The prospect of modern thermomechanics in structural integrity calculations of large-scale pressure vessels

Fekete, Tamás

doi:10.1007/s00161-018-0657-3

Cited by 7 publications

(2 citation statements)

References 156 publications

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“…To accurately compute the linear elastic fracture resistance parameter (K IC ) following the master curve approach, four experimental fracture toughness test data of the selected RPV steel material (Table 1) were collected from open literature (Figure 14). Two of the experimental fracture test data were then used to iteratively calculate T 0 based on the multitemperature method expressed in equation (8).…”

Section: Crack Locationmentioning

confidence: 99%

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Thermomechanical Analysis of a Reactor Pressure Vessel under Pressurized Thermal Shock Caused by Inadvertent Actuation of the Safety Injection System

Annor-Nyarko

Xia

Ayodeji

2022

Science and Technology of Nuclear Installations

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The damage induced pressurized thermal shock (PTS) may pose to a reactor pressure vessel (RPV) is a critical safety requirement assessed as part of the ageing management programme of pressurized water reactors (PWRs). A number of researches have studied PTS initiated mainly by postulated accidents such as loss of coolant accidents (LOCAs). However, investigations on PTS-induced threat on RPV caused by inadvertent actuation of the safety injection, a frequent anticipated transient, have not been thoroughly studied. In this paper, a simplified multistep analysis method is applied to study the thermomechanical status of a two-loop PWR under PTS loads caused by inadvertent actuation of the safety injection system. A direct-coupling thermomechanical analysis is performed using a three-dimensional (3D) RPV finite element model. A 3D finite element submodel (consisting of the highiest stress concentration area in the RPV) and an assumed crack are then used to perform fracture mechanics analysis. Subsequently, the critical integrity parameter-stress intensity factor (SIF) is estimated based on FRANC3D-M-integral method coupled in the multistep simulation. The material fracture toughness of the vessel is computed based on the master curve method with experimental fracture toughness data. The results obtained from the direct coupling stress analysis in comparison with sequential coupling approach demonstrate the effectiveness of the proposed multistep method. Also, comparing SIF results obtained with that calculated based on the conventional virtual crack-closure technique (VCCT) and extended finite element method (XFEM) show good agreement. This study provides a useful basis for future studies on anticipated transient-induced crack propagation and remaining service life prediction of ageing reactor pressure vessels.

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Section: Crack Locationmentioning

confidence: 99%

“…Also, the thermomechanical coupling method applied mostly followed a sequential approach. Fekete T. has reviewed the prospect of modern thermomechanics in structural integrity calculations of pressure vessels [8]. Chouhan R. et al have also presented computational studies on pressurized thermal shock in an RPV [9].…”

Section: Introductionmentioning

confidence: 99%