Search Results - "DRUBAY, B"

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  1. 1

    French RSE-M and RCC-MR code appendices for flaw analysis: Presentation of the fracture parameters calculation—Part III: Cracked pipes by Marie, S., Chapuliot, S., Kayser, Y., Lacire, M.H., Drubay, B., Barthelet, B., Le Delliou, P., Rougier, V., Naudin, C., Gilles, P., Triay, M.

    “…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…”
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    Journal Article
  2. 2

    French RSE-M and RCC-MR code appendices for flaw analysis: Presentation of the fracture parameters calculation—Part IV: Cracked elbows by Marie, S., Chapuliot, S., Kayser, Y., Lacire, M.H., Drubay, B., Barthelet, B., Le Delliou, P., Rougier, V., Naudin, C., Gilles, P., Triay, M.

    “…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…”
    Get full text
    Journal Article
  3. 3

    French RSE-M and RCC-MR code appendices for flaw analysis: Presentation of the fracture parameters calculation—Part I: General overview by Marie, S., Chapuliot, S., Kayser, Y., Lacire, M.H., Drubay, B., Barthelet, B., Le Delliou, P., Rougier, V., Naudin, C., Gilles, P., Triay, M.

    “…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…”
    Get full text
    Journal Article
  4. 4

    A comparison between Japanese and French A16 defect assessment procedures for creep-fatigue crack growth by Wakai, T., Poussard, C., Drubay, B.

    Published in Nuclear engineering and design (01-10-2003)
    “…This paper presents the results of a benchmark on creep-fatigue crack growth evaluation for a plate subjected to cyclic bending loads with a 1 h dwell. The…”
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    Journal Article
  5. 5

    French RSE-M and RCC-MR code appendices for flaw analysis: Presentation of the fracture parameters calculation—Part V: Elements of validation by Marie, S., Chapuliot, S., Kayser, Y., Lacire, M.H., Drubay, B., Barthelet, B., Le Delliou, P., Rougier, V., Naudin, C., Gilles, P., Triay, M.

    “…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…”
    Get full text
    Journal Article
  6. 6

    A comparison between Japanese and French A16 defect assessment procedures for thermal fatigue crack growth by Wakai, T., Horikiri, M., Poussard, C., Drubay, B.

    Published in Nuclear engineering and design (01-04-2005)
    “…This paper presents the results of a benchmark on thermal fatigue crack growth evaluation for a thick-wall cylinder subjected to cyclic thermal transients. The…”
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    Journal Article
  7. 7

    French RSE-M and RCC-MR code appendices for flaw analysis: Presentation of the fracture parameters calculation—Part II: Cracked plates by Marie, S., Chapuliot, S., Kayser, Y., Lacire, M.H., Drubay, B., Barthelet, B., Le Delliou, P., Rougier, V., Naudin, C., Gilles, P., Triay, M.

    “…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…”
    Get full text
    Journal Article
  8. 8

    A16: guide for defect assessment at elevated temperature by Drubay, B., Marie, S., Chapuliot, S., Lacire, M.H., Michel, B., Deschanels, H.

    “…A large program has been performed in France in order to develop, for the design and operation of High Temperature Reactor plants, defect assessment and…”
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    Journal Article
  9. 9

    A comparison between Japanese and French A16 defect assessment procedures for fatigue crack growth by Wakai, T., Poussard, C., Drubay, B.

    Published in Nuclear engineering and design (01-03-2002)
    “…This paper presents the results of a benchmark on fatigue crack growth evaluation for plates subjected to cyclic bending loads. The simplified fatigue crack…”
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    Journal Article Conference Proceeding
  10. 10

    Evaluation of ductile tearing in cracked pipes and elbows under bending by Moulin, D., Clement, G., Drubay, B., Goudet, G.

    Published in Nuclear engineering and design (01-07-1997)
    “…A major project was launched in France to develop leak-before-break methods applicable to the primary circuit of pressurized water reactors. An important…”
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    Journal Article Conference Proceeding
  11. 11

    Energy release rate along any crack front in the thickness direction of shell elements by Suo, X.Z., Valeta, M.P., Drubay, B., Martelet, B., Deschanels, H.

    “…This paper deals with a numerical method for calculating the profile of the energy release rate G (or J-integral) along any crack front in the thickness…”
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    Journal Article
  12. 12

    Simplified J estimation methods for cracked cylinders under combined thermal and mechanical loading by Ignaccolo, S., Drubay, B., Papin, M.H., Michel, B., Gilles, P.

    Published in Nuclear engineering and design (01-04-1999)
    “…In the field of non-linear fracture mechanics, a lot of work has been done on structures submitted to mechanical loadings. However, for thermal loadings and…”
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    Journal Article Conference Proceeding
  13. 13

    Crack initiation under creep and creep-fatigue on CT specimens of an austenitic stainless steel by Laiarinandrasana, L., Piques, R., Drubay, B., Faidy, C.

    Published in Nuclear engineering and design (01-07-1995)
    “…In the nuclear industry, some methods for calculating the time of crack initiation from pre-existing defects are needed. For this purpose, a correlation is…”
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    Journal Article
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    Comparisons of simplified method J sub(S) and finite element for cracked pipes under thermal and mechanical loading by Papin, M H, Drubay, B, Michel, B

    Published in Nuclear engineering and design (01-01-1999)
    “…This paper presents the application of two simplified estimations of J on a complete set of finite element results performed on pipes. The simplified method J…”
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    Journal Article