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Recruitment

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
    J1Research on measures to strengthen nuclear nonproliferation and nuclear security
    Integrated Support Center for Nuclear Nonproliferation and Nuclear SecurityPolicy Research OfficeHead OfficeKazunori SUDA (Mr.)
    Tel: +81-29-282-0495
    E-mail: suda.kazunori@jaea.go.jp
    Non-Radiation WorkerNuclear Nonproliferation and Nuclear Security,
    Other
    In consideration of importance and necessity of enhancing nuclear nonproliferation and nuclear security, a post-doctoral fellow is expected to conduct various researches and analyses on nuclear nonproliferation and nuclear security issues, including how to utilize synergy effects when implementing technical measures on nuclear safeguards and security, risk assessment when utilizing such effects, and how to minimize such risks. The fellow is also expected to carry out studies on how to strengthen international regime on both nuclear nonproliferation and nuclear security.
    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.
    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)
    J36Research on concensus building of policies for fast reacor development
    Sector of Fast Reactor Research and DevelopmentPlanning and Co-ordination OfficeO-arai Research and Development CenterKiyoshi Ono
    Tel: +81-29-267-1919 (Ex.6470)
    E-mail: ono.kiyoshi@jaea.go.jp
    Non-Radiation WorkerOther
    The purpose of this reseasrch is to clarify the process of national consensus building by adopting social scientific approaches, and refelct it to the formulation of development strategies and policy recommendations. Specifically, analyses are performed on obstructive factors in siting, maintaining and developing facilites facing similar problems even though such facilites are required for maintaining the stable livelihood of the people, as well as the transition of fast reactor development at home and abroad. These analyses can cralify the process of consensus builing including roles of relevant entities to study what actions should be taken.
    https://www.jaea.go.jp/04/fast_reactor/
    F2Studies on Radiolysis and Radiation Damege for Advanced Safety Control of Hydrogen (H2) in Nuclear Engineering
    Collaborative Laboratories for Advanced Decommissioning Science (CLADS)Strage Equipment Soundness Evaluatuon GroupNuclear Science Reserch InstituteRyuji Nagaishi
    Tel: +81-29-282-5493
    E-mail: nagaishi.ryuji@jaea.go.jp
    Radiation WorkerRadiation,
    Chemistry,
    Material,
    Other
    To realize advanced safety control of H2 generated in severe accidents in nuclear facilities, subsequent decommissioning and waste management, radiolysis of aqueous solution systems and radiation damage of materials such as adsorbents, catalysis and debris will be studied experimentally and analytically. Then their data will be applied to construction of analysis code for the H2 behavior, and to development of technologies for the reduction and prevention of accidents originated from the H2 generation.