DOCSLIB.ORG

High Temperature Gas Cooled Reactor HTGR Training Materials

Total Page：16

File Type：pdf, Size：1020Kb

Download full-text PDF Read full-text
High Temperature Gas Cooled Reactor HTGR Training Materials High Temperature Gas-cooled Reactor Technology Training Curriculum Presented by Idaho National Laboratory July 16-17, 2019 High Temperature Gas-cooled Reactor Technology Training Curriculum Presented by Idaho National Laboratory July 16-17, 2019 Day 1 – Tuesday July 16, 2019 Time Topic Presenter 8:30 High Temperature Gas-cooled Reactor: Introduction Hans Gougar • Motivation and Applications for HTGRs • High Level HTGR Design and Safety Approach 8:50 High Temperature Gas-cooled Reactor: History Hans Gougar • Overview: U.S., World Experience (Experimental, Demo, or Commercial) • Evolution of HTGRs • Lessons Learned 9:30 Break 9:45 High Temperature Gas-cooled Reactor: Core Design Hans Gougar • General Attributes of Modular Prismatic and Pebble Bed HTGRs o Physics o Neutronics o Prismatic and Pebble Fuel o Thermal-Fluidics o Inherent Safety • Plant Systems and Power Conversion o Reactivity Control o Instrumentation and Control o Helium Conditioning o Power Conversion • Normal Operation and Power Maneuvers 11:30 Lunch 12:30 TRISO Fuel: Design, Manufacturing, and Performance Paul Demkowicz • Background and History • Fabrication and Quality Control • Irradiation Performance • Accident Performance • Fuel Performance Modeling 1:45 Modular High Temperature Gas-cooled Reactor: Safety Design Approach Jim Kinsey • HTGR Design Criteria • Inherent and Passive Safety • Prevention vs. Mitigation • Radionuclide Sources/Barriers • Residual Heat Removal • Reactivity Control • Reactor Building 1 | Page High Temperature Gas-cooled Reactor Technology Training Curriculum Presented by Idaho National Laboratory July 16-17, 2019 Day 1 – Tuesday July 16, 2019 Time Topic Presenter 2:45 Break 3:00 Modular High Temperature Gas-cooled Reactor: Accident Analysis Hans Gougar • Types of Potential Accidents • Reactor Response • Safety Analysis Approach • Codes and Tools • Experimental Validation 4:00 Modular High Temperature Gas-cooled Reactor: Accident Analysis (continued) Jim Kinsey • Licensing Modernization Project • Use of PRA in LMP, ASME/ANS Non-LWR PRA Standard • Methods for Incorporating Passive System Reliability into a PRA 5:00 Adjourn Day 2 – Wednesday July 17, 2019 Time Topic Presenter 8:30 TRISO Fuel: Mechanistic Source Term Paul Demkowicz • Radionuclide Barriers • Radionuclide Design Criteria • Computational Tools • Source Term Estimation 9:30 Modular High Temperature Gas-cooled Reactor: Licensing Experience Jim Kinsey • Past US HTGRs Licensing Approach • Summary of NGNP Experience 10:00 Break 10:15 Modular High Temperature Gas-cooled Reactor: Licensing Experience (cont.) Jim Kinsey • NRC Regulatory Approach Assessment (Next Generation Nuclear Plant) 11:00 High Temperature Gas-cooled Reactor: Materials Richard Wright • Nuclear Graphite Components • Structural Alloys for HTGR and VHTR Systems • Component Design (Materials and Applications) 12:00 Lunch 1:00 Group Discussion and Review Hans Gougar 2:15 Overview and Concluding Remarks Hans Gougar 2 | Page Acronym List AC alternating current AF attenuation factors AGR Advanced Gas Reactor AHTR Advanced High-Temperature Reactor ALARA low as reasonably achievable ANL Argonne National Laboratory ANS American Nuclear Society AOO anticipated operational occurrences ART Advanced Reactor Technologies ASTM American Society for Testing and Materials AVR Arbeitsgemeinschaft Versuchsreaktor BDB beyond design basis BDBE beyond design basis events BWXT BWX Technologies, Inc. CDF core damage frequency CFD computational fluid dynamics Ci curries CO carbon monoxide CR control rod CRP Coordinated Research Program CTE coefficient of thermal expansion D&D decontamination and decommissioning DBA design basis accident DBE design basis events DID defense in depth DLOFC depressurized loss of forced cooling DOE Department of Energy EAB exclusion area boundary ECCS eliminating emergency core cooling system EPA Environmental Protection Act EPRI Electric Power Research Institute EU European Union F-C frequency-consequence FFC fuel and fuel cycle FGMS Fission Gas Monitoring System FHM Fuel Handling Machine FIMA fissions per initial metal atom FP fission product FSV Fort St. Vrain GA General Atomics GE General Electric GFR Gas-cooled Fast Reactor GIF Generation IV International Forum GTAW gas-tungsten arc welding HFIR High Flux Isotope Reactor HFR High Flux Reactor HMC heavy metal contamination HPB helium pressure boundary HPS Helium pressure systems HT&SS Helium Transfer and Storage System HTGR high-temperature gas-cooled reactors HTR-PM high-temperature gas-cooled reactor – Pebble Bed Module HTS heat transport system HTTF High Temperature Test Facility HTTR High Temperature Engineering Test Reactor IAEA International Atomic Energy Agency IHX intermediate heat exchanger IMGA Irradiated Microsphere Gamma Analyzer IPD Integrated Decision Panel IPyC inner pyrolytic carbon ISO International Organization for Standardization IVV-2M Russian reactor in Zarechny Russia LBE licensing basis event LERF large early release fraction LMP Licensing Modernization Project LWR light water reactor mHTGR modular high temperature gas-cooled reactor MHTGR modular high temperature gas-cooled reactor (Specific to General Atomics Design) MTR materials test reactors NDE nondestructive examination NEI Nuclear Energy Institute NEUP Nuclear Energy University Program NGNP Next Generation Nuclear Plant NPR new productive reactor NRC Nuclear Regulatory Commission NSRST non-safety-related with special treatment NST no special treatment NSTF natural circulation shutdown heat removal facility NUREG nuclear regulatory guide OPyC outer pyrolytic carbon ORIGEN OSU Oregon State University PAGs protective action guides PARFUME PARticle FUel ModEl PB1 Peach Bottom Unit 1 PBMR Pebble Bed Modular Reactor (Pty) Limited (Africa) PIRT Phenomena Identification and Ranking Tables PLOFC pressurized loss of forced cooling PRA probabilistic risk assessment PRISM power reactor inherently safe module PV pressure vessel QA quality assurance QAPD quality assurance program description QC quality control QHO qualitative health objective R&D research and development R/B release-rate-to-birth-rate RB reactor building RCCS reactor cavity cooling system RIDM risk-informed integrated decision-making RIPB risk-informed and performance based RIPB risk-informed, performance-based RN radionuclide RPV reactor pressure vessel SAFDL specified acceptable fuel design limit SARRDL system radionuclide release design limits SC-HTGR steam cycle high temperature gas-cooled reactor SCS shutdown cooling system SECY office of the secretary SG steam generator SiC standard industrial code SR safety-related SRCs Structural Reliability Classes SSC structures, systems, and components TECDOC IAEA technical document TEDE total effective dose equivalent TRISO tristructural isotropic UK United Kingdom VHTR very high-temperature reactor VHTRC very high-temperature reactor critical High Temperature Gas-cooled Reactor: Introduction Hans Gougar High Temperature Gas-cooled Reactor: Introduction Advanced Reactor Technologies Idaho National Laboratory Hans Gougar, PhD Nuclear Engineer NRC HTGR Training July 16-17, 2019 Modular High Temperature Gas-cooled Reactors • Inherently safe core cannot melt • High outlet temperature for more efficient electricity production and process heat • Minimal radiological or dynamic coupling between the reactor and the collocated process heat application • Environmentally benign, reliable, mature (for a non-LWR) 2 Electricity Fraction of Industrial Energy Use BTU) 15 Quad (10 3 Some Process Heat Applications suitable for Nuclear Baseload Electricity Electricity & Process Heat HTRs (HTGR, MSR, GFR) VHTR Electricity & Actinide Management SFRs 4 Potential Markets for Modular HTGR Steam Business Subsector Target Industry Required heat input Number of (MWt) between 150 MWt 300oC and 850oC HTGRs Required Petroleum and Coal Products Refineries 13456 399 Primary Metal Iron and Steel mills 3225 226 Manufacturing Chemical Manufacturing Basic Chemical 12714 85 Manufacturing (Methanol) Ethyl Alcohol 3448 23 Plastics Material and 8780 60 Resin Alkalies and Chlorine 545 4 Fertilizer (Ammonia) 2448 16 Food Manufacturing Wet Corn Milling 2239 15 Mining (exc. oil & gas) Potash, Soda, Borate 3318 22 McMillan, C. et al, “Generation and Use of Thermal Energy in the U.S. Industrial Sector and Opportunities to Reduce its Carbon Emissions”, NREL/TP-6A50-66763, INL/EXT-16-39680 5 Cost of Energy – HTGR vs. Natural Gas *High Temperature Gas-Cooled Reactor Projected Markets and Preliminary Economics, INL/EXT-10-19037 rev. 1, Aug. 2011. HTR and CCGT NG Electricity Production Price vs. HTR and CCNG Steam Production Price vs. Price of Price of Natural Gas with and w/o carbon tax Natural Gas with and w/o carbon tax 35 160 CCGT $50/MTCO2 Cost 30 $2.71 on 2/12 CCGT, $50/MT 140 CO2 Emissions Cost 25 120 $/1000 lb ~$4/MMBtu 20 HTGR ~$4/MMBtu 100 HTGR 15 $/MWhe ~$8.5/MMBtu ~$7/MMBtu 80 CCGT 10 No CO Cost 2 CCGT, No CO2 60 Emissions Cost 5 40 0 0 2 4 6 8 10 12 14 16 0 2 4 6 8 10 12 14 16 NG price $/MM Btu NG price $/MM Btu 6 Relatively Mature Technology Proof of Performance Engineering Reactors …but the fuels,fuels, materials,materials, and methods mmustust be qualiqualifiedfied forfor today’stoday’s market and rregulatoryegulatory environment 7 Current Industrial Interest in TRISO-fueled power Larger (200-625MWt) Plants for the Grid and Heat Users Microreactors (5-50 MWt) Units for Off-grid, Military Power 8 High Level Safety Design Objectives • Meet regulatory dose limits at the Exclusion Area Boundary (EAB) 25 rem Total
Load more

Recommended publications
  • Framatome in Latin America Strong History and Partnerships
    SEN – Semana da Engenharia Nuclear UFRJ 17/10/2019 Framatome– 2019 1 © Framatome All right reserved Framatome– 2019 2 © Framatome All right reserved Framatome at a glance 60 years of experience, alongside our customers, in developing safe and competitive nuclear power worldwide Design Supply Manufacture Integrate Maintain Framatome– 2019 3 © Framatome All right reserved Framatome at a glance High-performing people and technologies for safe and competitive nuclear plants worldwide 92 14 000 250 3.3 NPPs PEOPLE REACTORS € BILLION As OEM Servicing … All over the world 2017 turnover Framatome– 2019 4 © Framatome All right reserved Our values More than principles, our values guide our actions and describe how we work each other, with our customers and business partners Safety Future Performance Integrity Passion Framatome– 2019 5 © Framatome All right reserved Framatome worldwide presence Germany 4 sites France 17 sites USA 7 sites China 8 sites 58 locations Argentina Japan Sweden 21 Belgium Republic of South Switzerland countries Others Brazil Africa The Netherlands locations Bulgaria Russia Ukraine Canada Slovakia United Arab Emirates Framatome– 2019 Czech Republic Slovenia United Kingdom 6 Finland South Korea © Framatome Hungary Spain All right reserved Our customers Asia CNNC Nawah CGN Tepco North & South America Doosan Hitachi Bruce Power Exelon OPG KHNP Dominion Corporation PSEG Africa MHI Duke Energy Luminant TVA Entergy NA-SA Eskom ETN NextEra Europe ANAV EDF Energy Skoda CNAT Engie TVO CEA EPZ Vattenfall CEZ Iberdrola DCNS KKG EnBW NEK Framatome– 2019 7 EDF RWE © Framatome All right reserved Framatome shareholder structure 19,5% 75,5% 5% • Stock-listed company • Majority shareholder: French state 100% Framatome Inc.
    [Show full text]
  • RIL AMT Workshop Summary
    RIL 2021-03 NRC WORKSHOP ON ADVANCED MANUFACTURING TECHNOLOGIES FOR NUCLEAR APPLICATIONS Part I – Workshop Summary Date Published: Draft April 2021 Prepared by: A. Schneider M. Hiser M. Audrain A. Hull Research Information Letter Office of Nuclear Regulatory Research Disclaimer This report was prepared as an account of work sponsored by an agency of the U.S. Government. Neither the U.S. Government nor any agency thereof, nor any employee, makes any warranty, expressed or implied, or assumes any legal liability or responsibility for any third party’s use, or the results of such use, of any information, apparatus, product, or process disclosed in this publication, or represents that its use by such third party complies with applicable law. This report does not contain or imply legally binding requirements. Nor does this report establish or modify any regulatory guidance or positions of the U.S. Nuclear Regulatory Commission and is not binding on the Commission. EXECUTIVE SUMMARY Advanced manufacturing technologies (AMTs) are defined by the U.S. Nuclear Regulatory Commission (NRC) as those techniques and material processing methods that have not been traditionally used or formally standardized/codified by the nuclear industry. In June 2020, the NRC released Revision 1 to the Agency Action Plan for AMTs (AMT AP) (Agencywide Documents Access and Management System Accession No. ML19333B980 (package)). The AMT AP is a strategic plan that responds to the rapid pace of developments in respective AMTs and industry implementation plans. The NRC’s AMT activities are driven by industry interest in implementing specific AMTs and ensuring that the NRC staff are prepared to review potential AMT applications efficiently and effectively.
    [Show full text]
  • ITER Project Garching for the Fusion Community an Historic Milestone Was Achieved at the Eighth ITER Negotiations Meeting on February 18-19, 2003 in St
    newsletternewsletter Vol 2003 / 2 April 5, 2003 EUROPEAN FUSION DEVELOPEMENT AGREEMENT News Issued by the EFDA Close Support Unit China and the US as New Partners in the ITER Project Garching For the fusion community an historic milestone was achieved at the Eighth ITER Negotiations Meeting on February 18-19, 2003 in St. Petersburg (Russian Federation), when delega- tions from the People’s Republic of China and the United States of America joined those from Canada, the European Union, Japan and the Russian Federation in their efforts to reach agreement on the implementation of the ITER pro- ject. The Head of the Chinese Delegation indicated that Contents China, as the largest developing country in the world, has a great need to pursue alternative energy sources. China . Interview: believes that ITER can potentially lead to new forms of ener- Dr. Joseph V. Minervini gy and contribute to the peaceful and sustainable development page 2 of the world in the long-term. China expressed its strong wishes to be a valuable member of the ITER family, to make joint efforts with . Interview: other partners to the successful exploitation of fusion energy. Prof. Huo Yuping At their St. Petersburg meeting the ITER Negotiators approved the Report on the page 3 Joint Assessment of Specific Sites (JASS). The JASS Report provided as a main con- clusion and despite the differences between the candidate sites (Clarington in Canada, . ITER: Cadarache in France, Vandellos in Spain and Rokkasho-mura in Japan) that the JASS First Full Scale Primary assessment ascertained that all four sites are sound and fully capable to respond to all First Wall Panel ITER Site Requirements and Design Assumptions, as approved by the ITER Council in its January 2000 meeting.
    [Show full text]
  • A Comparison of Advanced Nuclear Technologies
    A COMPARISON OF ADVANCED NUCLEAR TECHNOLOGIES Andrew C. Kadak, Ph.D MARCH 2017 B | CHAPTER NAME ABOUT THE CENTER ON GLOBAL ENERGY POLICY The Center on Global Energy Policy provides independent, balanced, data-driven analysis to help policymakers navigate the complex world of energy. We approach energy as an economic, security, and environmental concern. And we draw on the resources of a world-class institution, faculty with real-world experience, and a location in the world’s finance and media capital. Visit us at energypolicy.columbia.edu facebook.com/ColumbiaUEnergy twitter.com/ColumbiaUEnergy ABOUT THE SCHOOL OF INTERNATIONAL AND PUBLIC AFFAIRS SIPA’s mission is to empower people to serve the global public interest. Our goal is to foster economic growth, sustainable development, social progress, and democratic governance by educating public policy professionals, producing policy-related research, and conveying the results to the world. Based in New York City, with a student body that is 50 percent international and educational partners in cities around the world, SIPA is the most global of public policy schools. For more information, please visit www.sipa.columbia.edu A COMPARISON OF ADVANCED NUCLEAR TECHNOLOGIES Andrew C. Kadak, Ph.D* MARCH 2017 *Andrew C. Kadak is the former president of Yankee Atomic Electric Company and professor of the practice at the Massachusetts Institute of Technology. He continues to consult on nuclear operations, advanced nuclear power plants, and policy and regulatory matters in the United States. He also serves on senior nuclear safety oversight boards in China. He is a graduate of MIT from the Nuclear Science and Engineering Department.
    [Show full text]
  • Olkiluoto 3: Framatome Teams All Set for Fuel Loading
    PRESS RELEASE March 26, 2021 Olkiluoto 3: Framatome teams all set for fuel loading March 26, 2021 – The Olkiluoto 3 EPR reactor completes a decisive stage of its commissioning. The Finnish safety authority (STUK) has authorized the fuel load for the Olkiluoto 3 EPR reactor. Loading operations led by plant operator TVO, with the support from AREVA and Framatome, can begin. "Fuel loading is a major milestone for the project. Reaching this milestone illustrates the expertise and know-how of our teams," said Bernard Fontana, CEO of Framatome. "Framatome's teams are fully mobilized alongside AREVA and TVO to finalize and deliver the nuclear power plant while meeting the highest safety and security standards. I thank them for their engagement.” To carry out the loading operations, an integrated team made up of approximately 40 employees from TVO, AREVA and Framatome has been formed. It includes around 15 fuel handlers, employees specializing in the fuel handling operations, and four neutronics engineers in charge of monitoring the core during loading. A total of 241 fuel assemblies manufactured in Framatome's plants in Germany and in France will be loaded in the reactor vessel to constitute the first core. The Areva NP and Areva NP GmbH Olkiluoto 3 project teams, who will later join Framatome, are supported by over 110 Framatome employees permanently based on the site, and by Framatome engineering teams located in France and in Germany. Completion of the fuel loading will be followed by a new series of hot functional tests before the first criticality and commissioning for commercial operation.
    [Show full text]
  • Specials Steels and Superalloys for Nuclear Industry
    Specials Steels and Superalloys for Nuclear Industry Enhancing your performance or almost 60 years Aubert & Duval has been a key partner for the development Aubert & Duval: Your partner F of forged and rolled products, especially those customized for the nuclear market. to energize your success With full vertical integration from melting, to remelting, hot converting and machining (rough machining through to near-net-shape parts), Aubert & Duval offers wide-ranging cutting edge capabilities for nuclear application. Equipment Process flow . MELTING Melting furnaces (EAF, AOD, LF) Melting up to 60 tons Vacuum Induction Melting (VIM) HPS NiSA up to 20 tons Remelting furnaces (ESR, VAR) up to 30 tons powder atomization (Gaz, VIM) . FORGING Open-die forging presses Remelting Powder atomization from 1,500 to 10,000 tons Closed-die forging presses from 4,500 to 65,000 tons . ROLLING MILL HPS 7-200 mm diameter bars High Performance Steels: Conversion . HEAT TREATMENT A range of alloyed steels with Solution and ageing furnaces tightly controlled characteristics HPS Ti NiSA AL PM Horizontal and vertical quenching offering optimum value for equipment customers. TESTING Forging Closed-die Hot Isostatic Immersion UT up to 13 tons and/or rolling Forging Forging Pressing (HIP) ©Valinox-Franck Dunouau (28,000 lbs) Automated contact UT up to 20 tons NiSA Aubert & Duval has also put in place over many decades dedicated skills to co-design re-engineered Nickel-base Superalloys: Nickel-based superalloys: materials metallurgical solutions with our clients. keeping high surface integrity while Sales of alloys and superalloys have progressively expanded across a broad spectrum of primary withstanding severe mechanical circuit contractors and their subcontractors.
    [Show full text]
  • Press Kit Inauguration of the Conversion Orano Tricastin BP 16 26 701 Pierrelatte Plant 10 September 2018
    Press kit Inauguration of the conversion Orano Tricastin BP 16 26 701 Pierrelatte plant 10 September 2018 Contacts Presse Nathalie Bonnefoy +33 (0)6 23 17 24 24 [email protected] Gilles Crest +33 (0)6 71 08 11 54 [email protected] www.orano.group Oranogroup EDITORIAL The plant we are opening today is a major industrial investment for Orano, for the French nuclear industry and for the industry of our country. ith the Georges Besse II enrichment plant on the same site, it is probably the largest industrial investment made in France in recent years. The Comurhex W II project was launched to give France an industrial facility offering cutting- edge safety, security, and environmental and industrial performance. A facility that gives us a global competitive advantage and guarantees an uninterrupted electricity supply for our markets. A tool integrating technological innovations in terms of safety, environment, and improvement of industrial performance: recycling of chemical reagents, reduction by 90% of water consumption, automated control-command system to improve the process control. It is an exceptional project that has required the best of our expertise from the teams of Orano Chemistry and Enrichment as well as Orano Projets, and throughout our group alongside our industrial partners. The project successfully completed at the same time as our group was reinventing itself to create a new flagship technology business to give nuclear materials all their value. While an important debate is taking place on France's multi-year energy program, the investment we have made in the Tricastin site and its plants shows the confidence we have in the future of nuclear energy.
    [Show full text]
  • The Jules Horowitz Reactor Core and Cooling System Design
    The Jules Horowitz Reactor core and cooling system design M. Boyard*, JM. Cherel**, C. Pascal*, B. Guigon*** * AREVA-Technicatome, 1100 rue Jean René Guillibert Gautier de la Lauzière 13100 Aix en Provence, FRANCE ** AREVA-Framatome-ANP, 9-10 rue Juliette Récamier 69006 Lyon, FRANCE *** Commissariat à l’Energie Atomique, 13108 Saint-Paul-lez-Durance cedex, FRANCE ABSTRACT The CEA (Commissariat à l’Energie Atomique) is planning to build a new MTR called the Jules Horowitz Reactor (JHR). JHR at Cadarache will become by 2014 and for decades a major research infrastructure in Europe for supporting existing power plants operation and lifetime extension as well as future reactor developments [1]. AREVA (Technicatome and Framatome- ANP) and EDF are performing the design studies. The JHR will be a tank pool type reactor using light water as coolant and moderator. The reactor has been designed to provide a neutron flux strong enough to carry out irradiation relevant for generations 2, 3 and 4 power plants: flexibility and adaptability, high neutron flux, instrumented experiments, loops to reproduce environments representatives of the different power plant technologies . Updated safety requirements and LEU fuel elements have been taken into account in the design of this high flux reactor. This paper presents the guidelines for the design of the main items, the various options considered and the choices made at the end of the detailed studies phase regarding: − Core shape, − Fuel element and core pitch, − Reflector and core-reflector interface, − Normal and emergency cooling systems, − Reactivity control system. MAIN OBJECTIVES OF THE REACTOR The “Jules Horowitz Reactor” (JHR) will be a structuring infrastructure of the European research area.
    [Show full text]
  • Operational and Decommissioning Experience with Fast Reactors
    IAEA-TECDOC-1405 Operational and decommissioning experience with fast reactors Proceedings of a technical meeting held in Cadarache, France, 11–15 March 2002 August 2004 IAEA-TECDOC-1405 Operational and decommissioning experience with fast reactors Proceedings of a technical meeting held in Cadarache, France, 11–15 March 2002 August 2004 The originating Section of this publication in the IAEA was: Nuclear Power Technology Development Section International Atomic Energy Agency Wagramer Strasse 5 P.O. Box 100 A-1400 Vienna, Austria OPERATIONAL AND DECOMMISSIONING EXPERIENCE WITH FAST REACTORS IAEA, VIENNA, 2004 IAEA-TECDOC-1405 ISBN 92–0–107804–8 ISSN 1011–4289 © IAEA, 2004 Printed by the IAEA in Austria August 2004 FOREWORD The fast reactor, which can generate electricity and breed additional fissile material for future fuel stocks, is a resource that will be needed when economic uranium supplies for the advanced water cooled reactors or other thermal-spectrum options diminish. Further, the fast-fission fuel cycle in which material is recycled offers the flexibility needed to contribute decisively towards solving the problem of growing ‘spent’ fuel inventories by greatly reducing the volume of high level waste that must be disposed of in long term repositories. This is a waste management option that also should be retained for future generations. The fast reactor has been the subject of research and development programmes in a number of countries for more than 50 years. Now, despite early sharing and innovative worldwide research and development, ongoing work is confined to China, France, India, Japan, the Republic of Korea, and the Russian Federation. Information generated worldwide will be needed in the future.
    [Show full text]
  • High Temperature Gas-Cooled Reactor: History
    High Temperature Gas-cooled Reactor: History Advanced Reactor Technologies Idaho National Laboratory Hans Gougar, PhD Nuclear Engineer NRC HTGR Training July 16-17, 2019 Overview • Early and related concepts • First Generation US and German plants • Modular High Temperature Gas-cooled Reactors (mHTGR*) * In these presentations, MHTGR refers to a specific design developed by General Atomics Visitor Entrance to THTR300 (European Institute for Climate and Energy website) The Training Course delivered to the NRC in 2010 was spread over a few more days and was prepared and delivered by experienced vendors (see Suggested Reading List). You are encouraged to review that course material for specific design details and the view from a vendor perspective. 2 Timeline of HTGR Development Proof of Commercial Modular Market Principle Demonstration Evolution Penetration (?) 14 Natural Gas price in US 12 HTR can compete here HTR- HTGR Projected Markets and Modul 10 Preliminary Economics, Peach NGNP 0 8 $ INL/EXT-10-19037, 8/201 Bottom-1 MHTGR /NPR HTR-PM? 6 AVR HTTR/HTR-10 DRAGON 4 2 Fort St. Vrain THTR 3 Related Concepts • British Advanced Gas-cooled Reactor (AGR) § CO2-cooled, 600°C outlet § UO2 rods in SSTL clad • Very High Temperature Reactor (VHTR) § Really hot HTGR (>850-1000°C) • Advanced High-Temperature Reactor (AHTR) or PB-FHR (Kairos) § Molten salt instead of He General Atomics EM2 GFR concept • Gas-cooled Fast Reactor (GFR) § Fast spectrum (no graphite) § UC fuel Torness AGR (Scotland) 4 Prologue – Graphite-moderated, Gas-cooled Reactors (US/UK/France) • CP-1 (air-cooled) • CO2 cooled § MAGNOX (UK), UNGG(Fr) • Production/Power Reactors § AGR (UO2 pellets in SS, <650°C CO2, concrete RPV, reasonable performance after a rocky start) Torness Calder Hall (2015) Chicago Pile 1 (1942) 5 HTR Conceived • Daniels Power Pile (1945) § F.
    [Show full text]
  • Quest Magazine Summer 2016
    Summer 2016 uest RESEARCH NEWS FROM PPPL HERE COMES THE SUN U.S. DEPARTMENT OF ENERGY Summer 2016 From the new University Vice President for PPPL am honored to succeed A.J. Stewart Smith as Princeton University’s vice president for I PPPL, and am very excited to help oversee the nation’s leading center for the exploration of plasma science and magnetic fusion energy. My own background is in space plasma physics and in the engineering of space instrumentation. I have worked in these areas for the past 35 years, both at Southwest Research Institute in San Antonio, Texas, a nonprot organization that specializes in the creation and transfer of technology in engineering and the physical sciences, and at Los Alamos National Laboratory, where I founded its Center for Space Science and Exploration. I serve as the University’s primary contact with the U.S. Department of Energy on David McComas matters related to PPPL. The Laboratory has entered a new and exciting era with the Princeton University completion of the National Spherical Torus Experiment-Upgrade and continuing advances Vice President for PPPL in plasma science. I really look forward to overseeing the Laboratory’s management and operation at this exciting time and in working to grow the PPPL program and to help develop the world-wide vision that will make fusion energy a reality in our lifetimes! From the Director of PPPL t is my pleasure to welcome readers to the fourth annual edition of Quest, the Laboratory’s Iresearch magazine. Research has begun full bore on the National Spherical Torus Experiment-Upgrade (NSTX-U), our agship fusion facility, whose construction was completed in 2015 after nearly four years of building and a cost of $94 million.
    [Show full text]
  • Operational Feedback Ventional Enriched FA
    Background › Starting in 2009, Framatome has been supplying Size- › Totally Framatome has delivered more than 1000 FAs to well B* with fuel assemblies (FAs) with Enriched Re- Sizewell B, approximately half of them containing ERU. processed Uranium (ERU). The enrichment process of the reprocessed uranium is completed in Russia with an objective of minimizing even › Reprocessed uranium is understood as a secondary uranium isotopes such as 232U and 236U. The even isoto- uranium supply pes do not contribute to fi ssion; they are considered – by direct enrichment services to be an absorber and therefore, their presence needs to be minimized, which improves overall fuel utilization. – by blending with other feed material of a higher The low residual fraction of these parasitic isotopes is enrichment compensated by having slightly higher enrichment of 235U – by a combination of both to achieve equivalent reactivity to conventional enriched Enriched uranium.1,2 Reprocessed Uranium Neutronic Design › T he neutronic design of ERU FAs is designed for having the same reactivity characteristic as the equivalent con- Operational Feedback ventional enriched FA. This is achieved by the compen- sation of the 236U and other isotopes content through higher 235U enrichment (see fi g. 1 and 2). › Figure 2 shows the kinf versus the FA burn up of up to 80 MWd/kgU. Since the kinf values are very similar for ENU (enriched natural uranium) and ERU (enriched re- Fig. 2 Fig. 1 k comparison of ENU and ERU fuel versus processed uranium) fuel, the delta is shown as well in inf 235U compensation burn up – for neutronic FA design, upper the lower section.
    [Show full text]