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- [1] TRANSIENT THERMAL-HYDRAULIC ANALYSIS FOR REACTOR CORES TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1976, 24 (NOV19): : 305 - 307
- [4] THERMAL-HYDRAULIC BEHAVIOR OF LIGHT-WATER REACTOR CORES TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1979, 32 (JUN): : 592 - 593
- [8] REACTOR CORE TRANSIENT ANALYSIS USING COUPLED NEUTRONICS AND THERMAL-HYDRAULIC MODELS TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1979, 31 (MAY): : 256 - 258
- [10] THERMAL-HYDRAULIC ANALYSIS OF FAST BREEDER REACTOR: PROTECTED LOSS OF FLOW (PLOF) TRANSIENT 22ND INTERNATIONAL CONFERENCE NUCLEAR ENERGY FOR NEW EUROPE, (NENE 2013), 2013,