A Measurable Lawson Criterion and Hydro-Equivalent Curves for Inertial Confinement Fusion C

Total Page:16

File Type:pdf, Size:1020Kb

A Measurable Lawson Criterion and Hydro-Equivalent Curves for Inertial Confinement Fusion C A measurable Lawson criterion and hydro-equivalent curves for inertial confinement fusion C. D. Zhou and R. Betti Citation: Phys. Plasmas 15, 102707 (2008); doi: 10.1063/1.2998604 View online: http://dx.doi.org/10.1063/1.2998604 View Table of Contents: http://pop.aip.org/resource/1/PHPAEN/v15/i10 Published by the American Institute of Physics. Related Articles Recover soft x-ray spectrum using virtual flat response channels with filtered x-ray diode array Rev. Sci. Instrum. 83, 113102 (2012) Average atom transport properties for pure and mixed species in the hot and warm dense matter regimes Phys. Plasmas 19, 102709 (2012) A novel technique for single-shot energy-resolved 2D x-ray imaging of plasmas relevant for the inertial confinement fusion Rev. Sci. Instrum. 83, 103504 (2012) Deuterium–tritium neutron yield measurements with the 4.5 m neutron-time-of-flight detectors at NIF Rev. Sci. Instrum. 83, 10D312 (2012) Characterizing time decay of bibenzyl scintillator using time correlated single photon counting Rev. Sci. Instrum. 83, 10D911 (2012) Additional information on Phys. Plasmas Journal Homepage: http://pop.aip.org/ Journal Information: http://pop.aip.org/about/about_the_journal Top downloads: http://pop.aip.org/features/most_downloaded Information for Authors: http://pop.aip.org/authors Downloaded 29 Nov 2012 to 128.151.164.152. Redistribution subject to AIP license or copyright; see http://pop.aip.org/about/rights_and_permissions PHYSICS OF PLASMAS 15, 102707 ͑2008͒ A measurable Lawson criterion and hydro-equivalent curves for inertial confinement fusion C. D. Zhou1 and R. Betti1,2 1Fusion Science Center and Laboratory for Laser Energetics, University of Rochester, Rochester, New York 14623, USA 2Departments of Mechanical Engineering & Physics and Astronomy, University of Rochester, Rochester, New York 14623, USA ͑Received 16 May 2008; accepted 12 September 2008; published online 30 October 2008; publisher error corrected 4 November 2008͒ It is shown that the ignition condition ͑Lawson criterion͒ for inertial confinement fusion ͑ICF͒ can be cast in a form dependent on the only two parameters of the compressed fuel assembly that can ͑ h͒ be measured with existing techniques: the hot spot ion temperature Ti and the total areal density ͑␳ ͒ ␳ Rtot , which includes the cold shell contribution. A marginal ignition curve is derived in the Rtot, h Ti plane and current implosion experiments are compared with the ignition curve. On this plane, hydrodynamic equivalent curves show how a given implosion would perform with respect to the Ͻ͗ h͘ Ͻ ignition condition when scaled up in the laser-driver energy. For 3 Ti n 6 keV, an approximate ͑ ͒ ͗ h͘2.6 ͗␳ ͘ Ͼ 2.6 / 2 form of the ignition condition typical of laser-driven ICF is Ti n · Rtot n 50 keV ·gcm , ͗␳ ͘ ͗ h͘ where Rtot n and Ti n are the burn-averaged total areal density and hot spot ion temperature, respectively. Both quantities are calculated without accounting for the alpha-particle energy deposition. Such a criterion can be used to determine how surrogate D2 and subignited DT target implosions perform with respect to the one-dimensional ignition threshold. © 2008 American Institute of Physics. ͓DOI: 10.1063/1.2998604͔ I. INTRODUCTION ment of the surrounding cold shell, and ͑b͒ the hot spot areal density cannot be experimentally measured. 1,2 In inertial confinement fusion ͑ICF͒, a shell of cryo- A more accurate form of the hot spot ignition condition genic deuterium and tritium ice is imploded at high velocities is given in Refs. 1 and 4–6 with the alpha heating balancing ͓͑ϳ2–4͔ϫ107 cm/s͒ and low entropy to achieve high cen- all the hot spot power losses ͑thermal conduction and radia- tral temperatures and high areal densities. The final fuel as- tion losses͒. Our approach to ignition is somewhat different sembly consists of a relatively low density ͑ϳ30–80 g/cc͒ from that in Ref. 4. First, our ignition model is dynamic as it high temperature ͑ϳ4–8 keV͒ core ͑the hot spot͒ sur- includes both the compression and expansion phases of the rounded by a dense ͑ϳ300–1000 g/cc͒ cold ͑ϳ100 eV͒ fuel shell motion. Second, our ignition condition is given in terms 3 layer ͑the compressed shell͒. The Lawson criterion deter- of the total areal density rather than the hot spot areal den- mining the onset of thermonuclear ignition is usually ex- sity. Third, the ignition condition is viewed as an instability pressed through the product p␶Ͼ10 atm·s, where p is the of both the pressure and the temperature rather than only the plasma pressure in atm and ␶ is the energy confinement time temperature. This causes the heat conduction losses to enter in seconds. In magnetic fusion devices, both the pressure and the ignition condition in a fundamentally different way. A confinement time are routinely measured and the perfor- more detailed discussion of this point is provided in Sec. II. mance of each discharge can be assessed by comparing the It is important to emphasize that the presence of a cold dense value of p␶ with respect to the ignition value ͑10 atm·s͒.In shell surrounding the hot spot significantly alters the onset of inertial confinement fusion, both p and ␶ cannot be directly the thermonuclear instability ͑a similar point is made in Refs. measured, and the performance of subignited ICF implosions 4, 12, and 18͒. Since the heat conductivity is negligible in the cannot be assessed with respect to the ignition condition. cold shell, most of the heat leaving the hot spot is recycled Often, the Lawson criterion is extended to ICF by simply back into the hot spot in the form of internal energy and pdV restricting its application to the hot spot and by replacing p work of the plasma ablated off the inner shell surface. Much ␳ / ͑␳ with the ideal gas equation of state p=2 hTh mi h is the hot of the radiation losses are also recycled back through abla- spot mass density, Th is the hot spot temperature, and mi is tion since the cold shell is opaque to the low-energy portion the DT average ion mass͒, and ␶ with the sound wave trav- of the x-ray bremsstrahlung spectrum ͑only the high-energy ␶ϳ / ͑ eling time through the hot spot, Rh Cs here Rh is the hot x rays can penetrate the dense shell͒. As is argued in Ref. 12, ϳͱ ͒ spot radius and Cs is the hot spot sound speed, Cs Th . the heat conduction and, to some extent, the radiation losses ͑␳ ͒ͱ ͑ This leads to the hot spot ignition condition hRh Th do not appreciably change the hot spot pressure i.e., en- Ͼ ␳ ͒ const, where hRh is the hot spot areal density. There are ergy . Instead, those losses raise the density and lower the two problems with such a simple derivation: ͑a͒ The confine- temperature while keeping pϳ␳T approximately constant. ment time is incorrect since it neglects the inertial confine- Since the fusion rate scales as n2͗␴v͘, with ͗␴v͘ϳT3–4 for 1070-664X/2008/15͑10͒/102707/12/$23.0015, 102707-1 © 2008 American Institute of Physics Downloaded 29 Nov 2012 to 128.151.164.152. Redistribution subject to AIP license or copyright; see http://pop.aip.org/about/rights_and_permissions 102707-2 C. D. Zhou and R. Betti Phys. Plasmas 15, 102707 ͑2008͒ TϽ6–8 keV and ͗␴v͘ϳT2 for 6–8ϽTϽ25 keV, it follows can conclude that such an OMEGA implosion scales to one- that the alpha self-heating is degraded by heat conduction dimensional ignition on the National Ignition Facility11 and radiation losses only at low temperatures less than ͑NIF͒. 6–8 keV but unchanged at high temperatures TϾ6–8 keV. The paper is organized as follows. The analytic ignition This occurs because at high temperatures, the fusion rates model is described in Sec. II while its initial conditions are depend only on the hot spot pressure ͑n2͗␴v͘ϳp2͒ that is derived in Sec. III. The ignition condition from the analytic independent of the heat losses. While these recycling effects model is derived in Sec. IV, and compared with the results of ͑described in detail in Ref. 12͒ improve the ignition thresh- one-dimensional hydrodynamic simulations in Sec. V. The old, the expansion losses, that are often not included in the assumptions concerning the alpha-particle confinement are ignition condition, cause a transfer of internal energy to ki- discussed in Sec. VI, and comparison with previous forms of netic energy and degrade the ignition conditions. Since the the ignition condition are presented in Sec. VII. The hydro- hot spot expansion occurs against the dense shell, the igni- equivalent curves are derived in Sec. VIII and discussed in tion conditions depend on the inertia of the dense shell. Fur- the Conclusions ͑Sec. IX͒. thermore, the hot spot internal energy comes from the shell kinetic energy, which is also used to assemble the shell areal II. DYNAMIC MODEL OF THERMONUCLEAR IGNITION density. As shown in Ref. 13, there is a direct correlation between the hot spot areal density and shell areal density. The dynamic model described in this section includes Thus, one can expect that the ICF Lawson criterion depends the standard energy losses and sources ͑heat conduction, ra- on the shell areal density. diation losses, alpha heating͒ as well as the compression and In this paper, we derive a form of the Lawson criterion expansion dynamics of a hot spot surrounded by a dense that can be directly measured in ICF implosions and includes shell. The model describes the assembly phase of the hot the confinement of the surrounding cold shell.
Recommended publications
  • Thermonuclear AB-Reactors for Aerospace
    1 Article Micro Thermonuclear Reactor after Ct 9 18 06 AIAA-2006-8104 Micro -Thermonuclear AB-Reactors for Aerospace* Alexander Bolonkin C&R, 1310 Avenue R, #F-6, Brooklyn, NY 11229, USA T/F 718-339-4563, [email protected], [email protected], http://Bolonkin.narod.ru Abstract About fifty years ago, scientists conducted R&D of a thermonuclear reactor that promises a true revolution in the energy industry and, especially, in aerospace. Using such a reactor, aircraft could undertake flights of very long distance and for extended periods and that, of course, decreases a significant cost of aerial transportation, allowing the saving of ever-more expensive imported oil-based fuels. (As of mid-2006, the USA’s DoD has a program to make aircraft fuel from domestic natural gas sources.) The temperature and pressure required for any particular fuel to fuse is known as the Lawson criterion L. Lawson criterion relates to plasma production temperature, plasma density and time. The thermonuclear reaction is realised when L > 1014. There are two main methods of nuclear fusion: inertial confinement fusion (ICF) and magnetic confinement fusion (MCF). Existing thermonuclear reactors are very complex, expensive, large, and heavy. They cannot achieve the Lawson criterion. The author offers several innovations that he first suggested publicly early in 1983 for the AB multi- reflex engine, space propulsion, getting energy from plasma, etc. (see: A. Bolonkin, Non-Rocket Space Launch and Flight, Elsevier, London, 2006, Chapters 12, 3A). It is the micro-thermonuclear AB- Reactors. That is new micro-thermonuclear reactor with very small fuel pellet that uses plasma confinement generated by multi-reflection of laser beam or its own magnetic field.
    [Show full text]
  • Article Thermonuclear Bomb 5 7 12
    1 Inexpensive Mini Thermonuclear Reactor By Alexander Bolonkin [email protected] New York, April 2012 2 Article Thermonuclear Reactor 1 26 13 Inexpensive Mini Thermonuclear Reactor By Alexander Bolonkin C&R Co., [email protected] Abstract This proposed design for a mini thermonuclear reactor uses a method based upon a series of important innovations. A cumulative explosion presses a capsule with nuclear fuel up to 100 thousands of atmospheres, the explosive electric generator heats the capsule/pellet up to 100 million degrees and a special capsule and a special cover which keeps these pressure and temperature in capsule up to 0.001 sec. which is sufficient for Lawson criteria for ignition of thermonuclear fuel. Major advantages of these reactors/bombs is its very low cost, dimension, weight and easy production, which does not require a complex industry. The mini thermonuclear bomb can be delivered as a shell by conventional gun (from 155 mm), small civil aircraft, boat or even by an individual. The same method may be used for thermonuclear engine for electric energy plants, ships, aircrafts, tracks and rockets. ----------------------------------------------------------------------- Key words: Thermonuclear mini bomb, thermonuclear reactor, nuclear energy, nuclear engine, nuclear space propulsion. Introduction It is common knowledge that thermonuclear bombs are extremely powerful but very expensive and difficult to produce as it requires a conventional nuclear bomb for ignition. In stark contrast, the Mini Thermonuclear Bomb is very inexpensive. Moreover, in contrast to conventional dangerous radioactive or neutron bombs which generates enormous power, the Mini Thermonuclear Bomb does not have gamma or neutron radiation which, in effect, makes it a ―clean‖ bomb having only the flash and shock wave of a conventional explosive but much more powerful (from 1 ton of TNT and more, for example 100 tons).
    [Show full text]
  • Cumulative List of INFUSE Awards
    Cumulative List of INFUSE Awards INFUSE 2021a, June 14, 2021 Company: Air Squared, Inc., DUNS: 824841027 Title: Design, test, and evaluation of a scroll roughing vacuum pump with filter and Vespel tip seals for tritium handling Abstract: Development of a novel scroll pump that meets the strict containment levels of D/T experimental campaigns aiming to replace both the scroll and metal bellows pumps with a single scroll pump utilizing Vespel tip seals to demonstrate improved reliability, discharge pressure, and reduced costs. Co. PI: Mr. John Wilson Co. e-mail: [email protected] Laboratory: ORNL Lab PI: Mr. Charles Smith III, [email protected] Cumulative List of INFUSE Awards INFUSE 2021a, June 14, 2021 Company: Commonwealth Fusion Systems, DUNS: 117005109 Title: Informing Layout and Performance Requirements for SPARC Massive Gas Injection Abstract: Commonwealth Fusion Systems (CFS) is designing a compact tokamak called SPARC and is evaluating massive gas injection (MGI) as its primary means of plasma disruption mitigation technique. Present conservative scoping has enabled a preliminary design of the MGI system. However, physics-based modeling can help CFS inform an optimized layout, which can either reduce the cost of MGI system by reducing the number of gas injectors or provide supporting evidence that present scoping estimates are correct. This program leverages the 3D magneto-hydrodynamic modeling expertise at Princeton Plasma Physics Laboratory (PPPL), which is maintained through the development and use of the M3D-C1 code. CFS and PPPL will develop a gas source model representative of SPARC MGI’s system. PPPL would then use M3D- C1 to simulate unmitigated SPARC disruptions, to develop a baseline response, and then simulate mitigated disruptions representing a variety of MGI system configurations.
    [Show full text]
  • Arxiv:2105.10954V1 [Physics.Plasm-Ph] 23 May 2021
    manuscript No. (will be inserted by the editor) Progress toward Fusion Energy Breakeven and Gain as Measured against the Lawson Criterion Samuel E. Wurzel · Scott C. Hsu the date of receipt and acceptance should be inserted later Abstract The Lawson criterion is a key concept in the products exceeds the sum of the energy required to heat pursuit of fusion energy, relating the fuel density n, (en- the fusion fuel and the energy lost from the fusion fuel ergy) confinement time τ, and fuel temperature T to due to radiation, Lawson concluded that the product the energy gain Q of a fusion plasma. The purpose of of fuel density n and pulse duration τ (Lawson used this paper is to explain and review the Lawson crite- t) must exceed a certain threshold value. When ther- rion and to provide a compilation of achieved parame- mal conduction losses are included (extending Lawson's ters for a broad range of historical and contemporary analysis), the product of n and energy confinement time fusion experiments. Although this paper focuses on the τE must exceed a certain threshold value. We call this Lawson criterion, it is only one of many equally impor- product nτE (also nτ) the Lawson parameter. A suffi- tant factors in assessing the progress and ultimate like- ciently high T is implied such that the energy of charged lihood of any fusion concept becoming a commercially fusion products overcomes radiation losses. These con- viable fusion energy system. Only experimentally mea- ditions are now known as the Lawson criterion. A fusion sured or inferred values of n, τ, and T that have been plasma that has reached these conditions is said to have published in the peer-reviewed literature are included achieved ignition.
    [Show full text]
  • ICF Ignition, the Lawson Criterion and Comparison with MCF FSC Deuterium–Tritium Plasmas 100 Ignition
    ICF Ignition, the Lawson Criterion and Comparison with MCF FSC Deuterium–Tritium Plasmas 100 Ignition E Q ~ 10 x i OMEGA (2009) T i 10 Q ~ 1 n Q = Tokamaks 1993–1999 W /W ) Fusion Input Q ~ 0.1 1 W = energy Laser direct kev s kev Q ~ 0.01 3 drive (1996) – 0.1 m Q ~ 0.001 Laser direct 20 0.01 drive (1986) 10 ( Q ~ 0.0001 Laser indirect 0.001 drive (1986) Q ~ 0.00001 Lawson fusion parameter, Lawson fusion parameter, 0.0001 0.1 1 10 100 “Review of Burning Plasma Physics,” Central ion temperature (keV) FESAC Report (September 2001). 51st Annual Meeting of the R. Betti American Physical Society University of Rochester Division of Plasma Physics Fusion Science Center and Atlanta, GA Laboratory for Laser Energetics 2–6 November 2009 Collaborators FSC K. S. Anderson (UO5.00004) P. Chang (TO5.00004) R. Nora C. D. Zhou University of Rochester Laboratory for Laser Energetics B. Spears (UO5.00013) J. Edwards S. Haan J. Lindl Lawrence Livermore National Laboratory Summary The measurable Lawson criterion and hydro-equivalent curves determine the requirements for an early hydro-equivalent demonstration of ignition on OMEGA and on the NIF (THD) FSC • Cryogenic implosions on OMEGA have achieved a Lawson parameter PxE á 1 atm-s comparable to large tokamaks • Performance requirements for hydroequivalent ignition on OMEGA and NIF (THD)* GtRH GT H YOC Px Hydro-equivalent ignition n i n E g/cm2 keV (atm s) 15% OMEGA (25 kJ) ~0.30 ~3.4 (~3 × 1013 2.6 neutrons) NIF (THD) ~1.8 ~4.7 ~40% 20 * NIF will begin the cryogenic implosion campaign using a surrogate Tritium– Hydrogen–Deuterium (THD) target.
    [Show full text]
  • Computer Simulations of the ITER Fusion Reactor Federico D
    Computer simulations of the ITER fusion reactor Federico D. Halpern*, Glenn Bateman, Christopher M. Wolfe, Alexei Pankin, and A. H. Kritz Department of Physics, Lehigh University ITER [1], the thermonuclear experimental device currently under construction in France, is the first fusion reactor that is expected to produce large amounts of power. In ITER, energy will be produced from the fusion of hydrogen isotopes (deuterium and tritium) into helium. In order to overcome the electrostatic repulsion between atomic nuclei, the mixture of deuterium and tritium gas must be heated to extremely high temperatures. The resulting gas forms a plasma in which atomic nuclei and electrons are no longer bound together. Fusion reactors such as ITER confine plasmas using strong magnetic fields. Plasmas must be confined for a long enough period of time at sufficiently high temperature and density to produce more fusion power than input power. This energy confinement prerequisite for fusion, usually expressed using the Lawson criterion [2], cannot be achieved in present day reactors. ITER is expected to confine plasma discharges for 500 seconds, at a density of 1020 m-3, and a temperature of 20 KeV, which is about 15 times the temperature of the center of the sun. It is anticipated that ITER will produce about ten times more fusion power than input power. The first plasma operation is projected to be in 2017. In the research described here, the performance of ITER is predicted with computer modeling simulations that are carried Figure 1: Rendition of the ITER design. To illustrate out using leading theory-based models for the colossal scale of the device, a person is shown whole-device simulations.
    [Show full text]
  • Introduction to Magnetic Fusion
    MIT Plasma Science & Fusion Center Introduction to Magnetic Fusion Dennis Whyte MIT Plasma Science and Fusion Center Nuclear Science and Engineering SULI, PPPL June 2015 Whyte, MFE, SULI 2015 1 Overview: Fusion Energy • Why? ! To meet growing world energy demands using a safe, clean method of producing electricity. • What? ! Extract net energy from controlled thermonuclear fusion of light elements • Who? ! International research teams of engineers and physicists. • Where? ! Research is worldwide ….eventual energy source has few geographical restrictions. • When? ! Many feasibility issues resolved….demonstration in next decades • How? ! This lecture Whyte, MFE, SULI 2015 2 Fusion & fission: binding energy, E = Δm c2 Whyte, MFE, SULI 2015 3 Thermonuclear fusion of hydrogen powers the universe: stars Whyte, MFE, SULI 2015 4 As a terrestrial energy source we are primarily interested in the exothermic fusion reactions of heavier hydrogenic isotopes and 3He • Hydrogenic species definitions: ! Hydrogen or p (M=1), Deuterium (M=2), Tritium (M=3) Whyte, MFE, SULI 2015 5 Exothermic fusion reactions of interest Net energy gain is distributed in the Kinetic energy of the fusion products Whyte, MFE, SULI 2015 6 D-T fusion facts d + t → α + n Q = 17.6 MeV 2 3 4 1 H + 1 H → 2 He + n Q = 17.6 MeV Conservation of energy & linear momentum when Ed,t<<Q mn 1 mα 4 Eα ! Q = QDT = 3.5 MeV En ! Q = QDT = 14.1 MeV mα + mn 5 mα + mn 5 Whyte, MFE, SULI 2015 7 A note about units • In nuclear engineering, nuclear science and plasmas we use the unit of electron-volt “eV” for both energy and temperature ! N.B.
    [Show full text]
  • The Fairy Tale of Nuclear Fusion L
    The Fairy Tale of Nuclear Fusion L. J. Reinders The Fairy Tale of Nuclear Fusion 123 L. J. Reinders Panningen, The Netherlands ISBN 978-3-030-64343-0 ISBN 978-3-030-64344-7 (eBook) https://doi.org/10.1007/978-3-030-64344-7 © The Editor(s) (if applicable) and The Author(s), under exclusive license to Springer Nature Switzerland AG 2021 This work is subject to copyright. All rights are solely and exclusively licensed by the Publisher, whether the whole or part of the material is concerned, specifically the rights of translation, reprinting, reuse of illustrations, recitation, broadcasting, reproduction on microfilms or in any other physical way, and transmission or information storage and retrieval, electronic adaptation, computer software, or by similar or dissimilar methodology now known or hereafter developed. The use of general descriptive names, registered names, trademarks, service marks, etc. in this publication does not imply, even in the absence of a specific statement, that such names are exempt from the relevant protective laws and regulations and therefore free for general use. The publisher, the authors and the editors are safe to assume that the advice and information in this book are believed to be true and accurate at the date of publication. Neither the publisher nor the authors or the editors give a warranty, expressed or implied, with respect to the material contained herein or for any errors or omissions that may have been made. The publisher remains neutral with regard to jurisdictional claims in published maps and institutional affiliations. This Springer imprint is published by the registered company Springer Nature Switzerland AG The registered company address is: Gewerbestrasse 11, 6330 Cham, Switzerland When you are studying any matter or considering any philosophy, ask yourself only what are the facts and what is the truth that the facts bear out.
    [Show full text]
  • Toroidal Plasma Conditions Where the P-11B Fusion Lawson Criterion Could Be Eased
    Toroidal plasma conditions where the p-11B fusion Lawson criterion could be eased Yueng-Kay Peng ( [email protected] ) ENN Science and Technology Development Co., Ltd. https://orcid.org/0000-0003-2948-1058 Yuejiang Shi ENN Science and Technology Development Co., Ltd. Mingyuan Wang ENN Science and Technology Development Co., Ltd. Bing Liu ENN Science and Technology Development Co., Ltd. Xueqing Yan Peking University Article Keywords: Posted Date: October 26th, 2020 DOI: https://doi.org/10.21203/rs.3.rs-93644/v1 License: This work is licensed under a Creative Commons Attribution 4.0 International License. Read Full License Page 1/11 Abstract We examine the theoretical conditions in which the Lawson ignition criterion for p-11B fusion in a magnetized toroidal plasma can be reduced substantially. It is determined that a velocity differential between the protons and the boron ions of the order of the plasma sound speed (Mach number of 1 or 2 at a plasma temperature of ~102 keV) could raise the p-11B fusion reaction rate to ~2x10-22 m3/s or ~6x10-22 m^3/s, respectively, from the ~1x10-22 m3/s level in a static plasma. The Lawson triple product 23 -3 (ni τE Ti) required for ignition can thereby be reduced to as low as ~10 m s keV, which is one order of magnitude above the ITER requirement for D-T burn. Since order-unity Mach numbers in velocity differentials between deuterons and impurity carbon ions have been maintained in tokamak plasmas under excellent connement conditions, similar levels of velocity differentials between protons and minority boron-11 ions could in principle be maintained also.
    [Show full text]
  • Nuclear Fusion Benjamin Harack
    Nuclear Fusion Benjamin Harack 2 Overview Introduction to Nuclear Fusion Analysis Tools Fusion Processes (Fuel Cycles) Considerations for Implementations Implementation Types Fusion's Status and Future 3 Fusion Nuclear fusion refers to any process of interaction of two nuclei in which they combine to form a heavier nucleus. For light elements, this process typically emits extra particles such as electrons and neutrinos along with a relatively large amount of energy. 4 Fusion as a Power Source The goal of fusion power production is to harness reactions of this nature to produce electrical power. Thermal power plants convert heat into electricity via a heat engine. Direct conversion involves capturing charged particles to create a current. 5 Net Energy We want net energy output from our fusion power plant. Later on we look at the details of the fusion energy gain factor Q, a useful quantity for describing the energy balance of a reactor. 6 Steady State Power In order to be producing useful electrical power, the reaction must be either in dynamic equilibrium or pulsed quickly. – JET (1982-present) (Joint European Torus) – ITER (~2018) (originally International Thermonuclear Experimental Reactor) – DEMO (~2033) (DEMOnstration Power Plant) 7 Energy Capture • Emitted energy from fusion reactions is primarily in the form of high energy neutrons and various charged particles. • Charged particles skid to a halt mainly through electromagnetic interactions • Neutrons deposit energy primarily through nuclear interactions. • Stopping neutrons generally requires different shielding than charged particles. 8 Safety Concerns The most popular fusion reactions produce a lot of neutron radiation. This fact has associated safety concerns: – Direct Neutron Flux – Activated Materials 9 Our Focus Most of the scientific work in fusion has been focused on achieving net energy gain.
    [Show full text]
  • Derivation of Lawson Criterion for D-T
    Benjamin Harack 1 Derivation of Lawson Criterion for D-T We are interested in how long the plasma contains energy. We use the quantity τE, called the ‘confinement time'. This is a measure of the rate at which the system loses energy to the environment. It can be defined as the energy content of the plasma divided by the power loss. W τE = (1) Ploss Where W is the energy content of the plasma, and Ploss is the power loss. The thermal energy of a plasma can be defined as: Z 3 W = k(n − T − + (n + n )T )dV (2) 2 e e D T ions Where k is Boltzmann's constant, ne− is the electron density, Te− is the electron temperature, nD and nT are the ion densities of deuterium and tritium respectively and Tions is their temperature. The integral is over the volume. If we assume that all temperatures are the same, and that the densities of tritium and deuterium are equal, we get: W = 3n k T (3) V e B Where in this equation, ne is the electron density and V is the volume. The number of fusions per volume per time is given by: 1 f = n n hσvi = n2hσvi (4) D T 4 e Where f is the number of fusions per volume per time, nD and nT are the ion densities of deuterium and tritium respectively, σ is the fusion cross-section, v is the relative velocity. The angle brackets mean an average over the Maxwellian velocity distribution. We are also assuming that the densities of the ions are equal, and that their total density is equal to the total electron density ne.
    [Show full text]
  • What Is Fusion? Two Fusion Types
    October 2016 October 2016 WHAT IS FUSION? TWO FUSION TYPES NEUTRONIC ANEUTRONIC TWO FUSION TYPES NEUTRONIC ANEUTRONIC TWO FUSION TYPES NEUTRONIC ANEUTRONIC produces neutrons produces NO neutrons NEUTRONIC FUSION • D+T -> He3 + n Deuterium + Tritium -> Helium-3 + neutron • Some radioactive waste, heat converted to electricity • Government funded, mainly • Far more expensive to build and maintain safely ANEUTRONIC FUSION • p+ B11 -> 3 He4 Hydrogen + Boron11 -> 3Helium-4, no neutrons • NO radioactive waste • direct conversion to electricity, no turbines needed • potentially far cheaper • Privately funded, mainly TWO FUSION TYPES NEUTRONIC ANEUTRONIC • D+T -> He3 + n • p+ B11 -> 3 He4 Deuterium + Tritium -> Hydrogen + Boron11 -> 3Helium-4, no neutrons Helium-3 + neutron • Some radioactive waste, • NO radioactive waste heat converted to • direct conversion to electricity electricity, no turbines • Government funded, needed mainly • potentially far cheaper • Far more expensive to build and maintain safely • Privately funded, mainly ANEUTRONIC FUSION Aneutronic → No neutrons → No Radioactive waste THE INGREDIENTS OF NET FUSION ENERGY TEMPERATURE T CONFINEMENT TIME DENSITY n EFFICIENCY THE INGREDIENTS OF NET FUSION ENERGY TEMPERATURE T CONFINEMENT TIME DENSITY n EFFICIENCY THE INGREDIENTS OF NET FUSION ENERGY TEMPERATURE T CONFINEMENT TIME DENSITY n EFFICIENCY THE INGREDIENTS OF NET FUSION ENERGY TEMPERATURE T CONFINEMENT TIME DENSITY n EFFICIENCY THE INGREDIENTS OF NET FUSION ENERGY TEMPERATURE T CONFINEMENT TIME DENSITY n EFFICIENCY FUSION
    [Show full text]