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Keywords: Pressurized water reactorClose
Proc. ASME. ICONE29, Volume 13: Risk Assessments and Management, V013T13A044, August 8–12, 2022
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...
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
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...
Proc. ASME. ICONE29, Volume 9: Decontamination and Decommissioning, Radiation Protection, and Waste Management, V009T09A032, August 8–12, 2022
Paper No: ICONE29-92807
... Abstract Carbon-14 is one of the most important radionuclides discharged to the environment from pressurized water reactors due to its long half-life and its important role in the biological chain. Carbon-14 is the largest contributor of the dose rate to the public from all radionuclides...
Proc. ASME. ICONE29, Volume 10: Advanced Methods of Manufacturing for Nuclear Reactors and Components, V010T10A024, August 8–12, 2022
Paper No: ICONE29-92165
... Abstract Carbon steel welding is a major manufacturing method for nuclear power construction. For the moment, there are two sets of standards of welding material for carbon steel which used in pressurized water reactor nuclear power plants of China. The coexistence of standards of two different...
Proc. ASME. ICONE29, Volume 10: Advanced Methods of Manufacturing for Nuclear Reactors and Components, V010T10A030, August 8–12, 2022
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...
Proc. ASME. ICONE28, Volume 4: Student Paper Competition, V004T14A037, August 4–6, 2021
Paper No: ICONE28-64451
... Proceedings of the 2021 28th International Conference on Nuclear Engineering ICONE28 August 4-6, 2021, Virtual, Online ICONE28-64451 LINEAR ACTIVE DISTURBANCE REJECTION CONTROL OF STEAM BYPASS SYSTEM FOR A PRESSURIZED WATER REACTOR Xianshan Zhang1, Peiwei Sun1 Xinyu Wei1, Xiaolong Gou2, Guocheng...
Proc. ASME. ICONE21, Volume 2: Plant Systems, Construction, Structures and Components; Next Generation Reactors and Advanced Reactors, V002T03A003, July 29–August 2, 2013
Paper No: ICONE21-15196
... show that the design of CRDM is reasonable and the operation is reliable. Key words Control rode drive mechanism (CRDM), Experimental, Cold test, Pressurized water reactor NOMENCLATURE CRDM Control rod drive mechanism LC Lifting coil LA Lifting armature MA Moving armature MC Moving coil MG Moving...