CFD simulations on the dynamics of liquid sloshing and its control in a storage tank for spent fuel applications
VS Sanapala, K Velusamy, BSV Patnaik - Annals of Nuclear Energy, 2016 - Elsevier
Spent nuclear liquid waste is often kept in partially filled storage tanks. When such storage
tanks are subjected to wind and/or earthquake induced excitations, this could lead to …
tanks are subjected to wind and/or earthquake induced excitations, this could lead to …
[HTML][HTML] Optimization of prevention and mitigation of severe accidents through Research: Major outcomes and outlook of the Spanish programme
LE Herranz, A Domínguez-Bugarín… - … Engineering and Design, 2024 - Elsevier
Severe accidents research activities in Spain have grown substantially since the Fukushima-
Daiichi accident. Most of these research activities have been conducting by a few …
Daiichi accident. Most of these research activities have been conducting by a few …
Station blackout mitigation strategies analysis for Maanshan PWR plant using TRACE
HT Lin, JR Wang, KC Huang, C Shih, SC Chiang… - Annals of Nuclear …, 2016 - Elsevier
Maanshan nuclear power plant (NPP) is a two-unit Westinghouse three-loop PWR NPP.
This research focuses on the analysis and simulation of Maanshan NPP station blackout …
This research focuses on the analysis and simulation of Maanshan NPP station blackout …
[HTML][HTML] Non-watertight door performance experiments and analysis under flooding scenarios
A Wells, ED Ryan, B Savage, A Tahhan, S Suresh… - Results in …, 2019 - Elsevier
Nuclear power plant flooding can cause extensive damage. A more robust understanding of
nuclear power plant performance in flooding scenarios can help identify weaknesses and …
nuclear power plant performance in flooding scenarios can help identify weaknesses and …
Analysis and improvement of hydrogen mitigation strategies during a severe accident in nuclear containments
K Fernández Cosials - 2017 - oa.upm.es
La simulación computacional de la fenomenología de una contención nuclear durante un
accidente ha sido históricamente un desafío. El tamaño de la contención, las características …
accidente ha sido históricamente un desafío. El tamaño de la contención, las características …
Transient 3D simulation for heating and melting process of PWR core after SBO
X Zhang, H Chen, F Liu, D Zhan - Annals of Nuclear Energy, 2018 - Elsevier
In the heat transfer between the core and coolant in a reactor pressure vessel (RPV), a
bounding structure such as a shroud has an important influence on the heating and melting …
bounding structure such as a shroud has an important influence on the heating and melting …
The ultimate response guideline simulation and analysis using TRACE, MAAP5, and FRAPTRAN for the Chinshan Nuclear Power Plant
TC Wang, JR Wang, HT Lin, HC Chen, SW Chen… - Annals of Nuclear …, 2017 - Elsevier
In this research, the TRACE and MAAP5 model of Chinshan BWR/4 nuclear power plant
(NPP) has been established for the simulation and analysis of ultimate response guideline …
(NPP) has been established for the simulation and analysis of ultimate response guideline …
[HTML][HTML] Transient thermal analysis of IVR strategy under a LB-LOCA based on ASTEC code
P Chen, H Fu, P Ou, D He, D Zhan, F Liao… - International Journal of …, 2021 - Elsevier
Abstract A Large-Break Loss of Coolant Accident (LB-LOCA) in a generic, 1000 MWe and 3-
loop Chinese Pressurized Water Reactor (PWR) with the In-Vessel corium Retention (IVR) …
loop Chinese Pressurized Water Reactor (PWR) with the In-Vessel corium Retention (IVR) …
The Establishment and Simulation of TRACE/FRAPTRAN/MELCOR/SNAP Model for Chinshan Nuclear Power Plant Ultimate Response Guideline
C Shih, JR Wang, TC Wang, HT Lin, HC Chen… - Proceedings of The 20th …, 2017 - Springer
Abstract Chinshan Nuclear Power Plant (NPP) was built in 1970 and is a BWR/4 NPP. The
original rated power of Chinshan NPP for each unit is 1775 MW. Chinshan NPP finished the …
original rated power of Chinshan NPP for each unit is 1775 MW. Chinshan NPP finished the …