Complexity of Accelerator Driven System

P. Singh

Bhabha Atomic Research Centre

Mumbai-400 085

Email: psingh@barc.gov.in

Plan of the talk:

1. Introduction

2. Why is Accelerator Driven sub-critical reactor System (ADS) so important?

3. Issues with ADS

4. Summary & conclusions.

Indo-Japan Accelerator School, IUAC Feb 17, 2015

Facing the energy challenge

Electricity generation worldwide

(OECD, 2007)

IAEA report-2006

At the present consumption level, known reserves for coal, oil and gas correspond to a duration:

Coal: 230 yrs

Oil: 45 yrs

Gas: 65 yrs

Nuclear Power appears to be an inevitable option as future energy source; but disposal of nuclear waste is an important issue of concern in harnessing nuclear energy through “critical reactors”, which needs to be addressed satisfactorily.

Pu (total) > 1000 tons. Np and Am > 200 tons.

Current Challenges in Nuclear Waste Management

• Long Lived Minor actinides (MA) & Fission products

• Minor actinides with high activity

• 239Pu (T1/2 24110 yrs)

• 237Np (T1/2 2.1 million yrs)

• 241Am (T1/2 432 yrs)

• decay from fission products

• 90Sr (T1/2 28.9yrs)

• 137Cs (T1/2 30 yrs)

• 129 I (T1/2 15.7 million yrs)

Adopting closed fuel cycle also reduces nuclear waste burden

Radiotoxicity of spent fuel is dominated by :

FPs for first 100 years.

subsequently, Pu (>90%)

After Pu removal

Minor Actinides specially Am (~ 9%)

Natural decay of spent

fuel radiotoxicity

With early introduction of fast reactors using (U+Pu+Am) based fuel, long term raditoxicity of nuclear waste will be reduced.

200000

years

300 years

A thorium fuel cycle offers several potential advantages over a uranium

fuel cycle

1. Greater abundance on Earth (1000+ year solution or a quality low-

carbon bridge to truly sustainable energy sources solving negative

environmental impact”.

2. superior physical and nuclear fuel properties

3. reduced nuclear waste production.

4. However, development of thorium power has significant start-up costs.

3. lack of weaponization potential as an advantage of thorium

Attractive Features of Thorium / Thoria

• High Abundance – Uniformly distributed in earth crust – 3 to 4 times abundant than uranium

• Better Fuel Performance Characteristics – Higher melting point – Better thermal conductivity – Lower fission gas release – Good radiation resistance and

dimensional stability – Reduced fuel deterioration in the event

of failure • Relative ease in Waste Management

– No oxidation -Superior behavior and suitable for direct disposal in repository as it is mono-valent.

– Generates less plutonium and minor actinides

MA MA from LMFBR (U-Pu Cycle), kg/GWeY

MA from Th-U cycle, Kg/GWeY

Np237 4.6 0.06

Am241 4.0 1E-7

Am242 0.07 0

Am243 1.9 0

Cm242 0.11 0

Cm244 0.13 0

Comparison of MAs produced in (Th-U) and (U –Pu) cycle

Minor actinide (g/T)

U235 + U238

U235 +Th232

U233+ U238

U233 +Th232

Np 900 107 13 3

Am 470 0.28 117 0.0018

Cm 220 0.14 132 0.00064

Production of minor actinides in U and Th fuel cycle in g/t of heavy metals at 60 GWD/t

MA production in U233-Th232 cycle is few orders lower!

Neutronic characteristics of fissile and fertile nuclides

• Larger thermal capture cross-section of thorium leading to lower losses due to structural and other parasitic captures – Improved conversion of Th232 to U233

• Constant η value (> 2.0) over a wide energy range – Higher conversion ratios with thorium utilisation in reactors operating in

the thermal/epithermal spectrum.

0

1

2

3

4

5

6

7

8

U238

Th232

Therm

al C

aptu

re

cro

ss s

ection (

barn

)

1eV 100eV 10keV 1MeV0

1

2

3

4

U235

U233

Pu239

Num

ber

of neutr

ons

rele

ase

d

per

neutr

on a

bso

rbed, [

]

Neutron energy

Thorium acts as a burnable poison in initial stages while contributes towards additional reactivity through U233 formation at a later stage- “fissible” poison

Thorium: Radioactive waste formation

• Capture cross section of U233 is much smaller than U235 and Pu239, but the fission cross section is of the same order

– Lower non-fissile absorption

– Feasibility of multiple recycling of U233, as compared to plutonium.

By virtue of being lower in the periodic table than uranium, the long-lived minor actinides resulting from burnup are in much lower quantity with the thorium cycle.

0

2

4

6

8

10

12R

atio

of fissio

n a

nd

ca

ptu

re

cro

ss s

ectio

ns (

f/

c)

U233 U235 Pu239

Thorium: Reduced formation of radioactive waste

Country Tons %

India 846,000 16

Turkey 744,000 14

Brazil 606,000 11

Australia 521,000 10

USA 434,000 8

Egypt 380,000 7

Norway 320,000 6

Venezuela 300,000 6

Canada 172,000 3

Russia 155,000 3

South Africa 148,000 3

China 100,000 2

Greenland 86,000 2

Finland 60,000 1

Sweden 50,000 1

Kazakhstan 50,000 1

Other countries 413,000 8

World total 5,385,000

OECD NEA & IAEA,

Uranium 2011:

Resources, Production

and Demand ("Red

Book"), using the lower

figures of any range

and omitting ‘unknown’

CIS estimate.

Uranium reserves are limited and also Thorium offers a

proliferation resistant fuel cycle

Produce Energy

Efficient use of Thorium resources

Transmutation of high level long-lived

radioactive waste

Incineration of Minor Actinides

India needs a system which

can…

ADS

Accelerator Driven Sub-critical Reactor System (ADS)

A new type of fission reactor, where

nuclear power (say, 500-1000 MWe)

can be generated in a neutron multiplying core (keff < 1.000 )

without the need of criticality.

But, ADS has to be driven by an

external neutron source and

hence it is inherently safe system

ACCELERATOR DRIVEN ENERGY AMPLIFIER

Target

Gain

G

Converter

th = 40 – 50%

Accelerator

d = 40 – 60%

(50%)

P (1-f)P

180 MW

30 mA, 1GeV, H+

30 MW

Gtarget = 20-40

f P

f =12-25%

60 MW

600 MW

240 MW (40%)

(25)%

Carlo Rubia et al

SCHEMATIC OF ACCELERATOR-DRIVEN SYSTEM

LINAC

ADS Energy generation using Thorium

Transmutation

Incineration

By Spallation process with GeV

energy protons striking on high Z

target.

Number of neutrons per proton

per Watt of beam 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

Pth (MW) I (mA)

k=0.95

1000 29.2

1500 43.9

2000 58.5

2500 73.1

3000 87.7

Proton Energy : 1 GeV νs = 25 neutrons/proton ν = 2.5 neutrons/fission

I (mA)

k=0.98

10.2

15.3

20.4

25.5

30.6

Beam current requirement

Power required

keff=0.95, i=33.7mA

keff=0.99

i=6.5mA

To meet a constraint of a 10 MW proton accelerator we need keff>0.985

21

Role of ADS in Indian nuclear power systems

• For sustainable thorium-based fuel cycle by introducing non-fission neutrons in the neutron inventory.

• For cleaner nuclear power from thorium that generates reduced minor actinides waste in the spent fuel.

• A safer way to incinerate minor actinides from spent U-Pu fuel system of stages-1 & 2 of the 3-stage nuclear power programme.

JAPAN

KOREA

ITALY

CHINA

BELGIUM

FRANCE

GERMANY

RUSSIA

USA

Under its OMEGA (Option Making Extra Gains of Actinides and FP), that is

extension of its earlier Actinides Burner Reactor (ABR).

Under its HYPER (Hybrid Power Extraction Reactor) programme.

Under its TRASCO (TRAnsmutazion SCOrie) Programme and, Industrial project

undertaken by ANSALDO for EC.

Proposed as CIAE+IHEP project but under an un-named ADS programme of

Sino-Italian collaboration.

Under MYRRHA project as extension of ADONIS (Accelerator-Driven Operated

New Irradiation System) programme for radioisotope production.

Its CNRS/IN2P3 institutes are spearheading waste incineration R&D with spinoff

of its TRISPAL activities for accelerator to ADS.

Activities under FZK in the yet un-named programme.

Undertaken several study projects in ITEP/ISTC against the EC/US funding.

Earlier as ATW. Now AAA (Advanced Accelerator Applications) aiming for having

ADTF in 10 years from 2001. Full technological Demo in next 10 years.

Some of the ADS Projects around the world

Reactor

• Subcritical or Critical modes

• 65 to 100 MWth

Accelerator

(600 MeV - 4 mA proton)

Fast

Neutron

Source

Spallation Source

Lead-Bismuth

coolant

Multipurpose

Flexible

Irradiation

Facility

MYRRHA - Accelerator Driven System

MYRRHA Accelerator Challenge

fundamental parameters (ADS)

particle p

beam energy 600 MeV

beam current 4 mA

mode CW

MTBF > 250 h

implementation

superconducting linac

frequency 176.1 / 352.2 / 704.4 MHz

reliability = redundancy double injector

“fault tolerant” scheme 24

failure = beam trip > 3 s

MEGAPIE (SINQ Facility, PSI) CYCLOTRON-DRIVEN

Ran successfully for 4 months in 2006

700 kW, CW, liquid Pb-Bi

First Pb-Bi spallation target

‘Makes future licensing simpler’

JAPAN: Subcritical Reactor Studies- FFAG-DRIVEN

Y.Ishi et al., ‘PRESENT STATUS AND FUTURE OF FFAGS AT KURRI

AND THE FIRST ADSR EXPERIMENT’, IPAC’10

Also RACE

and TRIGA/TRADE planned experiments, e.g. Gabrieli, D’Angelo, Nucl. Eng. Design, 239, 2349 (2009)

Accelerator Requirements Proton Energy ~ 1 GeV gives >20 spallation

neutrons per proton. For 1GW thermal power: • Need 3 1019 fissions/sec (200 MeV/fission) • 6 1017 spallation neutrons/sec (k=0.98

gives 50 fissions/neutron) • 3 1016 protons/sec Current 5 mA. Power = 5 MW Reliable! Spallation target runs hot. If beam

stops, target cools and stresses and cracks: no more than 3 trips per year – but this is a controversial number

Compare: PSI cyclotron: 590 MeV, 2mA, 1MW ISIS synchrotron: 800 MeV, 0.2mA, 0.1 MW Several trips per day

C. Bungau et al., PAC’09

Proton & Heavy Ions

6 MV Folded Tandem Ion Accelerator (BARC, Mumbai)

14 MV Pelletron + SC Linac booster ( BARC/TIFR, Mumbai)

K=130 Room temp cyclotron ( VECC)

K= 500 Superconducting Cyclotron at Kolkata,VECC -under commissioning

3 MV Tandetron at Hyderabad

3 MV Pelletron at IOP, Bhuvaneshwar

1.7 MV accelerator at IGCAR, Kalpakkam

16.5 MeV Medical Cyclotron at RMC, Mumbai

Electron

450 MeV INDUS-I (SRS at RRCAT, Indore)

2.5 GeV INDUS-II ( SRS at RRCAT, Indore)- 24X7 operation.

10 MeV, 10 kW Linac at Mumbai for industrial application (BARC, Mumbai)

3 MeV DC accelerator at EBC (under commissioning)

10 MeV Electron Linac at RRCAT (Agriculture)

7 MeV Electron accelerator ( BARC, Mumbai)

2 MeV Electron Linac (ILU-6) at Mumbai- industrial applications

750 keV Electron DC accelerator at RRCAT

500 keV Electron DC accelerator at Vashi

Projects

1 GeV, 30 mA Linac – ADS

1 GeV pulsed accelerator- SNS

6 GeV Advanced Synchrotron Facility

Hadron facility for Cancer therapy- TMC

Radioactive Ion Beam (ANURIB)- VECC

Accelerators in DAE

Proton IS 50 keV

RFQ 3 MeV

DTL 20 MeV

DTL/ CCDTL

Super- conducting

SC Linac

1 GeV

200 MeV

Normal Conducting

High current injector 20 MeV, 30 mA

Scheme for Accelerator Development for ADS

Design completed & fabrication is in progress

ECR Ion Source LEBT RFQ Drift Tube Linac

60 kW RF System 1.3 MW Klystron

Phase 1

Phase II

Phase III LEHIPA

50 kW RF Coupler

RRCAT pulsed

BARC CW

1 GeV

Project X

CW upto 3 GeV

LEBT

MEBT Elliptical

Cavities

200 MeV 1 GeV

IS RFQ HWR,

SSR

50 keV 3 MeV 150 MeV

Elliptical Cavities

Scheme for the 1 GeV High Intensity

Superconducting Proton Accelerator (HISPA) Frequency: 325 and 650 MHz

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

33

20 MeV Proton beam for ADS

experiments in HWR critical facility

Linac tunnel in

basement

Beam transport

line thru’

basement

Ground level

beam transport

gallery- with

shielding

HWR critical

facility building

Studies have

confirmed feasibility

of extending 20 MeV

proton beam to a

target in the core of

nearby HWR critical

facility.

Five electrodes

2.45 GHz

50 keV

50 mA

0.02 cm-mrad

ECR Ion Source P. Roychowdhary et al, APPD, BARC

Schematic of the ECR Ion Source

Ion source with 3 electrode extraction system made & Testing is in

progress ( 30 mA, 80% H+ , Emittance: 0.019 pi cm. mrad )

3 MeV RFQ under fabrication at BATL

- 4 segments ( 1 m each)

Tuners 64 tuners --- 16 per quadrant,

symmetrically placed in each

quadrant.

Static tuners.

Cooling required.

Tuning Range : 468.5 kHz/mm (all)

24 vacuum ports

Frequency detuning :

745.86 kHz (all)

Vacuum ports

Coupling cell

Solenoid 2 Solenoid 1

Faraday cup

BPM 2 BPM 1

Design, development and characterization of LEBT systems

He++, D+ and H+ beams were extracted.

LEHIPA LEBT and its

components have been

designed and fabricated.

It is ready for assembly.

y = 0.1816x2 - 0.9843x + 10.462

R2 = 0.8934

9

9.2

9.4

9.6

9.8

10

10.2

10.4

10.6

10.8

11

0 1 2 3 4 5 6

Q

sig

ma^2

•Slit scan method

2'2'2 xxxxx

LEBT Test bench

•Solenoid scan method Emittance Measurement was done

LEHIPA LEBT

RFQ: a) Focusing, b) bunching and c) Acceleration

RFQ Testing

Pulse width= 5 msec

Pulse Period= 1 sec

1 sec

5 msec

Facility for carrying out experiments on physics of ADS and for

testing the simulations is being set up. This will use 14 MeV neutrons

produced through D+T reaction.

Simple sub-critical assembly (keff=0.87) of natural uranium is chosen

Measurements of flux distribution, flux spectra, total fission power,

source multiplication, and degree of sub-criticality will be carried out.

For this purpose a 400 keV RFQ is being built .

Presently a 400 keV DC accelerator is used

Experimental facility

For deuteron current of 1mA at 400 keV,

14 MeV neutron yield is 1.0x 1011 n/s

D+T reaction

High Voltage

Power Supply

Ion

source

Dome Accelerating

Tube

Beam Steerer

BPM Faraday

Cup

Turbo

Molecular

Pump

14 MeV Neutron Generator (D+T)

Sub-critical facility for ADS Experiments, D+D and D+T , keff= 0.87

Reflector: BeO, Moderator: High Density Polyethylene.

Neutron Multiplication measured ( A. Sinha et al.)

BRAHMMA - “BeO Reflected And HDPE Moderated Multiplying Assembly

0

0.5

1

1.5

2

2.5

3

3.5

0 200 400 600 800 1000

30 mA

20 mA

10 mA

Hal

o p

aram

eter

Beam Energy (MeV)

Evolution of Beam Halo with 10%

mismatch in x, y and z for different

beam currents

Challenges in ADS accelerator design

Accelerators for ADS applications

•Require proton beam energy in the ~GeV range and operating with 10’s of mA beam

current

•Beam loss has to be limited to < 1 watt/m

•Require careful beam dynamics optimization to minimize the formation of beam halos

for a high current beam that could lead to beam loss and activation of the structure.

•Are required to operate in the CW mode making the thermal management of normal

conducting cavities difficult.

•Are required to be very reliable since they will be used for power production.

At present there is no such

accelerator operating in the

world!!

Beam loss produces activation that makes

maintenance difficult and time-consuming.

Control of beam halo formation and beam loss is a

fundamental requirement for high beam availability in

high-power proton linacs.

Beam mismatch is a major source of halo.

Mismatched beams evolve to a final equilibrium state with accompanying

growth of halo and emittance.

Beams are mismatched when focusing and defocusing forces (space charge

and emittance) are unbalanced, resulting in coherent rms oscillations.

Mismatched beam develops larger amplitudes than matched beam.

Maximum halo extent

0

1

2

3

4

5

6

-7.00 -5.00 -3.00 -1.00 1.00 3.00 5.00 7.00

matched

Quadrupole mode

Fast mode

Slow mode

X RMS size

log

(no

. of

par

ticl

es)

0

0.5

1

1.5

2

2.5

3

3.5

4

4.5

5

-6.00 -4.00 -2.00 0.00 2.00 4.00 6.00

matched

Quadrupole mode

Fast mode

Slow mode

log

(no

. of

par

ticl

es)

X RMS size

0

0.5

1

1.5

2

2.5

3

3.5

4

4.5

5

-6.00 -4.00 -2.00 0.00 2.00 4.00

matched

Quadrupole mode

Fast mode

Slow mode

X RMS size

log

(no

. of

par

ticl

es)

Output beam distribution for 30 % -30 % 30 % mismatch 10 mA 20 mA

30 mA 40 mA

Output beam distribution for a general mismatch

0

1

2

3

4

5

6

-8.00 -6.00 -4.00 -2.00 0.00 2.00 4.00

matched

10 % mismatch

20 % mismatch

30 % mismatch

40 % mismatch

log

(no

. of

par

ticl

es)

X RMS size

z

0

0.5

1

1.5

2

2.5

3

3.5

4

4.5

5

1.00 1.50 2.00 2.50 3.00 3.50

matched

10 % mismatch

20 % mismatch

30 % mismatch

40 % mismatch

X RMS size

log

(no

. of

par

ticl

es)

0

0.5

1

1.5

2

2.5

3

3.5

4

4.5

5

1.00 1.50 2.00 2.50 3.00 3.50

matched

10 % mismatch

20 % mismatch

30 % mismatch

40 % mismatch

X RMS size

log

(no

. of

par

ticl

es)

y x

Halo parameter for 30 % -30% 30% mismatch for different currents

10 mA 20 mA

30 mA 40 mA

Related Activities in Indian labs • Accelerator physics

• Spoke resonators

• Superconducting cavities

• Helium vessels and tuners for SCRF cavities.

• Vertical and Horizontal Test Stands.

• Cryomodules for SCRF cavities.

• High power solid state RF amplifiers.

• Infrastructure for SCRF cavity fabrication, processing and testing.

• LLRF system, RF protection system and related instrumentation.

• Beam diagnostics, monitoring and protecting systems

• Cryomodule test stand (CMTS)

Work in progress in all the areas

Spallation target R&D at BARC ( P. Satyamurthy et al. )

• Computational codes development and nuclear data for spallation reaction analysis in the target.

• Thermal hydraulics computational tools development for LBE target simulations.

• Experimental loops for validation of thermal hydraulics codes and corrosion studies on window materials.

Possible Liquid

Targets

Elemen

t

Atomi

c

Mass

(A)

Atomic

Numbe

r (Z)

A/Z

Melting

Temper

ature

(0C)

Boiling

Temper

ature

(0C)

Densi

ty at

room

Temp

(g/cc)

Pb

207

82

2.52

4

327

1725

11.36

Bi

209

83

2.51

8

271

1560

9.80

LBE

~208

~82.5

~2.5

2

125

Similar

to

Pb/Bi

~10.0

Hg

200

79

2.53

2

-38.36

357

13.54

U

238

92

2.59

0

1132.3

3818

19.07

Ta

181

73

2.47

9

2996

5425

16.6

W

184

74

2.48

6

3410

5930

19.3

Hg is not

suitable due to

low boiling

temp. for

reactors

LBE has been

identified as

best target

material

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)

LBE Corrosion Loop

Height ~ 7m

Flow Rate ~1.7 kg/s

Temp: 5500C and 4500C

Velocity in the Samples~0.6 m/s

Corrosion Tests: Charpy and Tensile

after 3000 hrs in the flow

(R Fotedar, S.V. Phatnis, Chintamani Das, A.K. Grover, A.K. Suri)

-Utilization of Thorium

-Inherent safety

-Transmutation of Nuclear Waste

Spallation

target; liquid

Lead-Bismuth

Coolant-Na,Pb,

Pb+Bi (Fast

Reactor)

Coolant –Light

Water and Heavy

Water (Thermal

reactors) Breeding 232Th 233U; 238U 239Pu

Target

Module

-Very High Heat Deposition Density by proton

beam ~ few kW/cm3

-Very High Radiation Damage ~100 DPA or

more/year Embrittlement

Irradiation Creep

Void Swelling

Hydrogen Generation

Helium Generation

Transmutation

Solution for both these issues – Use

circulating liquid target

LBE Target Module

CYCLOTRON

VAULT

Target section

Indian ADS Target Programme

Target Experiments - Coupling With Cyclotron Proton Beam 30 MeV and

500 µA (CW) Neutrons generated: 4.12 X 10^13

-Coupling of Beam with

Target Module

-Window heat extraction

-Radioactivity Issues

-Gas handling

-Irradiation studies

-Combined Control &

Instrumentation

-Remote Operation

-Remote Dismantling

Status: Civil works in progress

Beam line procurement in

progress

Prototype target under

installation

Simulates 1Gev, ~3mA Proton

Window Heating

• One way coupled fast and thermal subcritical reactor with spallation neutron source in centre • Inner core is subcritical fast reactor with thermal neutron absorber liner surrounded by gap • Outer core is subcritical thermal reactor, neutrons leaking from inner core can come here and get multiplied. • Neutron from thermal reactor cannot go to inner core due to absorber liner, that is why it is one way coupled

• Desired keff can be obtained, reduction in proton beam power

R&D on ADS in BARC

S.B. Degweker et al. Ann.

Nucl. Energy 26, 123 (1999).

ADS concepts: One way coupled ADS • Power in ADS is inversely proportional to

sub-criticality and directly proportional to neutron source strength

• In the control rod free concept, the operating keff is limited to the range 0.95-0.98

• This requires accelerator beam power of about 10 MW

• The one-way coupled booster-reactor concept can reduce this requirement five fold

– Inner fast core with source at centre boosts the neutron source

– These neutrons leak into the outer thermal (PHWR/AHWR) core where they undergo further multiplication

– This cascade multplication gives very high energy gain

– Due to the absorber lining and the gap very few neutrons return to the booster – i.e. there is a one way-coupling between the two

– The one-way coupling ensures that the overall keff is limited to the desired value

– Consequently, accelerator power requirement for 750 MW(t) is ~ 1-2 MW

• Similar ideas have been studied in Russia

Technological difficulties in use of Thorium

The daughter products have short half-lives and two of these, Bi212 and Tl208, emit strong gamma rays

Fuel fabrication and reprocessing will need shielding and remote access Commercial scale THOREX process for reprocessing may need more development

U233 + n1 U232 + 2 n1 , Pa231 +n1 Pa232 U232

β-

Thorium based fuel cycles are technologically less matured than uranium / plutonium cycles

Thorium based fuel cycles have formation of U232.

Summary

We have large quantity of Thorium – ADS is a suitable option for its utilization (fuel

fabrication).

ADS consists of High Intensity Accelerator, Spallation target and Sub-critical reactor

(how close one can go).

Design and development of high current, high energy proton linacs ( space charge,

beam halo, resonances etc)

Small beam loss needed ( < 1 nA/m) - hands on maintenance

Spallation target-work is in progress (removal of heat, radioactivity, LBE option)

Characterisation of prototype LBE loop

A sub-critical assembly has been built and testing in progress

One way coupled system reduces the current – welcomed ( have to handle 2 cores)

International collaborative efforts needed to see ADS a reality.

Acknowledgements

We thank all the members of IADD, BARC

P. Satyamurthy, BARC

S.B. Degwekar, BARC

H P Gupta, BARC

for inputs

Several institutes of DAE are contributing towards Indian

ADS program. IUAC actively involved in cavity

development- Thanks to them.

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

Solid State RF amplifier 3 kW, 325 MHz Unit

Design and Development of Focusing lenses for MEBT

S. no Type Qty. Integrated Gradient / integrated field

Field homogeneity in GFR of 23 mm

Longitudinal space

1 Quadrupole F (QF) 18 1.5 T 1% 100mm

2 Quadrupole D (QD) 16 0.85 T 1% 50mm

3 H/V Dipole corrector(DC) 15 2.1 mT*m 5% 55mm

Table1: Deliverables for PXIE MEBT/HEBT transverse focusing lattice with their optics requirements

Stages of Development work at BARC:

1. Electromagnetic design of Quadrupole

Focussing Magnets and dipole correctors

2. Engineering design

3. Development drawings

4. Fabrication and Geometrical inspection

5. Magnetic measurements (integral fields)

6. Quality checks and traveller

7. Qualification tests with H+ beam at 2.5 MeV

Current Status:

-A prototype of Quad F and dipole corrector

has been developed and qualified for its magnetic, electric, thermal design & for beam focusing.

- The prototype magnets have been shipped to Fermilab for detailed magnetic measurements and

integration with PXIE beam line. Fabrication of triplet and doublet frames with Dipole corrector

has been initiated at BARC.

Sr. no Beam Parameter Value

1. Beam H+

2. Beam energy 2.5 MeV

3. Beam Current 10nA

4. Beam size 3 mm

5. Target distance 1 meter

Qualification of dipole correctors with proton beam at FOTIA facility, BARC

Particle trajectory simulations

Dipole corrector magnet assembly installed in FOTIA beam line Steering of beam - analytical vs. measured

Wedge Tuner Installed for Testing at FNAL

66

Wedge Tuner A Double Wedge Tuner (DWT) has

been designed and developed for

compensation of Lorentz force

detuning and micro phonics

stabilization of the superconducting

RF cavities. This is a co-axial device

and can provide both the slow

structure tuning and the fast tuning

capabilities.

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 =

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.

)1(

)/1(

1

11

k

kk

2112 kkk

but, = k1 or k2 whichever is larger.

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

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)