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
暂无分享,去创建一个
[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 .