Showing papers in "Fusion Engineering and Design in 2018"

TL;DR: The progress of the DEMO Design Activities in Europe and particularly the work done to address critical design integration issues that affect the machine configuration and performance, the plant concept layout and the selection of system design and technologies are described.

TL;DR: The main DEMO requirements are identified, the rationales for the selected architecture of the DEMO tokamak are introduced, and how the configuration of the main toKamak components has been derived is described.

TL;DR: In this article, the authors examined the FNSF as part of a two-step program from ITER to commercial power plants, where the first step is considered mandatory to establish the materials and component database in the real fusion in-service environment before proceeding to larger electricity producing facilities.

TL;DR: In this article, a Discrete Element Method (DEM) for the evaluation of the effective thermal conductivity of pebble beds in fusion blankets is presented, to the best of our knowledge, for the first time in a DEM code.

TL;DR: In this paper, a pre-conceptual design of the superconducting magnet system has been developed for the toroidal field coils (TFCs), three winding pack (WP) options have been proposed; exploring different winding approaches (pancakes vs. layers), and manufacturing techniques (react & wind vs. react Nb3Sn).

TL;DR: Sorbom et al. as mentioned in this paper extended the ARC pilot plant conceptual design study to explore options for managing ∼525 MW of fusion power generated in a compact, high field tokamak that is approximately the size of JET.

TL;DR: In this article, the thermal properties of pure Tungsten and its alloys were measured, and the effect of alloying on the thermal property of pure tungsten was investigated.

TL;DR: The strategy for the DEMO BB down selection and BB operation in DEMO is presented and the status of the design evolution of the four EU BB concepts is described, to provide an overview of the challenges of the in-vessel and ex-vessels integration of the main systems interfacing the BBs and describe their design status.

TL;DR: In this paper, the authors present the design progress of the complex system's "chain" devoted to the extraction of the plasma generated pulsed thermal power and its conversion into electricity delivered to the grid, including the Primary Heat Transport System (PHTS), the Power Conversion System (PCS), and the intermediate heat transport System (IHTS) provided by an Energy Storage System (ESS) in between PHTS and PCS, which is introduced for the scope of smoothing thegenerated pulsed plasma power removed by PHTS transmitted to PCS for a more continuous conversion/production of

TL;DR: In this article, the authors performed an update of the screening for tritium breeder and neutron multiplier materials and to assess the trittium breeding performance of the selected compounds in order to reveal new options.

TL;DR: C-Model has been significantly improved with respect to C-lite in terms of specific system model design status and level of detail, focused on in-vessel and vessel components.

TL;DR: In this paper, the shape of the ITER divertor vertical targets has been refined as a consequence of manufacturing and engineering considerations during the prototype manufacturing activities and the reduction of W monoblock armour thickness to 6.5mm has been discussed.

TL;DR: This study provides an up to date account of future tritium availability by incorporating recent uncertainties over the life extension of the global CANDU fleet, as well as considering the potential impact oftritium demand by other fusion efforts.

TL;DR: Options for structural and plasma-facing materials are considered and a preliminary set of materials identified to meet the challenges of power core components and for the machine-lifetime components such as the vacuum vessel and the structural ring.

TL;DR: In this paper, 3D field-line tracing codes have been used to analyze the maximum heat flux and energy density for a specific first wall shape design, and optimize it using a broad range of transient input heat fluxes, on a series of high heat flux components concepts with tungsten armor, Eurofer steel or copper alloy as heat sink materials, and helium or water as coolant.

TL;DR: The JET tokamak with beryllium and tungsten ITER-like wall provides unique opportunity for detailed studies on dust generation: quantity, morphology, location, etc as discussed by the authors.

TL;DR: In this paper, a thermal-hydraulic model of the main components of the water cooled primary heat transfer system is developed, using RELAP5 system code, to support the design and sizing.

TL;DR: In this article, the current status of the DEMO conceptual design activity is presented, which is mainly focused on challenging DEMO design issues such as divertor heat removal, superconducting magnets, breeding blankets, remote maintenance and the water cooling system, in order to reach the systemic consistency toward a promising DEMO concept.

TL;DR: In this article, the main features of the various TBSs sub-systems, in particular, the cooling systems (helium, water and/or lithium-lead), the tritium system for extracting the tritium from the breeder, the coolant purification system, the Tritium accountancy system, and several instrumentation & control systems.

TL;DR: The negative ion source test facility ELISE represents an important step in the European R&D roadmap for the neutral beam injection (NBI) systems of ITER as discussed by the authors, which can extract and accelerate H− and D− beams up to 60'kV for short plasma pulses (10's) every ∼150's out of the continuously operating plasma source.

TL;DR: The content and format of the material property handbook currently counting over 20 DEMO design relevant material properties on baseline steel EUROFER97 is summarized and discussed on the base of selected examples.

TL;DR: Based on the first principles calculations, the effect of Mo alloying on the mechanical properties of W-Mo alloys was investigated in this article, where the lattice constants, the cell volumes and the formation energies of W1-xMox (x = 0, 0.0625,0.125, 0., 0.25, 0, 5, 0; 0.75, 0, 0.125; 0, 1.75; 0., 1.9375) alloys were calculated.

TL;DR: In this article, a detailed three-dimensional MCNP model of the latest WCLL layout has been generated and integrated in a DEMO MCNP generic model suitably designed for neutronic analyses, which highlights the potential and suitability of the WCLL breeding blanket for the application to DEMO, both in terms of tritium production and shielding performances.

TL;DR: The most important details of the proposed DCLL blanket design are summarized, the MHD thermohydraulic analysis for the PbLi flows in the blanket conduits are presented and the required pre-FNSF R&D in the area of MHD Thermofluids is discussed to support the further work on the DCLL blankets design & analysis and its integration into the fusion facility.

TL;DR: A procedure for fabricating explosion bonded TU1/316 L clad plates was successfully determined through the combination of numerical calculations and experiments, and the bimetallic plates were used to manufacture international thermonuclear experimental reactor (ITER) components as discussed by the authors.

TL;DR: In this paper, Lifshitz theory is employed for the calculation of the non-retarded Hamaker constants of ten common dust-wall material combinations, including graphite-on-graphite, tungstenon-tungsten and even beryllium-onberyllium.

TL;DR: In this paper, a model-based approach to real-time reconstruction of the particle density profile in tokamak plasmas is presented, based on a dynamic state estimator.

TL;DR: In this paper, a W-10Cr alloy with hafnium oxide particle dispersion was prepared by spark plasma sintering, and the phase and thermal stability of the alloy was evaluated at three fusion-relevant temperatures using detailed X-ray diffraction analysis, differential thermal analysis and microstructural observations in a scanning electron microscope.

TL;DR: In this paper, a 3 mm-thickness of pure copper claddings was developed using laser cladding process on an in-vessel component material (SS316L), which was characterized by X-ray diffraction (XRD) and Xray radiography analysis.

TL;DR: A new HCLL BB concept that has been designed in order to improve Tritium Breeding Ratio (TBR) and shielding performances is presented, and a new Back Supporting Structure (BSS) is presented in this paper, designed to support the BB modules, with the aim to reduce pressure drops and thermal stresses.