High temperature effects on fatigue performance and crack initiation mechanisms of 316LN stainless steel for nuclear power pipelines by JianNeng Zheng, JunChao Hu, YueHui Jiang, QingYuan Wang, Kun Yang

“…This study performed high-cycle fatigue tests on 316LN stainless steel (SS) for nuclear power application to evaluate its fatigue behavior at both room temperature (RT) and 350 °C. …”
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Temporal Change in Atmospheric Radiocesium during the First Seven Years after the Fukushima Dai-ich Nuclear Power Plant Accident by Tomohisa Abe, Kazuya Yoshimura, Yukihisa Sanada

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Unraveling the adsorption and diffusion behavior of H and O atoms at Zr(0001) surface doped with a Nb/Sn atom: A first-principles study by Rongjian Pan, Aitao Tang, Jiantao Qin, Qingqing Wang, Lu Wu

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Emission Characteristics of PCDD/Fs, Heavy Metals, and Nuclides during Incineration of Waste Resins Containing Nuclides by Yuhan Feng, Yingzhe Du, Shiying Li, Lili Li, Shi Feng, Kunfeng Li, Mingxiu Zhan, Jinqing Wang, Xu Xu, Peng Lin

“…Abstract The waste resins generated from nuclear power plants contain radioactive substances, such as 137Cs and 60Co. …”
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Epistemic Uncertainties in Climate Predictions: A Challenge for Practical Decision Making by Rafaela Hillerbrand

“…This distinguishes the ethical problems associated with climate change from other problems regarding energy supply and demand like, for example, those associated with nuclear power.…”
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Numerical Simulation Study on Hydrogen Accumulation and Explosion in Radioactive Gas Decay Chamber by Shutang Sun, Yuanyuan Li, Ying Ji, Yeming Zhu, Dong Zhao, Yiren Lian, Yu Rong, Jin Yan, Hongchao Sun, Guoqiang Li

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Debatten i debatten by Jenny Eklöf

“…The debate was also colored by its contemporary context; by other ongoing science-related controversies, such as that of nuclear power, and not least by the emergence of new journalistic ideals and broader public discussions about academic freedom and scientists’ communicative obligations. …”
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Reliability analysis of passive residual heat removal system for large advanced pressurized water reactors by Tianrui Li, Xinkun Xiao, Guoqing Lu, Shikang Chen, Ronghua Chen, Wenxi Tian

“…Such comprehensive analysis contributes to ensuring the safe operation and advancement of nuclear power plants. The best-estimate program VITARS is used to analyze and calculate accident scenarios, with sensitivity analysis conducted based on preliminary thermal-hydraulic calculations to optimize parameter selection and simplify the response surface model structure, thereby streamlining the analysis process. …”
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Miniaturized-specimen creep testing: an alternative for evaluating the remaining life of Cr-Mo steel components by Heloisa Cunha Furtado, Fernanda Figueiredo Martins dos Santos, Leonardo Sales Araújo, Levi de Oliveira Bueno

“… Creep is the main degradation mechanism in steel and superalloy components operating at high temperatures in thermal and nuclear power generation units. Therefore, acquiring creep data during equipment operation is vital for a realistic calculation of the remaining useful life of these units. …”
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Time-dependent model for in-situ concrete carbonation depth under combined effects of temperature and relative humidity by Ting Du, Yongjia Cai, Yipu Guo, Jinghao Chen, Sen Chen, Mofang Yuan, Fulin Qu

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Formation Pathways and Emission Characteristics of PCDD/Fs during Co-combustion Tests of Sewage Sludge in Coal-fired Power Plants by Xiangbo Zou, Ji Ye, Chuangting Chen, Hui Huang, Wenxin Yu, Yuxuan Ying, Tieying Mao, Yunfeng Ma, Bingjian Zhu, Xiaoqing Lin

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Comparative Analysis of the Outcomes of Laparoscopic Right Hemicolectomy with D2 and D3 Lymphadenectomy in the Treatment of Patients with Right Colon Cancer by A. A. Nevolskikh, V. A. Avdeenko, Yu. Yu. Mikhaleva, T. P. Pochuev, P. V. Sokolov, R. F. Zibirov, I. P. Reznik, N. D. Silin, L. O. Petrov, S. A. Ivanov, A. D. Kaprin

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