Based on the design and manufacture characteristics of AFA 3G high performance fuel assembly, this paper analyzes the various factors that lead to leakage of the fuel assembly, which is mainly escape of radioactive products caused by failure of the fuel cladding tubes. Aiming at the fuel assembly leakage, this paper comparatively analyzes three main diagnosis methods, including radioactive activity calculation of fission products, sipping test and ultrasonic detection technique. At the same time, the detection results are analyzed and verified for on-site detection of ultrasonic device, finally this paper raises improvement analysis of ultrasonic detection technique so that facilitating research and implementation of fuel assembly leakage detection better in the future.
Skip Nav Destination
2017 25th International Conference on Nuclear Engineering
July 2–6, 2017
Shanghai, China
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-5779-3
PROCEEDINGS PAPER
Analysis and Research on Diagnosis Methods of AFA 3G Fuel Assembly Leakage
Wei Xiaohui
Wei Xiaohui
Suzhou Nuclear Power Research Institute, Shenzhen, China
Search for other works by this author on:
Wei Xiaohui
Suzhou Nuclear Power Research Institute, Shenzhen, China
Paper No:
ICONE25-66024, V001T01A001; 7 pages
Published Online:
October 17, 2017
Citation
Xiaohui, W. "Analysis and Research on Diagnosis Methods of AFA 3G Fuel Assembly Leakage." Proceedings of the 2017 25th International Conference on Nuclear Engineering. Shanghai, China. July 2–6, 2017. V001T01A001. ASME. https://doi.org/10.1115/ICONE25-66024
Download citation file:
38
Views
Related Proceedings Papers
Related Articles
Pellet-Cladding Interaction of LMFBR Fuel Elements at Unsteady State: An Introduction to Computer Code ISUNE-5
J. Eng. Power (October,1981)
Discussion of Tag Gas Method Using in China Experimental Fast Reactor for Failed Fuel Assembly Location
ASME J of Nuclear Rad Sci (October,2018)
Fuel Performance Modeling at High Burn-Up by FEMAXI-6 Code
ASME J of Nuclear Rad Sci (October,2022)
Related Chapters
Nuclear Fuel Materials and Basic Properties
Fundamentals of Nuclear Fuel
PSA Level 2 — NPP Ringhals 2 (PSAM-0156)
Proceedings of the Eighth International Conference on Probabilistic Safety Assessment & Management (PSAM)
Short.Term Reactivity Change: Xenon Effects
Fundamentals of CANDU Reactor Physics