The case of flow blockage of a single fuel assembly in the JRR-3 20MW open-pool-type research reactor is investigated without taking into account the effect of the power regulation system. The coolant system and multi-channel reactor core are modeled in detail using thermal hydraulic system analysis code RELAP5/MOD3.4. MDNBR (Minimum Departure From Nucleate Boiling Ratio) and the maximum fuel central temperature are investigated to assess the integrity of fuels. The fuel plates in blocked assembly are not damaged until the blockage ratio exceeds 70%. In addition, the mitigative effect of the assumed 18 MW lower power emergency shutdown operation on the accident is also discussed qualitatively. Results indicate that although the assumed lower power emergency shutdown operation cannot avoid the most severe operating condition, it can obviously mitigate the consequences of the accident. The reactor eventually remains in the long-term safe state when natural circulation is established.
Skip Nav Destination
Close
Sign In or Register for Account
2018 26th International Conference on Nuclear Engineering
July 22–26, 2018
London, England
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-5148-7
PROCEEDINGS PAPER
Analysis of Flow Blockage of a Single Fuel Assembly in the JRR-3 20MW Research Reactor
Yuchuan Guo
,
Yuchuan Guo
China Academy of Engineering Physics, Mianyang, China
Search for other works by this author on:
Guanbo Wang
,
Guanbo Wang
China Academy of Engineering Physics, Mianyang, China
Search for other works by this author on:
Dazhi Qian
,
Dazhi Qian
China Academy of Engineering Physics, Mianyang, China
Search for other works by this author on:
Heng Yu
,
Heng Yu
China Academy of Engineering Physics, Mianyang, China
Search for other works by this author on:
Bo Hu
Bo Hu
China Academy of Engineering Physics, Mianyang, China
Search for other works by this author on:
Yuchuan Guo
China Academy of Engineering Physics, Mianyang, China
Guanbo Wang
China Academy of Engineering Physics, Mianyang, China
Dazhi Qian
China Academy of Engineering Physics, Mianyang, China
Heng Yu
China Academy of Engineering Physics, Mianyang, China
Bo Hu
China Academy of Engineering Physics, Mianyang, China
Paper No:
ICONE26-81313, V06AT08A030; 7 pages
Published Online:
October 24, 2018
Citation
Guo, Y, Wang, G, Qian, D, Yu, H, & Hu, B. "Analysis of Flow Blockage of a Single Fuel Assembly in the JRR-3 20MW Research Reactor." Proceedings of the 2018 26th International Conference on Nuclear Engineering. Volume 6A: Thermal-Hydraulics and Safety Analyses. London, England. July 22–26, 2018. V06AT08A030. ASME. https://doi.org/10.1115/ICONE26-81313
Download citation file:
- Ris (Zotero)
- Reference Manager
- EasyBib
- Bookends
- Mendeley
- Papers
- EndNote
- RefWorks
- BibTex
- ProCite
- Medlars
Close
Sign In
10
Views
0
Citations
Related Proceedings Papers
Related Articles
Deceleration Performance and Parameter Influence Analysis of the Control Rod Hydraulic Deceleration Device for Control Rod Hydraulic Drive System
ASME J of Nuclear Rad Sci (July,2019)
Assessment of the Code “PTCREEP” for IPHWR Pressure Tube Ballooning Study
J. Pressure Vessel Technol (February,2011)
An Investigation of the Collapse and Surface Rewet in Film Boiling in Forced Vertical Flow
J. Heat Transfer (May,1975)
Related Chapters
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)
Research of Key Technologies of the Stage Hydraulic System's Electro-Hydraulic Monitoring
International Conference on Information Technology and Management Engineering (ITME 2011)
LOCA Frequencies Estimated from Operating Experience (PSAM-0282)
Proceedings of the Eighth International Conference on Probabilistic Safety Assessment & Management (PSAM)