Uncertainty quantification of BWR core characteristics due to uncertainty of void correlations

Motohiro Ito

Presentation information

Oral presentation

III. Fission Energy Engineering » 301-1 Reactor Physics, Utilization of Nuclear Data, Criticality Safety

[2F01-05] Uncertainty Evaluation 2

Tue. Mar 27, 2018 9:30 AM - 10:50 AM Room F (U2-211 -U2 Building)

Chair: Go Chiba (Hokkaido Univ.)

9:30 AM - 9:45 AM

[2F01] Uncertainty quantification of BWR core characteristics due to uncertainty of void correlations

*Motohiro Ito¹, Akio Yamamoto¹, Tomohiro Endo¹, Takashi Yoshii², Tsuyoshi Ama² (1. Nagoya Univ., 2. TEPCO SYSTEMS)

Keywords:void correlations, thermal hydraulic, uncertainty analysis, core characteristics, BWR

Core characteristics of BWR are significantly affected by the thermal-hydraulics calculations. Uncertainty of core characteristics of a BWR core due to uncertainty of void correlations is quantitatively estimated by the random sampling method.