Liquid Fueled Reactors: Molten Salt Reactor Technology
|
|
- Erick Lloyd
- 6 years ago
- Views:
Transcription
1 Liquid Fueled Reactors: Molten Salt Reactor Technology Dr. Jess C. Gehin Lead, Reactor Technology R&D Integration Reactor and Nuclear Systems Division Thorium Energy Conference 2011 City College of New York October 10, 2011
2 Presentation Outline Motivations for the use of liquid Fuels The three primary ORNL MSR concepts Performance aspects of the ORNL MSR concepts Experience with MSRs at ORNL (ARE, MSRE) New Technologies for Commercial Deployment Current related research and development 2 Managed by UT-Battelle
3 Motivations for Liquid Fuels Liquid fuels seem novel today, but as will be described in the following slides, they were not seen as being unusual in the early days of nuclear energy Liquid fuel uniquely allows: Elimination of fuel fabrication processes (rather they become fuel material preparation processes) Can eliminate heat transfer issues as the fuel material also serves as the coolant and therefore support high power densities Supports online fueling/defueling operations by pumping rather than mechanical means Allows on-line fuel reprocessing (although this is not required) This is important for optimizing the use of thorium as in thermal breeders Potential for passive safety As a result, fluid-fueled reactors had a significant development effort from the 1940s to the 1970s. 3 Managed by UT-Battelle
4 Two very different schools of reactor design have emerged since the first reactors were built. One approach, exemplified by solid fuel reactors, holds that a reactor is basically a mechanical plant; the ultimate rationalization is to be sought in simplifying the heat transfer machinery. The other approach, exemplified by liquid fuel reactors, holds that a reactor is basically a chemical plant; the ultimate rationalization is to be sought in simplifying the handling and reprocessing of fuel. At the Oak Ridge National Laboratory we have chosen to explore the second approach to reactor development. R.C. Briant & Alvin Weinberg, Molten Fluorides as Power Reactor Fuels, Nuc. Sci. Eng, 2, (1957). 4 Managed by UT-Battelle
5 1959 Task Force and Down Selection In 1959 the three fluid-fueled reactor concepts were being developed were reviewed by an AEC expert task force Aqueous Homogenous Reactor (ORNL) Liquid Metal Fuel Reactor (BNL) Molten Salt Reactor (ORNL) This task force ultimately resulted in the down selection to the MSR as the primary fluid-fueled reactor concept (TID-8507): The molten salt reactor has the highest probability of achieving technical feasibility. This is largely due to the use of a solution fuel (as contrasted to a slurry fuel in the LMFR and the AHR), and the availability of a suitable container material (INOR-8) 5 Managed by UT-Battelle
6 Molten Salt Reactors Were Among the First Successful Reactor Demonstrations Molten Salt Reactors were being developed at the same time as the AHR at ORNL and the Liquid-Metal Reactor at BNL The first MSR was developed to support the Aircraft Nuclear Propulsion program Initial reactor the Air Craft Reactor Experiment provided initial technology push Proposed to overcome issues with solid fueled reactors at high temperatures (e.g. positive reactivity coefficient from Xenon) Very early demonstration of technology, operated for 100 MWh over nine days in November 1954 Considered successful, but did have issues with leaking radioactive gases ANP ended in 1961, but civilian program had already been launched. Aircraft Reactor Experiment 6 Managed by UT-Battelle
7 ORNL Matured Thorium-Fueled- MSRs Through The Development of Three Distinct Concepts Two-Fluid MSBR Fertile/Fissile salts separate Simpler salt processing More complex core design Modular Design Ultimately dropped by ORNL Single Fluid MSBR Mixes fissile/fertile into single salt Complex salt processing Simpler core design Reference MSBR concept at end of program Denatured MSR Developed in response to mid-70s proliferation concerns Once-through design (no processing) Keeps uranium in LEU form Requires LEU uranium support 7 Managed by UT-Battelle
8 Mature Two-Fluid MSBR Design (1967) Provided Graphite Element and Core Design 8 Managed by UT-Battelle
9 Two Fluid Reactor Core Layout 9 Managed by UT-Battelle
10 The Two-Fluid Reactor had a Modular Design (4 modules x 250 MWe = 1 GWe) Shared Salt Processing System 10 Managed by UT-Battelle
11 The Plumbing Problem Resulted in ORNL Moving to a Single Fluid Concept The two-fluid design required internal blankets, which created a plumbing problem Maintaining the coolant flow channels and returns resulted in a complex design Note that graphite shrinks and swells during irradiation Developments in the late 60s provide a way to separate the fission products from thorium Alternative designs have been proposed to address this and advanced materials may also provide an answer. So the two-fluid system may be of interest in the future. 11 Managed by UT-Battelle
12 The Single Fluid Design (1972) was the ORNL Reference MSBR at the end of the MSR Program 12 Managed by UT-Battelle
13 The Single Fluid Salt Processing Has Several Separation Steps Gaseous Fission Products/Nobel Metals Rare Earth Thorium Sep From Protactinium/Uranium Pa Decay/U Separation Rare Earth Separation Uranium Separation 13 Managed by UT-Battelle
14 The Chemistry of the Separations Processes Dictates FP/Actinide Removal Rates The Salt/Thorium Discard Is A Key Parameter in Determining Thorium Utilization. The discard is required for materials that cannot be separated from the salt and thorium 14 Managed by UT-Battelle
15 A Recent Assessment of the MSBR Performance Parameters A number of performance parameters have been evaluated for the MSR based on the historical MSBR concepts that are well documented in: ORNL-4528 Two fluid MSBR ORNL-4541 Single fluid MSBR ORNL/TM-7207 Denatured Molten Salt Reactor These are vintage 1970 (1980 in case of DMSR) designs We have no reasonably complete modern MSR concept design and performance evaluation One would expect that with advancements that the performance would be better than 1970 s version, but that remains to be proven. 15 Managed by UT-Battelle
16 Summary of Key MSBR Parameters These values from MSBR design report (ORNL-4541) (note that at the time it was assumed that the capacity factor would be 80%) 16 Managed by UT-Battelle
17 The DMSR Was Developed to Address Proliferation Concerns of the 1970s Online processing is not performed (other than Kr, Xe gas removal and noble metal plate out) Enriched Uranium (19.75%) for startup and as feed material (to make up for limited processing) Operated as once-through system Lower reactor power density (no graphite replacement) Fueling Thorium added only at initial loading Enriched uranium added as required to maintain criticality U-238 added as needed to maintain denatured state U-238 > (6 * U-233 )+(4 * U-235 ) 17 Managed by UT-Battelle
18 Summary of Key DMSR Performance Parameters 18 Managed by UT-Battelle
19 MSRs Provide Excellent Resource Utilization Fission consumes ~1 tonne of fuel/gwe-yr. So 11 tonnes/gwe-yr represents a 10% utilization of thorium. This value is primarily driven by the salt processing, not fuel burnup. 19 Managed by UT-Battelle
20 The MSBR Project Provided Cost Estimates along with a PWR Yard Stick 20 Managed by UT-Battelle
21 Nuclear Reactor Cost Escalation Must Account for Inflation + Other Factors Standard cost escalation approaches have been applied to the MSR and PWR costs from the 1972 design report. Escalation of 1970 s PWR to 2010 results in a capital cost of $1350/kWe The inflation adjusted cost is a factor of three lower than the current nominal PWR cost of $4000/kWe Factors other than inflation have lead to cost increases Examples: Schedule, regulatory, quality, financing, ES&H, security Many factors that did not exist in 1970) Therefore, you cannot simply apply standard escalation 21 Managed by UT-Battelle
22 There are Several Qualitative Comparisons that can be made to PWRs MSR favorable economics factors (compared to PWR): High temperature can provide higher conversion efficiency Lower operating pressure reduces metal thicknesses, fab costs, transportation costs, Modular fabrication/manufacturing approaches MSR Unfavorable economics factors (compared to PWR): While low pressure, must have containment to protect from external events Includes radiochemical plant, drain tanks, off-gas system Requires additional materials (graphite, high purity Li-7) 1970s estimate had low value of indirect costs (35%) compared with current practice (quality, regulatory, certification, etc.) We do not have a good estimate for MSR capital costs, but taking these considerations into account it appears to be similar to that of PWR (nominal value is $4,000/kWe), similar to original assessment The resulting estimate of levelized cost of electricity is expected to be comparable to that from PWR 22 Managed by UT-Battelle
23 The Successful Operation of Two MSRs at ORNL Provided Proof of Principle Two MSRs successfully operated ARE (9 days of operation at high temperature) Molten Salt Reactor Experiment (MSRE, 5 years of operation) A third was essentially constructed, but not operated (Air Craft Reactor Test) MSRE highly successful experiment involving operation of a molten salt reactor with attributes that are similar to a power reactor Established a proof of principle with good operating record Operated on U-235 and U-233 Identified issues for R&D program (e.g. Tritium, Tellurium attack of INOR) However, was not a complete demonstration (no thorium used in MSRE, no fission product removal, no power conversion system) ORNL proposed follow-on programs to lead to a commercial MSBR Molten Salt Breeder Experiment and a Demonstration Reactor 23 Managed by UT-Battelle ORNL MSRE
24 There are several new technologies that must be introduced for deployment of Commercial MSRs >5 wt%u-235 LEU fuel (needed for startup) U-233 as the fissile material The use of thorium Salt processing system (possibly online during operation) Development and deployment of a new Li-7 enrichment capability High temperature operation (potentially with a Brayton power conversion system) Off-gas handling and storage system 24 Managed by UT-Battelle
25 Salt-Cooled Reactors Use Common Technologies as MSRs DOE Advanced Reactor Concepts is supporting R&D on Fluoride-Salt-Cooled High Temperature Reactors (FHRs) Uses solid fuel (high temperature TRISO fuel) with liquid salt coolant (FLiBe) Leverages past development work on MSRs regarding salt, components, and materials Concepts under development (large and small) and salt loop being established at ORNL 125 MWe SmAHTR Integral Salt-Cooled Reactor 25 Managed by UT-Battelle
26 Summary of Key Points Liquid fueled MSRs provide an innovative means to effectively utilize thorium. MSRs demonstrate excellent performance in terms of resource utilization (10% Th Consumption with Historical Designs) and low TRU production. Economics are uncertain, but based on ORNL MSBR experience costs appear to be comparable to LWRs. Several concepts developed by ORNL, but no modern MSR design is available. Developing such a design is important to establishing and improving performance and cost. Experimental systems showed promising performance further R&D needed to move to engineering and commercial scale 26 Managed by UT-Battelle
27 For More information I suggest the following Murray W. Rosenthal, An Account of Oak Ridge Laboratory s Thirteen Nuclear Reactors, Oak Ridge National Laboratory, ORNL/TM-2009/181, December R. C. Robertson, et al., Two-Fluid Molten-Salt Breeder Reactor Design Study, Oak Ridge National Laboratory, ORNL-4528 (1970). R. C. Robertson, et al., Conceptual Design Study of a Single-Fluid Molten-Salt Breeder Reactor, Oak Ridge National Laboratory, ORNL-4541 (1971). J. R. Engel, et al., Conceptual Design Characteristics of a Denatured Molten-Salt Reactor with Once- Through Fueling, Oak Ridge National Laboratory, ORNL/TM-7207 (1980). David E. Shropshire, GNEP Economic Analysis Working group; Global Nuclear Energy Partnership Economic Tools, Algorithms, and Methodologies Report; INL/EXT ; May D. E. Shropshire, K.A. Williams, et al; Advanced Fuel Cycle Cost Basis; INL/EXT ; December 2009 U.S. AEC, Report of the Fluid Fuel Reactors Task Force to the Division of Reactor Development, TID- 8507, February S. R. Greene, et al, Pre-Cconceptional Design of a Fluoride-Salt Cooled Small Modular Advanced High Temperature Reactor (SmAHTR), Oak Ridge National Laboratory, ORNL/TM-2010/199 (2010) - ORNL FHR webpage (currently with information from FHR workshop) 27 Managed by UT-Battelle
28 Questions? 28 Managed by UT-Battelle
A Brief History of Molten Salt Reactors
A Brief History of Molten Salt Reactors EVOL Workshop IPN-Orsay, France May 21-22, 2012 Dr. David E. Holcomb Reactor and Nuclear Systems Division HolcombDE@ornl.gov First a Couple of Quotes That Point
More informationMolten Salt Reactor Technology for Thorium- Fueled Small Reactors
Molten Salt Reactor Technology for Thorium- Fueled Small Reactors Dr. Jess C. Gehin Senior Nuclear R&D Manager Reactor and Nuclear Systems Division gehinjc@ornl.gov, 865-576-5093 Advanced SMR Technology
More informationThe DMSR: Keeping it Simple
The DMSR: Keeping it Simple March 29 th 2010 2 nd Thorium Energy Conference Dr. David LeBlanc Physics Dept, Carleton University, Ottawa & Ottawa Valley Research Associates Ltd. d_leblanc@rogers.com What
More informationThe Tube in Tube Two Fluid Approach
The Tube in Tube Two Fluid Approach March 29 th 2010 2 nd Thorium Energy Conference Dr. David LeBlanc Physics Dept, Carleton University, Ottawa & Ottawa Valley Research Associates Ltd. d_leblanc@rogers.com
More informationMolten Salt Reactors: A 2 Fluid Approach to a Practical Closed Cycle Thorium Reactor
Molten Salt Reactors: A 2 Fluid Approach to a Practical Closed Cycle Thorium Reactor Oct 25 th 2007 Presentation to the Ottawa Chapter of the Canadian Nuclear Society Dr. David LeBlanc Physics Department
More informationFHRs and the Future of Nuclear Energy
FHRs and the Future of Nuclear Energy Presented to DOE FHR Workshop At Oak Ridge National Laboratory Sept. 20-21, 2010 By Sherrell Greene Director, Nuclear Technology Programs Oak Ridge National Laboratory
More informationMolten Salt Reactors
Molten Salt Reactors May 30th 2013 Presentation to 5th Thorium Energy Alliance Conference Chicago Dr. David LeBlanc Terrestrial Energy Inc. dleblanc@terrestrialenergyinc.com The Basics: Molten Salt Reactors
More informationMolten Salt Reactors (MSRs)
Molten Salt Reactors (MSRs) Dr. Charles W. Forsberg Oak Ridge National Laboratory * P.O. Box 2008 Oak Ridge TN 37830-6179 Tel: (865) 574-6783 Fax: (865) 574-9512 E-mail: forsbergcw@ornl.gov Manuscript
More informationThorium and Uranium s Mutual Symbiosis: The Denatured Molten Salt Reactor DMSR
Thorium and Uranium s Mutual Symbiosis: The Denatured Molten Salt Reactor DMSR Dr. David LeBlanc Physics Dept, Carleton University, Ottawa & Ottawa Valley Research Associates Ltd. d_leblanc@rogers.com
More informationTHE KNOWN UNKNOWNS OF MOLTEN SALT REACTORS
THE KNOWN UNKNOWNS OF MOLTEN SALT REACTORS R. Ortega Pelayo 1, M. Edwards 2 1 Canadian Nuclear Laboratories,Chalk River, Ontario, Canada (286 Plant Road, Stn. 42, (613) 584 3311 ext. 44155, rosaelia.ortegapelayo@cnl.ca)
More informationMolten Salt Reactors
Nuclear Engineering Panel Technical Presentation Molten Salt Reactors Date: Wednesday, 19 th March 2014 Time: 5.30 pm for 6.00 pm Venue: Engineers Australia Harricks Auditorium, Ground Floor, 8 Thomas
More informationFOR A FUTURE WE CAN BELIEVE IN. International Thorium Energy Conference 2015
FOR A FUTURE WE CAN BELIEVE IN International Thorium Energy Conference 2015 ( 10-13 - 2015 ) LFTR: In search of the Ideal Pathway to Thorium Utilization Development Program Update. Current Status Benjamin
More informationLiquid Fluoride Reactors: A Luxury of Choice
Liquid Fluoride Reactors: A Luxury of Choice Oct 20 th 2009 Thorium Energy Alliance Conference Dr. David LeBlanc Physics Dept, Carleton University, Ottawa & Ottawa Valley Research Associates Ltd. d_leblanc@rogers.com
More informationOnline Reprocessing Simulation for Thorium-Fueled Molten Salt Breeder Reactor
Online Reprocessing Simulation for Thorium-Fueled Molten Salt Breeder Reactor Andrei Rykhlevskii, Alexander Lindsay, Kathryn Huff Advanced Reactors and Fuel Cycles Group University of Illinois at Urbana-Champaign
More informationMolten Salt Converter Reactors: DMSR to SmAHTR and Back
Molten Salt Converter Reactors: DMSR to SmAHTR and Back March 22 nd 2013 Presentation to University of Ontario Institute of Technology Dr. David LeBlanc Terrestrial Energy Inc. dleblanc@terrestrialenergyinc.com
More informationINAC-ENFIR Recife, November Molten Salt Nuclear Reactors
INAC-ENFIR Recife, November 24-29 2013 Molten Salt Nuclear Reactors Dr Cassiano R E de Oliveira Department of Chemical and Nuclear Engineering The University of New Mexico cassiano@unm.edu Outline Motivation
More informationTOO GOOD TO LEAVE ON THE SHELF
As published in Mechanical Engineering magazine. 2010 ASME. Used with permission. TOO GOOD TO LEAVE ON THE SHELF A reactor design mothballed 40 years ago doesn t seem like a technology with much potential.
More informationBasic dynamics of graphite moderated LEU fueled MSRs
UTK seminar, July 18th 2014 Basic dynamics of graphite moderated LEU fueled MSRs Dr. Ondřej Chvála Seminar overview Historical context and lessons MSR salt & lattice choices Reactor dynamics:
More informationDenatured Molten Salt Reactors (DMSR): An Idea Whose Time Has Finally Come? Abstract
Denatured Molten Salt Reactors (DMSR): An Idea Whose Time Has Finally Come? D. LeBlanc 1,2 1 Physics Dept, Carleton University, Ottawa, Canada 2 Ottawa Valley Research Associates Ltd. Abstract Molten Salt
More informationDESIGN AND SAFETY- SUPPORT ANALYSES OF AN IN-PILE MOLTEN SALT LOOP IN THE HFR
DESIGN AND SAFETY- SUPPORT ANALYSES OF AN IN-PILE MOLTEN SALT LOOP IN THE HFR stempniewicz@nrg.eu M.M. Stempniewicz, E.A.R. de Geus, F. Alcaro, P.R. Hania, K. Nagy, N.L. Asquith, J. de Jong, L. Pool, S.
More informationCost of electricity from Molten Salt Reactors (MSR)*
Nuclear Technology 138 93-95 (2002)10/2/2001 Cost of electricity from Molten Salt Reactors (MSR)* R. W. Moir a Lawrence Livermore National Laboratory, P. O. Box 808, L-637, Livermore, CA 94550, Tel: 925-422-9808,
More informationThe Curious Tale of Molten Salt Reactors
The Curious Tale of Molten Salt Reactors May 2 nd 2013 Presentation to Canadian Nuclear Society, Ottawa Branch Dr. David LeBlanc Terrestrial Energy Inc. dleblanc@terrestrialenergyinc.com The Basics: Molten
More informationMolten Salt Reactors and the Oil Sands: Odd Couple or Key to North American Energy Independence?
Molten Salt Reactors and the Oil Sands: Odd Couple or Key to North American Energy Independence? June 12 th 2012 Presentation to Canadian Nuclear Society, Western Focus Track Dr. David LeBlanc Ottawa Valley
More informationMolten-Salt Reactor FUJI and Related Thorium Cycles
Thorium Energy Alliance Spring Conference 2010, March 29-30, 2010, Mountain View, USA 1 Molten-Salt Reactor FUJI and Related Thorium Cycles Ritsuo Yoshioka (Presenter)* K. Furukawa, Y. Kato, K. Mitachi
More informationMolten Salt Converter Reactors: From DMSR to SmAHTR
Molten Salt Converter Reactors: From DMSR to SmAHTR Jan 10 th 2013 Conference on Molten Salts in Nuclear Technology Dr. David LeBlanc Terrestrial Energy Inc. Formerly Ottawa Valley Research Associates
More information-What is is Thorium Molten-Salt Nuclear Energy Synergetic System: THORIMS-NES?
Thorium Energy Alliance Conference March 29-30, 2010, Mountain View, CA, USA: -What is is Thorium Molten-Salt Nuclear Energy Synergetic System: THORIMS-NES? (Establishing (Establishing SIMPLEST SIMPLEST
More informationU.S. MSR Development Programs & Supportive Efforts
U.S. MSR Development Programs & Supportive Efforts IAEA Workshop on Molten Salt Reactor Technology David Holcomb US-Department of Energy Technical Lead for MSRs Oak Ridge National Laboratory IAEA Headquarters,
More informationTeam 16: The Nuclear Family EN-FISSIONING A SUSTAINABLE FUTURE
Team 16: The Nuclear Family EN-FISSIONING A SUSTAINABLE FUTURE Outline 2 Systems Designs Power Cycle Economics Conclusion Questions https://inlportal.inl.gov/portal/server.pt?open=514&objid=1269&mode=2&f
More informationWorkshop on PR&PP Evaluation Methodology for Gen IV Nuclear Energy Systems. Tokyo, Japan 22 February, Presented at
PR&PP Collaborative Study with GIF System Steering Committees A Compilation of Design Information and Crosscutting Issues Related to PR&PP Characterization Presented at Workshop on PR&PP Evaluation Methodology
More informationThe role of Thorium for facilitating large scale deployment of nuclear energy
The role of Thorium for facilitating large scale deployment of nuclear energy R.K. Sinha Chairman, Atomic Energy Commission Government of India IAEA International Ministerial Conference on Nuclear Power
More informationProgress in Molten Salt Reactor (MSR) Modeling Seminar Series Ondřej Chvála
Nuclear Engineering Seminar 2013 Progress in Molten Salt Reactor (MSR) Modeling Seminar Series Ondřej Chvála Seminar overview Historical and international context of the work. Contemporary
More informationNexus of Safeguards, Security and Safety for Advanced Reactors
Nexus of Safeguards, Security and Safety for Advanced Reactors Dr. George Flanagan Oak Ridge National Laboratory, USA Dr. Robert Bari Brookhaven National Laboratory, USA Presentation for the Global Nexus
More informationMolten Salt Reactors: A New Vision for a Generation IV Concept
Molten Salt Reactors: A New Vision for a Generation IV Concept David LeBlanc Physics Department, Carleton University, Ottawa Ontario dleblanc@physics.carleton.ca Abstract Molten Salt Reactors were developed
More informationTransmutation of Transuranic Elements and Long Lived Fission Products in Fusion Devices Y. Gohar
Transmutation of Transuranic Elements and Long Lived Fission Products in Fusion Devices Y. Gohar Fusion Power Program Technology Division Argonne National Laboratory 9700 S. Cass Avenue, Argonne, IL 60439,
More informationAbundant and Reliable Energy from Thorium. Kirk Sorensen Flibe Energy UT Energy Week February 17, 2015
Abundant and Reliable Energy from Thorium Kirk Sorensen Flibe Energy UT Energy Week February 17, 2015 This is incorrect. Nuclear energy is our greatest hope for the future. Nuclear energy contains over
More informationThe Molten Salt Reactor Adventure
NUCLEAR SCIENCE AND ENGINEERING: 90, 374-380 (1985) The Molten Salt Reactor Adventure H. G. MacPherson Consultant, Oak Ridge, Tennessee 37831 Accepted March 15, 1985 Abstract - A personal history of the
More informationNeutronic and Fuel Cycle Consideration: from Single Stream to Two Fluid Th-U Molten Salt System. Olga S. Feinberg
Neutronic and Fuel Cycle Consideration: from Single Stream to Two Fluid Th-U Molten Salt System. Olga S. Feinberg RRC-Kurchatov Institute, 123182, Moscow, RF The History of the Problem In the 60 s and
More informationAdvanced Reactors Mission, History and Perspectives
wwwinlgov Advanced Reactors Mission, History and Perspectives Phillip Finck, PhD Idaho National Laboratory Senior Scientific Advisor June 17, 2016 A Brief History 1942 CP1 First Controlled Chain Reaction
More informationSmAHTR the Small Modular Advanced High Temperature Reactor
SmAHTR the Small Modular Advanced High Temperature Reactor Presented to DOE FHR Workshop Oak Ridge National Laboratory September 20-21, 2010 By Sherrell Greene Director, Nuclear Technology Programs Oak
More informationMolten Fluorides as Power Reactor Fuels 1
NUCLEAR SCIENCE AND ENGINEERING: 2, 797-803 (1957) Molten Fluorides as Power Reactor Fuels 1 R. C. BRIANT 2 AND ALVIN M. WEINBERG Oak Ridge National Laboratory, 3 P.O. Box X, Oak Ridge, Tennessee Received
More informationThorium Molten Salt Nuclear Energy Synergetic System (THORIMS-NES)
Thorium Molten Salt Nuclear Energy Synergetic System (THORIMS-NES) Ritsuo Yoshioka (*1), Koshi Mitachi (*1) & Motoyasu Kinoshita(*1,2) (*1) International Thorium Molten-Salt Forum (*2)University of Tokyo
More informationBasic neutronics and dynamics of graphite moderated LEU fueled MSRs
CVUT seminar, May 13th 2014 Basic neutronics and dynamics of graphite moderated LEU fueled MSRs Dr. Ondřej Chvála Seminar overview Historical context and lessons MSR salt & lattice choices
More informationMolten Salt Reactor system
Molten Salt Reactor system 2009-2012 Status J. Serp & H. Boussier* Chair of the Molten Salt Reactor System Steering Committee * Former Chairman Slides prepared in collaboration with CNRS (France) and JRC
More informationFusion-Fission Hybrid Systems
Fusion-Fission Hybrid Systems Yousry Gohar Argonne National Laboratory 9700 South Cass Avenue, Argonne, IL 60439 Fusion-Fission Hybrids Workshop Gaithersburg, Maryland September 30 - October 2, 2009 Fusion-Fission
More informationURANIUM-THORIUM LIQUID-SALT REACTOR FOR PRODUCING VALUABLE RADIOISOTOPES
URANIUM-THORIUM LIQUID-SALT REACTOR FOR PRODUCING VALUABLE RADIOISOTOPES Alexander DeVolpi (retired, Argonne National Laboratory) and Ralph Moir (retired, Lawrence Livermore National Laboratory) TEAC5,
More informationChemical Engineering 412
Chemical Engineering 412 Introductory Nuclear Engineering Lecture 20 Nuclear Power Plants II Nuclear Power Plants: Gen IV Reactors Spiritual Thought 2 Typical PWR Specs Reactor Core Fuel Assembly Steam
More informationElectromagnetic flowmeter, 861 Electromagnetic pumps, 844 characteristics, 845 efficiency, 845 End blanket effects, 869 Energy costs, summary, 921 Eng
PART III INDEX Activity coefficients, at infinite dilution, 808 Additives, effect on solubility of corrosion products in bismuth, 727 Alloy steel, 743 Annual aqueous processing costs vs plant throughput,
More informationPhysical Aspects of Molten Salt Reactors
EUROPEAN ACADEMIC RESEARCH Vol. VI, Issue 7/ October 2018 ISSN 2286-4822 www.euacademic.org Impact Factor: 3.4546 (UIF) DRJI Value: 5.9 (B+) Physical Aspects of Molten Salt Reactors BADAWY M. ELSHEIKH
More informationFJ/OH The 2004 Frédéric JOLIOT & Otto HAHN Summer School. August 25 September 3, 2004 CADARACHE, France TOPIC 2 THE REACTORS AND THEIR FUELS
FJ/OH 2004 The 2004 Frédéric JOLIOT & Otto HAHN Summer School August 25 September 3, 2004 CADARACHE, France TOPIC 2 THE REACTORS AND THEIR FUELS **** Reactors with Molten Salts: Options and Missions Charles
More informationARTICLE IN PRESS Nuclear Engineering and Design xxx (2010) xxx xxx
Nuclear Engineering and Design xxx (2010) xxx xxx Contents lists available at ScienceDirect Nuclear Engineering and Design journal homepage: www.elsevier.com/locate/nucengdes Molten salt reactors: A new
More informationModular Helium-cooled Reactor
Modular Helium-cooled Reactor The role of the GTMHR in GNEP E. Michael Campbell Francesco Venneri General Atomics April 2007 SEMA Conference 1 OUTLINE Motivation High Temperature gas reactors MHR as burner
More informationAim High! Thorium energy cheaper than from coal. Walk away safe.
Aim High! Thorium energy cheaper than from coal. Walk away safe. robert.hargraves@gmail.com Global environmental problems mount. Prosperity stabilizes population. GDP per capita 82 nations with populations
More informationPre-Conceptual Hydrogen Production Modular Helium Reactor Designs. IAEA International Conference on Non-Electric Applications of Nuclear Energy
Pre-Conceptual Hydrogen Production Modular Helium Reactor Designs Matt Richards, Arkal Shenoy, and Mike Campbell General Atomics IAEA International Conference on Non-Electric Applications of Nuclear Energy
More informationSimple Molten Salt Reactors: a time for couragous impatience
Simple Molten Salt Reactors: a time for couragous impatience Preliminary Draft for Discussion Only Jack Devanney Center for Tankship Excellence, USA, djw1@c4tx.org 1 History After World War II, there was
More informationFluoride Salt Cooled High Temperature Reactors
Fluoride Salt Cooled High Temperature Reactors Workshop on Advanced Reactors PHYSOR 2012 Knoxville, TN April 15, 2012 David Holcomb HolcombDE@ornl.gov FHRs Combine Desirable Attributes From Other Reactor
More informationModule 12 Generation IV Nuclear Power Plants. Atominstitute of the Austrian Universities Stadionallee 2, 1020 Vienna, Austria
Module 12 Generation IV Nuclear Power Plants Prof.Dr. H. Böck Atominstitute of the Austrian Universities Stadionallee 2, 1020 Vienna, Austria boeck@ati.ac.at Generation IV Participants Evolution of Nuclear
More informationINTEGRAL MOLTEN SALT REACTOR
1 INTERNATIONAL WORKSHOP ON ADVANCED REACTOR SYSTEMS AND FUTURE ENERGY MARKET NEEDS David Leblanc, President and CTO Terrestrial Energy April 12 th, 2017 INTEGRAL MOLTEN SALT REACTOR 1 2 IMSR TECHNOLOGY
More informationThorium Molten Salt Nuclear Energy Synergetic System (THORIMS-NES).
Paper for CMSNT (Conference on Molten Salts in Nuclear Technology), Mumbai, 2013 Thorium Molten Salt Nuclear Energy Synergetic System (THORIMS-NES). Ritsuo Yoshioka, Koshi Mitachi International Thorium
More informationWork in Progress. Assessment Matrix with Descriptions Version 11
Work in Progress The Generic Feasibility Assessment: An Essential Ingredient in Nuclear Policy making Assessment Matrix with Descriptions Version 11 Subject System: EVOL or GIF Molten Salt Fast Reactor
More informationThorCon Breeder Reactor Design
ThorCon Breeder Reactor Design MOLTEN SALT THORIUM REACTOR TEAM LOKI: Mitch Abeln, Samuel Cole, Matt Glattfelder, Valerie Nwadeyi UNIVERSITY OF WISCONSIN-MADISON 412 SENIOR DESIGN SECTION 1- Executive
More informationINTRODUCTION TO SMR S
1 INTRODUCTION TO SMR S Ferry Roelofs 20 April 2018 EU DuC = N 2 CONTENTS 1. What is an SMR? 2. Why SMR s? 3. Which SMR s? WHAT IS AN SMR? 3 4 WHAT IS AN SMR? DEFINITION: IAEA IAEA Small to Medium sized
More informationEnergy From Thorium Foundation
The Energy From Thorium Foundation Mission To educate and promote the adoption of Nuclear energy based on the use of Thorium in molten salt reactors, as a means to usher in an era of Sustainable Abundance
More informationPractical Aspects of Liquid-Salt-Cooled Fast-Neutron Reactors
Practical Aspects of Liquid-Salt-Cooled Fast-Neutron Reactors Charles Forsberg (ORNL) Per F. Peterson (Univ. of California) David F. Williams (ORNL) Oak Ridge National Laboratory P.O. Box 2008; Oak Ridge,
More informationNuclear power. ME922/927 Nuclear 1
Nuclear power ME922/927 Nuclear 1 The process The production of electricity by nuclear fission. Torness power station The impact of a neutron with a U 235 nucleus causes the fission process, from which
More informationSafeguard and protection requirements for Gen-IV reactor systems
Matthew Gill 25/03/13 Matthew.gill-2@postgrad.manchester.ac.uk Safeguard and protection requirements for Gen-IV reactor systems 1 Content 1. Gen-IV reactors Concepts and Advantages TRL and contribution
More information(This paper was taken from Terrestrial Energy s web site June )
(This paper was taken from Terrestrial Energy s web site June 18 2016) How it Works Molten Salt Reactors ( MSRs ) are nuclear reactors that use a fluid fuel in the form of a molten fluoride or chloride
More informationTHE USE OF THORIUM IN NUCLEAR POWER REACTORS JUNE 1969
WASH 1097 UC-80 THE USE OF THORIUM IN NUCLEAR POWER REACTORS JUNE 1969 PREPARED BY Brookhaven National Laboratory AND THE Division of Reactor Development and Technology WITH THE ASSISTANCE OF ARGONNE NATIONAL
More informationThe Advanced High-Temperature Reactor: High-Temperature Fuel, Molten Salt Coolant, and Liquid-Metal-Reactor Plant.
INES-1 Paper # 71 The Advanced High-Temperature Reactor: High-Temperature Fuel, Molten Salt Coolant, and Liquid-Metal-Reactor Plant Charles Forsberg Oak Ridge National Laboratory* P.O. Box 2008 Oak Ridge,
More informationMolten-Salt-Reactor Technology Gaps
Molten-Salt-Reactor Technology Gaps Proceedings of ICAPP 06 Charles W. Forsberg Oak Ridge National Laboratory * P.O. Box 2008; Oak Ridge, TN 37831-6165 Tel: (865) 574-6783; Fax: (865) 574-0382 E-mail:
More informationGeneration IV Water-Cooled Reactor Concepts
Generation IV Water-Cooled Reactor Concepts Technical Working Group 1 - Advanced Water- Cooled Reactors Generation IV Roadmap Session ANS Winter Meeting Reno, NV November 13, 2001 1 TWG 1 Members Mario
More informationRole of Advanced Nuclear Power In Environment Sustainability
Role of Advanced Nuclear Power In Environment Sustainability Ruchi Gakhar, UW Madison Earth Day Conference UW Madison 25 April 2016 UCB Thermal Hydraulics Lab Energy Sources Nuclear Plants United States
More informationThorium an alternative nuclear fuel cycle
Thorium an alternative nuclear fuel cycle 5th Smart Grids & Clean Power Conference, Cambridge, 5 June 2013 www.cir-strategy.com/events/cleanpower Kevin Hesketh, Senior Research Fellow Outline General Principles
More informationMOLTEN-SALT REACTORS-HISTORY, STATUS, AND POTENTIAL
MOLTEN-SALT REACTORS-HISTORY, STATUS, AND POTENTIAL M. W. ROSENTHAL, P.R. KASTEN, and R. B. BRIGGS Oak Rwge National Laboratory, Oak Rwge, Tennessee 37830 KEYWORDS: mo/ten sa/t re actors, breeder reactors,
More informationReview of R&D of thorium molten-salt reactor
KAMEI Takashi Kyoto Neutronics, 134 Chudoji Minamimachi, Shimogyo-ku, Kyoto, 600-8813, Japan (takashi.kamei@kyoto-neutronics.co.jp) 1 Introduction 1 Abstract: Nuclear power will be used continuously as
More informationInternational Thorium Energy Conference 2015 (ThEC15) BARC, Mumbai, India, October 12-15, 2015
International Thorium Energy Conference 2015 (ThEC15) BARC, Mumbai, India, October 12-15, 2015 Feasibility and Deployment Strategy of Water Cooled Thorium Breeder Reactors Naoyuki Takaki Department of
More informationThermal- and Fast-Spectrum Molten Salt Reactors for Actinide Burning and Fuel Production
Thermal- and Fast-Spectrum Molten Salt Reactors for Actinide Burning and Fuel Production Charles W. Forsberg Oak Ridge National Laboratory * P.O. Box 2008; Oak Ridge, TN 37831-6165 Tel: (865) 574-6783;
More informationThe European nuclear industry and research approach for innovation in nuclear energy. Dominique Hittner Framatome-ANP EPS, Paris, 3/10/2003
The European nuclear industry and research approach for innovation in nuclear energy Dominique Hittner Framatome-ANP EPS, Paris, 3/10/2003 Contents The EPS and MIT approach The approach of the European
More informationThe US Fast Breeder Reactor Development Programme
The US Fast Breeder Reactor Development Programme U.S. CIVILIAN REACTOR DEVELOPMENT STRATEGY* The world energy problem has spared few nations from its effects. While there are many common aspects of the
More informationAdvancing Prosperity. Checking Global Warming. Japan US China International Forum on Molten Salt Reactors. June 14, 2018 Tokyo Robert Hargraves
Advancing Prosperity Checking Global Warming Japan US China International Forum on Molten Salt Reactors June 14, 2018 Tokyo Robert Hargraves 1 A single 1 GW electric power plant enables $32 billion of
More informationStatus of Advanced Reactor Development and Deployment. Global Nexus Initiative Workshop
Status of Advanced Reactor Development and Deployment Global Nexus Initiative Workshop Gary T. Mays, Group Leader Advanced Reactor Systems & Safety Reactor and Nuclear Systems Division February 23, 2016
More informationX-energy and the Xe-100
X-energy and the Xe-100 N I C/ETEC Nuclear Supplier Workshop Dr. Pete Pa ppano, Vice President Fuel Production September 7, 2017 Reimagining Nuclear Energy X-energy is reimagining nuclear s role in solving
More informationThorium in de Gesmolten Zout Reactor
Thorium in de Gesmolten Zout Reactor 30-1-2015 Jan Leen Kloosterman TU-Delft Delft University of Technology Challenge the future Reactor Institute Delft Research on Energy and Health with Radiation 2 1
More informationPotential of Small Modular Reactors
Potential of Small Modular Reactors Energiforsk 2017 January 2017 Dr Fiona Rayment Director Fuel Cycle Solutions UK Experience of Different Reactor Systems Sodium-cooled fast reactors Gas-cooled reactors
More informationThe Longer-Term Option: The Advanced High-Temperature Reactor
The Longer-Term Option: The Advanced High-Temperature Reactor Charles Forsberg Oak Ridge National Laboratory* P.O. Box 2008 Oak Ridge, TN 37831-6165 Tel: (865) 574-6783 Fax: (865) 574-0382 E-mail: forsbergcw@ornl.gov
More informationThe Do-able Molten Salt Reactor a time for courageous impatience
The Do-able Molten Salt Reactor a time for courageous impatience Preliminary Draft for Discussion Only Jack Devanney Center for Tankship Excellence, USA, djw1@c4tx.org 1 History After World War II, there
More informationThe potential of the molten salt reactor for warship propulsion
The potential of the molten salt reactor for warship propulsion Sir Robert Hill KBE FREng HonFIMarEST Professor C G Hodge FREng FIMarEST T Gibbs MEng AMRINA BMT Defence Services Ltd, UK SYNOPSIS This paper
More informationONCE-THROUGH THORIUM FUEL CYCLE OPTIONS FOR THE ADVANCED PWR CORE
ONCE-THROUGH THORIUM FUEL CYCLE OPTIONS FOR THE ADVANCED PWR CORE Myung-Hyun Kim and Il-Tak Woo Department of Nuclear Engineering Kyung Hee University YoungIn, KyungGi-Do, 449-701, Korea mhkim@nms.kyunghee.ac.kr;
More informationSMAHTR A CONCEPT FOR A SMALL, MODULAR ADVANCED HIGH TEMPERATURE REACTOR
SMAHTR A CONCEPT FOR A SMALL, MODULAR ADVANCED HIGH TEMPERATURE REACTOR Sherrell R. Greene, David E. Holcomb, Jess C. Gehin, Juan J. Carbajo, Anselmo T. Cisneros 1, William R. Corwin, Dan Ilas, Dane F.
More informationJapan Revival Strategy by Thorium MSR
Japan Revival Strategy by Thorium MSR Takashi Kamei Ritsumeikan University, Kyoto, Japan HAE00675@nifty.com Thank you to all. We are facing lots of problems Transportation Power generation Global warming
More informationInstrumentation and Control Panel
Instrumentation and Control Panel Lead Pavel Tsvetkov Elvis Dominguez-Ontiveros David Holcomb Chris Poresky Raluca Scarlat Texas A&M University Oak Ridge National Laboratory Oak Ridge National Laboratory
More informationClimate Change and Energy Solutions. Frank H. Shu UCSD Academia Sinica 10 Sept 2010 University of Michigan Collaborators: M. J. Cai & F. T.
Climate Change and Energy Solutions Frank H. Shu UCSD Academia Sinica 10 Sept 2010 University of Michigan Collaborators: M. J. Cai & F. T. Luo Grand Challenge of Attributed to John Maynard Keynes: For
More informationAdvanced-High-Temperature-Reactor Spent-Fuel Characteristics and Repository Impacts
Advanced-High-Temperature-Reactor Spent-Fuel Characteristics and Repository Impacts Charles W. Forsberg Oak Ridge National Laboratory * P.O. Box 2008; Oak Ridge, Tennessee 37831-6165 Tel: (865) 574-6783;
More informationEM 2 : A Compact Gas-Cooled Fast Reactor for the 21 st Century. Climate Change and the Role of Nuclear Energy
EM 2 : A Compact Gas-Cooled Fast Reactor for the 21 st Century Presented at the Canon Institute for Global Studies Climate Change Symposium Climate Change and the Role of Nuclear Energy By Dr. Robert W.
More informationAn Overview of the Integral Molten Salt Reactor
1 Presentation to IAEA MSR Workshop 1 st Nov 2016 An Overview of the Integral Molten Salt Reactor 1 2 DISCLAIMER This presentation may contain forward-looking information as such term is defined under
More informationOverview and Status of SMRs Being Developed in the United States
Overview and Status of SMRs Being Developed in the United States Daniel Ingersoll Oak Ridge National Laboratory ingersolldt@ornl.gov October 10-14, 2011 INPRO Dialog Forum on Common User Considerations
More informationA Technology Roadmap for Generation IV Nuclear Energy Systems
A Technology Roadmap for Generation IV Nuclear Energy Systems Hussein Khalil Argonne National Laboratory Co-Chair, Roadmap Integration Team Workshop on R&D Needs for Current and Future Nuclear Systems
More informationTechnology options for long term nuclear power development. A. Kakodkar, Chairman, Atomic Energy Commission INDIA
Technology options for long term nuclear power development A. Kakodkar, Chairman, Atomic Energy Commission INDIA 1 Long term nuclear power development - The challenge of the numbers. A per capita electricity
More informationProgram on Technology Innovation: Technology Assessment of a Molten Salt Reactor Design
2015 TECHNICAL REPORT Program on Technology Innovation: Technology Assessment of a Molten Salt Reactor Design The Liquid-Fluoride Thorium Reactor (LFTR) Program on Technology Innovation: Technology Assessment
More informationMaterials and processes for energy: communicating current research and technological developments (A. Méndez-Vilas, Ed.)
Molten salt reactors M.K.M. Ho 1, G. H. Yeoh 1,2 and G. Braoudakis 1 1 Australian Nuclear Science and Technology Organisation, Lucas Heights, NSW 2234, Australia. 2 The University of New South Wales, School
More informationEconomic Evaluation of Electrical Power Generation Using Laser Inertial Fusion Energy (LIFE)
Economic Evaluation of Electrical Power Generation Using Laser Inertial Fusion Energy (LIFE) TM Anklam, Wayne Meier, Al Erlandson, Robin Miles, Aaron Simon Lawrence Livermore National Laboratory Submitted
More information