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	Robotics	Other	All

2. No	Theme
   	Department	Section	Location	Contact Person	Radiation Worker/ Non-Radiation Worker	Field (for reference）
   	Summary
   J2	R&D for Laser Processing Simulation Code with Laser Processing Experiment and Deployment of Sensing Technology
   	Tsuruga Center for International and Regional Collaboration	Applied Laser Technology Institute	Tsuruga Head Office	Toshiharu Muramatsu E-mail: muramatsu.toshiharu@jaea.go.jp	Non-Radiation Worker	Mechanics Material Applied Physics Computer and Information Measurements and Instruments Material
   	We are developing laser processing technologies for industrial applications. First, the development of simulation code named "SPLICE" should be advanced to improve the numerical turbulent model and to optimize the parameters. High power laser processing experiment is needed for quantitative analysis. New laser systems and several sensing technologies are required for structural health monitoring with multiple sensors. Heat resistant optical fiber sensor has been installed on the piping system of demo-plant. Data remote processing is needed for monitoring the integrity. ※Energy base-ization of research and development Fukui-ken advances, they're the research and development concerned with advance of laser improvement process simulation code SPLICE developed aiming at contribution to a plan, and I make them promote more prefecture use of SPLICE cable through an outcome of this case. All together, I aim at preservation optics in atomic energy and innovation of status monitoring.
   J3	Study on feasibility and effectiveness evaluation for severe accident countermeasures
   	Nuclear Safety Research Center	Severe Accident Analysis Research Group	Tokai Research and Development Center Nuclear Science Research Institute	Tomoyuki Sugiyama Tel:+81-29-282-5253 E-mail: sugiyama.tomoyuki@jaea.go.jp	Non-Radiation Worker	Physics Chemistry Mechanics Material Applied Physics Computer and Information 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.
   J4	Study on the methodology of the structural integrity assessment for nuclear reactor components
   	Nuclear Safety Research Center	Structural Integrity Research Group	Tokai Research and Development Center Nuclear Science Research Institute	Yinsheng Li Tel:+81-29-282-6457 E-mail: li.yinsheng@jaea.go.jp	Non-Radiation Worker	Mechanics Material Applied Physics Physics Architectural and Civil Engineering Computer and Information
   	Because of the ageing degradation due to long term operation for Japanese nuclear power plants, developing the methodologies of structural integrity assessments for the reactor components concerning neutron irradiation, stress corrosion cracking and so on is of great importance. In this theme, researches on the deterministic approaches such as weld residual stress evaluation, crack propagation evaluation under large scale yielding condition, fracture evaluation concerning the crack or thinning for nuclear components are conducted on the basis of numerical simulation, material testing, and fracture testing and so on. In addition, probabilistic fracture mechanics analysis codes concerning ageing degradation of nuclear components are developed on the basis of the knowledge obtained from simulation and testing.
   J5	Study on aging degradation of nuclear reactor structural materials under irradiation
   	Nuclear Safety Research Center	Materials and Water Chemistry Research Group	Tokai Research and Development Center Nuclear Science Research Institute	Yutaka Nishiyama Tel:+81-29-282-5044 E-mail: nishiyama.yutaka93@jaea.go.jp	Radiation Worker	Mechanics Material Measurements and Instruments
   	In the nuclear reactor structural materials used under irradiation, the material properties, the interface reactions with the coolant and the stress conditions etc. change simultaneously. They are important phenomena to evaluate the aging degradation of light water reactors. In this study, for ferritic steels and austenitic stainless steels used as the nuclear reactor structural materials, the changes in material and mechanical properties (such as microstructure, crack growth and fracture toughness etc.) induced by irradiation are investigated. From these results, the effects on the structural integrity of the reactor pressure vessels and the core internals are evaluated.
   J7	Study on high-temperature oxidation behavior of fuel cladding
   	Nuclear Safety Research Center	Fuel Safety Research Group	Tokai Research and Development Center Nuclear Science Research Institute	Masaki Amaya Tel:+81-29-282-5028 E-mail: amaya.masaki@jaea.go.jp	Non-Radiation Worker	Material Mechanics
   	It has been reported that a oxidation rate of light-water-reactor fuel cladding might rapidly increase when the fuel cladding was exposed to high-temperature steam for a long period, which is so-called "breakaway oxidation". In order to evaluate the embrittlement of fuel cladding under a loss-of-coolant accident (LOCA), it is important to consider the breakaway oxidation. However, sufficient information has not been obtained about the initiation condition of the breakaway oxidation and the effect of the breakaway oxidation on the mechanical strength of fuel cladding. In this study, the change of the high-temperature oxidation kinetics of fuel cladding, which may lead to the breakaway oxidation, will be investigated by conducting high-temperature oxidation tests of fuel cladding specimens under simulated LOCA conditions. Mechanical tests will be also conducted on the oxidized specimens in order to evaluate the effect of the change in high-temperature oxidation behavior on mechanical strength of fuel cladding.
   J8	Experimental Research on Safety Assessment of Storage and Disposal of Radioactive Waste
   	Nuclear Safety Research Center	Waste Safety Research Group	Tokai Research and Development Center Nuclear Science Research Institute	Tetsuji Yamaguchi Tel:+81-29-282-6001 E-mail: yamaguchi.tetsuji@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 and alteration of glass, metals, clays, concretes and polyethlene focusing on primary factors such as adjacent barrier materials, groundwater composition, geology, colloids, microbes and radiolysis. The goal is to obtain scientific basis for models evaluating changes in the barrier functions and for systematical establishment of datasets.
   J19	Electronic property of heavy element systems
   	Sector of Nuclear Science Research Advanced Science Research Center	Research Group for Materials Physics for Heavy Element Systems	Tokai Research and Development Center Nuclear Science Research Institute	Shinsaku Kambe Tel:+81-29-284-3525 E-mail: kambe.shinsaku@jaea.go.jp	Radiation Worker	Physics Applied Physics Material
   	Condensed matter physics in heavy element systems. Particularly magnetism and superconductivity in f-electron compounds.
   J20	Theoretical study on spin-energy transformation materials
   	Sector of Nuclear Science Research Advanced Science Research Center	Research Group for Spin-energy Transformation Science	Tokai Research and Development Center Nuclear Science Research Institute	Michiyasu Mori Tel:+81-29-284-3508 E-mail: mori.michiyasu@jaea.go.jp	Non-Radiation Worker	Physics Mathematics Material
   	A successful candidate will theoretically study spin- and thermal-transport properties using some numerical techniques such as density functional theory, density matrix renormalization group method, quantum Monte Carlo method and so on. Thermoelectric materials, primarily related to spin Seebeck effect, and radiation-proof devices will be also important subjects of candidate.
   J21	Materials science research by using a muon beam
   	Sector of Nuclear Science Research Advanced Science Research Center	Research Group for Nanoscale Structure and Function of Advanced Materials	Tokai Research and Development Center Nuclear Science Research Institute	Wataru Higemoto Tel:+81-29-284-3873 E-mail: higemoto.wataru@jaea.go.jp	Radiation Worker	Physics Chemistry Material Applied Physics Applied Chemistry Measurements and Instruments
   	The applicant will be involved in materials science research by using accelerator-produced muons, which are implanted into a material and used as a sensitive local probe. In our group, the applicant will be able to use advanced muon beams, such as an ultra-slow muon beam in J-PARC, to investigate various functional materials. Instrumentation is also encouraged for the purpose. (http://asrc.jaea.go.jp/soshiki/gr/Nanoscale-gr/index.html)
   J24	Research on high-performance oxygen sensor for liquid lead-bismuth eutectic
   	Nuclear Science and Engineering Center	Research Group for Corrosion Resistant Materials, Fuels and Materials Engineering Division	Tokai Research and Development Center Nuclear Science Research Institute	Fumiyoshi Ueno Tel:+81-29-284-3581 E-mail: ueno.fumiyoshi@jaea.go.jp	Non-Radiation Worker	Material Chemical Engineering
   	In JAEA, for the purpose of reducing the radioactive waste, Accelerator Driven System (ADS) for transmuting radioactive materials is developing. ADS is used lead-bismuth eutectic (LBE) liquid metal in the coolant and spallation target. Corrosion behavior of metallic material such as stainless steel changes by the oxygen concentration in the high temperature LBE, it is necessary to develop a high-performance sensor for measuring the oxygen concentration in the LBE. Therefore, in this theme, as fundamental research for measuring the oxygen concentration in the LBE with high accuracy, we will assemble a prototype oxygen sensor to perform measurement test. The effect of the impurities in LBE on measurement accuracy of the sensor will be investigated by analysis of surface deposits, thermodynamic analysis and electrochemical analysis.
   J25	Evaluation of correlation between changes in microstructure and mechanical properties in irradiated materials (metal, steel, and ceramics)
   	Nuclear Science and Engineering Center	Research Group for Radiation Materials Engineering, Fuels and Amterials Engineerign Division	Tokai Research and Development Center Nuclear Science Research Institute	Shinichiro Yamashita Tel:+81-29-282-5391 E-mail: yamashita.shinichiro@jaea.go.jp	Radiation Worker	Radiation Material Physics Mechanics
   	In order to increase safety and integrity in existing and future nuclear power plants, micrstructural observation and a wide variety of mechanical strength tests (tensile, hardness measurement, and toughness etc) of nuclear reactor component materials such as structural material and simulated fuel-like oxide irradiated at various environmental conditions will be performed. Based on the experimental data acquired, a correlation between changes in microstructure and mechanical properties in the materials will be evaluated. In addition to that, it is possible to conduct fundamental study on radiation damage for the materials. Through these works, it is expected that synergistic function among environmental factors (irradiation, thermal load, stress, atmosphere etc) influencing on correlation evaluation for those materials will be clarified, contributing increment of safety and integrity in the existing/future nuclear power plants.
   J28	Research and Development of Evaluation Method for Core Degradation and Release of Radioactive Materials at LWR Accident
   	Nuclear Science and Engineering Center	Develppment Group for Thermal-Hydraulics Technology, LWR Key Technology Development Division	Tokai Research and Development Center Nuclear Science Research Institute	Hiroyuki Yoshida Tel:+81-29-282-5275 E-mail: yoshida.hiroyuki@jaea.go.jp	Radiation Worker	Physics Chemistry Material Mechanics
   	A coupled analysis method of thermal-hydraulics and chemical reaction is developed to evaluate core degradation and release of radioactive materials in Light Water Reactor (LWR) accidents in this study. In detail, numerical methods and models simulating thermal-hydraulic behavior with chemical reactions are developed to solve melting of nuclear fuel and metals, release of radioactive materials and relocation of molten and released materials. In addition, new thermal-hydraulic and chemical reactions experiments are performed to validate developed methods and models. By developing this method, basic knowledge to understand multi-physics phenomena at LWR accidents is obtained, and numerical models for severe accident analysis codes are improved.
   J29	Research of fatigue evaluation method of target vessel for high-power spallation neutron source
   	Sector of Nuclear Science Research, J-PARC Center	Materials and Life Science Division Neutron Source Section	J-PARC	Eiichi Wakai Tel:+81-29-284-3745 E-mail: wakai.eiichi@jaea.go.jp	Radiation Worker	Material Mechanics Measurements and Instruments
   	In Materials and Life Science Experimental Facility (MLF) of J-PARC, it is required to develop the spallation neutron source for the stable operation at 1 MW proton beam power, and various researches of the mercury target vessel are performing by the quantitative evaluation method. In this theme, there are some research subjects as follows: (1) Study of the fatigue phenomenon and thermal stress in the mercury vessel induced by the pulsed proton beam, (2) The experimental technology R&D including the fatigue properties and the testing to improve and advance the evaluation method of life time estimation of the target vessel, (3) The related systematic studies of the spallation neutron source and the target vessel for the stable operation at 1 MW.
   J33	Development of lead-bismuth spallation target
   	Sector of Nuclear Science Research, J-PARC Center	Nuclear Transmutation Division Target Technology Development Section	J-PARC	Toshinobu Sasa Tel:+81-29-282-5364 E-mail: sasa.toshinobu@jaea.go.jp	Non-Radiation Worker	Physics Material Measurements and Instruments Robotics Computer and Information
   	JAEA plans to build Transmutation Experimental Facility (TEF) to realize innvative accelerator-driven systen (ADS) for transmutation of long-lived radioactive nuclides. R&Ds to install a 250kW lead-bismuth spallation target in TEF for material irradiation, such as simulation of neutronic- and thermal-hydraulic performance, development of target components and instruments, and remote handling systems, will be performed.
   J36	Study of geological environment during construction, operation and closure of underground facility.
   	Tono Geoscience Center	Crystalline environment research group	Tono Geoscience Center	Teruki Iwatsuki E-mail: iwatsuki.teruki@jaea.go.jp	Non-Radiation Worker	Geo and Environemtal Sciences Chemistry Biology Chemical Engineering Measurements and Instruments Material
   	The construction, operation and closure of large underground facility changes hydraulic and hydrochemical condition around the facility. Such disturbance process and the recovery mechanism are still unclear. It is required to develop the observation and simulation methods for understanding of the phenomenon. Postdoctoral fellow studies the hydraulic and hydrogeochemical evolution (artificial disturbance and the recovery) process, impact of burial materials such as cement, clay in deep underground around Mizunami Underground Research Laboratory (MIU) during facility construction and after the closure by analyzing the rock, groundwater and burial materials, and previous data.
   F3	Research on severe accident progression behavior of the Fukushima Daiichi NPP accident
   	Collaborative Laboratories for Advanced Decommissioning Science (CLADS), Sector of Fukushima Research and Development	Molten Core Behavior Analysis Group Severe Accident Propagation Behavior Evaluation Division	Tokai Research and Development Center (Nuclear Science Research Institute)	Toshio Nakagiri Tel:+81-(0)29-267-1919, Ex.5802 E-mail: nakagiri.toshio@jaea.go.jp	Non-Radiation Worker	Physics Chemistry Radiation Mechanics Material Measurements and Instruments Computer and Information
   	Analytical evaluation using SA codes (SCDAP, MELCOR, etc.) and 1F plant data are peroformed to enhance understanding on accident progression behavior in the Fukushima Daiichi NPP. In this theme, evaluation of 1F plant data with SA code analysis will be conducted and possibility of model improvement will be considered where appropriate.
   F4	Research on the degradation behavior of fuel assemblies in Fukushima Daiichi NPP accident condition
   	Collaborative Laboratories for Advanced Decommissioning Science (CLADS), Sector of Fukushima Research and Development	Molten Core Behavior Analysis Group Severe Accident Propagation Behavior Evaluation Division	Tokai Research and Development Center (Nuclear Science Research Institute)	Toshio Nakagiri Tel:+81-(0)29-267-1919, Ex.5802 E-mail: nakagiri.toshio@jaea.go.jp	Non-Radiation Worker	Physics Chemistry Mechanics Material Measurements and Instruments
   	Present knowledge on reaction behavior of the fuel assembly materials (control blade, fuel rod, channel box) is insufficient to understand degradation behavior of fuel asseblies in the Fukushima Daiichi NPP accident. In this theme, laboratory scale experiments on reaction behavior of fuel assembly materials, large scale experiments on the degradation behavior of fuel assemblies and development of individual reaction models will be performed.
   F8	Research on alteration and leaching of molten fuel
   	Collaborative Laboratories for Advanced Decommissioning Science (CLADS), Sector of Fukushima Research and Development	Fuel Debris Characterization and Conditioning Technology Development Group Fuel Debris Handling and Analysis Division	Tokai Research and Development Center (Nuclear Fuel Cycle Engineering Laboratories)	Hideki Ogino Tel:+81-29-282-1126 E-mail: ogino.hideki@jaea.go.jp	Non-Radiation Worker	Physics Material Chemical Engineering Chemistry Geo and Environemtal Sciences Radiation Computer and Information
   	The work on fuel debris removal from the damaged reactors at Fukushima Daiichi NPP requires a considerably long time. Considering long-term removal work and the subsequent processes such as storage, treatment and disposal, alteration of fuel debris should be evaluated . Although it is anticipated that alteration of fuel debris can be developed by external environments such as air, water and radiation (e.g., the conversion of debris surfaces into powder form and elution into the water), there is little knowledge about alteration. In this research, the alteration and leaching behavior of fuel debris will be evaluated and their models will also be developed based on the knowledge about the alteration of Chernobyl LFCM and the disposal technologies of spent fuel and vitrified waste, etc.
   F10	Research on the chemical form of radioactive material in the environment and its dissolution within environmental water systems by use of solid analysis techniques
   	Sector of Fukushima Research and Development Fukushima Environmetal Safety Center	Fukushima Environmental Restoration Group	Fukushima(Miharu)	Kazuki Iijima Tel:+81-：247-61-2913 E-mail: iijima.kazuki@jaea.go.jp	Non-Radiation Worker	Chemistry Geo and Environemtal Sciences Material Measurements and Instruments
   	The radioactive cesium deposited on the land surface of Fukushima exists mostly in forests and small portions of it discharge each year into the ocean through river systems. The dissolved form of radioactive cesium migrates most easily within the eco-system. Although dissolved radiocesium concentrations are low, it is still detected in stemflow and riverflows, and this fact is considered to be the reason for the existence of freshwater fish and mushrooms with high radioactive cesium concentration. In order to predict the future behaviour of radioactive cesium in the eco-system, it is necessary to clarify the chemical form of radioactive cesium in the forest and the mechanism by which it dissolves. In this research program, we will try to uncover these issues by utilizing solid analysis instruments such as TEM, EPMA, FIB, XPS, etc., installed in the Fukushima Environmental Creation Center.
   F13	Research and development of treatment method for radioactive wastes generated at the contaminated water treatment facility in Fukushima Daiichi Power Plant
   	Sector of Nuclear Science Research Advanced Science Research Center	Research Group for Interfacial Reaction Field Chemistry	Tokai Research and Development Center Nuclear Science Research Institute	Kazuya Tanaka Tel:+81-29-284-3518 E-mail: tanaka.kazuya@jaea.go.jp	Radiation Worker	Geo and Environemtal Sciences Chemistry 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 conversion to stable inorganic form and subsequent solidification.
   F15	Investigation of the characteritics of radioactive material in a severe accident condition
   	Nuclear Science and Engineering Center	Research Group for LWR Advanced Technology LWR Key Technology Development Division	Tokai Research and Development Cente (Nuclear Science Research Institute)	Masahiko Osaka Tel:+81-29-267-4141 E-mail: ohsaka.masahiko@jaea.go.jp	Radiation Worker	Physics Chemistry Material Mechanics
   	In order to acquire fundamental knowledge on fission product (FP) behavior and dose evaluation for the decommissioning of Fukushima Daiich Nuclear Power Station, we are investigating the behavior of radioactive material in the Primary Containment Vessel (PCV) under severe accident conditions. The post-doctoral fellow will investigate the characteristics of such radioactive material and aerosols (chemical form, size distribution, etc) by conducting simulation tests. These tests will simulate FP transport from core to PCV. The aerosols analyses on size distribution will be conducted in the different transport stages, and will be coupled with post characterizations of the deposits (microstructure and chemical state). The post-doctoral fellow will be also involved in the evaluation of the radioactive material behavior and aerosol formation mechanism, by performing analytical studies on the chemical reaction kinetics and by comparing the simulation tests with the analysis of environmental samples.
   F16	Clarification of Cs desorption mechanism on Cs free mineralization of clay minerals
   	Materials Sciences Research Center	Analytical Sciences Development Research Group	Tokai Research and Development Center (Nuclear Science Research Institute)	Iwao Shimoyama Tel:+81-29-284-3929 E-mail: shimoyama.iwao@jaea.go.jp	Radiation Worker	Chemistry Physics Geo and Environemtal Sciences Material
   	We study Cs desorption mechanism from clay minerals to develop Cs-free meneralization for volume reduction and reuse of radioactive contaminated soil in Fukushima. Weathered biotite (WB) in Fukushima is adopted as a model soil and sorbed with non-radioactive Cs. WB is heated with some alkaline salt reagents in ambient atomosphere condition or low-pressure conditions and products formed after the heating treatment are analyzed using X-ray diffraction and X-ray flulrescence analysis. Especially, we focus on the dependences of reagents and pressure on Cs desorption ratio and structural change of WB in this study.