Titlebook: Nuclear Simulation; Second European Nucl Moshe R. Heller Conference proceedings 1990 Springer-Verlag Berlin, Heidelberg 1990 Kernkraftwerke

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An Environment for Parallel Structuring of Fortran Programsonment are:.This paper has been structured so that the system’s capabilities are expressed through an example application involving the detection and expression of parallel program structures. Experience with this environment indicates that interactive support systems, which assist analysts in the g

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Practical Experience with Software Tools to Assess and Improve the Quality of Existing Nuclear Analynce (SQA). Most SQA techniques designed to manage the life cycle of new software development do not adequately address the risk factors of software developed before these methodologies were well-defined or practiced. By defining the risks as related to factors such as correctness, reliability, maint

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Nuclear Core and Power Plant Simulation on High Performance Parallel Computer Systemstransient conditions in the core and for the modeling of the coolant loops of light water reactors. The resulting parallel simulation program 3D-SIM is designed to run on the SUPRENUM multiprocessor system which has been accomplished as a German supercomputer project during the last few years.

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Knowledge-Based Systems to Support Dynamic Process Simulation. Combinations of numerical simulation and symbolic knowledge processing techniques have proved to be very useful for improving the adequate representation of system knowledge, the efficiency, flexibility and consistency of models and the support and advice of users in system modelling. Based on act

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Two Phase Flow Analysis Capability of Advanced Computer Codessed on the modeling of two-phase phenomena /1, 2, 3/. ABB Reaktor has investigated to what extent conventional phase-separation models are able to treat special two phase problems of a feedwater system. In comparison to this the characteristics of modern solutions with six equation models were explo

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Finite Element Weak Statement CFD Algorithms for Fluid-Thermal System Analysisble fluidthermal flow applications. Introduction of a domain discretization assists in finite element compact-support trial space basis construction. Implementation steps are highlighted for several NS reconstructions to account for the incompressibility constraint. Theoretical issues of accuracy an

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Real-Time Advanced Nuclear Reactor Core ModelLogic Systems Ltd. (KLSL). The model is based on application of modern equivalence theory to the solution of neutron diffusion equation in real time employing the finite differences method. The use of equivalence theory allows the application of the finite differences method to cores divided into hu

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