Search Results - "HU Yousen"

Experimental study on friction pressure drop and circumferential heat transfer characteristics in helical tubes by Zheng, Xiong, Lu, Xianghui, Gao, Yaxin, Jin, Desheng, Hu, Yisong, Hu, Yousen, Mao, Yulong

“…Helical tubes are widely used in nuclear plants, heat recovery process, and refrigeration technology. The fluid is influenced by centrifugal force flow through…”
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Experimental study on helical tubes heat transfer characteristics considering corrosion products by Yulong, Mao, Shuqi, Meng, Xianghui, Lu, Desheng, Jin, Xiaoting, Wang, Kejia, Li, Yisong, Hu, Yousen, Hu, Min, Rui

“…During the power operation of nuclear reactors, the corrosion products in the secondary circuit will deposit on the inside of Helical-coiled One-Through Steam…”
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Research of Thermal Hydraulic Conditions Effect on PWR CIPS Risk by Meng, Shuqi, Yan, Yalun, Hu, Yousen, Hu, Yisong, Ruan, Tianming

“…In order to reveal the effect of thermal hydraulic conditions on the PWR CIPS risk, the evaluation of a PWR CIPS risk in the first cycle under different core…”
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Corrosion release behavior of alloy 690 and its application in high-temperature water with Zn injection by Liao, Jiapeng, Hu, Yousen, Li, Jinggang, Jin, Desheng, Meng, Shuqi, Ruan, Tianming, Hu, Yisong, Zhang, Ziyu

“…Corrosion release behavior of Alloy 690 in high-temperature water was investigated under the conditions of injected Zn concentrations of 0 ppb, 10 ppb and…”
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Study on physical prediction model of liquid film development and dry out point in helical tube by Rui, Min, Chen, Tianming, Zhou, Mingjia, Zheng, Xiong, Hu, Yisong, Jin, Desheng, Hu, Yousen, Mao, Yulong

“…Helical tubes are widely used in nuclear plants, heat recovery process, refrigeration technology, etc. It is obtained the helical tubes dry out point…”
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Corrosion release behavior of alloy 690 and its application in high-temperature water with Zn injection by Liao, Jiapeng, Hu, Yousen, Li, Jinggang, Jin, Desheng, Meng, Shuqi, Ruan, Tianming, Hu, Yisong, Zhang, Ziyu

“…Corrosion release behavior of Alloy 690 in high-temperature water was investigated under the conditions of injected Zn concentrations of 0 ppb, 10 ppb and 50…”
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注锌对压水堆锆合金表面污垢的影响研究 by 胡艺嵩, 毛玉龙, 胡友森, 阮天鸣, 蒙舒祺

“…TL341; 腐蚀产物在压水堆(Pressurized Water Reactor,PWR)锆合金表面沉积后会形成污垢(Chalk Rivers Unidentified…”
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堆芯功率变化对燃料包壳表面污垢沉积行为的影响研究 by 廖家鹏, 叶杰, 金德升, 商超皓, 胡友森

“…TL38+2;…”
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注锌对燃料包壳表面污垢沉积及硼析出的影响研究 by 廖家鹏, 毛玉龙, 阮天鸣, 胡友森, 金德升, 厉井钢, 陈忠村

“…TL341;…”
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Effect of Zinc injection on the surface CRUD of PWR zirconium alloy by HU Yisong, MAO Yulong, HU Yousen, RUAN Tianming, MENG Shuqi

“…BackgroundThe corrosion products deposited on the surface of pressurized water reactor (PWR) zirconium alloy will form chalk rivers unidentified deposit…”
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Effect of core power variation on crud deposition behavior on fuel cladding surface by LIAO Jiapeng, YE Jie, JIN Desheng, SHANG Chaohao, HU Yousen

“…BackgroundFor a pressurized water reactor (PWR), under the synthesis effects of primary water chemistry, reactor operation mode, system facilities replacement,…”
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Effect of zinc injection on crud deposition and boron precipitation on fuel cladding surface by LIAO Jiapeng, MAO Yulong, RUAN Tianming, HU Yousen, JIN Desheng, LI Jinggang, CHEN Zhongcun

“…BackgroundUnder the condition of sub-cooled nucleate boiling (SNB), corrosion products in primary coolant of nuclear reactor will deposit on the outer surface…”
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