NDLI: Replacement of Secondary Heat Transport System Components in the Experimental Fast Reactor JOYO

Content Provider	The American Society of Mechanical Engineers (ASME) Digital Collection
Author	Kawahara, Hirotaka Ichige, Satoshi Isozaki, Kazunori Nakai, Satoru
Copyright Year	2004
Abstract	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.
Sponsorship	Nuclear Engineering Division
Starting Page	79
Ending Page	90
Page Count	12
File Format	PDF
ISBN	0791846881
DOI	10.1115/ICONE12-49192
e-ISBN	0791837351
Volume Number	12th International Conference on Nuclear Engineering, Volume 2
Conference Proceedings	12th International Conference on Nuclear Engineering
Language	English
Publisher Date	2004-04-25
Publisher Place	Arlington, Virginia, USA
Access Restriction	Subscribed
Subject Keyword	Welding Irradiation (radiation exposure) Alloys Mechanical properties Cooling systems Steel Thermal energy Design Welded joints Sodium Fast neutron reactors Damage Waste heat Pipes Heat transfer Sodium fast reactors
Content Type	Text
Resource Type	Article

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