Published April 1, 2016 | Version v1
Journal article

Development of V2UP (V&V plus uncertainty quantification and prediction) procedure for high cycle thermal fatigue in fast reactor—Framework for V&V and numerical prediction

Description

Highlights: • Proposal of a V&V and prediction procedure called as V2UP. • Introduction of framework of the V2UP. • Hierarchical classification of V&V problems. - Abstract: High cycle thermal fatigue on a structure caused by thermal striping phenomena is one of the most important issues in the design of fast breeder reactors (FBRs). In development of numerical simulation codes and in plant design and estimation by using the numerical estimation code, implementation of verification and validation (V&V) is indispensable process and also scaling issue from the subscale experiments to the full scale reactor should be considered. Therefore, a procedure called as V2UP (verification and validation plus uncertainty quantification and prediction) was made by referring to the existing guidelines on V&V (ASME V&V-10 and 20) and the methodologies of the safety assessment (CSAU, ISTIR, EMDAP). The V2UP consisted of five components as follows: (1) phenomena analysis with the Phenomena Identification and Ranking Table (PIRT) method, (2) implementation of the V&V, (3) design and rearrangement of experiments for the V&V, (4) uncertainty quantification in each problem and integration of uncertainties and (5) numerical prediction (estimation) for the target issue. Although the complete application of the procedure has not been performed at this moment, a flow chart of the V2UP procedure was described in this paper with recent results of the examinations.

Availability note (English)

Available from http://dx.doi.org/10.1016/j.nucengdes.2015.07.010

Additional details

Identifiers

DOI
10.1016/j.nucengdes.2015.07.010;
PII
S0029-5493(15)00280-0;

Publishing Information

Journal Title
Nuclear Engineering and Design
Journal Volume
299
Journal Page Range
p. 174-183
ISSN
0029-5493
CODEN
NEDEAU

Conference

Title
5. workshop on computational fluid dynamics for nuclear reactor safety
Acronym
CFD4NRS-5
Dates
9-11 Sep 2014
Place
Zurich (Switzerland)

INIS

Country of Publication
Netherlands
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
48005628
Subject category
S42: ENGINEERING; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
COMPUTERIZED SIMULATION; DIAGRAMS; FBR TYPE REACTORS; FORECASTING; IMPLEMENTATION; NUMERICAL ANALYSIS; REACTOR SAFETY; RISK ASSESSMENT; THERMAL FATIGUE; V CODES; VALIDATION; VERIFICATION
Descriptors DEC
BREEDER REACTORS; COMPUTER CODES; EPITHERMAL REACTORS; FAST REACTORS; FATIGUE; INFORMATION; MATHEMATICS; MECHANICAL PROPERTIES; REACTORS; SAFETY; SIMULATION; TESTING

Optional Information

Copyright
Copyright (c) 2015 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.