スポンサーリンク
Japan Nuclear Cycle Development Institute | 論文
- Analysis of Curium Isotopes in Mixed Oxide Fuel Irradiated in Fast Reactor
- Analysis of Minor Actinides in Mixed Oxide Fuel Irradiated in Fast Reactor, (I) Determination of Neptunium-237
- Development of a FBR Fuel Bundle-duct Interaction Analysis Code-BAMBOO Analysis Model and Verification by Phenix High Burn-up Fuel Subassemblies
- Fine Structure of Giant Resonance in the ^Si(γ, abs) Reaction
- Super High Resolution Measurement of Fine Structure in the Total Photonuclear Cross Section of ^C
- Thermal-Neutron Capture Cross Sections and Resonance Integrals of the ^Se(n,γ)^Se Reactions
- Measurement of Effective Capture Cross Section of Americium-243 for Thermal Neutrons
- Measurement of Effective Capture Cross Section of ^Np for Thermal Neutrurons
- Measurement of Thermal Neutron Capture Cross Section and Resonance Integral of the ^Np(n, γ)^Np Reaction
- Measurement of the Thermal Neutron Capture Cross Section and the Resonance Integral of the^Ag(n, γ)^Ag Reaction
- Measurement of Thermal Neutron Capture Cross Section and Resonance Integral of the ^Ho(n,γ)^Ho Reaction using a Two-Step Irradiation Technique
- Precise Measurement of Gamma-ray Emission Probabilities of ^Ru
- Measurement of the Thermal Neutron Capture Cross Section and the Resonance Integral of the ^Sr(n, ν)^Sr Reaction
- Production of the Isomeric State of ^Cs in the Thermal Neutron Capture Reaction ^Cs(η, γ)^Cs
- Behavior of Irradiated ATR/MOX Fuel under Reactivity Initiated Accident Conditions
- Analysis of Critical Electricity Price for the Investment for Constructing a Nuclear Power Plant using Real Options Approach
- JENDL-4.0 Benchmarking for Fission Reactor Applications
- Corrosion Behavior of FBR Candidate Materials in Stagnant Pb-Bi at Elevated Temperature
- ICONE11-36183 CORROSION PROPERTIES OF JAPANESE FBR MATERIALS IN STAGNANT PB-BI AT ELEVATED TEMPERATURE
- ICONE11-36611 A comparative design study of Pb-Bi cooled reactor cores with forced and natural convection cooling