4.5 Article

Integrated design strategy for EU-DEMO first wall protection from plasma transients

相关参考文献

注意:仅列出部分参考文献,下载原文获取全部文献信息。
Article Nuclear Science & Technology

Containment structures and port configurations

C. Bachmann et al.

Summary: This article provides an overview of the DEMO cryostat, vacuum vessel, and tokamak building, as well as the integration of in-vessel components and auxiliary systems. The vacuum vessel is crucial for radiation shielding and containment of radioactive material. The cryostat facilitates the operation of superconducting coils in a vacuum environment. The tokamak building layout is designed to align with the vacuum vessel ports, allowing for secondary confinement during in-vessel maintenance.

FUSION ENGINEERING AND DESIGN (2022)

Article Physics, Fluids & Plasmas

Inter-machine plasma perturbation studies in EU-DEMO-relevant scenarios: lessons learnt for prediction of EM forces during VDEs

G. Sias et al.

Summary: This study focuses on predictive simulations of the final plasma position and electromagnetic (EM) loads following a Vertical Displacement Event (VDE) in DEMO limiter structures, aiming to understand the effects of transient plasma perturbations on the vertical stability system control.

NUCLEAR FUSION (2022)

Article Physics, Fluids & Plasmas

Development and testing of an additively manufactured lattice for DEMO limiters

N. Mantel et al.

Summary: This paper presents the first investigations into lattice structures fabricated with tungsten powder for use as limiters in the conceptual design of EU-DEMO. The results show that these lattice structures have similar heat absorption to solid tungsten, suggesting they may be suitable for limiter applications with the added advantage of adjusting heat transfer and stiffness performance through geometry design or material properties.

NUCLEAR FUSION (2022)

Article Nuclear Science & Technology

Parametric study of the radiative load distribution on the EU-DEMO first wall due to SPI-mitigated disruptions

M. Moscheni et al.

Summary: Shattered Pellet Injection (SPI) is an effective technique to mitigate plasma disruptions by enhancing isotropic radiation emission and reducing heat load. The depth of penetration of shattered pellets significantly affects the radiative heat load on in-vessel structures following a disruption event mitigated via SPI.

FUSION ENGINEERING AND DESIGN (2021)

Article Nuclear Science & Technology

Experimental results of multiple shattered pellet injection systems in KSTAR

SooHwan Park et al.

Summary: Shattered pellet injection (SPI) technology is chosen for the ITER Disruption Mitigation System, with experiments needing to be conducted with two identical injectors installed on the device to demonstrate feasibility.

FUSION ENGINEERING AND DESIGN (2021)

Article Nuclear Science & Technology

Poloidal distribution of penalty factors for DEMO Single Module Segment with limiters in normal operation

M. L. Richiusa et al.

Summary: The DEMO device requires protection for the first wall in plasma scenarios to avoid damage caused by energy deposition. New design improvements offer better protection, with limiter strategy showing promising results.

FUSION ENGINEERING AND DESIGN (2021)

Article Nuclear Science & Technology

Impact of plasma-wall interaction and exhaust on the EU-DEMO design

F. Maviglia et al.

Summary: This work reviews the role of plasma facing components protection in driving the EU-DEMO design, focusing on both steady-state and transient situations. Different protection limiters are implemented to reduce heat load on the first wall and divertor, while alternative divertor configurations are under investigation to mitigate risks during various plasma transients.

NUCLEAR MATERIALS AND ENERGY (2021)

Article Nuclear Science & Technology

DEMO tritium breeding performances with different in-vessel components configurations

Pavel Pereslavtsev et al.

Summary: This study presents a global examination of the tritium breeding performances in DEMO for two different blanket concepts, HCPB and WCLL, showing that the installation of all currently considered limiters and auxiliary systems leads to a decrease in TBR values. The required TBR values may vary depending on the integration of limiters and auxiliary systems, with a potential impact on the project's TBR target range.

FUSION ENGINEERING AND DESIGN (2021)

Article Nuclear Science & Technology

Using MAXFEA code in combination with ANSYS APDL for the simulation of plasma disruption events on EU DEMO

R. Lombroni et al.

Summary: Plasma disruptions are a major concern in fusion device design due to the high eddy and Halo currents induced in passive structures. The Vertical Displacement Event starts with loss of position control, followed by a fast Thermal Quench and Current Quench. The impacts of these events on passive structures can be estimated using 2D axisymmetric codes like MAXFEA.

FUSION ENGINEERING AND DESIGN (2021)

Article Nuclear Science & Technology

Key design integration issues addressed in the EU DEMO pre -concept design phase

C. Bachmann et al.

FUSION ENGINEERING AND DESIGN (2020)

Article Nuclear Science & Technology

Simulation of the first wall shielding during upward VDE in DEMO

Sergey Pestchanyi et al.

NUCLEAR MATERIALS AND ENERGY (2020)

Article Nuclear Science & Technology

The EU DEMO equatorial outboard limiter - Design and port integration concept

Thomas Franke et al.

FUSION ENGINEERING AND DESIGN (2020)

Article Nuclear Science & Technology

European DEMO first wall shaping and limiters design and analysis status

Z. Vizvary et al.

FUSION ENGINEERING AND DESIGN (2020)

Article Nuclear Science & Technology

Impact of plasma thermal transients on the design of the EU DEMO first wall protection

Francesco Maviglia et al.

FUSION ENGINEERING AND DESIGN (2020)

Article Nuclear Science & Technology

Initial configuration studies of the upper vertical port of the European DEMO

Christian Vorpahl et al.

FUSION ENGINEERING AND DESIGN (2019)

Article Nuclear Science & Technology

DEMO First Wall misalignment study

Z. Vizvary et al.

FUSION ENGINEERING AND DESIGN (2019)

Article Nuclear Science & Technology

Simulation of the Divertor Target Shielding During Major Disruption in DEMO

Sergey Pestchanyi et al.

FUSION SCIENCE AND TECHNOLOGY (2019)

Article Nuclear Science & Technology

Simplified heat load modeling for design of DEMO discrete limiter

J. Gerardin et al.

NUCLEAR MATERIALS AND ENERGY (2019)

Article Nuclear Science & Technology

Physics basis for the first ITER tungsten divertor

R. A. Pitts et al.

NUCLEAR MATERIALS AND ENERGY (2019)

Article Nuclear Science & Technology

Wall protection strategies for DEMO plasma transients

F. Maviglia et al.

FUSION ENGINEERING AND DESIGN (2018)

Article Nuclear Science & Technology

Methodological approach for DEMO neutronics in the European PPPT programme: Tools, data and analyses

U. Fischer et al.

FUSION ENGINEERING AND DESIGN (2017)

Article Nuclear Science & Technology

Neutronic analyses for the optimization of the advanced HCPB breeder blanket design for DEMO

Pavel Pereslavtsev et al.

FUSION ENGINEERING AND DESIGN (2017)

Article Nuclear Science & Technology

Choice of a low operating temperature for the DEMO EUROFER97 divertor cassette

Giuseppe Mazzone et al.

FUSION ENGINEERING AND DESIGN (2017)

Article Nuclear Science & Technology

Validation of TOKES vapor shield simulations against experiments in the 2MK-200 facility

S. Pestchanyi et al.

FUSION ENGINEERING AND DESIGN (2017)

Article Physics, Fluids & Plasmas

The DEMO wall load challenge

R. Wenninger et al.

NUCLEAR FUSION (2017)

Article Nuclear Science & Technology

Conceptual design studies for the European DEMO divertor: Rationale and first results

J. H. You et al.

FUSION ENGINEERING AND DESIGN (2016)

Article Physics, Fluids & Plasmas

Presentation of the New SOLPS-ITER Code Package for Tokamak Plasma Edge Modelling

Xavier Bonnin et al.

PLASMA AND FUSION RESEARCH (2016)

Article Nuclear Science & Technology

Global shutdown dose rate maps for a DEMO conceptual design

D. Leichtle et al.

FUSION ENGINEERING AND DESIGN (2015)

Article Physics, Fluids & Plasmas

The SMARDDA Approach to Ray Tracing and Particle Tracking

Wayne Arter et al.

IEEE TRANSACTIONS ON PLASMA SCIENCE (2015)

Article Physics, Fluids & Plasmas

Characterization of scrape-off layer transport in JET limiter plasmas

C. Silva et al.

NUCLEAR FUSION (2014)

Article Physics, Fluids & Plasmas

The ITER blanket system design challenge

A. R. Raffray et al.

NUCLEAR FUSION (2014)

Article Nuclear Science & Technology

Radiation loads on the ITER first wall during massive gas injection

I. Landman et al.

FUSION ENGINEERING AND DESIGN (2013)

Article Nuclear Science & Technology

The design of the ITER first wall panels

R. Mitteau et al.

FUSION ENGINEERING AND DESIGN (2013)

Article Materials Science, Multidisciplinary

Modelling of power deposition on the JET ITER like wall using the code PFCFLux

M. Firdaouss et al.

JOURNAL OF NUCLEAR MATERIALS (2013)

Article Materials Science, Multidisciplinary

Physics basis and design of the ITER plasma-facing components

R. A. Pitts et al.

JOURNAL OF NUCLEAR MATERIALS (2011)

Article Materials Science, Multidisciplinary

Analysis for shaping the ITER first wall

P. C. Stangeby et al.

JOURNAL OF NUCLEAR MATERIALS (2009)

Article Physics, Fluids & Plasmas

3D edge transport analysis of ITER start-up configuration for limiter power load assessment

M. Kobayashi et al.

NUCLEAR FUSION (2007)