Thermal hydraulic analysis of a pebble-bed modular high temperature gas-cooled reactor with ATTICA3D and THERMIX codes
暂无分享,去创建一个
Eckart Laurien | Yanhua Zheng | J. Lapins | Lei Shi | Zhengming Zhang | J. Lapins | Lei Shi | Yanhua Zheng | Zhengming Zhang | E. Laurien
[1] H. Haque. Consequences of delayed air ingress following a depressurization accident in a high temperature reactor , 2008 .
[2] Zuoyi Zhang,et al. Economic potential of modular reactor nuclear power plants based on the Chinese HTR-PM project , 2007 .
[3] Lei Shi,et al. Thermohydraulic transient studies of the Chinese 200 MWe HTR-PM for loss of forced cooling accidents , 2009 .
[4] Kaifen Zuo,et al. Overview of the 10 MW high temperature gas cooled reactor—test module project , 2002 .
[5] Lei Shi,et al. A Personal Computer-Based Simulation-and-Control-Integrated Platform for 10-MW High-Temperature Gas-Cooled Reactor , 2004 .
[6] Eckart Laurien,et al. The 3-D time-dependent transport code TORT-TD and its coupling with the 3D thermal-hydraulic code ATTICA3D for HTGR applications , 2012 .
[7] Günter Lohnert,et al. TH3D: A Three-Dimensional Thermal Hydraulic Tool for Design and Safety Analysis of HTRs , 2008 .
[8] Günter Lohnert,et al. Development of a fast 3D thermal-hydraulic tool for design and safety studies for HTRS , 2008 .
[9] N. Kohtz,et al. Meeting fuel temperature limits in an HTR-Module Reactor during depressurized core heat-up , 1992 .
[10] S. R. Greene,et al. Application of THERMIX-KONVEK code to accident analyses of modular pebble bed high temperature reactors (HTRs) , 1986 .
[11] H. Gerwin,et al. The TINTE Modular Code System for Computational Simulation of Transient Processes in the Primary Circuit of a Pebble-Bed High-Temperature Gas-Cooled Reactor , 1989 .