Takafumi Okita

ORCID: 0000-0003-4687-8372
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About
Contact & Profiles
Research Areas
  • Nuclear Materials and Properties
  • Fusion materials and technologies
  • Nuclear reactor physics and engineering
  • Nuclear Physics and Applications
  • Laser-Plasma Interactions and Diagnostics
  • Nuclear Engineering Thermal-Hydraulics
  • Magnetic confinement fusion research
  • Metallurgical Processes and Thermodynamics
  • Thermodynamic and Structural Properties of Metals and Alloys
  • Radiation Detection and Scintillator Technologies
  • Particle accelerators and beam dynamics
  • Fluid Dynamics and Heat Transfer
  • Particle Dynamics in Fluid Flows
  • nanoparticles nucleation surface interactions
  • Laser-Matter Interactions and Applications
  • Spectroscopy Techniques in Biomedical and Chemical Research
  • Electrical Contact Performance and Analysis
  • Cyclone Separators and Fluid Dynamics
  • Magnetic Properties and Applications
  • Electrostatic Discharge in Electronics
  • Heat transfer and supercritical fluids
  • Ion-surface interactions and analysis
  • Nuclear and radioactivity studies
  • Magnetic properties of thin films
  • Gyrotron and Vacuum Electronics Research

Osaka University
2015-2025

Shimadzu (Japan)
2017

10.1016/s0168-9002(00)00056-5 article EN Nuclear Instruments and Methods in Physics Research Section A Accelerators Spectrometers Detectors and Associated Equipment 2000-05-01

10.1016/s0168-9002(01)01610-2 article EN Nuclear Instruments and Methods in Physics Research Section A Accelerators Spectrometers Detectors and Associated Equipment 2001-12-01

The international fusion materials irradiation facility (IFMIF) presents an intense neutron source to develop reactor materials. liquid metal Lithium (Li) jet with a free surface is planned as target irradiated by two deuteron beam generate neutrons and it thus important obtain information on the wave characteristic for safety efficiency of system in IFMIF. We have been studying characteristics experimentally using Li circulation at Osaka University numerically computational fluid dynamics...

10.1299/mej.2014tep0017 article EN cc-by-nc-nd Mechanical Engineering Journal 2014-01-01

The international fusion materials irradiation facility (IFMIF) presents an intense neutron source to develop reactor materials. liquid metal Lithium (Li) jet with a free surface is planned as target irradiated by two deuteron beam generate neutrons and it thus important obtain information on the wave characteristic for safety efficiency of system in IFMIF. We have been studying characteristics experimentally using Li circulation at Osaka University (Li loop) numerically computational fluid...

10.1115/icone21-16689 article EN Volume 5: Fuel Cycle, Radioactive Waste Management and Decommissioning; Reactor Physics and Transport Theory; Nuclear Education, Public Acceptance and Related Issues; Instrumentation and Controls; Fusion Engineering 2013-07-29

Liquid lithium (Li) jet is planned as a beam target in fusion neutron sources (FNSs), such IFMIF, A-FNS and IFMIF-DONES. For the safety efficiency of FNSs, high-speed Li need to be kept stable. investigation detailed flow pattern inside jet, numerical approaches using CFD simulation have been required evaluate it because its opacity. As one issues about inner structure, influence wall roughness on vortex structure surface variation concerned long-term operation actual FNSs. In our previous...

10.1080/00223131.2024.2352083 article EN Journal of Nuclear Science and Technology 2024-05-07

Abstract In this paper, formulas for evaluating expansion reactivity based on coefficients in sodium-cooled fast reactors are derived, and the approximation errors used derivation also evaluated. This research provides both Z-axis radial reactivity. These reactivities separated into effect of change geometric shape that cross-section. Since major present is separation effects due to changes cross-sectional area changes, error was evaluated using results neutron transport calculations...

10.1115/icone31-132277 article EN 2024-08-04

Abstract This paper presents a method for calculating reactivity changes caused by uniform thermal expansion in sodium-cooled fast reactors using coefficients. The due to both Z-axis and radial are separated into two effects: the shape change effect macroscopic cross-section effect. These effects expressed coefficients of materials reactor core. considers fuel, cladding, wrapper tube, while fuel pin, structural materials, core support structures. To confirm accuracy this approach,...

10.1115/1.4067483 article EN Journal of Nuclear Engineering and Radiation Science 2024-12-21
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