Assessing the applicability of the ASME V&V20 standard for uncertainty quantification of CFD in nuclear systems fluid modeling
Name
1011422494-MIT.pdf
Description
Full printable version
Size
3.9 MB
Format
Adobe PDF
Checksum (MD5)
d79fa5f14d29ed8a94043466855943ac
Author(s)
Alvarez, Andres Felipe, S.B. Massachusetts Institute of Technology
Advisor(s)
Emilio Baglietto.
Date Issued
2017
Publisher
Massachusetts Institute of Technology
Abstract
Advanced modelIng and sImulatIon (M&S) of nuclear systems could offer a key contrIbutIon In enhancIng the competItIveness and safety performance of nuclear power plants. Large multI-organIzatIonal InItIatIves such as the ConsortIum for Advanced SImulatIon of LIght Water Reactors (CASL) and the Nuclear Energy Advanced ModelIng and SImulatIon (NEAMS) emphasIzes the Importance of M&S research to the U.S. nuclear Industry. UncertaInty QuantIfIcatIon (UQ) represents a fundamental area of research necessary to expand the applIcatIon of M&S Into nuclear Industry, but the fIeld Is stIll not mature, and no general consensus exIsts on current UQ methods. In thIs study, the ASME V&V20 I a proposed methodology for UQ of CFD -- Is applIed to a benchmark nuclear system turbulent mIxIng case In an effort to assess the applIcabIlIty and lImItatIons of the standard.
Description
Thesis: S.B., Massachusetts Institute of Technology, Department of Nuclear Science and Engineering, 2017.
This electronic version was submitted by the student author. The certified thesis is available in the Institute Archives and Special Collections.
Cataloged from student-submitted PDF version of thesis.
Includes bibliographical references (pages 73-76).
Subjects
Nuclear Science and Engineering.
MIT Department
Massachusetts Institute of Technology. Department of Nuclear Science and Engineering
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