Nuclear Power Technology Development
Ottawa, Canada
Workshop on Advanced Code Suite for Design, Safety Analysis and Operation of Heavy Water Reactors
This page contains the most up-to-date information and materials regarding the event to assist participants in their preparations. Please visit this page regularly, as new and revised materials will be uploaded here as they become available.
Working Documents
Presentations
Session I: Reactor Physics
Challenges and Future Needs for Independent Reactor Physics Simulations – CNSC Approach and Practice
Mr Dumitru SERGHIUTA, CNSC, CanadaNeutron Code PUMA for fuel management, stationary and spatial kinetic reactor simulation – Cell Code HUEMUL for cell and multicell calculation
Mr Carlos Rodolfo GRANT, CNEA, ArgentinaCANDU refuelling optimization by successive two-step mathematical programming
Mr Wencong WANG, TQNPC, ChinaMonte Carlo Re-evaluation of CANDU 6 Physics Parameters
Mr Yonghee KIM, KAIST, KoreaDevelopment of 3D Space Time Kinetics Model for Coupled Neutron Kinetics and Thermalhydraulics
Mr Manual Philip Soris FERNANDO, NPCIL, IndiaAECL’s Next-Generation Reactor Physics Development Program
Mr Alexandre TROTTIER, AECL, CanadaMulti-physics and Multi-scale Integrated Simulation of Nuclear Reactors
Mr Vikas JAIN, BARC, India
Session II: Thermalhydraulics and Coupling with Physics
CATHENA 4: A Thermalhydraulics Network Analysis Code
Mr Nusret AYDEMIR, AECL, CanadaModeling of Thermalhydraulics-Neutronics Phenomena for Design & Safety Analysis of PHWR
Mr Rammohan Parthasarathy HONNALAGERE, NPCIL, IndiaINR Coupled Reactor Physics and Thermal Hydraulic Calculation System for CANDU Reactor
Mr Ilie PATRULESCU, INR, Romania
Session III: Safety Analysis
Development of a Suite of Advanced Safety Analysis Codes at AECL
Mr Glen MCGEE, AECL, CanadaHWR Computer Code Developments in Korea
Mr Joo Hwan PARK, KAERI, KoreaDevelopments in AECL’s Next Generation Code Suite Coupling (Backbone)
Mr David CASWELL, AECL, CanadaRomanian Approach Regarding the Computer Codes Used for Safety Analysis of Nuclear Power Plants
Ms Elena DINCA, CNCAN, Romania
Session IV: Fuel and Coupling with Physics
Advances in Modelling of Fuel Behaviour in CANDU Reactors
Mr Zhen XU, CEI, CanadaEnhancement of Computer Systems for CANDU Reactor Fuel and Physics Simulation
Ms Elisabeth VARIN, CEI, CanadaApplication of Commercial Finite Element Codes to Modeling Fuel Thermal-Mechanical Behaviour
Mr Jeffrey BASCHUK, AECL, Canada
Session V: Generals
Development of software SECTOREM-3 for prediction of sector emergency and intervention level
Mr Muharmmad AKRAM, KANUPP, PakistanCoarse Mesh Radiation Transport Code COMET for Whole-Core Neutronics Analysis
Mr Farzad RAHNEMA, GIT, USADevelopment of a Simplified Generic PRA Model for Regulatory Application
Mr Amin PATEL, CNSC, Canada
Please contact NENP Technology Development Section - Contact Point if you have any questions.
