DRAFT: THERMAL-HYDRAULIC MODELING OF CANDU-SCWR AND LINEAR DYNAMIC MODEL DEVELOPMENT
CANDU-SCWR is one Generation IV reactor being developed in Canada. Significant amount of efforts has been made to develop CANDU-SCWR. Little work has been done on the dynamic analysis and control design. To observe the dynamic behaviours of CANDU-SCWR, the detailed CANDU-SCWR thermal-hydraulic model is developed. The movable boundary method is adopted for CANDU-SCWR thermal-hydraulic modeling. The benefits of adopting movable boundary are derived from the comparisons with the fixed boundary method. The steady-state results agree well with the design data. The responses of CANDU-SCWR reactor to different disturbances are simulated and analyzed and the results are reasonable in theory. Linear dynamic models are derived from simulation data of CANDU-SCWR thermal-hydraulic model around the design operating point using a system identification technique to facilitate the control system design. The linear dynamic models are validated and it is shown that they can describe the dynamic characteristics of CANDU-SCWR around the design point accurately.
Peiwei Sun Jin Jiang
Department of Electrical and Computer Engineering University of Western Ontario London, Ontario, N6A Institute of Nuclear Science and Technology Xi’an Jiaotong University Xi’an, Shaanxi, 710049, China
国际会议
18th International Conference on Nuclear Engineering(第18届国际核能工程大会 ICONE 18)
西安
英文
1-9
2010-05-17（万方平台首次上网日期，不代表论文的发表时间）