This paper presents a fracture assessment methods used in leak before break (LBB) assessment of sodium piping system in the Japanese sodium cooled fast reactor (JSFR). Use of thin wall pipes and compact layout of piping system are features of the design in JSFR. Since the internal pressure of piping of JSFR is low, the critical load is thermal expansion. Supposing a through wall crack (TWC) in such piping, the stiffness of the crack part will decrease, the load balance of the piping system will change from the condition without crack. The fracture assessment methods paying attention to this stiffness change at the crack part were proposed and these methods enabled rational LBB assessment. The proposed methods are much effective to loosen LBB conditions for the piping system of which the compliance is low. These methods applied to the LBB assessment of the piping system of JSFR which has the compact layout, and it was checked that the validity of these methods to loosen the LBB conditions.
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ASME 2010 Pressure Vessels and Piping Division/K-PVP Conference
July 18–22, 2010
Bellevue, Washington, USA
Conference Sponsors:
- Pressure Vessels and Piping Division
ISBN:
978-0-7918-49255
PROCEEDINGS PAPER
Development of LBB Assessment Method for Japanese Sodium Cooled Fast Reactor (JSFR) Pipes: 3—Fracture Assessment Methods Considering Compliance at a Crack Part Available to Purchase
Takashi Wakai,
Takashi Wakai
Japan Atomic Energy Agency, Ibaraki, Japan
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Hideo Machida,
Hideo Machida
Tepco Systems Corporation, Tokyo, Japan
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Shinji Yoshida,
Shinji Yoshida
Tepco Systems Corporation, Tokyo, Japan
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Yasuhiro Enuma,
Yasuhiro Enuma
Mitsubishi FBR Systems, Inc., Tokyo, Japan
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Tai Asayama
Tai Asayama
Japan Atomic Energy Agency, Ibaraki, Japan
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Takashi Wakai
Japan Atomic Energy Agency, Ibaraki, Japan
Hideo Machida
Tepco Systems Corporation, Tokyo, Japan
Shinji Yoshida
Tepco Systems Corporation, Tokyo, Japan
Yasuhiro Enuma
Mitsubishi FBR Systems, Inc., Tokyo, Japan
Tai Asayama
Japan Atomic Energy Agency, Ibaraki, Japan
Paper No:
PVP2010-25244, pp. 715-724; 10 pages
Published Online:
January 10, 2011
Citation
Wakai, T, Machida, H, Yoshida, S, Enuma, Y, & Asayama, T. "Development of LBB Assessment Method for Japanese Sodium Cooled Fast Reactor (JSFR) Pipes: 3—Fracture Assessment Methods Considering Compliance at a Crack Part." Proceedings of the ASME 2010 Pressure Vessels and Piping Division/K-PVP Conference. ASME 2010 Pressure Vessels and Piping Conference: Volume 6, Parts A and B. Bellevue, Washington, USA. July 18–22, 2010. pp. 715-724. ASME. https://doi.org/10.1115/PVP2010-25244
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