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
   J2	Study on feasibility and effectiveness evaluation for severe accident countermeasures
   	Nuclear Safety Research Center	Severe Accident Analysis Research Group	Nuclear Science Research Institute	Tomoyuki Sugiyama Tel: +81-29-282-5253 E-mail: sugiyama.tomoyuki@jaea.go.jp	Non-Radiation Worker	Physics, 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.
   J3	Experimental and analytical studies on the fuel behavior under accident conditions of light-water-reactor
   	Nuclear Safety Research Center	Fuel Safety Research Group	Nuclear Science Research Institute	Masaki　Amaya Tel: +81-29-282-5028 E-mail: amaya.masaki@jaea.go.jp	Non-Radiation Worker	Mechanics, 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.
   J5	Study on the methodology of estimation of property changes in radioactive waste disposal system due to natural events
   	Nuclear Safety Research Center	Environmental Safety Research Group	Nuclear Science Research Institute	Seiji Takeda Tel: +81-29-282-6170 E-mail: takeda.seiji@jaea.go.jp	Non-Radiation Worker	Physics, 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.
   J6	Study on release and transport behavior of radioactive materials in reprocessing plant under severe accident conditions
   	Nuclear Safety Research Center	Fuel Cycle Safety Research Group	Nuclear Science Research Institute	Hitoshi Abe Tel: +81-29-282-6672 E-mail: abe.hitoshi@jaea.go.jp	Non-Radiation Worker	Chemistry, 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.
   J7	Study on analytical techniques for individual particles containing nuclear materials in environmental samples
   	Nuclear Safety Research Center	Research Group for Safeguards Analytical Chemisty	Nuclear Science Research Institute	Fumitaka Esaka Tel: +81-29-282-6165 E-mail: esaka.fumitaka@jaea.go.jp	Radiation Worker	Chemistry, 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 safeguards. 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.
   J8	Experimental Research on Safety Assessment of Storage and Disposal of Radioactive Waste
   	Nuclear Safety Research Center	Waste Safety Research Group	Nuclear Science Research Institute	Toshikatsu Maeda Tel: +81-29-282-6001 E-mail: maeda.toshikatsu@jaea.go.jp	Radiation Worker	Chemistry, 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 redox reactions and colloid formation associated with glass, metals, clays, concretes and polyethlene focusing on primary factors such as adjacent barrier materials, groundwater composition, geology, microbes and radiolysis. The goal is to obtain scientific basis for models evaluating changes in the barrier functions and for systematical establishment of datasets. Methods for chemical analysis of radioactive wastes themselves are also investigated.
   J9	Study on a Level 3 Probabilistic Risk Analysis of nuclear power plants
   	Nuclear Safety Research Center	Radiation Risk Analysis Research Group	Nuclear Science Research Institute	Masanori Kimura Tel: +81-29-282-5459 E-mail: kimura.masanori@jaea.go.jp	Non-Radiation Worker	Physics, 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.
   J14	Nuclear Chemistry of superheavy elements
   	Advanced Science Research Center	Sector of Nuclear Science Research	Nuclear Science Research Institute	Kazuaki Tsukada Tel: +81-29-282-5491 E-mail: tsukada.kazuaki@jaea.go.jp	Radiation Worker	Chemistry, Physics, Radiation, Measurements and Instruments, Applied Chemistry
   	The main objective is to understand chemical and atomic 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 from the measurements of ionization-energy, electron spin, surface adsorption, ionic radii, redox potentials, and molecular formations. The subjects include development of the measuring system based on an "atom-at-a-time" method. These experiments will be performed at the JAEA Tandem Accelerator Facility. (http://asrc.jaea.go.jp/soshiki/gr/HENS-gr/nc/index-e.htm)
   J16	Materials physics in heavy element systems
   	Advanced Science Research Center	Research group for Materials physics for heavy element systems	Nuclear Science Research Institute	Shinsaku KAMBE Tel: +81-29-284-3525 E-mail: kambe.shinsaku@jaea.go.jp	Non-Radiation Worker	Physics, Chemistry, Applied Physics, Material
   	New electronic states in heavy element systems are investigated experimentally and theoretically. Especially magnetic and superconducting properties at low temperatures in bulk and thin film samples are focused.
   J19	Interdisciplinary study on emergent properties of nanoscale structures by using advanced beams
   	Advanced Science Research Center	Research Group for Nanoscale Structure and Function of Advanced Materials	Nuclear Science Research Institute	Shin-ichi Shamoto Tel: +81-29-284-3521 E-mail: shamoto.shinichi@jaea.go.jp	Radiation Worker	Physics, Chemistry, Material, Applied Physics, Applied Chemistry, Measurements and Instruments
   	Structures and physical properties of materials from single-layer to bulk will be studied by using the advanced beams (neutron, positron and muon) produced at accelerator and reactor based facilities such as J-PARC. Those experiences are not required but high motivation for the researches are preferred.
   J21	Elucidation of circulation of dissolved organic matter in the ocean using radiocarbon as a tracer
   	Nuclear Science and Engineering Center	Reserch Group for Environmental Science	Nuclear Science Research Institute	Shigeyoshi Otosaka Tel: +81-29-282-5171 E-mail: otosaka.shigeyoshi@jaea.go.jp	Non-Radiation Worker	Geo and Environemtal Sciences, Chemistry
   	Dissolved organic matter (DOM) in seawater is known to play a role as a carrier for various materials, including radionuclides, in the ocean. In this study, “carbon age” of DOM in seawater collected in the North Pacific and its marginal seas are analyzed by radiocarbon measurement using an accelerator mass spectrometer (AMS). By adding information on "timescale" to the spatial distribution of DOM, the dynamics of the DOM-bound substances circulating in the ocean is elucidated.
   J24	Fission product behavior in the Primary Containment Vessel of Light Water Reactor
   	Nuclear Science and Engineering Center	Development Group for LWR Advanced Technology	Nuclear Science Research Institute	Masahiko Osaka Tel: +81-29-282-5922 E-mail: ohsaka.masahiko@jaea.go.jp	Radiation Worker	Chemistry, 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.
   J25	Research and development of minor actinide separation process from high level liquid waste
   	Nuclear Science and Engineering Center	Research Group for Partitioning	Nuclear Science Research Institute	Tatsuro Matsumura Tel: +81-29-282-6673 E-mail: matsumura.tatsuro@jaea.go.jp	Radiation Worker	Chemistry, 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.
   J27	Development of new separation reagents for radioactive nuclides based on the coodination chemistry of the transition metal complexes
   	Nuclear Science and Engineering Center	Research Group for Radiochemistry	Nuclear Science Research Institute	Masayuki Watanabe Tel: +81-29-282-5167 E-mail: watanabe.masayuki@jaea.go.jp	Radiation Worker	Chemistry, Physics, Geo and Environemtal Sciences
   	Radioactive wastes resulting from spent nuclear fuel contain numerous d-block or f-block transition metals such as platinum group or rare earths metals, as fission products. In this project, the coordination chemistry and physical properties of d-block and f-block elements are identified by various types of spectroscopy in order to develop effective separation reagents for these transition metal cations. The applicant should have profound scholarly knowledge about the redox reaction and complexation of the metal cations in radioactive wastes.
   J29	Research for controlling chemical reaction by laser
   	Materials Sciences Research Center	Actinide Chemistry Group	Energy and Environment Materials Science Division	Keiichi Yokoyama Tel: +81-791-58-0971 E-mail: yokoyama.keiichi@jaea.go.jp	Radiation Worker	Physics, Chemistry, Applied Physics
   	Fundamental studies to explore controllability of valence states of metal ions in solution are to be conducted using ultrafast lasers, aiming at developing new schemes in the nuclear fuel reprocessing. With respect to the f-electron elements such as lanthanides, through monitoring their valency after multi-photon excitations mediated by f-f transitions, you are expected to integrate the fundamental knowledge relevant to photo-induced element-selective valence control techniques. Development and application of ultrafast lasers and some spectroscopic techniques are to be included.
   J32	The experimental study to elucidate the relationship between functions and dynamics of bio-macromolecules using deuterated samples
   	J-PARC Center	Neutron Science Section	J-PARC Center	Kaoru Shibata Tel: +81-29-284-3199 E-mail: shibata.kaoru@jaea.go.jp	Radiation Worker	Biology, 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.
   J37	Study of aging deterioration mechanism and preservation technology by using the material of Fugen NPP
   	Fugen Decomissionning Engineering Center	Plant Material Examination Section	Tsuruga headquarters	Yoshiaki Katano Tel: +81-770-26-1221 E-mail: katano.yoshiaki@jaea.go.jp	Radiation Worker	Material, 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.
   F2	Studies 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 Group	Nuclear Science Reserch Institute	Ryuji Nagaishi Tel:　+81-29-282-5493 E-mail: nagaishi.ryuji@jaea.go.jp	Radiation Worker	Radiation, 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.
   F4	Mid- and Long-term stability of Fuel Debris
   	Collaborative Laboratories for Advanced Decommissioning Science (CLADS)	Fuel Debris Environmental Behavior Analysis Group	Nuclear Fuel Cycle Engineering Laboratories	Tadahiro Washiya Tel: +81-29-282-1133(66003) E-mail: washiya.tadahiro@jaea.go.jp	Radiation Worker	Chemistry, Mathematics, Material
   	Researcher will clarify the state of Pu in dominant phases of fuel debris and investigate chemical state of Pu such as the valent and solubilities of Pu in each phase and consider the possibility of Pu doposition in fuel debris
   F5	Study for advancing measurement and analysis techniques of radiation and radioactive substances in the environment
   	Fukushima Environmental Safety Center	Fukushima Radiation Measurement Group	Fukushima	Masanori　Takeyasu Tel: +81-247-61-2911 E-mail: takeyasu.masanori@jaea.go.jp	Non-Radiation Worker	Chemistry, Measurements and Instruments, Radiation, Geo and Environemtal Sciences
   	The measurement results of radiation in the environment are examined, and the measurement method is optimizated in terms of time and spacial resolutions. Also, quick analytical methods are developmed for radioavtivity in environmental samples. By these, it is expected that the measurement method of air dose rate is advanced and that the radiocesium, Sr-90 and Tritium in various environmental samples are analysed and determined quickly. http://fukushima.jaea.go.jp/initiatives/cat01/pdf1511/2-2_takeishi.pdf
   F6	Research and development of treatment method for radioactive wastes generated at the contaminated water treatment facility in Fukushima Daiichi Power Plant
   	Advanced Science Research Center	Research Group for Interfacial Reaction Field Chemistry	Nuclear Science Research Institute	Naofumi Kozai Tel: +81-29-282-6031 E-mail: kozai.naofumi@jaea.go.jp	Radiation Worker	Chemistry, Geo and Environemtal Sciences, 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 selective sepatarion (accumulation), conversion to stable inorganic form, and subsequent solidification.
   F7	Exploration and elucidation of novel interaction between microorganisms and radionuclides
   	Advanced Science Research Center	Research Group for Interfacial Reaction Field Chemistry	Nuclear Science Research Institute	Kazuya Tanaka Tel: ＋81-29-284-3518 E-mail: tanaka.kazuya@jaea.go.jp	Radiation Worker	Chemistry, Mathematics, Geo and Environemtal Sciences, Biology, Applied Chemistry
   	It is widely known that microorganisms affect the environmental migration behavior of radionuclides in various stiations. This theme performs fundamental research on microbial influence on the chemical states of radionuclides, the response of microorganisms to radionuclides, and microbial influence on interaction amongradionuclides, minerals, and plants. This study aims to discover and elucidate novel phenomena.
   F8	Development of volume reduction of Cs-contaminated soil and elucidation of Cs sorption-desorption mechanism.
   	Materials Sciences Research Center	Actinide Chemistry Group	Energy and Environment Materials Science Division	Hideaki Shiwaku Tel: +81-791-58-2615 E-mail: shiwaku@spring8.or.jp	Radiation Worker	Chemistry, 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.
   F9	Research on cesium removal from contaminated soils and selective formation of the product by heat treatment
   	Materials Sciences Research Center	Analytical Sciences Development Research Group	Nuclear Science Research Institute	Mitsunori Honda Tel: +81-29-284-3928 E-mail: honda.mitsunori@jaea.go.jp	Radiation Worker	Geo and Environemtal Sciences, Radiation, Physics, Chemistry, Material
   	Decontamination of a large quantity of radioactive cesium (Cs) released with The Fukushima Daiichi Nuclear Power Plant Accident is an urgent problem that should be solved. However, the decontamination method of the radioactive contamination soil is not established yet. We study Cs desorption mechanism of clay minerals to develop Cs-free mineralization for volume reduction and reuse of the treated soil in Fukushima. Weathered biotite (WB) is adopted as a model soil to sorb non-radioactive Cs. WB is heated with some alkaline salt reagents in ambient atmosphere or low-pressure conditions and the products formed after the heating treatment are analyzed using X-ray diffraction, X-ray fluorescence and X-ray absorption spectroscopy techniques. We focus on the dependences of reagents and pressure on Cs desorption ratio and structural change of WB.