Call Number (LC) Title Results
Y 3.N 88:53/0417 Post-test thermal-hydraulic analysis of PKL tests F1.1 and F1.2 / 1
Y 3.N 88:53/0418 Application of TRACE V5.0 P2 to natural circulation reactor safety analysis / 1
Y 3.N 88:53/0419 Analysis with TRACE code of ROSA test 1.1 : ECCS water injection under natural circulation condition / 1
Y 3.N 88:53/0420 Analysis with TRACE code of Rosa test 1.2 : small LOCA in the hot-leg with HPI and accumulator actuation / 1
Y 3.N 88:53/0421 Improvements and validation of the system code TRACE for lead and lead-alloy cooled fast reactors safety-related investigations / 1
Y 3.N 88:53/0422 Transient analysis of the research reactor MARIA MC fuel elements using RELAP5 Mod 3.3 / 1
Y 3.N 88:53/0423 Analysis with TRACE code of PKL-III test F 1.2 / 1
Y 3.N 88:53/0424 RELAP5 extended station blackout analyses / 1
Y 3.N 88:53/0425 TRACE5 assessment of 100% direct vessel injection line break in ATLAS facility / 1
Y 3.N 88:53/0426 Simulation of LSTF upper head break (OECD/NEA ROSA test 6.1) with TRACE code : application to a PWR NPP model / 1
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