DOCSLIB.ORG

Progress of Indirect Drive Inertial Confinement Fusion in the Us

Total Page：16

File Type：pdf, Size：1020Kb

Download full-text PDF Read full-text
Progress of Indirect Drive Inertial Confinement Fusion in the Us Kline DOI:10.1088/1741-4326/ab1ecf OV/2-5 Progress of Indirect Drive Inertial Confinement Fusion in the USA J. L. Kline1, S. H. Batha1, L. R. Benedetti2, D. Bennett2, S. Bhandarkar2, L. F. Berzak-Hopkines2, J. Biener2, M. M. Biener2, R. Bionta2, E. Bond2, D. Bradley2, P. A. Bradley1, T. Braun2, D. A. Callahan2, J. Caggiano2, T. Cardenas2, C. Cerjjan2, B. Cagadas2, D. Clark2, C. Castro2, W. S. Daughton1, E. L. Dewald2, T. Döppner2, L. Divol2, E. S. Dodd1, R. Dylla-Spears2, M. Eckart2, D. Edgell3, M. Farrell4, J. Field2, F. Fierro1, D. N. Fittinghoff2, M. Gatu-Johnson5, S. Johnson2, G. Grim2, N. Guler1, S. Haan2, B. M. Haines1, C. E. Hamilton1, A. V. Hamza2, E. P. Hartouni2, R. Hatarik2, K. Hernderson1, H. W. Herrmann1, D. Hinkel2, D. D. Ho2, M. Hohenburger2, D. Hoover4, H. Huang4, M. L. Hoppe4, O. A. Hurricane2, N. Izumi2, O. S. Jones2, S. Khan2, B. J. Kozioziemski2, C. Kong2, J. Kroll2, G. A. Kyrala2, R. J. Leeper2, S. LePape2, E. Loomis1, T. Ma2, A. J. Mackinnon2, A. G. MacPhee2, S. MacLaren2, L. Masse2, J. McNaney2, N. B. Meezan2, J. F. Merrill1, E. C. Merritt1, J. L. Milovich2, D. S. Montgomery1, J. Moody2, A. Nikroo2, J. Oertel1, R. E. Olson1, A. Pak2, S. Palaniyappan1, P. Patel2, B. M. Patterson1, T. S. Perry1, R. R. Peterson1, E. Piceno2, J. E. Ralph2, R. B. Randolph1, N. Rice4, H. F. Robey2, J. S. Ross2, J. R. Rygg3, M. R. Sacks1, J. Sauppe1, J. Salmonson2, D. Sayre2, J. D. Sater2, M. Schneider2, M. Schoff4, D. W. Schmidt1, S. Sepke2, R. Seugling2, R. C. Shah3, M. Stadermann2, W. Stoeffl2, D. J. Strozzi2, R. Tipton2, C. Thomas2, R. P. J. Town2, P. L. Volegov1, C. Walters2, M. Wang2, C. Wilde1, C. Wilson1, E. Woerner2, C. Yeamans2, S. A. Yi1, B. Yoxall2, A. B. Zylstra1, J. Kilkenny4, O. L. Landen2, W. W. Hsing2, and M. J. Edwards2 1Los Alamos National Laboratory (LANL), Los Alamos, NM 87545, USA 2Lawrence Livermore National Laboratory (LLNL), Livermore, CA 94550, USA 3Laboratory for Laser Energetics, University of Rochester, Rochester, NY 14623, USA 4General Atomics, San Diego, CA 92186, USA 5Massachusetts Institute of Technology (MIT), Cambridge, MA 02139, USA Corresponding Author: J. L. Kline, [email protected] Indirect drive converts high power laser into X-rays using small high-Z cavities called hohlraums. X-rays generated at the hohlraum walls drive a capsule filled with DT fusion fuel. Recent experiments have produced fusion yields exceeding 50 kJ where alpha heating provides „ 3ˆ increase in yield over P dV work. Comparison of the results to the common Lawson criterion suggests the current implosions performance is „ 30% from conditions expected to initiate thermonuclear gain. Improvements to close the gap on the last „ 30% are challenging requiring optimization of the target/implosions and the laser to extract maximum energy. The US programme has a three-pronged approach to maximize target performance each closing some portion of the gap. The first item is optimizing the hohlraum to couple more energy to the capsule while maintaining symmetry control. Novel hohlraum designs are being pursued that enable larger capsule to be driven symmetrically to both reduce 3D effects and increase energy coupled to the capsule. The second issue being addressed is capsule stability. Seeding of instabilities by the hardware used to mount the capsule and fill it with DT fuel remains a concern. Work such reducing the impact of the DT fill tubes and novel capsule mounts such as three sets of two single wire stands forming a cage, as opposed to the thin membranes currently used, are being pursed to reduce the effect of mix on the capsule implosions. There is also growing evidence native capsule seeds such as microstructure may be playing a role on limiting capsule performance and dedicated experiments are being developed to better understand the phenomenon. The last area of emphasis is the laser. As technology progresses and understanding of laser damage/mitigation advances, increasing the laser energy to as much as 2.6 MJ at 351 nm and increasing the laser power to 600 TW seems possible. This would increase the amount of energy available to couple to the capsule and allow larger capsules potentially increasing the hot spot pressure and confinement time. The combination Published as a journal article in Nuclear Fusion http://iopscience.iop.org/article/10.1088/1741-4326/ab1ecf OV/2-5 DOI:10.1088/1741-4326/ab1ecf Kline of each of these focus areas have the potential to produce conditions to initiate thermonuclear ignition. The current understanding, status, and plans for near term research in each of these areas will be presented in the context of what is believed to be needed to obtain burning plasmas on NIF. Published as a journal article in Nuclear Fusion http://iopscience.iop.org/article/10.1088/1741-4326/ab1ecf PROGRESS OF INDIRECT DRIVE INERTIAL CONFINEMENT FUSION IN THE US J. L. KLINE,1 S. H. BATHA,1 L. R. BENEDETTI,2 D. BENNETT,2 S. BHANDARKAR,2 L. F. BERZAK HOPKINS,2 J. BIENER,2 M. M. BIENER2, R BIONTA,2 E. BOND,2 D. BRADLEY,2 P. A. BRADELY,1 T. BRAUN,2 D. A. CALLAHAN,2 J. CAGGIANO,2 T. CARDENAS,1 C. CERJAN,2 B. CAGADAS,2 D. CLARK,2 C. CASTRO,2 W. S. DAUGHTON,1 E. L. DEWALD,2 T. DÖPPNER,2 L. DIVOL,2 E. S. DODD,1 R. DYLLA-SPEARS,2 M. ECKART,2 D. EDGELL,4 M. FARRELL,3 J. FIELD,2 F. FIERRO,1 D. N. FITTINGHOFF,2 M. GATU JOHNSON,5 S. JOHNSON,2 G. GRIM,2 N. GULER,1 S. HAAN,2 B. M. HAINES,1 C. E. HAMILTON,1 A. V. HAMZA,2 E P. HARTOUNI,2 B. HAINES,1 R. HATARIK,2 K. HENDERSON,1 H.W. HERRMANN,1 D. HINKEL,2 D. HO,2 M. HOHENBERGER,2 D. HOOVER,3 H. HUANG,3 M. L. HOPPE,3 O. A. HURRICANE,2 N. IZUMI,2 O. S. JONES,2 S. KHAN,2 B. J. KOZIOZIEMSKI,2 C. KONG,2 J. KROLL,2 G. A. KYRALA,1 R. J. LEEPER,1 S. LEPAPE,2 E. LOOMIS,1 T. MA, 2 A. J. MACKINNON,2 A. G. MACPHEE,2 S. MACLAREN,2 L. MASSE,2 J. MCNANEY,2 N. B. MEEZAN,2 J. F. MERRILL,1 E. C. MERRITT,1 J. L. MILOVICH,2 D. S. MONTGOMERY,1 J. MOODY,2 A. NIKROO,2 J. OERTEL,1 R. E. OLSON,1 A. PAK,2 S. PALANIYAPPAN,1 P. PATEL,2 B. M. PATTERSON,1 T. S. PERRY,1 R. R. PETERSON,1 E. PICENO,2 J. E. RALPH,2 R. B. RANDOLPH,1 N. RICE,3H. F. ROBEY,2 J. S. ROSS,2 J. R. RYGG,4 M. R. SACKS,1 J. SAUPPE,1 J. SALMONSON,2 D. SAYRE,2 J. D. SATER,2 J. SAUPPE,1 M. SCHNEIDER,2 M. SCHOFF,3 D. W. SCHMIDT,1 S, SEPKE,2 R. SEUGLING,2 R. C. SHAH,4M STADERMANN,2 W. STOEFFL,2 D. J. STROZZI,2 R. TIPTON,2 C. THOMAS,2 RPJ TOWN,2 P. L. VOLEGOV,1 C.WALTERS,2 M. WANG,2 C. WILDE, 1 C. WILSON,1E WOERNER,2 C. YEAMANS,2 S. A. YI,1 B. YOXALL,2 A. B. ZYLSTRA,1 J. KILKENNY,2 O. L. LANDEN, 2 W. HSING, 2 AND M. J. EDWARDS2 1Los Alamos National Laboratory, Los Alamos, NM, USA 2Lawrence Livermore National Laboratory, Livermore, CA, USA 3General Atomics, San Diego, CA, USA 4Laboratory for Laser Energetics, Rochester, NY, USA 5Massechusettes Institute of Technology, Boston, MA, USA Abstract Indirect drive converts high power laser into x rays using small high-Z cavities called hohlraums. X rays generated at the hohlraum walls drive a capsule filled with DT fusion fuel. Recent experiments have produced fusion yields exceeding 50 kJ where alpha heating provides ~3x increase in yield over PdV work. Improvements needed to approach ignition are challenging requiring optimization of the target/implosions and the laser to extract maximum energy. The US program has a three-pronged approach to maximize target performance each closing some portion of the gap. The first item is optimizing the hohlraum to couple more energy to the capsule while maintaining symmetry control. Novel hohlraum designs are being pursued that enable larger capsule to be driven symmetrically to both reduce 3D effects and increase energy coupled to the capsule. The second issue being addressed is capsule stability. Seeding of instabilities by the hardware used to mount the capsule and fill it with DT fuel remains a concern. Work such reducing the impact of the DT fill tubes and novel capsule mounts such as three sets of two single wire stands forming a cage, as opposed to the thin membranes currently used, are being pursed to reduce the effect of mix on the capsule implosions. There is also growing evidence native capsule seeds such as micro-structure may be playing a role on limiting capsule performance and dedicated experiments are being developed to better understand the phenomenon. The last area of emphasis is the laser. As technology progresses and understanding of laser damage/mitigation advances, increasing the laser energy seems possible. This would increase the amount of energy available to couple to the capsule and allow larger capsules potentially increasing the hot spot pressure and confinement time. The combination of each of these focus areas have the potential to produce conditions to initiate thermo-nuclear ignition. 1. INTRODUCTION Indirect drive Inertial Confinement Fusion (ICF) converts high power laser light into x rays traditionally using small cylindrically-shaped, high-Z radiation cavities called hohlraums.
Load more

Recommended publications
  • Status of ITER Neutron Diagnostic Development
    INSTITUTE OF PHYSICS PUBLISHING and INTERNATIONAL ATOMIC ENERGY AGENCY NUCLEAR FUSION Nucl. Fusion 45 (2005) 1503–1509 doi:10.1088/0029-5515/45/12/005 Status of ITER neutron diagnostic development A.V. Krasilnikov1, M. Sasao2, Yu.A. Kaschuck1, T. Nishitani3, P. Batistoni4, V.S. Zaveryaev5, S. Popovichev6, T. Iguchi7, O.N. Jarvis6,J.Kallne¨ 8, C.L. Fiore9, A.L. Roquemore10, W.W. Heidbrink11, R. Fisher12, G. Gorini13, D.V. Prosvirin1, A.Yu. Tsutskikh1, A.J.H. Donne´14, A.E. Costley15 and C.I. Walker16 1 SRC RF TRINITI, Troitsk, Russian Federation 2 Tohoku University, Sendai, Japan 3 JAERI, Tokai-mura, Japan 4 FERC, Frascati, Italy 5 RRC ‘Kurchatov Institute’, Moscow, Russian Federation 6 Euratom/UKAEA Fusion Association, Culham Science Center, Abingdon, UK 7 Nagoya University, Nagoya, Japan 8 Uppsala University, Uppsala, Sweden 9 PPL, MIT, Cambridge, MA, USA 10 PPPL, Princeton, NJ, USA 11 UC Irvine, Los Angeles, CA, USA 12 GA, San Diego, CA, USA 13 Milan University, Milan, Italy 14 FOM-Rijnhuizen, Netherlands 15 ITER IT, Naka Joint Work Site, Naka, Japan 16 ITER IT, Garching Joint Work Site, Garching, Germany E-mail: [email protected] Received 7 December 2004, accepted for publication 14 September 2005 Published 22 November 2005 Online at stacks.iop.org/NF/45/1503 Abstract Due to the high neutron yield and the large plasma size many ITER plasma parameters such as fusion power, power density, ion temperature, fast ion energy and their spatial distributions in the plasma core can be measured well by various neutron diagnostics. Neutron diagnostic systems under consideration and development for ITER include radial and vertical neutron cameras (RNC and VNC), internal and external neutron flux monitors (NFMs), neutron activation systems and neutron spectrometers.
    [Show full text]
  • 1958 Geneva Conference on the Discontinuation of Nuclear Weapons
    1 2 3 4 5 6 7 8 Presidential Decisions on Stockpile Stewardship Test-Based Stewardship and the Cold War Transitioning to Stockpile Stewardship Science: Research, Development, and Technology Deterrence and the Life Extension Program Global Nuclear Security Timeline of U.S. Stockpile Stewardship Innovation The Path Forward Today, I am announcing my “decision to negotiate a true zero-yield comprehensive test ban.” U.S. President Bill Clinton, August 11, 1995 The National Defense Authorization Act for fiscal year 1994 (P.L. 103-160) estab- lished the Stockpile Stewardship Program (SSP) to sustain the nuclear deterrent in the absence of nuclear explosive testing. The SSP supports U.S. national security missions through leading-edge scientific, engineering, and technical tools and expertise – a U.S. response to the end of the Cold War and the need to remake the global nuclear landscape. One year later, on August 11, 1995, Presi- dent Bill Clinton announced that the United States would support a “zero yield” Compre- hensive Nuclear-Test-Ban Treaty (CTBT): “I am assured by the Secretary of Energy and the Directors of our nu- clear weapons labs that we can meet the challenge of maintaining our nuclear deterrent under a Compre- hensive Test-Ban Treaty through a Science-Based Stockpile Stewardship program without nuclear testing.” This year, the Nation and the Department of Energy (DOE) celebrate the 20th anniver- sary of that announcement and the scientific and technical capabilities that have devel- oped to support this policy direction. The national investment in stockpile stewardship has enabled resolution of many stockpile issues and provided more detailed knowledge than what could have been attained through nuclear explosive testing.
    [Show full text]
  • An Integrated Model for Materials in a Fusion Power Plant: Transmutation, Gas Production, and Helium Embrittlement Under Neutron Irradiation
    Home Search Collections Journals About Contact us My IOPscience An integrated model for materials in a fusion power plant: transmutation, gas production, and helium embrittlement under neutron irradiation This article has been downloaded from IOPscience. Please scroll down to see the full text article. 2012 Nucl. Fusion 52 083019 (http://iopscience.iop.org/0029-5515/52/8/083019) View the table of contents for this issue, or go to the journal homepage for more Download details: IP Address: 193.52.216.130 The article was downloaded on 13/11/2012 at 13:27 Please note that terms and conditions apply. IOP PUBLISHING and INTERNATIONAL ATOMIC ENERGY AGENCY NUCLEAR FUSION Nucl. Fusion 52 (2012) 083019 (12pp) doi:10.1088/0029-5515/52/8/083019 An integrated model for materials in a fusion power plant: transmutation, gas production, and helium embrittlement under neutron irradiation M.R. Gilbert, S.L. Dudarev, S. Zheng, L.W. Packer and J.-Ch. Sublet EURATOM/CCFE Fusion Association, Culham Centre for Fusion Energy, Abingdon, Oxfordshire OX14 3DB, UK E-mail: [email protected] Received 16 January 2012, accepted for publication 11 July 2012 Published 1 August 2012 Online at stacks.iop.org/NF/52/083019 Abstract The high-energy, high-intensity neutron fluxes produced by the fusion plasma will have a significant life-limiting impact on reactor components in both experimental and commercial fusion devices. As well as producing defects, the neutrons bombarding the materials initiate nuclear reactions, leading to transmutation of the elemental atoms. Products of many of these reactions are gases, particularly helium, which can cause swelling and embrittlement of materials.
    [Show full text]
  • Neutronic Model of a Fusion Neutron Source
    STATIC NEUTRONIC CALCULATION OF A FUSION NEUTRON SOURCE S.V. Chernitskiy1, V.V. Gann1, O. Ågren2 1“Nuclear Fuel Cycle” Science and Technology Establishment NSC KIPT, Kharkov, Ukraine; 2Uppsala University, Ångström Laboratory, Uppsala, Sweden The MCNPX numerical code has been used to model a fusion neutron source based on a combined stellarator- mirror trap. Calculation results for the neutron flux and spectrum inside the first wall are presented. Heat load and irradiation damage on the first wall are calculated. PACS: 52.55.Hc, 52.50.Dg INTRODUCTION made in Ref. [5] indicates that under certain conditions Powerful sources of fusion neutrons from D-T nested magnetic surfaces could be created in a reaction with energies ~ 14 MeV are of particular stellarator-mirror machine. interest to test suitability of materials for use in fusion Some fusion neutrons are generated outside the reactors. Developing materials for fusion reactors has main part near the injection point. There is a need of long been recognized as a problem nearly as difficult protection from these neutrons. and important as plasma confinement, but it has The purpose is to calculate the neutron spectrum received only a fraction of attention. The neutron flux in inside neutron exposing zone of the installation and a fusion reactor is expected to be about 50-100 times compute the radial leakage of neutrons through the higher than in existing pressurized water reactors. shield. Furthermore, the high-energy neutrons will produce Another problem studied in the paper concerns to hydrogen and helium in various nuclear reactions that the determination of the heat load and irradiation tend to form bubbles at grain boundaries of metals and damage of the first wall of the device, where will be a result in swelling, blistering or embrittlement.
    [Show full text]
  • Revamping Fusion Research Robert L. Hirsch
    Revamping Fusion Research Robert L. Hirsch Journal of Fusion Energy ISSN 0164-0313 Volume 35 Number 2 J Fusion Energ (2016) 35:135-141 DOI 10.1007/s10894-015-0053-y 1 23 Your article is protected by copyright and all rights are held exclusively by Springer Science +Business Media New York. This e-offprint is for personal use only and shall not be self- archived in electronic repositories. If you wish to self-archive your article, please use the accepted manuscript version for posting on your own website. You may further deposit the accepted manuscript version in any repository, provided it is only made publicly available 12 months after official publication or later and provided acknowledgement is given to the original source of publication and a link is inserted to the published article on Springer's website. The link must be accompanied by the following text: "The final publication is available at link.springer.com”. 1 23 Author's personal copy J Fusion Energ (2016) 35:135–141 DOI 10.1007/s10894-015-0053-y POLICY Revamping Fusion Research Robert L. Hirsch1 Published online: 28 January 2016 Ó Springer Science+Business Media New York 2016 Abstract A fundamental revamping of magnetic plasma Introduction fusion research is needed, because the current focus of world fusion research—the ITER-tokamak concept—is A practical fusion power system must be economical, virtually certain to be a commercial failure. Towards that publically acceptable, and as simple as possible from a end, a number of technological considerations are descri- regulatory standpoint. In a preceding paper [1] the ITER- bed, believed important to successful fusion research.
    [Show full text]
  • Fusion: the Way Ahead
    Fusion: the way ahead Feature: Physics World March 2006 pages 20 - 26 The recent decision to build the world's largest fusion experiment - ITER - in France has thrown down the gauntlet to fusion researchers worldwide. Richard Pitts, Richard Buttery and Simon Pinches describe how the Joint European Torus in the UK is playing a key role in ensuring ITER will demonstrate the reality of fusion power At a Glance: Fusion power • Fusion is the process whereby two light nuclei bind to form a heavier nucleus with the release of energy • Harnessing fusion on Earth via deuterium and tritium reactions would lead to an environmentally friendly and almost limitless energy source • One promising route to fusion power is to magnetically confine a hot, dense plasma inside a doughnut-shaped device called a tokamak • The JET tokamak provides a vital testing ground for understanding the physics and technologies necessary for an eventual fusion reactor • ITER is due to power up in 2016 and will be the next step towards a demonstration fusion power plant, which could be operational by 2035 By 2025 the Earth's population is predicted to reach eight billion. By the turn of the next century it could be as many as 12 billion. Even if the industrialized nations find a way to reduce their energy consumption, this unprecedented increase in population - coupled with rising prosperity in the developing world - will place huge demands on global energy supplies. As our primary sources of energy - fossil fuels - begin to run out, and burning them causes increasing environmental concerns, the human race faces the challenge of finding new energy sources.
    [Show full text]
  • Memorandum to Participants JASON 1994 Summer Study
    Hydronnclear Testing and the Comprehensive Test Ban: Memorandum to Participants JASON 1994 Summer Study Natural Resources Defense Council, Inc. 1350 New York Avenue, NW, Suite 300 Washington, D.C. 20005 Tel (main): (202) 783-7800 Cochran (direct dial): (202) 624-9329 Paine (direct dial): (202) 624-9350 Fax: (202) 783-5917 INTERNET: [email protected] Although no commonly accepted defInition exists, a "hydronuclear test" may be generally described as a nuclear weapons test, or high-explosive driven criticality experiment, characterized by a nuclear energy release that is insuffIcient to heat the core material to the plasma temperatures that would cause it to explode "like a bomb." In such a test, the TNT equivalent energy release from fission would therefore not exceed the amount released by the chemical high explosive used to compress the fIssile material, and could be considerably ,less. Nuclear-weapon states, and possibly other states, also perform high-explosive driven implosion experiments using fusjon material, although" these' are not nonnally characterized as "hydronuclear tests". Hydronuclear tests can serve a useful role in the development of the full spectrum of unboosted fIssion weapons, including'first generation nuclear weapons of the implosion type with yields in the 5 to 30 kiloton range, more sophisticated designs with yields up to about a megaton, and advanced micro-nuclear weapons with yields of 5 to 500 tons. For pure fIssion weapons hydronuclear tests can be used to:' * optimize the timing of initiation of the
    [Show full text]
  • The Tokamak As a Neutron Source
    PREPARED FOR THE U.S. DEPARTMENT OF ENERGY, UNDER CONTRACT DE-AC02-76-CHO-3073 PPPL-2656 PPPL-2656 UC-420 THE TOKAMAK AS A NEUTRON SOURCE BY H.W. HENDEL AND D.L JASSBY November 1989 PMNCITON PLASMA PHYSICS LASOffATORY PRINCETON UNIVERSITY, PRINCETON, NEW JERSEY NOTICE Available from: National Technical Information Service U.S. Department of Commerce 5285 Port Royal Road Springfield. Virginia 22161 703-487-4650 Use the following price codes when ordering: Price: Printed Copy A04 Microfiche A01 THE TOKAMAK AS A NEUTRON SOURCE by H.W. Hendel and D.L. Jassby PPPL—2656 DE90 001821 Princeton Plasma Physics Laboratory Princeton University Princeton, N.J. 08543 ABSTRACT This paper describes the tokamak in its role as a neutron source, with emphasis on experimental results for D-D neutron production. The sections summarize tokamak operation, sources of fusion and non-fusion neutrons, principal nsutron detection methods and their calibration, neutron energy spectra and fluxes outside the tokamak plasma chamber, history of neutron production in tokamaks, neutron emission and fusion power gain from JET and TFTR (the largest present-day tokamaks), and D-T neutron production from burnup of D-D tritons. This paper also discusses the prospects for future tokamak neutron production and potential applications of tokamak neutron sources. DISCLAIMER This report was prepared as JH account or work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsi­ bility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or repre^r-s that its use would not infringe privately owned rights.
    [Show full text]
  • Neutronics Analyses for a Stellarator Power Reactor Based on the HELIAS Concept
    Neutronics analyses for a stellarator power reactor based on the HELIAS concept André Häußlera, Felix Warmerb, Ulrich Fischera aKarlsruhe Institute of Technology (KIT), Institute for Neutron Physics and Reactor Technology (INR), 76344 Eggenstein- Leopoldshafen, Germany bMax Planck Institute for Plasma Physics (IPP), 17491 Greifswald, Germany A first neutronics analysis of the Helical-Axis Advanced Stellarator (HELIAS) power reactor is conducted in this work. It is based on Monte Carlo (MC) particle transport simulations with the Direct Accelerated Geometry Monte Carlo (DAGMC) approach which enables particle tracking directly on the CAD geometry. A suitable geometry model of the HELIAS reactor is developed, including a rough model of a breeder blanket based on the Helium Cooled Pebble Bed (HCPB) breeder blanket concept. The resulting model allows to perform first neutronic calculations providing a 2D map of the neutron wall loading, a 3D distribution of the neutron flux, and a rough assessment of the tritium breeding capability. It is concluded that the applied methodology, making use of MC particle transport simulations based on the DAGMC approach, is suitable for performing nuclear analyses for the HELIAS power reactor. Keywords: STELLARATOR; HELIAS; NEUTRONICS; CAD; MCNP; DAGMC 1. Introduction design (CAD). The developed models are usually not directly applicable for Monte Carlo (MC) particle The Helical-Axis Advanced Stellarator (HELIAS) is transport codes and need preprocessing with regard to a conceptual design of a fusion power reactor proposed the geometrical simplification and adaption to the by the Max Planck Institute for Plasma Physics (IPP) in requirements of neutronic simulations including the Greifswald, Germany. HELIAS-5B is a specific 5-field- decomposition of complex CAD models.
    [Show full text]
  • Advanced Neutron Diagnostics for ITER Fusion Experiments
    UU-NF 04#14 (December 2004) U ppsala U niversity N eutron Physics R eport ISSN 1401-6269 Advanced neutron diagnostics for ITER fusion experiments L.Giacomelli, A.Hjalmarsson, H.Sjostrand, W.Glasser, J.Kallne, S.Conroy, G.Ericsson, M.Gatu Johnson, G.Gorini, H.Henriksson, S.Popovichev, E.R onchi, J.Sousa, E.Sunden Andersson, M.Tardocchi, J.Thun, M.Weiszflog, AND CONTRIBUTORS TO THE JET-EFDA WORK PROGRAM UPPSALA UNIVERSITY D epartment of N eutron Research Program of N eutron Physics U ppsala , Sweden UPPSALA UNIVERSITY Department of Neutron Research Program of Neutron Physics Uppsala , Sweden UU-NF 04# 14 (December 2004) U ppsala U niversity N eutron Physics R eport ISSN 1401-6269 Editor: J Kallne Advanced neutron diagnostics for ITER fusion experiments L.Giacomelli, A.Hjalmarsson, H.Sjostrand, W.Glasser, J.Kallne, S.Conroy, G.Ericsson, M.Gatu Johnson, G.GorinU, H.Henriksson, S.Popovichev2), E.Ronchi, J.Sousa3), E.Sunden Andersson, M.TardocchU, J.Thun, M.Weiszflog, and contributors to the JET-EFDA work program Dept, of Neutron Research, Uppsala University, Sweden EURATOM-VR Association n INFM, Dept, of Physics, Univ. of Milano-Bicocca and Istituto di Fisica del Plasma, EURATOM-ENEA-CNR Association, Milan, Italy; 2) JET, Culham Science Centre, ABINGDON, UK, EURATOM-UKAEA Association; 3) Associagdo EURATOM 1ST, Centro de Fusdo Nuclear, Instituto Superior Tecnico, Av. Rovisco Pais 1, 1049-001 Lisboa, Portugal. Abstract. The diagnostics functions of neutron measurements are reviewed as well as the roles played by neutron yield monitors, cameras and spectrometers. The importance of recent developments in neutron emission spectroscopy (NES) diagnostics is emphasized.
    [Show full text]
  • Monte Carlo Calculation of First Wall Neutron Flux in Tokamak Fusion Reactor
    Journal of NUCLEAR SCIENCE and TECHNOLOGY, 17[4], pp. 301~304 (April 1980). 301 TECHNICAL REPORT Monte Carlo Calculation of First Wall Neutron Flux in Tokamak Fusion Reactor Yasushi SEKI and Hiromasa IIDA Japan Atomic Energy Research Institute* Received August 30, 1979 The poloidal distribution of the first wall 14 MeV neutron flux and the tritium breed- ing ratio in a Tokamak fusion reactor were calculated using Monte Carlo method. The poloidal distribution of the 14 MeV neutron flux in the first wall was found to be quite different from that of the primary incident flux. The tritium breeding ratio calculated by the Monte Carlo method became about 5% larger than the value obtained from SN transport calculations. KEYWORD: Monte Carlo method, neutron flux, first wall, tritium breeding ratio, Tokamak fusion reactors, track length estimator I. INTRODUCTION The poloidal peaking of the first wall 14 MeV neutron flux and the tritium breeding ratio in a Tokamak fusion reactor(1) are calculated using a newly modified Monte Carlo code(2). The poloidal peaking of 14 MeV neutron flux in the first wall of a toroidal fusion reactor will be one of the factors limiting the lifetime of the first wall. The primary 14 MeV neutron flux incident on the first wall from a toroidal plasma has been calculated by several authors(3)~(7), using the ray-tracing method which derives the primary flux of a point on the first wall by numerically integrating the source density distribution ob- servable from that point. With this method, only the primary 14 MeV neutron flux can be obtained but not the actual** 14 MeV neutron flux.
    [Show full text]
  • Magnetic Fusion Commercial Power Plants
    The suomtted manuscript nas been authored by a cmrnctor ot the U.S. Govanmat under Connact KO. DE-ACOS-840R21400. Accormngly, the US. Government rcum a nonexuulve, royalty-free hccncc 10 publuh or repwuce the PUDlUhCd form Of thlS conmDuuon, or dow orhcn to do ao. for U.S. Government purposes;' PRESENTATION TO THE FUSION POWER ASSOCIATES ANNUAL MEETING AND SYMPOSIUM September 8-9, 1994, San Diego, California MAGNETIC FUSION COMMERCIAL POWER PLANTS John Sheffield, Fusion Energy Division Oak Ridge National Laboratory 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 agency thereof, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsi- bility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Refer- ence herein to any specific commercial product, process, or service by trade name, trademark, ~ manufacturer, or otherwise does not necessarily constitute or imply its endorsement, recom- mendation, or favoring by the United States Government or any agency thereof. The views and opinions of authors expressed herein do not necessarily state or reflect those of the United States Government or any agency thereof. *Research sponsored by the Office of Fusion Energy. Department of Energy, under contract DE-AC05-840R21400with the Martin Marietta Energy Systems, Inc. DISCLAIMER Portions of this document may be illegible in electronic image products. Images are produced from the best available original document.
    [Show full text]