|
Y 3.N 88:53/0446
|
Assessment of channel coolant voiding in RD-14M test facility using TRACE / |
1 |
|
Y 3.N 88:53/0447
|
RELAP5/MOD3.3 assessment by comparison with PKL III G3.1 experiment (small break in the main steam line) / |
1 |
|
Y 3.N 88:53/0448
|
Uncertainty analysis for Maanshan LBLOCA by TRACE and DAKOTA / |
1 |
|
Y 3.N 88:53/0449
|
Post-test analysis of Upper Plenum 11% break at PSB-VVER facility using TRACE v5.0 and RELAP5/MOD3.3 code / |
1 |
|
Y 3.N 88:53/0450
|
The development and application of Kuosheng (BWR/6) nuclear power plant TRACE/SNAP model / |
1 |
|
Y 3.N 88:53/0451
|
The establishment and assessment of Kuosheng (BWR/6) NPP dry-storage system TRACE/SNAP model / |
1 |
|
Y 3.N 88:53/0452
|
Spent fuel pool safety analysis of TRACE in Chinshan NPP / |
1 |
|
Y 3.N 88:53/0453
|
Benchmarking of a generic CANDU reactor with PARCS, MCNP and RFSP / |
1 |
|
Y 3.N 88:53/0454
|
Modelling of ROCOM mixing test 2.2 with TRACE v5.0 Patch 3 / |
1 |
|
Y 3.N 88:53/0455
|
Analysis of the control rod drop accident (CRDA) for lungmen ABWR / |
1 |
|
Y 3.N 88:53/0456
|
BEPU analysis and benchmark with IIST 2% SBLOCA experiment using TRACE/DAKOTA / |
1 |
|
Y 3.N 88:53/0457
|
Assessment of critical subcooled flow through cracks in large and small pipes using TRACE and RELAP5 / |
1 |
|
Y 3.N 88:53/0458
|
RELAP5/MOD3.3 analysis of event with actuation of safety injection system at the loss of external power / |
1 |
|
Y 3.N 88:53/0459
|
EPR medium break LOCA benchmarking exercise using RELAP5 and CATHARE / Sebastian Gurgacz [and five others] |
1 |
|
Y 3.N 88:53/0460
|
Model 3D cores for PWR using vessel components in TRACEv5.OP3 / |
1 |
|
Y 3.N 88:53/0461
|
TRAC-BF1 to TRACE model semi-automatic conversion : PBTT example / |
1 |
|
Y 3.N 88:53/0462
|
Uncertainty and sensitivity investigations with TRACE-SUSA and TRACE-DAKOTA by means of post-test calculations of NUPUC BFBT experiments / |
1 |
|
Y 3.N 88:53/0463
|
(Availability of) an international report on safety critical software for nuclear reactors by the regulator task force on safety critical software (TF-SCS) / |
1 |
|
Y 3.N 88:53/0464
|
RELAP5/MOD3.3 model assessment and hypothetical accident analysis of Kuosheng Nuclear Power Plant with SNAP interface / |
1 |
|
Y 3.N 88:53/0465
|
Fuel rod performance uncertainty analysis during overpressurization transient for Kuosheng Nuclear Power Plant with TRACE/FRAPTRAN/Dakota codes in SNAP interface / |
1 |
