Neutronics and thermal hydraulic coupling analysis of integrated pressurized water reactor-Reference-Cited by-同舟云学术

Neutronics and thermal hydraulic coupling analysis of integrated pressurized water reactor

Published:2012-11-20 Issue:13 Volume:37 Page:1709-1717
ISSN:0363-907X
Container-title:International Journal of Energy Research
language:en
Short-container-title:Int. J. Energy Res.

Author:

Khan Salah Ud-Din¹,Peng Minjun²,Khan Shahab Ud-Din³

Affiliation:

1. Sustainable Energy Technologies Center; King Saud University; Riyadh; 11421; Kingdom of Saudi Arabia

2. Nuclear Power Simulation and Research Center, College of Nuclear Science and Technology; Harbin Engineering University; Harbin; 150001; P.R. China

3. College of Mathematics and Statistics; Chongqing University; Chongqing; 400044; P.R. China

Publisher

Wiley

Subject

Energy Engineering and Power Technology,Fuel Technology,Nuclear Energy and Engineering,Renewable Energy, Sustainability and the Environment

Reference18 articles.

1. Analysis of the Boiling Water Reactor Turbine Trip Benchmark with the Codes DYN3D and ATHLET/DYN3D;Ulrich;Nuclear Science and Engineering,2004

2. Asaka H Zimin VG Iguchi T Anoda Y Coupling of the thermal hydraulics TRAC codes with 3D Neutron Kinetic codes SKETCH-N Proceedings of the OECD/CSNI workshop on Advanced thermal hydraulic neutron kinetic codes: current and future applications Barcelona, Spain 2000 1 15

3. Features and performance of Three dimensional Thermal Hydraulic/kinetic TRAC-PF1/NEM PWR analysis code;Ivano;Annals of Nuclear Energy,1999

4. Analysis of the OECD/NRC BWR Turbine Trip Benchmark by the Coupled-Code System ATHLET-QUABOX/CUBBOX;Langenbuch;Nuclear Science and Engineering,2004

5. Analysis of the OECD/NEA PWR Main Steam Line Break (MSLB) Benchmark Exercise 3 with the Coupled Code System RELAP5/PANBOX;Espinoza;FZKA: Forschungszentrum Karlsruhe,2002

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