HOME > News & Information > Recruitment > Recruitment for Postdoctoral Fellow(Fixed-term researcher)
| No | Theme | |||||
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| Department | Section | Location | Contact Person | Radiation Worker/ Non-Radiation Worker |
Field (for reference） |
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| 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. | ||||||
| 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. | ||||||
| J10 | Experimental and analytical study on thermohydraulic safety of light water reactor | |||||
| Nuclear Safety Research Center | Thermohydraulic Safety Research Group | Nuclear Science Research Institute | Yasuteru Sibamoto Tel: +81-29-282-5263 E-mail: sibamoto.yasuteru@jaea.go.jp | Non-Radiation Worker | Mechanics, 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. | ||||||
| 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. | ||||||
| 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. | ||||||
| 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. | ||||||
| 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. | ||||||
