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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. Besshou, K. Ogata, K. Kondo, T. Mizuuchi, K. Nagasaki, H. Okada, F. Sano, H. Zushi, T. Obiki
Fusion Science and Technology | Volume 27 | Number 3 | April 1995 | Pages 219-222
Helical Systems | doi.org/10.13182/FST95-A11947073
Articles are hosted by Taylor and Francis Online.
This paper describes the realization of magnetic detection of the finite β free boundary plasma shin for a toroidal helical plasma. Recent experimental results, the normalized displacement Δb/ap as a function of volume average beta <β>, are discussed. The measured typical plasma boundary shift, Δb/ap, in the standard Heliotron E configuration (Rp=2.20m, ap=0.21m, Ԏ/2ᴨ(0)~0.53, Ԏ/2ᴨ(ap)~2.8) is (5–12)x10–3, when the volume averaged beta is 0.50%. The measured normalized plasma boundary shift is nearly proportional to the diamagnetic volume-averaged beta, for values of beta up to 0.95%. The magnetically determined plasma boundary shift Δb is less than 3 mm. The measured shift is in the range in-between the expected upper limit (Δb/ap = β(0)/2βeq) and the lower limit (Δb/ap = <β>/2βeq), where βeq = (Ԏ/2ᴨ(ap))2(ap/Rp)~0.77 for the standard configuration of Heliotron E.
We find that the measured free boundary plasma shift strongly depends on the initial vacuum magnetic configuration parameters such as the horizontal position of magnetic axis and the rotational transform. When the vacuum magnetic axis is shifted inward toward the major axis, we observed a significant decrease of the normalized plasma shift (Δb/ap) and the plasma induced vertical field, which we interpret as being due to a reduction of Pfirsch-Schlüter current.