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1-8 of 8
Keywords: pressurized water reactor
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Proceedings Papers
Proc. ASME. ICONE31, Volume 11: Student Paper Competition, V011T15A058, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135376
... Abstract Cogeneration is one of the ways to reduce carbon emissions and improve the efficiency of nuclear reactor plants. After adding thermal load, the power balance relationship between the supply and demand is changed in cogeneration pressurized water reactors (Co-PWR). So, the steam...
Proceedings Papers
Proc. ASME. ICONE29, Volume 9: Decontamination and Decommissioning, Radiation Protection, and Waste Management, V009T09A032, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92807
...Proceedings of the 2022 29th International Conference on Nuclear Engineering ICONE29 August 8-12, 2022, Virtual, Online ICONE29-92807 RESEARCH ON THE EXPECTED CARBON-14 PRODUCTION AND DISCHARGE IN PRESSURIZED WATER REACTORS Pengtao Fu China Nuclear Power Technology Research Institute Co., Ltd...
Proceedings Papers
Proc. ASME. ICONE29, Volume 10: Advanced Methods of Manufacturing for Nuclear Reactors and Components, V010T10A024, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92165
...Proceedings of the 2022 29th International Conference on Nuclear Engineering ICONE29 August 8-12, 2022, Virtual, Online ICONE29-92165 RESEARCH OF THE STANDARDS COMPILATION OF WELDING MATERIAL FOR CARBON STEEL IN PRESSURIZED WATER REACTOR NUCLEAR POWER PLANTS Bai Lin China Nuclear Power Engineering...
Proceedings Papers
Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A002, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-88883
... the development of high-temperature gas-cooled reactors (HTGRs). In this study, we investigated the state of fuel element damage monitoring technology in HTGRs and pressurized water reactors (PWRs), summarized their characteristics and parameters, and compared their advantages and disadvantages. The radioactive...
Proceedings Papers
Proc. ASME. ICONE29, Volume 10: Advanced Methods of Manufacturing for Nuclear Reactors and Components, V010T10A030, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92321
... Abstract The service performances in terms of stress corrosion cracking (SCC) of pressurized water reactor structural components in coolants are critical for the economic and long-term safe operation. the materials, microstructual and mechanical properties resulting from material manufacturing...
Proceedings Papers
Proc. ASME. ICONE29, Volume 13: Risk Assessments and Management, V013T13A044, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93128
... that the reason that the online detection system of fuel damage is not widely used is mainly due to precision limitation. Future efforts should be made on decomposition and failure diagnosis part in order to reach a fast response and high accuracy. fuel damage pressurized water reactor diagnosis method...
Proceedings Papers
Proc. ASME. ICONE28, Volume 4: Student Paper Competition, V004T14A037, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64451
.... Most of the nuclear reactors currently in operation in China are pressurized water reactors (PWR). The nuclear steam supply system (NSSS) in PWR is a complex nonlinear system. The steam bypass system ensures the steam generator’s cooling capacity in accident conditions and is essential for safe...
Proceedings Papers
Proc. ASME. ICONE21, Volume 2: Plant Systems, Construction, Structures and Components; Next Generation Reactors and Advanced Reactors, V002T03A003, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-15196
.... The test results show that the design of CRDM is reasonable and the operation is reliable. Control rode drive mechanism (CRDM) Experimental Cold test Pressurized water reactor EXPERIMENTAL INVESTIGATIONS OF CONTROL ROD DRIVE MECHANISM LU Guangyao, Lu Zhaohui, XIANG Wenyuan, LV Yonghong, HUANG...
