A validated approach for probabilistic structural integrity design code implementation. (November 2021)

• Record Type: Journal Article
• Authors: Chavoshi, Saeed Zare; Bradford, Rick; Booker, Julian
• Is Part Of: Engineering fracture mechanics. Volume 257(2021)
• Publication Date: 2021-11
• Subjects: Probabilistic assessment -- Reference Damage -- Creep-fatigue -- Design Chart; AGR Advanced Gas-cooled Reactor -- AMR Advanced Modular Reactor -- BWR Boiling Water Reactor -- CI Confidence Interval -- CL Confidence Level -- CoV Coefficient of Variation -- CSD Cold Shut-Down -- FAVOR Fracture Analysis of Vessels Oak Ridge -- HAZ Heat-Affected Zone -- HSB Hot StandBy -- HTBASS High Temperature Behaviour of Austenitic Stainless Steels -- JSME Japan Society of Mechanical Engineers -- LBB Leak-Before-Break -- LHS Latin Hypercube Sampling -- MC Monte Carlo -- ORNL Oak Ridge National Laboratory -- ONR Office for Nuclear Regulation -- PDF Probability Density Function -- PFM Probabilistic Fracture Mechanics -- PWR Pressurised Water Reactor -- RVP Reactor Pressure Vessel -- SCF Stress Concentration Factor -- WSEF Weld Strain Enhancement Factor -- 3T-RDM Three-Term Reference Damage Model; Fracture mechanics -- Periodicals; Rupture, Mécanique de la -- Périodiques; Fracture mechanics; Periodicals; 620.112605
• DOI: 10.1016/j.engfracmech.2021.108028
• Languages: English
• ISSNs: 0013-7944

Abstract

Highlights: A simple approach for incorporating probabilistic structural integrity assessment is proposed. The approach is validated using real EDF nuclear plant case-studies. The approach is not restricted to a particular failure mechanism and material. Monte Carlo probabilistic assessment based on R5V2/3 is conducted. Abstract: This paper provides a possible approach for incorporating probabilistic structural integrity assessment which is sufficiently simple to encourage its adoption by design engineers. The approach, called the "Three-Term Reference Damage Model (3T-RDM)", is developed in the context of a particular benchmark problem and a proposed Design Chart where the probability of crack initiation by creep-fatigue in a widely used material in nuclear plants, namely 316H austenitic stainless steel, is estimated based on the R5V2/3 high temperature procedure. In principle, the 3T-RDM is not restricted to a particular failure mechanism, i.e., fracture, creep rupture, creep-fatigue crack initiation and growth are all within its scope, and non-metallic materials may also be addressed. To further validate the accuracy and generality of the proposed 3T-RDM and Design Chart, deterministic and Monte Carlo probabilistic structural integrity assessments are conducted for three EDF nuclear plant case-studies and the results are superimposed on the Design Chart obtained from the benchmark problem. The analysis indicates an excellent consistency between the results, justifying the adoption of the 3T-RDM for an intermediate level of probabilistic assessment in the nuclear sector.