Comparative analysis of neutronics/thermal-hydraulics multi-scale coupling for LWR analysis
نویسندگان
چکیده
The aim of the research described in this paper is to perform consistent comparative analyses of two different approaches for coupling of two-scale, two-physics phenomena in reactor core calculations. The physical phenomena of interest are the neutronics and the thermal-hydraulics core behaviors and their interactions, while the spatial scales are the “global” (assembly/channel-wise) and the “local” (pin/sub-channelwise). The objective is three-fold: qualification of coupled code systems by consistent step-by-step crosscomparison (in order to understand the prediction deviations in both neutronics and thermal-hydraulics parameters); assessment of fine scale (local/subchannel-wise) thermal-hydraulic effects; and evaluation of the impact of on-line modeling of interactions of the two spatial scales. The reported work is within the cooperation between the Universidad Politécnica de Madrid (UPM), Spain and the Pennsylvania State University (PSU), USA. The paper first presents the two multi-scale coupled code systems followed by cross-comparisons for steady state calculations. Selected results are discussed to highlight some of the issues involved in comparative analysis of coupled multi-scale simulations. The transient comparisons are subject of future work and publications. * Corresponding author, [email protected] Tel: +34 91 336 3108; Fax: +34 91 336 3102
منابع مشابه
Status Report on SHARP Coupling Framework
This report presents the software engineering effort under way at ANL towards a comprehensive integrated computational framework (SHARP) for high fidelity simulations of sodium cooled fast reactors. The primary objective of this framework is to provide accurate and flexible analysis tools to nuclear reactor designers by simulating multiphysics phenomena happening in complex reactor geometries. ...
متن کاملInvestigation of efficient and reliable numerical algorithms for coupled reactor calculations X-TREAM project: Task 1b Survey of the state-of-the-art numerical techniques for solving coupled non-linear multi-physics equations
Nowadays, the precise modeling of a nuclear reactor core is a challenge. This task involves several aspects, from the computational power needed to perform simulations, to the physics and analysis of the outcome. The need to better understand the physical phenomena is critical in order to quantify and qualify nuclear safety parameters. Currently, substantial research has been done in order to o...
متن کاملNeutronics/Thermal-hydraulics Coupling in LWR Technology, Vol. 1 CRISSUE-S - WP1: Data Requirements and Databases Needed for Transient Simulations and Qualification 5th Euratom Framework Programme (1998-2002)
Pursuant to Article 1 of the Convention signed in Paris on 14 th December 1960, and which came into force on 30 th September 1961, the Organisation for Economic Cooperation and Development (OECD) shall promote policies designed: to achieve the highest sustainable economic growth and employment and a rising standard of living in member countries, while maintaining financial stability, and thus t...
متن کاملScalable Parallel Solution Coupling for Multi-Physics Reactor Simulation
Reactor simulation depends on the coupled solution of various physics types, including neutronics, thermal/hydraulics, and structural mechanics. This paper describes the formulation and implementation of a parallel solution coupling capability being developed for reactor simulation. The coupling process consists of mesh and coupler initialization, point location, field interpolation, and field ...
متن کاملThermal-Hydraulics analysis of pressurized water reactor core by using single heated channel model
Thermal hydraulics of nuclear reactor as a basis of reactor safety has a very important role in reactor design and control. The thermal-hydraulic analysis provides input data to the reactor-physics analysis, whereas the latter gives information about the distribution of heat sources, which is needed to perform the thermal-hydraulic analysis. In this study single heated channel model as a very f...
متن کامل