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Recruitment for Postdoctoral Fellow
(Fixed-term researcher)

  1. Physics Chemistry Mathematics Geo and Environemtal Sciences Biology Radiation
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    Department Section Location Contact Person Radiation Worker/
    Non-Radiation Worker
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    (for reference)
    Summary
    J1Research on measures to strengthen nuclear nonproliferation and nuclear security
    Integrated Support Center for Nuclear Nonproliferation and Nuclear SecurityPolicy Research OfficeHead OfficeKazunori SUDA
    Tel:029-282-0495
    E-mail: suda.kazunori@jaea.go.jp
    Non-Radiation WorkerOther
    In consideration of importance and necessity of enhancing nuclear nonproliferation and nuclear security, a post doctorial fellow is expected to conduct various researches and analyses on nuclear nonproliferation and nuclear security, including assesment of nuclear proliferation and nuclear security risks, measures to reduce such risks as well as how to manage such risks, and possible mechanisms to strengthen existing international frameworks for nuclear nonproliferation and nuclear security.
    J2R&D for Laser Processing Simulation Code with Laser Processing Experiment and Deployment of Sensing Technology
    Tsuruga Center for International and Regional CollaborationApplied Laser Technology InstituteTsuruga Head OfficeToshiharu Muramatsu
    E-mail: muramatsu.toshiharu@jaea.go.jp
    Non-Radiation WorkerMechanics
    Material
    Applied Physics
    Computer and Information
    Measurements and Instruments
    Material
    We are developing laser processing technologies for industrial applications. First, the development of simulation code named "SPLICE" should be advanced to improve the numerical turbulent model and to optimize the parameters. High power laser processing experiment is needed for quantitative analysis. New laser systems and several sensing technologies are required for structural health monitoring with multiple sensors. Heat resistant optical fiber sensor has been installed on the piping system of demo-plant. Data remote processing is needed for monitoring the integrity.

    ※Energy base-ization of research and development Fukui-ken advances, they're the research and development concerned with advance of laser improvement process simulation code SPLICE developed aiming at contribution to a plan, and I make them promote more prefecture use of SPLICE cable through an outcome of this case. All together, I aim at preservation optics in atomic energy and innovation of status monitoring.
    J3Study on feasibility and effectiveness evaluation for severe accident countermeasures
    Nuclear Safety Research CenterSevere Accident Analysis Research GroupTokai Research and Development Center
    Nuclear Science Research Institute
    Tomoyuki Sugiyama
    Tel:+81-29-282-5253
    E-mail: sugiyama.tomoyuki@jaea.go.jp
    Non-Radiation WorkerPhysics
    Chemistry
    Mechanics
    Material
    Applied Physics
    Computer and Information
    Other
    This research aims at development of analysis models and tools to improve evaluation techniques of severe accident countermeasures. One of the following tasks or that related to the tasks is carried out.
    - Source term analysis of Fukushima daiichi NPS accident using the SA analysis code THALES2/KICHE.
    - Analysis of fluid dynamic behaviors of core melt in containment vessel using the mechanistic FCI code JASMINE.
    - Analysis of thermal-hydraulic and deflagration/detonation behaviors of hydrogen in containment vessel or reactor building using the open CFD code OpenFOAM.
    J4Study on the methodology of the structural integrity assessment for nuclear reactor components
    Nuclear Safety Research CenterStructural Integrity Research GroupTokai Research and Development Center
    Nuclear Science Research Institute
    Yinsheng Li
    Tel:+81-29-282-6457
    E-mail: li.yinsheng@jaea.go.jp
    Non-Radiation WorkerMechanics
    Material
    Applied Physics
    Physics
    Architectural and Civil Engineering
    Computer and Information
    Because of the ageing degradation due to long term operation for Japanese nuclear power plants, developing the methodologies of structural integrity assessments for the reactor components concerning neutron irradiation, stress corrosion cracking and so on is of great importance. In this theme, researches on the deterministic approaches such as weld residual stress evaluation, crack propagation evaluation under large scale yielding condition, fracture evaluation concerning the crack or thinning for nuclear components are conducted on the basis of numerical simulation, material testing, and fracture testing and so on. In addition, probabilistic fracture mechanics analysis codes concerning ageing degradation of nuclear components are developed on the basis of the knowledge obtained from simulation and testing.
    J5Study on aging degradation of nuclear reactor structural materials under irradiation
    Nuclear Safety Research CenterMaterials and Water Chemistry Research GroupTokai Research and Development Center
    Nuclear Science Research Institute
    Yutaka Nishiyama
    Tel:+81-29-282-5044
    E-mail: nishiyama.yutaka93@jaea.go.jp
    Radiation WorkerMechanics
    Material
    Measurements and Instruments
    In the nuclear reactor structural materials used under irradiation, the material properties, the interface reactions with the coolant and the stress conditions etc. change simultaneously. They are important phenomena to evaluate the aging degradation of light water reactors.
    In this study, for ferritic steels and austenitic stainless steels used as the nuclear reactor structural materials, the changes in material and mechanical properties (such as microstructure, crack growth and fracture toughness etc.) induced by irradiation are investigated. From these results, the effects on the structural integrity of the reactor pressure vessels and the core internals are evaluated.
    J6Experimental and analytical study on thermohydraulic safety of the light water reactor
    Nuclear Safety Research CenterThermohydraulic Safety Research GroupTokai Research and Development Center
    Nuclear Science Research Institute
    Taisuke Yonomoto
    Tel:+81-29-282-5263
    E-mail: yonomoto.taisuke@jaea.go.jp
    Non-Radiation WorkerMechanics
    Measurements and Instruments
    Computer and Information
    This experimental and analytical research focuses on thermo-hydraulic phenomena occurring in the reactor and the containment of the nuclear power plant during an accident before and after core damage. For the experimental study, two-phase flow and/or heat transfer are investigated using a high-pressure reactor simulation test facility or a small-scale test device that exits or will be built for this research. The development of the two-phase flow measurement technique is also an important topic for this research. By using the data obtained from the experiments, prediction models are validated and improved in order to be used in lumped parameter codes such as RELAP5 and MELCOR, or the CFD codes. A specific research topic will be selected considering the request by the applicant.
    J7Study on high-temperature oxidation behavior of fuel cladding
    Nuclear Safety Research CenterFuel Safety Research GroupTokai Research and Development Center
    Nuclear Science Research Institute
    Masaki Amaya
    Tel:+81-29-282-5028
    E-mail: amaya.masaki@jaea.go.jp
    Non-Radiation WorkerMaterial
    Mechanics
    It has been reported that a oxidation rate of light-water-reactor fuel cladding might rapidly increase when the fuel cladding was exposed to high-temperature steam for a long period, which is so-called "breakaway oxidation". In order to evaluate the embrittlement of fuel cladding under a loss-of-coolant accident (LOCA), it is important to consider the breakaway oxidation. However, sufficient information has not been obtained about the initiation condition of the breakaway oxidation and the effect of the breakaway oxidation on the mechanical strength of fuel cladding. In this study, the change of the high-temperature oxidation kinetics of fuel cladding, which may lead to the breakaway oxidation, will be investigated by conducting high-temperature oxidation tests of fuel cladding specimens under simulated LOCA conditions. Mechanical tests will be also conducted on the oxidized specimens in order to evaluate the effect of the change in high-temperature oxidation behavior on mechanical strength of fuel cladding.
    J8Experimental Research on Safety Assessment of Storage and Disposal of Radioactive Waste
    Nuclear Safety Research CenterWaste Safety Research GroupTokai Research and Development Center
    Nuclear Science Research Institute
    Tetsuji Yamaguchi
    Tel:+81-29-282-6001
    E-mail: yamaguchi.tetsuji@jaea.go.jp
    Radiation WorkerChemistry
    Geo and Environemtal Sciences
    Material
    Chemical Engineering
    Safety assessments of storage and disposal of radioactive wastes require quantitative analysis of long-term alteration of barrier materials used in storage and disposal systems. This study investigates long-term alteration behavior such as corrosion, dissolution and alteration of glass, metals, clays, concretes and polyethlene focusing on primary factors such as adjacent barrier materials, groundwater composition, geology, colloids, microbes and radiolysis. The goal is to obtain scientific basis for models evaluating changes in the barrier functions and for systematical establishment of datasets.
    J9Study on analytical techniques for individual particles containing nuclear materials in environmentl samples
    Nuclear Safety Research CenterResearch Group for Safeguards Analytical ChemistyTokai Research and Development Center
    Nuclear Science Research Institute
    Fumitaka Esaka
    Tel:+81-29-282-6165
    E-mail: esaka.fumitaka@jaea.go.jp
    Radiation WorkerChemistry
    Physics
    Analysis of trace amounts of nuclear materials in environmental samples taken at nuclear facilities in the world is performed to reveal nuclear activities, which is important for nuclear non-proliferation. In this study, analytical techniques for such samples are developed. For example, in order to clarify elemental composition, chemical states and isotopic composition, individual micron-sized particles containing uranium and/or plutonium are measured by using scanning electron microscopy, total-reflection X-ray analysis, micro-Raman spectroscopy and secondary ion mass spectrometry.
    J10Study on a Level 3 Probabilistic Risk Analysis of nuclear power plants
    Nuclear Safety Research CenterRadiation Risk Analysis Research GroupTokai Research and Development Center
    Nuclear Science Research Institute
    Masanori Kimura
    Tel:+81-29-282-5459
    E-mail: kimura.masanori@jaea.go.jp
    Non-Radiation WorkerPhysics
    Chemistry
    Mathematics
    Geo and Environemtal Sciences
    Radiation
    Architectural and Civil Engineering
    Computer and Information
    A level 3 probabilistic risk assessment (PRA) is an offsite consequence analysis for a severe accident and estimates the frequency and severity of the consequences to the public. Probabilistic accident consequence assessment models and computer codes are an integral part of level 3 PRA of nuclear power plants. Our research group has developed a level 3 PRA code, OSCAAR. In this theme, researches on the probabilistic accident consequence assessment for health effects and economic consequence are conducted considering site-dependent on metrological, population, agricultural and economic data by using OSCAAR.
    J11Study on release and transport behavior of radioactive materials in reprocessing plant under severe accident conditions
    Nuclear Safety Research CenterFuel Cycle Safety Research GroupTokai Research and Development Center
    Nuclear Science Research Institute
    Hitoshi Abe
    Tel:+81-29-282-6672
    E-mail: abe.hitoshi@jaea.go.jp
    Non-Radiation WorkerChemistry
    Physics
    Newly defined as as severe accidents in fuel reprocessing plant are organic solvent fire in cell as well as boiling and exsiccation of highly-active liquid waste in concentrators. Therefore, establishment of method for evaluating their effect on the public dose and effectiveness of countermeasures for the accidents become an urgent issue. Purposes of this study are 1) acquiring data about release, transport and confinement of radioactive materials under the accident conditions and 2) establishing a simulation code to evaluate the accident evolution with high applicability.
    J12Study on the volcanic activity evaluation in a geological radioactive waste disposal
    Nuclear Safety Research CenterEnvironmental Safety Research GroupTokai Research and Development Center
    Nuclear Science Research Institute
    Seiji Takeda
    Tel:+81-29-282-6170
    E-mail: takeda.seiji@jaea.go.jp
    Non-Radiation WorkerApplied Chemistry
    Physics
    Geo and Environemtal Sciences
    Measurements and Instruments
    In a safety assessment of geological radioactive waste disposal, it is necessary to estimate the environmental impact at the site due to occurrence of natural phenomenon such as a volcanic activity, an earthquake and fault activity. In this theme, the research on the volcanic activity evaluation characterized by magma residence time, accumulated volume and temporal distribution of magma is conducted, in order to estimate the thermal and/or geochemical effects of a disposal site by a volcanic activity.
    J13Research on Criticality Safety/Management of Damaged- or Molten-Fuel formed by Severe Accidents
    Nuclear Safety Research CenterCriticality Safety Research GroupTokai Research and Development Center
    Nuclear Science Research Institute
    Kotaro Tonoike
    Tel:+81-29-284-3762
    E-mail: tonoike.kotaro@jaea.go.jp
    Radiation WorkerPhysics
    Computer and Information
    Applied Physics
    Other
    It is important to establish both the cooling and the criticality control of fuel debris after the severe accident, such as the Fukushima Daiichi accident, where large amount of fuel is damaged and melts. It is difficult, however, to control the situation of fuel debris and the coolant flow path, which leads the difficulty in securing the subcritical condition. Thus, the evaluation of re-criticality risk is necessary. In this research, critical mass, kinetic parameters, etc. of fuel debris will be obtained by computation; and critical experiments to validate the computation will be studied as well.
    J14Nuclear reaction and structure study for exotic nuclei
    Sector of Nuclear Science Research Advanced Science Research CenterResearch Group for Heavy Element Nuclear Science
    Tokai Research and Development Center
    Nuclear Science Research Institute
    Katsuhisa Nishio
    Tel:+81-29-282-5454
    E-mail: nishio.katsuhisa@jaea.go.jp
    Radiation WorkerPhysics
    Applied Physics
    Mathematics
    Measurements and Instruments
    Other
    Experimental nuclear physics programs dedicated to exotic nuclei such as neutron-rich, proton-rich and super-heavy nuclei will be promoted. Challenge to find a new phenomenon in nuclear structure, nuclear reaction and fission processes will be highly encouraged. Experiments will be carrieod out using JAEA facility and also other facilities inside and outside Japan to produce exotic nuclei and unique states in nuclei. (http://asrc.jaea.go.jp/soshiki/gr/HENS-gr/index_e.html)
    J15Chemical properties of superheavy elements
    Sector of Nuclear Science Research Advanced Science Research CenterResearch Group for Heavy Element Nuclear Science
    Tokai Research and Development Center
    Nuclear Science Research Institute
    Kazuaki Tsukada
    Tel:+81-29-282-5491
    E-mail: tsukada.kazuaki@jaea.go.jp
    Radiation WorkerChemistry
    Physics
    Measurements and Instruments
    The main objective is to understand chemical properties of superheavy elements (SHEs) placed at the uppermost end of the Periodic Table. This theme will focus on the valence electronic structure of SHEs that is experimentally evaluated from their redox potentials, ionic radii, and compound formations as well as the development of chemical analysis methods for SHEs on an "atom-at-a-time" basis. (http://asrc.jaea.go.jp/soshiki/gr/HENS-gr/nc/index-e.htm)
    J16Physics and chemistry studies for superheavy elements by using slow superheavy-element beams
    Sector of Nuclear Science Research Advanced Science Research CenterResearch Group for Heavy Element Nuclear Science
    Tokai Research and Development Center
    Nuclear Science Research Institute
    Masato Asai
    Tel:+81-29-282-5490
    E-mail: asai.masato@jaea.go.jp
    Radiation WorkerPhysics
    Chemistry
    Radiation
    Measurements and Instruments
    Nuclear physics, nuclear chemistry, and atomic and molecular physics of superheavy elements are studied through developments of new methods utilizing slow superheavy-element beams. The research subjects are as follows: developments of superheavy-element-beam production and ion-guide techniques; ionization-energy measurements; nuclear-structure and fission studies using an on-line isotope separator; nuclear mass measurements; surface adsorption and molecular formation studies for superheavy elements. These developments and experiments are mainly performed at the JAEA Tandem Accelerator Facility.
    J17Development of metal recognition reagents and high efficient chemical separation systems
    Sector of Nuclear Science Research Advanced Science Research CenterResearch Group for Interfacial Reaction-Field ChemistryTokai Research and Development Center
    Nuclear Science Research Institute
    Hirochika Naganawa
    Tel:+81-29-282-6615
    E-mail: naganawa.hirochika@jaea.go.jp
    Radiation WorkerChemistry
    Applied Chemistry
    Chemical Engineering
    The purpose of this research is to develop new chemical separation and sensing technologies having high efficiency and sensitivity for radioactive materials in environmental samples and valuable metals in industrial wastes. Specifically, separation systems for actinides, rare(minor) metals, precious metals, and heavy metals will be developed by using new extractants, adsorbents, and biomaterials that have high selectivity and binding ability for the metal ions. In this theme, fundamental and practical studies go together by applying "emulsion flow extractor" of a new-type extracting device.
    J18Hadron and Nuclear Physics at J-PARC
    Sector of Nuclear Science Research Advanced Science Research CenterResearch Group for Hadron and Nuclear PhysicsTokai Research and Development Center
    Nuclear Science Research Institute
    Hiroyuki Sako
    Tel:+81-29-284-3113
    E-mail: sako.hiroyuki@jaea.go.jp
    Radiation WorkerPhysics
    The successful candidate will work on either experimental or theoretical research of hadron and nuclear physics at J-PARC. The experimental research includes R&D of a fast DAQ system for J-PARC Heavy-Ion Program and experimental studies with the kaon beamlines or the high momentum beamline at J-PARC. The theoretical research includes hadron and nuclear physics related to J-PARC, and promotion of international theoretical research activities.
    J19Electronic property of heavy element systems
    Sector of Nuclear Science Research Advanced Science Research CenterResearch Group for Materials Physics for Heavy Element SystemsTokai Research and Development Center
    Nuclear Science Research Institute
    Shinsaku Kambe
    Tel:+81-29-284-3525
    E-mail: kambe.shinsaku@jaea.go.jp
    Radiation WorkerPhysics
    Applied Physics
    Material
    Condensed matter physics in heavy element systems. Particularly magnetism and superconductivity in f-electron compounds.
    J20Theoretical study on spin-energy transformation materials
    Sector of Nuclear Science Research Advanced Science Research CenterResearch Group for Spin-energy Transformation ScienceTokai Research and Development Center
    Nuclear Science Research Institute
    Michiyasu Mori
    Tel:+81-29-284-3508
    E-mail: mori.michiyasu@jaea.go.jp
    Non-Radiation WorkerPhysics
    Mathematics
    Material
    A successful candidate will theoretically study spin- and thermal-transport properties using some numerical techniques such as density functional theory, density matrix renormalization group method, quantum Monte Carlo method and so on. Thermoelectric materials, primarily related to spin Seebeck effect, and radiation-proof devices will be also important subjects of candidate.
    J21Materials science research by using a muon beam
    Sector of Nuclear Science Research Advanced Science Research CenterResearch Group for Nanoscale Structure and Function of Advanced MaterialsTokai Research and Development Center
    Nuclear Science Research Institute
    Wataru Higemoto
    Tel:+81-29-284-3873
    E-mail: higemoto.wataru@jaea.go.jp
    Radiation WorkerPhysics
    Chemistry
    Material
    Applied Physics
    Applied Chemistry
    Measurements and Instruments
    The applicant will be involved in materials science research by using accelerator-produced muons, which are implanted into a material and used as a sensitive local probe. In our group, the applicant will be able to use advanced muon beams, such as an ultra-slow muon beam in J-PARC, to investigate various functional materials. Instrumentation is also encouraged for the purpose.
    (http://asrc.jaea.go.jp/soshiki/gr/Nanoscale-gr/index.html)
    J22Research and development of minor actinide separation process from high level liquid waste
    Nuclear Science and Engineering CenterResearch Croup for Partitioning, Partitioning and Transmutation Technology DivisionTokai Research and Development Center
    Nuclear Science Research Institute
    Tatsuro Matsumura
    Tel:+81-29-282-6673
    E-mail: matsumura.tatsuro@jaea.go.jp
    Radiation WorkerChemistry
    Applied Chemistry
    Chemical Engineering
    In order to reduce the burden of the geological disposal of high level waste (HLW), partitioning and transmutation technology has been investigated. Since minor actinides have high radiotoxity and long half lives, the separation from HLW is very important. The subject of this theme is development of recovery and separation process of minor actinides with novel extractant from HLW for partitioning and transmutation technology. In this study, the novel extractants which has high selectivity of americium and curium from high level liquid waste will be studied and evaluated applicability for practical separation process. The experiments using minor actinides and high level liquid waste in glove boxes and hot cells will be carried out.
    J23Study on Accurate Neutron Cross Section Measurement
    Nuclear Science and Engineering CenterNuclear Data Center,
    Nuclear Data and Reactor Engineering Division
    Tokai Research and Development Center
    Nuclear Science Research Institute
    Atsushi Kimura
    Tel:+81-29-282-5796
    E-mail: kimura.atsushi04@jaea.go.jp
    Radiation WorkerPhysics
    Measurements and Instruments
    Accurate nuclear data for minor actinides (MAs) and long-lived fission products (LLFPs) are required for the development of nuclear transmutation systems, since present uncertainties are large. In order to decrease the uncertainties of the cross sections, we have been carrying out neutron-TOF experiments using ANNRI installed at BL04/MLF/J-PARC and other facilities. The assigned post-doc fellow is requested to perform one or more topics from; 1) Capture, fission and total cross-section measurements with neutron-TOF method, 2) Calculation of the detector weighting function in ANNRI, 3) Resonance analysis of the obtained cross sections.
    J24Research on high-performance oxygen sensor for liquid lead-bismuth eutectic
    Nuclear Science and Engineering CenterResearch Group for Corrosion Resistant Materials, Fuels and Materials Engineering DivisionTokai Research and Development Center
    Nuclear Science Research Institute
    Fumiyoshi Ueno
    Tel:+81-29-284-3581
    E-mail: ueno.fumiyoshi@jaea.go.jp
    Non-Radiation WorkerMaterial
    Chemical Engineering
    In JAEA, for the purpose of reducing the radioactive waste, Accelerator Driven System (ADS) for transmuting radioactive materials is developing. ADS is used lead-bismuth eutectic (LBE) liquid metal in the coolant and spallation target. Corrosion behavior of metallic material such as stainless steel changes by the oxygen concentration in the high temperature LBE, it is necessary to develop a high-performance sensor for measuring the oxygen concentration in the LBE. Therefore, in this theme, as fundamental research for measuring the oxygen concentration in the LBE with high accuracy, we will assemble a prototype oxygen sensor to perform measurement test. The effect of the impurities in LBE on measurement accuracy of the sensor will be investigated by analysis of surface deposits, thermodynamic analysis and electrochemical analysis.
    J25Evaluation of correlation between changes in microstructure and mechanical properties in irradiated materials (metal, steel, and ceramics)
    Nuclear Science and Engineering CenterResearch Group for Radiation Materials Engineering, Fuels and Amterials Engineerign DivisionTokai Research and Development Center
    Nuclear Science Research Institute
    Shinichiro Yamashita
    Tel:+81-29-282-5391
    E-mail: yamashita.shinichiro@jaea.go.jp
    Radiation WorkerRadiation
    Material
    Physics
    Mechanics
    In order to increase safety and integrity in existing and future nuclear power plants, micrstructural observation and a wide variety of mechanical strength tests (tensile, hardness measurement, and toughness etc) of nuclear reactor component materials such as structural material and simulated fuel-like oxide irradiated at various environmental conditions will be performed. Based on the experimental data acquired, a correlation between changes in microstructure and mechanical properties in the materials will be evaluated. In addition to that, it is possible to conduct fundamental study on radiation damage for the materials. Through these works, it is expected that synergistic function among environmental factors (irradiation, thermal load, stress, atmosphere etc) influencing on correlation evaluation for those materials will be clarified, contributing increment of safety and integrity in the existing/future nuclear power plants.
    J26Study on carbon cycling in terrestrial ecosystems and its interaction with environmental changes, using radioactive and stable carbon isotope analysis
    Nuclear Science and Engineering CenterResearch Group for Radiochemistry, Environment and Radiation Sciences DivisionTokai Research and Development Center
    Nuclear Science Research Institute
    Dr. Jun Koarashi
    Tel:+81-29-282-5903
    E-mail: koarashi.jun@jaea.go.jp
    Non-Radiation WorkerGeo and Environmental Sciences
    Biology
    Chemistry
    Measurements and Instruments
    There is growing concern that recent rapid changes in climate and environment could have a significant influence on carbon cycling in terrestrial ecosystems and could consequently lead to a positive feedback for global warming. However, the magnitude and timing of this effect remain highly uncertain due to a lack of quantitative understanding of the migration and storage processes of carbon in terrestrial ecosystems (especially forests) and their responses to the changes in environment. In this study, we will conduct field (with different ecosystem properties) and laboratory (under controlled environmental conditions) experiments to quantify the processes and their interactions with changes in environment, using radioactive (14C) and stable carbon isotopes as tracers for carbon cycling in terrestrial ecosystems.
    J27Research and development of non-destructive analysis for nuclear materials.
    Nuclear Science and Engineering CenterResearch Group for Nuclear Sensing, Nuclear Data and Reactor Engineering DivisionTokai Research and Development Center
    Nuclear Science Research Institute
    Yosuke Toh
    Tel:+81-29-282-6211
    E-mail: toh.yosuke@jaea.go.jp
    Radiation WorkerMeasurements and Instruments
    Physics
    Radiation
    Applied Physics
    Non-destructive analysis of nuclear materials is required in many fields, namely nuclear non-proliferation and nuclear security, nuclear decommissioning, nuclear transmutation and nuclear industry. In this research, non-destructive techniques of nuclear materials and long-lived radioisotopes, which are difficult to quantify by conventional methods, are developed by combining several method, such as neutron and gamma-ray detection and imaging techniques.
    J28Research and Development of Evaluation Method for Core Degradation and Release of Radioactive Materials at LWR Accident
    Nuclear Science and Engineering CenterDevelppment Group for Thermal-Hydraulics Technology, LWR Key Technology Development DivisionTokai Research and Development Center
    Nuclear Science Research Institute
    Hiroyuki Yoshida
    Tel:+81-29-282-5275
    E-mail: yoshida.hiroyuki@jaea.go.jp
    Radiation WorkerPhysics
    Chemistry
    Material
    Mechanics
    A coupled analysis method of thermal-hydraulics and chemical reaction is developed to evaluate core degradation and release of radioactive materials in Light Water Reactor (LWR) accidents in this study. In detail, numerical methods and models simulating thermal-hydraulic behavior with chemical reactions are developed to solve melting of nuclear fuel and metals, release of radioactive materials and relocation of molten and released materials. In addition, new thermal-hydraulic and chemical reactions experiments are performed to validate developed methods and models. By developing this method, basic knowledge to understand multi-physics phenomena at LWR accidents is obtained, and numerical models for severe accident analysis codes are improved.
    J29Research of fatigue evaluation method of target vessel for high-power spallation neutron source
    Sector of Nuclear Science Research,
    J-PARC Center
    Materials and Life Science Division
    Neutron Source Section
    J-PARCEiichi Wakai
    Tel:+81-29-284-3745
    E-mail: wakai.eiichi@jaea.go.jp
    Radiation WorkerMaterial
    Mechanics
    Measurements and Instruments
    In Materials and Life Science Experimental Facility (MLF) of J-PARC, it is required to develop the spallation neutron source for the stable operation at 1 MW proton beam power, and various researches of the mercury target vessel are performing by the quantitative evaluation method. In this theme, there are some research subjects as follows: (1) Study of the fatigue phenomenon and thermal stress in the mercury vessel induced by the pulsed proton beam, (2) The experimental technology R&D including the fatigue properties and the testing to improve and advance the evaluation method of life time estimation of the target vessel, (3) The related systematic studies of the spallation neutron source and the target vessel for the stable operation at 1 MW.
    J30Study of Performance Improvement for the J-PARC Accelerators
    Sector of Nuclear Science Research,
    J-PARC Center
    Accelerator Division
    J-PARCMichikazu Kinsho
    Tel:81-29-284-3172
    E-mail: kinsho.michikazu@jaea.go.jp
    Radiation WorkerPhysics
    Applied Physics
    Radiation
    Electricity and Electronics
    Measurements and Instruments
    The goal of the J-PARC proton accelerators is to achieve stable beam operation at 1 MW. Beam loss reduction is crucial to increase beam power and to achieve stable operation. And also, long-lasting components are important for reliable operation. The subject of this theme is to study beam loss reduction for the J-PARC linac and/or 3 GeV Synchrotron (RCS). He/she will perform a study of beam diagnostics, beam loss handling and component development for stabler operation.
    J31The experimental study to elucidate the relationship between functions and dynamics of bio-macromolecules using deuterated samples
    Sector of Nuclear Science Research,
    J-PARC Center
    Neutron Science Section
    Materials and Life Science Division
    J-PARCKaoru Shibata
    Tel:+81-(0)29-284-3199
    E-mail: shibata.kaoru@jaea.go.jp
    Radiation WorkerBiology
    Chemistry
    Measurements and Instruments
    By mainly using the inelastic and quasielastic scattering spectrometer DNA installed in J-PARC/MLF neutron facility, the corresponding researcher will perform the experimental study to investigate the relationship between functions and dynamics of bio-macromolecules, such as the molecular mechanisms of the functions of enzymatic proteins, using particularly the deuterated protein samples.
    Therefore, it will be given special importance that the corresponding researcher has the extensive experience of preparation of bio-macromolecules, especially proteins by using bacterial expression systems.
    The corresponding researcher will also be expected to perform the research assistance for the related research fields in addition to his/her own research.
    J32Development of Neutron Detectors at Materials and Life Science Facility of J-PARC
    Sector of Nuclear Science Research,
    J-PARC Center
    Materials and Life Science Division
    Neutron Instrumentation Section
    J-PARCKaoru Sakasai
    Tel:+81-29-284-3519
    E-mail: sakasai.kaoru@jaea.go.jp
    Radiation WorkerRadiation
    Measurements and Instruments
    Electricity and Electronics
    The work of neutron instrumentation section focuses on development of various neutron detectors and neutron optical devices for Materials and Life Science Facility (MLF) of J-PARC. Construction of a new neutron diffractometer for analysis of large protein-crystals is now under planning at the MLF. The neutron detectors for the diffractometer are required to have high performances such as large sensitive area and high spatial resolution. The successful applicant will participate in the development of such detectors using scintillators.
    J33Development of lead-bismuth spallation target
    Sector of Nuclear Science Research,
    J-PARC Center
    Nuclear Transmutation Division
    Target Technology Development Section
    J-PARCToshinobu Sasa
    Tel:+81-29-282-5364
    E-mail: sasa.toshinobu@jaea.go.jp
    Non-Radiation WorkerPhysics
    Material
    Measurements and Instruments
    Robotics
    Computer and Information
    JAEA plans to build Transmutation Experimental Facility (TEF) to realize innvative accelerator-driven systen (ADS) for transmutation of long-lived radioactive nuclides. R&Ds to install a 250kW lead-bismuth spallation target in TEF for material irradiation, such as simulation of neutronic- and thermal-hydraulic performance, development of target components and instruments, and remote handling systems, will be performed.
    J34Development and application of spin-contrast variation technique on structual study of complex materials using polarized neutron and polarized protons
    Materials Sciences Research Center Hierarchical Structure Research GroupTokai Research and Development Center
    Nuclear Science Research Institute
    Takayuki Kumada
    Tel:+81-29-284-3834
    E-mail: kumada.takayuki@jaea.go.jp
    Radiation WorkerMeasurements and Instruments
    Physics
    Electricity and Electronics
    Mathematics
    Chemistry
    Scattering power of protons against neutrons remarkably depends on relative direction of spins of the protons and neutrons. We have developed a dyanamic nuclear polarization system for the proton polarization of composite materials, and then carried out polarized neutron scattering study to determine detailed structure of the materials. We will extend this technique named spin contrast variation to deterimine nano-scale bulk and surface structures using small-angle scattering diffractometers and reflectrometers at the neutron facilities, JRR-3 and J-PARC.
    J35Study on in-vessel thermal-hydraulic behavior during the loss of forced cooling accidents in HTTR
    Sector of Nuclear Science Research
    Oarai Research and Development Center
    Department of HTTR
    HTTR Reactor Engineering SectionO-arai Research and Development CenterDaisuke Tochio
    Tel:029-267-1919-3730
    E-mail: tochio.daisuke@jaea.go.jp
    Non-Radiation WorkerMechanics
    Computer and Information
    The Loss Of Forced Cooling (LOFC) Test Plan is in progress in the High Temperature Engineering Test Reactor (HTTR) under the international collaboration. The thermal-hydraulic behavior of fuel, structure and coolant is important during LOFC. In this study,thermal-hydraulic analysis model is constructed and numerical analysis is performed using commercial CFD analysis code to reveal the in-vessel thermal-hydraulic behavior during the LOFC.
    J36Study of geological environment during construction, operation and closure of underground facility.
    Tono Geoscience CenterCrystalline environment research groupTono Geoscience CenterTeruki Iwatsuki
    E-mail: iwatsuki.teruki@jaea.go.jp
    Non-Radiation WorkerGeo and Environemtal Sciences
    Chemistry
    Biology
    Chemical Engineering
    Measurements and Instruments
    Material
    The construction, operation and closure of large underground facility changes hydraulic and hydrochemical condition around the facility. Such disturbance process and the recovery mechanism are still unclear. It is required to develop the observation and simulation methods for understanding of the phenomenon. Postdoctoral fellow studies the hydraulic and hydrogeochemical evolution (artificial disturbance and the recovery) process, impact of burial materials such as cement, clay in deep underground around Mizunami Underground Research Laboratory (MIU) during facility construction and after the closure by analyzing the rock, groundwater and burial materials, and previous data.
    J37The study of knowledge management method on the decommissioning of nuclear facilities
    Sector of Decommissioning and Radioactive Waste Management
    Fugen Decommissioning Engineering Center
    Technology Development Department
    Dismantlement Engineering Section
    Fugen Decommissioning Engineering CenterMasashi Tezuka
    E-mail: tezuka.masashi@jaea.go.jp
    Radiation WorkerMathematics
    Computer and Information
    The decommissioning of a nuclear facility is a long term project. The transfer of knowledge and education to the next generation is a crucial issue. It is necessary to systemize of knowledge based on the knowledge engineering method such as ontology. Concretely speaking, we collect a large amount of explicit knowledge regarding decommissioning such as domestic and foreign information, instruments information and know-how, and arrange it. On the other hand, we try to translate personal tacit knowledge collected by interview to explicit knowledge as possible. After these, we can use whole knowledge of decommissioning organized and systematized, and study advanced knowledge engineering method available for education and succession.
    F1Computational study on the chemical form of radionuclides in environment and their transport
    Center for Computational Science & e-SystemsSimulation technology R&D Office178-4-4 Wakashiba, Kashiwa, Chiba, 277-0871, JapanMasahiko Machida
    Tel:+81-04-7135-2349
    E-mail: machida.masahiko@jaea.go.jp
    Non-Radiation WorkerPhysics
    Geo and Environmental Sciences
    Computer and Information
    Chemistry
    The transport of radioactive Cesium and other radionuclides in the environment (including soil, rivers, coastal area and other environment) widely varies depending on the surroundings. These variation mainly originates from changes in the chemical and physical form of substances which absorb the radionuclides, such as soil particles and organic polymers of biological origin. Thus comprehensive evaluation of the transport of radionuclides in various environment requires development of transport model that incorporates the effects of different circumstances, based on the bottom-up modeling framework from the atomistic and molecular level up to the mesoscopic and macroscopic scales.
    The applicant is supposed to develop the modeling framework and simulation codes for the evaluation of transport of radionuclides that incorporates the change of physical and chemical form of radionuclides in various circumstances, to clarify the overall transport of Cesium and other radionuclides in Fukushima environment.
    F2Development of evaluation method of dose rate distribution in primary containment vessel of the Fukushima Daiichi Nuclear Power Station
    Collaborative Laboratories for Advanced Decommissioning Science (CLADS),
    Sector of Fukushima Research and Development
    Dose Evaluation and Nuclear Material Accountancy Group
    Fuel Debris Handling and Analysis Division
    Tokai Research and Development Center
    (Nuclear Science Research Institute)
    Keisuke Okumura
    Tel:+81-(0)29-282-5840
    E-mail: okumura.keisuke@jaea.go.jp
    Non-Radiation WorkerPhysics
    Geo and Environemtal Sciences
    Measurements and Instruments
    In order to contribute to planning of fuel debris retrieval, we develop the evaluation method of the most possible dose rate distribution in the primary containment vessel (PCV) by using information obtained from irradiation calculations of fuels and structural materials, severe accident analyses, local dose rate measurement in PCV with robots, and so on.
    F3Research on severe accident progression behavior of the Fukushima Daiichi NPP accident
    Collaborative Laboratories for Advanced Decommissioning Science (CLADS),
    Sector of Fukushima Research and Development
    Molten Core Behavior Analysis Group
    Severe Accident Propagation Behavior Evaluation Division
    Tokai Research and Development Center
    (Nuclear Science Research Institute)
    Toshio Nakagiri
    Tel:+81-(0)29-267-1919, Ex.5802
    E-mail: nakagiri.toshio@jaea.go.jp
    Non-Radiation WorkerPhysics
    Chemistry
    Radiation
    Mechanics
    Material
    Measurements and Instruments
    Computer and Information
    Analytical evaluation using SA codes (SCDAP, MELCOR, etc.) and 1F plant data are peroformed to enhance understanding on accident progression behavior in the Fukushima Daiichi NPP.
    In this theme, evaluation of 1F plant data with SA code analysis will be conducted and possibility of model improvement will be considered where appropriate.
    F4Research on the degradation behavior of fuel assemblies in Fukushima Daiichi NPP accident condition
    Collaborative Laboratories for Advanced Decommissioning Science (CLADS),
    Sector of Fukushima Research and Development
    Molten Core Behavior Analysis Group
    Severe Accident Propagation Behavior Evaluation Division
    Tokai Research and Development Center
    (Nuclear Science Research Institute)
    Toshio Nakagiri
    Tel:+81-(0)29-267-1919, Ex.5802
    E-mail: nakagiri.toshio@jaea.go.jp
    Non-Radiation WorkerPhysics
    Chemistry
    Mechanics
    Material
    Measurements and Instruments
    Present knowledge on reaction behavior of the fuel assembly materials (control blade, fuel rod, channel box) is insufficient to understand degradation behavior of fuel asseblies in the Fukushima Daiichi NPP accident.
    In this theme, laboratory scale experiments on reaction behavior of fuel assembly materials, large scale experiments on the degradation behavior of fuel assemblies and development of individual reaction models will be performed.
    F5Development of Technology for Working Environment Data Collection and Accumulation by Remote Operated Robots
    Collaborative Laboratories for Advanced Decommissioning Science (CLADS),
    Sector of Fukushima Research and Development
    Remote Technology and Robotics Group,
    Remote System and Sensing Technology Division
    Tokai Research and Development Center (Nuclear Science Research Institute) or Tomioka International Collaborative Research Building (now under constructing)Dr. Tatsuo TORII
    Tel:+81-(0)29-282-6329
    E-mail: torii.tatsuo@jaea.go.jp
    Non-Radiation WorkerComputer and Information
    Robotics
    Electricity and Electronics
    Mechanics
    For long-term decommissioning process of the Fukushima Daiichi NPP, it is importatnt to gather and accumulate the data of the working environment as the reference to plan the missons and to use for the workers' training. The objective of this reseach subject is to develp the map building and working enviromental modeling method based on collected sensory data by remote operated robots and sensing systems. Design and implementation of spatio-temporal database to register the working environment data is also included in this research project.
    F6R&Ds on Radiation Imaging Technologies under High-dose Environments
    Collaborative Laboratories for Advanced Decommissioning Science (CLADS),
    Sector of Fukushima Research and Development
    Radiation Imaging and Instrument Group
    Remote System and Sensing Technology Division
    Tokai Research and Development Center (Nuclear Science Research Institute) or Tomioka International Collaborative Research Building (now under constructing)Jun Saegusa
    Tel:+81-(0)29-282-6144
    E-mail: saegusa.jun@jaea.go.jp
    Radiation WorkerPhysics
    Radiation
    Computer and Information
    Electricity and Electronics
    Applied Physics
    Measurements and Instruments
    For the decommissioning of TEPCO Fukushima Daiichi Nuclear Power Plants, gamma-ray detectors that can estimate the position, shape and nuclide distributions of residual debris are to be developed. In particular, a prototype detection system consisting of two-dimensional-gamma-imaging units and compact scintillator crystals is developed for the application to fuel debris measurements, and response characteristics of each element to gamma-rays are evaluated. In addition, a compact/lightweight gamma-camera is to be manufactured for the evaluation of its detection capability to radioactive materials and of durability against radiations. An unmanned remote radiation measurement system for the imaging of the radioactivity distribution in the Fukushima reactor building are also to be developed.
    F7R&Ds on Image Processing Technologies for Radiation Measurement Data on Reactor Decommissioning
    Collaborative Laboratories for Advanced Decommissioning Science (CLADS),
    Sector of Fukushima Research and Development
    Radiation Imaging and Instrument Group
    Remote System and Sensing Technology Division
    Tokai Research and Development Center (Nuclear Science Research Institute) or Tomioka International Collaborative Research Building (now under constructing)Jun Saegusa
    Tel:+81-(0)29-282-6144
    E-mail: saegusa.jun@jaea.go.jp
    Non-Radiation WorkerComputer and Information
    Radiation
    Physics
    Mathematics
    Applied Physics
    Measurements and Instruments
    Towards the planned removal of fuel debris from the TEPCO Fukushima Daiichi Nuclear Power Plants in 2021, reduction of radiation doses to workers and countermeasures against the spreading of radioactive contaminations are essential. For the purpose, three-dimensional visualization (mapping) of dose rates and radionuclide distributions are required as well as the real time monitoring of dose rates in the reactor building. So far, developments on radiation measurement techniques in the Fukushima Daiichi NPPs are in progress, and results obtained from these developments are to be visualized by the proposed R&Ds. Especially, developments of the algorithm for the three-dimensional image reconstruction is to be performed.
    F8Research on alteration and leaching of molten fuel
    Collaborative Laboratories for Advanced Decommissioning Science (CLADS),
    Sector of Fukushima Research and Development
    Fuel Debris Characterization and Conditioning Technology Development Group
    Fuel Debris Handling and Analysis Division
    Tokai Research and Development Center
    (Nuclear Fuel Cycle Engineering Laboratories)
    Hideki Ogino
    Tel:+81-29-282-1126
    E-mail: ogino.hideki@jaea.go.jp
    Non-Radiation WorkerPhysics
    Material
    Chemical Engineering
    Chemistry
    Geo and Environemtal Sciences
    Radiation
    Computer and Information
    The work on fuel debris removal from the damaged reactors at Fukushima Daiichi NPP requires a considerably long time. Considering long-term removal work and the subsequent processes such as storage, treatment and disposal, alteration of fuel debris should be evaluated . Although it is anticipated that alteration of fuel debris can be developed by external environments such as air, water and radiation (e.g., the conversion of debris surfaces into powder form and elution into the water), there is little knowledge about alteration.
    In this research, the alteration and leaching behavior of fuel debris will be evaluated and their models will also be developed based on the knowledge about the alteration of Chernobyl LFCM and the disposal technologies of spent fuel and vitrified waste, etc.
    F9Research for 3D visualization of environmental radiation distribution
    Sector of Fukushima Research and Development,
    Fukushima Environmental Safety center
    Fukushima Radiation measurement Group,Minami-soma(Environmental Radiation Monitoring Centre)Yukihisa Sanada
    Tel:+81-244-25-2072
    E-mail: sanada.yukihisa@jaea.go.jp
    Non-Radiation WorkerPhysics
    Geo and Environemtal Sciences
    Measurements and Instruments
    In FukushimaEnvironmental radiation monitoring centre, radiation monitoring system using unmanned vehicle was developed for environmental radiation monitoring. We recruit a postdoctoral fellow who can demonstrate his/her ability for development of 3D tecqnique of visualization results of environmental radiation monitoring based on image reconstruction tecqnique using PET. So, it is desirable that applicants have knowledge of a radiation and the computer language.
    F10Research on the chemical form of radioactive material in the environment and its dissolution within environmental water systems by use of solid analysis techniques
    Sector of Fukushima Research and Development
    Fukushima Environmetal Safety Center
    Fukushima Environmental Restoration GroupFukushima(Miharu)Kazuki Iijima
    Tel:+81-:247-61-2913
    E-mail: iijima.kazuki@jaea.go.jp
    Non-Radiation WorkerChemistry
    Geo and Environemtal Sciences
    Material
    Measurements and Instruments
    The radioactive cesium deposited on the land surface of Fukushima exists mostly in forests and small portions of it discharge each year into the ocean through river systems. The dissolved form of radioactive cesium migrates most easily within the eco-system. Although dissolved radiocesium concentrations are low, it is still detected in stemflow and riverflows, and this fact is considered to be the reason for the existence of freshwater fish and mushrooms with high radioactive cesium concentration. In order to predict the future behaviour of radioactive cesium in the eco-system, it is necessary to clarify the chemical form of radioactive cesium in the forest and the mechanism by which it dissolves. In this research program, we will try to uncover these issues by utilizing solid analysis instruments such as TEM, EPMA, FIB, XPS, etc., installed in the Fukushima Environmental Creation Center.
    F11Development of analytical method for small amount radionuclides in environment
    Sector of Fukushima Research and Development
    Fukushima Environmental Safety Center
    Fukushima Safety Administration and Radiation Measurement GroupFukushima(Miharu)Yasuhiro UEZU
    Tel:+81-247-61-2911
    E-mail: uezu.yasuhiro@jaea.go.jp
    Non-Radiation WorkerChemistry
    Geo and Environemtal Sciences
    Radiation
    The transfer factor of Sr-90 and H-3(OBT) are not same of Cs-137 in environment .
    Therefore, our group would like to develop simple and rapid analytical methods for Sr-90 and OBT in environmental samples.
    The study points of Sr-90 analytical method by using Q-ICP-MS are reduction of isobar interference and increasing of sensitivity. The study points of OBT are aqueous yield from samples.
    http://fukushima.jaea.go.jp/initiatives/cat01/pdf1511/2-2_takeishi.pdf
    F12High-energy gamma-rays accompanied by fission
    Sector of Nuclear Science Research Advanced Science Research CenterResearch Group for Heavy Element Nuclear Science
    Tokai Research and Development Center
    Nuclear Science Rsearch Institute
    Dr. Katsuhisa Nishio
    Tel:+81-29-282-5454
    E-mail: nishio.katsuhisa@jaea.go.jp
    Radiation WorkerPhysics
    Radiation
    Measurements and Instruments
    Applied Physics
    Computer and Information
    Measurement of high-energy gamma-rays accompanied by fission will be carried out, and the mechanism of this radiation will be investigated. The main goal is to use this radiactivity to monitor the criticality of nuclear fuel debris of damaged Fukushima atomic power plants, which is necessary in the process of decommissioning. An experiment will be carried out using neutron beam supplied by a research reactor. Fission study is also the scope of this program using heavy-ion beams and and photons.
    F13Research and development of treatment method for radioactive wastes generated at the contaminated water treatment facility in Fukushima Daiichi Power Plant
    Sector of Nuclear Science Research Advanced Science Research CenterResearch Group for Interfacial Reaction Field ChemistryTokai Research and Development Center
    Nuclear Science Research Institute
    Kazuya Tanaka
    Tel:+81-29-284-3518
    E-mail: tanaka.kazuya@jaea.go.jp
    Radiation WorkerGeo and Environemtal Sciences
    Chemistry
    Material
    Applied Chemistry
    At Fukushima Daiichi, radionuclides in the contaminated water have been removed according to thier physicochemical forms. Posttreatment method for disposal of those radionuclides collected by various materials has yet to be decided. This study aims to develop effective posttreatment methods for mainly long-life anionic radionuclides for which few effective treatment methods for geological disposal are known. The posttreatment methods for them include conversion to stable inorganic form and subsequent solidification.
    F14Elucidation of migration behavior of radioactive cesium in forest and technological development for preventing dispersion of contaminates
    Sector of Nuclear Science Research Advanced Science Research CenterResearch Group for Interfacial Reaction Field ChemistryTokai Research and Development Center
    Nuclear Science Research Institute
    Fuminori Sakamoto
    Tel:+81-29-284-3517
    E-mail: sakamoto.fuminori@jaea.go.jp
    Radiation WorkerGeo and Environemtal Sciences
    Biology
    Chemistry
    Applied Chemistry
    Fungi including mushrooms have a high ability to absorb radioactive cesium from contaminated soil and woods. This ability is supposed to give significant impact on migration behavior of radioactive cesium in forest although the mechanism has yet to be elucidated. The Japanese government recently decided to decontaminate Satoyama, undeveloped woodland near the populated areas, in near future. To achieve this, prevention of radioactive cesium dispersion from the depths of the forest to Satoyama areas is necessary The purposes of this study is to elucidate the migration behavior of radioactive cesium in forest through investigating biological transformation of radioactive cesium by fungi and cesium immobilization by minerals. This study also aims to develop methods to preventing dispersion of radioactive cesium in forest.
    F15Investigation of the characteritics of radioactive material in a severe accident condition
    Nuclear Science and Engineering CenterResearch Group for LWR Advanced Technology
    LWR Key Technology Development Division
    Tokai Research and Development Cente (Nuclear Science Research Institute)Masahiko Osaka
    Tel:+81-29-267-4141
    E-mail: ohsaka.masahiko@jaea.go.jp
    Radiation WorkerPhysics
    Chemistry
    Material
    Mechanics
    In order to acquire fundamental knowledge on fission product (FP) behavior and dose evaluation for the decommissioning of Fukushima Daiich Nuclear Power Station, we are investigating the behavior of radioactive material in the Primary Containment Vessel (PCV) under severe accident conditions. The post-doctoral fellow will investigate the characteristics of such radioactive material and aerosols (chemical form, size distribution, etc) by conducting simulation tests. These tests will simulate FP transport from core to PCV. The aerosols analyses on size distribution will be conducted in the different transport stages, and will be coupled with post characterizations of the deposits (microstructure and chemical state). The post-doctoral fellow will be also involved in the evaluation of the radioactive material behavior and aerosol formation mechanism, by performing analytical studies on the chemical reaction kinetics and by comparing the simulation tests with the analysis of environmental samples.
    F16Clarification of Cs desorption mechanism on Cs free mineralization of clay minerals
    Materials Sciences Research CenterAnalytical Sciences Development Research GroupTokai Research and Development Center
    (Nuclear Science Research Institute)
    Iwao Shimoyama
    Tel:+81-29-284-3929
    E-mail: shimoyama.iwao@jaea.go.jp
    Radiation WorkerChemistry
    Physics
    Geo and Environemtal Sciences
    Material
    We study Cs desorption mechanism from clay minerals to develop Cs-free meneralization for volume reduction and reuse of radioactive contaminated soil in Fukushima. Weathered biotite (WB) in Fukushima is adopted as a model soil and sorbed with non-radioactive Cs. WB is heated with some alkaline salt reagents in ambient atomosphere condition or low-pressure conditions and products formed after the heating treatment are analyzed using X-ray diffraction and X-ray flulrescence analysis. Especially, we focus on the dependences of reagents and pressure on Cs desorption ratio and structural change of WB in this study.