Search Results - Wang, Jong-Rong
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1
TRACE/SNAP model establishment of Chinshan nuclear power plant for ultimate response guideline / by Wang, Jong-Rong
Published 2017Call Number: Loading…Online Access
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2
Thermal hydraulic and fuel rod mechanical combination analysis of Kuosheng Nuclear Power Plant with RELAP5 MOD3.3/FRAPTRAN/Python in SNAP interface / by Wang, Jong-Rong
Published 2016Call Number: Loading…Online Access
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Government Document eBook -
3
TRACE simulation of SBO accident and mitigation strategy in Maanshan PWR / by Wang, Jong-Rong
Published 2013Call Number: Loading…Online Access
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4
Analysis of loss of feedwater heater transients for Lungmen ABWR by TRACE/PARCS / by Wang, Jong-Rong
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5
The FSAR transients analysis of Lungmen ABWR using TRACE/PARCS / by Wang, Jong-Rong
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6
Performing uncertainty analysis of IIST facility SBLOCA by TRACE and DAKOTA / by Wang, Jong-Rong
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7
The development and assessment of TRACE model for Maanshan Nuclear Power Plant LOCA / by Wang, Jong-Rong
Published 2012Call Number: Loading…Online Access
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8
Using SNAP/RADTRAD and HABIT to establish the analysis methodology for Maanshan PWR / by Wang, Jong-Rong
Published 2019Call Number: Loading…Online Access
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9
Uncertainty analysis for Maanshan LBLOCA by TRACE and DAKOTA / by Wang, Jong-Rong
Published 2014Call Number: Loading…Online Access
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10
The development and application of TRACE/PARCS model for Lungmen ABWR / by Wang, Jong-Rong
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11
The establishment and assessment of Chinshan (BWR/4) Nuclear Power Plant TRACE/SNAP model / by Wang, Jong-Rong
Published 2014Call Number: Loading…Online Access
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12
ATWS analysis of Lungmen ABWR for MSIV closure transient / by Wang, Jong-Rong
Published 2014Call Number: Loading…Online Access
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13
TRACE analysis on heat removal decrease accidents for AP1000 / by Wang, Jong-Rong
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14
The alternate mitigation strategies study of Chinshan BWR/4 by using the LOCA and SBO analysis of TRACE / by Wang, Jong-Rong
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15
Sensitivity study of the DEG LBLOCA transient on the counter-current flow limitation by using TRACE / by Wang, Jong-Rong
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16
Assessment of the TRACE code using transient data from Maanshan PWR Nuclear Power Plant by Wang, Jong-Rong
Published 2010Call Number: Loading…Online Access
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Government Document Electronic eBook -
17
Using TRACE, MELCOR, CFD, and FRAPTRAN to establish the analysis methodology for Chinshan Nuclear Power Plant spent fuel pool / by Wang, Jong-Rong
Published 2018Call Number: Loading…Online Access
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18
Assessment of LONF ATWS for Maanshan PWR using TRACE code / by Wang, Jong-Rong
Published 2014Call Number: Loading…Online Access
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19
The development and verification of TRACE model for IIST experiments
Published 2011Other Authors: “…Wang, Jong-Rong…”
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Related Subjects
Nuclear power plants
Computer simulation
Pressurized water reactors
Safety measures
Accidents
Computer programs
Boiling water reactors
Testing
Loss of coolant
Evaluation
Nuclear reactor accidents
Analysis
Control
Control rooms
Instruments
Nuclear engineering
Nuclear fuel rods
Nuclear reactors
Spent reactor fuels
Storage
Water cooled reactors