The GDT-based fusion neutron source as a driver of subcritical nuclear fuel systems
|
|
- Godfrey Booker
- 5 years ago
- Views:
Transcription
1 The GDT-based fusion neutron source as a driver of subcritical nuclear fuel systems Presented by A.A.Ivanov Budker Institute, FZD Rossendorf, Joint Institute for Nuclear,, VNIITF, Snejinsk
2 Layout of the talk Physics of GDT based neutron source Application as a driver for sub-critical fission reactor Application as a MA burner Possible re-optimization GDT-NS for application as a driver Conclusions
3 Gas Dynamic Trap 3
4 Basic principles of GDT operation The Gas-Dynamic Trap is a version of a standard simple mirror whose characteristic features are a very high mirror ratio, R, in the range of a few tens; a relatively large length, L,exceeding an effective mean free path, λ ii lnr /R, with respect to scattering into the loss cone. The warm target plasma is almost Maxwellian behaves like an ideal gas in a container with a pinhole leak MHD-stable even though system is fully axially symmetric non-negligible amount of plasma in the regions beyond the mirror throats, where magnetic field has favorable curvature MHD ballooning/interchange modes limit stability at β 40-60% The electron neat flux to the end walls is suppressed by strong reduction of magnetic field in expanders 4
5 Requirements to VNS for fusion materials testing Fusion neutron spectrum About 2MW/m 2 neutron flux or higher for accelerated tests Small enough gradient of neutron flux density Continuous operation Availability more than 70% Reasonable tritium consumption
6 Schematic view of the GDT-NS for the material tests
7 Basic set of parameters for two and three component version of GDT-NS Parameter Two component version Three component version Tritium beam energy (kev) Deuterium beam energy (kev) - 80 Tritium beam power (MW) Deuterium beam power (MW) Electron temperature (kev) Plasma density (m -3 ) 2 x x10 20 Plasma radius at the center (m) Mirror ratio Central field (T) Injection angle (deg.) Max. neutron flux (MW/m 2 ) Power consumption (MW) 50 60
8 Neutron spectrum in GDT-NS
9 GDT-NS: reference set of parameters POWER CONSUMPTION - 47 MW MAGNETIC FIELD IN MIRRORS, B m = 13 T; MIRROR RATIO R = 10 INJECTION ANGLE, θ =30 0 INJECTION ENERGY - 65 kev PLASMA DIAMETER AT MIDPLANE, 2a = 16 cm RATIO OF ELECTRON TEMPERATURE TO THE INJECTION ENERGY T e /E INJ =10-2 MIRROR-TO-MIRROR, 11.4 m NEUTRON SOURCE INTENSITY s -1
10 Neutron flux density vs injection energy
11 Neutron flux density vs electron temperature Injection energy 65keV Power consumption 60MW
12 Cutaway view of the GDT-NS
13 Elevation view of GDT-NS
14 Neutron yield profile in GDT-NS
15 Neutron field characteristics
16 GDT device general view 16
17 Physics issues addressed in the experiments Factors controlling electron temperature Microstability of fast ions Steady state operation Ballooning instability threshold Effect of ambipolar fields on confinement Effect of plasma rotation/vortex barrier formation Non-paraxial effects due to high β
18 GDT device - important results MHD stable confinement of plasma with β exceeding 0.4 is achieved in axially symmetric magnetic field Stability of high-β plasma is demonstrated with external anchor cells (expander and cusp) Plasma stabilization by vortex barrier is demonstrated Plasma energy balance is determined by energy transfer from fast ions and losses through end mirrors Electron heat conduction to the end walls is suppressed by strong reduction of magnetic field in expander Relaxation rates of anisotropic fast ions are classical no microinstabilities Skew injection of neutral beams at midplane provides formation of fast ion density peaks near turning points Plasma is sustained during several characteristic times with extended neutral beams 18
19 Measured axial profile of DD-reaction intensity
20 Neutron flux vs plasma temperature NB energy 65keV 65keV injection energy 20
21 Electron temperature vs time 21
22 Plasma β in steady stay with D 0 beams βmax 40% n f 5x10 19 m -3 22
23 Formation of vortex barrier
24 End loss reduction by fast ion density peaking near the ends Peak density in local mirror cell vs trapped NB power Reduction of end loss current density with beam injection into local mirror cell
25 Experiment with max Te Standard experimental scenario Te 230eV Mean ion energy 8.0keV Confinement time Transient regime 160eV 10keV 0.001s Injected power Electron density 3.5MW 1.5x10 19 m MW Fusion triple product (nτei=2.0x10 17 kevm -3 s) Maximum stored energy Maximum β Plasma parameters in GDT 1.2 KJ <beta> 50% at B=0.5T Maximum density >10 20 m -3 Values in bold are maximum attained ones. 5.0x10 19 m -3 25
26 Existing GDT-NS version as a driver for sub-critical reactor
27 Results of simulations Neutron production in driver s -1 Overall multiplication factor 0.95 Thermal power generated ~0.5GW Neutron shield for SS coils Pb+water 60cm Filter material Pb 10cm
28 Energy amplifier proposed by C. Rubbia (1995): Principles of an ADS: Accelerator particle beam Target neutrons Sub-critical system (protons) (heavy metal) (spallation) (arrangement of nuclear fuel) Strong neutron field inside the whole volume of the fuel system by means of fissions! Important features: 1. Sub-criticality: k eff 0.98! 2. No control rods! Power control by proton beam! Release of nuclear energy Transmutation of nuclear waste!
29 Introduction Nuclear systems Driven sub-critical system, ADS, FDS? Accelerator z Effective multiplication factor: k eff Driven systems: k eff determines the self-multiplicity of the system: p E p 1 GeV Sub-critical Driven Reactor: system: k eff = < 1 I p = =const. 10 = ~ 0S 200 > ma 0 k eff < 1: M eff =k eff /(1-k eff ): f eff =M eff /ν : Core n Spallation n s/p=10-30 r Reflector
30 Energy spectra of ADS and GDT neutron source:
31 total n,2n n,γ n,3n 10 MeV
32 Consideration of GDT-NS for fission fuel systems Re-arrangement of neutron production zone (elongation (keff<0.97) to L 5 m on each side gives: Sn= n/s, Pfus=7.1 MW, Pfis 1400 MW, Pinp 200 MW) Re-optimization of operational parameters Increase of electron temperature (Te higher than 1.5keV would provide higher efficiency than ADS) Reduction of axial losses by ambipolar potential peaks (demonstrated) On-site tritium breeding K. Noack,et al, Annals of Nuclear Energy, 35(7), pp , (2008) P.Bagryansky, et al, Fusion eng. and design, 70, pp , (2004)
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 informationª 10 KeV. In 2XIIB and the tandem mirrors built to date, in which the plug radius R p. ª r Li
Axisymmetric Tandem Mirrors: Stabilization and Confinement Studies R. F. Post, T. K. Fowler*, R. Bulmer, J. Byers, D. Hua, L. Tung Lawrence Livermore National Laboratory *Consultant, Presenter This talk
More informationPHYSICS BASIS FOR THE GASDYNAMIC MIRROR (GDM) FUSION ROCKET. Abstract
PHYSICS BASIS FOR THE GASDYNAMIC MIRROR (GDM) FUSION ROCKET T. Kammash Department of Nuclear Engineering and Radiological Sciences University of Michigan Ann Arbor, MI 48109 (313) 764-0205 W. Emrich Jr.
More informationThermonuclear Prospects of Modern Mirror Systems
Thermonuclear Prospects of Modern Mirror Systems E.P.Kruglyakov, A.V.Burdakov, A.A.Ivanov, Budker Institute of Nuclear Physics, Novosibirsk, 630090, Russian Federation e-mail: e.kruglyakov@inp.nsk.su Abstract.
More informationTransmutation of Minor Actinides in a Spherical
1 Transmutation of Minor Actinides in a Spherical Torus Tokamak Fusion Reactor Feng Kaiming Zhang Guoshu Fusion energy will be a long-term energy source. Great efforts have been devoted to fusion research
More informationDesign 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 informationAdvances in Plasma Heating and Confinement in the GOL-3 Multiple-Mirror Trap
1 Advances in Plasma Heating and Confinement in the GOL-3 Multiple-Mirror Trap A.V. Burdakov 1), A.V. Arzhannikov 2), V.T. Astrelin 1), V.I. Batkin 1), V.S. Burmasov 1), G.E. Derevyankin 1), V.G. Ivanenko
More informationA 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 informationCompact, 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 informationA MIRROR FUSION DEVICE FOR ADVANCED SPACE PROPULSION
A MIRROR FUSION DEVICE FOR ADVANCED SPACE PROPULSION Terry Kammash and Myoung-Jae Lee Department of Nuclear Engineering The University of Michigan Ann Arbor, M148109 (313) 764-0205 Abstract An open-ended
More informationBurn Stabilization of a Tokamak Power Plant with On-Line Estimations of Energy and Particle Confinement Times
Burn Stabilization of a Tokamak Power Plant with On-Line Estimations of Energy and Particle Confinement Times Javier E. Vitela vitela@nucleares.unam.mx Instituto de Ciencias Nucleares Universidad Nacional
More informationStudies of Next-Step Spherical Tokamaks Using High-Temperature Superconductors Jonathan Menard (PPPL)
Studies of Next-Step Spherical Tokamaks Using High-Temperature Superconductors Jonathan Menard (PPPL) 22 nd Topical Meeting on the Technology of Fusion Energy (TOFE) Philadelphia, PA August 22-25, 2016
More informationNuclear Fission. 1/v Fast neutrons. U thermal cross sections σ fission 584 b. σ scattering 9 b. σ radiative capture 97 b.
Nuclear Fission 1/v Fast neutrons should be moderated. 235 U thermal cross sections σ fission 584 b. σ scattering 9 b. σ radiative capture 97 b. Fission Barriers 1 Nuclear Fission Q for 235 U + n 236 U
More informationD. Cano Ott Nuclear Innovation Nuclear Fission Division Dept. of Energy. CIEMAT-IFIC-UPC collaboration
Beta-delayed neutron measurements for nuclear technologies D. Cano Ott Nuclear Innovation Nuclear Fission Division Dept. of Energy CIEMAT-IFIC-UPC collaboration i i B i GT K f i I ( Z, Q i ) T 1/ 2 K 1
More informationNeutron Sources Fall, 2017 Kyoung-Jae Chung Department of Nuclear Engineering Seoul National University
Neutron Sources Fall, 2017 Kyoung-Jae Chung Department of Nuclear Engineering Seoul National University Neutrons: discovery In 1920, Rutherford postulated that there were neutral, massive particles in
More informationMegawatt Range Fusion Neutron Source for Technology and Research
Nuclear Fusion Institute Moscow, 123182, Russia Megawatt Range Fusion Neutron Source for Technology and Research B.V. Kuteev, A.A. Borisov, A.A. Golikov, P.R. Goncharov 1, V.I. Khripunov, V.E. Lukash,
More informationAspects of Advanced Fuel FRC Fusion Reactors
Aspects of Advanced Fuel FRC Fusion Reactors John F Santarius and Gerald L Kulcinski Fusion Technology Institute Engineering Physics Department CT2016 Irvine, California August 22-24, 2016 santarius@engr.wisc.edu;
More informationThorium-Cycle Fission for Green Nuclear Power. Pt Peter McIntyre MIt Texas A&M University
Thorium-Cycle Fission for Green Nuclear Power Pt Peter McIntyre MIt Texas A&M University Criteria for green nuclear power: Use the most plentiful fissionable fuels: Thorium and depleted d uranium Operate
More informationBenchmark Experiments of Accelerator Driven Systems (ADS) in Kyoto University Critical Assembly (KUCA)
Benchmark Experiments of Accelerator Driven Systems (ADS) in Kyoto University Critical Assembly (KUCA) C. H. Pyeon, T. Misawa, H. Unesaki, K. Mishima and S. Shiroya (Kyoto University Research Reactor Institute,
More informationNeutral beam plasma heating
Seminar I b 1 st year, 2 nd cycle program Neutral beam plasma heating Author: Gabrijela Ikovic Advisor: prof.dr. Tomaž Gyergyek Ljubljana, May 2014 Abstract For plasma to be ignited, external heating is
More informationExperiments with Thin Electron Beam at GOL-3
8 th International Conference on Open Magnetic Systems for Plasma Confinement July 8, 21, Novosibirsk, Russia Experiments with Thin Electron Beam at GOL-3 V.V. Postupaev, A.V. Arzhannikov, V.T. Astrelin,
More informationThorium-Cycle Fission for Green Nuclear Power. Pt Peter McIntyre MIt Texas A&M University
Thorium-Cycle Fission for Green Nuclear Power Pt Peter McIntyre MIt Texas A&M University Criteria for green nuclear power: Use the most plentiful fissionable fuels: Thorium and depleted d uranium Operate
More informationOverview 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 informationDT Fusion Power Production in ELM-free H-modes in JET
JET C(98)69 FG Rimini and e JET Team DT Fusion ower roduction in ELM-free H-modes in JET This document is intended for publication in e open literature. It is made available on e understanding at it may
More informationThe Levitated Dipole Experiment: Towards Fusion Without Tritium
The Levitated Dipole Experiment: Towards Fusion Without Tritium Jay Kesner MIT M.S. Davis, J.E. Ellsworth, D.T. Garnier, M.E. Mauel, P.C. Michael, P.P. Woskov MCP I3.110 Presented at the EPS Meeting, Dublin,
More informationFusion/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 informationJoint ITER-IAEA-ICTP Advanced Workshop on Fusion and Plasma Physics October Introduction to Fusion Leading to ITER
2267-1 Joint ITER-IAEA-ICTP Advanced Workshop on Fusion and Plasma Physics 3-14 October 2011 Introduction to Fusion Leading to ITER SNIPES Joseph Allan Directorate for Plasma Operation Plasma Operations
More informationUnpressurized 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 informationPlasma and Fusion Research: Regular Articles Volume 10, (2015)
Possibility of Quasi-Steady-State Operation of Low-Temperature LHD-Type Deuterium-Deuterium (DD) Reactor Using Impurity Hole Phenomena DD Reactor Controlled by Solid Boron Pellets ) Tsuguhiro WATANABE
More informationFusion 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 informationAXISYMMETRIC, WALL-STABILIZED TANDEM MIRRORS. J. Kesner. Plasma Fusion Center Massachusetts Institute of Technology Cambridge, Massachusetts 02139
PFC/JA-84-29 AXISYMMETRIC, WALL-STABILIZED TANDEM MIRRORS J. Kesner Plasma Fusion Center Massachusetts Institute of Technology Cambridge, Massachusetts 02139 August, 1984 ABSTRACT We discuss the possibility
More informationAxial symmetric open magnetic traps with depressed transversal losses of plasmas
Axial symmetric open magnetic traps with depressed transversal losses of plasmas A. Sidorov, S. Golubev, I. Izotov, S. Razin, V. Skalyga and A. Vodopyanov Institute of Applied Physics, RAS, 603950 Nizhny
More informationPolywell Fusion J A E YO UNG PA R K E NN F USION SYMPOSIUM, A P R I L
Polywell Fusion J A E YO UNG PA R K E NERGY MAT T E R CONVERSION CORPORATION E NN F USION SYMPOSIUM, A P R I L 20 20 1 8 History of EMC2 1985 Energy Matter Conversion Corporation is a US-incorporated,
More informationStudies of H Mode Plasmas Produced Directly by Pellet Injection in DIII D
Studies of H Mode Plasmas Produced Directly by Pellet Injection in by P. Gohil in collaboration with L.R. Baylor,* K.H. Burrell, T.C. Jernigan,* G.R. McKee, *Oak Ridge National Laboratory University of
More informationAdditional Heating Experiments of FRC Plasma
Additional Heating Experiments of FRC Plasma S. Okada, T. Asai, F. Kodera, K. Kitano, T. Suzuki, K. Yamanaka, T. Kanki, M. Inomoto, S. Yoshimura, M. Okubo, S. Sugimoto, S. Ohi, S. Goto, Plasma Physics
More informationControl of the fission chain reaction
Control of the fission chain reaction Introduction to Nuclear Science Simon Fraser University Spring 2011 NUCS 342 April 8, 2011 NUCS 342 (Lecture 30) April 8, 2011 1 / 29 Outline 1 Fission chain reaction
More informationChapter IX: Nuclear fusion
Chapter IX: Nuclear fusion 1 Summary 1. General remarks 2. Basic processes 3. Characteristics of fusion 4. Solar fusion 5. Controlled fusion 2 General remarks (1) Maximum of binding energy per nucleon
More informationThe 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 informationFluctuation Suppression during the ECH Induced Potential Formation in the Tandem Mirror GAMMA 10
EXC/P8-2 Fluctuation Suppression during the ECH Induced Potential Formation in the Tandem Mirror GAMMA M. Yoshikawa ), Y. Miyata ), M. Mizuguchi ), Y. Oono ), F. Yaguchi ), M. Ichimura ), T. Imai ), T.
More informationReceived: 30 October 2015; Accepted: 27 November 2015; Published: 4 December 2015 Academic Editor: Jie Lian
Article Progress in Mirror Based Fusion Neutron Source Development A. V. Anikeev 1,2, *, P. A. Bagryansky 1,2, A. D. Beklemishev 1,2, A. A. Ivanov 1,2, E. Yu. Kolesnikov 1, M. S. Korzhavina 1, O. A. Korobeinikova
More informationHIGH PERFORMANCE EXPERIMENTS IN JT-60U REVERSED SHEAR DISCHARGES
HIGH PERFORMANCE EXPERIMENTS IN JT-U REVERSED SHEAR DISCHARGES IAEA-CN-9/EX/ T. FUJITA, Y. KAMADA, S. ISHIDA, Y. NEYATANI, T. OIKAWA, S. IDE, S. TAKEJI, Y. KOIDE, A. ISAYAMA, T. FUKUDA, T. HATAE, Y. ISHII,
More informationIntroduction 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 informationAdaptation 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 informationExternal neutrons sources for fissionbased
External neutrons sources for fissionbased reactors S. David, CNRS/IN2P3/IPN Orsay sdavid@ipno.in2p3.fr S. David,external neutron source for fission-based reactors, IZEST, Orsay, Nov 2017 1 World Energy
More informationInfluence of Beta, Shape and Rotation on the H-mode Pedestal Height
Influence of Beta, Shape and Rotation on the H-mode Pedestal Height by A.W. Leonard with R.J. Groebner, T.H. Osborne, and P.B. Snyder Presented at Forty-Ninth APS Meeting of the Division of Plasma Physics
More informationNuclear Reactions A Z. Radioactivity, Spontaneous Decay: Nuclear Reaction, Induced Process: x + X Y + y + Q Q > 0. Exothermic Endothermic
Radioactivity, Spontaneous Decay: Nuclear Reactions A Z 4 P D+ He + Q A 4 Z 2 Q > 0 Nuclear Reaction, Induced Process: x + X Y + y + Q Q = ( m + m m m ) c 2 x X Y y Q > 0 Q < 0 Exothermic Endothermic 2
More information3.12 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 informationFast ion physics in the C-2U advanced, beam-driven FRC
Fast ion physics in the C-2U advanced, beam-driven FRC Richard Magee for the TAE Team 216 US-Japan Workshop on the Compact Torus August 23, 216! High β FRC embedded in magnetic mirror is a unique fast
More informationSimulation of alpha particle current drive and heating in spherical tokamaks
Simulation of alpha particle current drive and heating in spherical tokamaks R. Farengo 1, M. Zarco 1, H. E. Ferrari 1, 1 Centro Atómico Bariloche and Instituto Balseiro, Argentina. Consejo Nacional de
More informationUppsala University. Access to the published version may require subscription.
Uppsala University This is an accepted version of a paper published in Annals of Nuclear Energy. This paper has been peer-reviewed but does not include the final publisher proof-corrections or journal
More informationNotes on fusion reactions and power balance of a thermonuclear plasma!
SA, 3/2017 Chapter 5 Notes on fusion reactions and power balance of a thermonuclear plasma! Stefano Atzeni See S. Atzeni and J. Meyer-ter-Vehn, The Physics of Inertial Fusion, Oxford University Press (2004,
More informationDevelopment of a Systematic, Self-consistent Algorithm for the K-DEMO Steady-state Operation Scenario
Development of a Systematic, Self-consistent Algorithm for the K-DEMO Steady-state Operation Scenario J.S. Kang 1, J.M. Park 2, L. Jung 3, S.K. Kim 1, J. Wang 1, D. H. Na 1, C.-S. Byun 1, Y. S. Na 1, and
More informationAdvancing Local Helicity Injection for Non-Solenoidal Tokamak Startup
Advancing Local Helicity Injection for Non-Solenoidal Tokamak Startup M.W. Bongard G.M. Bodner, M.G. Burke, R.J. Fonck, J.L. Pachicano, J.M. Perry, C. Pierren, J.A. Reusch, A.T. Rhodes, N.J. Richner, C.
More informationTWO APPROACHES TO NEUTRON PRODUCTION FOR ACCELERATOR BREEDING AND RADWASTE TRANSMUTATION. V.N. Sosnin, Yu. A. Korovin (Obninsk Inst.
TWO APPROACHES TO NEUTRON PRODUCTION FOR ACCELERATOR BREEDING AND RADWASTE TRANSMUTATION V.N. Sosnin, Yu. A. Korovin (Obninsk Inst., Russia) 145 TWO APPROACHES TO NEUTRON PRODUCTION FOR ACCELERATOR BREEDING
More informationSTELLARATOR REACTOR OPTIMIZATION AND ASSESSMENT
STELLARATOR REACTOR OPTIMIZATION AND ASSESSMENT J. F. Lyon, ORNL ARIES Meeting October 2-4, 2002 TOPICS Stellarator Reactor Optimization 0-D Spreadsheet Examples 1-D POPCON Examples 1-D Systems Optimization
More informationPhysics & 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 informationPlasma Heating by an Electron Beam in Corrugated Magnetic Field
Plasma Heating by an Electron Beam in Corrugated Magnetic Field V.V. Postupaev, A.V. Arzhannikov, V.T. Astrelin, A.M. Averkov, A.D. Beklemishev, A.V. Burdakov, I.A. Ivanov, M.V. Ivantsivsky, V.S. Koidan,
More informationA Method of Knock-on Tail Observation Accounting Temperature Fluctuation Using 6 Li+T/D+T Reaction in Deuterium Plasma
A Method of Knock-on Tail Observation Accounting Temperature Fluctuation Using 6 Li+T/D+T Reaction in Deuterium Plasma Yasuko KAWAMOTO and Hideaki MATSUURA Department of Applied Quantum Physics and Nuclear
More informationPLASMA CONFINEMENT IN THE GAMMA 10 TANDEM MIRROR
PLASMA CONFINEMENT IN THE GAMMA TANDEM MIRROR K.YATSU, L.G.BRUSKIN, T.CHO, M.HAMADA, M.HIRATA, H.HOJO, M.ICHIMURA, K.ISHII, A.ITAKURA, I.KATANUMA, Y.KIWAMOTO, J.KOHAGURA, S.KUBOTA, A.MASE, Y.NAKASHIMA,
More informationEstimations of Beam-Beam Fusion Reaction Rates in the Deuterium Plasma Experiment on LHD )
Estimations of Beam-Beam Fusion Reaction Rates in the Deuterium Plasma Experiment on LHD ) Masayuki HOMMA, Sadayoshi MURAKAMI, Hideo NUGA and Hiroyuki YAMAGUCHI Department of Nuclear Engineering, Kyoto
More informationPlasma Wall Interactions in Tokamak
Plasma Wall Interactions in Tokamak Dr. C Grisolia, Association Euratom/CEA sur la fusion, CEA/Cadarache Outline 1. Conditions for Fusion in Tokamaks 2. Consequences of plasma operation on in vessel materials:
More informationCharacteristics of the H-mode H and Extrapolation to ITER
Characteristics of the H-mode H Pedestal and Extrapolation to ITER The H-mode Pedestal Study Group of the International Tokamak Physics Activity presented by T.Osborne 19th IAEA Fusion Energy Conference
More informationPHYSICS OF CFETR. Baonian Wan for CFETR physics group Institute of Plasma Physcis, Chinese Academy of Sciences, Hefei, China.
PHYSICS OF CFETR Baonian Wan for CFETR physics group Institute of Plasma Physcis, Chinese Academy of Sciences, Hefei, China Dec 4, 2013 Mission of CFETR Complementary with ITER Demonstration of fusion
More informationTURBULENT TRANSPORT THEORY
ASDEX Upgrade Max-Planck-Institut für Plasmaphysik TURBULENT TRANSPORT THEORY C. Angioni GYRO, J. Candy and R.E. Waltz, GA The problem of Transport Transport is the physics subject which studies the physical
More informationD- 3 He HA tokamak device for experiments and power generations
D- He HA tokamak device for experiments and power generations US-Japan Fusion Power Plant Studies Contents University of Tokyo, Japan January -, 5 O.Mitarai (Kyushu Tokai University).Motivation.Formalism,
More informationWhat we ve learned so far about the Stability of Plasma Confined by a Laboratory Dipole Magnet
What we ve learned so far about the Stability of Plasma Confined by a Laboratory Dipole Magnet M. E. Mauel and the CTX and LDX Experimental Teams Annual Meeting of the Division of Plasma Physics Philadelphia,
More informationExperimental Facility to Study MHD effects at Very High Hartmann and Interaction parameters related to Indian Test Blanket Module for ITER
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,
More informationDesign window analysis of LHD-type Heliotron DEMO reactors
Design window analysis of LHD-type Heliotron DEMO reactors Fusion System Research Division, Department of Helical Plasma Research, National Institute for Fusion Science Takuya GOTO, Junichi MIYAZAWA, Teruya
More informationHelium Catalyzed D-D Fusion in a Levitated Dipole
Helium Catalyzed D-D Fusion in a Levitated Dipole Jay Kesner, L. Bromberg, MIT D.T. Garnier, A. Hansen, M.E. Mauel Columbia University APS 2003 DPP Meeting, Albuquerque October 27, 2003 Columbia University
More informationTerry Kammash and Myoung-Jae Lee Department of Nuclear Engineering The University of Michigan Ann Arbor, MI (313)
ANTIPROTON ANNIHILATION DYNAMICS IN FUSION ROCKET Terry Kammash and Myoung-Jae Lee Department of Nuclear Engineering The University of Michigan Ann Arbor, MI 4819 (313) 764-25 THE GASDYNAMIC Abstract The
More informationMission 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 informationDevelopment of Experiment on Multiple-Mirror Trap for Fusion in Budker INP
EX/P8-5 Development of Experiment on Multiple-Mirror Trap for Fusion in Budker INP A.V. Burdakov,, A.V. Arzhannikov,3, V.T. Astrelin,3, A. P. Avrorov, V.I. Batkin,3, A.D. Beklemishev,3, V.S. Burmasov,3,
More informationShear Flow Generation in Stellarators - Configurational Variations
Shear Flow Generation in Stellarators - Configurational Variations D. A. Spong 1), A. S. Ware 2), S. P. Hirshman 1), J. H. Harris 1), L. A. Berry 1) 1) Oak Ridge National Laboratory, Oak Ridge, Tennessee
More informationPower Installations based on Activated Nuclear Reactions of Fission and Synthesis
Yu.V. Grigoriev 1,2, A.V. Novikov-Borodin 1 1 Institute for Nuclear Research RAS, Moscow, Russia 2 Joint Institute for Nuclear Research, Dubna, Russia Power Installations based on Activated Nuclear Reactions
More information- Effect of Stochastic Field and Resonant Magnetic Perturbation on Global MHD Fluctuation -
15TH WORKSHOP ON MHD STABILITY CONTROL: "US-Japan Workshop on 3D Magnetic Field Effects in MHD Control" U. Wisconsin, Madison, Nov 15-17, 17, 2010 LHD experiments relevant to Tokamak MHD control - Effect
More informationAdvanced Tokamak Research in JT-60U and JT-60SA
I-07 Advanced Tokamak Research in and JT-60SA A. Isayama for the JT-60 team 18th International Toki Conference (ITC18) December 9-12, 2008 Ceratopia Toki, Toki Gifu JAPAN Contents Advanced tokamak development
More informationDIII D UNDERSTANDING AND CONTROL OF TRANSPORT IN ADVANCED TOKAMAK REGIMES IN DIII D QTYUIOP C.M. GREENFIELD. Presented by
UNDERSTANDING AND CONTROL OF TRANSPORT IN ADVANCED TOKAMAK REGIMES IN Presented by C.M. GREENFIELD for J.C. DeBOO, T.C. LUCE, B.W. STALLARD, E.J. SYNAKOWSKI, L.R. BAYLOR,3 K.H. BURRELL, T.A. CASPER, E.J.
More informationPedestals and Fluctuations in C-Mod Enhanced D α H-modes
Pedestals and Fluctuations in Enhanced D α H-modes Presented by A.E.Hubbard With Contributions from R.L. Boivin, B.A. Carreras 1, S. Gangadhara, R. Granetz, M. Greenwald, J. Hughes, I. Hutchinson, J. Irby,
More informationNeutron Testing: What are the Options for MFE?
Neutron Testing: What are the Options for MFE? L. El-Guebaly Fusion Technology Institute University of Wisconsin - Madison http://fti.neep.wisc.edu/uwneutronicscenterofexcellence Contributors: M. Sawan
More informationECR ION SOURCES : A BRIEF HISTORY AND LOOK INTO THE NEXT GENERATION
ECR ION SOURCES : A BRIEF HISTORY AND LOOK INTO THE NEXT GENERATION T. Nakagawa, Nishina center for accelerator based science, RIKEN, Hirosawa 2-1, Wako, Saitama 351-0198, Japan Abstract In the last three
More informationA Hybrid Inductive Scenario for a Pulsed- Burn RFP Reactor with Quasi-Steady Current. John Sarff
A Hybrid Inductive Scenario for a Pulsed- Burn RFP Reactor with Quasi-Steady Current John Sarff 12th IEA RFP Workshop Kyoto Institute of Technology, Kyoto, Japan Mar 26-28, 2007 The RFP fusion development
More informationA Polywell p+11b Power Reactor Joel G. Rogers, Ph.D.
A Polywell p+11b Power Reactor Joel G. Rogers, Ph.D. rogersjg@telus.net Aneutronic fusion is the holy grail of fusion power research. A new method of operating Polywell was developed which maintains a
More informationMUSE-4 BENCHMARK CALCULATIONS USING MCNP-4C AND DIFFERENT NUCLEAR DATA LIBRARIES
MUSE-4 BENCHMARK CALCULATIONS USING MCNP-4C AND DIFFERENT NUCLEAR DATA LIBRARIES Nadia Messaoudi and Edouard Mbala Malambu SCK CEN Boeretang 200, B-2400 Mol, Belgium Email: nmessaou@sckcen.be Abstract
More informationSTATUS AND PROSPECTS OF GOL-3 MULTIPLE-MIRROR TRAP.
STATUS AND PROSPECTS OF GOL-3 MULTIPLE-MIRROR TRAP A. Burdakov a,c, A. Arzhannikov a,b, V. Astrelin a, V. Batkin a, V. Burmasov a,b, G. Derevyankin a, V. Ivanenko a, I. Ivanov a, M. Ivantsivskiy a,c, I.
More informationSpherical 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 informationThe 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 informationGA A22689 SLOW LINER FUSION
GA A22689 SLOW LINER FUSION by AUGUST 1997 DISCLAIMER This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any
More informationIssues 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 informationFusion Nuclear Science - Pathway Assessment
Fusion Nuclear Science - Pathway Assessment C. Kessel, PPPL ARIES Project Meeting, Bethesda, MD July 29, 2010 Basic Flow of FNS-Pathways Assessment 1. Determination of DEMO/power plant parameters and requirements,
More informationIntegral Benchmark Experiments of the Japanese Evaluated Nuclear Data Library (JENDL)-3.3 for the Fusion Reactor Design
1 Integral Benchmark Experiments of the Japanese Evaluated Nuclear Data Library (JENDL)-3.3 for the Fusion Reactor Design T. Nishitani 1), K. Ochiai 1), F. Maekawa 1), K. Shibata 1), M. Wada 2), I. Murata
More informationGeneral Physics (PHY 2140)
General Physics (PHY 2140) Lecture 20 Modern Physics Nuclear Energy and Elementary Particles Fission, Fusion and Reactors Elementary Particles Fundamental Forces Classification of Particles Conservation
More informationA-BAQUS A multi-entry graph assisting the neutronic design of an ADS Case study: EFIT
Fifth International Workshop on the Utilisation and Reliability of High Power Proton Accelerator SCK-CEN Mol, Belgium 6-9 May 7 A-BAQUS A multi-entry graph assisting the neutronic design of an ADS Case
More informationThorium Energy Alliance Conference 6 Chicago, May 29, 2014
Thorium Energy Alliance Conference 6 Chicago, May 29, 2014 Th/U233 breeding at zero cost in stacked D+D colliding beam fusion exyder mini cells financed from the sale of by products 3He and Tritium Bogdan
More informationNuclear Cross-Section Measurements at the Manuel Lujan Jr. Neutron Scattering Center
1 Nuclear Cross-Section Measurements at the Manuel Lujan Jr. Neutron Scattering Center M. Mocko 1, G. Muhrer 1, F. Tovesson 1, J. Ullmann 1 1 LANSCE, Los Alamos National Laboratory, Los Alamos NM 87545,
More informationThe New Sorgentina Fusion Source Project
The New Sorgentina Fusion Source Project P. Agostini, P. Console Camprini, D. Bernardi, M. Pillon, M. Frisoni, M. Angelone, A. Pietropaolo, P. Batistoni, A. Pizzuto ENEA Agenzia Nazionale per le Nuove
More informationChapter V: Interactions of neutrons with matter
Chapter V: Interactions of neutrons with matter 1 Content of the chapter Introduction Interaction processes Interaction cross sections Moderation and neutrons path For more details see «Physique des Réacteurs
More informationMagnetic 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 informationRecent Development of LHD Experiment. O.Motojima for the LHD team National Institute for Fusion Science
Recent Development of LHD Experiment O.Motojima for the LHD team National Institute for Fusion Science 4521 1 Primary goal of LHD project 1. Transport studies in sufficiently high n E T regime relevant
More informationLecture 14, 8/9/2017. Nuclear Reactions and the Transmutation of Elements Nuclear Fission; Nuclear Reactors Nuclear Fusion
Lecture 14, 8/9/2017 Nuclear Reactions and the Transmutation of Elements Nuclear Fission; Nuclear Reactors Nuclear Fusion Nuclear Reactions and the Transmutation of Elements A nuclear reaction takes place
More informationComparison 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