Results 101 to 110 of about 2,651,698 (166)

Modeling TBM Components by Using RELAP5 Code

Volume 5: Fuel Cycle, Radioactive Waste Management and Decommissioning; Reactor Physics and Transport Theory; Nuclear Education, Public Acceptance and Related Issues; Instrumentation and Controls; Fusion Engineering, 2013
RELAP5 is a best estimate system code suitable for the analysis of all transients and postulated accidents in Light Water Reactor systems. It was usually used to solve plant thermal-hydraulic problems on system scale. RELAP5 was used to study thermal-hydraulic behavior on component level in this paper.
Yaoli Zhang, Tianji Peng
semanticscholar   +2 more sources

Thermal hydraulic analysis of ETRR-2 using RELAP5 code

Kerntechnik, 2015
Abstract The present work was developed within the frame of the IAEA Coordinated Research Project 1496 “Innovative methods in research reactor analysis: Benchmark against experimental data on neutronics and thermal-hydraulic computational methods and tools for operation and safety analysis of research reactors”.
I. Abdelrazek, A. G. A. Elnour, M. A. Gaheen   +2 more
semanticscholar   +2 more sources

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

Annals of Nuclear Energy, 2017
Xiaofan Hou, Zhong-ning Sun, Wenjing Lei
semanticscholar   +3 more sources

Multi-component diffusion analysis and assessment of GAMMA code and improved RELAP5 code

Nuclear Engineering and Design, 2007
Abstract A loss-of-coolant accident (LOCA) has been considered a critical event for very high temperature gas-cooled reactor (VHTR). Following helium depressurization, it is anticipated that unless countermeasures are taken, air will enter the core through the break by molecular diffusion and ultimately by natural convection leading to oxidation of ...
H. No, Hong-Sik Lim, J. Kim, C. Oh, L. J. Siefken, C. Davis   +5 more
semanticscholar   +3 more sources

Development of a thermal–hydraulic system code for simulators based on RELAP5 code

Nuclear Engineering and Design, 2005
Abstract A thermal–hydraulic system code for simulators, RELAPSIM, was developed at NSSE based on RELAP5. The development procedure consists of three major parts. Firstly, time control function was added into the code to meet real-time calculation needs.
Meng Lin, Y. Su, R. Hu, R. Zhang, Yanhua Yang   +4 more
semanticscholar   +2 more sources

Benchmarking RSG-GAS reactor thermal hydraulic data using RELAP5 code

Annals of Nuclear Energy, 2014
I. Abdelrazek, M. Aly, A. Badawi, A. G. A. Elnour   +3 more
semanticscholar   +3 more sources

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
S. Khan, S. Khan, M. Peng
semanticscholar   +3 more sources

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

Progress in Nuclear Energy, 2009
E. Zarifi, G. Jahanfarnia, S. Mousavian, F. D’Auria   +3 more
semanticscholar   +3 more sources

COBRA/RELAP5: A Merged Version of the COBRA-TF and RELAP5/MOD3 Codes

Nuclear Technology, 1992
The best-estimate thermal-hydraulic codes RE-LAP5/MOD3 and COBRA-TF were adopted to the Apollo DN 10000 workstation and subsequently merged.
Sang Yong Lee, Jae Jun Jeong, Si-Hwan Kim, Soon Heung Chang   +3 more
openaire   +1 more source

Improvement of RELAP5 code for density wave instability analysis in parallel narrow rectangular channels

Annals of Nuclear Energy, 2018
As one of the most common types of oscillatory instability, density wave oscillation (DWO) is of practical importance in the general analysis of two-phase boiling systems.
Qiang Lian, W. Tian, S. Qiu, G. Su
semanticscholar   +1 more source