Development of tall-3d test matrix for APROS code validation
2015 (English)In: International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015, 2015, 4562-4575 p.Conference paper (Refereed)Text
APROS code is a multifunctional process simulator which combines System Thermal-Hydraulic (STH) capabilities with ID,'3D reactor core neutronics and full automation system modeling. It is applied for various tasks throughout the complete power plant life cycle including R&D, process and control engineering, and operator training. Currently APROS is being developed for evaluation of Generation IV conceptual designs using Lead-Bismuth Eutectic (LBt) alloy coolant. TALL-3D facility has been built at KTH in order to provide validation data for standalone and coupled STH and Computational Fluid Dynamics (CFD) codes. The facility consists of sections with measured inlet and outlet conditions for separate effect and integral effect tests (SETs and lETs). The design is aimed at reducing experimental uncertainties and allowing fall separation of code validation from model input calibration. In this paper we present the development of experimental TALL-3D lest matrix for comprehensive validation of APROS code. First, the representative separate effect and integral system response quantities (SRQs) arc defined. Second, sources of uncertainties are identified and code sensitivity analysis is carried out to quantify the effects of code input uncertainties on the code prediction. Based on these results the test matrixes for calibration and validation experiments arc determined in order to minimize the code input uncertainties. The applied methodology and the results arc discussed in detail.
Place, publisher, year, edition, pages
2015. 4562-4575 p.
APROS, Dynamic process simulation, Generation IV, Lead-bismuth eutectic, Validation, Automation, Beam plasma interactions, Bismuth, Calibration, Computational fluid dynamics, Eutectics, Hydraulics, Life cycle, Nuclear reactors, Personnel training, Sensitivity analysis, Separation, Uncertainty analysis, Lead-bismuth eutectics, Codes (symbols)
IdentifiersURN: urn:nbn:se:kth:diva-187536ScopusID: 2-s2.0-84964057682ISBN: 9781510811843OAI: oai:DiVA.org:kth-187536DiVA: diva2:937907
16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2015, 30 August 2015 through 4 September 2015
Qc 201606162016-06-162016-05-252016-06-16Bibliographically approved