1. Radioactive Nuclides in Japan
Eighth Information Exchange Meeting on
Actinide and Fission Product Partitioning & Transmutation
Las Vegas, Nevada, USA
9-11 November 2004
Resent Research and Development Activities on Partitioning and Transmutation of
Radioactive Nuclides in Japan　
Kazuo Minato
Japan Atomic Energy Research Institute, Japan
Tetsuo Ikegami
Japan Nuclear Cycle Development Institute, Japan
Tadashi Inoue
Central Research Institute of Electric Power Industry, Japan

2. OMEGA Program in Japan
In Japan, the spent fuels from nuclear reactors are to be reprocessed
A long-term program for research and development on partitioning and transmutation (P&T) technology
Reduction of the burden of the backend of the nuclear fuel cycle
The Atomic Energy Commission of Japan (AEC) began the program in October 1988.
Advisory Committee of AEC reviewed the progress in 1999.
The Committee issued the report in March 2000.
OMEGA: Options for Making Extra Gains from Actinides and fission products generated in nuclear fuel cycle

3. OMEGA Check and Review in 2000
In P&T technology, there is a possibility to reduce the burden of waste disposal and to utilize waste as resources.
P&T technology is still on the fundamental stage. It is appropriate to steadily promote the research and development (R&D) and to demonstrate its feasibility. Then engineering tests are to be performed to obtain various knowledge such as safety data...
Three main institutes should promote their R&D steadily and effectively by collaborations with other institutes and universities in Japan and in foreign countries.
Innovative idea is required in the development of P&T technology It is necessary to prepare attractive condition for young researchers and engineers where they can exert their full ability.

4. P&T Technology in Japan
In Japan, P&T technologies are studied mainly at three institutes:
JAERI (Japan Atomic Energy Research Institute)
JNC (Japan Nuclear Cycle Development Institute)
CRIEPI (Central Research Institute of Electric Power Industry)
JAERI is studying P&T technology using Accelerator Driven System (ADS) and dedicated transmutation fuel cycle.
JNC and CRIEPI are studying P&T technology using critical fast reactor fuel cycle. Their activities are now organized as the “Feasibility Study on Commercialized FR Cycle Systems”.

5. Other Remarks to P&T in Japan
Long-term Nuclear Program (2000)
“…… Although P&T is still on the fundamental stage of R&D, there is a possibility to reduce the burden of waste disposal and to utilize waste as resources……”
Fundamental Policy for Specified Radioactive Waste Final Disposal (2000)
“…… Government and relevant institutes are required to steadily promote the research and development of P&T technology to reduce burden of final disposal, where viewpoints of international collaboration and periodic evaluation are important……”

6. JAERI’s Concept on P&T Dedicated Transmutation Cycle with ADS
Commercial Fuel Cycle
Partitioning & Transmutation Fuel Cycle
(1st Stratum)
(2nd Stratum)
Proton Beam
(1.5GeV-30MW)
Superconducting LINAC
30%
U, Pu
Electric Power
70%
Spallation Target
(Pb-Bi)
Grid
Nuclear Power Plants
MA, LLFP (Nitride Fuel)
Spent Fuel
Fuel Manufactiring
Reprocessing
Pu, MA, LLFP Recovered N-15
MA, LLFP
High Level Waste
Spent Fuel
Partitioning
Pb-Bi cooled
Subcritical core
(k-eff=0.95~0.93)
Radioactive Waste without Long-lived Nuclides
Pyrochemical Reprocessing
Final Geological Disposal

7. R&D on Partitioning Process JAERI
4-group Partitioning Process
For HLLW
TRU, Tc-PGM, Sr-Cs, Others
The process was tested with concentrated real HLLW
ARTIST Process
For spent fuel
Phosphorus-free agents consisting of C, H, O and N (CHON principle)
BAMA & DOHA : Separation of U, Pu
TOGDA : An, Ln recovery
N-donor ligand : An/Ln separation
ARTIST Process
Amide-based Radio-resources Treatment with Interim Storage of Transuranica

8. R&D on Transmutation Fuel Cycle JAERI
Nitride Fuel
Fabrication of (Pu,Am,Cm,Zr)N
Property measurements
Irradiation test of (Pu, Zr)N and PuN+TiN fuel pin in JMTR
Irradiation: , PIE: 2005
Pyrochemical Process
Electrolysis of UN, NpN, PuN, (U,Pu)N in LiCl-KCl eutectic melt
Recovery of Pu, U+Pu into liquid Cd cathode (Joint Research with CRIEPI)
Nitride formation behavior of U, Pu in liquid Cd
(Pu,Zr)N
PuN+TiN
Liquid Cd cathod after recovery of Pu

9. R&D on Dedicated Transmutation System JAERI
Accelerator
Superconducting LINAC
High-intensity proton accelerator (J-PARC Project)
Lead-Bismuth Eutectic (LBE)
Material corrosion/errosion test
Thermal-hydraulics test for the beam window
Evaporation test of Po from LBE
Sub-critical Reactor
800 MWth ADS
Transmutation of 250 kg of minor actinides annually
Conceptual view of 800 MWth LBE-cooled ADS

10. JNC’s Concept on P&T Fast Reactor Fuel Cycle
Basic Standpoints
Treatment of all TRU in the same manner without distinguishing between Pu and MA
Homogeneous loading of TRU in fuel assembly
Classification of fission products into four categories
Transmutation (Tc, I)
Storage for cooling (Sr, Cs)
Utilization (Ru, Rh, Pd, etc.)
Waste
Advanced fast reactor fuel cycle

11. R&D on Radiotoxicity Reduction JNC
Next Process
New Extraction System for TRU Recovery
Advanced aqueous reprocessing method developed by JNC
TRU recovery of > 99%
MA-bearing MOX Fuel
Fabrication
2%Np-2%Am-MOX
5%Am-MOX
Irradiation Experiment
In fast experimental reactor JOYO
In 2006
MA-MOX irradiation experiment in JOYO

12. R&D on HLW Reduction JNC
ORIENT-cycle: Optimization by Removing Impedimental Elements
New concept of fast reactor fuel cycle system
Reduction of HLW: < 1/10

13. R&D on Utilization of Noble Metal FP JNC
Noble metal fission products
About 30 kg/t-spent fuel
Electrolytic extraction of Ru, Rh, Pd, etc.
Utilization as catalyst for hydrogen production by water electrolysis
Fission products of Sr and Cs
Utilization as
radioactive source
Heat source
Experimental apparatus of electrolysis

14. CRIEPI’s Concept on P&T Fast Reactor Fuel Cycle
Metal fuelled FR cycle
LWR cycle
Mining
Fuel fabrication FP
Pyrometallurgical process (Electrorefining)
U, Pu, MA, FP
U, Pu U U
LWR
Spent fuel
(Oxide)
Metal fuel FR
Fresh fuel
(Metal)
Enrichment
U, Pu, MA
Pyro-process with electrochemical reduction and fuel fabrication
U, Pu, MA, FP
U, Pu, MA U
Fuel fabrication
Aqueous reprocessing MA ：
Minor actinide FP ：
Fission product

15. R&D on Partitioning Process CRIEPI
Separation of U and TRU from HLLW
Conversion of HLLW to oxides by heat-treating at 500oC
Chlorination of the oxides by chlorine gas at 700oC in LiCl-KCl
Reductive extraction of noble metals in LiCl-KCl/Cd at 500oC
Multistage extraction in the same system to separate U and TRU from rare earth elements
Most of solvents, molten salt, liquid metal and chlorine gas can be recycled after treatment H L W D e n i t r a o M u l s g - x c
> 9 % f T R U E w 2 O , N A k m S d v C K b / = 1 ( h ) F Z
Process flow of pyro-partitioning

16. R&D on Partitioning Process CRIEPI
Measurements of electrochemical potentials and distribution coefficients of actinides and lanthanides
Separation tests of actinides by reductive extraction
With simulated waste
Recovery of > 99% actinides
Setup of caisson in hot cell facility (cooperation of ITU)
Electrorefining test of Pu recovery from metal fuel
Currently, the program proceeds to use the genuine HLLW to finalize the process flow
External and internal views of the caisson
U-Pu-Zr alloy before and after experiment

17. R&D on Transmutation CRIEPI
Characterization of Alloy with MA
Solubility of tri-valence species in U-Pu-Zr is less than 1 wt%
Properties of alloys with MA and lanthanides up to 5% each are approximately the same as those of U-Pu-Zr
No melting phase appears below 650oC in U-Pu-Zr/Fe couple (Pu/(Pu+U) < 25 wt%)
Irradiation test of MA-containing Alloys
U-Pu-Zr-MA-RE
In core region of PHENIX
METAPHIX-1: 2.4 at % (2004)
METAPHIX-2: 7 at % ( )
METAPHIX-3: 11 at % ( )

18. Concluding Remarks R&D activities for P&T technologies are summarized
JAERI: ADS transmutation fuel cycle with nitride fuel and pyro-process
JNC: fast reactor fuel cycle with MA-MOX and aqueous process
CRIEPI: fast reactor fuel cycle with metal fuel and pyro-process
Integration of JAERI and JNC is scheduled in 2005
Other activities in Japan
Tokyo Institute of Technology
Basic study for innovative separation / transmutation systems toward vanishing HLW within the framework of COE-INES
Measurement and evaluation of nuclear data for MA transmutation in collaboration with JAERI, JNC, Kyoto University
Kyoto University and High Energy Accelerator Research Organizatio (KEK)
Construction of proton accelerator to couple with an existing critical assembly, though the purpose of this program is not only for study of transmutation but also for energy production