Design and installation of "In-pile tritium-release experimental apparatus" In-situ study of tritium release from uranium dioxides.:In-situ study of Tritium Release from Uranium Dioxides
スポンサーリンク
概要
- 論文の詳細を見る
The "In-pile tritium-release experimental apparatus" was designed and installed at JRR-4 in order to study tritium release from UO<SUB>2</SUB> during reactor operation. It mainly consists of three systems: the irradiation rig, the gas-supplying system and the tritium-collecting system. The mixture of Ne and H<SUB>2</SUB> was used as a sweep gas to avoid the tritium-contamination by the nuclear reaction of the sweep gas and the adsorption of the released tritium on the surface of the irradiation rig. The released tritium was transformed to HT by the isotopic exchange reaction HTO+H<SUB>2</SUB>=HT+H<SUB>2</SUB>O, and collected into the water-bubbler after oxidizing to tritiated water by CuO. The temperature of UO<SUB>2</SUB> irradiated was controlled by changing either the ratio of H<SUB>2</SUB>/Ne mixture gas or the distance between the irradiation rig and reactor core surface. The experimental temperature was from about 400 to 1, 000°C.
- 一般社団法人 日本原子力学会の論文
一般社団法人 日本原子力学会 | 論文
- Estimation of Heat Transfer Coefficient and Flow Characteristics on Heat Transfer Tube in Sodium-Water Reaction
- Application of Pressure Swing Adsorption to Water Detritiation Process
- Numerical Estimation Method of the Hydrogen Isotope Inventory in the Hydrogen Isotope Separation System for Fusion Reactor
- Fatigue Crack Initiation in Proton-Irradiated Austenitic Stainless Steel
- Application of Organic Photodiodes to X-ray Measurements — A Feasibility Study