1 N uclear & P article P hysics S ection , P hysics D epartment
核工业西南物理研究院 S outh W estern I nstitute of P hysics
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Transcript of 核工业西南物理研究院 S outh W estern I nstitute of P hysics
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第十三届全国核电子学与核探测技术学术年会
核工业西南物理研究院核工业西南物理研究院SSouthouthWWestern estern IInstitute of nstitute of PPhysicshysics
R&D Status of NFM and Neutron Source in China
YANG Jin-wei YANG Qingwei SONG Xian-ying
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Outline of talk• 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 an
d trillium production-test blanket module • Plan and summary
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ITERConstruction 5 billion $; Operation 5 billion $
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ITER Parameters
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
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Plant Description: Tokamak Systems Design &
Assessment 1. Magnets 2. Vacuum Vessel 3. Blanket 4. Divertor 5. Additional Heating and Current Drive 6. Plasma Diagnostic System 7. Vacuum Pumping & Fuelling 8. Cryostat, Vacuum Vessel Suppression System, and Thermal Shields 9. Remote Handling 10. Assembly Equipment and Procedures 11. ITER Decommissioning Procedures 12. Mechanical Loads and Machine Supports Configuration 13. Materials Assessment 14. Nuclear Assessment
15. Tokamak Seismic Analysis
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Plant Description: Plant Systems Design & Assessment
1.Tritium Plant & Detritiation
2.Cooling Water
3.Cryoplant and Cryodistribution
4.Pulsed and Steady State Power Supplies
5.Miscellaneous Plant Systems
6.Site Layout and Buildings
7.Plant Control
Plasma Performance
Safety
Plans
Resources
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Time –line for pre-construction
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Time-line for construction phase
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Time-line for operation phase
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Decommission phase(1)1. De-activation
a. Removal of mobilizable tritium and dust from the machine using available techniques & equipment. Removal and deactivation of coolants.
b. Classification and packaging of active, contaminated and toxic material.
c. Removal of all the in-vessel components.OPTION 1: removal of ex-vessel components (if not done in phase 2). Duration: 5 years.
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Decommission phase(2)
THE ITER FACILITY IS HANDED OVER TO AN ORGANIZATION AT THE HOST COUNTRY
RESPONSIBLE FOR THE COMPLETION OF DECOMMISSIONING
Radioactivity decay period
a.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.
b.No site activities are required except security and monitorin
Duration :A few decade years
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Decommission phase(3)
Final Dismantling & Disposal
a. 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)
b. classification & packaging of active, contaminated and toxic material .
Duration: 6 years
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Beyond ITER(1)- IFMIF (International Fusion Materials Irradiation Facility) 7Li(d,n)
40MeV/250mA
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Beyond ITER(2)
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Vacuum Vessel and Diagnostic Ports
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Map-ITER- Partners( http:/WWW.iter.org)
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HL-2A-SWIP(Chengdu)
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EAST-Hefei
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Development of Prototype of NFM for ITER
• Photograph of fission chamber assembly
• Electronics
• Voltage plateau-characteristic curve
• Counting plateau curve
• Results of measurement on HL-2A Results of measurement on HL-2A tokamak using prototype NFMtokamak using prototype NFM
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Photograph of fission chamber assembly with polyethylene moderator
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Fission chamber and pre-amplifier
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Electronics
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Pulse signal of neutron
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Voltage plateau-characteristic curve of
fission chamber detector
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Counting plateau curve
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Results of measurement on HL-2A Results of measurement on HL-2A tokamak using prototype NFMtokamak using prototype NFM
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Results of measurement on Results of measurement on HL-1M tokamak using BF3 HL-1M tokamak using BF3
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Conclusion and discussion• 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-ray radiation 2.8×10-2Gy/s• This assembly has being used for photo-
neutron measurement in the HL-2A tokamak
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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
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Profile of DD and DT neutron flux
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DD neutron spectrum
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Profile of DT neutron flux
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DT neutron spectrum
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Fusion power density
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Fusion energy deposition
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Detail design of NFM• Counting rates and dynamic ranges of fission c
hambers 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.
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Schematic drawing of three equatorial diagnostic ports positions in toroidal and poloidal direction.
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Equatorial Ports
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Ranges of output power, neutron yield, neutron flux behind F.W., counting rates and dynamic ranges of fission chambers
235U and 238U.
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Structures of high (a) and low (b) sensitivity fission chamber detectors.
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Detection efficiencies and covering neutron flux range of six fission chambers and their three
combinations
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第十三届全国核电子学与核探测技术学术年会 Structures and assemblies of three type NFMs
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Eq#01
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Eq#7
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第十三届全国核电子学与核探测技术学术年会
Eq#8
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第十三届全国核电子学与核探测技术学术年会
Eq17
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第十三届全国核电子学与核探测技术学术年会
Portable neutron tube
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第十三届全国核电子学与核探测技术学术年会
Preliminary design for diagnostic of neutron flux and spectrum in NT-TBM
• Diagnostic system
• Coolant loop of helium
• Micro-fission chamber assembly
• Schematic drawing of MFC Assembly
• Structure of NT-TBM(CN HCSB)
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第十三届全国核电子学与核探测技术学术年会
Neutron fluxes and spectra measurement system and cooling loop for NT-TBM.
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第十三届全国核电子学与核探测技术学术年会
Preliminary design for diagnostic of neutron flux in NT-TBM(CN HCSB)
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第十三届全国核电子学与核探测技术学术年会
Micro-fission chamber assembly (1)
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第十三届全国核电子学与核探测技术学术年会
Three types MFC
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第十三届全国核电子学与核探测技术学术年会
Micro-fission chamber assembly (2)
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第十三届全国核电子学与核探测技术学术年会
Schematic drawing of MFC Assembly
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第十三届全国核电子学与核探测技术学术年会
Plan• Development of low detection efficiency an
d wide dynamic range 235U FC operated in Campbelling or current mode.
• Development of 238U FC.
• Development of electronics(low noise).
• Development of compact ~1011 n/s DT neutron source for NFM calibration.
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第十三届全国核电子学与核探测技术学术年会
谢谢谢谢 ThThank youank you