Results 121 to 130 of about 362 (143)

Validation of neutronics and thermal-hydraulics coupling model of the RELAP5-3D code using the MSRE reactivity insertion tests

Nuclear Engineering and Design, 2022
Hiroyasu Mochizuki
exaly  

Assessment of a RELAP5 model for the IPR-R1 TRIGA research reactor

Annals of Nuclear Energy, 2010
Claubia Pereira, Antonella Lombardi Costa, Amir Zacarias Mesquita   +2 more
exaly  

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

Annals of Nuclear Energy, 2017
Zhongning Sun
exaly  

Preliminary validation of RELAP5/Mod4.0 code for LBE cooled NACIE facility

Nuclear Engineering and Design, 2017
Ashok Khanna
exaly  

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

Fusion Engineering and Design, 2014
Victor Manuel Martinez Quiroga, Lluís Batet, F Reventós   +2 more
exaly  

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

Annals of Nuclear Energy, 2012
Mehdi Hashemi-Tilehnoee, Kamal Hadad
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, Suizheng Qiu
exaly  

Investigation of LBLOCA in VVER-1000 NPP using RELAP5/SCDAP and CONTAIN codes

Annals of Nuclear Energy, 2020
Gholamreza Jahanfarnia
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
Chengcheng Deng, Jun Yang
exaly