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Publications by Mitsufumi ASAMI
Application of Dose Evaluation of the McNp Code for the Spent Fuel Transport Cask
Progress in Nuclear Science and Technology
Related publications
Below Grade Assessment of Spent Nuclear Fuel (SNF) Cask Transport Route
Evaluation of FSV-1 Cask for the Transport of LWR Irradiated Fuel Assemblies
Role of Gamma-Ray Dose Rate at the Surface of Spent Fuel Shipping Cask in Calculation of Dose Rate Distribution Throughout Ship by Using MANYCASK Code.
Journal of the Atomic Energy Society of Japan / Atomic Energy Society of Japan
Application of Muon Tomography to Fuel Cask Monitoring
Philosophical Transactions of the Royal Society A: Mathematical, Physical and Engineering Sciences
Mathematics
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Astronomy
Physics
Conceptual Design Report for a Transportable DUCRETE Spent Fuel Storage Cask System
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 Shielding Analysis for a Spent Fuel Storage Cask Under Normal Storage Conditions
COBRA-SFS Thermal Analysis of a Sealed Storage Cask for the Monitored Retrievable Storage of Spent Fuel
PIQUA-ELK RIVER REACTORS SPENT FUEL SHIPPING CASK. Thermal Test Report