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Publications by Yasuto INOHARA
Application of Advanced Neutron Absorbing Materials to Structural Material of Inner Basket of Storage Casks for High Burnup and MOX Spent Fuels.
Journal of the Atomic Energy Society of Japan / Atomic Energy Society of Japan
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Development of a New Neutron Absorber Material for Dry Casks and Spent Fuel Pool Racks
Keikinzoku/Journal of Japan Institute of Light Metals
Mechanics of Materials
Alloys
Materials Chemistry
Metals
Mechanical Engineering
Concept of Radiation Dose Rate Sensitivity Applicable to Spent Fuel Shipping Casks. Definition of Concept and Application to Evaluation of Array Effect Obtained Upon Arranging Spent Fuels in Different Burnup States Within Same Shipping Cask.
Journal of the Atomic Energy Society of Japan / Atomic Energy Society of Japan
Radiation Imaging of Dry Storage Casks for Spent Nuclear Fuel
Application of Neutron-Absorbing Structural-Amorphous Metal (SAM) Coatings for Spent Nuclear Fuel (SNF) Container to Enhance Criticality Safety Controls
Materials Research Society Symposium - Proceedings
Mechanics of Materials
Materials Science
Condensed Matter Physics
Mechanical Engineering
Neutron Intensity Measurements of BWR Spent Fuels
Journal of Nuclear Science and Technology
High Energy Physics
Nuclear
Engineering
Nuclear Energy
Feasibility Assessment of Burnup Credit in the Criticality Analysis of Shipping Casks With Boiling Water Reactor Spent Fuel
Nuclear Technology
High Energy Physics
Nuclear
Engineering
Nuclear Energy
Condensed Matter Physics
FRAPCON-3: Modifications to Fuel Rod Material Properties and Performance Models for High-Burnup Application
Analysis of Measured Isotopic Compositions of High-Burnup PWR MOX and UO2fuels in the MALIBU Program
Journal of Nuclear Science and Technology
High Energy Physics
Nuclear
Engineering
Nuclear Energy
Research and Development on High Burnup HTGR Fuels in JAEA
Mechanical Engineering Journal