Development and Application of an Engineering Simulator for HTR-PM Using THERMIX/BLAST and vPower
暂无分享,去创建一个
[1] Zuoyi Zhang,et al. Economic potential of modular reactor nuclear power plants based on the Chinese HTR-PM project , 2007 .
[2] Zhongwei Zhang,et al. Development and application of a deterministic-realistic hybrid methodology for LOCA licensing analysis , 2011 .
[3] William D. Fullmer,et al. Experimental Validation of RELAP5 and TRACE5 for Licensing Studies of the Boron Injection System of Atucha II , 2011 .
[4] Kaifen Zuo,et al. Overview of the 10 MW high temperature gas cooled reactor—test module project , 2002 .
[5] Egon Ziermann. Review of 21 years of power operation at the AVR experimental nuclear power station in Jülich , 1990 .
[6] Lei Shi,et al. Thermohydraulic transient studies of the Chinese 200 MWe HTR-PM for loss of forced cooling accidents , 2009 .
[7] Jie Liu,et al. A Personal Computer-Based Simulator for Nuclear-Heating Reactors , 2000 .
[8] Yujie Dong,et al. Current status and technical description of Chinese 2 × 250 MWth HTR-PM demonstration plant , 2009 .
[9] R. A. Hedrick,et al. BLAST: a digital computer program for the dynamic simulation of the high temperature gas cooled reactor reheater-steam generator module , 1976 .
[10] Thomas K.S. Liang,et al. Development and application of a dual RELAP5-3D-based engineering simulator for ABWR , 2009 .
[11] Robert Luh,et al. The Operator Training Simulator System for the Pebble Bed Modular Reactor (PBMR) Plant , 2008 .
[12] Yujie Dong,et al. Assessments of Water Ingress Accidents in a Modular High-Temperature Gas-Cooled Reactor , 2005 .
[13] Lei Shi,et al. A Personal Computer-Based Simulation-and-Control-Integrated Platform for 10-MW High-Temperature Gas-Cooled Reactor , 2004 .
[14] Yanhua Zheng,et al. Post-test analysis of helium circulator trip without scram at 3 MW power level on the HTR-10 , 2009 .
[15] L. Wolf,et al. High temperature reactor core physics and reactor dynamics , 1990 .
[16] S. R. Greene,et al. Application of THERMIX-KONVEK code to accident analyses of modular pebble bed high temperature reactors (HTRs) , 1986 .
[17] Francesco Saverio D'Auria,et al. The Best Estimate Plus Uncertainty Challenge in the Current Licensing Process of Present Reactors , 2011 .
[18] Li Shi,et al. Safety Analysis for Hot Gas Duct Vessel in HTR-PM , 2011 .
[19] Zhiwei Zhou,et al. HTR-PM Simulation Analysis of Accident Conditions Based on vPower Platform , 2014 .
[20] Yangping Zhou,et al. Thermal hydraulic simulation of reactor of HTR-PM based on thermal-fluid network and SIMPLE algorithm , 2013 .
[21] Zongxin Wu,et al. The design features of the HTR-10 , 2002 .
[22] M. Ding,et al. Evaluation of experiments in the AVR with the DALTON-THERMIX coupled code system , 2009 .
[23] Yang Tang,et al. Improving Thermal-Hydraulic Calculation Modules of THERMIX Code Based on LU Decomposition , 2013 .
[24] Eckart Laurien,et al. Thermal hydraulic analysis of a pebble-bed modular high temperature gas-cooled reactor with ATTICA3D and THERMIX codes , 2012 .
[25] Fu Li,et al. Design aspects of the Chinese modular high-temperature gas-cooled reactor HTR-PM , 2006 .
[26] Yujie Dong,et al. Thermal-hydraulic feasibility analysis on uprating the HTR-PM , 2006 .
[27] Francesco Saverio D'Auria,et al. Development and Application of MCNP5 and KENO-VI Monte Carlo Models for the Atucha-2 PHWR Analysis , 2009 .
[28] Zhou Zhi-wei,et al. Simulation for the Secondary Loop of the Chinese 200Mwe HTR-PM Base on Vpower , 2012 .