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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. A. Gentile, S. Raftopoulos, P. LaMarche, M. Viola, T. Walters, M. Kalish, T. Kozub, H. Carnevale, D. Shaltis, S. Vinson, W. Walker, L. Ciebiera, R. Yager, M. Quigley, R. Meagher, C. Bunting, E. Rogers, M. Casey, R. Hawes, R. Raucci, D. Reeves, E Amarescu, M. Gibson, T. Granger, S. Langish, S. Bush, J. Langford, D. Hyatt, J. L. Anderson
Fusion Science and Technology | Volume 30 | Number 3 | December 1996 | Pages 1564-1566
Safety and Environment | doi.org/10.13182/FST96-A11963173
Articles are hosted by Taylor and Francis Online.
The Tokamak Fusion Test Reactor which is the progenitor for full D-T operating tokamaks has successfully processed > 81 grams of tritium in a safe and efficient fashion. Many of the fundamental operational techniques associated with the safe movement of tritium through the TFTR facility were developed over the course of many years at DOE tritium facilities (LANL, LLNL, SRS, Mound). In the mid 1980's The Tritium Systems Test Assembly (TSTA) at LANL began reporting operational techniques for the safe handling of tritium, and became a major conduit for the transfer of safe tritium handling technology from DOE weapons laboratories to non-weapon facilities. TFTR has built on many of the TSTA operational techniques and has had the opportunity of performing and enhancing these techniques at America's first operational D-T fusion reactor. This paper will discuss negative pressure employing “elephant trunks” in the control and mitigation of tritium contamination at the TFTR facility, and the interaction between contaminated line operations and Δ pressure control. In addition the strategy employed in managing the movement of tritium through TFTR while maintaining an active tritium inventory of < 50,000 Ci will be discussed.