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NUCLEAR TECHNIQUES
Editors-in-Chief
Yugang MA
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Characteristics of heat transfer and pressure boosting in high-pressure water injecting into liquid lead-bismuthNUCLEAR ENERGY SCIENCE AND ENGINEERING
Han HU... Gen LI and Xiaowen LIANG|Show fewer author(s)
Apr. 15, 2025NUCLEAR TECHNIQUES
DOI：10.11889/j.0253-3219.2025.hjs.48.230493
Characteristics of heat transfer and pressure boosting in high-pressure water injecting into liquid lead-bismuth
Development of the neutronics calculation module of neutronics and thermal hydraulic calculation program NECP-Panda for pebble-bed high temperature gas-cooled reactorNUCLEAR ENERGY SCIENCE AND ENGINEERING
Yuxuan WU... Yongping WANG, Shuai QIN, Liangzhi CAO, Hongchun WU and Yong LUO|Show fewer author(s)
Apr. 15, 2025NUCLEAR TECHNIQUES
DOI：10.11889/j.0253-3219.2025.hjs.48.230471
Development of the neutronics calculation module of neutronics and thermal hydraulic calculation program NECP-Panda for pebble-bed high temperature gas-cooled reactor
Flow field characteristics of the mixing vane in the fuel rod bundle region of a pressurized water reactorNUCLEAR ENERGY SCIENCE AND ENGINEERING
Xiaoqing CHEN... Guangliang CHEN, Hao QIAN, Lin SUN, Qian LI, Yi HU, Teng YI and Dalin ZHANG|Show fewer author(s)
Apr. 15, 2025NUCLEAR TECHNIQUES
DOI：10.11889/j.0253-3219.2025.hjs.48.240292
Flow field characteristics of the mixing vane in the fuel rod bundle region of a pressurized water reactor
Study on the influence of novel mixing vanes on fretting wear caused by fuel rods flow-induced vibrationNUCLEAR ENERGY SCIENCE AND ENGINEERING
Shuo YUAN... Xiang CHAI, Xiaojing LIU and Hui HE|Show fewer author(s)
Apr. 15, 2025NUCLEAR TECHNIQUES
DOI：10.11889/j.0253-3219.2025.hjs.48.230466
Study on the influence of novel mixing vanes on fretting wear caused by fuel rods flow-induced vibration
Analysis of heat transfer characteristics of geyser boiling in high-temperature sodium heat pipesNUCLEAR ENERGY SCIENCE AND ENGINEERING
Yan WANG... Yugao MA, Zaiyong MA, Liangming PAN, Longxiang ZHU, Simiao TANG and Qiang LIAN|Show fewer author(s)
Apr. 15, 2025NUCLEAR TECHNIQUES
DOI：10.11889/j.0253-3219.2025.hjs.48.240491
Analysis of heat transfer characteristics of geyser boiling in high-temperature sodium heat pipes
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Investigation of the feasibility of DRAGON/DONJON codes with CARR neutronics calculations
NUCLEAR TECHNIQUESVol. 47, Issue 10, 100603 (2024)
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The diffusion behavior of oxygen and hydrogen in Chromium coating on fuel cladding
NUCLEAR TECHNIQUESVol. 47, Issue 9, 090603 (2024)
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NECP-MCX software simulation of AB-BNCT neutron transport process
NUCLEAR TECHNIQUESVol. 47, Issue 9, 090205 (2024)
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Development of power supply system of EXL-50U magnet coils
NUCLEAR TECHNIQUESVol. 47, Issue 5, 050013 (2024)
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Coupled irradiation-thermal-mechanical analysis of fuel in solid core of heat pipe cooled reactor
NUCLEAR TECHNIQUESVol. 47, Issue 7, 070601 (2024)
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Criticality safety analysis of nuclear fuel storage of molten salt reactor
NUCLEAR TECHNIQUESVol. 47, Issue 8, 080606 (2024)
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Topics Research ArticlesINVITED REVIEWACCELERATOR, RAY TECHNOLOGY AND APPLICATIONSNUCLEAR ELECTRONICS AND INSTRUMENTATIONNUCLEAR CHEMISTRY, RADIOCHEMISTRY, RADIOPHARMACEUTICALS AND NUCLEAR MEDICINE