Thermochemical Prediction of Chemical Form Distributions of Fission Products in LWR Oxide Fuels Irradiated to High Burnup
スポンサーリンク
概要
- 論文の詳細を見る
- Atomic Energy Society of Japanの論文
- 1997-09-25
著者
-
MORIYAMA Kiyofumi
Japan Atomic Energy Agency
-
Furuya Hirotaka
Department Of Applied Quantum Physics And Nuclear Engineering Division Of Engineering Graduate Schoo
-
Furuya Hirotaka
Department Of Nuclear Engineering Faculty Of Engineering Kyushu University
-
MORIYAMA Kouki
Department of Nuclear Engineering, Faculty of Engineering, Kyushu University
-
Moriyama Kouki
Department Of Nuclear Engineering Division Of Engineering Graduate School Kyushu University
-
Moriyama K
Japan Atomic Energy Agency
関連論文
- Experiments on the Release of Gaseous Iodine from Gamma-Irradiated Aqueous CsI Solution and Influence of Oxygen and Methyl Isobutyl Ketone (MIBK)
- Evaluation of Containment Failure Probability by Ex-Vessel Steam Explosion in Japanese LWR Plants
- Modeling for Evaluation of Debris Coolability in Lower Plenum of Reactor Pressure Vessel
- Unit Sphere Concept for Macroscopic Triggering of Large-scale Vapor Explosions
- A Simple Evaluation Method of the Molten Fuel Amount in a Premixing Region of Fuel-Coolant Interactions
- Thermochemical Prediction of Chemical Form Distributions of Fission Products in LWR Oxide Fuels Irradiated to High Burnup
- Experiment and Modeling for Solvent Leaching from Paint Matrix Considering Equilibrium
- Thermochemical Prediction of Chemical Form Distributions of Fission Products in LWR Mixed Oxide Fuels
- Behavior of Fission Products Zirconium and Barium in Fast Reactor Fuel Irradiated to High Burnup
- Corrosion Behavior of a Powdered Simulated Nuclear Waste Glass in the Presence of Bentonite.
- Penertration behavior of cesium in oxide film growing on surface of stainless steel under condition of high oxygen potential.
- Volumetric change of simulated radioactive waste glass irradiated by electron accelerator.
- Determination of heat capacity of simulated radioactive waste glasses by drop calorimetry.
- Preparation of thorium-uranium mixed oxide pellets.
- Effect of grain size of stainless steel on oxidation rate under oxygen pressure controlled by Mo/MoO2 oxygen buffer.