共 50 条
- [32] BEHAVIOR OF THE SPENT FUEL POOL AND DOSE RATE CALCULATIONS FOR THE CPR1000 REACTOR UNDER SEVERE ACCIDENT CONDITIONS USING THE INTEGRAL CODE MELCOR PROCEEDINGS OF THE 21ST INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING - 2013, VOL 6, 2014,
- [33] SEVERE ACCIDENT ANALYSIS WITH SPATIAL DISCRETIZED MODEL BY MAAP - (1) PARAMETRIC STUDY ON FUKUSHIMA-DAIICHI UNIT-2 PROCEEDINGS OF THE 26TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, 2018, VOL 6B, 2018,
- [35] Analysis of a postulated 2-inch Cold Leg LOCA severe accident in a PWR-like 900 MWe with MELCOR code 27TH INTERNATIONAL CONFERENCE NUCLEAR ENERGY FOR NEW EUROPE (NENE 2018), 2018,