OVERVIEW OF FHR TECHNOLOGY. Per F. Peterson University of California, Berkeley April 27, 2017
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1 OVERVIEW OF FHR TECHNOLOGY Per F. Peterson University of California, Berkeley April 27, 2017
2 Meet the presenter Per F. Peterson holds the William and Jean McCallum Floyd Chair in the Department of Nuclear Engineering at the University of California, Berkeley. He performs research related to hightemperature fission energy systems, as well as studying topics related to the safety and security of nuclear materials and waste management. He participated in the development of the Generation IV Roadmap in 2002 as a member of the Evaluation Methodology Group, and co-chairs its Proliferation Resistance and Physical Protection Working Group. His research in the 1990's contributed to the development of the passive safety systems used in the GE ESBWR and Westinghouse AP-1000 reactor designs. Currently his research group focuses on heat transfer, fluid mechanics, and regulation and licensing for advanced reactors, including fluoride-salt cooled, high temperature reactors (FHRs). peterson@nuc.berkeley.edu 2
3 Fluoride salt cooled high-temperature reactors (FHRs) combine three earlier technologies Nickel-based structural materials Coated particle fuel LMR FHR Liquid fluoride salt coolants
4 The idea of a fluoride-salt cooled, high temperature reactor dates to 2002
5 FHRs leverage experience and technology from multiple sources Passive Advanced Light Water Reactors Established licensing methodology for passive safety Integral Effects Test (IET) experiments, CSAU/PIRT Sodium Fast Reactors Design and structural materials for low pressure, high temperature Inert cover gas systems; thermal insulation and control, DRACS/RVACS High Temperature Gas Reactors TRISO fuel / functional containment Graphite and ceramic-fiber composite structural materials Molten Salt Reactors Fluoride salt chemistry control and thermophysical properties Natural Gas Combined Cycle Plants (some types of FHRs) Current dominant technology for new U.S. power conversion; adaptable to FHRs
6 FHRs have unique safety characteristics for accidents resulting in long-term off-site land use restrictions from Cs-137 FHRs LWRs Low Cs-137 inventory ~30 g/mwe ~105 g/mwe High thermal margin to fuel damage T damage > 1800 C T damage ~ C High solubility of cesium in coolant Intrinsic low pressure CsF has high solubility High coolant boiling temperature and chemical stability Cs forms volatile compounds High vapor pressure at accident temperatures
7 Expert Workshops and White Papers R&D has developed an improved foundation for understanding FHRs MWt PB-AHTR MWt SmAHTR UCB CIET NGNP AGR MWt ORNL AHTR MWt Mk1 PB-FHR UW/MIT flibe corrosion/irradiation Experiments and Simulation UCB PREX Multiple FHR Conceptual Design Studies 4 th FHR Workshop, MIT, Oct. 2012
8 Studies for FHR fuels and materials are encouraging INL testing of NGNP TRISO fuel shows excellent fission product retention up to 1800 C UW static corrosion tests show low corrosion rates for 316 SS and Alloy N in flibe at 700 C (1000 hr) 316SS in graphite, #2 316SS in 316SS liner, #2 Triso_fuel_triumphs_at_extreme_temperatures html 316SS in 316SS liner, #1 316SS in graphite, #1
9 USDOE-Funded Integrated Research Projects have advanced the understanding of FHR technology
10 UC Berkeley FHR research focuses on thermal hydraulics, neutronics, safety and licensing MWt Mk1 PB-FHR CIET PB-HTX Conceptual Design Studies SINAP TMSR- SF1 Coupled neutronics and thermal hydraulics Separate and integral effect tests 4 th FHR Workshop, MIT, Oct X-PREX Pebble Bed Tomography Organize Expert Workshops and White Papers
11 University of Wisconsin - Production, Purification, and Reduction of flibe (Li 2 BeF 4 ) As-received BeF 2 As-received LiF Melted FLiBe Salt
12 Flow direction UW Natural Circulation Molten flibe Salt Flow Loop Enable Measuring Corrosion Under a Wider Set of Conditions Sample insert valves Flow-loop schematic and sample holder CFD predictions of temperature profiles at the bottom, middle, and top of the heated riser IR image during heater testing - inside of the loop is at 700 o C Thermal hydraulics Flow velocities Temperature profiles Beryllium transport rates Characteristics of the natural circulation Heat transfer characteristics Mass Transport Beryllium redox agent transport throughout system Corrosion products transport Corrosion Stainless Steel, SiC/SiC, Alloy 800H etc. Flow-assisted corrosion Dissolution in hot leg and plating on cold leg
13 In-Reactor Materials Testing for FHRs 3 rd FHR Irradiation in MITR (Fall 2016) 1000 hours at 700 C in enriched flibe Graphite and C/C specimens (previously irradiated SiC, 316SS, Hastelloy-N, TRISO)
14 Separate Effects Test (SET) and Integral Effects Test (IET) for FHRs, using simulant fluids
15 The similitude of convective heat transfer in oil and molten salts was discovered in 2005 By appropriate selection of length, velocity, average temperature, and temperature difference scales, it is possible to simultaneously match Reynolds, Froude, Prandtl, and Grashof numbers. Mechanical pumping power and heat input reduced to 1 to 2% of prototype power inputs. Steady state and transient heat transfer to steel and graphite structures can be reproduced using Pyrex and high-thermalconductivity epoxies, respectively New experiments to verify similitude for key FHR/MSR phenomena will be valuable
16 The UCB Compact Integral Effects Test (CIET) facility scaling matches the Mk1 reactor design UC Berkeley CIET (50% Height) Mk1 PB-FHR (100% Height) DRACS Head Tank DRACS Loop Primary Head Tank TCHX (Thermosyphon Cooled Heat Exchanger) CTAH/IHX (Coiled Tube Air Heater or Intermediate Heat Exchanger) DHX (DRACS Heat Exchanger) Core bypass DHX flow diode Primary Pump Heater/Core CIET/Mk1 heat sources and sinks
17 CIET can validate FHR transient models Pipe Thermal insulation 35a 34 Flow mixer Heat Flux to solid Thermal isolation NDHX Flow meter Heat transfer structure heat sink Heat transfer structure 35b Needle valve Expansion tank Juction Center line Height Manometer line 36 Thermalcouple CTAH a 7b DHX By-pass flow a CIET In Operation CIET Front View Heater b RELAP Nodalization for CIET/FHR simulation
18 X-PREX experiments have enabled 3-D tomography of pebble translation and rotation
19 Mk1 PB-FHR Reference Design Overview An example for FHR Design
20 Nominal Mk1 PB-FHR Design Parameters Annular pebble bed core with center reflector Core inlet/outlet temperatures 600 C/700 C Control elements in channels in center reflector Shutdown elements cruciform blades insert into pebble bed Reactor vessel 3.5-m OD, 12.0-m high Vessel power density 3 x higher than S-PRISM & PBMR Power level: 236 MWth, 100 MWe (base load), 242 MWe (peak w/ gas co-fire) Power conversion: GE 7FB gas turbine w/ 3-pressure HRSG Air heaters: Two 3.5-m OD, 10.0-m high CTAHs, direct heating Tritium control and recovery Recovery: Absorption in fuel and blanket pebbles Control: Kanthal coating on air side of CTAHs PB-FHR cross section
21 Mk1 PB-FHR flow schematic Air inlet Thermosyphoncooled heat exchangers (TCHX) DRACS heat exchangers (DHX) LEGEND Primary coolant Graphite Fuel pebbles Blanket pebbles Primary coolant flow Water flow Air flow Natural gas flow Direct reactor aux. cooling system loops (DRACS loops) De-fueling machines Control rods Hot well/ main salt pumps Feedwater Heat Recovery Steam Gen. Gas co-firing Turbines Unloading vent Coiled tube air heaters (CTAHs) Steam Filtered Air Compressor Generator Shutdown cooling blowers
22 Mk1 NACC physical arrangement Main exhaust stack Air intake filter Simple cycle vent stack Generator GE F7B compressor HP/LP turbines HP air ducts HP CTAH Hot well Reactor vessel DRACS Heat recovery steam generator Combustor Hot air bypass LP air ducts LP CTAH Main salt drain tanks
23 The Mk1 structures are designed for modular construction Underground common utilities tunnel Shield building DRACS chimney Personnel airlock Equipment hatch Fuel canister well Grade level Intake filter Main stack Simple cycle bypass stack Modified GE 7FB gas turbine HRSG Below-grade air duct vault Ventilation exhaust system
24 Mk1 Reactor Cross Section 3.50 m Defueling wells (2) Hot leg nozzle (1) Vessel outer lid Vessel inner lid Support skirt DHX wells (3) Shutdown blades (8) Control rods (8) Outer radial reflector Center radial reflector Graphite blanket pebbles Fuel pebbles Downcomer Lower reflector support
25 Modular Construction for Small Modular Reactors: Concepts for reduced construction costs for multimodule reactor sites
26 The Mk1 uses steel-plate composite modular construction Vogtle Unit 3 shield building wall panels, May 2014 Summer Unit 2 CA20 Transported from MAB CA20 being set in place by heavy crane
27 The Mk1 design uses 10 primary structural modules SB7a-g SB6 SB5 SB4 SB3 AD3 SB2 AD2 SB1 Base mat AD1
28 Mk1 Construction Story-Board (1) Construction occurs adjacent to an existing Mk1 module, outside a temporary protected area fence
29 Mk1 Construction Story-Board (2) Excavation for the new Mk1 module
30 Mk1 Construction Story-Board (3) Construction of the common tunnel section, for plant utilities
31 Mk1 Construction Story-Board (4) Construction lift tower
32 Mk1 Construction Story-Board (6) Pour base mat
33 Mk1 Construction Story-Board (7) Install first-level module of Mk1 shield building
34 Mk1 Construction Story-Board (8) Install second-level module of Mk1 shield building
35 Mk1 Construction Story-Board (9) Install first-level module of Mk1 air-duct vault
36 Mk1 Construction Story-Board (10) Install second-level module of Mk1 air-duct vault
37 Mk1 Construction Story-Board (11) Install third-level module of Mk1 air-duct vault
38 Mk1 Construction Story-Board (12) Install Mk1 reactor cavity module
39 Mk1 Construction Story-Board (13) Install Mk1 CTAH and I.O. pipes
40 Mk1 Construction Story-Board (14) Install third-level module of Mk1 shield building.
41 Mk1 Construction Story-Board (15) Back fill below-grade structures to grade level Excavation for the next unit may begin
42 Mk1 Construction Story-Board (16) Install main shield building cylinder.
43 Mk1 Construction Story-Board (17) Install polar crane.
44 Mk1 Construction Story-Board (18) Install shield building roof.
45 Mk1 Construction Story-Board (19) Install DRACS chimneys and ventilation filter and exhaust enclosures.
46 Mk1 Construction Story-Board (20) Install gas turbine, intake filter housing, generator and main transformer).
47 Mk1 Construction Story-Board (20) Install heat recover steam generator and stacks.
48 Mk1 Construction Story-Board (21) The crane and rails are removed.
49 Mk1 Construction Story-Board (22) Install new protected area fence, and remove temporary protected area fence.
50 Mk1 Construction Story-Board (23) Construction on next unit continues
51 Notional 12-unit Mk1 PB-FHR nuclear station 1200 MWe base load; 2900 MWe peak ) Mk1 reactor unit (typ. 12) 2) Steam turbine bldg (typ. 3) 3) Switchyard 4) Natural gas master isolation 5) Module assembly area 6) Concrete batch plant 7) Cooling towers (typ. 3) ) Dry cask storage 9) Rad. waste bldg 10) Control room bldg 11) Fuel handling bldg 12) Backup generation bldg 13) Hot/cold machine shops 14) Protected area entrance 15) Main admin bldg 16) Warehouse 17) Training 18) Outage support bldg 19) Vehicle inspection station 20) Visitor parking For more info: fhr.nuc.berkeley.edu
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