کد مقاله | کد نشریه | سال انتشار | مقاله انگلیسی | نسخه تمام متن |
---|---|---|---|---|
1728020 | 1521100 | 2016 | 4 صفحه PDF | دانلود رایگان |
• Application of nanofluid as a complement to the safety systems during normal operation.
• Using nanofluid as the means of reactivity control instead of boric acid.
• Evaluation of critical nanofluid concentration at the beginning of cycle for a VVER-1000 core.
• Coupling detailed fluid dynamic and neutronics calculations to achieve core criticality with the fresh fuel.
The use of nanofluid as a dual heat transfer enhancer and excess reactivity controller in a typical pressurized power reactor (PWR) is the focus of this study. Presently, boric acid is the dominant method for reactivity control in PWRs and Chemical & Volume Control System (CVCS) controls the boric acid concentration during reactor operation. In this study, we have replaced the coolant fluid of the first loop with a nanofluid which act as coolant, neutron moderator and neutron absorber. A full core of VVER-1000 as a typical PWR system is modeled with coupled neutronics and fluid dynamic codes. Among five nanofluids investigated, 2% volume fraction silver oxide is found to satisfy both neutronics and thermohydraulics safety margins of VVER-1000 nuclear reactor.
Journal: Annals of Nuclear Energy - Volume 97, November 2016, Pages 179–182