[en] Concepts for fitting and installation of the scissor keys, triangular keys, and truss keys in the ITER Toroidal Field (TF) Coil Assembly were developed and evaluated. In addition, the process of remote removal and replacement of a failed TF coil was considered. Two concepts were addressed: central solenoid installed last (Naka Option 1) and central solenoid installed first (Naka Option 2). In addition, a third concept was developed which utilized the favorable features of both concepts. A time line for installation was estimated for the Naka Option 1 concept

[en] This is a general overview pamphlet on the ITER tokamak

[en] The history of Kazakstan entry to elaborating of the ITER project is given. An industrial and scientific and research works on controlled thermonuclear synthesis carrying out in Kazakstan are described. The main executors and expenditures on scientific work of the ITER project in Kazakstan are given. The general tasks and results on ITER technical project in Kazakstan are listed. General managers of the ITER project in Kazakstan are the Kazakstan National Nuclear Centre, National Stock Company KATEP is includes kazakstani atomic energy plants, the Scientific Research Institute of Experimental and Teoretical Physics. General results on the ITER project are folowing: the experiments on the hydrogen saturation of the beryllium and grafit materials during in reactor irradiation process were carryed out; on the IVG-1 reactor the experiments on researches of the hydrogen permeability through the constructive austenitic steel during the reactor irradiation were carryed out; the variations of element composition of the beryllium sample surfaces under the interaction with hydrogen were studied by the auger spectroscopy methods and the diffusion parameters of hydrogen into beryllium were producted; the interaction parameters for hydrogen with vanadium alloy VCr6Ti5 were provided. The beryllium samples were producted in the Production Company Ulba Metallurgical Plant for the Programme under the ITER project

[en] Beginning in 1988 and continuing through 1990, the four Parties involved, under the auspices of the IAEA, have been cooperating in the ITER Conceptual Design Activities. In order to develop ways and means to comply with the objective of the cooperation, a Working Party was chartered by the Council in July, 1989. This report contains the outcome of the Working Party's effort to fulfil the Council's charge and subsequent additional guidance, which are also given in this document. 2 figs, 13 tabs

[en] A model of ITER and various other means of information on nuclear fusion were on display at the IAEA Headquarters from the 21st to 25th of September 1998

[en] One of the problems that has to be resolved during ITER work by is connected with use of beryllium as one of the materials for ITER plasma facing components (PFC). Current baseline estimate of beryllium (Be) inventory is roughly 13500 kg Be. The use of beryllium in ITER PFC demands that the designers pay serious attention to provision for safety from two points of view: 1) beryllium as toxic material should be isolated from the site personnel and the public living in the vicinity of ITER site, during all process operation and experiments at the reactor; 2) the combined use of beryllium as plasma facing material and water as coolant in ITER poses the potential risk of significant hydrogen production in accident situation. To carry out on beryllium safety a vacuum chamber with Be-copper samples and additional structures to simulate transfer from atmosphere to hot structures will be needed. The in-chamber structures should be capable to be heated up to 1000 deg C to represent accidental situation. For Be-steam samples even higher temperatures should be explored (up 1300 deg C). The plasma chamber should allow controlled steam air ingress. The reaction between air/steam and beryllium should be measured be at least two methods (e.g. weight gain and H₂ production. The pressure/temperature curve during steam/air ingress shall be measured at various location. Special attention is needed to monitor the Be surface temperature. The Be-metal samples should allow (internal) gas cooling to allow temperature control (avoid runaway reaction at elevated temperatures

[en] JET has been unable to recover historical confinement levels when operating with an ITER-like wall (ILW) due largely to the inaccessibility of high pedestal temperatures. Finding a path to overcome this challenge is of utmost importance for both a prospective JET DT campaign and for future ITER operation. Gyrokinetic simulations (using the Gene code) quantitatively capture experimental transport levels for a representative experimental discharge and qualitatively recover the major experimental trends. Microtearing turbulence is a major transport mechanisms for the low-temperature pedestals characteristic of unseeded JET-ILW discharges. At higher temperatures and/or lower ${\mathrm{\rho <!--\; ??\; -->}}_{\ast <!--\; ???\; -->}$, we identify electrostatic ITG transport of a type that is strongly shear-suppressed on smaller machines. Consistent with observations, this transport mechanism is strongly reduced by the presence of a low-Z impurity (e.g. carbon or nitrogen at the level of $Z_{\text{eff}}\sim <!--\; ???\; -->2$), recovering the accessibility of high pedestal temperatures. Notably, simulations based on dimensionless ${\mathrm{\rho <!--\; ??\; -->}}_{\ast <!--\; ???\; -->}$ scans recover historical scaling behavior except in the unique JET-ILW parameter regime where ITG turbulence becomes important. Our simulations also elucidate the observed degradation of confinement caused by gas puffing, emphasizing the important role of the density pedestal structure. This study maps out important regions of parameter space, providing insights that may point to optimal physical regimes that can enable the recovery of high pedestal temperatures on JET. (paper)

[en] Physics considerations are central to the ITER Engineering Design Activity and impact it in several ways. First, the ITER size, shape, and magnetic field strength are chosen via a judicious balance of cost, technological constraints, and extrapolation of confinement data from present tokamak experiments by a process mostly empirical in nature but constrained to obey fundamental principles of plasma physics. Present experiments indicate that resistive modes and collisionality govern the beta-limit for discharges of the ITER shape and collisionality. The resulting machine parameters yield a design that, by intent, has modest margins with respect to obtaining the desired goal of steady, controllable thermonuclear burn. Operational responses, especially driven-burn operations, exist that will likely enable ITER to fulfill its mission of 1-1.5 GW of sustained fusion power if shortfalls in projected performance occur. Second, the scale of ITER presents especially difficult challenges in the areas of divertor and disruption effects, which are generic to tokamak fusion reactors. It is the role of ITER to meet these challenges and demonstrate reliable, continuing operations of a tokamak at the reactor scale. Third, the MR design strives to accomodate a variety of advanced tokamak operations. Plasma shaping capabilities are comparable to those of ASDEX-U, the principal constraint being that of a single-null divertor. A segmented central solenoid is under consideration as a potential design improvement that could augment plasma shaping capabilities and reduce cost. Site power requirements are set by a criterion that calls for the ability to apply almost the full auxiliary heating power (70 MW out of 100 MW) while ramping up the plasma current. NBI is planned to provide plasma rotation appreciably in excess of the natural diamagnetic rotation velocity

[en] I want to discuss the role of ITER in the US MFE Program Strategy. I should stress that any opinions I present are purely my own. I'm not speaking ex cathedra, I'm not speaking for the ITER Home Team, and I'm not speaking for the Lawrence Livermore National Laboratory. I'm giving my own personal opinions. In discussing the role of ITER, we have to recognize that ITER plays several roles, and I want to identify how ITER influences MFE program strategy through each of its roles

[en] Design of ITER entails the application of physics design tools that have been validated against the world-wide data base of fusion research. In many cases, these tools do not yet exist and must be developed as part of the ITER physics program. ITER's considerable increases in power and size demand significant extrapolations from the current data base; in several cases, new physical effects are projected to dominate the behavior of the ITER plasma. This paper focuses on those design tools and data that have been identified by the ITER team and are not yet available; these needs serve as the basis for the ITER Physics Research Needs, which have been developed jointly by the ITER Physics Expert Groups and the ITER design team. Development of the tools and the supporting data base is an on-going activity that constitutes a significant opportunity for contributions to the ITER program by fusion research programs world-wide