Validation of the Be ground-state molecular structure using Be()He triple differential reaction cross-section measurements

Li, P. J.*; Beaumel, D.*; Lee, J.*; Assi, M.*; Chen, S.*; Franchoo, S.*; Gibelin, J.*; Hammache, F.*; Harada, T.*; Kanada-En'yo, Yoshiko*; et al.

Physical Review Letters, 131(21), p.212501_1 - 212501_7, 2023/11

https://doi.org/10.1103/PhysRevLett.131.212501

The cluster structure of the neutron-rich isotope Be has been probed via the () reaction. The triple differential cross-section was extracted and compared to distorted-wave impulse approximation reaction calculations performed in a microscopic framework using the Tohsaki-Horiuchi-Schuck-Rpke wave function and the wave function deduced from Antisymmetrized Molecular Dynamics calculations. The remarkable agreement between calculated and measured cross-sections in both shape and magnitude validates the description of the Be ground-state as a rather compact nuclear molecule.

High-spin structure of Cl, intruder excitations, and the - shell gap

Ionescu-Bujor, M.*; Iordachescu, A.*; Lenzi, S. M.*; Napoli, D. R.*; Mrginean, N.*; Medina, N. H.*; Bazzacco, D.*; Bucurescu, D.*; de Angelis, G.*; Della Vedova, F.*; et al.

Physical Review C, 80(3), p.034314_1 - 034314_12, 2009/09

https://doi.org/10.1103/PhysRevC.80.034314

no abstracts in English

A New design for JT-60SA Toroidal field coils conductor and joints

Zani, L.*; Pizzuto, A.*; Semeraro, L.*; Ciazynski, D.*; Cucchiaro, A.*; Decool, P.*; della Corte, A.*; Di Zenobio, A.*; Dolgetta, N.*; Duchateau, J. L.*; et al.

IEEE Transactions on Applied Superconductivity, 18(2), p.216 - 219, 2008/06

https://doi.org/10.1109/TASC.2008.921259

The upgrade of JT-60U to JT-60 Super Advanced (JT-60SA), a fully superconducting tokamak, will be performed in the framework of the Broader Approach (BA) agreement between Europe (EU) and Japan. In particular, the Toroidal Field (TF) system, which includes 18 coils, is foreseen to be procured by France, Italy and Germany. This work covers activities from design and manufacturing to shipping to Japan. The present paper is mainly devoted to the analyses that lead to the conductor design and to the technical specifications of the joints for the JT-60SA TF coils. The conductor geometry is described, which is derived from Cable-In-Conduit concept and adapted to the actual JT-60SA tokamak operating conditions, principally the ITER-like scenario. The reported simulations and calculations are particularly dealing with the stability analysis and the power deposition during normal and off-normal conditions (AC losses, nuclear heating). The final conductor solution was selected through a trade-off between scientific approach and industrial technical orientation. Besides, the TF system connections layout is shown, derived from the industrially assessed twin-box concept, together with the associated thermo-hydraulic calculations ensuring a proper temperature margin.

JT-60SA toroidal field magnet system

Pizzuto, A.*; Semeraro, L.*; Zani, L.*; Bayetti, P.*; Cucchiaro, A.*; Decool, P.*; della Corte, A.*; Di Zenobio, A.*; Dolgetta, N.*; Duchateau, J. L.*; et al.

IEEE Transactions on Applied Superconductivity, 18(2), p.505 - 508, 2008/06

https://doi.org/10.1109/TASC.2008.920827

The Broader Approach agreement between Europe and Japan includes the construction of a fully superconducting tokamak, the JT-60 Super Advanced (JT-60SA), as a satellite experiment to ITER. Toroidal field (TF) magnet which consists of 18 D-shaped coils will be provided to Japan by EU. TF coil main constituents are conductor, winding pack, joints, casing and current leads. The design criteria about conductor and structure were discussed between JA and EU adopted to fulfill the machine requirements. The results of the analyses performed by EU and JA to define and assess the TF magnet system conceptual design, are reported and commented.

Implications of NbTi short-sample test results and analysis for the ITER Poloidal Field Conductor Insert (PFCI)

Zanino, R.*; Bagnasco, M.*; Baker, W.*; Bellina, F.*; Bruzzone, P.*; della Corte, A.*; Ilyin, Y.*; Martovetsky, N.*; Mitchell, N.*; Muzzi, L.*; et al.

IEEE Transactions on Applied Superconductivity, 16(2), p.886 - 889, 2006/06

https://doi.org/10.1109/TASC.2006.873318

As the test of the PFCI is foreseen at JAERI Naka, Japan, it is essential to consider in detail the lessons learned from the short NbTi sample tests, as well as the issues left open after them, in order to develop a suitable test program of the PFCI aimed at bridging the extrapolation gap between measured strand and future PF coil performance. Here we consider in particular the following issues: (1) the actual possibility to quench the PFCI conductor in the TCS tests before quenching the intermediate joint, (2) the question of the so-called sudden or premature quench, based on SULTAN sample results, applying a recently developed multi-solid and multi-channel extension of the Mithrandir code to a short sample analysis; (3) the feasibility of the AC losses calorimetry in the PFCI. These results show that Tcs measurement and the calorimetric measurement of AC losses will be carried out successfully. However, we need further analytic works for the problem of the sudden quench.

High spin structure of S and the proton-neutron coupling of intruder states

Mason, P.*; Mrginean, N.*; Lenzi, S. M.*; Ionescu-Bujor, M.*; Della Vedova, F.*; Napoli, D. R.*; Otsuka, Takaharu*; Utsuno, Yutaka; Nowacki, F.*; Axiotis, M.*; et al.

Physical Review C, 71(1), p.014316_1 - 014316_8, 2005/01

https://doi.org/10.1103/PhysRevC.71.014316

no abstracts in English

Progress on design and R&D of ITER FW/blanket

Ioki, Kimihiro*; Akiba, Masato; Cardella, A.*; Daenner, W.*; Elio, F.*; Enoeda, Mikio; Lorenzetto, P.*; Miki, Nobuharu*; Osaki, Toshio*; Rozov, V.*; et al.

Fusion Engineering and Design, 61-62, p.399 - 405, 2002/11

https://doi.org/10.1016/S0920-3796(02)00109-6

We report progress on the ITER-FEAT Blanket design and R&D during 2001-2002. Four major sub-components (FW, shield body, flexible support and electrical connection) have been highlighted. Regarding the FW, design on a separate FW panel concept has progressed, and heat load tests on a small-scale mock-up have been successfully performed with 0.7 MW/m, 13000 cycles. Full-scale separate FW panels (dimensions: 0.90.250.07 m) have been fabricated by HIPing and brazing. Regarding the shield body, a radial flow cooling design has been developed, and full-scale partial mock-ups have been fabricated by using water-jet cutting. A separate FW panel was assembled with one the shield body mock-ups. Regarding the flexible support, mill-annealed Ti (easier fabricability) alloy has been selected, and the remote assembly has been considered in the design. In mechanical tests, the requires buckling strength and mechanical fatigue characteristics have been confirmed. Regarding the electrical connection, one-body structure design without welding joints has been developed. Mechanical fatigue tests in the 3 directions, have been carried out, and thermal fatigue tests and electrical tests in a solenoidal magnetic field have been performed. Feasibility of the design has been confirmed. Through progress on design and R&D of the blanket, cost reduction has been achieved, and feasibility of design and fabricability of the components have been confirmed.

Electron beam irradiation experiments of monoblock divertor mock-up

Sato, Kazuyoshi; Akiba, Masato; Araki, Masanori; ; ; I.Smid*; A.Cardella*; R.Duwe*; E.D.Pietro*

JAERI-M 93-058, 22 Pages, 1993/03

JAERI-M-93-058.pdf:1.23MB

no abstracts in English

An Interlaboratory comparison on EPR on tooth enamel within the WG 10 of the EURADOS group; Preliminary data analysis

Della, S. M.*; Trompier, F.*; Aboelezz, E.*; Ciesielski, B.*; D'Oca, M. C.*; Hayes, R.*; Juniewicz, M.*; Maltar-Strmecki, N.*; Marciniak, M.*; Marrale, M.*; et al.

no journal, , 

no abstracts in English