| Call Number (LC) | Title | Results |
|---|---|---|
| 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 |
| Y 3.N 88:53/0466 | Analysis of the OSU-MASLWR 001 and 002 tests by using the TRACE code / | 1 |
| Y 3.N 88:53/0467 | RELAP5 analysis of mitigation strategy for extended blackout power condition in PWR / | 1 |
| Y 3.N 88:53/0468 | Validation of RELAP5 model of ringhals 4 against a load step test at uprated power / | 1 |
| Y 3.N 88:53/0469 | Development of a coupled TRACE/PARCS model for KKL and benchmark against the turbine trip test / | 1 |
| Y 3.N 88:53/0470/V.1 | Nuclear regulatory authority experimental program to characterize and understand high energy arcing fault (HEAF) phenomena / | 1 |
| Y 3.N 88:53/0471 | Fuel rod behavior and uncertainty analysis by FRAPTRAN/TRACE/DAKOTA code in maanshan LBLOCA / | 1 |
| Y 3.N 88:53/0472 | RELAP5/MOD3.3 model assessment of Maanshan Nuclear Power Plant with SNAP interface / | 1 |
| Y 3.N 88:53/0473 | Feedwater line break analysis using RELAP5/MOD3.3 for steam generator blowdown load assessment / | 1 |
| Y 3.N 88:53/0474 | Steam line break analysis using RELAP5/MOD3.3 for steam generator blowdown load assessment / | 1 |
| Y 3.N 88:53/0475 | TRACE/RELAP5 comparative calculations for double-ended LBLOCA and SBO / | 1 |
| Y 3.N 88:53/0476 |
Main steam line break analysis for Lungmen ABWR / Main stream line break analysis for lungmen ABWR / |
2 |
| Y 3.N 88:53/0477 | Thermal hydraulic and fuel rod mechanical combination analysis of Kuosheng Nuclear Power Plant with RELAP5 MOD3.3/FRAPTRAN/Python in SNAP interface / | 1 |
| Y 3.N 88:53/0478 | TRACE/SNAP model establishment of Chinshan nuclear power plant for ultimate response guideline / | 1 |
| Y 3.N 88:53/0479 | RELAP5 and TRACE calculations of LOCA in PWR / | 1 |
| Y 3.N 88:53/0480 | TRACE assessment for effect of spacer grid in RBHT reflood heat transfer experiments / | 1 |
| Y 3.N 88:53/0481 | Evaluation of TRACE spacer grid model with FLECHT-SEASET reflood test / | 1 |
| Y 3.N 88:53/0482 | Using TRACE, MELCOR, CFD, and FRAPTRAN to establish the analysis methodology for Chinshan Nuclear Power Plant spent fuel pool / | 1 |
