A simplified leak-before-break evaluation procedure for austenitic and ferritic steel piping

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Division of Engineering, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Supt. of Docs., U.S. G.P.O. [distributor] , Washington, DC
Ferritic steel -- Safety measures., Pipe, Steel -- Evalua
Other titlesSimplified leak before break evaluation procedures for austenitic and ferritic steel piping.
Statementprepared by R.M. Gamble, A. Zahoor, B. Ghassemi.
ContributionsZahoor, A., Ghassemi, B., U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Division of Engineering., Novetech Corporation.
The Physical Object
Pagination1 v. (various pagings)
ID Numbers
Open LibraryOL15399510M

Get this from a library. A simplified leak-before-break evaluation procedure for austenitic and ferritic steel piping. [R M Gamble; A Zahoor; B Ghassemi; U.S.

Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Division of Engineering.; Novetech Corporation.]. A simplified leak-before-break evaluation procedure for austenitic and ferritic steel piping Technical Report Gamble, R M ; Zahoor, A ; Ghassemi, B A simplified procedure has been defined for computing the allowable circumferential throughwall crack length as a function of applied loads in piping.

SearchWorks Catalog Stanford Libraries. Catalog start Subject "Pipe, Steel." A simplified leak-before-break evaluation procedure for austenitic and ferritic steel piping [microform] [] Gamble, R.

A preliminary comparison between the leak-before-break curve determined analytically using the plastic limit load concept from Kanninen et al.

()and the experiments is shown in Fig. The maximum bending moments of the pipes with the defect sited in the base metal lie on the calculated curve (through-wall defect 2 α =°) or about 15% Cited by: A sulfidation- and oxidation-resistant ferritic stainless steel containing aluminum [microform] / by J.

Photometric calibrations [microform] / Yoshihiro Ohno; A simplified leak-before-break evaluation procedure for austenitic and ferritic steel piping [microform] Mass calibrations [microform] / R.S. Davis. Leak-Before-Break assessment of a welded piping based on 3D finite element method.

(the base metal is the ferritic steel 16 MND 5 and the welding is the austenitic stainless welding) is the low strength-match WPJ (the strength of the welding is lower than that of the base metal), and it can represent the welded joints between the vessel and Cited by: 3.

Important Effects in Environmentally Assisted Fatigue (EAF) of Austenitic and Ferritic Steel Components Including Welds and Their Consideration in a Fatigue Assessment Concept Jürgen Rudolph, Matthias Herbst, Armin Roth, Christian Swacek, Tim Schopf. Environmental Influences on the Fatigue Assessment of Austenitic and Ferritic Steel Components Including Welds.

Design, Fast neutron reactors, Fitness-for-service, Industrial research, Japan Society of Mechanical Engineers, Leak-before-break, Reliability Proposal for Update on Evaluation Procedure for Reactor Pressure Vessels. Development of guidance for leak-before-break analysis of complex shaped cracks PVP Leak Before Break: Studies in Support of New R6 Guidance on Leak Rate Evaluation by Neutron Diffraction and Finite Element Analyses of Residual Stress Formation in Repair Welds Applied to Ferritic Steel Plates.

Ohms, C. / Wimpory, R. higher cooling rate. Occurrence of IGSCC in austenitic stainless steel (ASS) piping is deterrent in demonstration of Leak Before Break (LBB) design criteria. In view of the improved material specification and welding process optimization, the chances of IGSCC will reduce significantly and help.

Microstructural features, mechanical properties and high temperature failures of ferritic to ferritic dissimilar welds, International Materials Reviews, DOI: / Cracking in Stabilized Austenitic Stainless Steel Piping of German Boiling Water Reactors — Characteristic Features and Root Causes.

MPA-Seminarvol. 2, pa pp–). F.1 The leak-before-break diagram G.1 Flow chart of assessment procedure J.1 Flow chart for selection of appropriate correlation K.1 Evaluation of F L for single primary stress M.1 Through-thickness flaw geometry N.1 Relationship between actual flaw dimensions and the parameter for surface flaws O.1 Typical warm prestress cycles.

The procedure is based upon the principles of fracture mechanics (LEFM and EPFM) and applies to ferritic and austenitic materials of the main components and piping. It makes use of partial safety factors on loading and material mechanical properties, so these properties must rely on a statistical approach.

PVP Proposal for Update on Evaluation Procedure for Reactor Pressure Vessels Against Pressurized Thermal Shock Events in Japan PVP Finite Element Modelling of Welded Austenitic Stainless Steel Plate With 8-Passes. Patel, V.I PVP Residual Stress Evaluation of Small Diameter Stainless Steel Piping by.

Details A simplified leak-before-break evaluation procedure for austenitic and ferritic steel piping FB2

“Simplified evaluation of J integral in cylinders under thermal loading,» in “13 International Conference on Structural Mechanics in Reactor Technology, Vol.2,” Rieara and Rocha, eds., Editora da Universidade Federal do Rio Grande deI Sul, Porto Alegre, pp.

– ().Author: Dominique P. Miannay. Leak Before Break (3) Plastic Pipe (3) Analytical Study of the Relaxation of Welding Residual Stress by Excessive Loading for Austenitic Stainless Steel Piping Welds.

Jinya Katsuyama, Kunio Onizawa. Strain Rate Dependence of Yield Strength and Long-Term Creep Strength Evaluation of ASME Grade 91 Steel.

Kazuhiro Kimura, Kota Sawada. Both the book and the course are a combination of a tutorial and of presentation of the current achievements in the field. Starting from the basic elements of expert systems (knowledge based systems), the book should "guide" the reader up to the applications in various particular sub-domains.

A simplified J-integral evaluation method applicable to unstable failure analysis in Leak Before Break (LBB) assessment of Sodium-cooled Fast Reactor (SFR) in Japan was proposed. Mod.9Cr-1Mo steel is supposed to be a candidate material for the coolant systems of SFR in Japan.

Full text of "DTIC ADA Preceedings of the International Congress (12th), Corrosion Control for Low-Cost Reliability, Held in Houston, Texas on September 19Volume 4.

Oil/Gas/Pipeline" See other formats. "Describes the systematic procedure for using process and mechanical design information to select construction materials suitable for a range of chemical and hydrocarbon processing plants. The volume features tables for locating the American Society for Testing and Materials (ASTM) product form specifications for construction materials that.

In the absence of access to software or the time required for such an evaluation, simplified methods of approximating thermal displacement can be applied.

Download A simplified leak-before-break evaluation procedure for austenitic and ferritic steel piping PDF

Ferritic and austenitic stainless steels. A, A, A, A, A A, A, A, A, A (continued) Superseded ASTM/ASME Steel Piping Specifications ASTM/ASME Superseded.

9F Fracture Toughness of Austenitic Stainless Steel 9F In most cases, austenitic stainless steels do not experience a ductile-brittle transition like ferritic steels. The fracture toughness is usually high, even at low temperatures, provided the material has not experienced degradation in toughn.

AWS AM: Standard procedures for calibrating magnetic instruments to measure the delta ferrite content of austenitic and duplex ferritic-austenitic stainless steel weld metal ISO modified Calibration procedures are specified for a number of commercial instruments that can then provide reproducible measurements of the ferrite 5/5(1).

For the steel designated as BM C (Δ), the number of cycles to failure only reduced by about 30% as hold time per cycle increased to 1 hour. In contrast, steel designated BM A (o) showed a life reduction with increasing hold time of about 80%.

The performance of the other steel BM B () was between these : Jonathan Parker. MIT22 F11 Read Core Gif. of Share & Embed. A Bayesian approach to treat expert-elicited probabilities in human reliability analysis model construction Podofillini L, Dang V N RELIABILITY ENGINEERING & SYSTEM SAFETY().

DOI: / A Long-Term Electricity Dispatch Model with the TIMES Framework Kannan Ramachandran, Turton Hal ENVIRONMENTAL MODELING & ASSESSM ().

Debris Impact on Emergency Cool - OECD OCDE код для вставки. Advanced Nuclear Reactor Safety - OECD OCDE код для вставки. Introductory Fracture Mechanics - Free ebook download as PDF File .pdf), Text File .txt) or read book online for free.

Description A simplified leak-before-break evaluation procedure for austenitic and ferritic steel piping FB2

good in leaner and plastic fracture mechanics and fatique fracture have good example on crack tip opening and j-integral5/5(2). The two biggest global challenges facing the energy world today are climate change and the huge increase in energy consumption.

Global electricity consumption is expected to double by the year There will be increasing competition in the world for energy resources. On the other hand there is a need to lower energy intensity of the economy and turn to CO 2-free forms of energy production.A new USNRC Standard Review Plan (SRP) section, numbered [19] and entitled Leak Before Break Evaluation Procedures, providing review guidance for the implementation.

32 of the revised GDC-4, was published for public comment on 28 August The development of the final form of SRP by the USNRC staff is continuing.The approach for mechanistic pipe break evaluations is aimed to demonstrate that for the piping satisfying the Leak Before Break criteria, the sudden Double Ended Guillotine Break and the catastrophic rupture of the piping is not a credible event, as clearly demonstrated, for instance, in several U.S.

reports (NUREG/CR “Degraded Piping program” phase II”, NUREG/ Vol