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Indian ADS Programme
P. SinghP. SinghRaja Ramanna Fellow
Bhabha Atomic Research Centre, Mumbai-400085, IndiaEmail: [email protected]
Status of Accelerator Driven Systems Research and Technology Development, CERN, Feb 7- 9, 2017
Indian Installed Capacity : 303 GW (April 30, 2016)Renewable power : 28 %Non-newable power : 72 %Gross Electricity generated : 1272 TWh
India was 3rd largest producer of electricity In 2013 with 4.8 % Global share.
2014-15: Per capita Electricity Generation : 1010 kWhPer Capita Electricity Consumed : 746 kWh
Per Capita Electricity Consumed (kWh)
USA : 13616
Japan : 8474
World : 2752
China : 2328
End 2015: power surplusBrazil : 2154
India : 746
Need to reduce CO2
Plans to reach world average
21 reactors in operation
5 reactors under construction
(10.73 GWe nuclear)
Power Generation in India
Nuclear
2%Hydro25%
Renewable
3%Coal70%
Uranium reserves are limited and also Thorium offers a proliferation resistant fuel cycle
Country Reserves (tons)India 963,000USA 440,000Australia 300,000Canada 100,000Brazil 16,000Malaysia 4,500
American Estimates of World Thorium Resources:
USGS (2011)
OECD NEA & IAEA, Uranium 2011: Resources, Production and Demand ("Red Book"), using the lower figures of any range and omitting ‘unknown’ CIS estimate.
Malaysia 4,500 Other Countries 90,000World total 1,913,000
Estimated Indian Reserves: 11.93 MTons(with 8-10% ThO2
)
Program for ADS development in India
• High energy and high current proton accelerator• Development of 30 mA 20 MeV Linac (LEHIPA)• Development of High energy Linac (1 GeV)
• Spallation target and materials• Computational tools
• Spallation reaction analysis in the target.• Thermal hydraulics for LBE target simulations.
• Experimental loops for validation of thermal hydraulics codes and • Experimental loops for validation of thermal hydraulics codes and corrosion studies on window materials.
• Reactor Physics Development of Computer Codes and Nuclear data for ADS Other theoretical studies Experimental facility and studies Fuel Cycle and Conceptual Design Studies for Th utilisation
ADS
By Spallation process with GeV energy protonsstriking on high Z target.
Number of neutrons per proton per Watt ofbeam power reaches a plateau just above 1 GeV.
Most cost effective way to produce neutrons
( ) ( ) ( )1
sthermal fission
kP MW E MeV I A
k
Proton Energy : 1 GeVνs = 25 neutrons/protonν = 2.5 neutrons/fission
Beam currentBeam Energy
Most cost effective way to produce neutrons
Pth (MW) I (mA)
k=0.95
1000 29.2
1500 43.9
2000 58.5
2500 73.1
3000 87.7
I (mA)
k=0.98
10.2
15.3
20.4
25.5
30.6
DAE Accelerator Development Program
DAE labs have proposed Physics Studies and Enabling Technology Development for Ion Accelerators (BARC)
High Energy Proton LINAC Based Spallation Neutron Source (RRCAT)
BARC
1 GeV
RRCAT
BARC
Proton IS50 keV
RFQ3 MeV
DTL20 MeV
SC Linac
1 GeV
High current injector 20 MeV, 30 mA
Accelerator Development for ADS
ECR Ion Source RFQ DTL
Phase I
Phase IIILEHIPA
SC Linac
HWR/SSR
Phase II
200 MeV
ECR Ion Source RFQ DTL
400 keV RFQ LEBT Elliptical SC Cavity
LEBT MEBTEllipticalCavities
IS RFQ HWR, SSR
Elliptical Cavities
Scheme for the 1 GeV High Intensity Superconducting Proton Accelerator for ADS
(Frequency: 325 and 650 MHz)
200 MeV 1 GeV50 keV 3 MeV 150 MeV
20 MeV Linac (LEHIPA) at BARC
Ion Source RFQ DTL Beam Dump
LEBT MEBT BeamDiagnostics
600 kW
2.45 GHzECR Ion source
50 keV, 35mA.
352.21 MHz,4 Vane type RFQ3 MeV, 30 mA
352.21 MHz,20 MeV, 30 mAAlvarez type DTL
Conical target for Neutron generation
ECR LEBT RFQ DTL Beam Dump
High Yield Neutron Facility
IS DTL
LEBT MEBT
RFQ
Proton Current = 30 mA
1.00E+14
6.00E+14
1.10E+15
1.60E+15
2.10E+15
2.60E+15
3.10E+15
3.60E+15
4.10E+15
0 5 10 15 20 25
Proton Energy (MeV)
Yie
ld (
Ne
utr
on
s/s
ec
)
Reflector(Pb)
Moderator
Beryllium target
Proton Beam(20 MeV, 30 mA)
S0(EP) = 4.476 x 1011 x EP1.886 x I n/sec
Neutron Yield for Beryllium target
20 MeV Proton beam for ADS experiments in HWR critical facility
Linac tunnel in basement
HWR critical facility building
Beam transport line thru’ basement
Ground level beam transport gallery- with shielding
Studies have confirmed feasibility of extending 20 MeV proton beam to a target in the core of nearby HWR critical facility (commissioned)
400 keV RFQ
Pulse width= 5 msec
Pulse Period= 1 sec
1 sec
Beam acceleration : 400 keV RFQ
5 msec
RF
Beam
• D+ beam Transmission (96%), H2+ beam also accelerated to 400 keV
Neutron Generator (Purnima Labs) is an indigenously built 300 kV DCelectrostatic accelerator based neutron generator. Neutrons are produced usingtwo fusion reactions 3H(D, n) 4He and 2H(D, n) 3He popularly known as DD andDT fusion reactions. The D+ ions are produced in a RF ion source, which areextracted, focused, accelerated up to 300 keV energy and bombarded on thetarget to produce neutrons.
Neutron Generator
For deuteron current of 1mA at 400 keV, 14 MeV neutron yield is 1.0x 1011 n/s D+T reaction
Development of 400 keV, 1 mA RFQ for ADS
Facility for carrying out experiments on physics of ADS and for testing the simulations. This uses 14 MeV neutrons produced through D+T reaction.
Simple sub-critical assembly (keff=0.87) of natural uranium.
Measurements of flux distribution, flux spectra, total fission power, source multiplication, and degree of sub-criticality is carried out.
Key Design Features: Fuel : Metallic Natural Uranium,
Moderator : High density PolytheneReflector : Beryllium Oxide
Whole assembly covered with Borated Polythene & cadmium to isolatesystem from scattered neutrons.
13X13 square lattice: Centre 3X3 left vacant for insertion of Neutron Source 7 experimental channels 3 axial (10 mm diameter) & 4 radial (7.2 mm dia).
BRAHMMA :(Beryllium Oxide Reflected And High Density Polythene Moderated Multiplying Assembly)
BRAHMMA coupled to the PurnimaNeutron Generator
Experimental Channels
7 experimental channels3 Axial (diameter 10mm) EC1, EC2 &EC3 located at a radialdistance of 122mm, 238mm and 265 mm4 Radial (diameter 7.2 mm) EC5, EC6 & EC7 located in midelevation plane run upto cavity, EC4 located above mid elevation planeand covers full length of moderator
It is a Deep Subcritical System using Natural uranium as fuel We are testing our reactivity measurement techniques experimental as well as
data analysis part Modular and Compact Design Zero power Deep Subcritical System keff : 0.89 Possibility of using different fuel configurations Testing of Codes developed for performing Noise studies
in deep subcritical system for a non-Poisson source.
BRAHMMA
Why Deep Subcritical system ??
To study modal contamination in deep subcritical systems Modify & Validate codes based on point kinetics for deep subcritical systems where they
are not completely valid We have developed an experimental technique for extracting fundamental mode for deep
subcritical system – validated with noise measurements Possible Other Applications:
Reactivity monitoring for spent fuel storage
Development of special detectors to be used for measurements Miniature He-3 gas filled
detectors Optical fiber detectorFlux measurements: Axial and radial flux profile
measurement in various experimental channels.
Reactivity measurements:
Basic Experimental Measurement (BRAHMMA)
Reactivity measurements: Pulsed neutron techniques
(Area Ratio method, Slope Fit method, Source-jerk)
Noise measurements (Feynman-α, Rossi-α)
Frequency based measurement.
K-source Measurements Measurement of Source
multiplicationFundamental mode extraction
1. A Sinha et al Annals Nucl. Energy 75(2015) 2. Shefali Bajpai et al, Nuclear science and engineering 2015 3. Amar Sinha et al, Thorium Energy Conference Mumbai 2015 4. Tushar Roy et al Nucl. Sc. Eng.184(4)2016
BRAHMMA – Thermal ADSNat. U fuelDeep subcritical (Keff = 0.890)
Next stages proposed
Thermal ADS with higher Keff _ProposedSimilar configuration as BRAHMMA with SEU/LEU fuel
ADS programme in INDIA- Current Scenario
Similar configuration as BRAHMMA with SEU/LEU fuelKeff ~ 0.95
Fast ADS -PROPOSEDTh-Pu fuelKeff ~ 0.97-0.98
a) A schematic diagram of Folded Tandem Ion Accelerator, b) High voltage column section
E = (1+q) eV, For q=10, E= 66 MeV possible
a) b)
Relevance for ADS and Gen-IV fast reactors :
Accurate knowledge of Fission fragment kinetic energy, prompt neutron energy spectrum and multiplicity, prompt gamma multiplicity and average energy are of extreme importance in
7Li(p,n)7Be
multiplicity, prompt gamma multiplicity and average energy are of extreme importance in modeling innovative cores of Gen-IV reactors and ADS that runs on fast neutron spectrum.
Studies being carried out at FOTIA:Measurement of prompt fission neutron spectrum in fast neutron (0.5 MeV–5 MeV) induced fission of 232Th and 238U in coincidence with fission fragments.
Future experiments (to be carried out at FOTIA/LEHIPA) for several Actinide targets 237Np,235U, 239Pu etc. LEHIPA is expected to provide high current proton beams, thereby increasing the fast neutron flux many fold. This improves the statistics particularly in case of triple coincidence experiments (Fission-neutron-gamma)
Renju Thomas et al, NPD, BARC
20 MeV LEHIPA(Low Energy High Intensity Proton Accelerator)
Ion Source RFQ DTL Beam Dump
LEBT MEBTBeam
Diagnostics
ECR Ion source50 keV, 35mA.
RFQ 4 Vane type 3MeV, 30 mA
DTL20 MeV, 30 mA
LEBT : Low Energy Beam Transport System
RFQ : Radio Frequency Quadrupole
MEBT : Medium Energy Beam Transport System
DTL : Drift Tube Linac
LEHIPA Injector line
ECR PLASMA
ION SOURCE
30 mA, 50 KeV
RFQLength=4 m
50 KeV to 3 MeV
Solenoid 1 Solenoid 2
Steerer 1 Steerer 2
Faraday CupEmittance setup
The accelerator beam line consists the 50 keV ECR ion source, Low Energy Beam Transport (LEBT) line, RFQ and bending magnet for beam energy measurements.
Solenoid 1
AEC
Beam Dynamics in LEBT
Solenoid 1 Solenoid 2
Measured Beam profile atRFQ entrance
1.5 mm
ECR Ion Source (50 mA)
LEHIPA Injector line sub-systems
RFQ and analyzing Magnet
Analysing Magnet
RF Coupler
ECR Ion Source (50 mA)
RFQ
LEBT
First Beam Acceleration
Accelerated beam
Optimized accelerated beam pulse
Proton Acceleration - 1.24 MeV
WITHOUT RF POWER WITH RF POWER
Beam before RFQ
Beam after RFQ
(Un-accelerated beam)
3 MeV RFQ
Prototypes : DTL and DTs
Post Couplers Vacuum port
TunersDrift Tube Linac
0.00E+00
5.00E-04
1.00E-03
1.50E-03
2.00E-03
2.50E-03
3.00E-03
3.50E-03
3 4 5 6 7 8
Stre
ngt
h n
orm
aliz
ed t
o
Qu
ad c
om
po
nen
t
Pole Index (n=1 is dipole)
0
0.05
0.1
0.15
0.2
0.25
0.3
20
36
52
68
84
10
0
11
6
13
2
14
8
16
4
18
0
Mag
net
ic F
ield
(Te
sla)
Distance in mm
Post Couplers Vacuum port
Uniformity measurements Magnetic field measurements
Spallation target R&D at BARC
• Computational codes development and nuclear data for spallation reaction analysis in the target.
• Thermal hydraulics computational tools • Thermal hydraulics computational tools development for LBE target simulations.
• Experimental loops for validation of thermal hydraulics codes and corrosion studies on window materials.
PossibleLiquid
Targets
Element AtomicMass(A)
AtomicNumber(Z)
A/Z MeltingTemperature(0C)
BoilingTemperature (0C)
Density atroomTemp(g/cc)
Pb 207 82 2.524 327 1725 11.36
Bi 209 83 2.518 271 1560 9.80
Spallation target
TargetsLBE ~208 ~82.5 ~2.52 125 Similar
to Pb/Bi~10.0
Hg 200 79 2.532 -38.36 357 13.54
U 238 92 2.590 1132.3 3818 19.07
Ta 181 73 2.479 2996 5425 16.6
W 184 74 2.486 3410 5930 19.3
Hg is not suitable due to low boiling temp. for reactors
LBE has been identified as best target material
LBE Corrosion LoopHeight ~ 7mFlow Rate ~1.7 kg/sTemp: 5500C and 4500C
Spallation targets experiments
Mercury Loop
• Simulation of Window/Windowless Target
• Velocity field mapping by UVP monitor
• Carry-under studies
• Two-phase flow studies by Gamma Ray
• Laser-triangulation for free surface measurement
• CFD code validation
• Gas-driven flow studies(P. Satyamurthy et al, BARC)
Temp: 5500C and 4500CVelocity in the Samples~0.6 m/sCorrosion Tests: Charpy and Tensile
after 3000 hrs in the flow(R Fotedar, S.V. Phatnis, Chintamani Das,
A.K. Grover, A.K. Suri)
• One way coupled fast and thermal subcritical reactor with spallation neutron source incentre• Inner core is subcritical fast reactor with thermal neutron absorber liner surrounded bygap• Outer core is subcritical thermal reactor, neutrons leaking from inner core can comehere and get multiplied.• Neutron from thermal reactor cannot go to inner core due to absorber liner, that is whyit is one way coupled• Desired k can be obtained, reduction in proton beam power
One way Coupled System for ADS
• Desired keff can be obtained, reduction in proton beam power
S.B. Degweker et al. ; Ann. Nucl. Energy 26, 123 (1999)
Concept of one-way coupled ADS
By using two-energy amplifiers, requirement of primary proton beam current can be lowered substantially.
Gb = G0 * k1 /(1-k1); gain in booster
Net neutronic gain Gn = )1(
)/1(
1
11
k
kk
INNER CORE (fast neutron spectrum ADS) BOOSTER with multiplication
1 1 &kk
OUTER CORE (thermal neutron spectrum ADS fed by neutrons from inner core) with multiplication
2k
Driver beam current requirements reduced by factor Gn in one-way coupled system.
Fast booster may consume 240,242Pu, Np etc….and thermal region has Th as fuel.
2112 kkk but, = k1 or k2 whichever is larger.
GAP (between inner and
outer core)
Thermal neutron absorber lining
1. S.B. Degweker et al. Ann. Nucl. Energy 26, 123 (1999).
2. O.V. Shvedov et al. IAEA-TECDOC 985, D4.1, pp 313 (1987).
Inner Core: Fast Pb/LBE cooled and MOX (Pu-Th later U233-Th)
Outer Core: Thermal, PHWR type, MOX Fuel (U233-Th)
Accelerator R&D
1. Accelerator Physics 2. Ion Sources3. Magnets (Quadrupoles, Dipoles Steerers and
Solenoids)4. Solid State RF Amplifiers5. RF power couplers, tuners 6. Control Electronics 6. Control Electronics 7. Beam diagnostics 8. Superconducting cavities9. Cryogenics10.Test benches
Magnets for Medium Energy beam transport line
Quadrupole Magnet Assembly Quadrupole mounted in beam line Dipole Corrector Magnet Assembly
•Electromagnetic design of lenses - Quadrupole Focussing Magnets and dipole correctors
•Qualification tests with H+ beam at 2.5 MeV in FOTIA facility, IADD
At BARC At Fermilab
Production of magnets and characterization
25 nos. of Quadrupoles (designed at BARC and fabricated indigenously) arranged in the form of Doublets and Triplets.
BARC developed Combined Function Dipole Correctors shipped to FNAL
Quadrupole Triplet Assembly undergoing magnetic measurement at Stretch Wire Bench
SSR1 built at IUAC (Achieved 27 MV/m > specifications) -under IIFC
1.3 GHz TESLA type Cavity under IIFC. 1.3 GHz TESLA type Cavity under IIFC. Achieved > 35 MV/m
RRCAT & IUAC have also developed a 1.3 GHz TESLA-type 5-Cell Niobium Cavity.
650 MHz Cavity development is done at VECC (β=0.61) and for β=0.92 at RRCAT.
650 MHz (β=0.61) single cell cavity VTS testing
Sumit Som, VECC
Solid State RF amplifiers at 325 MHz
• Power: 3 kW• Overall Gain: > 65 dB• Efficiency : 65 %• 2nd Harmonics: - 41.9 dB
• Power: 1 kW• Overall Gain: > 65dB• Efficiency : 61 %• 2nd Harmonics: - 41.5 dB
1 kW Amplifier 3 kW Amplifier 7 kW Amplifier
• Power: 7 kW• Overall Gain: > 90 dB• Efficiency : 68 %• 2nd Harmonics: - 41.9 dB
RF Amplifiers at 650 MHz are developed at RRCAT, Indore
Summary & Conclusions
• India has large Thorium reserves and ADS is planned to use it.
• R&D is in progress for high intensity accelerator, spallation target and reactor design etc.
• ADS related experiments conducted using accelerator based neutron sources.based neutron sources.
• Indian Institutions & Fermilab Collaboration very useful and working very well.
• India is now Associate Member of CERN, our participation/collaborations could be more intense and fruitful.
AcknowledgementsWe thank colleagues for encouragement, useful discussions and providing inputs.
Dr Sekhar Basu, Chairman, AEC
Shri K N Vyas, Director, BARC
Dr D. Kanjilal, Director, IUACDr D. Kanjilal, Director, IUAC
Shri P V Bhagwat
Dr Gopal Joshi
Shri Sanjay Malhotra
Dr P Satyamurthy
Dr S B Degweker/ Dr K P Singh
Dr Sumit Som, VECC
Fermilab Colleagues ( Shekhar Mishra et al.)