Development of a thermal–mechanical behavior coupling analysis code for a dual-cooled annular fuel element in PWRs
暂无分享,去创建一个
Dalin Zhang | Wenxi Tian | Guanghui Su | Suizheng Qiu | Yingwei Wu | Yangbin Deng | G. Su | S. Qiu | W. Tian | Dalin Zhang | Yingwei Wu | Yangbin Deng
[1] Wang Kee In,et al. Pressure drop in dual-cooled annular and cylindrical solid fuel assemblies for pressurized water reactor , 2012 .
[2] Mujid S. Kazimi,et al. Thermomechanical Performance of High-Power-Density Annular Fuel , 2007 .
[3] Tae Hyun Chun,et al. HIGH BURNUP FUEL TECHNOLOGY IN KOREA , 2008 .
[4] S. L. Solov’ev,et al. Prospects for using annular fuel elements in nuclear power engineering , 2010 .
[5] Youn Ho Jung,et al. RAPID model to predict radial burnup distribution in LWR UO2 fuel , 2000 .
[6] Yong Sik Yang,et al. A New Mechanistic and Engineering Fission Gas Release Model for a Uranium Dioxide Fuel , 2008 .
[7] Ali R Massih,et al. Models for fuel rod behaviour at high burnup , 2005 .
[8] K. Lassmann,et al. TRANSURANUS: a fuel rod analysis code ready for use , 1992 .
[9] J. Jacoud,et al. An efficient model for the analysis of fission gas release , 2002 .
[10] Pekka Lösönen,et al. Modelling intragranular fission gas release in irradiation of sintered LWR UO2 fuel , 2002 .
[11] D. D. Lanning,et al. FRAPCON-3: A computer code for the calculation of steady-state, thermal-mechanical behavior of oxide fuel rods for high burnup , 1997 .
[12] Mujid S. Kazimi,et al. Annular Fuel for High-Power-Density Pressurized Water Reactors: Motivation and Overview , 2007 .
[13] T. Nakajima,et al. A comparison between fission gas release data and FEMAXI-IV code calculations , 1987 .
[14] Ju-Yong Park,et al. Pressure loss coefficient and flow rate of side hole in a lower end plug for dual-cooled annular nuclear fuel , 2013 .
[15] Yi Yuan. The design of high power density annular fuel for LWRs , 2004 .
[16] Julien Beccherle,et al. High-Power-Density Annular Fuel for Pressurized Water Reactors: Manufacturing Costs and Economic Benefits , 2007 .