Published November 2014 | Version v1
Journal article

Investigation of V and V process for thermal fatigue issue in a sodium cooled fast reactor – Application of uncertainty quantification scheme in verification and validation with fluid-structure thermal interaction problem in T-junction piping system

Description

Highlights: • Outline of numerical simulation code MUGTHES for fluid-structure thermal interaction was described. • The grid convergence index (GCI) method was applied according to the ASME V and V-20 guide. • Uncertainty of MUGTHES can be successfully quantified for thermal-hydraulic problems and unsteady heat conduction problems in the structure. • Validation for fluid-structure thermal interaction problem in a T-junction piping system was well conducted. - Abstract: Thermal fatigue caused by thermal mixing phenomena is one of the most important issues in design and safety assessment of fast breeder reactors. A numerical simulation code MUGTHES consisting of two calculation modules for unsteady thermal-hydraulics analysis and unsteady heat conduction analysis in structure has been developed to predict thermal mixing phenomena and to estimate thermal response of structure under the thermal interaction between fluid and structure fields. Although verification and validation (V and V) of MUGTHES has been required, actual procedure for uncertainty quantification is not fixed yet. In order to specify an actual procedure of V and V, uncertainty quantifications with the grid convergence index (GCI) estimation according to the existing guidelines were conducted in fundamental laminar flow problems for the thermal-hydraulics analysis module, and also uncertainty for the structure heat conduction analysis module and conjugate heat transfer model was quantified in comparison with the theoretical solutions of unsteady heat conduction problems. After the verification, MUGTHES was validated for a practical fluid-structure thermal interaction problem in T-junction piping system compared with measured results of velocity and temperatures of fluid and structure. Through the numerical simulations in the verification and validation, uncertainty of the code was successfully estimated and applicability of the code to the thermal fatigue issue was confirmed

Availability note (English)

Available from http://dx.doi.org/10.1016/j.nucengdes.2014.03.006

Additional details

Identifiers

DOI
10.1016/j.nucengdes.2014.03.006;
PII
S0029-5493(14)00138-1;

Publishing Information

Journal Title
Nuclear Engineering and Design
Journal Volume
279
Journal Page Range
p. 91-103
ISSN
0029-5493
CODEN
NEDEAU

INIS

Country of Publication
Netherlands
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
46100754
Subject category
S42: ENGINEERING;
Descriptors DEI
COMPUTERIZED SIMULATION; DESIGN; FLUIDS; GRIDS; RISK ASSESSMENT; SODIUM COOLED REACTORS; THERMAL CONDUCTION; THERMAL FATIGUE; THERMAL HYDRAULICS; VERIFICATION
Descriptors DEC
ELECTRODES; ENERGY TRANSFER; FATIGUE; FLUID MECHANICS; HEAT TRANSFER; HYDRAULICS; LIQUID METAL COOLED REACTORS; MECHANICAL PROPERTIES; MECHANICS; REACTORS; SIMULATION

Optional Information

Copyright
Copyright (c) 2014 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.