In order to enhance the inherent safety of sodium-cooled fast reactors, innovative hydraulically suspended absorber rod (HSR) passive shut-down system have been proposed for China demonstration fast reactor. In this study, based on the functional and performance requirements, a full-scale experimental setup has been designed and fabricated for the analysis of the HSR as applied to the prototype reactor. The main characteristic of the test facility is the actuation of the mobile safety rod is triggered by coolant flow rate decrease in the primary loop below half the nominal value and then the rod inserts into the stationary sleeve by gravity. The objective is to investigate the dynamic performance of HSR and establish the laws of its movement at lowering the flow rate modeling the coastdown of primary circulating pump. A series of tests have been performed, including start-up, steady-state operation, loss of flow accident, sensitivity analysis and reliability test. This study also focused on the effect of various factors on scram time, the effect of pump coasting time, rod weight, gap between rod and guide tube, bypass holes, cone angle of rod, flow rate and fluid temperature are analyzed. The experimental results demonstrate the functionality and reliability of the HSR, which would lay foundation for further optimization design.
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
Characterization and Experimental Investigation for the Dynamic Performance of the Hydraulically Suspended Passive Shutdown System in China Sodium-Cooled Fast Reactor
Jian Song,
Jian Song
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:
Wenxi Tian,
Wenxi Tian
Xi'an Jiaotong University, Xi'an, China
Search for other works by this author on:
Suizheng Qiu,
Suizheng Qiu
Xi'an Jiaotong University, Xi'an, China
Search for other works by this author on:
Guanghui Su
Guanghui Su
Xi'an Jiaotong University, Xi'an, China
Search for other works by this author on:
Jian Song
Xi'an Jiaotong University, Xi'an, China
Yingwei Wu
Xi'an Jiaotong University, Xi'an, China
Wenxi Tian
Xi'an Jiaotong University, Xi'an, China
Suizheng Qiu
Xi'an Jiaotong University, Xi'an, China
Guanghui Su
Xi'an Jiaotong University, Xi'an, China
Paper No:
ICONE26-81248, V009T16A016; 6 pages
Published Online:
October 24, 2018
Citation
Song, J, Wu, Y, Tian, W, Qiu, S, & Su, G. "Characterization and Experimental Investigation for the Dynamic Performance of the Hydraulically Suspended Passive Shutdown System in China Sodium-Cooled Fast Reactor." Proceedings of the 2018 26th International Conference on Nuclear Engineering. Volume 9: Student Paper Competition. London, England. July 22–26, 2018. V009T16A016. ASME. https://doi.org/10.1115/ICONE26-81248
Download citation file:
27
Views
Related Proceedings Papers
Related Articles
Statistical Methodology for a Quantified Validation of Sodium Fast Reactor Simulation Tools
J. Verif. Valid. Uncert (September,2019)
External Hazard Coinciding With Small Break LOCA—Thermohydraulic Calculation With System Code ATHLET
ASME J of Nuclear Rad Sci (April,2020)
Neutronic Analysis of the European Sodium Fast Reactor: Part I—Fresh Core Results
ASME J of Nuclear Rad Sci (January,2022)
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)
New Generation Reactors
Energy and Power Generation Handbook: Established and Emerging Technologies
Modeling of SAMG Operator Actions in Level 2 PSA (PSAM-0164)
Proceedings of the Eighth International Conference on Probabilistic Safety Assessment & Management (PSAM)