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Tham khảo tài liệu 'nuclear power system simulations and operation part 9', kỹ thuật - công nghệ, cơ khí - chế tạo máy phục vụ nhu cầu học tập, nghiên cứu và làm việc hiệu quả | A Literature Survey of Neutronic and Thermal-Hydraulics Codes for Investigating Reactor Core Parameters Artificial Neural Networks as the VVER-1000 Core Predictor 109 No. Title and authors Coupled codes NPP Transient type ef. 11 Analysis of a Boron Dilution Accident for VVER-440 Combining the Use of the Codes DYN3D and SiTap U. Rohde I. Elkin V. Kalinenko SiTap dyn3d VVER 440 RIA 12 RELAP5-PANTHER Coupled Code Transient Analysis B.J. Holmes G.R. Kimber J.N. Lillington M.R. Parkes RELAP5 PANTHER PWR Sizewell-B Grid frequency error injection test Single turbine trip event 13 TACIS R2.30 94 Project Transient Analysis for RBMK Reactors H. Schoels Yu. M. Nikitin Nikiet FLICA GIDRA SADC DINAO CRONOS QUABOX CUBOX RBMK Smolensk 3 RIA 14 PWR Anticipated Transients Without SCRAM Analyses Using PVM Coupled RETRAN and STAR 3-D Kinetics Codes M. Feltus K. Labowski RETRAN STAR 3-D PWR ATWS 15 Development and First Results of Coupled Neutronic and Thermal-hydraulics Calculations for the High -performance LWR C.H.M. Broeders V. Sanchez-Espinoza A. Travleev RELAP5 KAPROS HPLWR FA tests 16 Analysis and Calculation of an Accident with Delayed Scram on NPP Greifswald using the Coupled Code DYN3D-AtHLET S. Kliem ATHLET DYN3D VVER-440 Greifswald Delayed scram 17 Multi-dimensional TMI-1 Main Steam Line Break Analysis Methodology using TRAC-PF NEM K. Ivanov T. Beam A. Baratta A. Irani N. Trikouros TRAC-PF NEM PWR B W TMI-1 MSLB 18 Realistic and Conservative Rod Ejection Simulation in a PWR Core at HZP EOC with Coupled PARCS and RELAP Codes J. Riverola T. Nunez J. Vicente RELAP PARCS Three-loop PWR Peripheral rod ejection 19 OECD NRC BWR Benchmark 3rd Workshop ATHLET QUABOX CUBBOX BWR Peach Bottom TT ATWS Anticipated Transient without Scram RIA Reactivity Induced Accident REA Rod Ejection Accident MCP Main Coolant Pump LOFW Loss Of proper Feed Water Table l. continues Overview of 3-D coupled neutronics thermal-hydraulics calculations available from the literature 110 Nuclear Power - System
