Green Energy-Multiplier Sub-critical, Thermal-spectrum, Accelerator-driven, Recycling Reactor

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Transcription:

Green Energy-Multiplier Sub-critical, Thermal-spectrum, Accelerator-driven, Recycling Reactor R. Bruce Vogelaar Virginia Tech December 12, 2011 ADS & TU Mumbai, India 1

view from a newcomer (who asks and perhaps answers questions in a slightly different way) 2

3

classic nuclear option 4

What are obstacles? in US: safety waste weapons proliferation cost in India? 5

Safety Events/Reactor -Year Probabilistic Risk Assessment (PRA) of Core Damage Frequency (CDF) SMR claim 10-8 events per reactor-year that s 1 event in 1,000,000 reactors over 100 years 6 is re a credibility issue?

Waste long-lived fission products and actinides bury in Yucca Mountain? (now cancelled!) burn with accelerators? burn in next generation reactors? store on site current practice Weapons Proliferation enrichment reprocessing 7

Cost current prices for electricity (estimated by Black and Veatch, Overland Park, Kansas) cents/kwh Coal without CO 2 capture 7.8 Natural gas at high efficiency 10.6 Old nuclear 3.5 New nuclear 10.8 Wind in stand alone 9.9 Wind with necessary base line back-up 12.1 Solar source for steam-driven electricity 21.0 Solar voltaic cells; higher than solar steam electricity *NYT, Sunday (3/29/09) by Matw Wald 8 GEM*STAR: 4.5 per kwh with natural uranium fuel

What is being done 9 DOE-NE DOE-Science small modular reactors high intensity frontier safety - safety waste waste - weapons proliferation weapons proliferation cost - cost India PHWR (nat U) FBR ( 239 Pu & Th) AHWR ( 233 U & Th)

Are re or avenues to explore? to address clean energy now that would compete today with coal costs not being captured by previous slide low enough cost to try without requiring broad consensus first 10

Base Energy Paradigm Shift Natural Uranium Natural uranium or LWR spent fuel Enrichment Thermal Reactors Liquid Fuel Recycling Reactor Reprocessing Fast Reactors With supplemental neutrons Geologic Storage 11 No enrichment, no reprocessing End-of-life waste remnant reduced by x10 and delayed by centuries Geologic Storage

The cost of neutrons has dropped dramatically Neutron cost ($ per gram) 1.00E+12 1.00E+11 1.00E+10 1.00E+09 1.00E+08 1.00E+07 1.00E+06 1.00E+05 Electrostatic tandem with stopping length deuterium target Electron linac with W target LAMPF with W target 1950 1960 1970 1980 1990 2000 2010 2020 Year SNS with Hg target GEM*STAR with U target ~40 grams of neutrons will produce 1GWe for one year 12 ($432M @ 5 /kwh)

Proton Driven Sub-Critical System E wall a electric rmal t E beam beam fission t beam beam n f t beam 1 f n t wall a 1 f t n net electric power out electric wall power on target wall a m t E electric 1 f n t 1 a 13

f t a Reference parameters: e f 200 MeV / fission e n 19 MeV / neutron (for 1 GeV protons on Uranium) m 15 fissions / neutron t 44% rmal to electric conversion a 20% accelerator efficiency G = 65 (ie: 1MW target 65 MW e net output) 14

Design criteria: large m (fissions per neutron), reduces need to maximize a (accelerator efficiency) eg: changing accelerator efficiency from 20% to 10% only lowers G from 65 to 60 note: using k eff is really very misleading for a driven system a 15

Solid Fuel Issues much more centrally peaked for driven systems non-uniform fuel consumption volatile fissionproduct build-up within cladding 16 rmal shock due to beam trips (~800 320)

Molten Salt Eutectic Fuel Proven in ORNL MSRE reactor using Modified Hastelloy-N ( 235 U, 239 Pu, 233 U) 565 o 568 o 550 ThF 4 1111 o 950 850 1050 Uranium or Thorium fluorides form eutectic mixture with 7 LiF salt. High boiling point low vapor pressure 750 650 500 o 17 LiF 845 o 490 o LiF : UF 4 UF 4 1035 o

18 Initial fill feed consider a clear liquid which releases heat when exposed to light, eventually turning a dark purple increasing light exposure fast internal mixing 10-6 less volatile fission-product build-up in core with continuous feed-and-bleed beginning here bleed color and heat output remains constant indefinitely equilibrated isotope fractions throughout core and throughout time

For 50 years, and even today, people argue for fast-spectrum systems. Why? Faster burn-up of heavy actinides. 19

But Using Thermal Spectrum 0.01 0.2 ev highest tolerance for fission products: spin structure and resonance spacing reduces capture cross-section at rmal energies: -fission ( 239 Pu) ~ 100 (vs ~ 10 @ 50 kev) -capture (f.p.) 151 Sm (transmuted rapidly to low c nuclei) 135 Xe (continuously removed as a gas) more than compensates for slower fission of heavy actinides (which are burned anyway) 20

extracts many times more fission energy, without additional long-lived actinides Relative Waste after 2 passes Feed material: LWR spent fuel 20 GWy Acc 1 Acc 2 etc 40 GWy 60 GWy 21 major reduction and deferral of waste

Recycling 40 years worth of LWR spent fuel under-core interim storage under-core interim storage under-core interim storage first pass (40+ years) each can be used to start anor pre-equililbrated core every 5 years second pass (40+ years) 22 subsequent passes (fusion n source?)

23 Existing Proton Beam Power

Target Considerations 24 GEM*STAR Internal Target diffuse (or multiple) beam spots molten salt used for heat removal high neutron yield from uranium (but minimize target fission) spent target fluorinated and used as fuel minimize impact on local reactivity

25 redacted

Net Electric Power Out / Power on Target 360 330 300 270 240 210 180 150 120 90 60 30 running at peak gives 91% Pu-239 plutonium Fuel: Natural Uranium (MCNPX) equiv. to a LWR burning 0.5% of natural uranium 0-0.005 0.00 0.50 1.00 1.50 2.00 2.50 3.00 Fissioned Fraction (%) GEM*STAR Split Design Traditional Graphite (0.6 ppm B) Fluence running at x60 gives 70% Pu-239 plutonium 0.030 0.025 0.020 0.015 0.010 0.005 0.000 Fluence (n/b) 26

400 Fuel: un-reprocessed Light-Water-Reactor spent fuel 0.040 Net Electric Power / Power on Target 350 300 250 200 150 100 50 running at x140 gives 45% Pu-239 plutonium Super Critical 0 0.000 0.00 0.50 1.00 1.50 2.00 2.50 3.00 3.50 Additional Fission Fraction (%) GEM*STAR split design Traditional Graphite 100 * keff + 50 Fluence feed LWR spent fuel fission product fraction 0.035 0.030 0.025 0.020 0.015 0.010 0.005 Fluence (n/b) 27

System no enrichment; no reprocessing; can burn MANY fuels (pure, mixed, including LWR spent fuel) with no redesign required 28

High Temperature MS Advantages over LWRs no high-pressure containment vessel 34% 44% efficiency for rmal to electric conversion (low-pressure operation) match to existing coal-fired turbines, enables staged transition for coal plants, addressing potential cap-and-trade issues syntic fuels via modified Fischer-Tropsch methods very attractive (much more realistic than hydrogen economy) 29

30 redacted

What are obstacles? GEM*STAR uses liquid fuel but NRC is only comfortable with solid fuel, despite MSRE success Existing commercial deployed fleet of LWRs Engineers in nuclear industry have little experience with accelerators; physicists using accelerators have little experience with nuclear power plants little cooperation in base programs (vague talk about a distant ATW application) current focus (in US) only on existing and new modular reactors (scaled down versions of existing deployed technology) 31

advantages seem clear so why does this happen DOE NE Report to Congress, April 2010, Nuclear Energy Research and Development Roadmap does not include word accelerator even once. DOE Science (HEP & NP) ADS Report (September 17, 2010) Finding #2: Accelerator-driven sub-critical systems offer potential for safely burning fuels which are difficult to incorporate in critical systems, for example fuel without uranium or thorium. [ WHY not U??? ] Finding #3: Accelerator driven subcritical systems can be utilized to efficiently burn minor actinide waste. Finding #4: Accelerator driven subcritical systems can be utilized to generate power from thorium-based fuels MIT Energy Initiative;O Bama s Blue Ribbon Panel 100 year horizon, no new direction, yet continue DOE-NE funding at current level DOE NE thinking about an ADS demonstration in 2050 (ie, when I m 90 ) 32

33 ADS Technology Readiness Assessment Front End System Accelerating System RF Plant Beam Delivery Target Systems Instrumentation and Control Beam Dynamics Reliability Performance Reliability RF Structure Development and Performance Linac Cost Optimization Reliability Performance Cost Optimization Reliability Performance Performance Reliability Performance Emittance/halo growth/beamloss Lattice design Rapid SCL Fault Recovery System Reliability Engineering Analysis Transmutation Demonstration Industrial Scale Transmutation Green: ready, Yellow: may be ready, but demonstration or furr analysis is required, Red: more development is required. Power Generation

what drives this? 34 Table 1: Range of Parameters for Accelerator Driven Systems for four missions described in this whitepaper Transmutation Demonstration Industrial Scale Transmutation Industrial Scale Power Generation with Energy Storage Beam Power 1 2 MW 10 75 MW 10 75 MW 10 75 MW Beam Energy 0.5 3 GeV 1 2 GeV 1 2 GeV 1 2 GeV Beam trips (t > 5 min) < 50/year < 50/year < 50/year < 3/year Availability > 50% > 70% > 80% > 85% Industrial Scale Power Generation without Energy Storage helps motivate Intensity Frontier (ie: Project X at Fermilab); but higher efficiency via higher-power beams is not a requirement; $100 s of millions are going into solar and wind which have far greater outages. DOE-NE: It takes about 20 years to validate any new fuel system, so 2050 is earliest one might imagine for ADS. based on input from solid-fuel manufacturers; but consider how this might change if a new system actually addressed waste, proliferation, LWR spent fuel usage, and safety (thus becoming politically, publicly, and financially desirable).

People (and agencies), in US and India, and pretty much everywhere, are legitimately afraid that if y blink y might lose what y already have. Or that if y don t first obtain consensus opinion y won t get new funding. How can one n even try GEM*STAR in this environment? 35

Sequencing 36 CLF Corp. Syntic Liquid Fuel (driven with traditional green energy ) Syntic Liquid Fuel Production profits help fund nuclear effort transition SLF production to G*S heat source Full Scale GEM*STAR Commercialization (Long-Term Stretch Research for all) Interested parties in this room? (with ADNA) GEM*STAR Design first G*S demo Electricity Generation