Loss of flow accident analysis in Atucha II nuclear power plant using RELAP5 model

Thermal hydraulic simulation of the steam generator under fast transient events

(2022) Dario M. Godino et al.   ANNALS OF NUCLEAR ENERGY

Thermal hydraulic analysis of loss of flow accident in the JRR-3M research reactor under the flow blockage transient

(2018) Yuchuan Guo et al.   ANNALS OF NUCLEAR ENERGY

Analysis of a loss-of-flow accident resulting from the primary pump shaft break transient of the NUR research reactor

(2018) Mohammed Azzoune et al.   JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY

Simulation of the EBR-II Loss-of-Flow Tests Using the MARS Code

(2017) Kwi-Seok Ha et al.   NUCLEAR TECHNOLOGY

CFD model of a moderator tank for a pressure vessel PHWR nuclear power plant

(2016) Santiago F. Corzo et al.   APPLIED THERMAL ENGINEERING

1/3D modeling of the core coolant circuit of a PHWR nuclear power plant

(2015) Santiago Corzo et al.   ANNALS OF NUCLEAR ENERGY

A review of modern advances in analyses and applications of single-phase natural circulation loop in nuclear thermal hydraulics

(2014) Dipankar N. Basu et al.   NUCLEAR ENGINEERING AND DESIGN

Capability of the RELAP5 code to simulate natural circulation behavior in test facilities

(2012) Amit Mangal et al.   PROGRESS IN NUCLEAR ENERGY

Experimental and computational investigation of a natural circulation system in Regional Energy Reactor-10MWth

(2011) Byeong-Il Jang et al.   NUCLEAR ENGINEERING AND DESIGN

Transient flow analysis in reactor coolant pump systems during flow coastdown period

(2010) Hong Gao et al.   NUCLEAR ENGINEERING AND DESIGN