Call Number (LC) Title Results
Y 3.N 88:53/0427 Application of TRACE V5.0 P2 to China domestic PWR LBLOCA analysis / 1
Y 3.N 88:53/0428 Performing uncertainty analysis of IIST facility SBLOCA by TRACE and DAKOTA / 1
Y 3.N 88:53/0429 Analysis of loss of feedwater heater transients for Lungmen ABWR by TRACE/PARCS / 1
Y 3.N 88:53/0430 TRACE simulation of SBO accident and mitigation strategy in Maanshan PWR / 1
Y 3.N 88:53/0431 The FSAR transients analysis of Lungmen ABWR using TRACE/PARCS / 1
Y 3.N 88:53/0432 Analysis of the test OECD-PKL2 G7.1 with the thermal-hydraulic system code TRACE / 1
Y 3.N 88:53/0433 RELAP5/MOD3.3 release pre & postprocessor / 1
Y 3.N 88:53/0434 The development and application of TRACE/PARCS model for Lungmen ABWR / 1
Y 3.N 88:53/0435 Assessment of RELAP5/MOD3.3 and TRACE V5.0 computer codes against LOCA test data from PSB-VVER test facility / 1
Y 3.N 88:53/0436 Assessment of LONF ATWS for Maanshan PWR using TRACE code / 1
Y 3.N 88:53/0437 Sensitivity study of the DEG LBLOCA transient on the counter-current flow limitation by using TRACE / 1
Y 3.N 88:53/0438 ATWS analysis of Lungmen ABWR for MSIV closure transient / 1
Y 3.N 88:53/0439 TRACE analysis on heat removal decrease accidents for AP1000 / 1
Y 3.N 88:53/0440 The alternate mitigation strategies study of Chinshan BWR/4 by using the LOCA and SBO analysis of TRACE / 1
Y 3.N 88:53/0441 Assessment against ACHILLES reflood experiment with TRACE V5.0 Patch3 / 1
Y 3.N 88:53/0442 RELAP5/MOD3.3 analysis of steam generator tube rupture (SGTR) accident for NPP Krško / 1
Y 3.N 88:53/0443 Research reactor 'MARIA' primary cooling loop transient analysis using RELAP5 Mod 3.3 / 1
Y 3.N 88:53/0444 Simulation of LSTF hot leg break (OECD/NEA ROSA-2 test 1) with TRACE code : application to a PWR NPP model / 1
Y 3.N 88:53/0445 The establishment and assessment of Chinshan (BWR/4) Nuclear Power Plant TRACE/SNAP model / 1
Y 3.N 88:53/0446 Assessment of channel coolant voiding in RD-14M test facility using TRACE / 1