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- [1] THERMAL-HYDRAULIC ANALYSIS OF FAST BREEDER REACTOR: PROTECTED LOSS OF FLOW (PLOF) TRANSIENT 22ND INTERNATIONAL CONFERENCE NUCLEAR ENERGY FOR NEW EUROPE, (NENE 2013), 2013,
- [3] TRANSIENT THERMAL-HYDRAULIC ANALYSIS FOR REACTOR CORES TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1976, 24 (NOV19): : 305 - 307