Pre-Conceptual Hydrogen Production Modular Helium Reactor Designs. IAEA International Conference on Non-Electric Applications of Nuclear Energy

Transcription

1 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 Japan Atomic Energy Agency Oarai, Japan April 16-19, 2007 Matt Richards General Atomics, San Diego, CA, USA (JAEA Oarai Research Center) 大洗 2007 年 4 月日 Slide 1

2 MHR Design Features Are Well Suited for Significant Expansion of Nuclear Energy Passive Safety No active safety systems required No evacuation plans required Competitive Economics High Thermal Efficiency Siting Flexibility Lower waste heat rejection, reduced water cooling requirements High-Temperature Capability with Flexible Energy Outputs Electricity Hydrogen Synfuels, etc. Flexible Fuel Cycles LEU, HEU, Pu, TRU, Thorium Hot Gas Duct Control Rod Drive Assemblies Reactor Metallic Internals Replaceable Reflector Core Reactor Vessel Shutdown Cooling System 大洗 2007 年 4 月日 Slide 2

3 One Reactor Design Can Use Multiple Fuels for Multiple Applications Low-Enriched Uranium TRISO Common Reactor Core - Ultra Safe Design LWR Spent Fuel TRISO Electricity Heat Weapons Surplus Pu TRISO TRISO fuel in fuel blocks Thorium Utilization TRISO Hydrogen 大洗 2007 年 4 月日 Slide 3

4 The MHR is a Passively Safe Design Passive Safety Features Ceramic, coated-particle fuel Maintains integrity during loss-of-coolant accident Annular graphite core with high heat capacity Helps to limit temperature rise during loss-of-coolant accident Low power density Helps to maintain acceptable temperatures during normal operation and accidents Inert Helium Coolant Reduces circulating and plateout activity Passive Air- Cooled RCCS 大洗 2007 年 4 月日 Slide 4

5 Hydrogen Plant Will Not Impact Passive Safety Potential Licensing issue is colocation of MHR and Hydrogen Plant Passive safety of MHR allows co-location Earthen berm provides defense-in-depth Other reactors located in close proximity to hazardous chemical plants and transportation routes NRC allows risk-based approach INL recommends 60 to 100 m separation distance JAEA studies also support close separation distance 大洗 2007 年 4 月日 Slide 5

6 The GT-MHR Produces Electricity Economically with High Efficiency MHR coupled to a directcycle Brayton powerconversion system PCS MHR Control Rods 600 MW(t), 102 column, annular core, prismatic blocks 48% thermal efficiency with 850 C Outlet Temperature Generator Turbocompressor Recuperator Annular Core Installed capital costs of approximately $1000/kW(e) Busbar electricity generation costs of approximately 3.1 cents per kw(e)-h. Precooler Intercooler 大洗 2007 年 4 月日 Slide 6

7 H2-MHR Can Produce Hydrogen with High Efficiency MHR Coupled to Thermochemical Water Splitting (Sulfur-Iodine Process) MHR Coupled to High- Temperature Electrolysis 大洗 2007 年 4 月日 Slide 7

8 SI-Based H2-MHR Uses IHX to Interface MHR with Hydrogen Production System 590 C Electricity for Pumps/Compressors 565 C Hydrogen Production System H 2 O H 2 IHX Design Concept Using Heatric Modules Height ~30 m Diameter ~6 m MHR MW(t) IHX Residual Heat Removal System O 2 Waste Heat (120 C) 950 C 925 C Annual H 2 Production (4-module plant): 3.68 x 10 5 metric tons Hydrogen Production Efficiency: 45.0% (based on HHV of H 2 ) Product H 2 Pressure: 4 MPa 大洗 2007 年 4 月日 Slide 8

9 HTE-Based H2-MHR Generates Both Electricity and High- Temperature Steam to Drive Solid-Oxide Electrolyzer Modules Electricity 321 kg/s 590 C Power Conversion System Secondary He H 2 O Hydrogen Production System SOE Module Concept 4 MW(e) per Trailer MHR 600 MW(t) IHX, 59 MW(t) SG Waste Heat 42 kg/s 950 C (13%) Steam/H kg/s 827 C (87%) Product Hydrogen H 2 O H 2 /Steam Steam Sweep O 2 /Steam Annual H 2 Production (4-module plant): 2.68 x 10 5 metric tons Hydrogen Production Efficiency: 55.8% (based on HHV of H 2 ) Product H 2 Pressure: 4.95 MPa Power Recovery Toshiba developing tubular-cell concept as part of NGNP USIT Team. 大洗 2007 年 4 月日 Slide 9

10 N th -of-a-kind Hydrogen Production Costs are Approximately $2/kg for both SI-Based and HTE-Based Plants SI-Based Plant Total Hydrogen Production Cost = $1.97/kg HTE-Based Plant Total Hydrogen Production Cost = $1.92/kg MHR Plant Capital Charges (24.9%) SI Plant Capital Charges (18.6%) MHR Plant O&M Costs (5.2%) SI Plant O&M Costs (10.6%) Nuclear Fuel Costs (9.8%) Electricity Costs (30.9%) MHR Plant Capital Charges (34.8%) HTE Plant Capital Charges (28.3%) MHR Plant O&M Costs (7.3%) HTE Plant O&M Costs (15.8%) Nuclear Fuel Costs (13.8%) Electricity costs result mostly from pumping process fluids in the hydrogen plant (not from pumping helium). Efforts are being made to optimize the flow sheets to reduce pumping requirements. SOE module unit costs assumed to be $500/kW(e). If module unit costs are increased to $1000/kW(e), hydrogen production cost increased to $2.52/kg. 大洗 2007 年 4 月日 Slide 10

11 Nuclear Hydrogen Production Costs Compare Favorably with Steam-Methane Reforming 4.50 SMR - No CO2 Penalty 4.00 SMR - $30/mt CO2 Penalty Cost of Hydrogen ($/kg) SMR - $50/mt CO2 Penalty Nuclear Hydrogen, $1.97/kg Nuclear Hydrogen with $20/mt O2 Credit, $1.81/kg $9.72/MMBTU December 2005 Natural Gas Wellhead Price Price of Natural Gas ($/MMBtu) Economic comparisons are especially favorable if carbon dioxide penalties and oxygen credits are taken into account. 大洗 2007 年 4 月日 Slide 11

12 VHTR Can Provide a Wide Variety of Energy Outputs Coal Gasification Electricity Natural Gas Steam Process Heat Hydrogen 大洗 2007 年 4 月日 Slide 12

13 GT-MHRs and H2-MHRs Can Be Deployed with Advanced Fuel Cycles to Address Spent Fuel Management and Sustainability Issues MHRs can be used to process legacy LWR spent fuel U recycle LWR Spent Fuel UREX TRU Deep Burn using MHRs fully fueled with TRU Waste accumulation 75 kgtru /GWe-yr Pu-239 burnup > 95 % All-Actinides burnup > 60 % Np-237 and Precursors > 60 % Successful Deep-Burn Irradiation of Coated- Particle Pu-Fuel Pu Oxide (PuO 1.68 ) Fission Products Residual radioactivity is contained by ceramic coatings over geologic time scales 747,000 MW-days/tonne >95% 239 Pu Transmuted at Peach Bottom I 大洗 2007 年 4 月日 Slide 13

14 MHRs Can Be Deployed Using a Self-Cleaning Fuel Cycle to Relieve Repository Burdens TRISO FAB LEU (15-20%) E URANIUM Uranium UREX FP DB-TRISO FAB Pu, Transuranics Waste accumulation: 35 kgtru /GWe-yr 8 times less than present LWRs Sustainability: years in U.S. 大洗 2007 年 4 月日 Slide 14

15 FBR/VHTR System Deployment Provides Sustainability, Proliferation Resistance, and Energy Flexibility 13 Recycled Uranium Depleted Uranium SFR Core Fuel Manufacturing SFR Blanket Fuel Manufacturing 25 Loss 4 5 Loss SFR Core 6 Blanket 7 8 SFR Spent Fuel Storage 9 22 SFR Front End Reprocessing Loss 10 LWR Pu + MA Heavy Metal Storage U Spent Fuel Reprocessing 11 Seperations 27 FPs 24 Loss VHTR Once-Through Option 23 Loss Loss 14 Heavy Metal Storage 21 Unrecycled Cm VHTR Fuel Manufacturing 16 VHTR 17 Spent Fuel 18 Storage VHTR Front End Reprocessing LWR Pu + MA VHTR 15 Deep Burn Fuel Cycle. Generate degraded TRU to spike SFR Blanket. Long-term sustainability for resource-deficient countries (e.g., Japan) JAEA/GA jointly investigating FBR/VHTR deployment scenarios in Japan. 大洗 2007 年 4 月日 Slide 15

16 Conclusions MHR design features make it an outstanding choice for future deployment of nuclear energy Passive safety High-temperature capability High thermal efficiency, flexible siting Flexible fuel cycles and energy outputs MHR deployment supports significant, sustainable expansion of nuclear energy Better utilization of repository space with greatly reduced requirements for recycle of nuclear fuel Deployment in symbiosis with FBRs can provide virtually unlimited sustainability 大洗 2007 年 4 月日 Slide 16

17 ご静聴 有難うございました Thank you for your kind attention. Mito Plum Festival 大洗 2007 年 4 月日 Slide 17