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