The Current Status of R&D for Accelerator-driven System at JAERI

GENES4/ANP2003, Sep. 15-19, 2003, Kyoto, JAPAN Paper 1184 The Current Status of R&D for Accelerator-driven System at JAERI Toshinobu Sasa *, Hiroyuki Oigawa, Kazufumi Tsujimoto, Kenji Nishihara, Makoto Umeno and Hideki Takano Nuclear Transmutation Group, Japan Atomic Energy Research Institute, Tokai, Naka, Ibaraki, 319-1195, Japan Management of the nuclear waste is one of the important issues for future nuclear power generation. Japan Atomic Energy Research Institute (JAERI) performs research and development for accelerator-driven transmutation systems under national OMEGA (Options Make Extra Gains from Actinide and Fission Product) program. Transmutation of radioactive waste is helpful to improve the environmental impact and increase a capacity of waste disposal plant. The system consists of a superconducting proton LINAC, Pb-Bi eutectic spallation target and Pb-Bi cooled subcritical core. The nitride fuel is selected as a fuel of subcritical core because of the good compatibility with minor actinides and application of pyrochemical process for the reprocessing. To minimize the burnup reactivity swing, plutonium is mixed into the virgin fuel. Thermal output of the system is 800MW by injection of the proton beam with the power of 20 to 30 MW and then, about 250kg of minor actinides can be transmuted annually at load factor of 80%. A turbine generator is connected to supply the electricity for ADS operation. To study and evaluate the feasibility of ADS by a physical and an engineering viewpoint, the Transmutation Experimental Facility (TEF) is proposed under a framework of JAERI-KEK joint J-PARC (Japan Proton Accelerator Research Complex) project. The TEF consists of two facilities named as Transmutation Physics Experimental Facility (TEF-P) and ADS Target Test Facility (TEF-T). The TEF-P consists of a zero-power critical assembly which operates with a low power proton beam to research the reactor physics and the controllability of ADS. The TEF-T is a facility for material irradiation and partial mockup of beam window which can accept a maximum 600MeV-200kW proton beam into the Pb-Bi spallation target to simulate an irradiation environment of beam window and structural materials for Pb-Bi cooled ADS. KEYWORDS: Accelerator-driven System, Transmutation, Minor Actinide, Long-lived Fission Product, Lead-Bismuth Alloy I. Introduction The Japan Atomic Energy Commission launched a long term research and development program named OMEGA (Options Making Extra Gains from Actinides and fission products) for partitioning and transmutation of long-lived radioactive nuclides in 1988. The objectives of OMEGA project are to widen options for future waste management and to explore the possibility to utilize high-level radioactive wastes as useful resources. In the OMEGA program, Japan Atomic Energy Research Institute (JAERI) has been proposed a double-strata fuel cycle concept 1) which consists of two fuel cycles as shown in Fig.1; current commercial fuel cycle and dedicated fuel cycle for the transmutation of minor actinides (MA) and long lived fission products (LLFP). By the double-strata fuel cycle, no significant modification is required to the current fuel cycle and long-lived nuclides are confined into the small cycle that is optimized to the transmutation of MA and LLFP. For the transmutation of MA and LLFP, JAERI proposes an accelerator-driven system (ADS). When the fuel is mainly composed of MA, a delayed neutron fraction, which influences the safety operation of critical reactor, becomes lower than that of conventional nuclear reactors. In the case of ADS, the delayed neutron fraction does not directly affect * Corresponding author, Tel. +81-29-282-6436, Fax. +81-29-282-5671, E-mail: sasa@omega.tokai.jaeri.go.jp First Stratum ( Commercial Power Reactor Fuel Cycle) Fuel Fabrication LWR 3400MWt X 10 Reprocessing Second Stratum (Transmutation Cycle) Processing Short-lived FP Recovered U, Pu I-129 MA,LLFP Dedicated Fuel Transmuter Fabrication 800MWt MA, LLFP Partitioning HLW (MA, FP) Short-lived FP Final Geological Disposal Fig.1 Double strata fuel cycle concept the operation in comparison with a critical reactor because of the subcriticality of the system. There also exists a wide margin of reactivity to install various compositions of MA

that are related to the burnup profile and the types of spent fuel. JAERI proposes a lead-bismuth (Pb-Bi) target/coolant system as a primary candidate of the ADS 2). A proton beam of 1.5 GeV - 22 MW is injected and the system is designed to generate 800 MW of thermal power. To realize the ADS, there are many technical subjects; the neutronics of the subcritical core driven by spallation neutrons, the engineering application of the high power spallation target, the development and the operation of the intense proton accelerator and so on. To solve these technical issues relevant to the ADS development, construction of the Transmutation Experimental Facility (TEF) is planned under the Japan Proton Accelerator Research Complex (J-PARC) Project that is directed by JAERI and High Energy Accelerator Research Organization (KEK) 3). Proton beam of 600 MeV and 0.33 ma (200 kw) is to be delivered to this facility. To perform different research purposes, TEF consists of two buildings, the Transmutation Physics Experimental Facility (TEF-P) and the ADS Target Test Facility (TEF-T). II. Accelerator-driven transmutation system design 1. Overview The reference ADS design proposed by JAERI is the 800MWth fast subcritical core fueled with MA nitride, cooled by liquid lead-bismuth eutectic alloy (Pb-Bi). The subcritical core is driven by the spallation neutron source using Pb-Bi target and proton accelerator. This ADS can be transmute about 250kg of MA annually by fission reactions, which corresponds to the amount of MA produced in 10 units of LWRs whose burn-up is 33,000 MWD/t. In this reference design, maximum value of the effective multiplication factor, k eff, is set to 0.95. To achieve the above mentioned thermal power with this k eff, a high-power proton beam over 20MW is required. This proton beam must be supplied constantly and safely with sufficient cost. To satisfy such requirements, a superconducting linear accelerator is adopted. Considering the energy efficiency of a neutron source, the specification of the proton beam, 1.5 GeV 15 to 20mA, is temporally chosen, though the acceleration energy should be finally determined by taking account of the factors such as the cost of the accelerator and the beam density on the beam window. As for the spallation target, Pb-Bi was chosen from several heavy metals, such as Hg and W, because of its good thermal property; the melting point of 398K and the boiling point of 1943K. Although Pb-Bi is comparatively corrosive to steel at the high temperature above 700K, Russia has a lot of experience to use it as the coolant of reactors in submarines. Many countries have therefore started research and development to establish the technology for the usage of Pb-Bi as the spallation target. To achieve the effective transmutation of MA by fission reactions, the fast neutron spectrum is essential because MA has a threshold fission cross section. So, effective fission cross section is more larger than that of capture cross section. However, since large positive void reactivity is unacceptable for the ADS where subcritical state should be kept at all times, Na is not preferable. Gas such as He and CO 2 can be used as the primary coolant, but very high pressure such as 10MPa might be necessary to keep the good cooling performance. Taking account of above factors, Pb-Bi is also chosen as the primary candidate of the coolant for ADS. Nitride fuel has the advantage of accommodating various MA with a wide range of composition besides good thermal properties. Because of the high MA density and application of hard neutron spectrum, nitride fuel suitable for effective transmutation of MA. For avoiding the production of hazardous 14 C, however, 15 N enriched nitrogen to 99.9% shall be used in the nitride fuel. In our reference design, tank-type structure is adopted as shown in Fig.2. The inlet and the outlet temperatures of the primary Pb-Bi are 603K and 703K, respectively. Steam generators can be directly inserted in the reactor vessel because Pb-Bi is chemically compatible with water. The electric power is about 250MW, which means the ADS can be a self-sustaining system provided the efficiency of the accelerator is more than 15%. Beam duct Fuel region Beam window Steam generator Proton beam Pb-Bi Main pump Fig.2 Pb-Bi target/cooled ADS Concept Core support To realize an ADS, JAERI performed various R&D for neutronics code development, accelerator, nitride fuel and Pb-Bi application. Experiments that is indispensable to design the ADS, Transmutation Experimental Facility (TEF) is planned under the framework of JAERI-KEK joint J-PARC project.

2. Neutronics code development The incident particle of ADS is a proton with an energy around 1 GeV and reactions in spallation target mainly occur in the energy range above 100 MeV. Reactions in such high energy region are different from those considered in conventional reactor analysis. On the other hand, in the fuel surrounding the target, most of reactions occur below several tens MeV. For the design study of ADS, calculations in the wide energy range from ev or kev up to GeV are required to analyze specific neutronics parameters such as spallation neutron yield from the spallation target, spatial and energy distribution of the spallation neutrons, heat deposition distribution, time evolution of the isotope composition of the fuel and of the subcriticality of the core, particle flux and power density distribution in the subcritical core, decay heat of the spallation target and fuel, coolant void reactivity, Doppler coefficient and so on. To analyze these parameters, an analysis code system named ATRAS (Accelerator-driven Transmutation Reactor Analysis code System) to analyze the neutronics and burnup properties of ADS was developed 4). ATRAS is an integrated code system that performs the following analyses: spallation, evaporation and high energy fission reactions in high energy region, proton, neutron and pion transport in high energy region, neutron reactions and transport in low energy region and core burnup in low energy region. The structure of the ATRAS is illustrated in Fig.3. Analysis codes included in ATRAS are connected to each other through CCCC format binary file 5). In ATRAS, hadronic cascade processes that occur in the energy range from MeV to GeV are calculated with the NMTC/JAERI97 6). NMTC/JAERI97 calculates hadronic cascade processes, such as a intra-nuclear cascade process, an evaporation process and a high energy fission process. An isobar model and a pre-equilibrium model can also be considered. A high energy fission model, nucleon-nucleon reaction cross sections and level density parameters were revised and applied to the NMTC/JAERI97. When neutrons produced from hadronic cascade processes are slowed down below a cut-off energy, that can be arbitrary defined by user, they are scored into a neutron history file. The position, direction, energy and importance of the cut-off neutrons are recorded. The FSOURCE code was developed to create a fixed neutron source file for a succeeding neutron transport analysis by the deterministic method. FSOURCE generates the spatial, energy and angular distributions of the cut-off neutrons from the history file. The angular distribution of the cut-off neutrons is expressed in the form of a Legendre polynomial. The number of energy groups and the order of the Legendre polynomial can be arbitrary specified by user. To transport the neutrons below cutoff energy, the two-dimensional discrete ordinate transport code TWODANT 7) is prepared. It is difficult to solve fixed neutron source problem with fissile material by Monte Carlo JENDL- 3.2 NJOY-AJAX 73Group XS Library (AMPX Master form) SCALE-4 Effective 73Group XS (ISOTXS form) NMTC/JAERI FSOURCE TWODANT Neutron Spectrum ATRAS Driver BURNER Material Comp. ATRAS Utility Input for each codes Burnup and decay chain Neutrons <20MeV Fixed Neutron Source (FIXSRC) CHFUEL NEUTP (LCS-2.7) Burnup and Decay Chain Data Cross section, Spectrum, Flux distribution etc. Fig.3 Structure of the ATRAS code system method. Source neutrons are multiplied as a function of neutron multiplication factor and this requires very long computation time to obtain the results. Therefore, for the calculation models containing fissile material, a deterministic analysis code TWODANT is selected and included into ATRAS. One unique function of ATRAS is its capability of burnup analysis for accelerator-driven systems. It is important to determine the burnup characteristics of ADS transmutor, since it specifies the efficiency of transmutation. And it should be ensured that the burnup reactivity change does not cause the core to become critical. The BURNER code, the burnup calculation module in the VENTURE 8) code system, is included into ATRAS. When the user uses BURNER together with TWODANT, it is possible to obtain the burnup characteristics by using the energy spectrum and flux distribution taking account of the spallation neutron source. In the BURNER code, the user can easily modify the burnup and decay chain of the nuclides and apply the latest data to the analysis. The program CHFUEL was developed to simulate the fuel exchange at the end of the burnup cycle. The neutron group cross section set for the ATRAS code system was prepared from the JENDL-3.2 9) cross section library. About 150 nuclides that are necessary to analyze the JAERI-proposed ADS were selected from the JENDL-3.2 library. Higher actinides such as Bk and Cf, long-lived fission products and lanthanides that would mix with MA in a dry reprocessing process were also included. Average cross sections of fission products were prepared as a lumped fission product. These lumped fission product cross sections are used to consider the nuclides which are not explicitly

considered in the burnup chain. Nuclides required for the analysis of the systems using 232 Th - 233 U fuel were also prepared. The effective cross sections for the deterministic neutron transport and burnup calculation in the low energy region are prepared by the CSAS module in the SCALE-4 10) code system. Heterogeneity of the fuel pin configuration and correction of the self-shielding factor can be considered to construct the effective cross section files. A utility program MKISO was prepared to convert the effective microscopic cross section file from the SCALE standard AMPX format to the CCCC format. To obtain the neutronics and burnup characteristics of ADTS, several calculation codes in ATRAS are used. To facilitate the data input, we developed a pre-processing program named ATRAS driver and included it into ATRAS. The user needs to specify the calculation model only once into the input data file of the ATRAS driver. Then, the ATRAS driver creates input data files for the calculation codes used in the analysis. Parameters those are required for the heterogeneous cell calculation and the analysis by TWODANT can be specified into the input data file of the ATRAS driver. The ATRAS code system adopts the CCCC format binary files to save disk space and access time, but these files are unreadable for the user. Furthermore, some calculation results like the neutron energy spectrum are listed in separate files from the hadronic cascade code and neutron transport code. A post-processing program ATRAS utility was created to read the binary files and calculate the results such as a particle energy spectrum from high energy region to low energy region, reaction rates and actinide inventories at each burnup step. The decay heat and the radiotoxicity of residual MA in the spent fuel can also be analyzed by the ATRAS utility. 3. R&D for Pb-Bi application In the reference design of ADS, Pb-Bi is selected as a primary candidate of the spallation target and primary coolant. However, many R&D are necessary to examine its feasibility. To study the compatibility of the structural material such as steel with Pb-Bi, static corrosion equipment has been installed in JAERI. The first test was performed at 823 K for 500 to 3000 hours for eight kinds of materials such as ferritic/martensitec steel, austenitic stainless steel and pure iron. It was found that the thickness of the corrosion film decreases with increasing the chromium contents in the material 11). Further tests are scheduled with changing the conditions such as the Pb-Bi temperature and the oxygen contents in the Pb-Bi; these factors are considered to largely influence the corrosion behavior. In addition to above mentioned tests, a Pb-Bi test loop has been also installed to know the corrosion behavior in the flowing Pb-Bi and to test the feasibility of mechanical device such as an electromagnetic pump and an electromagnetic flow meter. The appearance of the loop is shown in Fig.4. Three phases of 3000 hours test were performed with different conditions of test specimens and temperature. The flow speed of the Pb-Bi was fixed about 1m/s at the test section where an austenitic stainless steel pipe was used. The Pb-Bi temperature was kept at 723K at the test section, while it was cooled to 723 to 673K at the electromagnetic pump. After the operation, the test section was detached and various tests on the corrosion behavior are under way. The irradiation damage by protons and neutrons on the structural material, especially on the beam window, is one of the crucial issues for the feasibility of the ADS. Although the material database of the irradiation test will be accumulated at the ADS Target Test Facility described in section 3 of chapter III, the preliminary irradiation was carried out at the SINQ facility at the Paul Scherrer Institute in Switzerland. Small pieces of irradiated samples were transported to JAERI, and the tensile test and the fatigue test are underway at the hot cell facility. Fig.4 Pb-Bi test loop III. Transmutation Experimental Facility 1. Outline of the facility To study the basic characteristics of the ADS and to demonstrate its feasibility from viewpoints of the reactor physics and the spallation target engineering, JAERI plans to build the Transmutation Experimental Facility (TEF) in the Tokai site under a framework of the J-PARC Project as shown in Fig.5. The construction of the TEF is scheduled to start since 2006. TEF consists of two buildings: the Transmutation Physics Experimental Facility (TEF-P) and the ADS Target Test Facility (TEF-T) as shown in Fig.6. TEF-P is a zero-power critical facility where a low power proton beam is available to research the reactor physics and the controllability of the ADS. TEF-T is a material irradiation facility which can accept a maximum 200kW-600MeV proton beam into the spallation target of Pb-Bi. Details of TEF-P and TEF-T are presented in the following sections.

3 GeV Synchrotron Nuclear Physics Facility Transmutation Experimental Facility Neutrino Facility 50 GeV Synchrotron LINAC Material and Life Science Facility Fig.5 Site plan of the J-PARC project Fig.6 Transmutation Experimental Facility 2. Transmutation Physics Experimental Facility (TEF-P) Several kinds of experiments to investigate neutronic performance of the ADS have been performed worldwide. Some of them are for the characteristics of the subcritical system such as MUSE program12). MASURCA, a critical assembly for the fast reactor in France, is used with newly developed DT and DD neutron source. In Japan, subcritical experiments were just started at the Fast Critical Assembly (FCA) by using a 252Cf neutron source. Installation of DT neutron source to the FCA is also planned. Moreover, many experimental studies have been performed to the neutronics of the spallation neutron source with various target material such as lead, tungsten, mercury and uranium. These experiments for spallation target are not directly related to the ADS, but they are also useful to validate the neutronic characteristics of ADS. There has been, however, no experiment aiming at the research and the demonstration of the fast subcritical system combined with a spallation source. So the purpose of the TEF-P is divide roughly into three subjects ; 1) reactor physics aspects of the subcritical core driven by a spallation source, 2) demonstration of the controllability of the subcritical core including a power control by the proton beam power adjustment, and

3) investigation of the transmutation performance of the subcritical core using certain amount of MA and LLFP. The details of the experimental items are described later. The most serious problem to build a new nuclear facility is how to prepare the fuel, since tons of low-enriched uranium or plutonium are necessary to make the core critical or near-critical (e.g. k eff = 0.95) in the fast neutron system. We expect to use the plate-type fuel of the FCA in JAERI/Tokai, or preferably to merge FCA into TEF-P. About two tons of metallic fuel of enriched uranium and plutonium will be available as well as natural and depleted uranium. Various simulation materials required to simulate fast reactor and ADS such as lead and sodium for coolant, tungsten for solid target, ZrH for moderator, B 4 C for absorber, and AlN for nitride fuel will be prepared. TEF-P is therefore designed with referring to FCA; the horizontal table-split type critical assembly with a rectangular lattice matrix. Figure 7 shows a conceptual view of the assembly. Proton beam was introduced horizontally from the center of the fixed half assembly. neutron spectrum are measured by changing parametrically the subcriticality and the spallation source position. The material of the target will also be altered with Pb, Pb-Bi, W, and so on. The reactivity worth is also measured for the case of the coolant void and the intrusion of the coolant into the beam duct. It is desirable to make the core critical in order to ensure the quality of experimental data of the subcriticality and the reactivity worth. As for the demonstration of the hybrid system, feedback control of the reactor power is examined by adjusting the beam intensity. Operating procedures at the beam trip and the re-start are also examined. As for the transmutation characteristics of MA and LLFP, fission chambers and activation foils are used to measure the transmutation rates. The cross section data of MA and LLFP for high energy region (up to several hundreds MeV) can be measured by the Time Of Flight (TOF) technique with the proton beam of about 1ns pulse width. Several kinds of MA and LLFP samples are also prepared to measure their reactivity worth, which is important for the integral validation of cross section data. Ultimate target of the facility is to install a partial mock-up region of MA nitride fuel with air cooling to measure the physics parameters of the transmutation system. Figure 8 shows a schematic view of the partial loading of pin-type MA fuel around the spallation target. The central rectangular region (28cm x 28cm) will be replaced with a hexagonal subassembly. Fig.7 Conceptual view of TEF-P critical assembly In the experiment with the proton beam, the effective multiplication factor, k eff, of the critical assembly will be kept less than 0.98. One proton with energy of 600 MeV produces about 15 neutrons by the spallation reaction with heavy metal target such as lead. The 10 W proton beam corresponds to the source strength of 1.5x10 12 neutrons/s, which is strong enough to measure the power distribution at the deep subcritical state such as k eff = 0.90. In the conceptual design of the facility, the shielding property for high energy neutrons is calculated. About 2m thickness of concrete shield is necessary even when the core is surrounded by about 1m of lead reflector. Safety aspect of the facility is also extensively studied. The prompt critical accident can be terminated without fuel melting by the reactor scram system with multiplicity and variety. The unexpected introduction of the 10 W beam into the critical state also can be terminated safely with the reactor scram. Using TEF-P facility, many experimental studies are planned. The R&D to be carried out at TEF-P is described below. As for the neutronics in the subcritical system, power distribution, k eff, effective neutron source strength, and Fig.8 Pin-type fuel partial loading section for TEF-P The distinguished points of TEP-P in comparison with existing experimental facilities can be summarized as follows: (1) both the high energy proton beam and the nuclear fuel are available, (2) the maximum neutron source intensity of about 10 12 n/s is strong enough to perform precise measurements even in the deep subcritical state (e.g. k eff =0.90), and, is low enough to easily access to the assembly after the irradiation, (3) wide range of pulse width (1ns - 0.5ms) can be available by the laser charge exchange technique described later, (4) MA and LLFP can be used as a shape of foil, sample and fuel by installing an appropriate

shielding and a remote handling devise. 3. ADS Target Test Facility (TEF-T) JAERI proposes an ADS using a Pb-Bi for both spallation target and coolant of subcritical core. Pb-Bi is one of the alternative options of the coolant of the fast system and it also has a function of liquid spallation target simultaneously in the ADS. There are, however, many technical issues to use Pb-Bi. To solve them, several R&D programs are proposed. Material irradiation experiment in stagnant Pb-Bi environment has been performed at the SINQ facility in Paul Scheller Institute, Switzerland. MEGAPIE project 13) are planned to demonstrate feasibility of Pb-Bi target by using the existing accelerator facilities. According to the limitation of existing equipments of the facility and machine time, experimental data obtained from these programs are limited. So, parametric and systematic experimental data are required to perform the detailed design of the ADS. TEF-T aims at preparation of the database required for ADS design. Another important component for ADS is a beam window. Beam window forms a boundary between an accelerator and a subcritical core. Beam window suffers heavy irradiation of proton and spallation neutron, mechanical stress caused by the pressure difference between the accelerator and flowing Pb-Bi target, thermal stress arising from heat deposition of high energy particles and beam transients (startup, shutdown and beam trip) and chemical interaction with Pb-Bi. It is important to prepare the database to estimate a lifetime of the beam window. So that, the experiments to obtain the design database for beam window are also the important mission of TEF-T. Some technical subjects must be investigated for the high-power spallation target system, e.g. the purification system for spallation products and the polonium, remote handling device for the Pb-Bi system, and so on. R&D of these items is, also necessary to build TEF-T. Hence, non-radioactive tests described later have been performed at JAERI. TEF-T mainly consists of a Pb-Bi spallation target, a Pb-Bi cooling system (primary loop), a helium gas cooling system (secondary loop) and an access cell to handle irradiation test pieces. Pb-Bi eutectic is filled into a cylindrical vessel made by type 316 stainless steel. An effective size of the vessel is about 15cm diameter and 60cm long. Several kinds of target are planned and designed according to the objective of the experiment. One of the target vessels is designed to irradiate ten or more irradiation samples in the flowing Pb-Bi environment. A primary Pb-Bi loop is designed to allow Pb-Bi flow with 2 m/s of a maximum velocity and 723K of maximum temperature. Though we selected type 316 stainless steel as a structural material of the target vessel, other candidate material can be used according to the result of corrosion test in Pb-Bi cold loop. Target vessel is mounted on a movable trolley and is to be withdrawn to the access cell after the irradiation. The access cell has functions to replace target vessel, to clean up residual Pb-Bi to reduce exposure dose by the spallation products, and to pick up irradiated material test pieces remotely. The primary cooling devices are also located in the access cell to make a path of the loop short and improve maintainability. Neutronic analysis of the Pb-Bi target was performed. Pb-Bi (45%Pb-55%Bi) is filled in a cylindrical vessel made by type 316 stainless steel with 1mm thick. Average Pb-Bi temperature is assumed to 400 degree centigrade. An ATRAS code system described in the paper was used. Figure 9 shows a 1 to 1 scale target model. Fig.9 Pb-Bi spallation target model (1/1 scale) Figure 10 indicates axial DPA distribution of the irradiation sample made by type 316 stainless steel at various radial positions. Profile of the beam is assumed as a Gaussian shape and annual operation time assumes 4,500 hours. A radiation dose over 10 DPA is observed on the sample at 1 st and 2 nd column. The figures indicate that the Pb-Bi target of TEF-T has enough performance to irradiate samples at ADS operating condition by adjusting the beam profile. Fig.10 Axial DPA distribution in irradiation IV. Conclusion After the basic R&D mentioned above and the experiments in the TEF, an experimental ADS with thermal

power of 80MW is considered to become necessary in late 2010s to demonstrate the feasibility of the ADS from engineering aspects. The experimental ADS will be operated by MOX fuel at first and the fuel will be gradually altered to MA nitride fuel which will be supplied from the fuel fabrication pilot plant. The demonstration of the MA transmutation will be completed by 2030, including the reprocessing of the nitride fuel irradiated in the experimental ADS. The ADS is the innovative and flexible nuclear system to incinerate the long-lived nuclear waste. It is also considered to be used for energy production and for 233 U production from 232 Th. The ADS is, therefore, suitable for many kinds of scenarios for nuclear power development. This fact means that the ADS can be deployed in many nations and hence its research and development can be effectively promoted by international collaborations. To establish the technical basis for ADS, the construction of TEF is proposed under the J-PARC Project. TEF consists of two buildings: TEF-P and TEF-T. These buildings are connected by the beam transport, which includes a special device to extract very low power proton beam. A current status of design study of TEF was summarized. TEF-P is a critical assembly, which can accept the 600 MeV - 10 W proton beam for the spallation neutron source. The purposes of TEF-P are the experimental validation of the data and method to predict neutronics of the fast subcritical system with spallation neutron source, the demonstration of the controllability of a hybrid system driven by an accelerator, and the basic research of reactor physics for transmutation of MA and LLFP. TEF-T is a facility to perform the experiments to prepare the database for engineering design of ADS using 600 MeV - 200 kw proton beam and the Pb-Bi spallation target. The purposes of TEF-T are R&D for the irradiation damage of the beam window, the compatibility of the structural material with flowing liquid Pb-Bi and the operation of the high power spallation target. The neutronic, thermalhydraulic and structural characteristics of the Pb-Bi target were described. Combining the experimental results and experiences obtained at both facilities, the feasibility of the ADS will be evaluated and demonstrated. References 1) H. Takano, et al., "Transmutation of Long-Lived Radioactive Waste Based on Double-Strata Concept", Progress in Nuclear Energy, 37, 371 (2000). 2) K. Tsujimoto, et al., "Accelerator-Driven System for Transmutation of High-Level Waste", Progress in Nuclear Energy, 37, 339 (2000). 3) The Joint Project Team of JAERI and KEK, "The Joint Project for High-Intensity Proton Accelerators", JAERI- Tech 99-056 (KEK Report 99-4, JHF-99-3) (1999). 4) T. Sasa, et al., Accelerator-driven Transmutation Reactor Analysis Code System -ATRAS-, JAERI-Data/Code 99-007 (1999) 5) R. Douglas O' Dell, Standard Interface Files and Procedures for Reactor Physics Codes, Version IV, LA-6941-MS (1977). 6) H. Takada, et al., An Upgrade Version of the Nucleon Meson Transport Code:NMTC/JAERI97, JAERI-Data/Code 98-005 (1998). 7) R. E. Alcouffe, et al., Users Guide for TWODANT: A Code Package for Two-Dimensional, Diffusion- Accelerated, Neutral-Particle Transport, LA-10049-M (1990). 8) BOLD VENTURE IV, A Reactor Analysis Code System, Version IV, CCC-459 (1980). 9) T. Nakagawa, et al., JENDL-3 Revision 2, J. Nucl. Sci. Technol. 32, 1259 (1995). 10) SCALE-4 A Modular Code System for Performing Standardized Computer Analysis for Licensing Evaluation, CCC-545 (1990). 11) Y. Kurata, et al., "Corrosion Studies in Liquid Pb-Bi Alloy at JAERI: R&D Program and First Experimental Results", J. Nucl. Mater. 301, 28-34 (2002). 12) J. F. Lebart, et al., Experimental Investigation of Multiplying Subcritical Media in Presence of an External Source Operating in Pulsed or Continuous Mode : the MUSE-3 Experiment, Proc. of the 3rd. International Conference on Accelerator Driven Transmutation Technologies and Applications, ADTTA99, 7-11 June, 1999, Prague, Czech (1999) 13) G. S. Bauer, et al., MEGAPIE, a 1 MW Pilot Experiment for a Liquid Metal Spallation Target, Proc. of the Fifteenth Meeting of the International Collaboration on Advanced Neutron Sources, ICANS-XV, Tsukuba, Japan, 6-9 November, 2000, JAERI-Conf 2001-002 (KEK Proceedings 2000-22), Vol. II, p.1146 (2001).