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Thermal consideration of CANDU-SCWR sliding pressure startup through subchannel analysis |
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| Authors: | Jianqiang Shan Junjie Pan Yang Jiang |
| Affiliation: | School of Nuclear Science and Technology, Xi’an Jiaotong University, Xianning West Rd 28, Xi’an 710049, Shaanxi, China |
| Abstract: | A startup system and startup procedures are designed based on the subchannel analysis for CANDU-SCWR sliding pressure startup. Lookup tables are selected to predict the CHF and PDO heat transfer due to their wide application range. Plant parameters are analyzed in detail. The results show that the maximum cladding surface temperature can be well restricted lower than criterion (850 °C), and the proposed startup procedure is feasible for CANDU-SCWR from the point of view of thermal-hydraulics. |
| Keywords: | ATHAS advanced thermal-hydraulics analysis subchannel BWR boiling water reactor CANDU CANada Deuterium Uranium CHF critical heat flux FPP fossilfired power plant LWR light water reactor PDO post-dry out PHWR pressurized heavy water reactor PWR pressurized water reactor SCWR supercritical water-cooled reactor SCFR supercritical water-cooled fast reactor (designed in Japan) CANFLEX CANada FLEXible fueling RBMK reactor of large capacity channel type (in Russian abbreviations) |
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