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Sana Ullah
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Source term evaluation for the upgraded LEU Pakistan Research Reactor-1 under severe accidents
S Ullah, SE Awan, NM Mirza, SM Mirza
Nuclear Engineering and Design 240 (11), 3740-3750, 2010
262010
Suppression of Radioactive Material Dispersion in the event of a Radioactivity Release Accident at a Nuclear Power Plant
S Ullah, MS Yim
GLOBAL 2017, 2017
52017
Steam Generator Tube Rupture Accident at a NPP and Exploration of Mitigation Strategies for Its Consequence
S Ullah, MS Yim
Korea Nuclear Society Spring Meeting, 2018
22018
Modeling and simulation of release of radioactivity from a typical MTR type research reactor under accidental conditions
S Ullah, SE Awan, NM Mirza, SM Mirza
2009 IEEE 13th International Multitopic Conference, 1-6, 2009
12009
Conceptual Design of Underground Toroidal Containment Extension Building for Increased Containment Integrity and Natural Decontamination Capability of Radioactive Materials …
SW Kanga, S Ullaha, MS Yima
2021 한국원자력학회 춘계학술발표회, 2021
2021
Investigation of aerodynamic barrier-based approach for consequence mitigation of a radioactivity release accident at a nuclear power plant
S Ullah
한국과학기술원, 2020
2020
Evaluation of an aerodynamic barrier approach to limit the dispersion of fission products in the event of containment failure
S Ullah, MS Yim
Progress in Nuclear Energy 118, 103120, 2020
2020
Study on Capturing Nozzle Design Configurations for Consequence Mitigation of Steam Generator Tube Rupture Accident (SGTR)
S Ullah, MS Yim
International Congress on Advances in Nuclear Power Plants (ICAPP), 2019
2019
Examining the effect of plume rise on radiological consequences of nuclear accidents
S Ullah, MS Yim
American Nuclear Society, 804-807, 2017
2017
Effect of Air-Curtain Discharge Speed on the Effectiveness of Vortex-like Air-Curtain Approach for Severe Accident Management
S Ullah, MS Yim
Korean Nuclear Society, 2017
2017
Effect of Suction Parameters in Vortex-like Air-Curtain based approach for Radioactivity Dispersion Prevention following Containment breach at a Nuclear Power Plant
S Ullah, MS Yim
Transactions of the Korean Nuclear Society Autumn Meeting, 2016
2016
Preliminary Investigations of Vortex Based Ex-Containment Radioactivity Release-Barrier System for Severe Accident Management at NPPs
HJS S Ullah, Man Sung Yim, Jinsoo Park
International Congress on Advances in Nuclear Power Plants (ICAPP), 985-990, 2016
2016
Vortex-Concept for Radioactivity Release Prevention at NPP: Development of Computational Model of Lab-Scale Experimental Setup
S Ullah, YM Sung, JS Park, HJ Sung
2016
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Artikelen 1–13