スポンサーリンク
Nuclear Engineering Research Laboratory, Faculty of Engineering, University of Tokyo | 論文
- Studies on hydrogen absorption-desorption proterties of U-Th-Zr alloys for developing new reactor fuel materials
- Development of New Reactor Fuel Materials Hydrogen Absorption Properties of U-Th, U-Th-Zr and U-Th-Ti-Zr Alloys
- New Ternary Hydride Formation in U-Ti-H System
- Numerical Modeling for Coextraction of Tc(VII)with U(VI)by n-Octyl(phenyl)-N, N-diisobutylcarbamonylmethylphosphine Oxide from Nitric Acid Solution
- Flowing Afterglow: Construction of an Apparatus, Measurement of Rate Constants, and Consideration of the Diffusive Behavior of Charges
- Negative Ion Formation by Thermal Electron Attachment to Nitrous Oxide at Atomospheric Pressure (イオン化特集-続-)
- Thermodynamic Study of a U-Fe Alloy by Means of Knudsen Effusion Mass Spectrometry (高温マススペクトロメトリ-)
- Stability and chemical form of iodine sorbed on silver-exchanged zeolite X.
- Neutron streaming through narrow and long annulus.
- Simulation of multigroup X-ray, alpha-particle and neutron transport in ion beam driven ICF target.
- Verification experiment of threshold detector 107Ag(n,n')107mAg on "YAYOI" standard neutron field.
- Fission spectrum averaged cross sections of some threshold reactions measured with fast reactor "YAYOI".
- Some New Applications of Neutron Slowing Down Time Spectrometry
- Some relations of neutronic noise with fluctuation of inlet coolant temperature and vibration of a control rod obtained by simultaneous measurements at KUR.
- Development of three-dimensional space dependent kinetics code IBIS and analysis of transient behavior of LMFBR cores.
- Stability of krypton fixed in zeolite-3A and -5A.
- Development of method based on perturbation theory for estimating and correcting errors in numerical solution of transport equation.
- Radiation field for fisson neutron enhanced boron neutron capture therapy employing fast neutron source reactor "YAYOI".
- Fast neutron spectra transmitted through iron and sodium slabs.
- Concept and nuclear performance of direct-enrichment fusion breeder blanket using UO2 powder.