Materials and Fabrication

Development of Leak-Before-Break Assessment Method for Japan Sodium Cooled Fast Reactor Pipe—Part 1 Crack Opening Displacement Assessment of Thin Wall Pipes Made of Modified 9Cr-1Mo Steel

[+] Author and Article Information
Takashi Wakai

Structural Reliability Research Group,
Japan Atomic Energy Agency,
4002 Narita-cho Oarai,
Ibaraki 3111393, Japan
e-mail: wakai.takashi@jaea.go.jp

Hideo Machida

e-mail: machida-hideo@tepsys.co.jp

Manabu Arakawa

e-mail: arakawa-manabu@tepsys.co.jp
Nuclear Plant Engineering Department,
TEPCO Systems Corporation,
2-37-28 Eitai Koto-ku,
Tokyo 1350034, Japan

Shinji Yoshida

TEPCO Systems Corporation,
2-37-28 Eitai Koto-ku,
Tokyo 1350034, Japan
e-mail: yoshida-shinji@tepsys.co.jp

Yasuhiro Enuma

JSFR Systems Development Planning Office,
Japan Atomic Energy Agency,
4002 Narita-cho Oarai,
Ibaraki, 3111393, Japan
e-mail: enuma.yasuhiro@jaea.go.jp

1Presently Japan Atomic Energy Agency.

Contributed by the Pressure Vessel and Piping Division of ASME for publication in the Journal of Pressure Vessel Technology. Manuscript received May 9, 2011; final manuscript received June 15, 2012; published online December 4, 2012. Assoc. Editor: Kunio Hasegawa.

J. Pressure Vessel Technol 135(1), 011401 (Dec 04, 2012) (9 pages) Paper No: PVT-11-1116; doi: 10.1115/1.4007642 History: Received May 09, 2011; Revised June 15, 2012

This was carried out to establish crack opening displacement (COD) evaluation methods used in leak-before-break (LBB) assessment of sodium pipes of the Japan sodium cooled fast reactor (JSFR). For sodium pipes of JSFR, the continuous leak monitoring will be adopted as an alternative to a volumetric test of the weld joints under conditions that satisfy LBB. The sodium pipes are made of ASME Gr.91 (modified 9Cr-1Mo steel). Thickness of the pipes is small, because the internal pressure is very low. Modified 9Cr-1Mo steel has a relatively large yield stress and small work hardening coefficient comparing to the austenitic stainless steels which are currently used in the conventional plants. In order to assess the LBB behavior of the sodium pipes made of modified 9Cr-1Mo steel, the coolant leak rate from a through-wall crack must be estimated properly. Since the leak rate is strongly related to the COD, an appropriate COD assessment method must be established to perform LBB assessment. However, COD assessment method applicable for JSFR sodium pipes—thin wall and small work hardening material—has not been proposed yet. Thus, a COD assessment method applicable to thin walled large diameter pipe made of modified 9Cr-1Mo steel was proposed in this study. In this method, COD was calculated by classifying the components of COD; elastic, local plastic, and fully plastic. In addition, the verification of this method was performed by comparing with the results of a series of four-point bending tests at elevated temperature using thin wall modified 9Cr-1Mo steel pipe containing a circumferential through-wall crack. As a result, COD values calculated by the proposed method were in a good agreement with the experimental results for the uniform pipe without a weld. In the case that the crack was machined in the weld metal or heat affected zone (HAZ), the proposed method predicted relatively larger COD than the experimental results. The causes of such discrepancies were discussed by comparing with the results of finite element analyses. Based on these examinations, the rational leak rate evaluation method in LBB assessment was proposed.

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RCC-MR Edition 2002 Appendix A16, “Guide for Leak Before Break Analysis and Defect Assessment”.
Electric Power Research Institute, 1988, “Crack-Opening Area Calculations for Circumferential Through-Wall Pipe Cracks,” Report No. NP-5959-SR.
Rahmam, S., Brust, F. W., Ghadiali, N., and Wilkowski., G. M., 1998, “Crack-Opening-Area Analyses for Circumferential Through-Wall Cracks in Pipes-Part I: Analytical Models,” Int. J. Pressure Vessels Piping, 75, pp. 357–373. [CrossRef]
Wakai, T., Machida, H., Arakawa, M., Enuma, Y., and Asayama, T., 2010, “Development of LBB Assessment Method for Japanese Sodium Cooled Fast Reactor (JSFR) Pipes (2)Crack Opening Displacement Assessment of Thin Wall Pipes Made of Modified 9Cr-1Mo Steel,” ASME Paper No. PVP2010-25249.
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Wakai, T., Machida, H., Yoshida, S., Enuma, Y., and Asayama, T., 2010, “Development of LBB Assessment Method for Japanese Sodium Cooled Fast Reactor (JSFR) Pipes (3) Fracture Assessment Methods Considering Compliance at a Crack Part,” ASME Paper No. PVP2010-25244.


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Fig. 1

Compact plant design achieved by employing some innovative technologies

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Fig. 2

Provisional LBB assessment flowchart for JSFR pipes

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Fig. 3

An example of FEA model of a pipe with a circumferential through-wall crack

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Fig. 4

Relation between COD and applied load (n = 15, R/t = 50, θ = 45 deg, λ/(λ + 1) = 0.5)

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Fig. 5

Comparison between assessed COD and FEA

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Fig. 6

COD fitting errors

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Fig. 7

Comparison between assessed COD and experimental results



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