Experimental Facility to Study MHD effects at Very High Hartmann and Interaction parameters related to Indian Test Blanket Module for ITER

Size: px
Start display at page:

Download "Experimental Facility to Study MHD effects at Very High Hartmann and Interaction parameters related to Indian Test Blanket Module for ITER"

Transcription

1 Experimental Facility to Study MHD effects at Very High Hartmann and Interaction parameters related to Indian Test Blanket Module for ITER P. Satyamurthy Bhabha Atomic Research Centre, India P. Satyamurthy, December 21-23, 2009, IITK

2 Team members P. Satyamurthy, P. K. Swain, D. Kumar, K. Kulkarni, S. Kumar, D. N. Badodkar and L. M. Gantayet Bhabha Atomic Research Centre, Mumbai E. Rajendra Kumar, R. Bhattacharyay and G. Vadolia Institute of Plasma Research, Gandhi Nagar, Ahmedabad P. Satyamurthy, December 21-23, 2009, IITK

3 Fusion Energy Lecture Contents ITER (International Thermo-nuclear Experimental reactor) Indian TBM Experimental and Theoretical programme for development of Indian TBM P. Satyamurthy, December 21-23,2009, IITK

4 Origin of Nuclear Fusion Energy Deuterium 17.6 MeV Neutron 80% of energy release (14.1 MeV) Used to breed tritium and close the DT fuel cycle Li + n T + He Tritium Helium 20% of energy release (3.5 MeV) Illustration from DOE brochure Deuterium and tritium is the easiest, attainable at lower plasma temperature, because it has the largest reaction rate and high Q value and hence the program is focused on the D-T Cycle P. Satyamurthy, December 21-23, 2009, IITK Ref: Prof. Abdou, UCLA

5 Advantages of Fusion Energy Sustainable energy source No emission of Greenhouse or other polluting gases No risk of a severe accident No long-lived radioactive waste Fusion energy can be used to produce electricity, hydrogen and for desalination.

6 Technology Issues in Fusion Energy Requires High temperatures (Millions of degrees) in a pure High Vacuum environment are required Technically complex and high capital cost reactors are necessary Still in R&D Stage

7 Fuel Cycle for Fusion Energy Deuterium from water (0.02% of all hydrogen is deuterium) Tritium from lithium (a light metal common in the Earth s crust)

8 Tritium Breeding 6 Li (n,α) t Natural lithium: 7.42% 6 Li and 92.58% 7 Li Required: 90% 6 Li and 10% 7 Li 7 Li (n;n α) t P. Satyamurthy, December 21-23, 2009-ITK

9 Neutron Multipliers for Fusion Energy Growth Desired characteristics: Small absorption crosssections Large (n, 2n) crosssection with low threshold Candidates - Beryllium, Lead Candidates: Beryllium is the best (large n, 2n with low threshold, low absorption) 9 Be (n, 2n) Pb (n,2n) Pb is most effective in Li-Pb eutectic P. Satyamurthy December 21-23, 2009-IITK

10 ITER Objectives Demonstrate the scientific and technological feasibility of fusion energy Demonstrate extended burn of DT plasmas, with steady state as the ultimate goal Integrate and test all essential fusion power reactor technologies and components Demonstrate safety and environmental acceptability of fusion. P. Satyamurthy, December 21-23,2009-IITK

11 THE ITER DEVICE International Thermonuclear Experimental Reactor Parameters Total Fusion Power Q- Fusion Power /Auxiliary heating power 500 MW 10 Average Neutron wall loading 0.57 MW/m 2 Plasma Major Radius Plasma minor Radius Plasma Current Toroidal Field at major radius 6.2 m 2.0 m 15 MA 5.3 tesla Plasma Volume 837 m 3 Height: 25 m, Diameter: 28 m Neutrons Generated 1.5 x n/s 11

12 Typical DEMO Reactor 12

13 Major Sub-systems of ITER Shield Blanket Vacuum vessel Radiation Plasma Neutrons First Wall Tritium breeding zone Coolant for energy conversion Magnets P. Satyamurthy, December 21-23, IITK

14 BLANKET Functions Tritium Breeding High grade heat extraction Radiation Shielding 14

15 ITER is a collaborative effort among Europe, Japan, US, Russia, China, South Korea, and India

16 ITER Location- Caradache (France)

17 Typical ITER-TBM (proposed by US) 3 ITER equatorial ports (1.75 x 2.2 m 2 ) for TBM testing Bio-shield He pipes to TCWS Each port can accommodate only 2 modules (i.e. 6 TBMs max) Typical TBM System 2.2 m A PbLi loop Transporter located in the Port Cell Area Vacuum Vessel TBM System ( Heat Extraction from Neutrons & First wall radiation + T Breeding) P. Satyamurthy, December 21-23,2009-IITK

18 Indian TBM System 18

19 Indian Lead-Lithium cooled Ceramic Breeder (LLCB) TBM First wall Top-bottom plate assembly Breeder assembly Inner back plate Outer back plate Manifolds and pipes Flexible housings and support keys Poloidal 1660 mm Toroidal 480 mm Radial 536 mm

20 Details of Indian TBM P. Satyamurthy, December 21-23, IITK

21 Flow Configuration Indian LLCB TBM

22 LLCB DEMO / TBM Design Parameters Dimensions Plasma Facing Material ~1.7(P) x 1.0 (T) x 0.5(R) m (DEMO) ~ 1.7(P) x 0.5(T) x 0.5(R) m (TBM) Be coating (~2 mm) Structural material RAFMS Breeder PbLi, Li 2 TiO 3 Neutron Wall Loading Total Power Deposition 2.42 MW/m 2 (0.78MW/m 2 ) 2.24 MW (0.857 MW) Average. Heat Flux 0.5 MW/m 2 Primary Coolant PbLi and Helium P. Satyamurthy, December 21-23, 2009-IITK

23 MHD Effects in TBM P. Satyamurthy, December 21-23, 2009, IITK

24 The Liquid Metal MHD in TBM Flow across the magnetic field induces current J in the fluid volume. This current interacts with the magnetic field to produce opposing Lorentz force (JxB o ) The current also produces induced magnetic field along x Due to All these effects: 1) Additional pressure drop 2) Flow modifications 2) Additional joule heating 3) Turbulent suppression or 4)Hartman effects can make the flow 2-D turbulent X- flow direction Y-Induced current Z- Applied Magnetic Field Walls perpendicular to B-Hartmann walls Walls parallel to B side walla

25 Equations Governing Flow in TBM 3-D MHD-CFD code is being developed 1) ANUPRAVAHA IIT-BARC Code (Prof. Eswaran,IITK) 2) M/s Fluidyne (Bangaluru)

26 Non-dimensional Parameters in MHD flow Interaction Parameter-Ratio of magnetic body force to inertial force Magnetic Reynolds number-ratio of induced magnetic field to applied field Hartmann Number Ratio of Magnetic body force to Viscous force This ratio decides the flow structure 3-D turbulence or 2-D turbulence or Laminar

27 Hartmann-effect Increasing Hartmann Number P. Satyamurthy, December 21-23,2009-IITK

28 MHD effects- M profiles Across Side walls σ s i d e = 0, σ HWall = σ s i d e =, σ HWall = u average = m/s

29 Effect of transverse B variation - Transition to M- Profile (strong function of N) -Generation of additional currents P. Satyamurthy, December 21-23,2009-IITK

30 Effects of MHD on Turbulence Non uniform Suppression of Turbulence -2D turbulence Introduction of Turbulent Anisotropy This has a bearing on: Pressure drop in the module Heat Transfer

31 MHD Effects on Turbulence

32 2-D MHD Turbulence Ref: Smolentsev et al Vorticity Distribution-Ha/ Re>>1/300

33 Combined Forced & Natural Convection - Buoyancy Effects + Suitable Turbulent Model

34 Flow complexity in TBM Flow - U bend U y U x U y B z Toroidal Flow U y -Downwords Flow U y - Upwards Poloidal- y Toroidal-z Flow -L bend Radial-x U x U y L-bend Under Developed Flow - Transient Region U x, Geometry change

35 Experimental Programme to Study MHD Phenomena in TBM

36 Properties Similarities of Pb-Li, Hg and Pb-Bi liquid metals Pb-Li (300 0 C) Hg (50 0 C) Pb-Bi Density kg/m Electrical Conductivity mho/m 0.77x x10 6 ~1.0x10 6 Viscosity m 2 /s 0.188x x x10-6 Thermal conductivity W/mK Pr C p J/kg-K

37 TBM Mercury-TBM B ~4T ~ T Ha ~18500 ~6000 Re ~ 50,000 ~24500 N ~ 6700 ~1200 Ha/Re ~0.36 ~0.22 B = 4T Pb 83%-Li -17% (enriched 90% of Li 6 ) T i = C, v =0.1m/s Actual TBM Scale down Mercury TBM

38 Proposed Mercury facility for MHD studies (Ha ~6000, N ~2000, Re ~15,000) Coil Cooling tower water supply in. HX Pump Control Valve Flow meter Magnet~2 T Mercury- TBM BGV Dump Tank

39 Major components of the MHD-TBM Simulation Facility MHD-TBM Mercury 1.5 tons Magnet - ~2.0T electro magnet Dump Tank Heat Exchanger Mercury-Water Pump -Vertical Cantilever Centrifugal pump Embedded Heaters in the walls to simulate solid breeder heat Diagnostics Primary coolant circuit Water Thermal Insulation Control & Instrumentation Power supplies and Utilities Motor for magnet movement Safety related instrumentation

40 Simulation of Nuclear Heat and Solid Breeder Heat Generation in Mercury-TBM Heat deposition area of LLCB TBM (m 2 ) First wall Top & Bottom wall Right & Left wall First Solid Breeder Second Solid breeder Third Solid Breeder Heat generation in LLCB TBM Walls (kw) Surface heat flux (kw/m 2 ) Heat to be supplied in Mercury TBM for heat flux simulation (kw) 59 ~ 43 ~ ~ 2.8 (for each wall) ~ 5.1 (for each wall) ~ ~ ~ 2.0

41 Diagnostics in the Mercury-TBM Ports: Thermocouple in Hg (1) :58 no.s Thermocouple in wall (2) : 46 no.s Velocity Profile meter : 08 no.s Pressure :08 no.s Potential pins in Wall :181 no.s

42 Process details of the Facility

43 Current Status of the Facility Basic and Process design is complete Civil works are in progress Sizing and specifications of most of the components are completed Vendor for detailed mechanical design of the TBM has been finalised Instrument and diagnostic equipment procurement has started Expecting the facility to be ready by early 2011

44 Conclusions India is proposing an LLCB - TBM for ITER MHD effects dominate the thermal-hydraulics of TBM (Ha ~18500, N~6700, Ha/Re ~ 0.36) For Successful design of TBM many MHD issues are needed to be understood An Experimental facility based on Mercury is being setup to under stand and address these issues In addition MHD-CFD code suitable for TBM design is being developed

45 Thank You

Role and Challenges of Fusion Nuclear Science and Technology (FNST) toward DEMO

Role and Challenges of Fusion Nuclear Science and Technology (FNST) toward DEMO Role and Challenges of Fusion Nuclear Science and Technology (FNST) toward DEMO Mohamed Abdou Distinguished Professor of Engineering and Applied Science (UCLA) Director, Center for Energy Science & Technology

More information

Perspective on Fusion Energy

Perspective on Fusion Energy Perspective on Fusion Energy Mohamed Abdou Distinguished Professor of Engineering and Applied Science (UCLA) Director, Center for Energy Science & Technology (UCLA) President, Council of Energy Research

More information

Design optimization of first wall and breeder unit module size for the Indian HCCB blanket module

Design optimization of first wall and breeder unit module size for the Indian HCCB blanket module 2018 Hefei Institutes of Physical Science, Chinese Academy of Sciences and IOP Publishing Printed in China and the UK Plasma Science and Technology (11pp) https://doi.org/10.1088/2058-6272/aab54a Design

More information

Fusion: The Ultimate Energy Source for the 21 st Century and Beyond

Fusion: The Ultimate Energy Source for the 21 st Century and Beyond Fusion: The Ultimate Energy Source for the 21 st Century and Beyond Mohamed Abdou Distinguished Professor of Engineering and Applied Science (UCLA) Director, Center for Energy Science & Technology (UCLA)

More information

The Path to Fusion Energy creating a star on earth. S. Prager Princeton Plasma Physics Laboratory

The Path to Fusion Energy creating a star on earth. S. Prager Princeton Plasma Physics Laboratory The Path to Fusion Energy creating a star on earth S. Prager Princeton Plasma Physics Laboratory The need for fusion energy is strong and enduring Carbon production (Gton) And the need is time urgent Goal

More information

Concept of Multi-function Fusion Reactor

Concept of Multi-function Fusion Reactor Concept of Multi-function Fusion Reactor Presented by Songtao Wu Institute of Plasma Physics, Chinese Academy of Sciences, P.O. Box 1126, Hefei, Anhui, 230031, P.R. China 1. Motivation 2. MFFR Concept

More information

Validation Of COMSOL Multiphysics For Magneto-hydro-dynamics (MHD) Flows In Fusion Applications

Validation Of COMSOL Multiphysics For Magneto-hydro-dynamics (MHD) Flows In Fusion Applications Validation Of COMSOL Multiphysics For Magneto-hydro-dynamics (MHD) Flows In Fusion Applications Yi Yan (yiyan@fusion.ucla.edu) Fusion Science and Technology Center, UCLA October 05, 2017 1 Introduction

More information

Physics of fusion power. Lecture 14: Anomalous transport / ITER

Physics of fusion power. Lecture 14: Anomalous transport / ITER Physics of fusion power Lecture 14: Anomalous transport / ITER Thursday.. Guest lecturer and international celebrity Dr. D. Gericke will give an overview of inertial confinement fusion.. Instabilities

More information

Toward the Realization of Fusion Energy

Toward the Realization of Fusion Energy Toward the Realization of Fusion Energy Nuclear fusion is the energy source of the sun and stars, in which light atomic nuclei fuse together, releasing a large amount of energy. Fusion power can be generated

More information

Magnetic Confinement Fusion-Status and Challenges

Magnetic Confinement Fusion-Status and Challenges Chalmers energy conference 2012 Magnetic Confinement Fusion-Status and Challenges F. Wagner Max-Planck-Institute for Plasma Physics, Greifswald Germany, EURATOM Association RLPAT St. Petersburg Polytechnic

More information

VERIFICATION TEST OF A THREE-SURFACE-MULTI-LAYERED CHANNEL TO REDUCE MHD PRESSURE DROP

VERIFICATION TEST OF A THREE-SURFACE-MULTI-LAYERED CHANNEL TO REDUCE MHD PRESSURE DROP NTHAS8: The Eighth Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety Beppu, Japan, December 9-12, 212 Paper Number N8P189 VERIFICATION TEST OF A THREE-SURFACE-MULTI-LAYERED CHANNEL TO REDUCE

More information

STABILITY ANALYSIS FOR BUOYANCY-OPPOSED FLOWS IN POLOIDAL DUCTS OF THE DCLL BLANKET. N. Vetcha, S. Smolentsev and M. Abdou

STABILITY ANALYSIS FOR BUOYANCY-OPPOSED FLOWS IN POLOIDAL DUCTS OF THE DCLL BLANKET. N. Vetcha, S. Smolentsev and M. Abdou STABILITY ANALYSIS FOR BUOYANCY-OPPOSED FLOWS IN POLOIDAL DUCTS OF THE DCLL BLANKET N. Vetcha S. Smolentsev and M. Abdou Fusion Science and Technology Center at University of California Los Angeles CA

More information

THERMAL ANALYSIS OF A SOLID BREEDER TBM UNDER ITER OPERATIONAL CONDITIONS. A. Abou-Sena, A. Ying, M. Youssef, M. Abdou

THERMAL ANALYSIS OF A SOLID BREEDER TBM UNDER ITER OPERATIONAL CONDITIONS. A. Abou-Sena, A. Ying, M. Youssef, M. Abdou THERMAL AALYSIS OF A SOLID BREEDER TBM UDER ITER OPERATIOAL CODITIOS A. Abou-Sena, A. Ying, M. Youssef, M. Abdou Mechanical and Aerospace Engineering Dep., UCLA, Los Angeles, CA 90095 aliabousena@engineering.ucla.edu

More information

Tritium Safety of Russian Test Blanket Module

Tritium Safety of Russian Test Blanket Module Tritium Safety of Russian Test Blanket Module V.K. Kapyshev, V.G. Kovalenko, Y.S. Strebkov N.A. Dollezhal Research and Development Institute of Power Engineering, PO Box 788, Moscow 101000, Russia Abstract

More information

Design concept of near term DEMO reactor with high temperature blanket

Design concept of near term DEMO reactor with high temperature blanket Design concept of near term DEMO reactor with high temperature blanket Japan-US Workshop on Fusion Power Plants and Related Advanced Technologies March 16-18, 2009 Tokyo Univ. Mai Ichinose, Yasushi Yamamoto

More information

Basics of breeding blanket technology

Basics of breeding blanket technology Basics of breeding blanket technology Dr Fabio CISMONDI Karlsruher Institut für Technologie (KIT) Institut für Neutronenphysik und Reaktortechnik e-mail: fabio.cismondi@kit.edu www.kit.edu Development

More information

EU PPCS Models C & D Conceptual Design

EU PPCS Models C & D Conceptual Design Institut für Materialforschung III EU PPCS Models C & D Conceptual Design Presented by P. Norajitra, FZK 1 PPCS Design Studies Strategy definition [D. Maisonnier] 2 models with limited extrapolations Model

More information

Tritium Transport Modelling: first achievements on ITER Test Blanket Systems simulation and perspectives for DEMO Breeding Blanket

Tritium Transport Modelling: first achievements on ITER Test Blanket Systems simulation and perspectives for DEMO Breeding Blanket Tritium Transport Modelling: first achievements on ITER Test Blanket Systems simulation and perspectives for DEMO Breeding Blanket I. Ricapito 1), P. Calderoni 1), A. Ibarra 2), C. Moreno 2), Y. Poitevin

More information

ELECTROMAGNETIC LIQUID METAL WALL PHENOMENA

ELECTROMAGNETIC LIQUID METAL WALL PHENOMENA ELECTROMAGNETIC LIQUID METAL WALL PHENOMENA BY BOB WOOLLEY 15-19 FEBRUARY 1999 APEX-6 MEETING LIQUID WALLS A sufficiently thick, flowing, liquid first wall and tritium breeding blanket which almost completely

More information

Adaptation of Pb-Bi Cooled, Metal Fuel Subcritical Reactor for Use with a Tokamak Fusion Neutron Source

Adaptation of Pb-Bi Cooled, Metal Fuel Subcritical Reactor for Use with a Tokamak Fusion Neutron Source Adaptation of Pb-Bi Cooled, Metal Fuel Subcritical Reactor for Use with a Tokamak Fusion Neutron Source E. Hoffman, W. Stacey, G. Kessler, D. Ulevich, J. Mandrekas, A. Mauer, C. Kirby, D. Stopp, J. Noble

More information

Elements of Strategy on Modelling Activities in the area of Test Blanket Systems

Elements of Strategy on Modelling Activities in the area of Test Blanket Systems Elements of Strategy on Modelling Activities in the area of Test Blanket Systems I. Ricapito, TBM & MD Project Team, ITER Department, F4E, Barcelona (Spain) Barcelona, Sept 17 th 2014 Information Day FPA-611

More information

ARIES-AT Blanket and Divertor Design (The Final Stretch)

ARIES-AT Blanket and Divertor Design (The Final Stretch) ARIES-AT Blanket and Divertor Design (The Final Stretch) The ARIES Team Presented by A. René Raffray and Xueren Wang ARIES Project Meeting University of Wisconsin, Madison June 19-21, 2000 Presentation

More information

CFD simulation of the magnetohydrodynamic flow inside the WCLL breeding blanket module

CFD simulation of the magnetohydrodynamic flow inside the WCLL breeding blanket module EUROFUSION WPBB-CP(16) 15530 A. Tassone et al. CFD simulation of the magnetohydrodynamic flow inside the WCLL breeding blanket module Preprint of Paper to be submitted for publication in Proceedings of

More information

Neutronic Activation Analysis for ITER Fusion Reactor

Neutronic Activation Analysis for ITER Fusion Reactor Neutronic Activation Analysis for ITER Fusion Reactor Barbara Caiffi 100 Congresso Nazionale SIF 1 Outlook Nuclear Fusion International Thermonuclear Experimental Reactor (ITER) Neutronics Computational

More information

MHD Analysis of Dual Coolant Pb-17Li Blanket for ARIES-CS

MHD Analysis of Dual Coolant Pb-17Li Blanket for ARIES-CS MHD Analysis of Dual Coolant Pb-17Li Blanket for ARIES-CS C. Mistrangelo 1, A. R. Raffray 2, and the ARIES Team 1 Forschungszentrum Karlsruhe, 7621 Karlsruhe, Germany, mistrangelo@iket.fzk.de 2 University

More information

INTRODUCTION TO MAGNETIC NUCLEAR FUSION

INTRODUCTION TO MAGNETIC NUCLEAR FUSION INTRODUCTION TO MAGNETIC NUCLEAR FUSION S.E. Sharapov Euratom/CCFE Fusion Association, Culham Science Centre, Abingdon, Oxfordshire OX14 3DB, UK With acknowledgments to B.Alper for use of his transparencies

More information

School on Physics, Technology and Applications of Accelerator Driven Systems (ADS) November 2007

School on Physics, Technology and Applications of Accelerator Driven Systems (ADS) November 2007 1858-36 School on Physics, Technology and Applications of Accelerator Driven Systems (ADS) 19-30 November 2007 Thermal Hydraulics of Heavy Liquid Metal Target for ADS. Part I Polepalle SATYAMURTHY BARC

More information

Conceptual Design of Advanced Blanket Using Liquid Li-Pb

Conceptual Design of Advanced Blanket Using Liquid Li-Pb Japan- US workshop on Fusion Power Plants and related advanced technologies with participation of EU February 5-7, 2007 at Kyoto, Japan Conceptual Design of Advanced Blanket Using Liquid Li-Pb Y. Yamamoto,

More information

CALIBRATION OF MHD FLOWMETER USING COMSOL SOFTWARE. Institute for Plasma Research Bhat, Gandhinagar, India

CALIBRATION OF MHD FLOWMETER USING COMSOL SOFTWARE. Institute for Plasma Research Bhat, Gandhinagar, India CALIBRATION OF MHD FLOWMETER USING COMSOL SOFTWARE By Srikanta Sahu Institute for Plasma Research Bhat, Gandhinagar, India OUTLINE Introduction Flow meter description Usage of COMSOL Results Velocity Profile

More information

FLOW ANALYSIS IN THE HCLL-TBM ITER CHANNELS INCLUDING MHD AND HEAT TRANSFER

FLOW ANALYSIS IN THE HCLL-TBM ITER CHANNELS INCLUDING MHD AND HEAT TRANSFER V European Conference on Computational Fluid Dynamics ECCOMAS CFD 2010 J. C. F. Pereira and A. Sequeira (Eds) Lisbon, Portugal,14-17 June 2010 FLOW ANALYSIS IN THE HCLL-TBM ITER CHANNELS INCLUDING MHD

More information

Possibilities for Long Pulse Ignited Tokamak Experiments Using Resistive Magnets

Possibilities for Long Pulse Ignited Tokamak Experiments Using Resistive Magnets PFC/JA-91-5 Possibilities for Long Pulse Ignited Tokamak Experiments Using Resistive Magnets E. A. Chaniotakis L. Bromberg D. R. Cohn April 25, 1991 Plasma Fusion Center Massachusetts Institute of Technology

More information

Unpressurized steam reactor. Controlled Fission Reactors. The Moderator. Global energy production 2000

Unpressurized steam reactor. Controlled Fission Reactors. The Moderator. Global energy production 2000 From last time Fission of heavy elements produces energy Only works with 235 U, 239 Pu Fission initiated by neutron absorption. Fission products are two lighter nuclei, plus individual neutrons. These

More information

A SUPERCONDUCTING TOKAMAK FUSION TRANSMUTATION OF WASTE REACTOR

A SUPERCONDUCTING TOKAMAK FUSION TRANSMUTATION OF WASTE REACTOR A SUPERCONDUCTING TOKAMAK FUSION TRANSMUTATION OF WASTE REACTOR A.N. Mauer, W.M. Stacey, J. Mandrekas and E.A. Hoffman Fusion Research Center Georgia Institute of Technology Atlanta, GA 30332 1. INTRODUCTION

More information

Fusion Development Facility (FDF) Mission and Concept

Fusion Development Facility (FDF) Mission and Concept Fusion Development Facility (FDF) Mission and Concept Presented by R.D. Stambaugh PERSISTENT SURVEILLANCE FOR PIPELINE PROTECTION AND THREAT INTERDICTION University of California Los Angeles FNST Workshop

More information

Physics & Engineering Physics University of Saskatchewan. Supported by NSERC, CRC

Physics & Engineering Physics University of Saskatchewan. Supported by NSERC, CRC Fusion Energy Chijin Xiao and Akira Hirose Plasma Physics laboratory Physics & Engineering Physics University of Saskatchewan Supported by NSERC, CRC Trends in Nuclear & Medical Technologies April il6-7,

More information

The Dynomak Reactor System

The Dynomak Reactor System The Dynomak Reactor System An economically viable path to fusion power Derek Sutherland HIT-SI Research Group University of Washington November 7, 2013 Outline What is nuclear fusion? Why do we choose

More information

Issues for Neutron Calculations for ITER Fusion Reactor

Issues for Neutron Calculations for ITER Fusion Reactor Introduction Issues for Neutron Calculations for ITER Fusion Reactor Erik Nonbøl and Bent Lauritzen Risø DTU, National Laboratory for Sustainable Energy Roskilde, Denmark Outline 1. Fusion development

More information

Summary Tritium Day Workshop

Summary Tritium Day Workshop Summary Tritium Day Workshop Presentations by M. Abdou, A. Loarte, L. Baylor, S. Willms, C. Day, P. Humrickhouse, M. Kovari 4th IAEA DEMO Programme Workshop November 18th, 2016 - Karlsruhe, Germany Overall

More information

HEAT TRANSFER CAPABILITY OF A THERMOSYPHON HEAT TRANSPORT DEVICE WITH EXPERIMENTAL AND CFD STUDIES

HEAT TRANSFER CAPABILITY OF A THERMOSYPHON HEAT TRANSPORT DEVICE WITH EXPERIMENTAL AND CFD STUDIES HEAT TRANSFER CAPABILITY OF A THERMOSYPHON HEAT TRANSPORT DEVICE WITH EXPERIMENTAL AND CFD STUDIES B.M. Lingade a*, Elizabeth Raju b, A Borgohain a, N.K. Maheshwari a, P.K.Vijayan a a Reactor Engineering

More information

Fusion Reactor Research Activities at SWIP (1)

Fusion Reactor Research Activities at SWIP (1) Fusion Reactor Research Activities at SWIP (1) Design Studies of DEMO Reactor 1. Introduction Considering that there is still a long way to go towards an economically competitive commercial fusion power

More information

Mission Elements of the FNSP and FNSF

Mission Elements of the FNSP and FNSF Mission Elements of the FNSP and FNSF by R.D. Stambaugh PERSISTENT SURVEILLANCE FOR PIPELINE PROTECTION AND THREAT INTERDICTION Presented at FNST Workshop August 3, 2010 In Addition to What Will Be Learned

More information

Provisional scenario of radioactive waste management for DEMO

Provisional scenario of radioactive waste management for DEMO US-Japan Workshop on Fusion power plants and Related advanced technologies 13-14 March 2014 UCSD, USA Provisional scenario of radioactive waste management for DEMO Youji Someya Japan Atomic Energy Agency,

More information

Experimental Studies of Active Temperature Control in Solid Breeder Blankets

Experimental Studies of Active Temperature Control in Solid Breeder Blankets Experimental Studies of Active Temperature Control in Solid Breeder Blankets M. S. Tillack, A. R. Raffray, A. Y. Ying, M. A. Abdou, and P. Huemer Mechanical, Aerospace and Nuclear Engineering Department

More information

Preliminary Safety Analysis of CH HCSB TBM

Preliminary Safety Analysis of CH HCSB TBM Preliminary Safety Analysis of CH HCSB TBM Presented by: Chen Zhi SWIP ITER TBM Workshop, China Vienna, Austria, IAEA, July 10-14, 2006 1 Introduction Calculation model Outline Review of CH HCSB TBM preliminary

More information

Yuntao, SONG ( ) and Satoshi NISHIO ( Japan Atomic Energy Research Institute

Yuntao, SONG ( ) and Satoshi NISHIO ( Japan Atomic Energy Research Institute Conceptual design of liquid metal cooled power core components for a fusion power reactor Yuntao, SONG ( ) and Satoshi NISHIO ( Japan Atomic Energy Research Institute Japan-US workshop on Fusion Power

More information

The PPCS In-Vessel Component Concepts (focused on Breeding Blankets)

The PPCS In-Vessel Component Concepts (focused on Breeding Blankets) International School of Fusion reactor Technology Erice, July 26 August 1, 2004 The PPCS In-Vessel Component Concepts (focused on Breeding Blankets) Presented by L. Giancarli Commissariat à l Energie Atomique,

More information

Nuclear Energy in the Future. The ITER Project. Brad Nelson. Chief Engineer, US ITER. Presentation for NE-50 Symposium on the Future of Nuclear Energy

Nuclear Energy in the Future. The ITER Project. Brad Nelson. Chief Engineer, US ITER. Presentation for NE-50 Symposium on the Future of Nuclear Energy Nuclear Energy in the Future The ITER Project Brad Nelson Chief Engineer, US ITER Presentation for NE-50 Symposium on the Future of Nuclear Energy November 1, 2012 Fusion research is ready for the next

More information

The Development and Application of One Thermal Hydraulic Program Based on ANSYS for Design of Ceramic Breeder Blanket of CFETR

The Development and Application of One Thermal Hydraulic Program Based on ANSYS for Design of Ceramic Breeder Blanket of CFETR J Fusion Energ (2015) 34:1088 1093 DOI 10.1007/s10894-015-9923-6 ORIGINAL RESEARCH The Development and Application of One Thermal Hydraulic Program Based on ANSYS for Design of Ceramic Breeder Blanket

More information

HT-7U* Superconducting Tokamak: Physics design, engineering progress and. schedule

HT-7U* Superconducting Tokamak: Physics design, engineering progress and. schedule 1 FT/P2-03 HT-7U* Superconducting Tokamak: Physics design, engineering progress and schedule Y.X. Wan 1), P.D. Weng 1), J.G. Li 1), Q.Q. Yu 1), D.M. Gao 1), HT-7U Team 1) Institute of Plasma Physics, Chinese

More information

Thermal-hydraulic design of a DCLL breeding blanket for the EU DEMO

Thermal-hydraulic design of a DCLL breeding blanket for the EU DEMO EUROFUSION WPBB-CP(16) 15491 I. Fernandez-Berceruelo et al. Thermal-hydraulic design of a DCLL breeding blanket for the EU DEMO Preprint of Paper to be submitted for publication in Proceedings of 29th

More information

JET and Fusion Energy for the Next Millennia

JET and Fusion Energy for the Next Millennia JET and Fusion Energy for the Next Millennia JET Joint Undertaking Abingdon, Oxfordshire OX14 3EA JG99.294/1 Talk Outline What is Nuclear Fusion? How can Fusion help our Energy needs? Progress with Magnetic

More information

Compact, spheromak-based pilot plants for the demonstration of net-gain fusion power

Compact, spheromak-based pilot plants for the demonstration of net-gain fusion power Compact, spheromak-based pilot plants for the demonstration of net-gain fusion power Derek Sutherland HIT-SI Research Group University of Washington July 25, 2017 D.A. Sutherland -- EPR 2017, Vancouver,

More information

International Journal of Mathematical Archive-5(5), 2014, Available online through ISSN

International Journal of Mathematical Archive-5(5), 2014, Available online through   ISSN International Journal of Mathematical Archive-5(5), 014, 135-14 Available online through www.ijma.info ISSN 9 5046 STUDY ON LIQUID METAL MHD FLOW THROUGH A TRIANGULAR DUCT UNDER THE ACTION OF VERY STRONG

More information

Design of structural components and radial-build for FFHR-d1

Design of structural components and radial-build for FFHR-d1 Japan-US Workshop on Fusion Power Plants and Related Advanced Technologies with participations from China and Korea February 26-28, 2013 at Kyoto University in Uji, JAPAN 1 Design of structural components

More information

ITER DIAGNOSTIC PORT PLUG DESIGN. N H Balshaw, Y Krivchenkov, G Phillips, S Davis, R Pampin-Garcia

ITER DIAGNOSTIC PORT PLUG DESIGN. N H Balshaw, Y Krivchenkov, G Phillips, S Davis, R Pampin-Garcia N H Balshaw, Y Krivchenkov, G Phillips, S Davis, R Pampin-Garcia UKAEA, Culham Science Centre, Abingdon, Oxon,OX14 3DB, UK, nick.balshaw@jet.uk Many of the ITER diagnostic systems will be mounted in the

More information

Conceptual Design of CFETR Tokamak Machine

Conceptual Design of CFETR Tokamak Machine Japan-US Workshop on Fusion Power Plants and Related Advanced Technologies February 26-28, 2013 at Kyoto University in Uji, JAPAN Conceptual Design of CFETR Tokamak Machine Yuntao Song for CFETR Design

More information

EFFECT OF DISTRIBUTION OF VOLUMETRIC HEAT GENERATION ON MODERATOR TEMPERATURE DISTRIBUTION

EFFECT OF DISTRIBUTION OF VOLUMETRIC HEAT GENERATION ON MODERATOR TEMPERATURE DISTRIBUTION EFFECT OF DISTRIBUTION OF VOLUMETRIC HEAT GENERATION ON MODERATOR TEMPERATURE DISTRIBUTION A. K. Kansal, P. Suryanarayana, N. K. Maheshwari Reactor Engineering Division, Bhabha Atomic Research Centre,

More information

Nuclear Fusion 1 of 24 Boardworks Ltd 2011

Nuclear Fusion 1 of 24 Boardworks Ltd 2011 Nuclear Fusion 1 of 24 Boardworks Ltd 2011 2 of 24 Boardworks Ltd 2011 How do we get energy from atoms? 3 of 24 Boardworks Ltd 2011 Energy is produced from atoms in power stations using the process of

More information

Magnetic Confinement Fusion and Tokamaks Chijin Xiao Department of Physics and Engineering Physics University of Saskatchewan

Magnetic Confinement Fusion and Tokamaks Chijin Xiao Department of Physics and Engineering Physics University of Saskatchewan The Sun Magnetic Confinement Fusion and Tokamaks Chijin Xiao Department of Physics and Engineering Physics University of Saskatchewan 2017 CNS Conference Niagara Falls, June 4-7, 2017 Tokamak Outline Fusion

More information

NATURAL CONVECTION HEAT TRANSFER CHARACTERISTICS OF KUR FUEL ASSEMBLY DURING LOSS OF COOLANT ACCIDENT

NATURAL CONVECTION HEAT TRANSFER CHARACTERISTICS OF KUR FUEL ASSEMBLY DURING LOSS OF COOLANT ACCIDENT NATURAL CONVECTION HEAT TRANSFER CHARACTERISTICS OF KUR FUEL ASSEMBLY DURING LOSS OF COOLANT ACCIDENT Ito D*, and Saito Y Research Reactor Institute Kyoto University 2-1010 Asashiro-nishi, Kumatori, Sennan,

More information

HCLL Test Blanket Module Test program in ITER

HCLL Test Blanket Module Test program in ITER International Workshop on Liquid Metals Breeder Blankets 23-24 September 2010 CIEMAT, Madrid, Spain HCLL Test Blanket Module Test program in ITER Y. Poitevin, M. Zmitko, I. Ricapito, Fusion for Energy

More information

Lectures on Applied Reactor Technology and Nuclear Power Safety. Lecture No 6

Lectures on Applied Reactor Technology and Nuclear Power Safety. Lecture No 6 Lectures on Nuclear Power Safety Lecture No 6 Title: Introduction to Thermal-Hydraulic Analysis of Nuclear Reactor Cores Department of Energy Technology KTH Spring 2005 Slide No 1 Outline of the Lecture

More information

Summary of Thick Liquid FW/Blanket for High Power Density Fusion Devices

Summary of Thick Liquid FW/Blanket for High Power Density Fusion Devices Summary of Thick Liquid FW/Blanket for High Power Density Fusion Devices The replacement of the first wall with a flowing thick liquid offers the advantages of high power density, high reliability and

More information

Fusion/transmutation reactor studies based on the spherical torus concept

Fusion/transmutation reactor studies based on the spherical torus concept FT/P1-7, FEC 2004 Fusion/transmutation reactor studies based on the spherical torus concept K.M. Feng, J.H. Huang, B.Q. Deng, G.S. Zhang, G. Hu, Z.X. Li, X.Y. Wang, T. Yuan, Z. Chen Southwestern Institute

More information

Diagnostics for Burning Plasma Physics Studies: A Status Report.

Diagnostics for Burning Plasma Physics Studies: A Status Report. Diagnostics for Burning Plasma Physics Studies: A Status Report. Kenneth M. Young Princeton Plasma Physics Laboratory UFA Workshop on Burning Plasma Science December 11-13 Austin, TX Aspects of Plasma

More information

Nuclear Fusion and ITER

Nuclear Fusion and ITER Nuclear Fusion and ITER C. Alejaldre ITER Deputy Director-General Cursos de Verano UPM Julio 2, 2007 1 ITER the way to fusion power ITER ( the way in Latin) is the essential next step in the development

More information

Neutronics analysis of inboard shielding capability for a DEMO fusion reactor

Neutronics analysis of inboard shielding capability for a DEMO fusion reactor *Manuscript Click here to view linked References Neutronics analysis of inboard shielding capability for a DEMO fusion reactor Songlin Liu a, Jiangang Li a, Shanliang Zheng b, Neil Mitchell c a Institute

More information

Activation Calculation for a Fusion-driven Sub-critical Experimental Breeder, FDEB

Activation Calculation for a Fusion-driven Sub-critical Experimental Breeder, FDEB Activation Calculation for a Fusion-driven Sub-critical Experimental Breeder, FDEB K. M. Feng (Southwestern Institute of Physics, China) Presented at 8th IAEA Technical Meeting on Fusion Power Plant Safety

More information

A Technology Review of Electricity Generation from Nuclear Fusion Reaction in Future

A Technology Review of Electricity Generation from Nuclear Fusion Reaction in Future International OPEN ACCESS Journal Of Modern Engineering Research (IJMER) 3 A Technology Review of Electricity Generation from Nuclear Fusion Reaction in Future 1 Joydeep Sarkar, 2 Karishma P. Patil, 3

More information

Tokamak Divertor System Concept and the Design for ITER. Chris Stoafer April 14, 2011

Tokamak Divertor System Concept and the Design for ITER. Chris Stoafer April 14, 2011 Tokamak Divertor System Concept and the Design for ITER Chris Stoafer April 14, 2011 Presentation Overview Divertor concept and purpose Divertor physics General design considerations Overview of ITER divertor

More information

Materials for Future Fusion Reactors under Severe Stationary and Transient Thermal Loads

Materials for Future Fusion Reactors under Severe Stationary and Transient Thermal Loads Mitglied der Helmholtz-Gemeinschaft Materials for Future Fusion Reactors under Severe Stationary and Transient Thermal Loads J. Linke, J. Du, N. Lemahieu, Th. Loewenhoff, G. Pintsuk, B. Spilker, T. Weber,

More information

The influence of a magnetic field on turbulent heat transfer of a high Prandtl number fluid

The influence of a magnetic field on turbulent heat transfer of a high Prandtl number fluid Experimental Thermal and Fluid Science 32 (27) 23 28 www.elsevier.com/locate/etfs The influence of a magnetic field on turbulent heat transfer of a high Prandtl number fluid H. Nakaharai a, *, J. Takeuchi

More information

HIGH TEMPERATURE THERMAL HYDRAULICS MODELING

HIGH TEMPERATURE THERMAL HYDRAULICS MODELING HIGH TEMPERATURE THERMAL HYDRAULICS MODELING OF A MOLTEN SALT: APPLICATION TO A MOLTEN SALT FAST REACTOR (MSFR) P. R. Rubiolo, V. Ghetta, J. Giraud, M. Tano Retamales CNRS/IN2P3/LPSC - Grenoble Workshop

More information

CFD STUDIES IN THE PREDICTION OF THERMAL STRIPING IN AN LMFBR

CFD STUDIES IN THE PREDICTION OF THERMAL STRIPING IN AN LMFBR CFD STUDIES IN THE PREDICTION OF THERMAL STRIPING IN AN LMFBR K. Velusamy, K. Natesan, P. Selvaraj, P. Chellapandi, S. C. Chetal, T. Sundararajan* and S. Suyambazhahan* Nuclear Engineering Group Indira

More information

Study of Impacts on Tritium Breeding Ratio of a Fusion DEMO Reactor

Study of Impacts on Tritium Breeding Ratio of a Fusion DEMO Reactor CCFE-PR(17)32 S. Zhen and T.N. Todd Study of Impacts on Tritium Breeding Ratio of a Fusion DEMO Reactor Enquiries about copyright and reproduction should in the first instance be addressed to the Culham

More information

MELCOR model development for ARIES Safety Analysis

MELCOR model development for ARIES Safety Analysis MELCOR model development for ARIES Safety Analysis Paul Humrickhouse Brad Merrill INL ARIES Meeting UCSD San Diego, CA January 23 rd -24 th, 2012 Presentation Outline Status of MELCOR modeling for ARIES-ACT

More information

1 FT/P5-15. Assessment of the Shielding Efficiency of the HCLL Blanket for a DEMOtype Fusion Reactor

1 FT/P5-15. Assessment of the Shielding Efficiency of the HCLL Blanket for a DEMOtype Fusion Reactor 1 FT/P5-15 Assessment of the Shielding Efficiency of the HCLL Blanket for a DEMOtype Fusion Reactor J. Jordanova 1), U. Fischer 2), P. Pereslavtsev 2), Y. Poitevin 3), J. F. Salavy 4), A. Li Puma 4), N.

More information

Spherical Torus Fusion Contributions and Game-Changing Issues

Spherical Torus Fusion Contributions and Game-Changing Issues Spherical Torus Fusion Contributions and Game-Changing Issues Spherical Torus (ST) research contributes to advancing fusion, and leverages on several game-changing issues 1) What is ST? 2) How does research

More information

Safety Issues Related to Liquid Metals

Safety Issues Related to Liquid Metals Safety Issues Related to Liquid Metals Kathryn A. McCarthy Fusion Safety Program APEX Meeting July 27-31, 1998 Albuquerque, NM Idaho National Engineering and Environmental Laboratory Lockheed Martin Idaho

More information

DEMO Concept Development and Assessment of Relevant Technologies. Physics and Engineering Studies of the Advanced Divertor for a Fusion Reactor

DEMO Concept Development and Assessment of Relevant Technologies. Physics and Engineering Studies of the Advanced Divertor for a Fusion Reactor FIP/3-4Rb FIP/3-4Ra DEMO Concept Development and Assessment of Relevant Technologies Y. Sakamoto, K. Tobita, Y. Someya, H. Utoh, N. Asakura, K. Hoshino, M. Nakamura, S. Tokunaga and the DEMO Design Team

More information

Atomic physics in fusion development

Atomic physics in fusion development Atomic physics in fusion development The next step in fusion development imposes new requirements on atomic physics research by R.K. Janev In establishing the scientific and technological base of fusion

More information

3.12 Development of Burn-up Calculation System for Fusion-Fission Hybrid Reactor

3.12 Development of Burn-up Calculation System for Fusion-Fission Hybrid Reactor 3.12 Development of Burn-up Calculation System for Fusion-Fission Hybrid Reactor M. Matsunaka, S. Shido, K. Kondo, H. Miyamaru, I. Murata Division of Electrical, Electronic and Information Engineering,

More information

Aiming at Fusion Power Tokamak

Aiming at Fusion Power Tokamak Aiming at Fusion Power Tokamak Design Limits of a Helium-cooled Large Area First Wall Module Clement Wong General Atomics International Workshop on MFE Roadmapping in the ITER Era Princeton University,

More information

Principles of Nuclear Fusion & Fusion research in Belgium R. R. Weynants

Principles of Nuclear Fusion & Fusion research in Belgium R. R. Weynants Principles of Nuclear Fusion & Fusion research in Belgium R. R. Weynants Laboratorium voor Plasmafysica - Laboratoire de Physique des Plasmas Koninklijke Militaire School - Ecole Royale Militaire 1040

More information

Tokamak Fusion Basics and the MHD Equations

Tokamak Fusion Basics and the MHD Equations MHD Simulations for Fusion Applications Lecture 1 Tokamak Fusion Basics and the MHD Equations Stephen C. Jardin Princeton Plasma Physics Laboratory CEMRACS 1 Marseille, France July 19, 21 1 Fusion Powers

More information

Hydrogen and Helium Edge-Plasmas

Hydrogen and Helium Edge-Plasmas Hydrogen and Helium Edge-Plasmas Comparison of high and low recycling T.D. Rognlien and M.E. Rensink Lawrence Livermore National Lab Presented at the ALPS/APEX Meeting Argonne National Lab May 8-12, 2

More information

Fusion Energy: Pipe Dream or Panacea

Fusion Energy: Pipe Dream or Panacea Fusion Energy: Pipe Dream or Panacea Mike Mauel Columbia University Energy Options & Paths to Climate Stabilization Aspen, 9 July 2003 Fusion Energy: Pipe Dream or Panacea Promise, Progress, and the Challenge

More information

Observations of Thermo-Electric MHD Driven Flows in the SLiDE Apparatus

Observations of Thermo-Electric MHD Driven Flows in the SLiDE Apparatus Observations of Thermo-Electric MHD Driven Flows in the SLiDE Apparatus M.A. Jaworski, Wenyu Xu, M. Antonelli, J.J. Kim, M.B. Lee, V. Surla and D.N. Ruzic Department of Nuclear, Plasma and Radiological

More information

If there is convective heat transfer from outer surface to fluid maintained at T W.

If there is convective heat transfer from outer surface to fluid maintained at T W. Heat Transfer 1. What are the different modes of heat transfer? Explain with examples. 2. State Fourier s Law of heat conduction? Write some of their applications. 3. State the effect of variation of temperature

More information

Journal of NUCLEAR SCIENCE and TECHNOLOGY, Vol. 41, No. 7, p (July 2004)

Journal of NUCLEAR SCIENCE and TECHNOLOGY, Vol. 41, No. 7, p (July 2004) Journal of NUCLEAR SCIENCE and TECHNOLOGY, Vol. 41, No. 7, p. 765 770 (July 2004) TECHNICAL REPORT Experimental and Operational Verification of the HTR-10 Once-Through Steam Generator (SG) Heat-transfer

More information

Thermo-mechanical analyses and ways of optimization of the helium cooled DEMO First Wall under RCC-MRx rules

Thermo-mechanical analyses and ways of optimization of the helium cooled DEMO First Wall under RCC-MRx rules EUROFUSION WPBB-CP(16) 15736 J Aubert et al. Thermo-mechanical analyses and ways of optimization of the helium cooled DEMO First Wall under RCC-MRx rules Preprint of Paper to be submitted for publication

More information

Introduction to Fusion Physics

Introduction to Fusion Physics Introduction to Fusion Physics Hartmut Zohm Max-Planck-Institut für Plasmaphysik 85748 Garching DPG Advanced Physics School The Physics of ITER Bad Honnef, 22.09.2014 Energy from nuclear fusion Reduction

More information

Multiple Effects/ Multiple Interactions and the Need for Fusion Nuclear Science Facility prior to construction of DEMO

Multiple Effects/ Multiple Interactions and the Need for Fusion Nuclear Science Facility prior to construction of DEMO Multiple Effects/ Multiple Interactions and the Need for Fusion Nuclear Science Facility prior to construction of DEMO Issues, Role, Design Features, and R&D requirements Mohamed Abdou Distinguished Professor

More information

Heat Transfer Experiment and Simulation of the Verification Facility for High Power Rotating Tritium Target System

Heat Transfer Experiment and Simulation of the Verification Facility for High Power Rotating Tritium Target System J Fusion Energ (2015) 34:1252 1256 DOI 10.1007/s10894-015-9952-1 ORIGINAL RESEARCH Heat Transfer Experiment and Simulation of the Verification Facility for High Power Rotating Tritium Target System Gang

More information

Plasma & Fusion on Earth: merging age-old natural phenomena into your present and future

Plasma & Fusion on Earth: merging age-old natural phenomena into your present and future Plasma & Fusion on Earth: merging age-old natural phenomena into your present and future Presented by Rick Lee Chief Operator, DIII-D Operations Manager, Energy/Fusion Outreach Program General Atomics

More information

Overview of Pilot Plant Studies

Overview of Pilot Plant Studies Overview of Pilot Plant Studies and contributions to FNST Jon Menard, Rich Hawryluk, Hutch Neilson, Stewart Prager, Mike Zarnstorff Princeton Plasma Physics Laboratory Fusion Nuclear Science and Technology

More information

Breeding Blanket Modules testing in ITER: An international program on the way to DEMO

Breeding Blanket Modules testing in ITER: An international program on the way to DEMO Fusion Engineering and Design 81 (2006) 393 405 Breeding Blanket Modules testing in ITER: An international program on the way to DEMO L. Giancarli a,, V. Chuyanov b, M. Abdou c, M. Akiba d, B.G. Hong e,r.lässer

More information

EF2200 Plasma Physics: Fusion plasma physics

EF2200 Plasma Physics: Fusion plasma physics EF2200 Plasma Physics: Fusion plasma physics Guest lecturer: Thomas Jonsson, johnso@kth.se Department for Fusion Plasma Physics School of Electrical Engineering 1 ITER (EU, China, India, Japan, Russia,

More information

Seminar Chengdu, China Southwestern Institute of Physics (SWIP)

Seminar Chengdu, China Southwestern Institute of Physics (SWIP) Blanket/First Wall Challenges and Required R&D on the pathway to DEMO for the near term in laboratory experiments and medium term in FNSF/CFETR Mohamed Abdou Distinguished Professor of Engineering and

More information

Comparison of 2 Lead-Bismuth Spallation Neutron Targets

Comparison of 2 Lead-Bismuth Spallation Neutron Targets Comparison of 2 Lead-Bismuth Spallation Neutron Targets Keith Woloshun, Curtt Ammerman, Xiaoyi He, Michael James, Ning Li, Valentina Tcharnotskaia, Steve Wender Los Alamos National Laboratory P.O. Box

More information