Review of the experimental research on the thermal‐hydraulic characteristics in the pebble bed nuclear reactor core and fusion breeder blanketsLimin Liu, Hanyang Gu, Jian Deng et al.|International Journal of Energy Research|2020Cited by 25
Study on two-phase flow instability of parallel helical tubes in steam generator of small modular reactorsCong Shen, Hanyang Gu, Limin Liu et al.|International Communications in Heat and Mass Transfer|2023Cited by 23
Preliminary thermal and mechanical analysis on the reactor core of a new heat pipe cooled reactor applied in the underwater environmentLimin Liu, Hui Guo, Бо Лю et al.|Progress in Nuclear Energy|2022Cited by 22
Development of one-dimensional transient model for predicting flow instability at supercritical pressuresJiayue Chen, Zhenqin Xiong, Hanyang Gu|Progress in Nuclear Energy|2018Cited by 21
Experimental investigation on heat transfer behavior in a tight 19 rod bundle cooled with supercritical R134aJiayue Chen, Hanyang Gu, Zhenqin Xiong|Annals of Nuclear Energy|2018Cited by 19