HOME > News & Information > Recruitment > Recruitment for Postdoctoral Fellow(Fixed-term researcher)
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| Department | Section | Location | Contact Person | Radiation Worker/ Non-Radiation Worker |
Field (for reference） |
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| 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. | ||||||
| J6 | Experimental and analytical study on thermohydraulic safety of the light water reactor | |||||
| Nuclear Safety Research Center | Thermohydraulic Safety Research Group | Tokai Research and Development Center Nuclear Science Research Institute | Taisuke Yonomoto Tel:+81-29-282-5263 E-mail: yonomoto.taisuke@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. | ||||||
| J10 | Study on a Level 3 Probabilistic Risk Analysis of nuclear power plants | |||||
| Nuclear Safety Research Center | Radiation Risk Analysis Research Group | Tokai Research and Development Center 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. | ||||||
| J13 | Research on Criticality Safety/Management of Damaged- or Molten-Fuel formed by Severe Accidents | |||||
| Nuclear Safety Research Center | Criticality Safety Research Group | Tokai Research and Development Center Nuclear Science Research Institute | Kotaro Tonoike Tel:+81-29-284-3762 E-mail: tonoike.kotaro@jaea.go.jp | Radiation Worker | Physics 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. | ||||||
| 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. | ||||||
| J35 | Study on in-vessel thermal-hydraulic behavior during the loss of forced cooling accidents in HTTR | |||||
| Sector of Nuclear Science Research Oarai Research and Development Center Department of HTTR | HTTR Reactor Engineering Section | O-arai Research and Development Center | Daisuke Tochio Tel:029-267-1919-3730 E-mail: tochio.daisuke@jaea.go.jp | Non-Radiation Worker | Mechanics Computer and Information | |
| The Loss Of Forced Cooling (LOFC) Test Plan is in progress in the High Temperature Engineering Test Reactor (HTTR) under the international collaboration. The thermal-hydraulic behavior of fuel, structure and coolant is important during LOFC. In this study,thermal-hydraulic analysis model is constructed and numerical analysis is performed using commercial CFD analysis code to reveal the in-vessel thermal-hydraulic behavior during the LOFC. | ||||||
| J37 | The study of knowledge management method on the decommissioning of nuclear facilities | |||||
| Sector of Decommissioning and Radioactive Waste Management Fugen Decommissioning Engineering Center | Technology Development Department Dismantlement Engineering Section | Fugen Decommissioning Engineering Center | Masashi Tezuka E-mail: tezuka.masashi@jaea.go.jp | Radiation Worker | Mathematics Computer and Information | |
| The decommissioning of a nuclear facility is a long term project. The transfer of knowledge and education to the next generation is a crucial issue. It is necessary to systemize of knowledge based on the knowledge engineering method such as ontology. Concretely speaking, we collect a large amount of explicit knowledge regarding decommissioning such as domestic and foreign information, instruments information and know-how, and arrange it. On the other hand, we try to translate personal tacit knowledge collected by interview to explicit knowledge as possible. After these, we can use whole knowledge of decommissioning organized and systematized, and study advanced knowledge engineering method available for education and succession. | ||||||
| F1 | Computational study on the chemical form of radionuclides in environment and their transport | |||||
| Center for Computational Science & e-Systems | Simulation technology R&D Office | 178-4-4 Wakashiba, Kashiwa, Chiba, 277-0871, Japan | Masahiko Machida Tel:+81-04-7135-2349 E-mail: machida.masahiko@jaea.go.jp | Non-Radiation Worker | Physics Geo and Environmental Sciences Computer and Information Chemistry | |
| The transport of radioactive Cesium and other radionuclides in the environment (including soil, rivers, coastal area and other environment) widely varies depending on the surroundings. These variation mainly originates from changes in the chemical and physical form of substances which absorb the radionuclides, such as soil particles and organic polymers of biological origin. Thus comprehensive evaluation of the transport of radionuclides in various environment requires development of transport model that incorporates the effects of different circumstances, based on the bottom-up modeling framework from the atomistic and molecular level up to the mesoscopic and macroscopic scales. The applicant is supposed to develop the modeling framework and simulation codes for the evaluation of transport of radionuclides that incorporates the change of physical and chemical form of radionuclides in various circumstances, to clarify the overall transport of Cesium and other radionuclides in Fukushima environment. | ||||||
| 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. | ||||||
| F5 | Development of Technology for Working Environment Data Collection and Accumulation by Remote Operated Robots | |||||
| Collaborative Laboratories for Advanced Decommissioning Science (CLADS), Sector of Fukushima Research and Development | Remote Technology and Robotics Group, Remote System and Sensing Technology Division | Tokai Research and Development Center (Nuclear Science Research Institute) or Tomioka International Collaborative Research Building (now under constructing) | Dr. Tatsuo TORII Tel:+81-(0)29-282-6329 E-mail: torii.tatsuo@jaea.go.jp | Non-Radiation Worker | Computer and Information Robotics Electricity and Electronics Mechanics | |
| For long-term decommissioning process of the Fukushima Daiichi NPP, it is importatnt to gather and accumulate the data of the working environment as the reference to plan the missons and to use for the workers' training. The objective of this reseach subject is to develp the map building and working enviromental modeling method based on collected sensory data by remote operated robots and sensing systems. Design and implementation of spatio-temporal database to register the working environment data is also included in this research project. | ||||||
| F6 | R&Ds on Radiation Imaging Technologies under High-dose Environments | |||||
| Collaborative Laboratories for Advanced Decommissioning Science (CLADS), Sector of Fukushima Research and Development | Radiation Imaging and Instrument Group Remote System and Sensing Technology Division | Tokai Research and Development Center (Nuclear Science Research Institute) or Tomioka International Collaborative Research Building (now under constructing) | Jun Saegusa Tel:+81-(0)29-282-6144 E-mail: saegusa.jun@jaea.go.jp | Radiation Worker | Physics Radiation Computer and Information Electricity and Electronics Applied Physics Measurements and Instruments | |
| For the decommissioning of TEPCO Fukushima Daiichi Nuclear Power Plants, gamma-ray detectors that can estimate the position, shape and nuclide distributions of residual debris are to be developed. In particular, a prototype detection system consisting of two-dimensional-gamma-imaging units and compact scintillator crystals is developed for the application to fuel debris measurements, and response characteristics of each element to gamma-rays are evaluated. In addition, a compact/lightweight gamma-camera is to be manufactured for the evaluation of its detection capability to radioactive materials and of durability against radiations. An unmanned remote radiation measurement system for the imaging of the radioactivity distribution in the Fukushima reactor building are also to be developed. | ||||||
| F7 | R&Ds on Image Processing Technologies for Radiation Measurement Data on Reactor Decommissioning | |||||
| Collaborative Laboratories for Advanced Decommissioning Science (CLADS), Sector of Fukushima Research and Development | Radiation Imaging and Instrument Group Remote System and Sensing Technology Division | Tokai Research and Development Center (Nuclear Science Research Institute) or Tomioka International Collaborative Research Building (now under constructing) | Jun Saegusa Tel:+81-(0)29-282-6144 E-mail: saegusa.jun@jaea.go.jp | Non-Radiation Worker | Computer and Information Radiation Physics Mathematics Applied Physics Measurements and Instruments | |
| Towards the planned removal of fuel debris from the TEPCO Fukushima Daiichi Nuclear Power Plants in 2021, reduction of radiation doses to workers and countermeasures against the spreading of radioactive contaminations are essential. For the purpose, three-dimensional visualization (mapping) of dose rates and radionuclide distributions are required as well as the real time monitoring of dose rates in the reactor building. So far, developments on radiation measurement techniques in the Fukushima Daiichi NPPs are in progress, and results obtained from these developments are to be visualized by the proposed R&Ds. Especially, developments of the algorithm for the three-dimensional image reconstruction is to 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. | ||||||
| F12 | High-energy gamma-rays accompanied by fission | |||||
| Sector of Nuclear Science Research Advanced Science Research Center | Research Group for Heavy Element Nuclear Science | Tokai Research and Development Center Nuclear Science Rsearch Institute | Dr. Katsuhisa Nishio Tel:+81-29-282-5454 E-mail: nishio.katsuhisa@jaea.go.jp | Radiation Worker | Physics Radiation Measurements and Instruments Applied Physics Computer and Information | |
| Measurement of high-energy gamma-rays accompanied by fission will be carried out, and the mechanism of this radiation will be investigated. The main goal is to use this radiactivity to monitor the criticality of nuclear fuel debris of damaged Fukushima atomic power plants, which is necessary in the process of decommissioning. An experiment will be carried out using neutron beam supplied by a research reactor. Fission study is also the scope of this program using heavy-ion beams and and photons. | ||||||
