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Recruitment for Postdoctoral Fellow
(Fixed-term researcher)

  1. Physics Chemistry Mathematics Geo and Environemtal Sciences Biology Radiation
    Mechanics Material Electricity and Electronics Architectural and Civil Engineering Applied Physics Applied Chemistry
    Chemical Engineering Measurements and Instruments Computer and Information Nuclear Nonproliferation and
    Nuclear Security    		 Other All
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    Department Section Location Contact Person Radiation Worker/
    Non-Radiation Worker    		 Field
    (for reference）
    Summary
    J2Study on feasibility and effectiveness evaluation for severe accident countermeasures
    Nuclear Safety Research CenterSevere Accident Analysis Research GroupNuclear Science Research InstituteTomoyuki Sugiyama
    Tel: +81-29-282-5253
    E-mail: sugiyama.tomoyuki@jaea.go.jp    		Non-Radiation WorkerPhysics,
    Chemistry,
    Mechanics,
    Applied Physics,
    Chemical Engineering,
    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.
    J6Study on release and transport behavior of radioactive materials in reprocessing plant under severe accident conditions
    Nuclear Safety Research CenterFuel Cycle Safety Research GroupNuclear Science Research InstituteHitoshi Abe
    Tel: +81-29-282-6672
    E-mail: abe.hitoshi@jaea.go.jp
    		Non-Radiation WorkerChemistry,
    Physics,
    Chemical Engineering
    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.
    J24Fission product behavior in the Primary Containment Vessel of Light Water Reactor
    Nuclear Science and Engineering CenterDevelopment Group for LWR Advanced TechnologyNuclear Science Research InstituteMasahiko Osaka
    Tel: +81-29-282-5922
    E-mail: ohsaka.masahiko@jaea.go.jp    		Radiation WorkerChemistry,
    Physics,
    Material,
    Chemical Engineering,
    Measurements and Instruments
    Fission product (FP) behavior in the Primary Containment Vessel (PCV) of Light Water Reactor (LWR) should be known for the estimation of FP amounts released into environment (source term estimation) in the case of severe accident. Simulant FP aerosol behavior is directly viewed and deposited aerosol is characterized by experiments in a small-sized model PCV. Results are analyzed by thermal-hydraulic and chemical analysis codes to interpret the aerosol behavior in PCV. Complementary experiment/analysis on the FP aerosol formation and deposit revaporization/resuspention behaviors would be conducted, for the comprehensive understanding of FP behavior in the PCV under various conditions of such as hydraulics, moisture content, surface status and so on. The research is conducted in collaboration with researchers in the group.
    J25Research and development of minor actinide separation process from high level liquid waste
    Nuclear Science and Engineering CenterResearch Group for PartitioningNuclear Science Research InstituteTatsuro 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), we are investigating partitioning and transmutation technology. The separation of minor actinides from HLW is particularly important since they have high radiotoxity and long half lives. 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, and the minor actinide separation process from HLW will be developed with the novel extractant. The experiments using minor actinides and high level liquid waste will be carried out in glove boxes and hot cells.
    J37Study of aging deterioration mechanism and preservation technology by using the material of Fugen NPP
    Fugen Decomissionning Engineering CenterPlant Material Examination SectionTsuruga headquartersYoshiaki Katano
    Tel: +81-770-26-1221
    E-mail: katano.yoshiaki@jaea.go.jp    		Radiation WorkerMaterial,
    Measurements and Instruments,
    Physics,
    Chemistry,
    Chemical Engineering,
    Computer and Information
    The operation period of a nuclear power plant is limited to 40 years by law in Japan. The Nuclear Regulation Authority (NRA) can extend the period by 20 years more when the plant passed the review of the NRA. By using the real used material of the “Fugen” NPP after 25 years operation, the research of the deterioration and preservation mechanism is carried out for the long-term integrity of nuclear facilities. The main study programs are aging mechanism related to embrittlement by corrosion, thermal and radiation characteristics, by using data obtained from the three-dimensional atom probe (3DAP), the electron beam backscattering diffraction (EBSD) and focused ion beam scanning electron microscope (FIB-SEM) in the laboratory of the Fugen site. Moreover, the study of mechanism theory is implemented by simulation technology of the microscopic stress analysis by ABAQUS and phase field method. In this way, it will contribute to the long-term integrity of the nuclear power plant, by investigating the aging deterioration mechanism and improving the preservation technology.
    F1Research on evaluation of middle and long term soundness for nuclear industry materials in radiation environment
    Collaborative Laboratories for Advanced Decommissioning Science (CLADS)Strage Equipment Soundness Evaluatuon GroupNuclear Science Reserch InstituteTakafumi Motooka
    Tel: +81-29-282-5950
    E-mail: motoka.takafumi@jaea.go.jp    		Radiation WorkerMechanics,
    Chemical Engineering,
    Applied Chemistry,
    Radiation,
    Material
    Reasearch on evaluation of meddle and long term soundness for nuclear industry materials in radiation environment will be conducted. Especifically, basic data on corrosion behavior was obtained by immersion test, electrochemical tests and so on under a wide range of environmental conditions taking into consideration the environment in Fukushima Daiichi nuclear power station (1F) where high radiation field was expected. We will elucify corrosion phenomena which can occur during the decommissioning of 1F.
    F8Development of volume reduction of Cs-contaminated soil and elucidation of Cs sorption-desorption mechanism.
    Materials Sciences Research CenterActinide Chemistry GroupEnergy and Environment Materials Science DivisionHideaki Shiwaku
    Tel: +81-791-58-2615
    E-mail: shiwaku@spring8.or.jp    		Radiation WorkerChemistry,
    Physics,
    Geo and Environemtal Sciences,
    Chemical Engineering,
    Measurements and Instruments
    Radioactive cesium (Cs-134 and Cs-137) released to environment by the accident of TEPCO Fukushima Daiichi Nuclear Power Plant. Radioactive cesium was taken into soil in the environment after the accident immediately and produced enormous contaminated soil. Contaminated soil is planned to be exported outside Fukushima after 30 years. Therefore, the development study of the volume reduction of this contaminated soil is very important from the viewpoint of economic efficiency, environmental impact, radiation exposure, etc. In this study, structural analysis will be performed using synchrotron radiation (SPring-8) on the elucidation of radioactive cesium adsorption mechanism for farmland soil, including many clay minerals such as weathered biotite. We will contribute to environmental recovery of Fukushima.