Nuclear Reactors and Radioisotopes for Space
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MULTIPHYSICS DESIGN and SIMULATION of a TUNGSTEN-CERMET NUCLEAR THERMAL ROCKET a Thesis by BRAD APPEL Submitted to the Office O
MULTIPHYSICS DESIGN AND SIMULATION OF A TUNGSTEN-CERMET NUCLEAR THERMAL ROCKET A Thesis by BRAD APPEL Submitted to the Office of Graduate Studies of Texas A&M University in partial fulfillment of the requirements for the degree of MASTER OF SCIENCE August 2012 Major Subject: Nuclear Engineering Multiphysics Design and Simulation of a Tungsten-Cermet Nuclear Thermal Rocket Copyright 2012 Brad Appel ii MULTIPHYSICS DESIGN AND SIMULATION OF A TUNGSTEN-CERMET NUCLEAR THERMAL ROCKET A Thesis by BRAD APPEL Submitted to the Office of Graduate Studies of Texas A&M University in partial fulfillment of the requirements for the degree of MASTER OF SCIENCE Approved by: Chair of Committee, Karen Vierow Committee Members, Shannon Bragg-Sitton Paul Cizmas Head of Department, Yassin Hassan August 2012 Major Subject: Nuclear Engineering iii iii ABSTRACT Multiphysics Design and Simulation of a Tungsten-Cermet Nuclear Thermal Rocket. (August 2012) Brad Appel, B.S., Purdue University Chair of Advisory Committee: Dr. Karen Vierow The goal of this research is to apply modern methods of analysis to the design of a tungsten-cermet Nuclear Thermal Rocket (NTR) core. An NTR is one of the most viable propulsion options for enabling piloted deep-space exploration. Concerns over fuel safety have sparked interest in an NTR core based on tungsten-cermet fuel. This work investigates the capability of modern CFD and neutronics codes to design a cermet NTR, and makes specific recommendations for the configuration of channels in the core. First, the best CFD practices available from the commercial package Star-CCM+ are determined by comparing different modeling options with a hot-hydrogen flow experiment. -
Fusion & High Energy Density Plasma Science
Fusion & High Energy Density Plasma Science Opportunities using Pulsed Power Daniel Sinars, Sandia National Laboratories Fusion Power Associates Dec. 4-5, 2018 Sandia National Laboratories is a multimission laboratory managed and operated by National Technology and Engineering Solutions of Sandia, LLC., a wholly owned subsidiary of Honeywell International, Inc., for the U.S. Department of Energy’s National Nuclear Security Administration under contract DE-NA-0003525. Sandia is the home of Z, the world’s largest pulsed power facility, and its adjacent multi-kJ Z-Beamlet and Z-PW lasers Pulsed power development area Z Periscope ZBL/ZPW Chama ZPW ZBL Chamber Jemez Chamber Chaco Pecos Target Chamber Chaco Chaco Probe Chambers Laser Beam Using two HED facilities, we have demonstrated the scaling of magneto-inertial fusion over factors of 1000x in energy 3 Our fusion yields have been increasing as expected with increased fuel preheating and magnetization Progress since 1st MagLIF in 2014 Demonstrated platform on Omega • Improved laser energy coupling • Improved magnetic field from ~0.3 kJ to 1.4 kJ strength from 9 T to 27 T • Demonstrated 6x improvement • Achieved record MIF yields on in fusion performance, reaching Omega of 5x109 DD in 2018 2.5 kJ DT-equivalent in 2018 4 We believe that Z is capable of producing a fusion yield of ~100 kJ DT-equivalent with MagLIF, though doing it with DT would exceed our safety thresholds for both T inventory & yield Preheat Energy = 6 kJ into 1.87 mg/cc DT § 2D simulations indicate a 22+ MA and 25+ T with 22.6 MA 6 kJ of preheat could produce ~100 kJ 21.1 MA § Presently, we cannot produce these inputs 17.4 MA S. -
NIAC 2011 Phase I Tarditti Aneutronic Fusion Spacecraft Architecture Final Report
NASA-NIAC 2001 PHASE I RESEARCH GRANT on “Aneutronic Fusion Spacecraft Architecture” Final Research Activity Report (SEPTEMBER 2012) P.I.: Alfonso G. Tarditi1 Collaborators: John H. Scott2, George H. Miley3 1Dept. of Physics, University of Houston – Clear Lake, Houston, TX 2NASA Johnson Space Center, Houston, TX 3University of Illinois-Urbana-Champaign, Urbana, IL Executive Summary - Motivation This study was developed because the recognized need of defining of a new spacecraft architecture suitable for aneutronic fusion and featuring game-changing space travel capabilities. The core of this architecture is the definition of a new kind of fusion-based space propulsion system. This research is not about exploring a new fusion energy concept, it actually assumes the availability of an aneutronic fusion energy reactor. The focus is on providing the best (most efficient) utilization of fusion energy for propulsion purposes. The rationale is that without a proper architecture design even the utilization of a fusion reactor as a prime energy source for spacecraft propulsion is not going to provide the required performances for achieving a substantial change of current space travel capabilities. - Highlights of Research Results This NIAC Phase I study provided led to several findings that provide the foundation for further research leading to a higher TRL: first a quantitative analysis of the intrinsic limitations of a propulsion system that utilizes aneutronic fusion products directly as the exhaust jet for achieving propulsion was carried on. Then, as a natural continuation, a new beam conditioning process for the fusion products was devised to produce an exhaust jet with the required characteristics (both thrust and specific impulse) for the optimal propulsion performances (in essence, an energy-to-thrust direct conversion). -
Fission and Fusion Can Yield Energy
Nuclear Energy Nuclear energy can also be separated into 2 separate forms: nuclear fission and nuclear fusion. Nuclear fusion is the splitting of large atomic nuclei into smaller elements releasing energy, and nuclear fusion is the joining of two small atomic nuclei into a larger element and in the process releasing energy. The mass of a nucleus is always less than the sum of the individual masses of the protons and neutrons which constitute it. The difference is a measure of the nuclear binding energy which holds the nucleus together (Figure 1). As figures 1 and 2 below show, the energy yield from nuclear fusion is much greater than nuclear fission. Figure 1 2 Nuclear binding energy = ∆mc For the alpha particle ∆m= 0.0304 u which gives a binding energy of 28.3 MeV. (Figure from: http://hyperphysics.phy-astr.gsu.edu/hbase/nucene/nucbin.html ) Fission and fusion can yield energy Figure 2 (Figure from: http://hyperphysics.phy-astr.gsu.edu/hbase/nucene/nucbin.html) Nuclear fission When a neutron is fired at a uranium-235 nucleus, the nucleus captures the neutron. It then splits into two lighter elements and throws off two or three new neutrons (the number of ejected neutrons depends on how the U-235 atom happens to split). The two new atoms then emit gamma radiation as they settle into their new states. (John R. Huizenga, "Nuclear fission", in AccessScience@McGraw-Hill, http://proxy.library.upenn.edu:3725) There are three things about this induced fission process that make it especially interesting: 1) The probability of a U-235 atom capturing a neutron as it passes by is fairly high. -
On Fusion Driven Systems (FDS) for Transmutation
R-08-126 On fusion driven systems (FDS) for transmutation O Ågren Uppsala University, Ångström laboratory, division of electricity V E Moiseenko Institute of Plasma Physics, National Science Center Kharkov Institute of Physics and Technology K Noack Forschungszentrum Dresden-Rossendorf October 2008 Svensk Kärnbränslehantering AB Swedish Nuclear Fuel and Waste Management Co Box 250, SE-101 24 Stockholm Tel +46 8 459 84 00 CM Gruppen AB, Bromma, 2008 ISSN 1402-3091 Tänd ett lager: SKB Rapport R-08-126 P, R eller TR. On fusion driven systems (FDS) for transmutation O Ågren Uppsala University, Ångström laboratory, division of electricity V E Moiseenko Institute of Plasma Physics, National Science Center Kharkov Institute of Physics and Technology K Noack Forschungszentrum Dresden-Rossendorf October 2008 This report concerns a study which was conducted for SKB. The conclusions and viewpoints presented in the report are those of the authors and do not necessarily coincide with those of the client. A pdf version of this document can be downloaded from www.skb.se. Summary This SKB report gives a brief description of ongoing activities on fusion driven systems (FDS) for transmutation of the long-lived radioactive isotopes in the spent nuclear waste from fission reactors. Driven subcritical systems appears to be the only option for efficient minor actinide burning. Driven systems offer a possibility to increase reactor safety margins. A comparatively simple fusion device could be sufficient for a fusion-fission machine, and transmutation may become the first industrial application of fusion. Some alternative schemes to create strong fusion neutron fluxes are presented. 3 Sammanfattning Denna rapport för SKB ger en övergripande beskrivning av pågående aktiviteter kring fusionsdrivna system (FDS) för transmutation av långlivade radioaktiva isotoper i kärnavfallet från fissionskraftverk. -
Nuclear Propulsion
16 Nuclear Propulsion Claudio Bruno DIMA, University of Rome (La Sapienza), Roma Italy 1. Introduction Nuclear propulsion (NP) concepts go back to the very end of WW II. Scientists informed about the effects of the US atomic bomb thought of exploiting its energy release for applications like commercial electric power generation, but also rockets and space flight [Shepherd and Cleaver, 1948, 1949; Bussard and DeLauer, 1958]. However, space flight was still considered science fiction, and the military had to deal with more concrete things, like the Cold War. Thus, besides power generation, second stages of ICBM, submarine propulsion, long range and long duration airplanes and missiles became the focus of nuclear energy applications. It was the second-stage and airplane application that drove R&D in nuclear propulsion. With the advent of reliable ICBM (the Atlas missile) and lighter fission and thermonuclear warheads, a nuclear-powered second stage became no longer necessary. Airplane applications were found impractical: the Convair NB-36 required such a heavy lead shield for the crew that testing and operation were much restricted. Nuclear-powered missiles were easier to design, e.g., project PLUTO, but still far more complicated compared to conventional. The Soviets investigated airplanes and rockets powered by nuclear power as well, and discarded them too. The history of NP can be found in [Czysz and Bruno, 2009, Chapter 7; Lawrence, 2008; Lawrence et al, 1995; Gunn and Ehresman, 2003; Dewar, 2004] and will not be reported here. Basic technology is also discussed in the references above, in particular reactor design is in [Lawrence et al, 1995]. -
Fusion Public Meeting Slides-03302021-FINAL
TitleDeveloping Lorem a Regulatory Ipsum Framework for Fusion Energy Systems March 30, 2021 Agenda Time Topic Speaker(s) 12:30-12:40pm Introduction/Opening Remarks NRC Discussion on NAS Report “Key Goals and Innovations Needed for a U.S. Fusion Jennifer Uhle (NEI) 12:40-1:10pm Pilot Plant” Rich Hawryluk (PPPL) Social License and Ethical Review of Fusion: Methods to Achieve Social Seth Hoedl (PRF) 1:10-1:40pm Acceptance Developers Perspectives on Potential Hazards, Consequences, and Regulatory Frameworks for Commercial Deployment: • Fusion Industry Association - Industry Remarks Andrew Holland (FIA) 1:40-2:40pm • TAE – Regulatory Insights Michl Binderbauer (TAE) • Commonwealth Fusion Systems – Fusion Technology and Radiological Bob Mumgaard (CFS) Hazards 2:40-2:50pm Break 2:50-3:10pm Licensing and Regulating Byproduct Materials by the NRC and Agreement States NRC Discussions of Possible Frameworks for Licensing/Regulating Commercial Fusion • NRC Perspectives – Byproduct Approach NRC/OAS 3:10-4:10pm • NRC Perspectives – Hybrid Approach NRC • Industry Perspectives - Hybrid Approach Sachin Desai (Hogan Lovells) 4:10-4:30pm Next Steps/Questions All Public Meeting Format The Commission recently revised its policy statement on how the agency conducts public meetings (ADAMS No.: ML21050A046). NRC Public Website - Fusion https://www.nrc.gov/reactors/new-reactors/advanced/fusion-energy.html NAS Report “Key Goals and Innovations Needed for a U.S. Fusion Pilot Plant” Bringing Fusion to the U.S. Grid R. J. Hawryluk J. Uhle D. Roop D. Whyte March 30, 2021 Committee Composition Richard J. Brenda L. Garcia-Diaz Gerald L. Kathryn A. Per F. Peterson (NAE) Jeffrey P. Hawryluk (Chair) Savannah River National Kulcinski (NAE) McCarthy (NAE) University of California, Quintenz Princeton Plasma Laboratory University of Oak Ridge National Berkeley/ Kairos Power TechSource, Inc. -
The High-Field Path to Practical Fusion Energy
The High-Field Path to Practical Fusion Energy M. Greenwald, D. Whyte, P. Bonoli, D. Brunner, Z. Hartwig, J. Irby, B. LaBombard, E. Marmar, J. Minervini, R. Mumgaard, B. Sorbom, M. Takayasu, J. Terry, R. Vieira, S. Wukitch MIT – Plasma Science & Fusion Center Objective This white paper outlines a vision and describes a coherent roadmap to achieve practical fusion energy in less time and at less expense than the current pathway. The key technologies that enable this path are high-field, high-temperature demountable superconducting magnets, a molten salt liquid blanket, high-field-side lower hybrid current drive and a long-legged divertor. We argue that successful development and integration of these innovative and synergistic technologies would dramatically change the outlook for fusion, providing a real opportunity to positively impact global climate change and to reverse the loss of U.S. leadership in fusion research, suffered in recent decades. Table of Contents 1. Executive summary .............................................................................................................. 1 2. High Temperature Superconductors ................................................................................... 4 3. Demountable Superconducting Magnet Coils ..................................................................... 7 4. Molten-Salt Liquid Blankets ................................................................................................. 9 5. High-Field Launch RF for Heating and Current Drive ........................................................ -
Introduction to Fusion Energy
Introduction to Fusion Energy Jerry Hughes IAP @ PSFC January 8, 2013 Acknowledgments: Catherine Fiore, Jeff Freidberg, Martin Greenwald, Zach Hartwig, Alberto Loarte, Bob Mumgaard, Geoff Olynyk Presenter’s e-mail: [email protected] Questions to answer • What is fusion? • Why do we need it? • How do we get it on earth? • Where do we stand? • Where are we headed? What is fusion, anyway? What is fusion, anyway? What is fusion, anyway? What is fusion, anyway? Fusion is a form of nuclear energy E mc2 • A huge amount of energy is released when isotopes lighter than iron combine to form heavier nuclei, with less final mass • It is an ubiquitous energy source in the universe • It is not (yet) a practical energy source on earth Fusion is a form of nuclear energy E mc2 • A huge amount of energy is released when isotopes lighter than iron combine to form heavier nuclei, with less final mass • It is an ubiquitous energy source in the universe • It is not (yet) a practical energy source on earth Terrestrial energy sources have their origin in the nuclear fusion reactions of stars Supernova produces radioactive elements Solar heating of the Earth drives atmospheric circulation, water cycle Sun illuminates Earth Terrestrial energy sources have their origin in the nuclear fusion reactions of stars Geothermal Decay of radioactive particles generates heat in Earth’s interior Nuclear fission Supernova produces radioactive elements Splitting radioactive particles generates heat Solar heating of the Earth drives atmospheric circulation, water cycle -
The Dynomak: an Advanced Fusion Reactor Concept with Imposed-Dynamo Current Drive and Next-Generation Nuclear Power Technologies
1 FIP/P8-24 The dynomak: An advanced fusion reactor concept with imposed-dynamo current drive and next-generation nuclear power technologies D.A. Sutherland, T.R. Jarboe, K.D. Morgan, G. Marklin and B.A. Nelson University of Washington, Seattle, WA, USA. Corresponding Author: [email protected] Abstract: A high-β spheromak reactor concept called the dynomak has been designed with an overnight capital cost that is competitive with conventional power sources. This reactor concept uti- lizes recently discovered imposed-dynamo current drive (IDCD) and a molten salt (FLiBe) blanket system for first wall cooling, neutron moderation and tritium breeding. Currently available materials and ITER developed cryogenic pumping systems were implemented in this design from the basis of technological feasibility. A tritium breeding ratio (TBR) of greater than 1.1 has been calculated using a Monte Carlo N-Particle (MCNP5) neutron transport simulation. High temperature superconducting tapes (YBCO) were used for the equilibrium coil set, substantially reducing the recirculating power fraction when compared to previous spheromak reactor studies. Using zirconium hydride for neutron shielding, a limiting equilibrium coil lifetime of at least thirty full-power years has been achieved. The primary FLiBe loop was coupled to a supercritical carbon dioxide Brayton cycle due to attractive economics and high thermal efficiencies. With these advancements, an electrical output of 1000 MW from a thermal output of 2486 MW was achieved, yielding an overall plant efficiency of approximately 40%. 1 Introduction An advanced spheromak reactor concept called the dynomak was formulated around the recently discovered imposed-dynamo current drive (IDCD) mechanism on the HIT-SI ex- periment at the University of Washington [1]. -
High Energy Density Plasma Physics Experiments at the National Labs: X-Ray Spectroscopy, Inertial Confinement Fusion, and Laboratory Astrophysics
High Energy Density Plasma Physics Experiments at the National Labs: X-ray Spectroscopy, Inertial Confinement Fusion, and Laboratory Astrophysics David Cohen Swarthmore College Dept. of Physics and Astronomy astro.swarthmore.edu/~cohen → presentations → vanderbilt Talk Outline 1. Facilities and capabilities 2. Inertial Confinement Fusion (ICF) 3. OMEGA experiments: X-ray spectral diagnostics of ICF materials 4. Laboratory astrophysics 5. Creating an X-ray photoionized nebula in the laboratory High Energy Density Plasma Physics at National Facilities Lasers NOVA (Livermore) - closed in late 1990s - 10 beams, 20 kJ UV light in ~1 ns OMEGA (U. Rochester/LLE) - opened in 1970s - 60 beams, 30 kJ, UV (Nd glass laser) National Ignition Facility (NIF) (Livermore) - coming on line this decade - 192 beams, 2 MJ Z-pinches Z-machine/PBFA-II (Sandia) - originally built in 1970s - 20 MA of current in a cylindrical wire array - ~2 MJ of X- rays in ~10 ns These facilities are open to non-lab scientists DOE’s National Laser Users Facilities (NLUF) program enables university scientists access of OMEGA (and previously NOVA), as well as other facilities at Los Alamos, etc. - some coordination with lab scientists and technicians is required/provided Use of the Z-Machine generally requires a Sandia collaborator, but DOE’s fusion grants program (SBSS) provides support and can facilitate collaborations Types of experiments: generally involving high energy density plasmas (>105 atm) Can achieve multi-GPa pressures, 103 g cm-3 densities, multi-million K temperatures in 10 cm3 volume Sophisticated diagnostics are available at these facilities (time resolved imaging and spectroscopy, neutron and other particle detectors, fast radiography, etc.) - Plasma instability studies (instability growth rate, including applications to supernova explosions) - EOS studies (e.g. -
ABSTRACTS §§Il
TR0700270 13™ INTERNATIONAL CONFERENCE ON EMERGING NUCLEAR ENERGY SYSTEMS June 03 - 08, 2007 İstanbul, Türkiye ABSTRACTS HOST ORGANIZATIONS Gazi University, Ankara Bahçeşehir University, Istanbul MAJOR SPONSORS I S T C §§il iililSl M H T Permission is granted for single photocopies of single articles may be made for personal use to reproduce or distribute an individual abstract for educational purposes only. No commercial use or sale is permitted and on this purpose no part of this publication may be reproduced in any form, in an electronic retrieval system or otherwise, without the prior written permission of the publisher. ISBN-978-975-01805-0-7 The copyright to the full work naturally remains with the editor or other current copyright holder. Any copyright questions regarding this publication work therefore should be addressed to the publisher. All other questions also relating to copyright and permissions should be addressed to: Prof. Dr.-Ing. Sümer ŞAHİN Gazi Üniversitesi Teknik Eğitim Fakültesi Makina Bölümü Enerji Anabilim Dalı Teknikokullar-ANKARA 06503-TÜRKİYE Tel. + Fax: +90-312-212 43 04 E-mail: [email protected] Printed in TÜRKİYE ICENES 2007 13»T1H" INTERNATIONAL CONFERENCE ON EMERGING NUCLEAR ENERGY SYSTEMS ABSTRACTS June 03 - 08, 2007 Istanbul, Türkiye 13th International Conference on Emerging Nuclear Energy Systems June 03-08,2007, Istanbul, Türkiye INTRODUCTION AND WELCOME to ICENES2007 The main objective of International Conference series on Emerging Nuclear Energy Systems (ICENES) is to provide an international scientific and technical forum for scientists, engineers, industry leaders, policy makers, decision makers and young professionals who will shape future energy supply and technology, for a broad review and discussion of various advanced, innovative and non-conventional nuclear energy production systems.