[2F_PL02] Uncertainty Quantification and Validation using Experimental Data
The reactor physics engineers and researchers have promoted the verification and validation (V&V) of the reactor analysis codes and it contributes the improvement of the reliability of these codes. Atomic Energy Society of Japan published a guideline for fidelity assessment of simulations (AESJ-SC-A008:2015) in 2015. For promoting the V&V activity using this guideline, we discuss the current status and future issues of the V&V activities.