共 50 条
- [41] Pressurized Water Small Modular Reactor (SMR), Design Basis Accident Analysis using the ASTEC code 23RD INTERNATIONAL CONFERENCE NUCLEAR ENERGY FOR NEW EUROPE, (NENE 2014), 2014,
- [43] PRELIMINARY PHYSICS DESIGN OF A PRESSURIZED HEAVY-WATER REACTOR TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1978, 28 (JUN): : 723 - 724
- [44] Pressurized heavy water reactor technology: Its relevance today 1600, American Society of Mechanical Engineers (ASME), United States (03):
- [48] WESTINGHOUSE PRESSURIZED WATER-REACTOR FUEL DEVELOPMENT AND PERFORMANCE NUCLEAR ENERGY-JOURNAL OF THE BRITISH NUCLEAR ENERGY SOCIETY, 1980, 19 (05): : 335 - 346
- [50] DESIGN OPTIMIZATION OF MAIN COOLING WATER SYSTEMS FOR A PRESSURIZED WATER REACTOR PLANT TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1972, 15 (01): : 392 - &