Nuclear Simulation

Welcome to Bavaria - West Germany to the SECOND EUROPEAN NUCLEAR SIMULATION SYMPOSIUM. That workshop-type meeting is a follow-up of the first Symposium which took place also at Schliersee in October 1987. The objective of gatheri ng together is to cover most of the aspects of Nuclear Mathematical Modelling and Simulation in theory and practice to promote the exchange of knowledge and experience between different national and international research groups in that field taking into con sideration that Nuclear Safety in "United Europe" turned to be a main issue. Furthermore, there is to strengthen the international contact between deve lopers and users of mode 11 i ng and simu 1 ati on techniques consi deri ng the "open" European Community borders of 1992. This triennial International Conference jointly promoted by ASIMUTH - Applied Simulation Technology and the Gesellschaft fUr Reaktorsicherheit (GRS) created an interest to publish new projects including their new results. A large number of contributed papers has been strictly examined and selected by the editorial committee to guarantee a high international technical standard. The book contai ns the accepted papers whi ch wi 11 be presented at the Symposium. The papers have been classified according to the following topics: VI 1. NUCLEAR POWER PLANT SIMULATION 2. SOFTWARE TOOLS 3. ARTIFICIAL INTELLIGENCE 4. COMPUTATIONAL FLUID DYNAMICS 5. NEUTRON KINETICS PLANT ANALYSER 6.

Inhalt
Nuclear Power Plant Simulation Session.- Experience with Simulation of Nuclear Systems on Parallel Processing Computer Systems.- A Pump Model for Use in Real-Time Simulation.- Hydraulic Network Modelling for Real-Time Power Plant Simulation with Computer Aided Code Generation.- Software Tools Session.- SIPA, a Training and Engineering Simulator and AGLAE, a Flexible Workshop for Model Generation.- An Environment for Parallel Structuring of Fortran Programs.- Advanced Modular Simulation Techniques for Nuclear Power Plants.- Practical Experience with Software Tools to Assess and Improve the Quality of Existing Nuclear Analysis and Safety Codes.- Nuclear Core and Power Plant Simulation on High Performance Parallel Computer Systems.- Artificial Intelligence Session.- Knowledge-Based Systems to Support Dynamic Process Simulation.- Computational Fluid Dynamics Session.- Two Phase Flow Analysis Capability of Advanced Computer Codes.- Finite Element Weak Statement CFD Algorithms for Fluid-Thermal System Analysis.- Neutron Kinetics Session.- Real-Time Advanced Nuclear Reactor Core Model.- The Validity of the Point Kinetics Model During Reactor Start-Up.- Axial Flux Difference on Beijing Nuclear Power Plant Simulator.- Plant Analyser Session.- APROS Nuclear Plant Analyser.- Computer Based Education Session.- Pressurised Water Reactor Simulation in the Training Environment.- A Real-Time Core Model for Nuclear Power Plant Simulators.- Nuclear Waste Session.- Ground Water Flow Analysis of Potential Low Level Radioactive Waste Disposal Sites Using Electrical Circuit Analogies.