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
   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.
   J4	Study on material degradation and integrity evaluation of nuclear reactor components
   	Nuclear Safety Research Center	Materials and Water Chemistry Research Group	Nuclear Science Research Institute	Satoshi Hanawa Tel: +81-29-282-5044 E-mail: hanawa.satoshi@jaea.go.jp	Radiation Worker	Mechanics, Material, Measurements and Instruments
   	Integrity of nuclear reactor components such as reactor pressure vessel (RPV) for long-term operation should be confirmed by the latest scientific knowledge. In order to enhance the knowledge for evaluating the structural integrity of the components, effect of environmental conditions such as neutron irradiation, high temperature-high pressure coolant on material degradation is investigated by micro-structural analysis and mechanical testing. Not only from the viewpoint of material degradation mentioned above, but the approach by fracture mechanics is also performed.
   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
   	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.
   J11	Study on the methodology of the structural integrity assessment for nuclear reactor components
   	Nuclear Safety Research Center	Structural Integrity Research Group	Nuclear Science Research Institute	Yinsheng Li Tel: +81-29-282-6457 E-mail: li.yinsheng@jaea.go.jp	Non-Radiation Worker	Mechanics, 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.
   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.
   J20	Study on Advanced Nuclear Materials by Nanostructure Control
   	Advanced Science Research Center	Research Group for Nanoscale Structure and Function of Advanced Materials	Nuclear Science Research Institute	Satoshi Yasuda Tel: +81-29-284-3504 E-mail: yasuda.satoshi@jaea.go.jp	Radiation Worker	Material, Applied Physics, Applied Chemistry, Electricity and Electronics
   	Studies on nano-fabrication and characterization will be performed for novel multi-functionalized materials. Molecular beam epitaxial (MBE), scanning tunneling microscopy (STM) and electrochemical methods will be used for the research (e.g. elucidation of surface reaction and structures of surface oxygen sensor in liquid metal for partitioning and transmutation technology).
   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.
   J26	Computational materials science for nuclear reactor structural materials
   	Nuclear Science and Engineering Center	Research Group for Radiation Materials Engineering	Nuclear Science Research Institute	Tomohito Tsuru Tel: +81-29-282-5198 E-mail: tsuru.tomohito@jaea.go.jp	Non-Radiation Worker	Mechanics, Material
   	The purpose of this study is to develop a computational approach for deformation and fracture process and explore fundamental mechnism of microscopic defect mechanics of structural materials. We look for PhD holder or candidate who is experienced in mechanics/thermodynamics calculations based on both ab-initio and molecular dynamics simulations for the deformation and fracture mechanics of structural materials.
   J28	Electronic structure research of actinide and the related materials with synchrotron radiation X-ray spectroscopy
   	Materials Sciences Research Center	Electronic Structure Research Group	Energy and Environment Materials Science Division	Hiroshi Yamagami Tel: +81-791-58-2607 E-mail: yamagami@cc.kyoto-su.ac.jp	Radiation Worker	Physics, Applied Physics, Material, Measurements and Instruments
   	Our group is carrying out a research on electronic structure by synchotron radiation X-ray spectroscopies (soft x-ray angular-resolved photoemission, soft x-ray magnetic circular dichroism, and hard x-ray photoemission) at SPring-8 in order to elucidate a mechanism holding physical properties of actinides and the related materials including uranium compounds. Furthermore, we are engaged on Fukushima environmental recovery research and reactor decommissioning research. For going ahead with the above-mentioned research, our group will hope a researcher who can take part in a technical development on x-ray spectroscopy at beam lines of synchrotron radiation facility.
   J30	In situ studies of metallic materials using time-of-flight neutron diffraction
   	J-PARC Center	Materials and Life Science Directorate Neutron Science Section	J-PARC Center	Stefanus Harjo Tel: +81-29-284-3266 E-mail: stefanus.harjo@j-parc.jp	Radiation Worker	Material, Mechanics, Applied Physics, Physics, Measurements and Instruments
   	A high-resolution & high-intensity time-of-flight neutron diffractometer (TAKUMI) was constructed and now is operated for researches on various engineering materials at the Material & Life Science Experimental Facility of J-PARC. In this theme, the following studies using TAKUMI for the advanced steels and advanced light metals are planned. (1) The relationship between the microstructure evolution during deformation and the mechanical & functional properties, (2) the relationship between microstructural evolution during thermo-mechanical treatment and the mechanical properties, and (3) development of in situ hybrid neutron diffraction measurement technique (concurrent measurements of digital image correlation method and infrared thermography) for various deformation tests. Supporting researches at TAKUMI are also required.
   J34	Development of a He-3 neutron spin filter and promotion of research using pulsed polarized neutrons.
   	J-PARC Center	Technology Development Section	J-PARC Center	Takayuki Oku Tel: +81-29-284-3196 E-mail: takayuki.oku@j-parc.jp	Radiation Worker	Physics, Radiation, Material, Applied Physics, Measurements and Instruments
   	At J-PARC MLF, a He-3 neutron spin filter (NSF) based on spin-exchange optical pumping method has been developed for the efficient utilization of pulsed neutrons. The employee will improve the He-3 NSF performance and adapt it to various kinds of experiments at J-PARC MLF. The employee will also develop sample environment which is optimized for use of the He-3 NSF, and will promote research using pulsed polarized neutrons.
   J35	Research on advanced nuclear characterization method of accelerator driven transmutation system using J-PARC facility
   	J-PARC Center	Facility and Application Development Section	J-PARC Center	Shin-ichiro Meigo Tel: +81-29-284-3207 E-mail: meigo.shinichiro@jaea.go.jp	Radiation Worker	Physics, Radiation, Material
   	For R&D to reduce of long-life radioactive waste with an accelerator-driven system (ADS), "ADS target test facility" is planned to be built as a part of nuclear transformation experiment facility (TEF) in J-PARC, which utilize spallation neutron produced at a lead-bismuth target irradiated with a 400-MeV proton beam. In this theme, basic nuclear data such as hydrogen and helium generation and DPA cross-sections will be measured by using J-PARC accelerator. The obtained data will be compared with model calculation such as a nucleon and meson transport calculation code (PHITS) to improve the nuclear reaction model, which is aimed to contribute to the optimization of the neutronics of the ADS. R&D on the partitioning and transmutation technology: http://snsr.jaea.go.jp/en/topics/pt.html"
   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.
   F1	Research 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 Group	Nuclear Science Reserch Institute	Takafumi Motooka Tel: +81-29-282-5950 E-mail: motoka.takafumi@jaea.go.jp	Radiation Worker	Mechanics, 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.
   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.
   F3	Research on radioactive material recovery and immobilization technology of radioactive waste
   	Collaborative Laboratories for Advanced Decommissioning Science (CLADS)	Waste Treatment Technology Development Group	Nuclear Fuel Cycle Engineering Laboratories	Yoshikazu Koma Tel: +81-29-282-1133 (60661) E-mail: koma.yoshikazu@jaea.go.jp	Non-Radiation Worker	Geo and Environemtal Sciences, Applied Chemistry, Material
   	It is important to develop volume reduction and safety storage for a large amount of solid waste generated from the accident of Fukushima Daiichi Nuclear Power Station. Removal and recovery technology of radioactive material from the solid waste using subcritical water washing, volume reduction and immobilization technology of recovered material by inorganic solids like a functional glass are developed in this research.
   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
   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.
   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.