Overview of Main Current Msr Projects
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Molten Salt Reactor: Sustainable and Safe Reactor for the Future?
WIR SCHAFFEN WISSEN –HEUTE FÜR MORGEN Jiří Křepel :: MSR activity coordinator :: Paul Scherrer Institut Molten Salt Reactor: sustainable and safe reactor for the future? NES colloquium 14.09.2016 [email protected] INTRODUCTION Page 2 History of Molten Salt Reactor (MSR) Illustration, not MSR started at Oak Ridge National Laboratory 1950s • Aircraft Reactor Experiment (ARE)* 1960s • Molten Salt Reactor Experiment (MSRE)* 1970s • Molten Salt Breeder Reactor (MSBR)* 1970s • EIR (PSI) study (report nr. 411, 1975) fast spectrum, chlorides 1980s • Denatured Molten Salt Reactor (DMSR)* * ORNL <= <= <= Page 3 History of MSR: revival 100 90 80 1990s • Accelerator-driven transmutation 70 keff=0.95 [mA] of Nuclear Waste - ATW (LANL) 60 keff=0.97 curent 2000s • Generation IV, Amster, Sphinx, … 50 keff=0.98 40 2010s • MSFR, Mosart, … fast spectrum, fluorides Accelerator 30 keff=0.99 FHR (fluorides cooled HTR) 20 keff=0.995 2015+ • MCFR, Breed & Burn (TerraPower, PSI, …) 10 keff=0.997 WR at PSI 2.3mA 0 keff=1 fast spectrum, chlorides 0 0.5 1 1.5 2 2.5 3 3.5 ADS reactor power [GWth] <= <= <= Page 4 Classification of MSR MSR is a class of reactors with two groups Type of: Molten salt Application Molten salt fueled reactors cooled reactors Reactor Thermal reactors Fast reactors Fission reactors Fusion reactors Salt Fluorides Fluorides or Chlorides Fluorides Fluorides Core Graphite moderated “Empty” cylinder Graphite based fuel Blanket of the core (ZrH, H2O, D2O, Be, … (TRISO particles) (coolant and/or needs barrier) tritium production) Page 5 Anions in the salts Fluorides Chlorides 19 35 37 100% F 76% Cl + 24% Cl ] 1000 ‐ 1 [ 35Cl 37Cl 19F 0.1 100 interaction 0.01 [b] per XS 10 0.001 Total 0.0001 probabilty 1 0.00001 Capture 35Cl 37Cl 19F 0.1 0.000001 0.001 0.1 10 1000 100000 10000000 0.001 0.1 10 1000 100000 10000000 Incident neutron energy [eV] Incident neutron energy [eV] Number of collision to slow-down fast neutron (2MeV->1eV) 19F 35Cl 37Cl 142 (+big inelastic XS) 258 273 For instance: Iodine as the fission product is the next possible anion. -
Advances in Small Modular Reactor Technology Developments
Advances in Small Modular Reactor Technology Developments Advances in Small Modular Reactor Technology Developments Technology in Small Modular Reactor Advances A Supplement to: IAEA Advanced Reactors Information System (ARIS) 2018 Edition For further information: Nuclear Power Technology Development Section (NPTDS) Division of Nuclear Power IAEA Department of Nuclear Energy International Atomic Energy Agency Vienna International Centre PO Box 100 1400 Vienna, Austria Telephone: +43 1 2600-0 Fax: +43 1 2600-7 Email: [email protected] Internet: http://www.iaea.org Printed by IAEA in Austria September 2018 18-02989E ADVANCES IN SMALL MODULAR REACTOR TECHNOLOGY DEVELOPMENTS 2018 Edition A Supplement to: IAEA Advanced Reactors Information System (ARIS) http://aris.iaea.org DISCLAIMER This is not an official IAEA publication. The material has not undergone an official review by the IAEA. The views expressed do not necessarily reflect those of the International Atomic Energy Agency or its Member States and remain the responsibility of the contributors. Although great care has been taken to maintain the accuracy of information contained in this publication, neither the IAEA nor its Member States assume any responsibility for consequences which may arise from its use. The use of particular designations of countries or territories does not imply any judgement by the publisher, the IAEA, as to the legal status of such countries or territories, of their authorities and institutions or of the delimitation of their boundaries. The mention of names of specific companies or products (whether or not indicated as registered) does not imply any intention to infringe proprietary rights, nor should it be construed as an endorsement or recommendation on the part of the IAEA. -
Preliminary Quantitative Feasibility Analysis of Proposed Thorium-Based Nuclear Reactor
IOP Conference Series: Materials Science and Engineering PAPER • OPEN ACCESS Preliminary quantitative feasibility analysis of proposed Thorium-based nuclear reactor To cite this article: Anas Muhamad Pauzi et al 2019 IOP Conf. Ser.: Mater. Sci. Eng. 555 012006 View the article online for updates and enhancements. This content was downloaded from IP address 43.130.79.121 on 08/10/2021 at 08:30 International Nuclear Science, Technology and Engineering Conference 2018 IOP Publishing IOP Conf. Series: Materials Science and Engineering 555 (2019) 012006 doi:10.1088/1757-899X/555/1/012006 Preliminary quantitative feasibility analysis of proposed Thorium-based nuclear reactor Anas Muhamad Pauzi1,a), Azril Wasim Abdul Wahid1, Juniza Md Saad1 1College of Engineering, Universiti Tenaga Nasional, Jalan IKRAM-UNITEN, 43000 Kajang, Selangor, Malaysia [email protected] Abstract. In the beginning of the 21st century, several research institutions and also private companies had proposed various design of thorium-based nuclear reactor, ranging from solid fuel to molten fuel, fast and thermal neutron spectrum and also various path of waste management. This paper studies 10 of the proposed reactor designs by 10 different organizations, three key aspects analysed quantitatively namely price per kilowatt, safety features and spent fuel managements. Corresponding factors contributing to the key aspects mentioned above were gathered, weighted based on evidence available and analysed using decision matrix. Based on the information collected, preliminary ranking were constructed based on trends between various factors. 1. Introduction 1.1. Thorium reactor developer of the 21st century Thorium fuel reactor was first developed by the Oak Ridge National Laboratory (ORNL) in 1950s, under the Aircraft Reactor Experimental (ARE) by Alvin Weinberg, then director of ORNL. -
Molten-Salt Reactor MSR
Molten-salt reactor MSR Jan Willem Storm van Leeuwen independent consultant member of the Nuclear Consulting Group September 2019 [email protected] Note In this document the references are coded by Q-numbers (e.g. Q6). Each reference has a unique number in this coding system, which is consistently used throughout all publications by the author. In the list at the back of the document the references are sorted by Q-number. The resulting sequence is not necessarily the same order in which the references appear in the text. m44MSR20190924 1 Molten salt reactors A molten salt reactor (MSR) is a class of nuclear fission reactor in which the primary nuclear reactor coolant, or even the fuel itself, is a molten salt mixture. MSRs run at higher temperatures than water-cooled reactors for higher thermodynamic efficiency, while staying at low vapor pressure. The nuclear fuel may be solid or dissolved in the coolant itself. In many designs the nuclear fuel is dissolved in the molten fluoride salt coolant, e.g. uranium tetrafluoride (UF4). An MSR is not typical for thorium-based systems, for it can be fuelled by enriched uranium-235, plutonium and uranium-233. The fluid becomes critical in a graphite core which serves as the moderator. Solid fuel designs rely on ceramic fuel dispersed in a graphite matrix, with the molten salt providing low pressure, high temperature cooling. The Aircraft Reactor Experiment ARE (1954, 2.5 MW(th)) was primarily motivated by the small size that the design could provide. The Molten-Salt Reactor Experiment MSRE (1965–1969, 7.4 MW(th)) was a prototype for a thorium fuel cycle breeder reactor nuclear power plant. -
Validating Results from the Molten Salt Reactor Experiment by Use Of
Validating results from the Molten Salt Reactor Experiment by use of turbulent CFD simulations A study of a modified U-tube shell-and-tube primary heat exchanger and radiator with molten salts Malcolm Akner Space Engineering, master's level 2021 Luleå University of Technology Department of Computer Science, Electrical and Space Engineering PREFACE This thesis is produced as part of the graduating work for my Space Engineering master’s degree, with a profile in aerospace and mathematical modelling, at Luleå University of Technology (LTU). It has been produced in collaboration with Copenhagen Atomics, situated in Copenhagen, Denmark, where I spent the entirety of the project. The project spanned the duration from September 2020 to April 2021, under the supervision of Aslak Stubsgaard (CTO of Copenhagen Atomics) and Robin Andersson (Postdoc at LTU). I have always been interested in energy and electricity generation and have had a special interest in nuclear energy for many years. During my university studies I came across Kirk Sorensen and his work in molten salt reactors. His strong arguments and well-reasoned points, backed up by the successful operation of the Molten Salt Reactor Experiment, conducted in the U.S.A. in the 1960s, convinced me that the MSR technology might be a solution to the energy crisis the world is currently facing. This is a problem that must be solved, with scalable, cost efficient, energy efficient and robust solutions. In this thesis, the fluid dynamic aspects of reactor components from the MSRE were studied and modelled, with the intent to improve our understanding of the functionality and behaviour of high temperature, molten salt environments. -
Thorium for Fission Power
Thorium for fission power Jan Willem Storm van Leeuwen Independent consultant member of the Nuclear Consulting Group August 2019 [email protected] Note In this document the references are coded by Q-numbers (e.g. Q6). Each reference has a unique number in this coding system, which is consistently used throughout all base papers by the author. In the list at the back of the document the references are sorted by Q-number. The resulting sequence is not necessarily the same order in which the references appear in the text. m24thorium20190826 1 Contents 1 Thorium as nuclear fuel Thorium Promised advantages 2 Uranium-233 Safeguards of uranium-233 Cost 3 Thorium breeding cycle Thorium cycle Thorium reactors Time frame of building up a thorium cycle Hybrid reactor Feasibility Energy balance 4 Molten salt reactors 5 Seaborg Wasteburner and Copenhagen Atomics Wasteburner Epilogue References m24thorium20190826 2 1 Thorium as nuclear fuel Thorium Thorium is a radioactive metal, 3-4 times more abundant in the Earth’s crust than uranium. Thorium has a characteristic terrestrial isotopic composition, consisting for nearly 100% of Th-232, and traces of other isotopes, for example Th-228 and Th-230. Thorium is a highly reactive metal. At standard temperature and pressure, thorium is slowly attacked by water, but does not readily dissolve in most common acids, the exception being hydrochloric acid. It dissolves in concentrated nitric acid containing a small amount of catalytic fluoride or fluorosilicate ions; if these are not present, passivation can occur. At high temperatures, it is easily attacked by oxygen, hydrogen, nitrogen, the halogens, and sulfur. -
Evaluation of Power Fluidic Pumping Technology for Molten Salt Reactor Applications
ORNL/TM-2020/1551 Evaluation of Power Fluidic Pumping Technology for Molten Salt Reactor Applications Kevin Robb David Holcomb June 2020 Approved for Public Release CRADA Final Report - for CRADA Number NFE-17-06896 DOCUMENT AVAILABILITY Reports produced after January 1, 1996, are generally available free via US Department of Energy (DOE) SciTech Connect. Website www.osti.gov Reports produced before January 1, 1996, may be purchased by members of the public from the following source: National Technical Information Service 5285 Port Royal Road Springfield, VA 22161 Telephone 703-605-6000 (1-800-553-6847) TDD 703-487-4639 Fax 703-605-6900 E-mail [email protected] Website http://classic.ntis.gov/ Reports are available to DOE employees, DOE contractors, Energy Technology Data Exchange representatives, and International Nuclear Information System representatives from the following source: Office of Scientific and Technical Information PO Box 62 Oak Ridge, TN 37831 Telephone 865-576-8401 Fax 865-576-5728 E-mail [email protected] Website http://www.osti.gov/contact.html 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 responsibility 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. Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise, does not necessarily constitute or imply its endorsement, recommendation, or favoring by the United States Government or any agency thereof. -
Threats of Nuclear Power and Plans for the Future
1 OAK RIDGE INSTITUTE FOR SCIENCE AND EDUCATION Aryobimo Wibowoputro Threats of Nuclear Power and Plans for the Future 2 Table of Content 1. Introduction……………………………………………………………. 3 2. Threats, risk and danger..………………………………………………. 4 3. History of accidents..…………………………………………………… 5 4. Plans for the future.…………..…………………………………………. 7 5. Why Thorium is a better alternative.…….……………………………… 9 6. Conclusion………………………………………………………………. 11 7. References….…………………………………………..……………….. 12 3 Problem Statement Global Environmental Issue The United States alone emits an immense amount of carbon dioxide into the atmosphere. It is extremely likely that the rising global temperature trends since the mid-20th century is dominantly due to human activity. No scientific organization of national or international standing disputes this. Furthermore, the US department of Defense has officially stated that climate change poses a serious national security threat. In light of all that, the United States are committed to significantly reducing carbon emissions in regards to the Paris Climate Agreement. Given that in 2015 alone 2 billion metric tons of carbon dioxide were released from electricity generation only and fossil fuels are responsible for over 99% of these emissions, it would be pretty ideal to start replacing fossil fuel power plants with alternative energy sources like nuclear energy. Ideally, we’d have a source that doesn’t emit CO2 and is consistently reliable; this is known as a baseload energy source. In this context, nuclear energy is the main alternative energy source that works. Yet, unlike its fickle counterparts, nuclear energy is subjected to hostile attitudes adopted by a number of governments in the world which restrict the building or continual operation of power plants. -
Systematic Review: Thorium Molten Salt Reactor 2016-2020
INTERNATIONAL JOURNAL OF SCIENTIFIC & TECHNOLOGY RESEARCH VOLUME 10, ISSUE 01, JANUARY 2021 ISSN 2277-8616 Systematic Review: Thorium Molten Salt Reactor 2016-2020 Achmad Farid Wadjdi, Sigit Permana, Eko Misrianto Abstract: This study seeks to understand the Thorium Molten Salt Reactor (TMSR) readiness as a Thorium Power Plant. We explore the papers published in 2016-2020 to answer questions about the author's concern areas and issues related to the development of the TMSR. We reviewed the corpus of 242 papers out of 977 papers identified from reputable publishers. We present the research themes and trends of TMSR as a proposed power plant system, allowing future work to move forward as research support continues to evolve. The findings indicate an increasing trend of TMSR research mostly in reactor materials, tools, database enrichment, reactor type and design, neutronic, fuels, thermal-hydraulics, and safety/safeguard features. The polarization of research sentiment is 53% positive and 28% negative. We get an annual TMSR-1000MW(e) production cost figure of 3.01 cents/kWh, the total annual cost of $230.15 million, and the total plant cost of $3,507.84 million. We conclude that the TMSR as a power plant system meets technical feasibility, low power cost, and good fuel utilization. The recommendations are the need for collaborative research in advanced materials for the TMSR environment and necessary codes/standards in developing, licensing, waste management, security assurance, and safeguards of TMSR. Index Terms: nuclear power generation, research and development, systematic reviews, thorium molten salt reactor —————————— —————————— 1. INTRODUCTION T HORIUM based power generation has attracted the attention energy policy authorities.