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Proceedings Papers

Improvements on Fuel Failures Diagnosis Method for Pressurized Water Reactor Nuclear Power Plant Based on Radioactive Activities Inside the Waste Gas Treatment System

Weifeng Lyu, Runchun Guo, Wenwang Ran, Yaoyi Gao, Jun Xiong
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A072, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92996
https://doi.org/10.1115/ICONE29-92996
... Abstract The cladding of fuel elements in the core of a pressurized water reactor nuclear power plant (PWR) is the first barrier to the radioactive material in the reactor. Once the fuel cladding fails, the radioactive fission products or even fissile material in the fuel elements...
View Paper titled, Improvements on Fuel Failures Diagnosis Method for <span class="search-highlight">Pressurized</span> <span class="search-highlight">Water</span> <span class="search-highlight">Reactor</span> <span class="search-highlight">Nuclear</span> <span class="search-highlight">Power</span> <span class="search-highlight">Plant</span> Based on Radioactive Activities Inside the Waste Gas Treatment System
Open the PDF for Improvements on Fuel Failures Diagnosis Method for <span class="search-highlight">Pressurized</span> <span class="search-highlight">Water</span> <span class="search-highlight">Reactor</span> <span class="search-highlight">Nuclear</span> <span class="search-highlight">Power</span> <span class="search-highlight">Plant</span> Based on Radioactive Activities Inside the Waste Gas Treatment System in another window
Topics: Failure, Fuels, Nuclear power stations, Pressurized water reactors
Proceedings Papers

Assessment and Control Value Formulation on Radiological Consequence of On-Site Worker due to Radioactive Component Failure for Pressurized Water Reactor Plant

Zhou Jing, Ran Wen Wang, Gong Quan, Lv Wei Feng
Proc. ASME. ICONE29, Volume 9: Decontamination and Decommissioning, Radiation Protection, and Waste Management, V009T09A016, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91624
https://doi.org/10.1115/ICONE29-91624
... are the main factors for on-site radiological consequence evaluation, and the proposed method in this paper can assist in the safety classification of SSCs in the third generation of pressurized water reactor nuclear power plants. pressurized water reactor nuclear power plant safety barrier class dose...
View Paper titled, Assessment and Control Value Formulation on Radiological Consequence of On-Site Worker due to Radioactive Component Failure for Pressurized Water Reactor Plant
Open the PDF for Assessment and Control Value Formulation on Radiological Consequence of On-Site Worker due to Radioactive Component Failure for Pressurized Water Reactor Plant in another window
Topics: Failure, Nuclear power stations, Pressurized water reactors, Safety