共 50 条
- [31] Creep-fatigue analysis and evaluation of thorium-based molten salt reactor loop pipe Hedongli Gongcheng/Nuclear Power Engineering, 2017, 38 (01): : 56 - 59
- [32] THERMAL-HYDRAULIC ANALYSES FOR CRBRP CORE-RESTRAINT DESIGN TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1975, 21 (JUN): : 393 - 395
- [33] Thermal-hydraulic Feasibility Study of a Convex shaped Fast Reactor Core SPECIAL ISSUE OF FOR THE FIFTH INTERNATIONAL SYMPOSIUM ON INNOVATIVE NUCLEAR ENERGY SYSTEMS, 2017, 131 : 86 - 93
- [35] STUDY ON THE COUPLED NEUTRONIC AND THERMAL-HYDRAULIC CHARACTERISTICS OF THE NEW CONCEPT MOLTEN SALT REACTOR ICONE17, VOL 4, 2009, : 673 - 679
- [37] Study on the Coupled Neutronic and Thermal-Hydraulic Characteristics of the New Concept Molten Salt Reactor JOURNAL OF ENGINEERING FOR GAS TURBINES AND POWER-TRANSACTIONS OF THE ASME, 2010, 132 (10):