Amanote Research
Register
Sign In
Discover open access scientific publications
Search, annotate, share and cite publications
Publications by Tsuyoshi MISAWA
Experimental Study on Temperature Coefficient of Reactivity in Light-Water-Moderated and Heavy-Water-Reflected Cylindrical Core Loaded With Highly-Enriched-Uranium or Medium-Enriched-Uranium Fuel
Journal of Nuclear Science and Technology
High Energy Physics
Nuclear
Engineering
Nuclear Energy
Reaction Rate Analyses for an Accelerator-Driven System With 14 MeV Neutrons in the Kyoto University Critical Assembly
Journal of Nuclear Science and Technology
High Energy Physics
Nuclear
Engineering
Nuclear Energy
Related publications
Temperature Coefficient of Reactivity in Light-Water Moderated and Reflected Cores Loaded With Highly-Enriched-Uranium Fuel
Journal of Nuclear Science and Technology
High Energy Physics
Nuclear
Engineering
Nuclear Energy
Experimental Study on Reactivity Worth for Absorber Material in High Conversion Light Water Reactor Using FCA-HCLWR Core Fueled With Enriched Uranium.
Journal of Nuclear Science and Technology
High Energy Physics
Nuclear
Engineering
Nuclear Energy
Critical Masses of Spherical and Hemispherical Steel-Moderated, Oil- Reflected Enriched Uranium Assemblies.
A Study of Physics Parameters in Several Water-Moderated Lattices of Slightly Enriched and Natural Uranium.
Conversion and Blending Facility Highly Enriched Uranium to Low Enriched Uranium as Uranium Hexafluoride. Revision 1
Re-Evaluation of the Effective Delayed Neutron Fraction Measured by the Substitution Technique for a Light Water Moderated Low-Enriched Uranium Core
Journal of Nuclear Science and Technology
High Energy Physics
Nuclear
Engineering
Nuclear Energy
Fuel Temperature Coefficients of Reactivity for Heavy-Water-Moderated, Cluster-Type Fuel Lattices
Journal of Nuclear Science and Technology
High Energy Physics
Nuclear
Engineering
Nuclear Energy
Conversion and Blending Facility Highly Enriched Uranium to Low Enriched Uranium as Uranyl Nitrate Hexahydrate. Revision 1
CRITICAL EXPERIMENTS WITH 2.09% U$sup 235$-Enriched URANIUM METAL PLATES IN WATER
