Results 161 to 170 of about 2,939 (182)

Capability of RELAP5 code to simulate the thermal-hydraulic characteristics of open natural circulation

Annals of Nuclear Energy, 2017
Xiaofan Hou, Zhongning Sun
exaly  

Modelling of a supercritical CO2 power cycle for nuclear fusion reactors using RELAP5–3D

Fusion Engineering and Design, 2014
L Batet, E Mas De Les Valls, V Martinez-Quiroga   +2 more
exaly  

RELAP5 MOD3.2 modification and application to the transient analysis of a fluoride-salt-cooled high-temperature reactor

Annals of Nuclear Energy, 2017
Limin Liu, Dalin Zhang, Rongshuan Xu
exaly  

Simulation of a control rod ejection accident in a VVER-1000/V446 using RELAP5/Mod3.2

Annals of Nuclear Energy, 2012
K Hadad, Mohammadreza Nematollahi, M Hashemi-Tilehnoee   +2 more
exaly  

Validation of RELAP5/MOD3.2 model of VVER440 on reactor scram transient

Progress in Nuclear Energy, 2006
Pavlin Groudev
exaly  

Best Estimate Plus Uncertainty analysis of a large break LOCA on Generation III reactor with RELAP5

Annals of Nuclear Energy, 2019
Jun Yang, Chengcheng Deng
exaly  

Coupling RELAP5-3D to BISON

Jason Hales, Jan Cornelius Vermaak, Mauricio Tano Retamales   +2 more
openaire   +1 more source

Assessment of RELAP5/MOD3.2 for startup transients in a natural circulation test facility

Annals of Nuclear Energy, 2018
Shanbin Shi, Qingzi Zhu, Xiaodong Sun
exaly  

An investigation of numerical performance enhancement of RELAP5: Numerical stability, higher resolution and an alternative constitutive relation

Nuclear Engineering and Design, 2018
Koroush Shirvan
exaly  

Preliminary study of coupling CFD code FLUENT and system code RELAP5

Annals of Nuclear Energy, 2014
Dalin Zhang, Wenxi Tian, Suizheng Qiu
exaly