共 50 条
- [31] Open thermal-hydraulic research issues in Western Nuclear Power Reactors ATW-INTERNATIONAL JOURNAL FOR NUCLEAR POWER, 2004, 49 (05): : 342 - +
- [34] PRELIMINARY DEVELOPMENT ON THERMAL-HYDRAULIC ANALYSIS CODE FOR THE SPENT FUEL ROD UNDER THE CONDITION OF SPRAY COOLING PROCEEDINGS OF THE 2020 INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING (ICONE2020), VOL 3, 2020,
- [37] MANUFACTURE OF PLATE TYPE FUEL ELEMENTS FOR RESEARCH REACTORS METALLURGIA ITALIANA, 1967, 59 (05): : 359 - &
- [38] Development and validation of thermal-hydraulic and safety analysis code for CARR (TSACC) Hedongli Gongcheng/Nuclear Power Engineering, 2009, 30 (01): : 40 - 44
- [40] THE RESEARCH AND COMPARISON OF THERMAL-HYDRAULIC TEST FACILITIES FOR PRESSURIZED WATER REACTORS (PWRS) PROCEEDINGS OF THE 25TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, 2017, VOL 6, 2017,