ACTIVITIES ON ADS AT JAEA
Hiroyuki Oigawa
Nuclear Transmutation Technology Group
Nuclear Science and Engineering Directorate
Japan Atomic Energy Agency

September 26-28, 2006

OECD/NEA 9th Information Exchange Meeting on P&T

1

Contents
1.
2.
3.
4.
5.
6.
7.

New Structure for ADS Development at JAEA
Scenario Study
Conceptual Design
Engineering Feasibility
Reliability
Cost
Current Status of J-PARC Project Part of this work was entrusted by the Ministry of Education, Culture,
Sports, Science and Technology (MEXT).
September 26-28, 2006

OECD/NEA 9th Information Exchange Meeting on P&T

2

New Structure for ADS Development at JAEA:
Midterm Plan
Description in “Midterm Plan” of JAEA
Partitioning¾New Extractant, Process Design, Laboratory Demonstration, ….
Transmutation¾General• Nuclear Data and Reactor Physics• Material Properties of MA and LLFP
¾FBR• Design, Fuel Irradiation, ….
¾ADS• Design• Accelerator• Spallation Target (Material, Thermal-hydraulics)• Lead-Bismuth Eutectic (LBE) Technology (Corrosion, Po Behavior,..)• Dedicated MA Fuel
Scenario Study
Benefit of P&T on HLW Management
September 26-28, 2006

OECD/NEA 9th Information Exchange Meeting on P&T

3

New Structure for ADS Development at JAEA:
Directorates Concerning R&D on ADS
Nuclear
Nuclear Science
Science andand Engineering
Engineering Directorate
Directorate•• Director
Director General:
General: O.
O. Oyamada
Oyamada•• Deputy
Deputy Director
Director General:
General: T.
T. Ogawa
Ogawa

ResearchResearch Co-ordination
Co-ordination
andand Promotion
Promotion Office
Office¾¾ Division
Division ofof Nuclear
Nuclear Data
Data andand Reactor
Reactor Engineering
Engineering

R&D on ADS¾¾ Division
Division ofof Fuels
Fuels andand Materials
Materials Engineering
Engineering

R&D on ADS fuel andmaterials¾¾ Division
Division ofof Environment
Environment andand Radiation
Radiation Sciences
Sciences¾¾ Nuclear
Nuclear Applied
Applied Heat
Heat Technology
Technology Division
Division
Quantum
Quantum Beam
Beam Science
Science Directorate
Directorate¾¾ Proton
Proton Accelerator
Accelerator Facility
Facility Development
Development Unit
Unit
J-PARC
J-PARC Center
CenterOperation and maintenance of J-PARC

Advanced
Advanced Nuclear
Nuclear System
SystemResearchResearch andand Development
Development Directorate
Directorate
September 26-28, 2006

Development of J-PARC
accelerators and facilities

R&D on FBR cycle

OECD/NEA 9th Information Exchange Meeting on P&T

4

Scenario Study:
Characteristics of ADS and Possible Scenarios Two
Two significant
significant advantages
advantages ofof thethe dedicateddedicated transmutationtransmutation strategy:
strategy:(1)(1) ItIt can
can accommodate
accommodate various
various situations
situations ofof thethe commercial
commercial power
power
generation
generation fuelfuel cycle
cycle inin an
an appropriate
appropriate andand flexible
flexible manner.
manner.
------- Suitable
Suitable toto thethe transienttransient phase
phase fromfrom LWR
LWR toto FBR.
FBR.
(2)(2) MAMA cancan bebe confined
confined into
into aa small-scale
small-scale dedicateddedicated fuelfuel cycle.
cycle.
------- Helpful
Helpful forfor thethe deployment
deployment ofof thethe FBR.
FBR.
 Taking
Taking these
these advantages
advantages into
into account,account, three
three typical
typical situations
situations ofof nuclear
nuclear fuel
fuel
cycle
cycle with
with thethe dedicateddedicated transmutationtransmutation systemsystem cancan bebe assumed:
assumed:a.
a. LWR
LWR –– ADSADSb.
b. LWR
LWR –– FBRFBR –– ADS
ADS
c.
c. FBRFBR –– ADS
ADS

 In
In thisthis scenario
scenario study,
study, thethe total
total capacity
capacity ofof thethe nuclear
nuclear power
power generation
generation isis fixed
fixed
at
at 58
58 GWeGWe forfor all
all thethe situations.
situations.

September 26-28, 2006

OECD/NEA 9th Information Exchange Meeting on P&T

5

Scenario Study:
a. LWR–ADS

“Pseudo Equilibrium State” with UO2-LWR + MOX-LWR (58GWe)
Nat.U

UO2 fuel

LWR

7600t/y

960t/y49GWe

Reprocessing
960t/yPu

MOX fuel

MOX-LWR

8.2t/y180t/y9GWe

MA

MA-fuelADS

Reprocessing

1.1t/y9t/y800MWth X 4.4

9t/y

Storage

Cycle scale: 1/100

 MA
MA cancan bebe managed
managed inin aa very
very small
small dedicateddedicated fuelfuel cycle.
cycle.
 Pu
Pu will
will bebe stored
stored asas MOX
MOX spent
spent fuelfuel andand thenthen used
used asas FBRFBR fuel.
fuel.

September 26-28, 2006

OECD/NEA 9th Information Exchange Meeting on P&T

6

Scenario Study:b. Transient from LWR to FBR“Transient Phase” with UO2-LWR + MOX-FBR (58GWe)
Nat.U

UO2 fuel

LWR

7600(1-α)t/y1160(1-α)t/y58(1-α)GWe

Reprocessing
1160(1-α)t/y

α: Ratio of FBR deployment

Pu

MOX-LWR13(1-α)t/y

Spent fuel

MOX fuel

FBR

Reprocessing

Core: 310αt/yBlanket: 180αt/y

58αGWeBreeding Ratio=1.1

Core: 310αt/yBlanket: 180αt/yMAMA-fuelADS

Reprocessing[1.3+0.13α] t/y[10.4+α] t/y

800MWth X (5.2+0.5α)[10.4+α] t/yαSize of LWR fuelreprocessing

0.2
0.5
0.8

930t/y580t/y230t/ySize ofFBR cycle
98t/y250t/y390t/ySize ofADS cycle
10.6t/y10.9t/y11.2t/yU, Pu,
Np

Number of ADS
5.3
5.5
5.6


 SizeSize ofof ADSADS cycle
cycle will
will notnot bebe affectedaffected byby thethe situation
situation ofof LWRLWR andand FBR
FBR cycles.
cycles.
September 26-28, 2006

OECD/NEA 9th Information Exchange Meeting on P&T

7

Scenario Study:c. FBR with ADS“Symbiotic State” with FBR (58GWe) :

Nat.U
50t/y

MOX fuel

FBR

Reprocessing

Core: 310t/y
Blanket: 100t/y

58GWe
Breeding Ratio=1.03

Core: 310t/y
Blanket: 100t/y

Am,Cm

MA-fuelADS

Reprocessing

1.6t/y13t/y800MWth X6.5

13t/yU, Pu,
Np

Cycle scale: 1/30


 FBR
FBR andand ADSADS co-exist
co-exist symbiotically
symbiotically andand complementarily.
complementarily.
 By
By adopting
adopting ADS
ADS andand its
its dedicateddedicated transmutationtransmutation cycle,
cycle, MA
MA cancan bebe confined
confinedandand FBR
FBR cycle
cycle cancan bebe optimized
optimized fromfrom viewpoints
viewpoints ofof reliability,
reliability, safety
safety andandeconomy.
economy.
 The
The scalescale ofof ADSADS cycle
cycle isis about
about 1/30
1/30 ofof thethe commercial
commercial FBRFBR cycle.
cycle.
 The
The mass
mass flow
flow ofof thethe cycle
cycle will
will bebe about
about 13
13 t/y,t/y, which
which means
means about
about 50
50 kg/daykg/day ofofMA
MA fuelfuel will
will bebe enoughenough to
to be
be fabricated.
fabricated.
September 26-28, 2006

OECD/NEA 9th Information Exchange Meeting on P&T

8

Conceptual Design:
Reference ADS•• Proton
Proton beam
beam :: 1.5GeV
1.5GeV•• Spallation
Spallation target
target :: Pb-Bi
Pb-Bi•• Coolant
Coolant :: Pb-Bi
Pb-Bi•• Max.
= 0.97Max. kkeff
eff = 0.97•• Thermal
Thermal output
output :: 800MWt
800MWt•• MA
MA initial
initial inventory
inventory :: 2.5t
2.5t•• FuelFuel composition
composition ::(MA(MA +Pu)Nitride+Pu)Nitride ++ ZrN
ZrN
Initial
Initial loading:loading:
Zone-1:
Zone-1: Pu/HM=30.0%
Pu/HM=30.0%
Zone-2:
Zone-2: Pu/HM=48.5%
Pu/HM=48.5%•• Transmutation
Transmutation rate
rate ::
10%MA
10%MA // YearYear•• 600EFPD,
600EFPD, 11 batch
batch

Steam generator

Proton beamPrimary pump

Inner barrel
Beam duct
Beam window
Reactor vesselCore barrel
13.5m
Guard vesselCore support
structure

11.8m
September 26-28, 2006

OECD/NEA 9th Information Exchange Meeting on P&T

9

Engineering Feasibility:
Spallation Target and Beam Window
30
30 MW
MW proton
proton beam
beam with
with 1.5
1.5 GeV
GeV
causescauses heat
heat deposition
deposition ofof 15.7MW.
15.7MW.
Conditions
Conditions andand criteria
criteria forfor thethe beambeam
window:window:
9
9 Inlet
Inlet temp.
temp. :: 300
300 ºCºC
99 LBE
LBE flow:
flow: << 2m/s
2m/s
99 Temp.
Temp. ofof outerouter surface:surface: << 520ºC
520ºC
99 Structural
Structural strength:
strength:
ThermalThermal stress,
stress, buckling,buckling, etc.
etc.
The
The feasibility
feasibility ofof thethe beam
beam window
window was
wasverifiedverified under
under thethe nominal
nominal operation
operation
conditions,conditions, but
but thethe effecteffect ofof corrosion,
corrosion,
irradiation
irradiation andand fabrication
fabrication accuracy
accuracy
shouldshould be
be discussed.
discussed.
We
We should
should accumulate
accumulate experience
experience onon
LBE
LBE spallation
spallation target.
target.
September 26-28, 2006

Beam duct support
Proton beam
Beam duct
Beam window
Core barrelCore region
Reflector
Target region
Partition wall
Flow control nozzle

Coolant flow

Support structure

OECD/NEA 9th Information Exchange Meeting on P&T

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Engineering Feasibility:
Tensile Test of Irradiated Materials
JPCA-SA/250℃
1000

JPCA-SA, this study

AS24, Unirr.
F12, 140-170℃, 5.7dpa
800

700

316F-SA ,this study
304L-SA [LANSCE]

F7, 210-250℃, 7.9dpa
600

F10, 276-325℃, 10.1dpa

316L-SA [LANSCE]
EC316LN-SA [LANSCE]

500

600

ΔYS, MPaSt ress,MPa

Tirr., Ttest≦ 250℃

800

400

400
300
200

200

Neutronirradiation

100

0
0

10

20

30

Strain,%

40

50

60

0

0.01

0.1

1

10

dpa

The
The increase
increase in
in YS
YS of
of irradiatedirradiated specimens
specimens is
is within
within thethe fission
fission neutron
neutron irradiatedirradiateddata
data band
band at
at lower
lower dose.
dose. AtAt higher
higher dose,dose, thethe increase
increase in
in YS
YS of
of JPCA-SA
JPCA-SA shows
shows aatendency
tendency toto exceed
exceed thethe upper
upper boundbound thethe fission
fission neutron
neutron irradiatedirradiated data
data band.
band.
September 26-28, 2006

OECD/NEA 9th Information Exchange Meeting on P&T

11

Engineering Feasibility:
Fatigue Test of Irradiated Materials
 Bend fatigue tests for SINQ irradiated specimens
10000

Load cells

Lever arm

Eddy-current typedisplacement
meter

Auxiliary
specimen holderSpecimen

JPCA,unirr. "F"
JPCA,Irr.

Total strain range

Piezoelectric actuator

X10-6

F26(6.5dpa)
1000

104

Specimen holder

F24(9.1dpa) F27(6.5dpa)

105

106

107

108

Number of cycles to failure

No
No or
or little
little changechange ofof thethe fatigue
fatigue life
life waswasobserved
observed forfor thethe irradiatedirradiated JPCA-SA
JPCA-SA andand 316F316FSASA specimens.
specimens.
September 26-28, 2006

OECD/NEA 9th Information Exchange Meeting on P&T

12

Engineering Feasibility:
Reduction of Power Peaking

September 26-28, 2006

500

400
Power density (W/cm3)

ItIt isis important
important toto reduce
reduce thethe power
power
peakingpeaking factor
factor throughout
throughout thethe wholewholeburn-upburn-up stage.
stage.
Power
Power peaking
peaking will
will bebe thethe highest
highest at
at
EOC
EOC ofof thethe 2nd.
2nd. cycle.
cycle.
Two-zone
Two-zone core
core isis adopted
adopted toto reduce
reducepower
power peaking.
peaking.
The
The hot
hot spot
spot pin
pin will
will bebe about
about 600
600ooCCat
at EOCEOC ofof thethe 2nd.
2nd. cycle.
cycle.
Efforts
Efforts toto reduce
reduce this
this temperaturetemperatureo
below
below 550
550oC
C are
are being
being continued:
continued:¾More¾More detailed
detailed zoning
zoning¾Adjustment¾Adjustment ofof inert
inert matrix
matrix (ZrN)(ZrN) atat
every
every burnup
burnup stage
stage¾Adoption¾Adoption ofof partial
partial heightheight fuelfuel
¾Adoption¾Adoption ofof reactivity
reactivity adjustment
adjustment
rods,
rods, etc.
etc.

300

200

BOC of initial cycle
100

EOC of 2nd. cycle

0
20

40

60

80

100

120

Radial distance from core center (cm)Power density of two-zone core(axial position: center)OECD/NEA 9th Information Exchange Meeting on P&T

13

Engineering Feasibility:
Static Test – Low Oxygen Concentration
SX(18Cr-19Ni-5Si)
316SS
Pure iron
2.25Cr-1Mo

550 ºC , O2: 3x10-9wt%, 3000h

430SS

316SS

100µm

410SS

316SS shows deep
corrosion

JPCA(14Cr-16Ni-2Mo)
Mod.9Cr-1Mo
F82H(8Cr-2W)
0.00

0.20

0.40

0.60

0.80

1.00

1.20

2.25Cr-1Mo steel shows
grain boundary corrosion

Corrosion Depth (mm/y)Corrosion depth（mm/y）

Oxide

2.25Cr-1Mo
September 26-28, 2006

20µm

Grain boundary corrosion

OECD/NEA 9th Information Exchange Meeting on P&T

14

Engineering Feasibility:
Uncertainty Estimation for Neutronics Design
Np-237 Capture

Np-237 Capturekeff

Np-237 Fission
Np-237 ν

Np-237 Fission
Np-237 ν

Np-237 Capture

Pb-Bi
Void
Reactivity

Pu-238 Capture
Pu-239 Capture
Pu-239 Fission

Pu-239 Fission

Pu-239 Fission

Am-241 Capture

Am-241 Capture

Am-241 Fission

Am-241 Fission

Am-241 ν

Am-241 ν

Am-243 Capture

Am-243 Capture

N-15 Elastic Scattering

N-15 Elastic Scattering

Zr -91Elastic Scattering

Fe Inelastic Scattering

Fe Inelastic Scattering

Zr Inelastic Scattering

Pb Inelastic Scattering

Pb Inelastic Scattering

Bi Inelastic Scattering

Bi Inelastic Scattering

OthersOthersOthers

Total

Total

Total

0.0

0.2 0.4 0.6 0.8
Uncertainty (1σ) (%)

1.0

0.0

Δkeff

Am-241 Capture
Am-242m Fission
Am-243 Capture
Cm-244 Capture
N-15 Elastic Scattering
Zr Elastic Scattering
Zr Inelastic Scattering
Fe Inelastic Scattering
Pb Inelastic Scattering
Bi Inelastic Scattering

1.0 2.0 3.0 4.0
Uncertainty (1σ) (%)

5.0

0.0

5.0
10.0 15.0
Uncertainty (1σ) (%)

20.0

The
The reactor
reactor physics
physics parametersparameters areare veryvery influential
influential forfor thethe optimization
optimization ofof
core
core design.
design.
Uncertainty
Uncertainty ofof reactor
reactor physics
physics parametersparameters waswas estimatedestimated onon thethe basis
basis ofof thethesensitivity
sensitivity ofof nuclear
nuclear data
data andand thethe error
error files
files evaluatedevaluated forfor JENDL-3.3.
JENDL-3.3.
Largeand burnup reactivity.
Large uncertainty
uncertainty was
was foundfound inin kkeff
eff and burnup reactivity.
The
The capture
capture reaction
reaction ofof Am-241
Am-241 has
has significant
significant effect.
effect.
September 26-28, 2006

OECD/NEA 9th Information Exchange Meeting on P&T

15

Reliability:
Acceptable Beam Trip Frequency
ThermalThermal stressstress caused
caused byby beambeam trip
trip isis estimatedestimated to
to know
know acceptable
acceptable frequency
frequencyofof beambeam trip.
trip.
1.
1. BeamBeam window
window
2.
2. Inner
Inner barrel
barrel3.
3. Reactor
Reactor vessel
vesselThe
The influence
influence ofof thethe beam
beam trip
trip toto thethe power
power generation
generation systemsystem isis also
also estimated.
estimated.
SG

Pump

Inner barrel

H

H

Reactor vessel

InnerbarrelH

H
CC

Reactorvessel

C

Core
C

Beam
window

H :High temperature
C :Low temperatureA

Before beam trip
September 26-28, 2006

B
Several seconds
After beam trip

C
TransientD
Several minutes
after beam trip

OECD/NEA 9th Information Exchange Meeting on P&T

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Reliability:
Thermal Shock on Beam Window

September 26-28, 2006

600
500
o

Temperature ( C)Beam
Beam window
window ::450mm
450mmφφ,, 2mm
2mmtt,, 9Cr-1Mo
9Cr-1Mo steel,steel,
beam
beam power:
power: 30
30 MW
MW
Beam
Beam trip
trip will
will cause
cause max.
max. 179
179 MPa
MPa
thermalthermal stressstress 0.5
0.5 sec.
sec. after
after thethebeam
beam trip.
trip.
This
This thermal
thermal stressstress isis muchmuch lower
lower
than
than aa criteria
criteria toto prevent
prevent bucklingbuckling
failure.
failure.
The
The acceptable
acceptable number
number ofof thisthis5
thermalthermal shock
shock :: about
about 10105
SeveralSeveral beam
beam trips
trips perper anan hourhour isisacceptable
acceptable forfor 22 years
years (about(about15,00015,000 hours)
hours)
ItIt should
should be
be noted
noted thatthat this
thisestimation
estimation isis based
based onon thethe materialmaterial
data
data without
without radiation
radiation damage.
damage.

Restart400
300
Inner surface
Outer surface
Coolant
Temperature difference

200
100
0

max. 82oC
0

1

2

3
4
5
6
7
Time after beam trip (s)

8

9

10

Temperature of beam windowat beam trip transient

OECD/NEA 9th Information Exchange Meeting on P&T

17

Reliability:
Thermal Shock on Inner Barrel
Inner
Inner barrel
barrel :: 3cm
3cmtt,, 9Cr-1Mo
9Cr-1Mo steel
steel
Beam
Beam trip
trip will
will cause
cause max.
max. 130
130 MPa
MPa thermal
thermal stressstress 24
24 sec.
sec. after
after thethe beam
beam trip.
trip.
The
The stressstress range
range will
will bebe 260260 MPa
MPa considering
considering thethe following
following restart
restart transient.
transient.
The
The acceptable
acceptable number
number ofof thisthis thermal
thermal shock
shock :: about
about 101044
250
250 trips
trips perper yearyear isis acceptable
acceptable forfor 4040 years.
years.
150

450

100
Stress (N/mm2)oTemperature ( C)

Inner surface
Outer surface

400

350

50
2

max. 130N/mm at 24s

0

Inner surface
Outer surface

-50

-100

StressTemperature
-150

300
0

20

40

60

80

100

Time after beam trip (s)

120

0

20

40

60

80

100

120

Time after beam trip (s)Temperature and stress of inner barrel at beam trip transient
September 26-28, 2006

OECD/NEA 9th Information Exchange Meeting on P&T

18

Reliability:
Thermal Shock on Reactor Vessel
Reactor
Reactor vessel
vessel :: 5cm
5cmtt,, 9Cr-1Mo
9Cr-1Mo steel
steel
Temperature
Temperature difference
difference between
between inner
inner andand outerouter surface
surface will
will cause
cause 113
113 MPa
MPa
thermalthermal stressstress just
just before
before beam
beam restart
restart (400(400 s).
s).
Additionally,
Additionally, thethe formation
formation ofof thethe temperaturetemperature stratification
stratification andand thethe LBE
LBE level
level
lowering
lowering byby thermal
thermal shrinkage
shrinkage will
will also
also cause
cause 109
109 MPa.
MPa.
In
In total,
total, thethe stressstress range
range will
will bebe 270270 MPa
MPa considering
considering thethe following
following restart
restartThe
The acceptable
acceptable number
number ofof thisthis thermal
thermal shock
shock :: about
about 101044
250
250 trips
trips perper yearyear isis acceptable
acceptable forfor 4040 years.
years.
150

450

Stress (N/mm2)

350

300

Temperature

Inner surface temperature
Outer surface temperature

250

Stress of inner surface
Stress of outer surface

100

400

o

Temperature ( C)Beam restrat by full power (at 400s)

50
0
-50

Stress
-100

0

500

1000

1500

Time after beam trip (s)

0

500

1000

Time after beam trip (s)Temperature and stress of reactor vessel at beam trip transient

September 26-28, 2006

1500

OECD/NEA 9th Information Exchange Meeting on P&T

19

Reliability:
Behavior of Electric Power Generation System•• Saturated
Saturated steam
steam cycle
cycle with
with steam
steam drums
drums enables
enables us
us toto continue
continue power
power generation
generationinin casecase ofof short
short beam
beam trip.
trip.
600

120

Beam trip for 400 s

発電量 Power
Electric100

炉心入口冷却材温度500
炉心出口冷却材温度

Core outlet temperature
400

発電量(%)(%)
Power

温度(℃) (oc)Temperature

80

300

60

40

200

20

Core inlet temperature

100

0
0

500

1000
時間(s)

Time (s)September 26-28, 2006

1500

2000

0

500

1000

1500

2000

時間(s)
Time
(s)

OECD/NEA 9th Information Exchange Meeting on P&T

20

Reliability:
Summary of Criteria
Three
Three criteria
criteria depending
depending onon thethe beam
beam trip
trip duration
duration T
T
Beam trip duration T

Acceptable frequency

Remarks

T < 1 sec.

105 / 2 year
(50,000 / y)Beam window life time

1 sec. < T < 5 min.

104 / 40 year
(250 /y)Fatigue failure ofreactor structure

T > 5 min.

Once a week
(50 /y)System availability

September 26-28, 2006

OECD/NEA 9th Information Exchange Meeting on P&T

21

Reliability:
Strategy to Reduce Beam Trip Frequency
SINQ
SINQ andand LANSCELANSCE experiences
experiences show
show 11 oror 22 orders
orders ofof frequency
frequency reduction
reductionmight
might bebe necessary
necessary toto meetmeet thethe criteria.
criteria.
Criterion-1: Beam window

Beam trip frequency (times/year)

105

SINQ (2001)

104

103

Strategy-1:
Reduction of LANSCE （1997）
duration
Strategy-2:
Reduction of
frequency

102
Criterion-2:
Reactor structure

Criterion-3:
Turbine stop

10
Strategy-3:
Mitigation of
criteria

1
0-1 sec.

0-1 min.

1-5 min.

> 5 min.

Beam trip duration
September 26-28, 2006

Three
Three strategies
strategies forfor reduction:
reduction:
1.
1. Reduction
Reduction ofof thethe beambeam
trip
trip duration
duration down
down to
to 11
sec.
sec.
2.
2. Reduction
Reduction ofof frequency
frequency
forfor relatively
relatively long
long beam
beam
trip
trip
3.
3. Mitigation
Mitigation ofof thethe criteria
criteria
byby designdesign considerationconsiderationandand detailed
detailed transienttransientanalysis.
analysis.

Detailed
Detailed analysis
analysis onon thethe causes
causes ofof thethebeambeam trips
trips isis underway
underway toto explore
explore thetherealistic
realistic solutions
solutions forfor Strategy-1
Strategy-1 andand 2.
2.

OECD/NEA 9th Information Exchange Meeting on P&T

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Cost:
Preliminary Estimation
Preliminary Estimation of ADS Cost (billion Japanese Yen = 109 JY)
Operation and Decommissioning
maintenance
ADS-reactor
150
240a)
12b)
ADS-accelerator
76
122a)
6b)
Total
226
362
18
a) 4% of construction cost per year. b) 8% of construction cost
Items

Construction

Total
402
204
606

ADS Cycle Cost (109 JY)
Items
4 units of ADS
Partitioning process
MA fuel fabrication
MA fuel reprocessing
Profit by ADS electric power
Reduction of number ofrepository sites
Total

September 26-28, 2006

Cost
2450
570
520
450
-750
-1900


 Balance
Balance :: 0.12
0.12 ~~ 0.13
0.13 JY/kWh
JY/kWh(discount(discount rate
rate :: 00 %)%) about
about 2-3
2-3 %% increase
increase ofof thethe electricity
electricity
cost
cost inin Japan.
Japan.
 CostCost ofof ADSADS isis thethe most
most influential.
influential.

1340

OECD/NEA 9th Information Exchange Meeting on P&T

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Current Status of J-PARC Project:
Site Plan
Sept. 15, 2005

Hadron Experimental Facility
50 GeV
Material and Life
Science Facility
Neutrino

3 GeV

Site for Transmutation
Experimental Facility

September 26-28, 2006

LINAC

OECD/NEA 9th Information Exchange Meeting on P&T

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Current Status of J-PARC Project:
LINAC Klystron Gallery

Aug. 1,2006
September 26-28, 2006

OECD/NEA 9th Information Exchange Meeting on P&T

25

Current Status of J-PARC Project:
LINAC Beam Line

June 22, 2006
September 26-28, 2006

OECD/NEA 9th Information Exchange Meeting on P&T

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Current Status of J-PARC Project:
Transmutation Experimental Facility
Transmutation Experimental Facility (TEF) : Phase-2 Program.
TEF consists of the Transmutation Physics Experimental Facility (TEF-P) and theADS Target Test Facility (TEF-T).
Because of the budget shortage, step by step construction will be necessary.

TEF-P

Beam dump
Laser charge exchange
TEF-T

10W BT

133kW BT

600MeV SC-LINAC
Laser charge exchange
September 26-28, 2006

OECD/NEA 9th Information Exchange Meeting on P&T

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Current Status of J-PARC Project:
Call for Preliminary Letters Of Intent
The project team is calling for the Preliminary Letters Of Intent(Pre-LOI) for TEF.
Purposes: To
To know
know which
which groups
groups have
have anan interest
interest inin thisthis activity
activity ..
 To
To reflectreflect thethe proposals
proposals onon thethe specifications
specifications andand layout
layout ofof thethe TEFTEF
 To
To establish
establish anan appropriate
appropriate collaboration
collaboration scheme
scheme between
between J-PARC
J-PARC andand thetheanticipatedanticipated outside
outside users.
users.

Up to now, we received about 30 proposals on Reactor
Reactor physics
physics forfor ADSADS Experiments
Experiments using
using MA
MA forfor bothboth FRFR andand ADSADS HighHigh energy
energy particle
particle behavior
behavior MA
MA crosscross section
section measurement
measurement using
using pulsed
pulsed spallation
spallation source
source Engineering
Engineering feasibility
feasibility ofof LBE
LBE spallation
spallation target,
target, etc.
etc.

We are still accepting proposals, so please do not hesitate to contact us.
September 26-28, 2006

OECD/NEA 9th Information Exchange Meeting on P&T

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Step-by-step Approach for ADS andImportance of International Collaboration
ADS Transmutation Plant
800MWt, Pb-Bi Target/Coolant
Transmute 250kg of MA annually

power
GW

Experimental ADS
30 - 100MWt,
Pb-Bi Target/Coolant

MW

It is important to share acommon roadmap ininternational community

kW

Transmutation Experimental Facility
Pb-Bi Target with 200kW beam
Physics experiments at low power

W
Basic Experiments
2000
September 26-28, 2006

2010

year
2020

2030

OECD/NEA 9th Information Exchange Meeting on P&T

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Concluding Remarks
The new organization JAEA continues the R&D efforts on the ADS.
Scenario study shows the flexible nature of ADS to manage MA, andone of ultimate options would be FBR-ADS symbiotic state.
The engineering feasibility of ADS is being studied on beam window
and core performance.
The reliability of ADS, especially for beam trip transient, is also being
studied and the strategy to enhance the reliability is being discussed.
The preliminary cost estimation shows that about 2-3% of cost increase
would be expected to introduce P&T technology with ADS.
The TEF of J-PARC Project is waiting for the approval, and the Pre-LOI
is now being called for.

September 26-28, 2006

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