9th Information Exchange Meeting on
Actinide and Fission Product Partitioning & TransmutationNîmes, France
26-29 September 2006

Research and Development Activities on
Partitioning and Transmutation ofRadioactive Nuclides in Japan
Kazuo Minato, Masakazu Ichimiya
Japan Atomic Energy Agency, Japan

Tadashi Inoue
Central Research Institute of Electric Power Industry, Japan

Japan Atomic Energy Agency
JAEAz

On October 1st, 2005, the Japan Atomic Energy Agency
was established» as a result of integration of the Japan Atomic Energy ResearchInstitute (JAERI) and the Japan Nuclear Cycle Development
Institute (JNC)zJAEA is the only institute in Japan dedicated tocomprehensive research and development in the field ofnuclear energy

Employees: ~ 4,400
z Budget: ~ 200B JPYz2

Japan Atomic Energy Agency
R&D Centers
Tsuruga
Prototype fast reactor Monju,
Decommissioning of advanced
thermal reactor Fugen

Tono
High-levelrad-wasteresearch

Horonobe

Mutsu

High-level radwaste research

Decommissioning ofnuclear ship

Tokai
Basic research, Saftystudies, Neutron
Science, Nuclear fuelcycle technologies,
Rad-waste managementand disposal, etc.

Ningyotoge
Decommissioning ofuranium enrichment
plantsOarai

KansaiPhoton & synchrotronradiation science

NakaTakasaki
Radiation science

Fusion R&D,ITER support

Experimental reactors Joyo, HTTRand JMTR, Advanced reactor R&D
including FBR cycle
commercialization3

Nuclear Fuel Cycle Strategy in Japan
Current Status“Framework for Nuclear Energy Policy” (Oct., 2005)
z “Science and Technology Basic Plan” (March, 2006)
z “New National Energy Strategy” (May, 2006)
z “Nuclear Power Nation Plan” (Aug., 2006)
z “R&D Plan for Nuclear Energy” (tentative) (Sept., 2006)z4

Framework for Nuclear Energy Policy (1/4)
Atomic Energy Commission of Japanz

On October 11, 2005, the Atomic Energy Commission ofJapan decided the “Framework for Nuclear Energy Policy”» A basic principle for the nuclear energy policy that promotes
research, development and utilization of nuclear science andengineeringzOn October 14, 2005, the Government of Japan decided torespect the “Framework for Nuclear Energy Policy”

5Framework for Nuclear Energy Policy (2/4)
Atomic Energy Commission of Japan
Basic and fundamental research and development activities onpartitioning and transmutation technologies, which would
reduce the burden of disposal of radioactive waste, are to be
conducted to support the utilization of nuclear energy in Japan
Relative toxicity of radioactive wastez

1

Spent Fuel

10-1

Recovery of Pu (99.5%)
and U (99.6%)

10-2
10-3
10-4
10-5
10-6
10-7

Recovery of Pu (99.9%),
U (99.9%) and MA (99.9%)
Natural Uranium

10-8
100

102

104

106
Year

108

1010

6

Framework for Nuclear Energy Policy (3/4)
Atomic Energy Commission of Japanz

It is appropriate to aim at maintaining or increasing the current
level of nuclear power generation even after 2030
» 30 to 40% of the total electricity generationzz

Advanced models ofthe LWR are to beprepared for thereplacement of existing
nuclear power plants
The replacement will
start around 2030

Installed Capacity (GW)

70
6050Current
LWR40Current
LWR

3020

(if operationfor 60 years)

AdvancedLWR(operationfor 40 years)

FBR

1001960

1980

2000

2020 2040
Year

2060

2080

2100

7

Framework for Nuclear Energy Policy (4/4)
Atomic Energy Commission of Japanz

FR and its fuel cycle technology have the potential ofcontributing to long-term energy security and reduction of
the effects of potential toxicity of radioactive wastez

It is necessary to consistently promote the research anddevelopment toward its commercialization led by the Japan
Atomic Energy AgencyzFeasibility study on commercialized FR cycle systems
aims to establish the FR cycle technological scheme inaround 2015z

Development of FR cycle aims at its commercial
introduction at around 2050
8

Science and Technology Basic Plan
Council for Science and Technology Policyz

On March 28, 2006, the Government of Japan decided the“The 3rd Science and Technology Basic Plan”» for five years from FY2006 to FY2010» based on the report submitted to the prime minister by the Council
for Science and Technology Policy on Dec. 28, 2005z

FR cycle technology has been selected as key technologyof national importance» Intensive investment to FR cycle technology in the next five years

9Nuclear Power Nation Plan
Ministry of Economy, Trade and Industry (METI)z

On Aug. 8, 2006, a committee of METI reported the“Nuclear Power Nation Plan”

z

Created a concrete plan based on the “Framework forNuclear Energy Policy”» Being included in the “New National Energy Strategy”z

For the practical application of the FR cycle» Re-commence the operation of Monju at an early date and establish
sodium handling technology» Promote necessary technological developments such as the mixed
extraction of minor actinides» Aim to realize the demonstration reactor and related cycle facilities
by 2025» Develop the commercial reactor before 2050
10

R&D Plan for Nuclear Energy (1/2)
Ministry of Education, Culture, Sports, Science and Technology (MEXT)zOn Sept. 6, 2006, the “R&D Plan for Nuclear Energy”
was reported to Council for Science and Technology» as a result of intensive discussion in the Subdivision on R&D
planning and Evaluation, Council for Science and Technology» a concrete plan based on the “Framework for Nuclear Energy
Policy”z

Basic and fundamental research and development» It is important to promote the R&D on the partitioning andtransmutation technologies steadily

11

R&D Plan for Nuclear Energy (2/2)
Ministry of Education, Culture, Sports, Science and Technology (MEXT)zFR cycle technology» A council is set up to investigate demonstration process of fast
reactor cycle technology by MEXT, METI, JAEA, the electricutilities and fabricators» The most probable concept is sodium-cooled FR with advanced
aqueous reprocessing and simplified MOX fabrication» Re-start the operation of Monju by around 2008
» Optimization of conceptual designs of commercialized FR and its
cycle facilities is made based on engineering-scale demonstration
by 2015» Development of a demonstration FR aims at its introduction byaround 2025

12

R&D Activities on P&T in Japan
Two Types of P&T Schemesz

Homogeneous recycling with commercialized FR» MA-MOX fuel with aqueous reprocessing» MA-bearing metal fuel with pyrochemical reprocessingz

Double-strata concept with accelerator driven system» MA-bearing nitride fuel with pyrochemical reprocessing

Homogeneous recycling

Double strata concept13Advanced Aqueous Reprocessing
NEXT (New Extraction systems for TRU recovery) Process
Spent fuel

Reduction
Reduction ofof longlonglived
lived radioactive
radioactive
nuclidesnuclidesNp valenceadjustment

MA extraction
chromatography
U/Pu/NpAm, Cm

High levelliquid waste

RemovalRemoval ofof excess
excess U
U totoreducereduce processprocess solution
solution

Disassembling/decladding
Dissolution/clarification

Simplified
Simplified processprocess
without
without partitioning
partitioning andand
purification
steps
purification steps

Crystallization
Co-extraction“Centrifugal“Centrifugal contactor
contactor system”
system”

Co-stripping(U/Pu/Np recovery)

Solvent
regeneration

Concentration
Adjusting Pu
contentU/Pu/MA (product)U

Minimizing
Minimizing ofof wastes
wastesgeneration
bysalt-freegeneration by salt-freetechniquetechnique“Centrifugal“Centrifugal contactor
contactor system”
system”

If necessary

U (product)

This process separate
out no pure plutonium
14Advanced Aqueous Reprocessing
Experimental Validationz

U/Pu/Np co-recovery» Collection of data by hot tests» Development of centrifugal contactor– U extraction tests by multi-stage
centrifugal contactors (10 kg-HM/h)» Development of the instrumentation
systemz

MA recovery by extraction
Chromatography

Centrifugal contactor bank forU/Pu/Np co-recovery experiment» Collection of data by hot tests– SiO2-P: porous SiO2 covered by SDB
polymer– Resin: extactants (CMPO, TODGA,BTP, etc.) immobilized on SiO2-P» Development of the engineering setup

Adsorbent: CMPO/SiO2-P
15

Novel Extractants for MA Separation
Development of DGA and PDA

N» PDA can separate An(III)from Ln(III) in HNO3solutionz

DGA and PDA consist ofC, H, O, and N

R2OCO

CH2CO

R1R1R1NN

R2R2CNCN
R2OO

Atomic no. of An103

95

110Am(III)210
Distribution Factor

Pyridine dicarboxyamides(PDA) for MA/Lnseparation

H2CR1» High solubility in n-dodecane» Very high extraction ability
for An(III) and An(IV) from
HNO3 solutionz(PDA)(DGA)

Diglycolamides (DGA) for
TRU recovery

SF>10100

101

Th(IV)Np(V)
U(VI)
Pu(IV)
Am(III) 10-1
Cm(III)Lu(III)

Dz

100

10-1
10-2 -110La(III)0.1M TODGA+1M DHOA
010[HNO3] / M

1100.5 M DMDPhPDA-1 M HNO3
10-2

56

60 64

68 72

Atomic no. of Ln16

MA-bearing MOX FuelFabrication and Characterization
zSimplified pelletizing method» Die wall lubrication pelletizing, Sintering,O/M adjustment-5Property measurements» MA and simulated FP bearing
MOX fuel– Melting point– Thermal conductivity– Oxygen potential, etc.

-10Log (PO2)z

5%Am-MOX fuel pellets for
JOYO irradiation test

4.5%Am- MO X 1123 K
4.5%Am- MO X 1273 K
4.5%Am- MO X 1423 K
30%P u- MO X 1273 K [1]- 100- 200- 300-15- 400-20- 500-25

O xygen Potential for 1273K / kJ/m

– Good accuracy of Pu content adjustment bysolution mixing– Pellet fabrication with die wall lubrication– Good Sintering of Am/Np/simulated FP pellet
with low O/M ratio- 600
1.92 1.93 1.94 1.95 1.96 1.97 1.98 1.99 2.00 2.01 2.02 2.03
O/M ratio17

Electrometallurgical Process
Integrated ExperimentszWhole process was demonstrated in one continuous
operation using UO2 with good mass balance» Li reduction, electro-refining and distillation

Test with PuO2 was successfully finishedz Integrated test with MOX fuel is underway
zSolid cathode deposit

Cd cathode deposit

Recovered Pu-U-Cd
CRIEPI- JAEA collaboration

18

Phenix Irradiation of MA-metal Fuel
METAPHIX
Irradiation of metal fuel pins with U-Pu-Zr containing minor
actinides (Np,Am,Cm) and rare earthsz Fuel fabrication, PIE and recycling with pyro-process in ITUzBurnup
2.4 at.%
7.0 at.%11.0 at.%2003
Irrad.
Irrad.
Irrad.

2004→→→

U-Pu-Zr-MA-RE
MA; Np, Am, Cm
RE; Ce, Nd, Y, Gd(Fabricated by arc-melting)2005→→

2006 2007 2008 2009
Trans. PIE→Trans. PIE→→Trans. PIE

2010

→

Composition, wt%
U-19Pu-10Zr
U-19Pu-10Zr-2MA-2RE
U-19Pu-10Zr-5MA-5RE
CRIEPI- ITU collaboration

19

Phenix Irradiation of MA-metal Fuel
METAPHIXz

The non-destructive analysis on pins with 2.4 at% burnup at
Phenix was finished» No failure and no deformation were visually observed» To be transported to JRC-ITU for destructive PIE<Configuration of capsule><Pin configuration>
A,C: U-Pu-Zr B: U-Pu-Zr-MA-RE

Irradiation of 3 pins in the same capsule
at different burnup

1 79 38 08

2 85

1 00 1 00 1 04 67
1ABC

2N a - bo n d in g gas ple num
4 35

4 35

M O Xdrive r
H e - bo n d in g

MOX Driver pin
3Metal fuel pin with MA
Composition of region B, wt%
Pin1 : U-19Pu-10Zr
Pin2 : U-19Pu-10Zr-2MA-2RE
Pin3 : U-19Pu-10Zr-5MA-5RE

CRIEPI- ITU collaboration

20

Fuel Irradiation Test Plan
Oxide and Metal Fuels in JOYO
2005

Oxide fuel2010

2015

2020

BOL performance test (Am-MOX, Am-Np-MOX)
Steady state irradiation (Am-MOX, Am-Np-MOX)
Power-to-Melt tests of MA bearing MOX
MA bearing MOX(low DF process)

ODS clad. pin irradiation

Metal fuelHigh temperature performance test of
U-Pu-Zr Metal fuelSteady state irradiation of
U-Pu-MA-Zr Metal fuel21

Accelerator Driven System
Design and Key Technology Developmentz

Accelerator» Superconducting LINAC» High-intensity proton accelerator

Movable support(J-PARC Project)» Assessment and improvement ofreliabilityz

Spallation Target

Bending magnet

Proton beam

» Development of Pb-Bi technology» Design and material for feasible
beam windowz

Sub-critical Reactor» Reduction of power peaking» Management of beam trip transient» MA fuel handling» Transmutation of 250 kg-MA/yFuel exchanger
Beam ductPrimary pump

Steam generator

Spallation target

Reactor vessel
Subcritical core
Beam window

Core support

Conceptual view of 800 MWth
LBE-cooled ADS
22

MA-bearing Nitride Fuel
Fabrication, Characterization and Pyrochemical Processz

Nitride Fuel» Fabrication of (Np,Pu,Am,Cm)N, etc.
» Property measurements– Thermal conductivity, Thermal expansion,Heat capacity, etc.

» Post-irradiation examination of (Pu, Zr)Nand PuN+TiN fuel– No detrimental effect by addition ofdiluent materials of ZrN and TiNz

Heat capacity of actinide nitrides

Pyrochemical Process» Dissolution behavior of (Pu,Zr)N inLiCl-KCl eutectic melt was clarified» Nitride formation of Pu and U from
Pu-U-Cd alloy and pellet fabrication– Nitridation/distillation combined method(Pu,Zr)N pellets
Cross-section of (Pu,Zr)Npellet after irradiation

23

Summaryz

Nuclear Fuel Cycle Strategy in Japan» Basic and fundamental research and development activities onpartitioning and transmutation technologies are to be conducted tosupport the utilization of nuclear energy» Development of a demonstration FR aims at its introduction byaround 2025
» Development of FR cycle aims at its commercial introduction
before 2050z

R&D activities for P&T technologies» Using commercialized FR– MA-MOX fuel with aqueous reprocessing– MA-bearing metal fuel with pyrochemical reprocessing» Using ADS in double strata concept– MA-bearing nitride fuel with pyrochemical reprocessing
24