Results 81 to 90 of about 8,520 (102)

CHF experiments using a 2-D curved test section with additives for IVR-ERVC strategy

Nuclear Engineering and Design, 2012
Abstract This study describes critical heat flux (CHF) experiments using a 2-D curved test section with trisodium phosphate (TSP: Na 3 PO 4 ) and boric acid (BA: H 3 BO 5 ). The CHF values of TSP solution, BA solution, and TSP + BA solution were enhanced by as much as 50% for all experimental conditions except the condition of 150 mm radius with BA ...
Kim, TI Kim, Tae-Il, Park, HM Park, Hae-Min, Chang, SH Chang, Soon-Heung   +2 more
openaire   +2 more sources

Detailed evaluation of natural circulation mass flow rate in the annular gap between the outer reactor vessel wall and insulation under IVR-ERVC

Annals of Nuclear Energy, 2016
Abstract IVR (In-Vessel corium Retention) through ERVC (External Reactor Vessel Cooling) is known to be an effective means for maintaining the reactor vessel integrity during a severe accident in a nuclear power plant. Detailed simulations of a two phase natural circulation flow in the reactor cavity of an APR (Advanced Power Reactor) 1400 and ...
Rae-Joon Park, Kwang-Soon Ha
exaly   +2 more sources

Experimental study on the CHF of IVR-ERVC system with an elliptical lower head under forced circulation condition

Annals of Nuclear Energy
Bo Kuang
exaly   +2 more sources

Analysis of Focusing Effect of Light Metallic Layer in Stratified Molten Pool Under IVR-ERVC Condition

Journal of Nuclear Engineering and Radiation Science, 2015
The main failure mechanism of in-vessel corium retention through external reactor vessel cooling (IVR-ERVC) happens when the local heat flux through reactor pressure vessel (PRV) wall exceeds the critical heat flux (CHF). High local heat flux in the molten pool is usually caused by the metallic layer focusing effect due to stratification. In this paper,
Xi Wang, Xu Cheng
exaly   +2 more sources

CFD study on flow-boiling characteristics and predicting critical heat flux under natural circulation conditions of IVR-ERVC

International Journal of Thermal Sciences
Deqi Chen, Shanshan Bu, Zhen Zhang
exaly   +2 more sources

Preliminary Experiment: Quantitative Vapor Observation Through Flow Visualization Under IVR-ERVC Environment

Transactions of the American Nuclear Society, 2022
Jun Jung, Yong Jeong
openaire   +1 more source

Experimental Study of Ivr-Ervc Chf Limits for Cap1400

2023
openaire   +1 more source

Numerical Investigation on the Thermal-Hydraulic Characteristics near a Corroded Lower Head of the Reactor Vessel During IVR-ERVC

Nuclear Science and Engineering, 2022
Cheng Peng, Youya Song, Jian Deng, Sen Mao, Jiang Wu   +4 more
openaire   +1 more source

Sensitivity Analysis of Heat Transfer Limit Under IVR-ERVC Condition Based on a Newly Developed CHF Model

20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20), 2023
Gang Wang, Shilei Han, Bo Kuang, Pengfei Liu   +3 more
openaire   +1 more source

Spray Cooling Optimization for IVR-ERVC Applications

2025 4th International Conference on Advanced Electronics, Electrical and Green Energy (AEEGE)
Vitor Fernandes de Almeida, Jingqi Zhao, Lining Liu, Feng Xie   +3 more
openaire   +1 more source