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

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.

[1]  Hideki Kamide,et al.  Study on mixing behavior in a tee piping and numerical analyses for evaluation of thermal striping , 2009 .

[2]  P. Roache Perspective: A Method for Uniform Reporting of Grid Refinement Studies , 1994 .

[3]  G. E. Wilson,et al.  The role of the PIRT process in experiments, code development and code applications associated with Reactor Safety analysis , 1998 .

[4]  Masaaki Tanaka,et al.  Numerical Simulations of Thermal-Mixing in T-Junction Piping System Using Large Eddy Simulation Approach , 2011 .

[5]  Hideki Kamide,et al.  Development of High Cycle Thermal Fatigue Evaluation Method Based on Time Interval of Peak-to-Peak of Fluid Temperature , 2010 .

[6]  Martin Hoekstra,et al.  Discretization Uncertainty Estimation based on a Least Squares version of the Grid Convergence Index , 2006 .

[7]  Thomas L. Saaty,et al.  DECISION MAKING WITH THE ANALYTIC HIERARCHY PROCESS , 2008 .

[8]  Won-Pil Baek,et al.  A correction method for heated length effect in critical heat flux prediction , 2000 .

[9]  Leonard E. Schwer,et al.  An overview of the PTC 60/V&V 10: guide for verification and validation in computational solid mechanics , 2007, Engineering with Computers.

[10]  Osamu Watanabe,et al.  ICONE23-1577 WATER EXPERIMENTS ON THERMAL STRIPING IN REACTOR VESSEL OF JAPAN SODIUM-COOLED FAST REACTOR : COUNTERMEASURES FOR SIGNIFICANT TEMPERATURE FLUCTUATION GENERATION , 2015 .

[11]  I. Catton,et al.  Quantifying reactor safety margins part 1: An overview of the code scaling, applicability, and uncertainty evaluation methodology , 1990 .

[12]  H. Takeda,et al.  General purpose nonlinear analysis program FINAS for elevated temperature design of FBR components. [FINAS code] , 1982 .

[13]  Masaaki Tanaka,et al.  Investigation of V&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 , 2014 .

[14]  Christopher J. Roy,et al.  Evaluation of Model Validation Techniques in the Presence of Uncertainty , 2014 .

[15]  Masaaki Tanaka,et al.  Thermal Mixing in T-Junction Piping System Related to High-Cycle Thermal Fatigue in Structure , 2010 .

[16]  Sydney J Ball,et al.  Next Generation Nuclear Plant Phenomena Identification and Ranking Tables (PIRTs) Volume 1: Main Report , 2008 .

[17]  P. Roache QUANTIFICATION OF UNCERTAINTY IN COMPUTATIONAL FLUID DYNAMICS , 1997 .

[18]  B. E. Boyack,et al.  An integrated structure and scaling methodology for severe accident technical issue resolution: Development of methodology , 1998 .

[19]  Tomoyasu Mizuno,et al.  A NEXT GENERATION SODIUM-COOLED FAST REACTOR CONCEPT AND ITS R&D PROGRAM , 2007 .