Erratum: Intravenous ketamine for adolescents with treatment-resistant depression: An Open-Label Study, by Cullen KR, Amatya P, Roback MG, Albott CS, Westlund Schreiner M, Ren Y, Eberly LE, Carstedt P, Samikoglu A, Gunlicks-Stoessel M, Reigstad K, Horek N, Tye S, Lim KO, Klimes-Dougan B. (J Child Adolesc Psychopharmacol (2018) 28:7 (437-444) DOI: 10.1089/cap.2018.0030)

In the September 2018 issue of Journal of Child and Adolescent Psychopharmacology (vol. 28, no. 7, pp. 437-444), the article "Intravenous Ketamine for Adolescents with Treatment-Resistant Depression: An Open-Label Study," by Dr. Kathryn R. Cullen et al., was missing the financial support information as follows: This research was supported by the National Institutes of Health's National Center for Advancing Translational Sciences (UL1TR002494), the Biotechnology Research Center (P41 EB015 894), the NINDS Institutional Center Core Grants to Support Neuroscience Research (P30 NS076408), the High Performance Connectome Upgrade for Human 3TMR Scanner (1S10OD017974-01), and the University Foundation, Amplatz Scholarship. The online version of the article has been corrected to reflect this additional information. The authors wish to apologize for the omission

Overview of the JET results

Since the installation of an ITER-like wall, the JET programme has focused on the consolidation of ITER design choices and the preparation for ITER operation, with a specific emphasis given to the bulk tungsten melt experiment, which has been crucial for the final decision on the material choice for the day-one tungsten divertor in ITER. Integrated scenarios have been progressed with the re-establishment of long-pulse, high-confinement H-modes by optimizing the magnetic configuration and the use of ICRH to avoid tungsten impurity accumulation. Stationary discharges with detached divertor conditions and small edge localized modes have been demonstrated by nitrogen seeding. The differences in confinement and pedestal behaviour before and after the ITER-like wall installation have been better characterized towards the development of high fusion yield scenarios in DT. Post-mortem analyses of the plasma-facing components have confirmed the previously reported low fuel retention obtained by gas balance and shown that the pattern of deposition within the divertor has changed significantly with respect to the JET carbon wall campaigns due to the absence of thermally activated chemical erosion of beryllium in contrast to carbon. Transport to remote areas is almost absent and two orders of magnitude less material is found in the divertor