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  • 11
    Language: English
    In: International Journal of Pressure Vessels and Piping, 2007, Vol.84(10), pp.659-686
    Description: Two French nuclear codes include flaw assessment procedures: the RSE-M Code “Rules for In-service Inspection of Nuclear Power Plant Components” and the RCC-MR code “Design and Construction rules for mechanical components of FBR nuclear islands and high temperature applications”. Development of analytical methods has been made for the last 10 years through a collaboration between CEA, EDF and AREVA-NP, and through R&D actions involving CEA and IRSN. These activities have led to unification of the common methods of the two codes. The calculation of fracture mechanics parameters, and in particular the stress intensity factor and the integral, has been widely developed for industrial configurations. All the developments have been integrated in the 2005 edition of RSE-M and in 2007 edition of RCC-MR. This series of papers is composed of five parts: the first presents an overview of the methods proposed in the RCC-MR and RSE-M codes. Parts II–IV provide compendia for specific components. The geometries are plates (part II), pipes (part III) and elbows (part IV). Part V presents validation of the methods, with details on their accuracy. This paper presents the stress intensity factor and calculation for cracked elbows. General data applicable for all defect geometries are first presented, and then, compendia for and calculations are provided for the available defect geometries.
    Keywords: Engineering
    ISSN: 0308-0161
    E-ISSN: 1879-3541
    Library Location Call Number Volume/Issue/Year Availability
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  • 12
    Language: English
    In: International Journal of Pressure Vessels and Piping, 2007, Vol.84(10), pp.614-658
    Description: French nuclear codes include flaw assessment procedures: the RSE-M Code “Rules for In-service Inspection of Nuclear Power Plant Components” and the RCC-MR code “Design and Construction rules for mechanical components of FBR nuclear islands and high-temperature applications”. An important effort of development of these analytical methods has been made for the last 10 years in the frame of collaboration between CEA, EDF and AREVA-NP, and in the frame of R&D actions involving CEA and IRSN. These activities have led to a unification of the common methods of the two codes. The calculation of fracture mechanics parameters, and in particular the stress-intensity factor and the integral, has been widely developed for industrial configurations. All the developments have been integrated in the 2005 edition of the RSE-M and in the 2007 edition of the RCC-MR. This series of articles is composed of 5 parts: the first part presents an overview of the methods proposed in the RCC-MR and RSE-M codes. Parts II–IV provide compendia for specific components. The geometries are plates (part II), pipes (part III) and elbows (part IV). Part V presents validation, with details on the accuracy of the proposed analytical method. This third part in the series presents details of the stress intensity factor and calculations for cracked pipes. General data applicable for all defect geometries are first presented, and then, compendia for and calculations are provided for specific cases.
    Keywords: Engineering
    ISSN: 0308-0161
    E-ISSN: 1879-3541
    Library Location Call Number Volume/Issue/Year Availability
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  • 13
    Language: English
    In: International Journal of Pressure Vessels and Piping, 2007, Vol.84(10), pp.687-696
    Description: French nuclear codes include flaw assessment procedures: the RSE-M Code “Rules for In-service Inspection of Nuclear Power Plant Components” and the RCC-MR code “Design and Construction Rules for Mechanical Components of FBR Nuclear Islands and High Temperature Applications”. Development of analytical methods has been made for the last 10 years in the framework of a collaboration between CEA, EDF and AREVA-NP, and by R&D actions involving CEA and IRSN. These activities have led to a unification of the common methods of the two codes. The calculation of fracture mechanics parameters, in particular the stress intensity factor and the integral, has been widely developed for industrial configurations. All the developments have been integrated in the 2005 edition of RSE-M and in 2007 edition of RCC-MR. This series of articles consists of 5 parts: the first part presents an overview of the methods proposed in the RCC-MR and RSE-M codes. Parts II–IV provide the compendia for specific components. The geometries are plates (part II), pipes (part III) and elbows (part IV). This part presents validation of the methods, with details on the process followed for their development and of the evaluation accuracy of the proposed analytical methods.
    Keywords: Engineering
    ISSN: 0308-0161
    E-ISSN: 1879-3541
    Library Location Call Number Volume/Issue/Year Availability
    BibTip Others were also interested in ...
  • 14
    Language: English
    In: International Journal of Pressure Vessels and Piping, 2007, Vol.84(10), pp.601-613
    Description: French nuclear codes include flaw assessment procedures: the RSE-M Code “Rules for In-service Inspection of Nuclear Power Plant Components” and the RCC-MR code “Design and Construction rules for mechanical components of FBR nuclear islands and high temperature applications”. An important effort of development of these analytical methods has been made for the last 10 years in the frame of a collaboration between CEA, EDF and AREVA-NP, and in the frame of R&D actions involving CEA and IRSN. These activities have led to a unification of the common methods of the two codes. The calculation of fracture mechanics parameters, and in particular the stress intensity factor and the integral, has been widely developed for industrial configurations. All the developments have been integrated in the 2005 edition of RSE-M and in the 2007 edition of RCC-MR. This series of articles is composed of 5 parts: the first part presents an overview of the methods proposed in the RCC-MR and RSE-M codes. Parts II–IV provide compendia for specific components. The geometries are plates (part II), pipes (part III) and elbows (part IV). Finally, part V presents the validation elements of the methods, with details on the process followed for the development and evaluation of the accuracy of the proposed analytical methods. This second article in the series presents all details for the stress intensity factor and calculations for cracked plates. General data applicable for all defect geometries are first presented, and then, available defect geometries where compendia for and calculation are provided are given.
    Keywords: Engineering
    ISSN: 0308-0161
    E-ISSN: 1879-3541
    Library Location Call Number Volume/Issue/Year Availability
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  • 15
    Language: English
    In: International Journal of Pressure Vessels and Piping, 2007, Vol.84(10), pp.590-600
    Description: Two French nuclear codes include flaw assessment procedures: the RSE-M code “Rules for In-service Inspection of Nuclear Power Plant Components” and the RCC-MR code “Design and Construction rules for mechanical components of FBR nuclear islands and high temperature applications”. An important effort of development of these analytical methods has been made for the last 10 years in the frame of a collaboration between CEA, EDF and AREVA-NP, and in the frame of R&D actions involving CEA and IRSN. These activities have led to a unification of the common methods of the two codes. The calculation of fracture mechanics parameters, and in particular the stress intensity factor and the integral, has been widely developed for industrial configurations. All developments have been integrated in the 2005 edition of RSE-M and in the 2007 edition of RCC-MR. This series of articles is composed of five parts: this first one presents an overview of the methods proposed in the RCC-MR and RSE-M codes. Parts II–IV provide compendia for specific components: plates (part II), pipes (part III) and elbows (part IV). Finally, part V presents the validation elements of the methods, with details on the process followed for their development and on evaluation of the accuracy of the proposed analytical methods. This first article of the series presents an overview of the calculation of and in these two codes and describes briefly the defect assessment analyses. Specific details in the Appendix A16 of RCC-MR (LBB procedure and creep analyses) are also introduced in this article.
    Keywords: Engineering
    ISSN: 0308-0161
    E-ISSN: 1879-3541
    Library Location Call Number Volume/Issue/Year Availability
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  • 16
    Language: English
    In: Études rurales, 01 January 1991
    Keywords: Sociology & Social History
    ISSN: 0014-2182
    E-ISSN: 1777-537X
    Source: OpenEdition Journals
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