ULOF and UTOP Analyses of a Large Metal Fuel FBR Core Using a Detailed Calculation System

概要

論文の詳細を見る
ULOF and UTOP analyses of a large metal fuel FBR core (1,500 MWe, averaged discharge burnup: 150 GWd/t) are conducted. The effect of core radial expansion is considered as the major negative feedback during the transient. A detailed analysis system is used, in which a transient core thermal-hydraulic code is coupled with three dimensional core radial deformation and reactivity feedback calculation codes, in order to calculate the radial expansion feedback. In ULOF analysis, the pump flow halving time is assumed to be 10 s, which is reasonably long and effective in avoiding too large power to flow ratio. The reactivity insertion during UTOP is set to be 34\\slash{c}, based on the control rod reactivity design. As the analysis results, it is found that the core shows benign responses to both events, owing largely to the radial expansion feedback. No significant coolant boiling or fuel failure is predicted. The response during ULOF is compared to that of an oxide fuel core of similar design, and it is confirmed that the negative Doppler effect associated with the fuel temperature rise plays the major role in the quick power decrease.
社団法人日本原子力学会の論文
2001-06-25