Thorium, ADSRs…… and ns-FFAGs Bob Cywinski School of Applied Sciences CONFORM Open Day , 11 May 2008 The Carbon Problem Energy source Grammes of carbon per KWh of electricity Nuclear 4 Wind 8 Hydro electric power 8 Energy crops 17 Geothermal 79 Solar 133 Gas 430 Diesel 772 Oil 828 Coal 955 source: Government Energy Support Unit (confirmed by OECD) CONFORM Open Day , 11 May 2008 Meeting the Energy Challenge (2008) CONFORM Open Day , 11 May 2008 Fission....... and breeding U-Pu CONFORM Open Day , 11 May 2008 Th-U Thorium as a fuel.... Advantages 233U 232Th has superior fissile properties g Robust fuel and waste form 233Th n Generates no Pu and fewer higher actinides b Proliferation resistant 22 mins 233U 27 days 233Pa b Disadvantages Requires introduction of fissile seed (235U or Pu) 233U is weapon grade unless denatured Parasitic 232U production results in high gamma activity. Thorex processing of waste needs substantial development CONFORM Open Day , 11 May 2008 Annual energy resources Thorium equivalent ~5x109 tonnes of coal 27x109 barrels of oil 2.5x1012 m3 of natural gas 65x103 tonnes of uranium 5x103 tonnes of thorium After Sorenson CONFORM Open Day , 11 May 2008 Estimated global Th resources CONFORM Open Day , 11 May 2008 IAEA, status report May 2005 IAEA ….in recent times, the need for proliferation-resistance, longer fuel cycles, higher burn up, improved waste form characteristics, reduction of plutonium inventories and in situ use of bred-in fissile material has led to renewed interest in thorium-based fuels and fuel cycles in several developed countries……. CONFORM Open Day , 11 May 2008 Past experiences CONFORM Open Day , 11 May 2008 Current Power Strategy: India 3-stage closed cycle 500 MW prototype FBR is under construction in Kalpakkam is designed to breed 233U-from Th The FBR is expected to be operating in 2011, fuelled with uranium-plutonium oxide It will have a blanket of thorium and uranium to breed fissile U-233 and plutonium respectively CONFORM Open Day , 11 May 2008 Spallation “A high-energy nuclear reaction in which a target nucleus struck by an incident particle of energy greater than about 50 MeV ejects numerous lighter particles and becomes a product nucleus correspondingly lighter than the original nucleus. The light ejected particles may be neutrons, protons, or various composite particles…” Encyclopaedia Brittanica CONFORM Open Day , 11 May 2008 An alternative approach: The Energy Amplifier or Accelerator Driven Subcritical Reactor Concept CONFORM Open Day , 11 May 2008 MYRRHA: an ADSR transmutation proposal The MYRRHA design proposes a windowless Pb-Bi target: 350 Mev, 5mA proton beam The target surface results from the vertical co-axial confluent Pb-Bi liquid metal flow The beam impacts the target vertically from above MYRRHA is being designed to transmute Pu waste Can an ADSR operate on thorium only? U-Pu MOX core and blanket CONFORM Open Day , 11 May 2008 The Energy Amplifier/ADSR energy balance output 600MWe MWe η~40% electrical energy converter 1550MWth 20MWe MWth 10MW Energy gain: 155 η~50% accelerator sub critical reactor 232Th + n →233Th →233Pa (27d)→ CONFORM Open Day , 11 May 2008 233U Target size Proton energy CONFORM Open Day , 11 May 2008 Neutron energies The energy spectrum of the spallation neutrons at different incident proton energies. The target is a lead cylinder of diameter 20 cm At 1 Gev, approximately 24 neutrons per proton are produced CONFORM Open Day , 11 May 2008 Proton beam requirements for EA/ADSR The (thermal) power output of an ADSR is given by Pth with N E f k eff . 1 k eff N = number of spallation neutrons/sec Ef = energy released/fission (~200MeV) ν = mean number of neutrons released per fission (~2) keff= criticality factor (<1 for ADSR) So, for a thermal power of 1550MW we require 1 k eff N 9.6 1019 neutrons.s1 k eff Given that a 1 Gev proton produces 24 neutrons (in lead) this corresponds to a proton current of 9.6 1019 1 k eff 1 k eff i 1.6 10 19 amps 640 mA 24 k eff k eff CONFORM Open Day , 11 May 2008 Proton beam requirements keff=0.95, i=33.7mA keff=0.98, i=13.1mA keff=0.99, i=6.5mA To meet a constraint of a 10MW proton accelerator we need keff=0.985 CONFORM Open Day , 11 May 2008 Safety margins k=0.985 CONFORM Open Day , 11 May 2008 ...but why has no ADSR ever been built ? ...because existing accelerators are not sufficiently stable and reliable CONFORM Open Day , 11 May 2008 ADSR geometry (a) single target 232Th GEANT4 core CONFORM Open Day , 11 May 2008 Flux distribution in ADSR core Power density distribution improves with keff but remains non-optimal Solution is generally to increase fissile enrichment in several core zones (eg see step at zone boundary on left) A better solution might be to use several proton beams and spallation targets H.M. Broeders, I. Broeders : Nuclear Engineering and Design 202 (2000) 209–218 Multiple beams/targets should also alleviate accelerator stability problems CONFORM Open Day , 11 May 2008 Triple target ADSR Power density distribution (W:cm3) in a lead-cooled ADSR with Th:U233 fuel. The three beams with buffer zones are described by seven lead-filled fuel element positions. The over-all power distribution is satisfactory. CONFORM Open Day , 11 May 2008 Triple target ADSR Power density distribution (W:cm3) in a lead-cooled ADSR with Th:U233 fuel. The three beams with buffer zones are described by seven lead-filled fuel element positions. Trefoil of 3 nsFFAGs each providing 3.5mA at 1 GeV The over-all power distribution is satisfactory. Three ns-FFAG drivers should be no more expensive than a singe conventional driver.... Molten lead is both core coolant and spallation target Pb-cooled Th/U233 subcritical core with: keff=0.985 Pth=1550MWth .....and will provide the required reliability margin CONFORM Open Day , 11 May 2008 ADSR geometry (b) triple target 232Th GEANT4 core CONFORM Open Day , 11 May 2008 Can thorium fuel be used in conventional reactors? Miniature spallation target in central bore of fuel element assembly High power (MW) proton beam Spallation charging of Th fuel rods 232Th to 233U conversion can be better optimised, with mitigation against detrimental neutron absorption by 233Th and 233Pa Modifications to existing reactors are not necessary Wider global exploitation of nuclear technology is possible Fuel preparation and burn cycles are decoupled CONFORM Open Day , 11 May 2008 ThorEA – the thorium energy amplifier association CONFORM Open Day , 11 May 2008 The way forward ? The AESIR project: (Accelerator Energy System with Inbuilt Reliability) Stage 1: LOKI Cost Time £17M 2-3 years (The Low-key demonstrator) 35 MeV H- system ; High current. (10 mA?) Commercial source, standard Linac Stage 2: FREA (FFAG Research for the Energy Amplifier) 2nd stage ns-FFAG ring to boost energy to 390 MeV emphasis on reliability Gives useful proton machine (c.f. TRIUMF, PSI). £50 M + 4-5 years £1-2B + 7-8 years Stage 3: THOR Add a second ns-FFAG ring to give 1 GeV Use with a real target and nuclear core for First operational ADSR system “.. dream the unthinkable because we desperately need new ideas” Carlo Rubbia (ThorEA meeting, Huddersfield, April 2009) CONFORM Open Day , 11 May 2008 Summary Thorium is an underexploited fuel resource that could meet all our power generation requirements for many centuries Thorium fuel is proliferation resistant and produces relatively low level radiotoxic waste Although thorium is fertile, not fissile, it may be possible to construct safe and reliable EA/ADSR power systems, using spallation neutrons to drive the transmutation/fission process Similar processes could provide thorium fuel elements for conventional power reactors The key to both technologies is the development of compact, cheap and reliable accelerators: We believe ns-FFAGs may fit the bill Thorium might just save the planet!! CONFORM Open Day , 11 May 2008 (1941) FERMI’s logbook containing the design of PILE-1 CONFORM Open Day , 11 May 2008 Acknowledgements Professor Roger Barlow (Manchester) Dr Cristian Bungau (Manchester/Cockcroft) Dr Adrian Bungau (Huddersfield/Cockcroft) Dr Bill Nuttall and Geoff Parks (Cambridge) RCUK, EPSRC, STFC CONFORM Open Day , 11 May 2008