Results 161 to 170 of about 1,865 (177)

Improvement and validation of RELAP5/SCDAP code on evaluating the graphite behavior during oxidation process

Progress in Nuclear Energy, 2020
Penghui Chai, Koji Okamoto
exaly  

RELAP5/mod2 Code for Win95/NT Environment with F90 Capabilities

1997
Some aspects of modifications necessary to convert RELAP5/mod2 to fortran 90 and to initiate its usage as Windows 95/NT application are discussed. Main characteristics requested from new version are shown. The change in original memory allocation scheme (FTB package) and introduction of dynamic memory allocation are described.
Čavlina, Nikola, Bajs, Tomislav, Špalj, Srđan, Grgić, Davor   +3 more
openaire   +1 more source

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

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

Semi 2D modeling of the horizontal steam generator PGV-1000 using the RELAP5 code

Progress in Nuclear Energy, 2009
F D`Auria
exaly  

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

Nuclear Engineering and Design, 2017
Ashok Khanna
exaly  

Capability of RELAP5 MOD3.3 code to simulate density wave instability in parallel narrow rectangular channels

Annals of Nuclear Energy, 2013
Meng Lin
exaly  

Modeling the Dewatering of Open Systems Using the RELAP5 Code

Vestnik MEI, 2020
Evgeniy Yu. Bragin, Aleksandr O. Gol′tsev, Aleksandr V. Il′yin, Aleksey M. Osipov, Serhey V. Prokhorenkov, Anastasiya K. Smirnova   +5 more
openaire   +1 more source

Flow blockage accident or loss of flow accident by using comparative approach of NK/TH coupling codes and RELAP5 code

Annals of Nuclear Energy, 2014
Salah Ud-Din Khan, Shahab Ud-Din Khan, Minjun Peng   +2 more
exaly  

Thermal hydraulic analysis of small nuclear reactor core by using comparative approach of THEATRe and Relap5 code

International Journal of Nuclear Energy Science and Technology, 2011
Minjun Peng, Salah Ud-Din Khan, Shahab Ud-Din Khan   +2 more
exaly  

Development and validation of a thermal hydraulic transient analysis code for offshore floating nuclear reactor based on RELAP5/SCDAPSIM/MOD3.4

Annals of Nuclear Energy, 2019
Fulong Zhao, Sichao Tan
exaly