Balancing material selection and inspection requirements in structural design of fast breeder reactors based on “System Based Code” concept

Asayama, Tai; Kawasaki, Nobuchika; Morishita, Masaki; Shibamoto, Hiroshi; Inoue, Kazuhiko

doi:10.1016/j.nucengdes.2006.09.012

Cited by 7 publications

(5 citation statements)

References 7 publications

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“…The System Based Code (SBC) concept was proposed by Asada [2] and extensively studied not only in JSME [2][3][4][5] but also in ASME [13] as a new framework that would realize the most adequate allocation of margins to various technological aspects of plant design and operation. The SBC concept consists of three parts: 1) design to target reliability that must be met throughout the service life, 2) margin exchange among the various technical areas of concern such as design, inspection, fabrication, and fitness for service, and 3) expand technical options by the timely adoption of newly developed technologies that are not in current codes and standards.…”

Section: Derivation Of Inservice Inspection Requiremtns Based On Systmentioning

confidence: 99%

“…As to the framework of code requirements that allows to fully take advantage of structural materials for fast breeder reactors, the System Based Code (SBC) concept, the concept currently being extensively elaborated for the application to next generation reactors, can be utilized [2][3][4][5]. The SBC concept was proposed based on the recognition that existing codes and standards structure had become unnecessarily rigid in the long history of development and through a number of revisions.…”

Section: Introductionmentioning

confidence: 99%

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Structural Materials and Code Development for Japanese Sodium-Cooled Fast Reactors

Asayama

Nagae

Wakai

et al. 2014

ASME 2014 Symposium on Elevated Temperature Application of Materials for Fossil, Nuclear, and Petrochemical Industries

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This paper describes the latest status on the development of elevated temperature materials and structural codes for Japanese sodium-cooled fast reactors (SFRs). Based on the extensive research and development activities in the last decades in Japan, two materials, 316FR and Modified 9Cr-1Mo steels were recently incorporated into the 2012 Edition of Fast Reactor Design and Construction Code of the Japan Society of Mechanical Engineers (JSME). Structural design methodologies are continuously being improved towards the next major revision planed in 2016 Edition where methodologies for a 60-year design of Japanese demonstration fast reactor will be provided. Codes and guidelines for fitness-for-service, leak-before-break evaluation and reliability assessment are concurrently being developed utilizing the System Based Code concept aiming at establishing an integrated code system that encompasses a life cycle of SFRs. Paper published with permission.

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Section: Derivation Of Inservice Inspection Requiremtns Based On Systmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Structural Materials and Code Development for Japanese Sodium-Cooled Fast Reactors

Asayama

Nagae

Wakai

et al. 2014

ASME 2014 Symposium on Elevated Temperature Application of Materials for Fossil, Nuclear, and Petrochemical Industries

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“…F 24 ＋F 57 ≤ ~4.5x10 -8 /ry (3) Regarding the distribution ratio of "F 24 " and "F 57 " in the equation 3, we can select the value that we want. If the target value is equally distributed to "F 24 " and "F 57 ", equations (4) and (5) are obtained.…”

Section: Derivation Of the Reliability Targetmentioning

confidence: 99%

“…The SBC was advocated for the first time by the late Yasuhide Asada professor emeritus (1)- (3) . Since then, The SBC has been developed mainly in the domain of examination of structural design codes and standards for sodium-cooled fast reactor systems (4) (5) .…”

Section: Introductionmentioning

confidence: 99%

Development of System Based Code (1) Reliability Target Derivation of Structures and Components

Kurisaka

Nakai

Asayama

et al. 2011

JPES

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The present paper describes a new method for determining the target value of structural reliability in the framework of the System Based Code (SBC) by considering the safety point of view. This new method utilizes analysis models of a probabilistic safety assessment (PSA), and the reliability target is derived from (1) the proposal to a quantitative safety goal that was published by the nuclear safety commission (NSC) of Japan; (2) the quantitative safety design requirements on the core damage frequency (CDF) and the containment failure frequency (CFF) that were determined in the Fast Reactor Cycle Technology Development (FaCT) project by Japan Atomic Energy Agency (JAEA). This method was applied to determine the reliability target of the structures and components which constitute the reactor cooling system in the Japan sodium-cooled fast reactor (JSFR). The risk from the reactor is shown by the sum of combination of various elements in the PSA analysis model. Those elements include dynamic failures and static failures of the structures and components, and human errors. However, the present study focuses on the sequences including the static failure, and the probability of dynamic failures and human errors in those sequences is conservatively assumed as a unity. It was confirmed that the present method combined with the PSA analysis model for internal initiating events is applicable to determine the reliability target associated with a random failure of the structures and components, and also confirmed that the method related to seismic initiating events can derive the target value of the occurrence frequency at which any of the important structures and components fails due to an earthquake.

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“…A quantitative index that can correlate diverse areas such as load setting, fabrication, inspection, and maintenance is needed for life-cycle margin optimization and margin exchange. Some indices have been proposed, such as quality assurance index (2) , design factor, and probability of failure (13) . The determination of the target value is also one of the key points to implement the SBC concept.…”

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confidence: 99%

Development of System Based Code (2) Application of Reliability Target for Configuration of ISI Requirement

Takaya

Okajima

Kurisaka

et al. 2011

JPES

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The concept of System Based Code (SBC) has been proposed to achieve compatibility in matters of reliability, safety, and cost of fast breeder reactors (FBRs). This code extends the present structural design standard to include the broad areas such as load setting, fabrication, inspection, and maintenance related to FBR design and operation. Therefore, a quantitative index that can correlate these different areas is required. One such index is the probability of failure. The determination of a target value is also one of the key points to implement the SBC concept. We have proposed a new method to determine reliability targets for structures and components in FBR plants from the viewpoint of safety. Analysis models based on probabilistic safety assessments are used in the method for determining reliability targets. In this study, the effectiveness of the probability of failure as an index and the reliability targets produced using the new method are investigated through a trial setting of an in-service inspection (ISI) requirement for a reactor vessel. The probability of failure due to fatigue-creep interaction is calculated using a Monte Carlo simulation. The reliability targets for failure related to the risks arising from internal initiating events are derived using the new method. The summation of the probability of failure and of the reliability targets up to the end of the in-service period enables us to compare them directly. The results show that the reactor vessel has sufficient reliability even without an ISI. Through this example, we demonstrate that the probability of failure is a promising index and that reliability targets derived using the new method are compatible with SBC.

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Balancing material selection and inspection requirements in structural design of fast breeder reactors based on “System Based Code” concept

Cited by 7 publications

References 7 publications

Structural Materials and Code Development for Japanese Sodium-Cooled Fast Reactors

Structural Materials and Code Development for Japanese Sodium-Cooled Fast Reactors

Development of System Based Code (1) Reliability Target Derivation of Structures and Components

Development of System Based Code (2) Application of Reliability Target for Configuration of ISI Requirement

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