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Research Papers

Application of the System Based Code Concept to the Determination of In-Service Inspection Requirements

[+] Author and Article Information
Shigeru Takaya

Japan Atomic Energy Agency, 4002 Narita, O-arai, Ibaraki 311-1393, Japan e-mail: takaya.shigeru@jaea.go.jp

Tai Asayama

Japan Atomic Energy Agency, 4002 Narita, O-arai, Ibaraki 311-1393, Japan e-mail: asayama.tai@jaea.go.jp

Yoshio Kamishima

Mitsubishi FBR systems, Inc., 2-34-17, Jingumae Shibuya-ku, Tokyo 150-0001, Japan e-mail: yoshio_kamishima@mfbr.mhi.co.jp

Hideo Machida

TEPCO Systems Corporation, 2-37-28, Eitai Koto-ku, Tokyo 135-0034, Japan e-mail: machida-hideo@tepsys.co.jp

Daigo Watanabe

Mitsubishi Heavy Industries, Ltd., 5-717-1 Fukahori, Nagasaki, Nagasaki 851-0392, Japan e-mail: daigo_watanabe@mhi.co.jp

Satoru Nakai

Japan Atomic Energy Agency, 4002 Narita, O-arai, Ibaraki 311-1393, Japan e-mail: nakai.satoru@jaea.go.jp

Masaki Morishita

Japan Atomic Energy Agency, 4002 Narita, O-arai, Ibaraki 311-1393, Japan e-mail: morishita.masaki@jaea.go.jp

1Corresponding author.

Manuscript received July 16, 2014; final manuscript received September 29, 2014; published online February 9, 2015. Assoc. Editor: Joseph Miller.

ASME J of Nuclear Rad Sci 1(1), 011004 (Feb 09, 2015) (9 pages) Paper No: NERS-14-1020; doi: 10.1115/1.4026392 History: Received July 16, 2014; Accepted November 14, 2014; Online February 09, 2015

A new process for determination of in-service inspection (ISI) requirements was proposed on the basis of the system based code concept to realize effective and rational ISI by properly taking into account plant-specific features. The proposed process consists of two complementary evaluations, one focusing on structural integrity and the other one on detectability of defects before they would grow to an unacceptable size in light of plant safety. If defect detection was not feasible, structural integrity evaluation would be required under sufficiently conservative hypothesis. The applicability of the proposed process was illustrated through an application to the existing prototype fast breeder reactor, Monju.

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Figures

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Fig. 1

Stage I evaluation of the proposed ISI requirement determination process

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Fig. 2

Stage II evaluation of the proposed ISI requirement determination process

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Fig. 3

Monju reactor main components

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Fig. 4

Dimensions of the UCS in the vicinity of sodium surface level

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Fig. 5

Probability distribution of crack depth

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