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Recruitment for Postdoctoral Fellow 2022 (Fixed-term researcher)
Recruitment Field for Postdoctoral Fellow of JAEA

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No.J1
ThemeDevelopment of nuclear thermal hydraulic CFD simulaitons based on muli-phase fluid models
DepartmentCenter for Computer Science and e-Systems
SectionComputational Science Research and Development Office
LocationKashiwa, Chiba
ContactPersonYasuhiro Idomura
Tel +81-70-1470-5237
E-mail idomura.yasuhiro@jaea.go.jp
SummaryCCSE promotes the development of nuclear thermal hydraulic CFD simulations based on the Navier-Stokes equation, and conducts simulations studies on the safety evaluation of BWRs and the melt relocation behavior in severe accidents. In these simulations, phase changes such as boiling and condensation of fluids, and melting and solidification of materials are of critical importance, and improved physics models taking account of their physical properties are essential. The candidate is expected to address the improvement of multi-phase fluid models in nuclear thermal hydraulic CFD simulations on GPU based supercomputers.
Radiation Worker/
Non-RadiationWorker
Non-Radiation Worker
Field
(for reference)
Physics
Mechanics
Applied Physics
Applied Chemistry
Computer and Information
No.J2
ThemeDevelopment of visualization technologies for nuclear simulations
DepartmentCenter for Computer Science and e-Systems
SectionComputational Science Research and Development Office
LocationKashiwa, Chiba
ContactPersonYasuhiro Idomura
Tel +81-70-1470-5237
E-mail idomura.yasuhiro@jaea.go.jp
SummaryCCSE promotes the development of visual analytics techniques for state-of-the-art nuclear simulations such as nuclear thermal hydraulics and plume dispersion of radioactive substances. Such nuclear simulations compute not only complex physics models and larger scale problems, but also ensemble problesms for uncertainty quantification. To understand those simulations, new visualization technologies are needed. The candidate is expected to address the development of new visualization technologies such as ensemble data visualization and VR based visualization for advanced nuclear simulations.
Radiation Worker/
Non-RadiationWorker
Non-Radiation Worker
Field
(for reference)
Computer and Information
No.J3
ThemeR&D of big-data analytics and simulationmodeling utilizing machine learning
DepartmentCenter for Computer Science and e-Systems
SectionComputational Science Research and Development Office
LocationKashiwa, Chiba
ContactPersonMitsuhiro Itakura
Tel +81-80-9668-6997
E-mail itakura.mitsuhiro@jaea.go.jp
SummaryCenter for Computational Science and e-Systems (CCSE) is conducting R&D in nuclear engineering to extracthigh-level information and new knowledge from various data obtained by experiments and observations,utilizing machine-learning techniques. In addition, CCSE is also conducting R&D to develop fast surrogatemodel for atomistic simulations and fluid dynamics ones through machine-learning of their simulation results.Applicant is supposed to select themes from above mentioned R&D's in terms of applications of machine-learning techniquesand conduct research on them. Applicant is also supposed to communicate with researchers of JAEA and otherinstitutes closely to share data from experiment and observations as well as research problems and issues insimulation studies.
Radiation Worker/
Non-RadiationWorker
Non-Radiation Worker
Field
(for reference)
Computer and Information
Physics
Material
Geo and Environmental Sciences
Mechanics
No.J4
ThemeStudy on safety assessment of decommissioning of nuclear facilities
DepartmentNuclear Safety Research Center
SectionWaste and Environmental Safety Research Group
LocationTokai
ContactPersonTaro Shimada
Tel +81-29-284-3714
E-mail shimada.taro@jaea.go.jp
SummaryAt each stage of planning and completion of the decommissioning of nuclear facilties, it is required to assess the exposure dose of public and workers and to confirm them to be satisfied with the dose criteria. IAEA recomendation says that the minimization of radioactive wastes is also required in the decommissioning activities. In addtion, it is necessary to manage a risk depending on the progress of the dismantling activities. In this study, the methodology for the evaluation and the validation of the planning, conducting and the completion of the decommissioning will be sophisticated as follows.
- Modelling for optimization of reducing both of radioactive wastes arising and doses for worker and public, and developing the methodology
- Development of risk assessment methods during dismantling activities
- Development of evalution methods of radioactivity distribution at the site release, and nuclides migration and dose assessment based on the site characterization and the radioactivity distribution
Radiation Worker/
Non-RadiationWorker
Non-Radiation Worker
Field
(for reference)
Physics
Radiation
Computer and Information
No.J5
ThemeStudy on the methodology of the structural integrity assessment for nuclear reactor components
DepartmentNuclear Safety Research Center
SectionStructural Integrity Research Group
LocationTokai
ContactPersonYinsheng Li
Tel +81-29-282-6457
li.yinsheng@jaea.go.jp
SummaryDue to the long-term operation of some domestic nuclear power plants, the occurrence of the earthquakes beyond the designed seismic ground motion, and the regulation considering projectiles colliding in new regulatory standards, developing the methodologies of structural integrity assessments for the building , reactor components, and piping concerning seismic and impact loadings 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 seismic safety assessment research including development of three-dimensional evaluation models of nuclear facility buildings, components and piping systems, and numerical simulation considering nonlinear mechanical properties,
- Research and development on impact assessment methods for buildings and internal components due to projectile collision,
- 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.
Radiation Worker/
Non-RadiationWorker
Non-Radiation Worker
Field
(for reference)
Mechanics
Architectural and CivilEngineering
Material
Physics
Applied Physics
Measurements and Instruments
Computer and Information
No.J6
ThemeStudy on Material Degradation Evaluation for Nuclear Rector Components
DepartmentNuclear Safety Research Center
SectionMaterial evaluation research group
LocationTokai
ContactPersonJinya Katsuyama
Tel +81-29-282-5044
E-mail
katsuyama.jinya@jaea.go.jp
SummaryIn order to ensure the structural integrity of safety-related components in the light water reactors during long-term operation, the confirmation of conservativness and continuous improvement of the structural integrity assessment methods should be performed based on the latest knowledge on the material degradation mechanisms and assessment methods. In this study, for investigating the effects of peculiar environments to the reactors such as neutron irradiation, high temperature and pressureized water on the material deterioration, and improving the structural integrity assessment method based on fracture mechanics for pressure boundary components, we will perform the emperical investigatoins on microsturcture and fracture toughness of irradiated materials, initiation and propagation of the stress corrosion cracking in high temperature and pressure water environments, and the analytical investigations based on the finite element analysis using the local approach.
Radiation Worker/
Non-RadiationWorker
Radiation Worker
Field
(for reference)
Mechanics
Material
Measurements and Instruments
Computer and Information
No.J7
ThemeStudy on analytical techniques for individual particles containing nuclear materials in environmental samples
DepartmentNuclear Safety Research Center
SectionResearch Group for Safeguards Analytical Chemisty
LocationTokai
ContactPersonYutaka Miyamoto
Tel +81-29-282-5544
miyamoto.yutaka@jaea.go.jp
SummaryAnalysis of ultra-trace 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, ultra-trace analytical techniques for measuring isotopic composition and/or chemical states of uranium and/or plutonium in a nuclear particle are developed using secondary ion mass spectrometer and micro-Raman spectrometer.
Radiation Worker/
Non-RadiationWorker
Radiation Worker
Field
(for reference)
Chemistry
Applied Chemistry
No.J8
ThemeStudy on release and transport behavior of radioactive materials in reprocessing plant under severe accident conditions
DepartmentNuclear Safety Research Center
SectionFuel Cycle Safety Research Group
LocationTokai
ContactPersonHitoshi Abe
Tel +81-29-282-6672
abe.hitoshi@jaea.go.jp
SummaryNewly 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.
Radiation Worker/
Non-RadiationWorker
Non-Radiation Worker
Field
(for reference)
Chemistry
Chemical Engineering
Computer and Information
No.J9
ThemeStudy on methodology of accident consequence analysis and its application to the protection of people living in affected areas after a Nuclear Accident
DepartmentNuclear Safety Research Center
SectionRisk Analysis Research Group
LocationTokai
ContactPersonShogo Takahara
Tel +81-29-282-6139
takahara.shogo@jaea.go.jp
SummaryThe aim of this study is to develop the assessment methods of consequences due to a Nuclear Accident, and also application to the protection of people living in affected areas after the accident. To achieve this aim, one of the following tasks or other related tasks will be made:
①Development of accident consequence assessement methods including radiation dose assessement and social-econical impacts analysis;
②Development of calculation codes which are implemented latest methods related to consequence assessments, and of a level 3 PRA code OSCAAR;
③Optimization of nuclear emergency preparedness by using a level 3PRA code OSCAAR;
④Research on public understanding and behavior, and public communication in nuclear emergency preparedness.
Radiation Worker/
Non-RadiationWorker
Non-Radiation Worker
Field
(for reference)
Physics
Geo and Environmental Sciences
Chemistry
Mathematics
Radiation
Other
No.J10
ThemeExperimental and analytical studies on the fuel behavior under accident conditions of light-water-reactor
DepartmentNuclear Safety Research Center
SectionFuel Safety Research Group
LocationTokai
ContactPersonYutaka Udagawa
Tel +81-29-282-6230
E-mail udagawa.yutaka@jaea.go.jp
SummaryThe objective of this study is to develop and/or improve simulation tools and related models for safety evaluation on fuel behaviors primarily under accident conditions. The following or related studies will be carried out with both analytical and experimental approaches:
* Behaviors of accident torelant fuels (ATF): particularly Cr-coated Zr-alloy cladding and FeCrAl cladding
* Improvement of simulation techniques: probabilistic models for fuel performance code, coupling of fuel performance code with thermal-hydraulic calculation codes, fuel melt progression models under high temperature conditions, etc.
* Behaviors of high burnup fuels under accident conditions: clad deformation, rupture, hydride absorption, fuel pellet cracking, fuel axial relocation inside a fuel rod, fuel pulverization, fuel dispersal, etc.
* Evaluation of core coolability during and after accidents
Radiation Worker/
Non-RadiationWorker
Non-Radiation Worker
Field
(for reference)
Mechanics
Material
Physics
Applied Physics
Computer and Information
Mathematics
No.J11
ThemeExperimental and analytical study on thermohydraulic safety of light water reactor
DepartmentNuclear Safety Research Center
SectionThermohydraulic Safety Research Group
LocationTokai
ContactPersonYasuteru Sibamoto
Tel +81-29-282-5263
sibamoto.yasuteru@jaea.go.jp
SummaryThis research focuses on thermal hydraulic (TH) phenomena occurring in the reactor and the containment of nuclear power plant during an accident before and after core damage. The research topics include core heat transfer, system response of PWR, the related two-phase flow for before core damage, and containment TH as in containment cooling, hydrogen transport, combustion, and aerosol migration for sever accident. The analytical models used for CFD and BE codes are developed to improve evaluation techniques. In addition, experiments will be conducted using large and small scale facilitieis if necessary,
Radiation Worker/
Non-RadiationWorker
Non-Radiation Worker
Field
(for reference)
Mechanics
Measurements and Instruments
Computer and Information
No.J12
ThemeStudy on improvement of severe accident evaluation techniques
DepartmentNuclear Safety Research Center
SectionSevere Accident Research Group
LocationTokai
ContactPersonTomoyuki Sugiyama
Tel +81-29-282-5253
E-mail sugiyama.tomoyuki@jaea.go.jp
SummaryThis research aims at improvement of analysis techniques to evaluate plant response, accident progression, or radioactive materials transport/release behavior with effects of accident countermeasures. One of the followings or related task is carried out.
- Source term analysis for severe accidents such as the Fukushima Daiichi NPS accident, using the SA analysis code THALES2/KICHE.
- Analysis of coolability of molten core using the mechanistic FCI code JASMINE.
- CFD analysis of thermal-hydraulic and combustion behavior of hydrogen in containment vessel or reactor building.
Radiation Worker/
Non-RadiationWorker
Non-Radiation Worker
Field
(for reference)
Physics
Chemistry
Mechanics
Geo and Environmental Sciences
Computer and Information
Other
No.J13
ThemeResearch on Criticality Safety/Management of Damaged- or Molten-Fuel formed by Severe Accidents
DepartmentNuclear Safety Research Center
SectionCriticality Safety Research Group
LocationTokai
ContactPersonKenya SUYAMA
Tel +81-90-9803-7921
suyama.kenya@jaea.go.jp
SummaryIt might be requested to consider the change of isotopic composition of the nuclear fuel due to the burnup in the criticality safety evaluation of the fuel debris (damaged / melted fuel materials). This study contributes to the development and validation of the computer code system for the criticality safety analysis of the fuel debris in order to introduce the burnup calculation results using the latest computer code and nuclear data. This promotes the integration of the criticality safety evaluation system dedicated to the fuel debris.
Radiation Worker/
Non-RadiationWorker
Non-Radiation Worker
Field
(for reference)
Physics
Computer and Information
Applied Physics
Other
No.J14
Theme Physics of Exotic Nuclei
DepartmentSector of Nuclear Science Research Advanced Science Research Center
SectionResearch Group for Heavy Element Nuclear Science
LocationTokai, Nuclear Science Research Institute
ContactPersonKatsuhisa Nishio
Tel +81-29-282-5454
E-mail nishio.katsuhisa@jaea.go.jp
SummaryExperimental and theoretical studies of unstable nuclei and superheavy elements will be prompted. The research topics include nucler structure, nuclear reaction, and nuclear fission for nuclei far from the stable isotopes. In experimental programs, JAEA facilities and/or external facilities will be used to produce exotic nuclei. In theory subjects nuclear structure and fission process will be studied by taking advantage of the JAEA supercomputer.
(https://asrc.jaea.go.jp/soshiki/gr/HENS-gr/index_e.html)
Radiation Worker/
Non-RadiationWorker
Radiation Worker
Field
(for reference)
Physics
Mathematics
Radiation
Applied Physics
Measurements and Instruments
Computer and Information
Other
No.J15
ThemeNuclear chemistry of superheavy elements
DepartmentSector of Nuclear Science Research Advanced Science Research Center
SectionResearch Group for Heavy Element Nuclear Science
LocationTokai, Nuclear Science Research Institute
ContactPersonKazuaki Tsukada
Tel +81-29-282-5491
E-mail tsukada.kazuaki@jaea.go.jp
SummaryThe 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, molecular formations and so on related to the chemical phenomena of SHEs. The subjects include development of the measuring/analyzing system for the purpose based on an "atom-at-a-time" method. These experiments will be mainly performed at the JAEA Tandem Accelerator Facility.
(https://asrc.jaea.go.jp/soshiki/gr/HENS-gr/nc/index-e.htm)
Radiation Worker/
Non-RadiationWorker
Radiation Worker
Field
(for reference)
Chemistry
Radiation
Physics
Measurements and Instruments
Applied Chemistry
Other
No.J16
ThemeStudy of interface dynamics and order formation in soft condensed matter
DepartmentSector of Nuclear Science Research Advanced Science Research Center
SectionResearch Group for interfacial reaction-field chemistry
LocationTokai, Nuclear Science Research Institute
ContactPersonNoboru Aoyagi
Tel +81-(0)29-284-3769
E-mail aoyagi.noboru@jaea.go.jp
SummaryOur target is a theoretical, simulation, or experimental study on the reaction dynamics of heavy elements: e.g., at the solid-liquid interface—thin films and liquid phases—taking the phase transformation or critical phenomena into account. The research proceeds mainly at the facilities of the Nuclear Science Research Institute. The applicant is expected to actively utilize a wide range of knowledge and skills in physics, materials chemistry, electrical engineering, and computational science. Thus, we aim to design and develop flocculants and dispersants to recover heavy elements.
Radiation Worker/
Non-RadiationWorker
Radiation Worker
Field
(for reference)
Physics
Mathematics
Mechanics
Material
Computer and Information
No.J17
ThemeExperimental research for hadron and nuclear physics at J-PARC
DepartmentSector of Nuclear Science Research Advanced Science Research Center
SectionResearch Group for Hadron Nuclear Physics
LocationTokai, Nuclear Science Research Institute
ContactPersonHiroyuki Sako
Tel +81-29-284-3828
E-mail sako.hiroyuki@jaea.go.jp
SummaryThe successful candidates will work on hadron nuclear experimental research either at J-PARC Hadron Experimental Facility, J-PARC Heavy-Ion Project (J-PARC-HI), RHIC, or Belle (II), which are promoted by our group.
Radiation Worker/
Non-RadiationWorker
Radiation Worker
Field
(for reference)
Physics
No.J18
ThemeMaterials physics in heavy element systems
DepartmentSector of Nuclear Science Research Advanced Science Research Center
SectionResearch group for Materials physics for heavy element systems
LocationTokai, Nuclear Science Research Institute
ContactPersonShinsaku Kambe
Tel +81-29-284-3525
E-mail kambe.shinsaku@jaea.go.jp
SummaryNew 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.
Radiation Worker/
Non-RadiationWorker
Radiation Worker
Field
(for reference)
Physics
Applied Physics
Material
Chemistry
No.J19
ThemeStudy on Spin-current Generation
DepartmentSector of Nuclear Science Research Advanced Science Research Center
SectionResearch Group for Spin-energy Transformation Science
LocationTokai, Nuclear Science Research Institute
ContactPersonMichiyasu Mori
Tel +81-284-3508
E-mail mori.michiyasu@jaea.go.jp
SummaryA successful candidate will study the spin current generation using various degrees of freedom such as mechanical motions, surface acoustic waves, fluid motions, and rotational motions, nuclear spins, light, and heat. Nanomechanics such as cantilevers and a new spin current detection method using the diamond NV center are also involved. We aim to develop new energy conversion methods such as thermoelectric generation using magnetic materials.
Radiation Worker/
Non-RadiationWorker
Non-Radiation Worker
Field
(for reference)
Physics
Applied Physics
Material
No.J20
ThemeStudy on Spintronics Materials
DepartmentSector of Nuclear Science Research Advanced Science Research Center
SectionResearch Group for Spin-energy Transformation Science
LocationTokai, Nuclear Science Research Institute
ContactPersonMichiyasu Mori
Tel +81-284-3508
E-mail mori.michiyasu@jaea.go.jp
SummaryUsing various numerical methods such as first-principles calculation, finite element method, and so on, a successful candidate will develop useful materials and devices for spintronics, and apply them to spin thermoelectric generation and radiation-proof devices based on magnetic materials. We aim to improve energy efficiency and safety of nuclear power generation.
Radiation Worker/
Non-RadiationWorker
Non-Radiation Worker
Field
(for reference)
Physics
Applied Physics
No.J21
ThemeResearch of Material Science by using Advanced Muon Beam
DepartmentSector of Nuclear Science Research Advanced Science Research Center
SectionResearch Group for Nanoscale Structure and Function of Advanced Materials
LocationTokai, Nuclear Science Research Institute
ContactPersonWataru Higemoto
Tel +81-29-284-3873
E-mail higemoto.wataru@jaea.go.jp
SummaryMuon is one of an elemental paeticle and used as a probe of local state inside material. By using muon, which is obatined at J-PARC and other proton accelarator facilities, the candiate advance a material science and develpment of experimental instruments. An experience of muon experiment does not be required.
Radiation Worker/
Non-RadiationWorker
Radiation Worker
Field
(for reference)
Physics
Material
Chemistry
Measurements and Instruments
Applied Physics
Applied Chemistry
No.J22
ThemeStudy on Structure and Property of Nanoscale Materials
DepartmentSector of Nuclear Science Research Advanced Science Research Center
SectionResearch Group for Nanoscale Structure and Function of Advanced Materials
LocationTokai, Nuclear Science Research Institute
ContactPersonYuki Fukaya
Tel +81-29-282-6582
E-mail fukaya.yuki99@jaea.go.jp
SummaryThe research theme is focused on fabrication and structural investigation of nanoscale materials such as atomic sheets and surface superstructures. By using advanced surface-sensitive techniques, e.g. positron diffraction, electron diffraction, and scanning tunneling microscopy, the atomic configurations and electronic states are investigated, toward further developing novel functional materials having a radiation resistance.
Radiation Worker/
Non-RadiationWorker
Radiation Worker
Field
(for reference)
Physics
Material
Chemistry
Measurements and Instruments
Applied Physics
No.J23
ThemeStudy on Advanced Materials by Nanostructure control
DepartmentSector of Nuclear Science Research Advanced Science Research Center
SectionResearch Group for Nanoscale Structure and Function of Advanced Materials
LocationTokai, Nuclear Science Research Institute
ContactPersonSatoshi Yasuda
TEL: +81-29-282-6081
E-mail:yasuda.satoshi@jaea.go.jp
SummaryNovel functional electrocatalytic materials and the related devices such as fuel cell and CO2 reduction will be developed using molecular beam epitaxisy, scanning tunneling microscopy, X-ray photoelectron spectroscopy and electrochemical methods.
Radiation Worker/
Non-RadiationWorker
Radiation Worker
Field
(for reference)
Applied Physics
Material
Geo and Environmental Sciences
Physics
No.J24
ThemeTheoretical study of many-body quantun systems
DepartmentSector of Nuclear Science Research Advanced Science Research Center
SectionResearch Group for Advanced Theoretical Physics
LocationTokai, Nuclear Science Research Institute
ContactPersonYutaka Utsuno
Tel +81-29-282-6901
E-mail utsuno.yutaka@jaea.go.jp
SummaryWe invite candidates who will conduct theoretical researches of many-body quantum physics in quark, hadron, or nuclear physics, and the related areas beyond energy scale. The candidates are encouraged to strengthen links to experimental studies and condensed-matter physics performed in this center, and to carry out interdisciplinary researches.
Radiation Worker/
Non-RadiationWorker
Non-Radiation Worker
Field
(for reference)
Physics
No.J25
ThemeStudy of raidation-induced reaction at solid/liquid interface
DepartmentNuclear Science and Engineering Center
SectionResearch Group for Radiochemistry,Nuclear Chemistry Division
LocationTokai, Nuclear Science Research Institute
ContactPersonYuta Kumagai,
Tel +81-29-282-5268
E-mail kumagai.yuta@jaea.go.jp
SummaryOur research group has been studying radiation-induced reactions in solutions and solid/liquid heterogeneous systems for evaluating stability and performance of materials relating nuclear engineering. This research theme is intended to investigate reactions at solid/liquid interface under the action of ionizing radiation and to understand the mechanism of the interface phenomena. By exploring wide range of solid materials such as nuclear fuel materials, alloys, ceramics, and minerals, we aim to develop a solid foundation for analyzing and predicting chemistry at the interfaces.
Radiation Worker/
Non-RadiationWorker
Radiation Worker
Field
(for reference)
Chemistry
Radiation
Material
Applied Chemistry
Geo and Environmental Sciences
Measurements and Instruments
Chemical Engineering
No.J26
ThemeDevelopment of automation technology for radionuclide analysis
DepartmentNuclear Science and Engineering Center
SectionResearch Group for Analytical Chemistry,Nuclear Chemistry Division
LocationTokai, Nuclear Science Research Institute
ContactPersonYoshihiro KITATSUJI
+81-29-282-5517
E-mail: kitatsuji.yoshihiro@jaea.go.jp
SummaryWe are developing highly efficient and simplified techniques for radionuclide analysis with the aim of reducing radiation exposure and secondary radioactive waste generation through rapid and small amounts processing.This research theme aims to develop separation techniques for efficient enrichment of analyte and selective removal of interference. Micro-analysis for minimized samples and seamless-analysis integrating sample sort, chemical preparation, separation, and measurement will be also developed.
Radiation Worker/
Non-RadiationWorker
Radiation Worker
Field
(for reference)
Chemistry
Measurements and Instruments
Geo and Environmental Sciences
Radiation
Material
Applied Chemistry
Chemical Engineering
No.J27
ThemeStudy on carbon cycling in subsurface layers of forest soils, using radioactive and stable carbon isotope analyses
DepartmentNuclear Science and Engineering Center
SectionResearch Group for Environmental Science, Environment and Radiation Sciences Division
LocationTokai, Nuclear Science Research Institute
ContactPersonJun Koarashi
Tel +81-29-282-5903
E-mail koarashi.jun@jaea.go.jp
SummaryThere is growing concern about the recent progress of global warming, and the potential of storing carbon in forest soils has received increasing attention to mitigate global warming. Subsurface layers of forest soils contain more than half of the global soil carbon; however, the roles of subsurface layers of forest soils in the global carbon cycling remain poorly explored. In this study, we will conduct field (with different ecosystem properties) and laboratory (under controlled environmental conditions) experiments to reveal carbon dynamics in subsurface soils and its responses to climate changes, using multiple analytical approaches, such as radioactive (14C) and stable carbon isotope analyses, chemical characterization of organic materials, and DNA-based microbial community structure analysis.
Radiation Worker/
Non-RadiationWorker
Non-Radiation Worker
Field
(for reference)
Geo and Environmental Sciences
Biology
Chemistry
Measurements and Instruments
No.J28
ThemeImprovement of the Particle and Heavy Ion Transport code System PHITS
DepartmentNuclear Science and Engineering Center
SectionResearch Group for Radiation Transport Analysis, Environment and Radiation Sciences Division
LocationTokai, Nuclear Science Research Institute
ContactPersonTatsuhiko Sato
Tel +81-29-282-5803
E-mail sato.tatsuhiko@jaea.go.jp
SummaryParticle and Heavy Ion Transport code System (PHITS) is a multi-purpose Monte Carlo particle transport simulation code developed in JAEA.This study is dedicated to improving PHITS by implementing new physical, chemical, or biological phenomena that cannot be handled by the current PHITS, and extending its application fields to various research areas. The verification experiments will be also performed for the improved PHITS if necessary. We look forward to innovative proposals from young researchers.
Radiation Worker/
Non-RadiationWorker
Radiation Worker
Field
(for reference)
Radiation
Material
Physics
Chemistry
Biology
No.J29
ThemeNeutron diffraction study of hydrogen embrittlement delayed fracture mechanism under three axial stress state
DepartmentMaterials Sciences Research Center, Nuclear Science Research Institute, Sector of Nuclear Science Reseach,
SectionMechanical Stress and Imageing Research Group
LocationTokai
ContactPersonTakahisa Shobu
Tel +81-29-282-5478
E-mail:
shobu.takahisa@jaea.go.jp
SummaryToward realizing carbon neutrality by 2050, reasonable utilization of hydrogen energy is one of the most important ways where tank storage and transportation facilities of hydrogen gas are indispensable. However, hydrogen accumulation at vacancies, dislocations, and grain boundaries in steels degrades the strength and ductility of steels, and it is urgently necessary to find affordable routes for resolving such hydrogen embrittlement problem. Here, we will use neutron diffraction to identify the origin of hydrogen embrittlement delayed fracture, quantify the principal factors of hydrogen embrittlement by three axial stress state, and clarify the hydrogen embrittlement delayed fracture mechanism under multiple-axial stress loading. We welcome a highly capable young researcher having deep interest in this research topic by combining neutron diffraction measurements using RESA-1 at JRR-3 and TAKUMI at J-PARC MLF, together with FEM (finite element method) numerical simulations.
Radiation Worker/
Non-RadiationWorker
Radiation Worker
Field
(for reference)
Material
Mechanics
Applied Physics
Measurements and Instruments
No.J30
ThemeNanostructure study using small-angle neutron scattering and improvement of measurement technique
DepartmentMaterials Sciences Research Center, Nuclear Science Research Institute, Sector of Nuclear Science Reseach,
SectionHierarchical Structure Research Group
LocationTokai
ContactPersonTakayuki Kumada
Tel +81-29-284-3834
E-mail: kumada.takayuki@jaea.go.jp
SummaryTaking an advantage of small-angle neutron scattering diffractometer
(SANS-J) at JRR-3 and other neutron spectrometers in J-PARC MLF, we carry out nanostructure study. We also improve a measurement technique.
We want to work with a reseacher who shares the interest with us.
Radiation Worker/
Non-RadiationWorker
Radiation Worker
Field
(for reference)
Material
Chemistry
Physics
Measurements and Instruments
No.J31
ThemeNeutron scattering study on novel physical phenomena in strongly correlated electron systems
DepartmentMaterials Sciences Research Center, Nuclear Science Research Institute, Sector of Nuclear Science Reseach,
SectionMultiple-Degree-of-Freedom Correlation Research Group
LocationTokai
ContactPersonToyotaka Osakabe
Tel +81-29-282-6094
E-mail:
osakabe.toyotaka@jaea.go.jp
SummaryWe are conducting advanced materials research by neutron scattering. In this theme, you will conduct research on novel magnetic phenomena in the strongly correlated electron systems by making full use of advanced neutron scattering instruments installed in JRR-3 and J-PARC MLF. Further, you will take part in the development of neutron scattering technique and data analysis for three triple-axis spectrometers and the high-resolution powder diffractometer, which are owned by our group. We welcome young researchers who are willing to work on such research theme with high motivation.
Radiation Worker/
Non-RadiationWorker
Radiation Worker
Field
(for reference)
Physics
Material
Radiation
Measurements and Instruments
No.J32
ThemeFundamental research for separation of elements with chemical similarity
DepartmentMaterials Sciences Research Center, Nuclear Science Research Institute, Sector of Nuclear Science Reseach,
SectionActinide Chemistry Group
LocationHarima, Hyogo or Tokai
ContactPersonKeiichi Yokoyama
Tel +81-80-4869-1266
E-mail
yokoyama.keiichi@jaea.go.jp
SummaryWe are recruting a research scientist who is engaged in developing techniques and understanding phenomena regarding separation between elements with chemical similarity, such as neighboring elements in the lanthanide and actinide series and platinum group metals. Some of studies are performed through X-ray analyses of the complex structure, laser-induced photochemical processes, and computational chemistry as well as ordinary chemical processes. SPring-8 and SACLA can be used in these studies. Experience in related fields is prefferd but not necessary. Young scientist who has energy to challenge new fields and capability to publish their findings timely is welcome.
Radiation Worker/
Non-RadiationWorker
Radiation Worker
Field
(for reference)
Applied Chemistry
Chemical Engineering
Measurements and Instruments
Chemistry
Radiation
Computer and Information
No.J33
ThemeDevelopment of a valence state analysis for light to heavy elements in environmental samples using a high-energy x-ray microbeam in the same field of view and its application to correlation analysis of different elements
DepartmentMaterials Sciences Research Center, Nuclear Science Research Institute, Sector of Nuclear Science Reseach,
SectionAnalytivcal Sciences Development Research Group
LocationHarima, Hyogo
ContactPersonHajime Tanida
Tel +81-80-4903-5984
E-mail tanida.hajime@jaea.go.jp
SummaryA wide variety of elements contained in environmental samples such as radioactive particulates and nuclear fuel debris originating and futurely removed from the Fukushima Daiichi Nuclear Power Plant, and vitrified materials have been measured using high-energy X-ray microbeam focusing mirrors installed at the beamline BL22XU of Japan Atomic Energy Agency at SPring-8 to perform elemental mapping and valence mapping measurements in the same field of view over a wide energy range from the Ca K edge to the Ce K edge without changing the focusing beam setting. If necessary, we will also perform analysis using the STXM (scanning soft X-ray microscope) installed in the beamline BL23SU. Any enthusiastic young researcher is welcome to join this project, regardless of previous experience or expertise. We encourage an enthusiastic young researcher to submit an application regardless of the previous speciality.
Radiation Worker/
Non-RadiationWorker
Radiation Worker
Field
(for reference)
Geo and Environmental Sciences
Measurements and Instruments
Chemistry
Radiation
Physics
No.J34
ThemeStudy on dynamical properties of materials by neutron scattering technique
DepartmentSector of Nuclear Science Research J-PARC Center
SectionMaterials and Life Science Division Neutron Science Section
LocationTokai, Nuclear Science Research Institute
ContactPersonMaiko Kofu
Tel +81-29-284-3089
E-mail maiko.kofu@j-parc.jp
SummaryNeutron scattering techniques are powerful tools for investigation of dynamical properties of atoms, molecules and spins in materials. In this theme, we will mainly use the inelastic and quasi-elastic neutron scattering instruments installed at the Materials and Life Science Experimental Facility (MLF), J-PARC to study hydrogen compounds and magnetic materials promoted by JAEA. In addition, applicant will provide support for related research to be conducted at Cold-Neutron Disk-Chopper Spectrometer (AMATERAS) at MLF.
Radiation Worker/
Non-RadiationWorker
Radiation Worker
Field
(for reference)
Physics
Chemistry
Material
Applied Physics
No.J35
ThemeResearch and development of nuclear data measurement and beam diagnostic technology in accelerator-driven transmutation system (ADS)
DepartmentSector of Nuclear Science Research J-PARC Center
SectionNuclear Transmutation Division Facility and Application Development Section
LocationTokai, Nuclear Science Research Institute
ContactPersonShin-ichiro Meigo
Tel +81-29-284-3207
E-mail meigo.shinichiro@jaea.go.jp
SummaryWe are planning to build an irradiation facility using a high-intensity proton beam to obtain material irradiation data such as beam windows for the Accelerator Driven System (ADS). In order to improve the accuracy of the codes and nuclear data used for the nuclear design of the irradiation facility and the actual ADS, nuclear data measurements such as nuclide production cross sections and energy spectra of spallation neutrons have been carried out using several GeV protons. In addition, we are developing high-intensity proton beam diagnostic techniques for the beam introduced to the ADS target. In this theme, we will measure nuclear data related to the design of the ADS, develop beam diagnostic techniques, and promote the nuclear design of the irradiation facility.
Radiation Worker/
Non-RadiationWorker
Radiation Worker
Field
(for reference)
Physics
Radiation
Measurements and Instruments
Applied Physics
No.J36
ThemeDevelopment of Scintillator-based or Gas-based Neutron Detectors at Materials and Life Science Facility of J-PARC
DepartmentSector of Nuclear Science Research J-PARC Center
SectionMaterials and Life Science Division Neutron Instrumentation Section
LocationTokai, Nuclear Science Research Institute
ContactPersonTatsuya Nakamura
Tel: +81-29-282-5344
E-mail: nakamura.tatsuya@jaea.go.jp
SummaryThe successful candidatse will be participating in the development of scintillator or gas based neutron detectors for the world leading pulsed neutron scattering instruments in the J-PARC MLF. The candidates will be involved in the project to improve detector performances such as detector efficiency, spatial resolution, count rate capability. You will have a varied and wide ranging duties througout the detector system that will include development of new detection mateials, electronics cirucuit, signal processing and detection method.
Radiation Worker/
Non-RadiationWorker
Radiation Worker
Field
(for reference)
Radiation
Measurements and Instruments
Electricity and Electronics
Material
No.J37
ThemeResearch on improvement of J-PARC accelerators
DepartmentSector of Nuclear Science Research J-PARC Center
SectionAccelerator Division
LocationTokai, Nuclear Science Research Institute
ContactPerson Michikazu Kinsho
Tel +81-29-284-3172
E-mail: kinsho.michikazu@jaea.go.jp
SummaryThe J-PARC proton accelerator is being upgraded to achieve stable operation at a maximum output power of 1 MW. In order to increase the beam power and to operate the accelerator stably, it is essential to reduce the beam loss and to extend the lifetime of the components. In this theme, the development of beam diagnostics and countermeasures for beam losses are mainly carried out to reduce beam losses in the linac and the 3-GeV synchrotrons (RCS). To improve the stability of the accelerator, we will also study the upgrading of the beam generator, RF acceleration cavity, RF source and vacuum system, the development of the charge conversion system, the improvement of the power supply and electromagnets, and other accelerator components and beam control.
Radiation Worker/
Non-RadiationWorker
Radiation Worker
Field
(for reference)
Physics
Mechanics
Measurements and Instruments
Applied Physics
Computer and Information
Robotics
No.J38
ThemeDevelopment and application of a He-3 spin filter for neutron scattering experiments
DepartmentSector of Nuclear Science Research J-PARC Center
SectionMaterials and Life Science Division Technology Development Section
LocationTokai, Nuclear Science Research Institute
ContactPersonTakayuki Oku
Tel +81-29-284-3196
E-mail takayuki.oku@j-parc.jp
SummaryWe will improve He-3 spin filters based on a spin-exchanged optical pumping method and apply them to pulsed neutron beam experiments at J-PARC MLF. Moreover, we will also develop sample environment for the He-3 spin filters to diversify the applicable experiments
Radiation Worker/
Non-RadiationWorker
Radiation Worker
Field
(for reference)
Material
Physics
Chemistry
Applied Physics
No.J39
ThemeApplication of advanced computational science and technology on neutron scattering measurements and analyses at a pulsed neutron source facility.
DepartmentSector of Nuclear Science Research J-PARC Center
SectionMaterials and Life Science Division Technology Development Section
LocationTokai, Nuclear Science Research Institute
ContactPersonKazuyoshi Tatsumi
Tel +81-29-284-3169
E-mail tatsumi.kazuyoshi@jaea.go.jp"
SummaryIn order to further develop materials solutions in the pulsed neutron source facility promoted by JAEA, the researcher will conduct research and developments on one of the following three themes: 1) On-line sampling of neutron diffraction based on a Gaussian process, 2) Accurate intensity distribution representation of neutron scattering data by using a kernel density estimation technique, and 3) Calculation of neutron inelastic scattering cross-sections of hydrogen in metallic materials through the Schrodinger equation solution for the hydrogen nuclear.
Radiation Worker/
Non-RadiationWorker
Non-Radiation Worker
Field
(for reference)
Mathematics
Computer and Information
Measurements and Instruments
Material
No.J40
ThemeR&D on the multilayer optics for polarized neutrons
DepartmentSector of Nuclear Science Research J-PARC Center
SectionMaterials and Life Science Division Neutron Instrumentation Section
LocationTokai, Nuclear Science Research Institute
ContactPersonRyuji Maruyama
Tel: +81-29-284-3811
E-mail: ryuji.maruyama@j-parc.jp
SummaryThe core component of this role is to join our R&D in the field of the multilayer optics for polarized neutrons which enhances the capability of the polarized neutron scattering technique and meets a veriety of research demands in J-PARC MLF. This will involve elements such as a research of the magnetism of layered systems which are not seen in the bulk and development of the software and technique to analyze the in-plane/out-of-plane magnetic structure of the multilayers using the polarized neutron scattering with considerable flexibility depending on your particular skills and interests. As part of this role you will develop your own scientific research program in the field related to the ones mentioned above in collaboration with the staff in MLF.
Radiation Worker/
Non-RadiationWorker
Radiation Worker
Field
(for reference)
Physics
Applied Physics
No.J41
ThemeStudy on chemical form of radioactive nuclide on metallic waste and transport behavior during processing
DepartmentSector of Fukushima Research and Development Collaborative Laboratories for Advanced Decommissioning Science
SectionWaste Management Division Waste Processing and Disposal Technology Development Group
LocationTokai, Ibaraki
ContactPersonRyoichiro Kuroki
Tel +81-29-282-1133(ex.82-60500)
E-mail kuroki.ryoichiro@jaea.go.jp
SummaryA lot of metallic wastes will be generated in decommissioning of Fukushima Daiichi Nuclear Power Station at Tokyo Electric Power Company Holdings (TEPCO). Metal is the material which can be reused by decontamination and it is nesessary to establish methods for estimating amount of retained radionuclides with decontamination. This is a common issue for decommissioning of existing nuclear facilities. Radionuclide behavior during decontamination such as high tempature melting on experiment and analysis should be investigated.
Radiation Worker/
Non-RadiationWorker
Non-Radiation Worker
Field
(for reference)
Material
Radiation
Applied Physics
No.J42
ThemeResearch and developlment of risk assesment methodology for sodium-cooled fast reactors
DepartmentReactor Systems Design Department Sector of Fast Reactor and Advanced Reactor Research and Development
SectionFast Reactors Plant Design Group
LocationOarai
ContactPersonHiroyuki Nishino
SummaryTo develop a global standard for risk-informed safety design approach, our group has been studying on the development of Levels 1 to 3 probabilistic risk assessment (PRA) methodologies for sodium-cooled fast reactors (SFR), including external events. As part of the study, JAEA have joined the U.S. versatile test reactor (VTR) project to perform joint reliability assessment on components and peer review in the VTR PRA.This program will contribute to improving Japan’s PRA for SFRs through this international joint research on safety assessment including risk assessment and numerical analysis. The hired researcher will examine applicability of the PRA methodologies developed for light water reactors to SFRs and then develop the Level 1-3 PRA methodologies for SFRs. The scope of this program may be reviewed accorinding to applicant requests.
Radiation Worker/
Non-RadiationWorker
Non-Radiation Worker
Field
(for reference)
Physics
Mathematics
Radiology
Mechanics
No.J43
ThemeDesign study on small modular fast reactors with advanced power generation system for coexisting with renewable energy
DepartmentReactor Systems Design Department Sector of Fast Reactor and Advanced Reactor Research and Development
SectionFast Reactors Plant Design Group
LocationOarai
ContactPersonHidemasa Yamano
SummaryTo achieve net-zero emissions of greenhouse gases by 2050, the hired person will be involved in design and development of small modular reactors (SMRs) of sodium-cooled fast reactors for electricity generation that can coexist with renewable energy emerging as a future main power source. The SMRs will use advanced heat storage technology that enhances its performance and efficiency. In this program, the hired researcher will study heat storage plants in use and compare their plant design concepts and costs. The researcher will also create preliminary design of a new heat storage system installed with a heat storage tank that uses advanced techniques such as thermochemical heat storage systems, and will study SMR design capable of installing the advanced system. In addition, the person will research the prices of electricity and power production sources of the future and understand market needs. The scope of this program may be reviewed accorinding to applicant requests.
Radiation Worker/
Non-RadiationWorker
Non-Radiation Worker
Field
(for reference)
Physics
Mathematics
Environmentology
Mechanics
No.J44
ThemePractical research for producing desirable relations between a nuclear energy R&D institution and its local community by the social scientific approach, keeping O-arai Town in mind
DepartmentStrategy and Planning Office,Sector of Fast Reactor and Advanced Reactor Research and Development(SEFARD)
SectionStrategy and Social Environment Group
LocationO-arai Research and Development Center
ContactPersonTakao Kato
Tel +81-29-267-1919 ex.7130
E-mail kato.takao@jaea.go.jp
Summary Our group is now tackling research for promoting social acceptance to advanced nuclear reactors technology through social science. For example, we are preparing a discussion forum for tritium-water derived from the Fukushima nuclear power plants, utilizing the deliberative polling method, as a research for deepening relations between nuclear activities and local communities. Tokai-village local government also started recently ‘Jibun-gotoka (making issues to one’s own issues) meeting’.
Based on previous activities like the above and also keeping O-arai town in mind, candidate will do practical research to propose platforms and/or mechanisms of sharing issues which R&D institution and related local community have, and discussing those issues actively and constructively together.
Radiation Worker/
Non-RadiationWorker
Non-Radiation Worker
Field
(for reference)
Other
No.J45
ThemeResearch on how to secure, foster and keep technologies which are necessary for the implementation of advanced nuclear reactor in the society, from the viewpoint of national economic security
DepartmentStrategy and Planning Office,Sector of Fast Reactor and Advanced Reactor Research and Development(SEFARD)
SectionStrategy and Social Environment Group
LocationO-arai Research and Development Center
ContactPersonTakao Kato
Tel +81-29-267-1919 ex.7130
E-mail kato.takao@jaea.go.jp
Summary Based on the recent situation over the international struggle for supremacy of technology, discussions are emerged for getting and keeping advantage of strategic technology which supports economic growth and national security of Japan. Nuclear technology is one of the important technologies from the above point of view. On the other hand, nuclear technology infrastructure and supply chain in Japan is gradually weakened because of no large investment such as new nuclear power plant construction, which comes from severe public opinion to nuclear power generation. R&D activities for utilization of advanced nuclear reactor in the society is under the same situation.
Based on such points of view, candidate will analyze on the present status of technological advantage of the nuclear industry in Japan, research on the measures to secure, foster and keep technology which are necessary to implement advanced nuclear reactor in the society, from the viewpoints of international relation, competitive economy, free market mechanism, finance, legal system, and finally make use of the results to consider appropriate system for implementation of advanced nuclear technology in Japan.
Radiation Worker/
Non-RadiationWorker
Non-Radiation Worker
Field
(for reference)
Other
No.J46
ThemeResearch and development on identification and quantification technologies of dominant plant parameters affecting on the events regarding transient dynamics of the plant under fluid-Structure thermal interaction
DepartmentSector of Fast Reactor and Advanced Reactor Research and DevelopmentFast Reactor Cycle System Research and Development Center
SectionReactor Core and Plant System Evaluation Group
LocationOarai Research and Development Institute
ContactPersonMasaaki Tanaka
Tel +81-29-267-1919(Ext.6745)
E-mail tanaka.masaaki@jaea.go.jp
SummaryIn the numerical analysis of plant transient dynamics phenomena strongly related to thermal-hydraulic and structural problems in a sodium cooled first reactor (SFR), the analytical result depends on various parameters in the plant, such as thermal conditions and pump characteristics. In this study, developments of the knowledge data base of the plant parameters from the experiences in the past development of SFR, the methodology to search and specify the parameters which affect significantly to the analytical result, and the quantification method of the variation width of each parameter are included. These items to be developed enables to define the conditions of the plant design and the analysis efficiently so as to make the design optimization process effective.
Radiation Worker/
Non-RadiationWorker
Non-Radiation Worker
Field
(for reference)
Mechanics
Computer and Information
Measurements and Instruments
No.J47
ThemeV&V/UQ for fast reactor core characteristics analysis method by using post-irradiation experimental analysis
DepartmentSector of Fast Reactor and Advanced Reactor Research and DevelopmentFast Reactor Cycle System Research and Development Center
SectionReactor Core and Plant Evaluation Group
LocationOarai Research and Development Institute
ContactPersonShigeo OHKI
Tel +81-29-267-1919 (Ext.6445)
E-mail ohki.shigeo@jaea.go.jp
SummaryFor the purpose of verification and validation (V&V) of the fast reactor core characteristics analysis method, expeimental anaysis of core fuel compostions after irradiation will be conducted. The doctoral research fellow analyzes and evaluates the post-irradiation experimental data acquired in the experimental fast reactor "JOYO" of Japan and the experimental breeder reactor "EBR-II" of US, and develops a high-fidelity and high-quality experimental database for fast reactors to validate and improve the prediction accuracy of the fast reactor core characteristics analysis method, which consists of neutronics computer codes and nulear data libraires. In the analysis and evaluation, he/she should maximize the reliability of the experimental analysis by using the techniques of uncertainty quantification (UQ) for all possible factors of uncertainty and bias, such as uncertainty/bias due to experiments, bias due to anlalysis modeling, and uncertainty due to nulcear data.
Radiation Worker/
Non-RadiationWorker
Non-Radiation Worker
Field
(for reference)
Physics
Computer and Information
No.J48
ThemeStudy on inelastic behavior to contribute advanced design evaluation method for components used in elevated temperature condition
DepartmentSector of Fast Reactor and Advanced Reactor Research and DevelopmentFast Reactor Cycle System Research and Development Center
SectionStructural Mechanics and Seismic Evaluation Group
LocationOarai Research and Development Institute
ContactPersonMasashi MIYAZAKI
Tel +81-29-267-1919 (Ext.6825)
E-mail miyazaki.masashi@jaea.go.jp
SummaryIn elevated temperature design for the advanced reactors including Sodium-cooled Fast Reactor, the prediction of inelastic stress and strain behavior for components used under elevated temperature condition is essential to prevent the failure. In this theme, inelastic behaviors such as stress and strain re-distribution derived from creep behavior are studied through finite element analyses and structural examination, and theoretical model and practical design evaluation method will be developed to contribute advanced design evaluation technology.
Radiation Worker/
Non-RadiationWorker
Non-Radiation Worker
Field
(for reference)
Mechanics
Material
No.J49
ThemeStudy on seismic tecnology of mechancal components and pipings in advanced reactors
DepartmentSector of Fast Reactor and Advanced Reactor Research and DevelopmentFast Reactor Cycle System Research and Development Center
SectionStructural Mechanics and Seismic Evaluation Group
LocationOarai Research and Development Institute
ContactPersonMasashi MIYAZAKI
Tel +81-29-267-1919 (Ext.6825)
E-mail miyazaki.masashi@jaea.go.jp
SummaryAdvanced reactors are plan to be operated under elevated temperature condition compared with that of existing pressurized water reactors. To realize adequate seismic design of advanced reactors, development of seismic evaluation methods is necessary by considering elevated temperature operation condition. In this theme, ultimate strength of mechanical components and piping against seismic loading are clarified through finite element analyses and various tests, and appropriate seismic design methods and optimum design method using fragility evaluation will be developed to contribute the improvement and/or publishment of the design codes for advanced reactors.
Radiation Worker/
Non-RadiationWorker
Non-Radiation Worker
Field
(for reference)
Mechanics
Material
Computer and Information
Other
No.J50
ThemeDevelopment of computer codes to simulate irradiation behavior of fast reactor fuel elements and fuel assemblies
DepartmentFast Reactor Cycle System Research and Development Center/Sector of Fast Reactor and Advanced Reactor Research and Development
SectionFuel Technology Development Section/Fuels and Materials Department
LocationOarai Research and Development Institute
ContactPersonTomoyuki Uwaba
Tel +81-29-267-1919-Ext.6446
E-mail uwaba.tomoyuki@jaea.go.jp
SummaryFor the purpose of strengthening the research and development indispensable for the practical application of fast reactor cycle technology, a postdoctoral researcher shall develop computer codes to simulate irradiation behaviors of fuel elements and fuel assemblies in fast reactors and to realize highly reliable fuel design and innovative new fuels. In this research and development, the researcher shall analyze the post-irradiation examinations of fuel elements and subassemblies irradiated in fast reactors such as "Joyo" by using the "CEDAR" code that simulates the behavior of fuel elements, the "BAMBOO" code that simulates a fuel element bundle deformation under bundle-duct interactions, and the coupled system of the codes. Based on the analyses, the researcher shall develop models to predict fuel irradiation behaviors and introduce the models into the codes, improving their reliability and analytical functions.
Radiation Worker/
Non-RadiationWorker
Non-Radiation Worker
Field
(for reference)
Mechanics
Material
Computer and Information
Applied Physics
Mathematics
No.J51
ThemeEnhancement of electromagnetic simulations by nonlinear modelling of ferromagnetic materials using parallel computing based on multicore CPU and GPU system
DepartmentSector of Fast Reactor and Advanced Reactor Research and Development, Tsuruga Comprehensive Research and Development Center, Fast Reactor Plant Technology Development Department
SectionSodium Technology Development Group
LocationLocation close to Prototype Fast Breeder Reactor Monju
ContactPersonOvidiu Mihalache
Tel: +81-770 39 1031 (ext: 6865)
E-mail:mihalache.ovidiu@jaea.go.jp
SummaryElectromagnetic simulations in ferromagnetic metallic materials using coils with ferrite core is enhanced by implementing and optimizing new nonlinear algorithms in modeling using finite element method (FEM). Due to long simulation times, optimizations and speed-up of the nonlinear algorithms by parallel computing is required in nonlinear time transient or harmonic electromagnetic approximation.
The work is performed by starting from a code developed in the JAEA laboratory using parallel computing OpenMP in Fortran and enhanced it with additional parallel CPU optimizations and GPU computation acceleration using NVIDIA CUDA computing and new algorithms to implement nonlinear approximations for modeling of ferrites.
Radiation Worker/
Non-RadiationWorker
Non-Radiation Worker
Field
(for reference)
Physics
Mathematics
Measurements and Instruments
Computer and Information
No.J52
ThemeR&D on processing of radioactive organic liquids
DepartmentNuclear Backend Technology CenterNuclear Fuel Cycle Engineering LaboratoriesSector of Nuclear Fuel, Decommissioning and Waste Management Technology Development
SectionWaste Processing Technology Section Decommissioning Technology Department
LocationTokai-mura, Ibaraki (Nuclear Fuel Cycle Engineering Laboratories)
ContactPersonJunya Sato
Tel +81-29-282-1133 (ext. 65714)
E-mail sato.junya@jaea.go.jp
SummaryThis R&D attempts to treat radioactive organic liquids containing uranium after evaluating characterization of them, and will contribute to the promotion of decommissioning of domestic nuclear facilities. Waste organic solvent and machine oil used in nuclear facilities have been stored, and it can be predicted that many research facilities will generate them according to decommissioning. It is considered that these organic solvents and the like have a negative impact on the landfill environment and are difficult to be solidified by using cementitious materials. Therefore, it is positioned as one of the wastes that is difficult to treat, and it is required to establish an appropriate processing method as the steam reforming treatment or the alkali activated materials (AAM) solidification.
Radiation Worker/
Non-RadiationWorker
Radiation Worker
Field
(for reference)
Geo and Environmental Sciences
Radiation
Material
Applied Chemistry
Chemical Engineering
Computer and Information
No.J53
ThemeResearch and development of microbial effects on radionuclide migration in subsurface environments
DepartmentNuclear Backend Technology CenterNuclear Fuel Cycle Engineering LaboratoriesSector of Nuclear Fuel, Decommissioning and Waste Management Technology Development
SectionRadionuclide Migration Research Group Department of Geological Disposal Research
LocationTokai-mura, Ibaraki (Nuclear Fuel Cycle Engineering Laboratories)
ContactPersonYuki Amano
Tel +81-29-282-1133 (67509)
E-mail amano.yuki@jaea.go.jp
Summary Understanding geochemical conditions and mass transport in subsurface environments.
Exploration and understanding of microbial metabolic function in subsurface environments.
Understanding geochemical processes of water-rock-microbes interaction in subsurface environments.
Understanding microbial effects on geochemical conditons and mass transport in subsurface environments.
Radiation Worker/
Non-RadiationWorker
Non-Radiation Worker
Field
(for reference)
Applied Chemistry
Geo and Environmental Sciences
Biology
No.J54
ThemeR&D on processing of aluminum wastes for reducing hydrogen generation
DepartmentNuclear Backend Technology CenterNuclear Fuel Cycle Engineering LaboratoriesSector of Nuclear Fuel, Decommissioning and Waste Management Technology Development
SectionWaste Processing Technology Section Decommissioning Technology Department
LocationTokai-mura, Ibaraki (Nuclear Fuel Cycle Engineering Laboratories)
ContactPersonJunya Sato
Tel +81-29-282-1133 (ext. 65714)
E-mail sato.junya@jaea.go.jp
SummaryThis R&D attempts to reduce hydrogen gas generated by conditioning of radioactive aluminum wastes for safety store and disposal. This study investigates a mutual interaction with the aluminum and the solidification materials, and a deteriorate process of the solidified product. Generally, when radioactive wastes containing an aluminum are solidified using cement, hydrogen gas generated during the dissolution reaction deforms the waste form.
Radiation Worker/
Non-RadiationWorker
Non-Radiation Worker
Field
(for reference)
Material
Geo and Environmental Sciences
Architectural and Civil Engineering
Chemical Engineering
Applied Chemistry
Computer and Information
No.J55
ThemeR&D on establishment of mid-and-long-term behavior estimation method for a cementitious solidified product
DepartmentNuclear Backend Technology CenterNuclear Fuel Cycle Engineering LaboratoriesSector of Nuclear Fuel, Decommissioning and Waste Management Technology Development
SectionWaste Processing Technology Section Decommissioning Technology Department
LocationTokai-mura, Ibaraki (Nuclear Fuel Cycle Engineering Laboratories)
ContactPersonJunya Sato
Tel +81-29-282-1133 (ext. 65714)
E-mail sato.junya@jaea.go.jp
SummaryThis R&D attempts to verify and establish a mid-and-long-term behavior estimation method for a hundred or several thousand years and to construct its deterioration model, and will contribute to selection of a method for managent of radioactive wastes arising from decommissioning operations. A wide variety of radioactive wastes have arisen from decommissioning of the Fukushima Daiichi Nuclear Power Station. These wastes need to be managed (storage, processing, disposal) for a certain period. It is not rational to obtain each data on the soundness and deterioration of a waste solidified product for all wastes, since characteristics of a waste solidified product changes according to properties of the wastes.
Radiation Worker/
Non-RadiationWorker
Non-Radiation Worker
Field
(for reference)
Material
Geo and Environmental Sciences
Architectural and Civil Engineering
Chemical Engineering
Applied Physics
Computer and Information