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核工业西南物理研究院 S outh W estern I nstitute of P hysics

R&D Status of NFM and Neutron Source in China. YANG Jin-wei YANG Qingwei SONG Xian-ying. 核工业西南物理研究院 S outh W estern I nstitute of P hysics. Introduction of International Thermal-nuclear Experiment Reactor (ITER) Development status of nuclear fusion in China Development status of NFM

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核工业西南物理研究院 S outh W estern I nstitute of P hysics

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  1. R&D Status of NFM and Neutron Source in China YANG Jin-wei YANG Qingwei SONG Xian-ying 核工业西南物理研究院 SouthWestern Institute of Physics

  2. Introduction of International Thermal-nuclear Experiment Reactor (ITER) Development status of nuclear fusion in China Development status of NFM MCNP calculations Detail design for NFM Calibration neutron source Primary neutron detectors for comparision calibration Micro-fission chamber development for Neutronics and trillium production-test blanket module Plan and summary Outline of talk

  3. ITER Construction 5 billion $; Operation 5 billion $

  4. ITERParameters Plasma Major Radius 6.2m Plasma Minor Radius 2.0m Plasma Volume 840m3 Plasma Current 15.0MA Toroidal Field on Axis 5.3T Fusion Power 500MW Burn Flat Top >400s Power Amplification >10 

  5. Magnets Vacuum Vessel Blanket Divertor Additional Heating and Current Drive Plasma Diagnostic System Vacuum Pumping & Fuelling Cryostat, Vacuum Vessel Suppression System, and Thermal Shields Remote Handling Assembly Equipment and Procedures ITER Decommissioning Procedures Mechanical Loads and Machine Supports Configuration Materials Assessment Nuclear Assessment Tokamak Seismic Analysis Plant Description: Tokamak Systems Design & Assessment

  6. Plant Description: Plant Systems Design & Assessment Tritium Plant & Detritiation Cooling Water Cryoplant and Cryodistribution Pulsed and Steady State Power Supplies Miscellaneous Plant Systems Site Layout and Buildings Plant Control Plasma Performance Safety Plans Resources

  7. Time –line for pre-construction

  8. Time-line for construction phase

  9. Time-line for operation phase

  10. Decommission phase(1) 1. De-activation Removal of mobilizable tritium and dust from the machine using available techniques & equipment. Removal and deactivation of coolants. Classification and packaging of active, contaminated and toxic material. Removal of all the in-vessel components.OPTION 1: removal of ex-vessel components (if not done in phase 2). Duration: 5 years.

  11. Decommission phase(2) THE ITER FACILITY IS HANDED OVER TO AN ORGANIZATION AT THE HOST COUNTRYRESPONSIBLE FOR THE COMPLETION OF DECOMMISSIONING Radioactivity decay period The vacuum vessel radioactivity is left to decay to a level which allows extraction of vessel sectors into the tokamak building (during phase 2) for size reduction & disposal. No site activities are required except security and monitorin Duration :A few decade years

  12. Decommission phase(3) Final Dismantling & Disposal removal of vacuum vessel sectors and their size reduction by remote/semi-remote operationsOPTION 2: removal of ex-vessel components (if not done in phase 1) classification & packaging of active, contaminated and toxic material . Duration: 6 years

  13. Beyond ITER(1)- IFMIF (International Fusion Materials Irradiation Facility) 7Li(d,n) 40MeV/250mA

  14. Beyond ITER(2)

  15. Vacuum Vessel and Diagnostic Ports

  16. Map-ITER- Partners( http:/WWW.iter.org)

  17. HL-2A-SWIP(Chengdu)

  18. EAST-Hefei

  19. Photograph of fission chamber assembly Electronics Voltage plateau-characteristic curve Counting plateau curve Results of measurement on HL-2A tokamak using prototype NFM Development of Prototype of NFM for ITER

  20. Photograph of fission chamber assembly with polyethylene moderator

  21. Fission chamber and pre-amplifier

  22. Electronics

  23. Pulse signal of neutron

  24. Voltage plateau-characteristic curve of fission chamber detector

  25. Counting plateau curve

  26. Results of measurement on HL-2A tokamak using prototype NFM

  27. Results of measurement on HL-1M tokamak using BF3

  28. pulse width is 1µs, the plateau length from 300—800V, the plateau width is 500V,and the slope of plateau is 0.9%, sensitivity:1±0.15cps/nν,insulation resistance≥1×109 ohm. Anti γ-rayradiation 2.8×10-2Gy/s This assembly has being used for photo-neutron measurement in the HL-2A tokamak Conclusion and discussion

  29. MCNP calculations • MCNP calculations for NFM • Profile of DD neutron flux • DD neutron spectrum • Profile of DT neutron flux • DT neutron spectrum • Profile of fusion power density • Deposition of fusion energy

  30. Profile of DD and DT neutron flux

  31. DD neutron spectrum

  32. Profile of DT neutron flux

  33. DT neutron spectrum

  34. Fusion power density

  35. Fusion energy deposition

  36. Counting rates and dynamic ranges of fission chambers 235U and 238U. Structures of high (a) and low (b) sensitivity fission chamber detectors. Six fission chambers and their three combinations. Structures and assemblies of three type NFMs. Detail design of NFM

  37. Schematic drawing of three equatorial diagnostic ports positions in toroidal and poloidal direction.

  38. Equatorial Ports

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