UO2-BeO composite fuel may enable Light Water Reactors (LWRs) to have better safety due to its higher thermal conductivity. Much work have been done on the analysis of UO2-BeO fuel performance during LWRs steady state and Loss of Coolant Accident (LOCA) conditions using hypothetical thermal properties and behaviors models, leading to much uncertainty of the results. In this paper, firstly, fuel swelling and densification models for UO2-BeO fuel were developed based on Halden experiment data. Secondly, UO2-BeO fuel thermal properties and behaviors models have been coded in FRAPCON4.0 and FRAPTRAN2.0 after an evaluation of their applicability to UO2-BeO performance simulation. Then, both UO2-BeO composite fuel and traditional UO2 fuel performance during normal conditions and RIA were done in this paper by modified version of FRAPCON4.0 and FRAPTRAN2.0. Finally, comparisons between UO2-BeO and UO2 performance were conducted. The results shows that the peaking temperature of fuel can be reduced about 200K and 150K during normal conditions and RIA by adopting UO2-BeO, respectively. At the same time, the onset of pellet-cladding mechanic interaction (PCMI) can be delayed about 100days during normal conditions and the weakened PCMI effect can be expected during reactivity insertion accidents (RIA) due to the lower thermal expansion coefficient and temperature distribution for UO2-BeO composite fuel. Also, enthalpy stored in UO2-BeO fuel is reduced about 1/5 compared with that of UO2. However, fission gas release ration of UO2-BeO was a bit larger than that of UO2 due to its higher average burnup. And, further experiments stilled required to gain data for UO2-BeO during high burnup, like possibly reduced thermal conductivity and fission gas release threshold.
Skip Nav Destination
2018 26th International Conference on Nuclear Engineering
July 22–26, 2018
London, England
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-5153-1
PROCEEDINGS PAPER
Analysis of UO2-BeO Fuel Performance During Normal Conditions and RIA
Yanan He,
Yanan He
Xi'an Jiaotong University, Xi'an, China
Search for other works by this author on:
Yingwei Wu,
Yingwei Wu
Xi'an Jiaotong University, Xi'an, China
Search for other works by this author on:
Shihuai Wang,
Shihuai Wang
China Nuclear Power Technology Research Institute, Chengdu, China
Search for other works by this author on:
Bowen Qiu,
Bowen Qiu
Xi'an Jiaotong University, Xi'an, China
Search for other works by this author on:
G. H. Su
G. H. Su
Xi'an Jiaotong University, Xi'an, China
Search for other works by this author on:
Yanan He
Xi'an Jiaotong University, Xi'an, China
Yingwei Wu
Xi'an Jiaotong University, Xi'an, China
Shihuai Wang
China Nuclear Power Technology Research Institute, Chengdu, China
Bowen Qiu
Xi'an Jiaotong University, Xi'an, China
G. H. Su
Xi'an Jiaotong University, Xi'an, China
Paper No:
ICONE26-82076, V009T16A070; 9 pages
Published Online:
October 24, 2018
Citation
He, Y, Wu, Y, Wang, S, Qiu, B, & Su, GH. "Analysis of UO2-BeO Fuel Performance During Normal Conditions and RIA." Proceedings of the 2018 26th International Conference on Nuclear Engineering. Volume 9: Student Paper Competition. London, England. July 22–26, 2018. V009T16A070. ASME. https://doi.org/10.1115/ICONE26-82076
Download citation file:
33
Views
Related Proceedings Papers
Related Articles
COBRA-TF Simulation of DNB Response During Reactivity-Initiated Accidents Using the NSRR Pulse Irradiation Experiments
ASME J of Nuclear Rad Sci (July,2016)
Numerical Simulation Research on the Performance of SCWR Fuel Rod
ASME J of Nuclear Rad Sci (January,2018)
Enhanced Accident Tolerance of Thoria-Based Nuclear Fuels
ASME J of Nuclear Rad Sci (January,2020)
Related Chapters
Nuclear Fuel Materials and Basic Properties
Fundamentals of Nuclear Fuel
Experimental Investigation of an Improved Thermal Response Test Equipment for Ground Source Heat Pump Systems
Inaugural US-EU-China Thermophysics Conference-Renewable Energy 2009 (UECTC 2009 Proceedings)
Insights and Results of the Shutdown PSA for a German SWR 69 Type Reactor (PSAM-0028)
Proceedings of the Eighth International Conference on Probabilistic Safety Assessment & Management (PSAM)