Evaluating direct vessel injection accident-event progression of AP1000 and key figures of merit to support the design and development of water-cooled small modular reactors by Hossam H. Abdellatif, Palash K. Bhowmik, David Arcilesi, Piyush Sabharwall

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Application of Np–Am Mixture in Production of ²³⁸Pu in a VVER-1000 Reactor and the Reactivity Effect Caused by Loss-of-Coolant Accident in the Central Np–Am Fuel Assembl... by Anatoly N. Shmelev, Nikolay I. Geraskin, Vladimir A. Apse, Vasily B. Glebov, Evgeny G. Kulikov, Andrey A. Krasnoborodko

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Analyzing Simplified BWR Inherent Safety System using IAEA Generic Boiling Water Reactor Simulator by Arby Nuryana, Rida Siti Nur'aini Mahmudah

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Integral effect tests for intermediate and small break loss-of-coolant accidents with passive emergency core cooling system by Byoung-Uhn Bae, Seok Cho, Jae Bong Lee, Yu-Sun Park, Jongrok Kim, Kyoung-Ho Kang

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Development of a phenomena identification and ranking table (PIRT) for intermediate break loss-of-coolant accident in PWRs by Hae Min Park, Jong Hyuk Lee, Chiwoong Choi, Kwi-Seok Ha, Byung Hyun You, Jaeseok Heo, Kyung Doo Kim, Sung Won Bae, Seung Wook Lee, Dong Hyuk Lee, Sang Ik Lee, Chan Eok Park, Bub Dong Chung, Kwang Won Seul

Subjects: “…Intermediate break loss-of-coolant accident…”
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Experimental study of the fouling deposition on heating surface of narrow rectangular channel by CHENG Cheng, DUAN Zhongdi, XU Wei, LIU Xiaojing, TANG Wenyong

Subjects: “…loss of coolant accident…”
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Analysis on Phenomena of HPR1000 Large Break Loss of Coolant Accident Based on TRACE Code by SUN Wei;XU Chao;FU Hao;LIU Yusheng

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Research Progress on Thermal Hydraulic Characteristics of Spent Fuel Pools: A Review by Chende Xu, Zhengguang Wang, Shuai Tang, Xiangyu Chi, Xixi Zhu, Yaru Li, Naihua Wang

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Effect of Spray System on Fission Product Distribution in Containment During a Severe Accident in a Two-Loop Pressurized Water Reactor by Mehdi Dehjourian, Mohammad Rahgoshay, Reza Sayareh, Gholamreza Jahanfarnia, Amir Saied Shirani

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Study of a High Temperature–Resistant Shielding Material for the Shielding Doors of Nuclear Power Plants by LI Xiao-ling, Wu Rong-jun, Xu Xiao-hui, Zhang Duo-fei, YU Ming

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A long-term dependable and reliable method for reactor accident prognosis using temporal fusion transformer by Chengyuan Li, Chengyuan Li, Meifu Li, Zhifang Qiu

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Implicit Treatment of Technical Specification and Thermal Hydraulic Parameter Uncertainties in Gaussian Process Model to Estimate Safety Margin by Douglas A. Fynan, Kwang-Il Ahn

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Experimental Study on Critical Flow of Supercritical CO2 at Steady State and Model Verification by LI Weiqing;ZHANG Dongxu;ZHAO Minfu

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Enhancing LOCA Breach Size Diagnosis with Fundamental Deep Learning Models and Optimized Dataset Construction by Xingyu Xiao, Ben Qi, Jingang Liang, Jiejuan Tong, Qing Deng, Peng Chen

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Study on Void Reactivity of Supercritical Carbon Dioxide Cooled Reactor by LIU Minyun;CUI Rongyi;ZHAO Xingyu;HAN Wenbin;HUANG Shanfang;HUANG Yanping

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Enhancing equipment qualification testing facility for nuclear power plants: Achieving rapid temperature and pressure increase during design basis events by Kyungha Ryu, Seonggyu Cho, Taeho Roh, Sangkyo Kim, Taekook Park, Taehyun Lee, Jongwon Park, Jaehyun Cho

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Safety Evaluation of Silicon Carbide and Zircaloy-4 Cladding during a Large-Break Loss-of-Coolant Accident by Kwangwon Ahn, Kyohun Joo, Sung-Pil Park

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Analysis for fuel rod performance under LOCA based on the FROBA-ROD 2.0 code by Haoyu Liao, Chenxi Li, Yanan He, Yingwei Wu, Yapei Zhang, Wenxi Tian, G.H. Su, Suizheng Qiu

Subjects: “…Loss of coolant accident…”
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A Critical Flow Model for Supercritical Pressures by Yufeng Lv, Minfu Zhao, Kaiwen Du

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Prediction of severe accident occurrence time using support vector machines by Seung Geun Kim, Young Gyu No, Poong Hyun Seong

Subjects: “…Loss of coolant accident…”
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