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
YANG Jin-wei YANG Qingwei SONG Xian-ying
SouthWestern Institute of Physics
Introduction of International Thermal-nuclear Experiment Reactor (ITER)
Development status of nuclear fusion in China
Development status of NFM
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 summaryOutline of talk
Construction 5 billion $; Operation 5 billion $
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
Magnets Reactor (ITER)
Additional Heating and Current Drive
Plasma Diagnostic System
Vacuum Pumping & Fuelling
Cryostat, Vacuum Vessel Suppression System, and Thermal Shields
Assembly Equipment and Procedures
ITER Decommissioning Procedures
Mechanical Loads and Machine Supports Configuration
Tokamak Seismic AnalysisPlant Description: Tokamak Systems Design & Assessment
Tritium Plant & Detritiation
Cryoplant and Cryodistribution
Pulsed and Steady State Power Supplies
Miscellaneous Plant Systems
Site Layout and Buildings
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.
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
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
Photograph of fission chamber assembly Reactor (ITER)
Voltage plateau-characteristic curve
Counting plateau curve
Results of measurement on HL-2A tokamak using prototype NFMDevelopment of Prototype of NFM for ITER
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 tokamakConclusion and discussion
Counting rates and dynamic ranges of fission chambers plateau width is 500V,and the slope of plateau is 0.9%, sensitivity:1±0.15cps/nν,insulation resistance≥1×10235U 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
Diagnostic six fission chambers and their three combinationssystem
Coolant loop of helium
Micro-fission chamber assembly
Schematic drawing of MFC Assembly
Structure of NT-TBM(CN HCSB)Preliminary design for diagnostic of neutron flux and spectrum in NT-TBM
Development of low detection efficiency and 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 NFMcalibration.Plan
谢谢 range Thank you