R&D Status of  NFM and Neutron Source in China
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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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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

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


S outh w estern i nstitute of p hysics

ITER Reactor (ITER)

Construction 5 billion $; Operation 5 billion $


Iter parameters

ITER Reactor (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 


Plant description tokamak systems design assessment

Magnets Reactor (ITER)

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 Reactor (ITER)

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) Reactor (ITER)

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) Reactor (ITER)

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) Reactor (ITER)

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

40MeV/250mA


Beyond iter 2

Beyond ITER(2) Reactor (ITER)




Hl 2a swip chengdu
HL-2A-SWIP(Chengdu) Reactor (ITER)


East hefei

EAST-Hefei Reactor (ITER)


Development of prototype of nfm for iter

Photograph of fission chamber assembly Reactor (ITER)

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




Electronics
Electronics moderator






Results of measurement on hl 1m tokamak using bf3
Results of measurement on detector HL-1M tokamak using BF3


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 plateau width is 500V,and the slope of plateau is 0.9%, sensitivity:1±0.15cps/nν,insulation resistance≥1×10

  • 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


Profile of dd and dt neutron flux
Profile of DD and DT neutron flux plateau width is 500V,and the slope of plateau is 0.9%, sensitivity:1±0.15cps/nν,insulation resistance≥1×10


Dd neutron spectrum
DD neutron spectrum plateau width is 500V,and the slope of plateau is 0.9%, sensitivity:1±0.15cps/nν,insulation resistance≥1×10


Profile of dt neutron flux
Profile of DT neutron flux plateau width is 500V,and the slope of plateau is 0.9%, sensitivity:1±0.15cps/nν,insulation resistance≥1×10


Dt neutron spectrum
DT neutron spectrum plateau width is 500V,and the slope of plateau is 0.9%, sensitivity:1±0.15cps/nν,insulation resistance≥1×10


Fusion power density
Fusion power density plateau width is 500V,and the slope of plateau is 0.9%, sensitivity:1±0.15cps/nν,insulation resistance≥1×10


Fusion energy deposition
Fusion energy deposition plateau width is 500V,and the slope of plateau is 0.9%, sensitivity:1±0.15cps/nν,insulation resistance≥1×10


Detail design of nfm

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


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.


Equatorial ports
Equatorial Ports positions in toroidal and poloidal direction


S outh w estern i nstitute of p hysics
Ranges of positions in toroidal and poloidal directionoutput power, neutron yield, neutron flux behind F.W., counting rates and dynamic ranges of fission chambers 235U and 238U.



S outh w estern i nstitute of p hysics
Detection efficiencies and covering neutron flux range of six fission chambers and their three combinations


Structures and assemblies of three type nfms
Structures and assemblies of three type NFMs six fission chambers and their three combinations


Eq 01

Eq#01 six fission chambers and their three combinations


S outh w estern i nstitute of p hysics

Eq#7 six fission chambers and their three combinations


S outh w estern i nstitute of p hysics

Eq#8 six fission chambers and their three combinations


S outh w estern i nstitute of p hysics

Eq17 six fission chambers and their three combinations


Portable neutron tube
Portable neutron tube six fission chambers and their three combinations


Preliminary design for diagnostic of neutron flux and spectrum in nt tbm

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




Micro fission chamber assembly 1
Micro-fission chamber assembly NT-TBM(CN HCSB)(1)


Three types mfc
Three types MFC NT-TBM(CN HCSB)


Micro fission chamber assembly 2
Micro-fission chamber assembly NT-TBM(CN HCSB)(2)



S outh w estern i nstitute of p hysics

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


S outh w estern i nstitute of p hysics

谢谢 range Thank you