Search Results - "DRUBAY, B"
-
1
French RSE-M and RCC-MR code appendices for flaw analysis: Presentation of the fracture parameters calculation—Part III: Cracked pipes
Published in The International journal of pressure vessels and piping (01-10-2007)“…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 -
2
French RSE-M and RCC-MR code appendices for flaw analysis: Presentation of the fracture parameters calculation—Part IV: Cracked elbows
Published in The International journal of pressure vessels and piping (01-10-2007)“…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
French RSE-M and RCC-MR code appendices for flaw analysis: Presentation of the fracture parameters calculation—Part I: General overview
Published in The International journal of pressure vessels and piping (01-10-2007)“…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
A comparison between Japanese and French A16 defect assessment procedures for creep-fatigue crack growth
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…”
Get full text
Journal Article -
5
French RSE-M and RCC-MR code appendices for flaw analysis: Presentation of the fracture parameters calculation—Part V: Elements of validation
Published in The International journal of pressure vessels and piping (01-10-2007)“…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
A comparison between Japanese and French A16 defect assessment procedures for thermal fatigue crack growth
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…”
Get full text
Journal Article -
7
French RSE-M and RCC-MR code appendices for flaw analysis: Presentation of the fracture parameters calculation—Part II: Cracked plates
Published in The International journal of pressure vessels and piping (01-10-2007)“…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
A16: guide for defect assessment at elevated temperature
Published in The International journal of pressure vessels and piping (01-07-2003)“…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…”
Get full text
Journal Article -
9
A comparison between Japanese and French A16 defect assessment procedures for fatigue crack growth
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…”
Get full text
Journal Article Conference Proceeding -
10
Evaluation of ductile tearing in cracked pipes and elbows under bending
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…”
Get full text
Journal Article Conference Proceeding -
11
Energy release rate along any crack front in the thickness direction of shell elements
Published in International journal of solids and structures (01-02-2000)“…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…”
Get full text
Journal Article -
12
Simplified J estimation methods for cracked cylinders under combined thermal and mechanical loading
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…”
Get full text
Journal Article Conference Proceeding -
13
Crack initiation under creep and creep-fatigue on CT specimens of an austenitic stainless steel
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…”
Get full text
Journal Article -
14
French RSE-M and RCC-MR code appendices for flaw analysis: Presentation of the fracture parameters calculation-Part V: Elements of validation: Flaw analysis in the French RSE-M and RCC-MR code appendices
Published in The International journal of pressure vessels and piping (2007)Get full text
Journal Article -
15
French RSE-M and RCC-MR code appendices for flaw analysis: Presentation of the fracture parameters calculation-Part III: Cracked pipes: Flaw analysis in the French RSE-M and RCC-MR code appendices
Published in The International journal of pressure vessels and piping (2007)Get full text
Journal Article -
16
French RSE-N and RCC-MR code appendices for flaw analysis: Presentation of the fracture parameters calculation-Part II: Cracked plates: Flaw analysis in the French RSE-M and RCC-MR code appendices
Published in The International journal of pressure vessels and piping (2007)Get full text
Journal Article -
17
French RSE-M and RCC-MR code appendices for flaw analysis: Presentation of the fracture parameters calculation-Part IV: Cracked elbows: Flaw analysis in the French RSE-M and RCC-MR code appendices
Published in The International journal of pressure vessels and piping (2007)Get full text
Journal Article -
18
French RSE-M and RCC-MR code appendices for flaw analysis: Presentation of the fracture parameters calculation-Part I: General overview: Flaw analysis in the French RSE-M and RCC-MR code appendices
Published in The International journal of pressure vessels and piping (2007)Get full text
Journal Article -
19
-
20
Comparisons of simplified method J sub(S) and finite element for cracked pipes under thermal and mechanical loading
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…”
Get full text
Journal Article