A recently completed major upgrade of the JOYO experimental sodium-cooled fast reactor, to the MK-III design, increased its irradiation capability. One major change was a 40% increase in thermal power to 140 MWt, which necessitated the replacement of the cooling system. Major challenges in the replacement of secondary components were control of impurity ingress and assurance of welding integrity. Damage to existing systems was avoided during replacement operations by taking measures to prevent ingress of air into the sodium systems. The long exposure of the used pipes made of ferritic low-alloy steel to hot sodium was a concern because previous research showed that this material changes its mechanical property in sodium hotter than 673 K. Used pipe, heat transfer tubes and welds were subjected to material tests. These tests did not show notable material problems. The replacement of components was completed without major troubles, demonstrating the effectiveness of the methods used.
Skip Nav Destination
12th International Conference on Nuclear Engineering
April 25–29, 2004
Arlington, Virginia, USA
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
0-7918-4688-1
PROCEEDINGS PAPER
Replacement of Secondary Heat Transport System Components in the Experimental Fast Reactor JOYO
Hirotaka Kawahara,
Hirotaka Kawahara
Japan Nuclear Cycle Development Institute, Ibaraki-ken, Japan
Search for other works by this author on:
Satoshi Ichige,
Satoshi Ichige
Japan Nuclear Cycle Development Institute, Ibaraki-ken, Japan
Search for other works by this author on:
Kazunori Isozaki,
Kazunori Isozaki
Japan Nuclear Cycle Development Institute, Ibaraki-ken, Japan
Search for other works by this author on:
Satoru Nakai
Satoru Nakai
Japan Nuclear Cycle Development Institute, Ibaraki-ken, Japan
Search for other works by this author on:
Hirotaka Kawahara
Japan Nuclear Cycle Development Institute, Ibaraki-ken, Japan
Satoshi Ichige
Japan Nuclear Cycle Development Institute, Ibaraki-ken, Japan
Kazunori Isozaki
Japan Nuclear Cycle Development Institute, Ibaraki-ken, Japan
Satoru Nakai
Japan Nuclear Cycle Development Institute, Ibaraki-ken, Japan
Paper No:
ICONE12-49192, pp. 79-90; 12 pages
Published Online:
November 17, 2008
Citation
Kawahara, H, Ichige, S, Isozaki, K, & Nakai, S. "Replacement of Secondary Heat Transport System Components in the Experimental Fast Reactor JOYO." Proceedings of the 12th International Conference on Nuclear Engineering. 12th International Conference on Nuclear Engineering, Volume 2. Arlington, Virginia, USA. April 25–29, 2004. pp. 79-90. ASME. https://doi.org/10.1115/ICONE12-49192
Download citation file:
3
Views
Related Proceedings Papers
Related Articles
Computational Fluid Dynamic Analysis of the ESFR Reactor Pit Cooling System in Case of Sodium Leakage
ASME J of Nuclear Rad Sci (January,2022)
New Reactor Safety Measures for the European Sodium Fast Reactor—Part II: Preliminary Assessment
ASME J of Nuclear Rad Sci (January,2022)
Related Chapters
New Generation Reactors
Energy and Power Generation Handbook: Established and Emerging Technologies
HIGH STRAIN WELD SOLUTIONS FOR GEOHAZARD ACTIVE ENVIRONMENT
Pipeline Integrity Management Under Geohazard Conditions (PIMG)
Threshold Functions
Closed-Cycle Gas Turbines: Operating Experience and Future Potential