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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
  2. No Theme
    Department Section Location Contact Person Radiation Worker/
    Non-Radiation Worker    		 Field
    (for reference）
    Summary
    J3Experimental and analytical studies on the fuel behavior under accident conditions of light-water-reactor
    Nuclear Safety Research CenterFuel Safety Research GroupNuclear Science Research InstituteMasaki　Amaya
    Tel: +81-29-282-5028
    E-mail: amaya.masaki@jaea.go.jp    		Non-Radiation WorkerMechanics,
    Material,
    Electricity and Electronics,
    Measurements and Instruments,
    Computer and Information,
    Physics,
    Chemistry
    The objective of this study is to develop and/or improve models concerning fuel behavior under reactivity-initiated accidents (RIAs), loss-of-coolant accidents (LOCAs), etc. by conducting experiments on light-water-reactor fuel and/or analyses using calculation codes etc. The following or related studies will be carried out.
    ・Model development and evaluation by using calculation codes etc., concerning effects of the deformation of fuel cladding tube and axial relocation of fuel pellets inside the fuel rod on the fuel temperature during LOCAs.
    ・Analysis and model improvement in terms of fuel dispersal behavior following failures of fuel cladding tube during accidents by using calculation codes etc.
    J5Study on the methodology of estimation of property changes in radioactive waste disposal system due to natural events
    Nuclear Safety Research CenterEnvironmental Safety Research GroupNuclear Science Research InstituteSeiji Takeda
    Tel: +81-29-282-6170
    E-mail: takeda.seiji@jaea.go.jp    		Non-Radiation WorkerPhysics,
    Chemistry,
    Geo and Environemtal Sciences,
    Computer and Information,
    Architectural and Civil Engineering,
    Measurements and Instruments
    In the safety assessment for a geological disposal of radioactive wastes, it is important to estimate the effect of property changes in radioactive waste disposal system resulting from the occurrence of natural events such as volcanic and magmatic activity, seismic activity, uplifts and denudation etc.. In this study, the methodologies for estimating the possibility of the occurrence and the effect of topographical, hydrological/hydrogeological, physical and geochemical response to geological and/or climatic factors are developed using previous observation and data characterized by the factors in Japan.
    J9Study on a Level 3 Probabilistic Risk Analysis of nuclear power plants
    Nuclear Safety Research CenterRadiation Risk Analysis Research GroupNuclear Science Research InstituteMasanori 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.
    J10Experimental and analytical study on thermohydraulic safety of light water reactor
    Nuclear Safety Research CenterThermohydraulic Safety Research GroupNuclear Science Research InstituteYasuteru Sibamoto
    Tel: +81-29-282-5263
    E-mail: sibamoto.yasuteru@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.
    J11Study on the methodology of the structural integrity assessment for nuclear reactor components
    Nuclear Safety Research CenterStructural Integrity Research GroupNuclear Science Research InstituteYinsheng Li
    Tel: +81-29-282-6457
    E-mail: li.yinsheng@jaea.go.jp    		Non-Radiation WorkerMechanics,
    Architectural and Civil Engineering,
    Material,
    Physics,
    Applied Physics,
    Measurements and Instruments,
    Computer and Information
    Due to the long term operation of some domestic nuclear power plants and occurrence of the earthquakes beyond the designed seismic ground motion, developing the methodologies of structural integrity assessments for the reactor components concerning seismic loading, impact loading and age related degradation mechanisms such as neutron irradiation embrittlement, stress corrosion cracking and so on is of great importance. In this theme, one of the following related researches will be conducted.
    - Advanced structural integrity assessment research for important nuclear components, such as failure estimation, crack propagation or weld residual stress evaluation, on the basis of numerical simulation, material testing, and fracture testing and so on
    - Advanced seismic safety and impact assessment research including development of three-dimensional evaluation models of nuclear facility buildings, components and piping systems, and numerical simulation considering nonlinear mechanical properties.
    J12Research on Criticality Safety/Management of Damaged- or Molten-Fuel formed by Severe Accidents
    Nuclear Safety Research CenterCriticality Safety Research GroupNuclear Science Research InstituteKotaro 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.
    J13Experimental and theoretical studies of exotic nuclei
    Advanced Science Research CenterSector of Nuclear Science ResearchNuclear Science Research InstituteKatsuhisa Nishio
    Tel: +81-29-282-5454
    E-mail: nishio.katsuhisa@jaea.go.jp    		Radiation WorkerPhysics,
    Mathematics,
    Radiation,
    Applied Physics,
    Measurements and Instruments,
    Computer and Information,
    Other
    Experimental and theoretical studies of unstable nuclei and superheavy elements will be prompted. The research topics include nucler structure, nuclear reaction, and nuclear fission for nuclei far from the stable isotopes. In experimental programs, JAEA facilities and/or external facilities will be used to produce exotic nuclei. In theorey subjects nuclear structure and fission process will be studied by taking advantage of the JAEA supercomputer.
    (http://asrc.jaea.go.jp/soshiki/gr/HENS-gr/index_e.html)
    J23Elucidation of radiation effects due to exposure from insoluble particle
    Nuclear Science and Engineering CenterResearch Group for Radiation Transport AnalysisNuclear Science Research InstituteTatsuhiko Sato
    Tel: +81-29-282-5803
    E-mail: sato.tatsuhiko@jaea.go.jp    		Radiation WorkerRadiation,
    Biology,
    Computer and Information,
    Measurements and Instruments
    When a person inhales insoluble cesium with high radioactivity (so-called, Cs-ball), radiation dose can be extremely high within a limited micro region. Then, radiation effects can differ between insoluble cesium and cesium in other chemical forms. Aims of this theme are to clarify physical characteristics for internal exposure from Cs-ball using the Particle and Heavy Ion Transport code System (PHITS) and to elucidate influences of the physical characteristics on radiation effects (e.g., cell population response) by experimental studies.
    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.
    J39Research and development for modeling of hydrogeological heterogeneity of fractured crystalline rock
    Tono Geoscience CentorCrystalline Environment Research GroupTono Geoscience CentorHironori Onoe
    Tel: +81-572-66-2244
    E-mail: onoe.hironori@jaea.go.jp    		Non-Radiation WorkerGeo and Environemtal Sciences,
    Architectural and Civil Engineering,
    Computer and Information
    It is important to understand hydraulic heterogeneities influenced by presence of water conducting fractures and faults in fractured crystalline rock from the viewpoints of the sagety assessment og geological disposal of high-level radioactive waste. One of the research task is to establish comprehensive technigues for investigation, analysis and assessment of hydraulic heterogeneities in in fractured crystalline rock.
    Threfore, research and development for modeling method of hydrogeological heterogeneities of rock mass around the research gallery is located at several hundred meters depth will be carried out using the result of in-situ investigation and monitoring in the Mizunami Underground Research Laboratory at the Tono area, Central Japan.
    (https://www.jaea.go.jp/04/tono/tgc_e/index_e.html)