AbstractTime-dependent loads may significantly affect on structural integrity of RPV (Reactor Pressure Vessel) under severe accident conditions respecting to the core melting. Especially, creep rupture at the high-temperature should be regarded as an important phenomenon to cope with failure of the RPV lower plenum. In this paper, creep behavior of SA533B as a typical reactor material was assessed based on several creep relationships such as Bailey-Norton's power law, MGR (Monkman-Grant Relationship) and MMGR (Modified Monkman-Grant Relationship). Creep rupture test data were referred from experimental projects of OECD/NEA. Subsequently, corresponding parametric FE (Finite Element) analyses were carried out for various temperature and loadi...
The paper presents the validity of several interesting relationships examined for better understandi...
In this study, the Liu–Murakami (LM) creep damage-coupled model was considered to evaluate the creep...
In existing severe accident codes such as MELCOR and THALES2, rupture of reactor pressure vessel (RP...
The paper presents the results of the determination the creep strength properties and both the micro...
Considering the hypothetical core melt down scenario for a light water reactor (LWR) a possible fail...
Considering the hypothetical core melt down scenario for a light water reactor (LWR) a possible fail...
The efficient and accurate prediction of creep rupture limit poses a huge challenge for high-tempera...
After the Fukushima Daiichi nuclear power plant accident due to the pacific coast of Tohoku earthqua...
A severe accident in a nuclear power plant could result in the relocation of large quantities of mol...
This paper reports the short-term creep behavior at elevated temperatures of a MarBN steel variant. ...
The creep-rupture behaviour of a Type DIN 1.4970 austenitic stainless steel has been investigated at...
The understanding of the creep behavior of nuclear fuel claddings is essential to predict safely and...
In this study, creep tests were conducted on a set of specimens made from the same tube of T91 steel...
For acceptance creep testing of ferrite steels for high temperature service the Larson-Miller parame...
It is important to select materials having both high strength and good ductility in most engineering...
The paper presents the validity of several interesting relationships examined for better understandi...
In this study, the Liu–Murakami (LM) creep damage-coupled model was considered to evaluate the creep...
In existing severe accident codes such as MELCOR and THALES2, rupture of reactor pressure vessel (RP...
The paper presents the results of the determination the creep strength properties and both the micro...
Considering the hypothetical core melt down scenario for a light water reactor (LWR) a possible fail...
Considering the hypothetical core melt down scenario for a light water reactor (LWR) a possible fail...
The efficient and accurate prediction of creep rupture limit poses a huge challenge for high-tempera...
After the Fukushima Daiichi nuclear power plant accident due to the pacific coast of Tohoku earthqua...
A severe accident in a nuclear power plant could result in the relocation of large quantities of mol...
This paper reports the short-term creep behavior at elevated temperatures of a MarBN steel variant. ...
The creep-rupture behaviour of a Type DIN 1.4970 austenitic stainless steel has been investigated at...
The understanding of the creep behavior of nuclear fuel claddings is essential to predict safely and...
In this study, creep tests were conducted on a set of specimens made from the same tube of T91 steel...
For acceptance creep testing of ferrite steels for high temperature service the Larson-Miller parame...
It is important to select materials having both high strength and good ductility in most engineering...
The paper presents the validity of several interesting relationships examined for better understandi...
In this study, the Liu–Murakami (LM) creep damage-coupled model was considered to evaluate the creep...
In existing severe accident codes such as MELCOR and THALES2, rupture of reactor pressure vessel (RP...