Nov. 28, 2013

International Symposium on
Nuclear Back-end Issues and the Role ofNuclear Transmutation Technology
after the accident of TEPCO's Fukushima
Daiichi Nuclear Power Stations

ADS Study in JAEA

Hiroyuki Oigawa
Nuclear Science and Engineering Directorate (J-PARC Center)

Japan Atomic Energy Agency

1Partitioning and Transmutation (P&T)
Spent fuelReprocessing
FP、MA

Partitioning

RecycleU、Pu
Geological disposal(Glass waste form)

Conventional scheme

MA (Np, Am, Cm)

P&T technology
Transmutation by ADS and/or FR

PGM (Ru, Rh, Pd)

Utilization and/or disposal(Example)

MA:FP:PGM:
FR:
ADS:

Heat generator (Sr, Cs)

Geological disposal after cooling and/orutilization (Calcined waste form)

Remaining elements

Geological disposal(high-density glass waste form)

Minor Actinides
Fission Products
Platinum Group Metal
Fast Reactor
Accelerator Driven System

2Reduction of Radiological Toxicity by P&T
Radiological Toxicity:
Amount of radioactivity weighted by dose coefficient of each nuclide.
1.E+09

使用済燃料
Spent fuel (1t)
高レベル廃棄物
High-level waste
分離変換導入MA transmutation
天然ウラン9トン
Natural uranium (9t)Radiologicaltoxicity (Sv)
潜在的有害度（Sv）

1.E+081.E+071.E+06• Normalized by 1t ofspent fuel.
• 9t of natural uranium(NU) is raw material of
1t of low-enricheduranium including
daughter nuclides.

1.E+05Time period to decay
below the NU level:

1.E+04• Spent fuel
Reduction

1.E+03
1.E+02
1.E+01

100,000y↓• High-level waste 5,000y↓• MA transmutation 300y

Reduction

1.E+02

1.E+03

1.E+04

1.E+05Time after
reprocessing (Year)
処理後経過時間（年）1.E+06

1.E+073

Compact Disposal
by Coupling with Long-term Storage
Normalized by 32,000tHM of 45GWd/t spent fuelConventional Concept

Low-heating wastes (0.13km2)
CT: Cooling time before disposal

1.8 km2(Vertical emplacement in crystalline rock)

MA transmutation+
FP Partitioning
0.41 km2
MA transmutation+
FP Partitioning+
Long-term storage of Sr+Cs
0.015 km2

40,000 pieces of glass waste forms (1.8km2)(CT: 50 y)
5,100 pieces of Sr-Cs calcined forms (0.23km2)(CT: 130 y)
8,300 pieces of highly-loaded
glass waste forms (0.18km2)(CT: 5 y)
8,300 pieces of highly-loaded
glass waste forms (0.01km2)(CT: 45 y)
5,100 pieces of Sr-Cs calcined forms (0.005km2)(CT: 320 y)
Ref. : K. Nishihara, et al., “Impact of Partitioning and Transmutation on LWR Highlevel Waste Disposal”, J. Nucl. Sci. Technol., 45(1), 84-97 (2008).

4

Two Types of Fuel Cycles forPartitioning and Transmutation Technology
Commercial Fuel Cycle

Reprocessing,
Fuel fabrication Power Reactors(1GWe X10 units)
Partitioning
U, Pu

FPUtilization

FP: Fission Product
Final disposal
MA: Minor Actinide (Np, Am, Cm)
ADS: Accelerator-Driven System
ABR: Actinide Burner Reactor

Dedicated Transmutation
by ADS (Double-strata) •Transmutation cycle isattached to commercial
I-129
Transmutation
cycle.
Cycle•ADS or ABR is used as
dedicated transmutation
MAsystem.
FuelReprocess
ADS (800MWth)•MA can be confined into aMA
small cycle and transmuted
efficiently.
FP
Homogeneous Recycle in FBRCommercial FBR Cycle
FBR

Fuel fabrication

FBR

Reprocessing

FBR

U, Pu, MA, part of FP•MA is transmuted by commercial FBR
power plants.
•5% MA (max.) is added to conventional
FR fuel (MOX, Metal, ...)

FPFinal disposal

5

Accelerator Driven System (ADS)for MA Transmutation
Proton beam Max.30MWSuper-conducting LINAC
100MW
To accelerator

800MW

170MW

Fission energy

To grid
MA: Minor Actinides
LBE: Lead-Bismuth Eutectic

Spallation target(LBE)270MWPower generation

Transmutation by ADS
Utilizing chain reactions insubcritical state
Fission neutrons

Short-lived or stable
nuclidesProtonSpallation target
Fast neutrons Characteristics of ADS:

Long-livednuclides (MA)MA-fueled LBEcooled subcriticalcore• Chain reactions stop when the accelerator isturned off.
• LBE is chemically stable.
 High safety can be expected.
• High MA-bearing fuel can be used.
 MA from 10 LWRs can be transmuted.

6

ADS Proposed by JAEA

• Proton beam : 1.5GeV• Spallation target : Pb-Bi• Coolant : Pb-Bi• Max. keff = 0.97
• Thermal output : 800MWt• MA initial inventory : 2.5t
• Fuel composition :(MA +Pu)Nitride + ZrN• Transmutation rate :10%MA / Year• 600EFPD, 1 batch

Conceptual view of 800 MWth LBE-cooled ADS

7

Size of Nuclear Fuel Cycle for ADS
MA 1t/yReprocessing
LWR
800t/y40units (40GWe)
Transition

Reprocessing and fuelADS
fabrication 8t/y4units (1.1GWe)

MA 1.2t/y
FBR
Reprocessing and fuel40units (40GWe) fabrication 350t/y

ADS
Reprocessing and fuel5units (1.4GWe) fabrication 10t/y

 MA produced in 40 units of LWR (1GWe) is about 1t/y.
 4units of ADS (0.27GWe) are necessary to transmute 1 t/y of MA.
 Size of ADS fuel cycle is about 2-order smaller than that of LWR reprocessing.
 In the future FBR era, almost same size of ADS fuel cycle can manage MA.
8Reliability of Accelerator
Number of beam trips per year (7,200 hours)Beam trip rate (times/year)

Acceptable trip rate

 We are comparing the trip rate estimatedfrom data of existing accelerators and themaximum acceptable trips to keep theintegrity of the ADS components.
 Short beam trip (<10s) can meet the cliteria.
 Longer beam trip should be decreased by:
 Reducing the frequency and Reducing the beam trip duration

Estimation from experiences

0-10s

10s – 5min.

>5min.

Beam trip duration

9

Design of Beam Window Beam window is subjected to severe conditions: High temperature Corrosion and erosion by LBE Pressure difference between vacuum and LBE (~0.8MPa)
 Irradiation by protons and neutrons
Temperatur
温度分布eOutersurface

490oC
ビーム窓
Temperatureo
外表面温度Of beam
window 470 C

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

450oC

t3

Coolant flowt2

t1

Support structure(unit: Kelvin) Temperature at the outer surface of the window can be less than 500ºC.
 Buckling failure can be avoided by a factor of safety (FS)=3.
 The life time of the beam window should be evaluated from viewpoints of corrosion
and irradiation.  necessity of irradiation data base.
10Mock-up Experiments
for Beam Window Thermal-hydraulics

Heater: 6kW
Flow rate: 100-500 L/min.
Inlet temp.：330-430ºC

JLBL-3
Experimental approach toobserve LBE flow

Mock-up of beam window
3-D monitoring ofLBE flow by UVPFlow of LBE

It was confirmed that averageheat transfer at the beam
window can be calculatedwith good accuracy.
Stability of the flow should beinvestigated in detail.
Ultrasonic Velocity Profiling(UVP) is being developed.

JLBL-211

Accuracy of Neutronics Design
JAEA J3.3

1.01

JAEA J3.2

1

JAEA J4.0k-eff, JENDL

0.99

J4.0

0.98
0.97
0.96
0.95

J3.2, J3.3

0.94
0.93
BOC

EOC

Benchmark calculation for 800MWt ADS for BOC and EOC.
(Left: Comparison between JENDL-4.0 and JENDL-3.3, Right: Nuclide-wise contribution for differences in k-eff)

 There is 2% difference in k-eff between JENDL-4.0 and JENDL-3.2, which is toolarge to design ADS.  necessity of integral validation of nuclear data12

Japan Proton Accelerator Research Complex:
J-PARC
Jan. 28, 2008

Hadron Experimental Facility

50 GeV Synchrotron
Materials and Life Science Experimental
Facility
To neutrino
detector
3 GeV Synchrotron

Site forTransmutation
Experimental Facility
LINAC

13

Transmutation Experimental Facility (TEF)
of J-PARC
Transmutation Physics
Experimental Facility: TEF-P

ADS Target Test Facility：TEF-T

Purpose: To investigate physics properties ofsubcritical reactor with low power, and toaccumulate operation experiences of ADS.
Licensing: Nuclear reactor: (Critical assembly)
Proton beam: 400MeV-10W
Thermal power: <500W

Purpose: To research and develop a spallation
target and related materials with highpower proton beam.
Licensing: Particle accelerator
Proton beam: 400MeV-250kW
Target: Lead-Bismuth Eutectic (LBE, Pb-Bi)

Critical Assembly
Pb-Bi Target
Proton Beam
14

ADS Target Test Facility:
TEF-T
Thermal-hydraulics Analysis by STAR-CD
Geometry 3D 1/4 sector ~220,000 cells
Pb-Bi Flow 1 Litter/sec
ProtonInlet Temp. 330ºC
SolverStandard k- for High Re nr.
Material
316SS or T91 2mm thickProton
400MeV-250kW
Beam Prof. Gauss (Peak:20A/cm2)
Structural Analysis by ABAQUS
Static Stress
0.3~0.5 MPa (Pb-Bi)
Thermal Stress
Data from THA
Acceptable Beam Density: < 30A/cm2Proton15

Transmutation Physics Experimental Facility:
TEF-P•••

Critical facility for reactor physics and nuclear
data of transmutation systems: both ADS and FBR.
Neutron source: 1012n/s, 25Hz. 1ns pulsed beam
is available by laser charge exchange technique.
Pin-type MA fuel can be used with appropriate
cooling and remote handling.
Maximum thermal power : 500W

Stainless steel matrix

Pb block
Coolant simulator (Pb, Na, etc.)

Spallation target
Plate-type fuelBeam duct
Proton beam

Fuel drawer
Pin-type fuel
5.5cm
5.5cm

16

Preliminary Schedule of TEF
Fiscal Year

Beam line
TEF-T2013 2014 2015 2016 2017 2018 2019 2020 2021 2022 2023 2024

R&D, Design
Construction
Operation
R&D, Design

TEF-P

Licensing

Construction
Operation• The construction of Beam line and TEF-T will be started in 2015 and theoperation will be started in 2017.
• To start the construction of TEF-P in 2017, just after the completion ofTEF-T, a few years of licensing activities should be started in 2015.
17

International Collaboration with MYRRHAADS technologies by MOX fuelPowerExp. ADS⇒MYRRHA~2.4MWbeam, 50-100MWth・Proof of ADS, Fuel irrad.

ADS Plant
30MWbeam, 800MWth・Transmute MAs from 10 LWRs

Window Material data

MA-loaded core neutronics and material data

MYRRHA• Experimental ADS fueled with MOX• Fuel and material irradiation

TEF

J-PARC TEF

Loop Tests
2010

250kWbeam
・Pb-Bi Target
・ADS Neutronics

2020• Material Irradiation by proton beam
• Data for neutronics design of MA-loaded ADS
To establish ADS plant technologies in 2030s20302040

Year18

Working Party to Review Partitioning andTransmutation Technology
 The Ministry of Education, Culture, Sports Science and Technology (MEXT) in Japan
has launched a Working Party to review Partitioning and Transmutation Technology inAugust, 2013.
 An interim report was issued in November, 2013.
Key Descriptions:To reduce the burden of HLW management, it is expected that flexibility in future politicaldecision is extended by showing possibilities of new concepts of back-end with high social
receptivity.
The ADS Target Test Facility (TEF-T) is being proposed under J-PARC to verify the feasibility ofthe beam window. It is appropriate to shift the R&D of the facility to the next stage.
The Transmutation Physics Experimental Facility (TEF-P) is being proposed under J-PARC toovercome difficulties in reactor physics issues such as for a subcritical core and an MA-loaded one.
Since this facility is proposed as a nuclear reactor, the safety review by the new regulation is tobe applied. With taking care of this point, it is appropriate to shift the R&D of the facility to thenext stage.
For MYRRHA Program, it is appropriate to proceed with negotiation about JAEA’s
participation at a reasonable level and mutual collaboration with Belgium and other relevant
countries.
Progress of the development should be checked according to its stage.
19

Overview of future R&D plan:(1) Partitioning and ADS fuel cycle
MA separation
Separation process

Waste treatment

Fuel fabrication for MA transmutation
Plant design

New process development after 4-group partitioning
Innovative extractant

Genuine HLW tests
Process databasedevelopment

Waste estimation

Flowsheet design

Treatment of products
and secondary wastes

Solvent recoveryprocess
Process optimization

Design of separationequipment & plant

Process demonstration

Non-active tests ofequipment◎MA supply

2025

2020

2015

・Tracer tests
・MA+RE recovery
・MA/RE separation

Around 2050

◎Process demonstration in engineering scale（New experimental facility）◎Separation process operation in industrial scale(Supply of MA products for ADS fuel fabrication)

Note: Time axis does not
represent exact periodsof development

Pyroprocessing of MA fuel

Fuel fabrication
process / plant

Fuel performance

Preconditioning

Electrorefining / MA
recoveryConceptual study ofthe process

Preliminary
assessment of thefuel property

Chopping tests ofsurrogate fuel rods

Basic datameasurements

・Conceptual study
・Zeolite column
tests

Flowsheet design・Conceptual study ofequipment
・Conceptual study ofplant・Bench scale tests using
MA sample separated /recovered withpyroprocessing

・Property datameasurements/
database construction
・Separated MA
sample datameasurements
・Development of MA
・Manufacturing of MA fuel fuel analysis code
sample for irradiation
・Unit operation tests ofequipment with surrogates

Waste treatment

Engineering-scale
chopping tests withsurrogates

・Element tests ofthe main process
・Bench scale tests
using separated
MA samples
Engineering-scale
tests withsurrogates

Waste treatment
tests withsurrogates
Engineering-scale
tests withsurrogates

MA fuel sample
irradiation tests
・Design & optimization of the equipment/system☆Manufacturing MA
fuel rods/ assemblies
・Engineering-scale
fabrication tests withsurrogates

・Unit operation tests of actual scale equipment
・ Irradiation tests ofMA fuel rods/
assemblies
・Validation of reactor
core safety◎Actual fabrication plant(Supply of MA fuels)

Flow of technology

Item almost completed

Flow of MA

Item in progress (red),and to be focused on (black)☆Bench scale tests with irradiated fuels◎ Actual pyroprocessing plant(Processing of the actual spent MA fuels)

Item in the further future. An item requiring new facility
is shown by “☆” (~10gMA) and “◎” (kgMA~tMA).

20

Overview of future R&D plan:(2) ADS plant
Reactor physics･Nuclear data
Measurement･Covariance data
･JENDL-4

LBE thermal hydraulics,
spallation target

Conceptual designof plant・Concept of reactor
control・Safety concept

・Property, etc.
・Small-scale flow test
・Conceptual study of target

・Validation by small
amount of MASimulation of core
（KUCA）
element, sub-criticality ・Measurement
measurement（MASURCA, （J-PARC/MLF）
VENUS-F, KUCA, FCA, etc.） ・ MA sample
irradiation

Characteristic test of ADS and MA-loaded
core in the Transmutation physics
experimental facility (TEF-P)
Partially MAloaded test

・Conceptual designof safety instrument
・Control method ofaccelerator

Mock-up of beam window(MEGAPIE)

Material for LBE

Accelerator･Basic data acquisition for
corrosion and irradiation
effect･Corrosion test
･Proton irradiation test(SINQ,MEGAPIE)･Conceptual study･Lab-scale test ofelemental technology

Post irradiation test
(MEGAPIE)･Measurement techniques･Flow test for instruments

Engineering test of spallation target in the ADS
target test facility (TEF-T)

MA supply

Low-power testwith proton beam

Conceptual studyof elementtechnology◎2025

Safety, control

Demonstration of ADS plant in theirradiation ADS （MYRRHA）
Development,manufacturing andoperation ofinstruments (pump,SG, etc.)

Mock-up of beam
window（Real condition）

High-power
operation, safety
test

Data acquisition for
MYRRHA

Proton irradiation（Real condition）

Material dataacquisition for the 1stADS

J-PARC accelerator
Full-scale
development
Improvement ofreliability

Fast neutron irradiation(JOYO, MYRRHA, etc.)

2020

2015

･Code development･Physics of sub-critical･Basic experiment ofspallation reaction

Plant

MA nuclear data

Development ofsuperconducting
accelerator
Development ofsuperconducting
accelerator for the 1stADS (applying
MYRRHA’s experience)

Plant design and instrument development for the 1st ADS

Around 2050

◎Construction of the 1st ADS (800MWt, MOX fuel partially containing MA)

Note: Time axis does not
represent exact periodsof development

R&D on MA fuel manufacturing
and reprocessing
MA fuel loading

Flow of technology
Flow of MA

Item almost completed

Item to be promoted based on the evaluation

Item in progress (red),and to be focused on (black)

Item in the further future. An item requiring
new facility is shown by “◎”.

21Concluding Remarks






Double-strata fuel cycle concept including ADS provides us
a possibility to flexibly cope with the waste management invarious situations of nuclear power.
R&D on ADS and its compact fuel cycle are under way in JAEA,
and we are proposing the Transmutation Experimental
Facility as the Phase-II of J-PARC.
Recently, the Working Party of MEXT represented positive
views to facilitate the R&D on this technology.
To overcome various technical challenges for this technology,
the international collaboration is of great importance.

22