slide1
Download
Skip this Video
Download Presentation
核工业西南物理研究院 S outh W estern I nstitute of P hysics

Loading in 2 Seconds...

play fullscreen
1 / 68

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


  • 101 Views
  • Uploaded on

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

loader
I am the owner, or an agent authorized to act on behalf of the owner, of the copyrighted work described.
capcha
Download Presentation

PowerPoint Slideshow about ' 核工业西南物理研究院 S outh W estern I nstitute of P hysics' - sahkyo


An Image/Link below is provided (as is) to download presentation

Download Policy: Content on the Website is provided to you AS IS for your information and personal use and may not be sold / licensed / shared on other websites without getting consent from its author.While downloading, if for some reason you are not able to download a presentation, the publisher may have deleted the file from their server.


- - - - - - - - - - - - - - - - - - - - - - - - - - E N D - - - - - - - - - - - - - - - - - - - - - - - - - -
Presentation Transcript
slide1

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

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 and trillium production-test blanket module

Plan and summary

Outline of talk
slide3

ITER

Construction 5 billion $; Operation 5 billion $

iter parameters

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 

plant description tokamak systems design assessment
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
plant description plant systems design assessment

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

decommission phase 1

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.

decommission phase 2

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

decommission phase 3

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

beyond iter 1 ifmif international fusion materials irradiation facility 7 li d n

Beyond ITER(1)- IFMIF (International Fusion Materials Irradiation Facility) 7Li(d,n)

40MeV/250mA

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 tokamak using prototype NFM

Development of Prototype of NFM for ITER
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-rayradiation 2.8×10-2Gy/s

This assembly has being used for photo-neutron measurement in the HL-2A tokamak

Conclusion and discussion
mcnp calculations
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
detail design of nfm
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
schematic drawing of three equatorial diagnostic ports positions in toroidal and poloidal direction
Schematic drawing of three equatorial diagnostic ports positions in toroidal and poloidal direction.
slide51
Ranges ofoutput power, neutron yield, neutron flux behind F.W., counting rates and dynamic ranges of fission chambers 235U and 238U.
slide53
Detection efficiencies and covering neutron flux range of six fission chambers and their three combinations
preliminary design for diagnostic of neutron flux and spectrum in nt tbm
Diagnosticsystem

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
slide67
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
ad