and on whether the detritiated water is recycled back to a process system or is discharged to the environment.
This paper primarily discusses water detritiation requirements in fusion reactors and outlines process options that are suitable for meeting these requirements.