共 20 条
- [1] Development of integrated numerical analysis model for unsteady phenomena in upper plenum and hot-leg piping system of Japan Sodium-cooled Fast Reactor ASME Pressure Vessels Piping Div. Publ. PVP,
- [2] NUMERICAL ANALYSIS OF UNSTEADY PHENOMENA IN UPPER PLENUM AND HOT-LEG PIPING SYSTEM OF ADVANCED LOOP-TYPE SODIUM COOLED FAST REACTOR PROCEEDINGS OF THE ASME PRESSURE VESSELS AND PIPING CONFERENCE, 2016, VOL 3, 2017,
- [3] Prediction of unsteady flow field in a primary circuit hot-leg piping of a sodium-cooled fast reactor Nihon Kikai Gakkai Ronbunshu, B Hen/Transactions of the Japan Society of Mechanical Engineers, Part B, 2012, 78 (792):
- [6] LDV flow measurement of a deflected inflow using a 1/10-scale hot-log piping test facility of a primary circuit hot-leg piping in a sodium-cooled fast reactor Nihon Kikai Gakkai Ronbunshu, B, 792
- [7] DEVELOPMENT OF NUMERICAL ESTIMATION METHOD USING SPATIAL CONNECTION METHODOLOGY FOR THERMAL STRIPING IN UPPER PLENUM OF REACTOR VESSEL OF AN ADVANCED LOOP-TYPE SODIUM-COOLED FAST REACTOR IN JAPAN PROCEEDINGS OF THE 25TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, 2017, VOL 8, 2017,
- [8] Development of Numerical Simulation System for Thermal-Hydraulic Analysis in Fuel Assembly of Sodium-Cooled Fast Reactor INTERNATIONAL CONFERENCE OF COMPUTATIONAL METHODS IN SCIENCES AND ENGINEERING 2015 (ICCMSE 2015), 2015, 1702