검색결과 : 6건
No. | Article |
---|---|
1 |
Sub-channel-based multiscale thermal-hydraulic analysis of a medium-power, lead-cooled fast reactor Cao LK, Zhang XL, Chen HL International Journal of Energy Research, 44(7), 5305, 2020 |
2 |
Neutronic/thermal-hydraulic design features of an improved lead-bismuth cooled small modular fast reactor Wei SY, Sun H, Wang CL, Chen RH, Tian WX, Qiu SZ, Su GH International Journal of Energy Research, 43(8), 3794, 2019 |
3 |
Design and thermal-hydraulic evaluation of helium-cooled ceramic breeder blanket for China fusion engineering test reactor Lei MZ, Xu SL, Guo C, Liu SM, Song YT, Lu K, Pei K, Xu K International Journal of Energy Research, 42(4), 1657, 2018 |
4 |
Thermal-hydraulic analysis of nanofluids as the coolant in supercritical water reactors Rahimi MH, Jahanfamia G, Vosoughi N Journal of Supercritical Fluids, 128, 47, 2017 |
5 |
Thermal hydraulic analysis of the HECLIC blanket breeder unit for CFETR Lei MZ, Song YT, Ye MY International Journal of Energy Research, 39(3), 370, 2015 |
6 |
Subchannel analysis of nanofluids application to VVER-1000 reactor Zarifi E, Jahanfarnia G, Veysi F Chemical Engineering Research & Design, 91(4), 625, 2013 |