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3D Coupled Fault Modelling for the Gas-cooled Fast Reactor

3D Coupled Fault Modelling for the Gas-cooled Fast Reactor. Jason Dunstall KNOO PhD Student (EPSRC Funded) Applied Modelling and Computation Group (AMCG) Dept. Earth Sciences & Engineering Supervisors: Prof. C. Pain, Prof. A. Goddard KNOO Post-Doc. Support: Dr J Gomes.

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3D Coupled Fault Modelling for the Gas-cooled Fast Reactor

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  1. 3D Coupled Fault Modelling for the Gas-cooled Fast Reactor Jason Dunstall KNOO PhD Student (EPSRC Funded) Applied Modelling and Computation Group (AMCG) Dept. Earth Sciences & Engineering Supervisors: Prof. C. Pain, Prof. A. Goddard KNOO Post-Doc. Support: Dr J Gomes

  2. Presentation overview • The Gas-cooled Fast Reactor • What is the GFR • Why is it of interest? • Background of HTRs • AMCG involvement with GFR • Dragon Reactor Experiment • Background to the DRE • Benchmarking work using Dragon

  3. What is the GFR? • Gas-cooled Fast Reactor - one of six Generation IV innovative reactor systems • Design specifications: • He cooled • Carbide or nitride fuel • Zr3Si2 reflector, B4C shield • 600 / 2400 MWth designs • Power density ~100 MWth / m3 • ~ 850°C outlet temperature (direct cycle)

  4. Strengths of the GFR • Incorporation of passive safety features • Helium chemically inert, nearly neutronically inert, single phase • Favourable reactivity coefficients • Sustainability • High U utilisation, actinide management, integrated fuel cycle • High temperature reactor • Improved thermal efficiency, potential for use of process heat • But: high fuel rating, lack of moderation → cooling and control issues

  5. Technology base for GFR • Decommissioned reactors include: • Dragon (International / UK sited) • AVR, THTR (Germany) • Peach Bottom, Fort St. Vrain (USA) • Fast reactors inc. DFR / PFR (UK), Superphenix (France) • Extensive UK experience from AGRs • Current and future projects include: • HTTR (Japan) • HTR-10 (China) • PBMR (South Africa) • GT-MHR (Russia / General Atomics) • ETDR (~2015)

  6. AMCG work on GFR • AMCG Codes: • EVENT (radiation transport) • FLUIDITY (CFD) • FETCH (coupled radiation-fluids interface code) • Perform multiphysics analysis on GFR designs • Potential for cross-cutting with VHTR - fuels & materials.

  7. Background to Dragon • Dragon Reactor Experiment • OECD / NEA International collaboration • Operational 1964-75, Winfrith, Dorset • World’s first HTR • Testbed for HTR technology: • Fuel (TRISO particles) • Use of Helium coolant • Materials under HTR conditions • Physics description: • 1.5m3 core volume • Inlet temperature ~350°C, outlet ~750°C • Normal peak core temperature ~1200°C

  8. Dragon – some pictures

  9. Modelling the DRE (1) • Modelling the DRE: HTR benchmarking with FETCH • Reactivity measurements • Neutron fluxes & power distributions • Transients • EVENT Model: • 71650 nodes • 75927 surface • & volume elements Fuel (I) Fuel (II) Inner Reflector Control Rod Region Outer Reflector

  10. Modelling the DRE (2) • Example – Dragon first charge loading reactivity measurements and EVENT transport calculation results EVENT transport calculations Dragon experimental (solid line)

  11. Future PhD work for GFR • GFR (600 and / or 2400 MW) model in EVENT - benchmarking • Detailed multiphysics analysis using FETCH • 3D asymmetrical transients & accident scenarios including: • Control rod movement • Structural faults • Depressurisations • UTOP

  12. Summary • Use of well documented Dragon experiment for benchmarking of FETCH • Need for comprehensive awareness of materials, thermal hydraulics and control issues for GFR • Address use of fast spectrum cross section data • Plan to perform detailed GFR coupled transient fault studies

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