The behaviour of a model pressure vessel is studied in a pressurized thermal shock loading. The tests were performed at the Prometey Institute in St. Petersburg. The calculations were performed at the Technical Research Centre of Finland. This report describes the preliminary finite- element analyses for the fourth, fifth and sixth thermoshock tests with the first model pressure vessel. Seven pressurized thermoshock tests were made with the same model pressure vessel using five different flaw geometries. In the first three tests the flaw was actually a blunt notch. In the two following tests (tests 4 and 5) a sharp pre-crack was produced before the test. In the last two tests (tests 6 and 7) the old crack was used. According to the measurem...
The present work deals with the development of a detailed Finite Element (FE) model of the Atucha II...
A numerical modelling of pressurised thermal shock (PTS) accidents has been performed. Crack growth ...
We describe the model developed for integrity assessment of a reactor pressure vessel (RPV) subjecte...
The behaviour of a model pressure vessel is studied in a pressurized thermal shock loading. The test...
This report describes the pre-test analyses performed for the thermoshock tests with the first model...
This report describes the pre-test analyses performed for the thermoshock tests with the first model...
Pressurized thermal shock experiments are performed in the Prometey Institute for the purpose of inv...
A joint pressure vessel integrity research programme involving three partners is being carried out d...
The integrity of PWR pressure vessels is assured by keeping the crack tip stress intensity factor be...
The structural integrity assessment of pressure boundary components requires reliable knowledge of t...
The HSST Thermal Shock Program at ORNL was established for the purpose of investigating the behavior...
Safety and integrity assessments of pressure boundary components require reliable knowledge of the m...
This paper deals with the finite element modeling of the pressure vessel with two artificial interna...
The structural integrity assessment of pressure boundary components requires reliable knowledge of t...
A summary of the recently completed International Comparative Assessment Study of Pressurized-Therma...
The present work deals with the development of a detailed Finite Element (FE) model of the Atucha II...
A numerical modelling of pressurised thermal shock (PTS) accidents has been performed. Crack growth ...
We describe the model developed for integrity assessment of a reactor pressure vessel (RPV) subjecte...
The behaviour of a model pressure vessel is studied in a pressurized thermal shock loading. The test...
This report describes the pre-test analyses performed for the thermoshock tests with the first model...
This report describes the pre-test analyses performed for the thermoshock tests with the first model...
Pressurized thermal shock experiments are performed in the Prometey Institute for the purpose of inv...
A joint pressure vessel integrity research programme involving three partners is being carried out d...
The integrity of PWR pressure vessels is assured by keeping the crack tip stress intensity factor be...
The structural integrity assessment of pressure boundary components requires reliable knowledge of t...
The HSST Thermal Shock Program at ORNL was established for the purpose of investigating the behavior...
Safety and integrity assessments of pressure boundary components require reliable knowledge of the m...
This paper deals with the finite element modeling of the pressure vessel with two artificial interna...
The structural integrity assessment of pressure boundary components requires reliable knowledge of t...
A summary of the recently completed International Comparative Assessment Study of Pressurized-Therma...
The present work deals with the development of a detailed Finite Element (FE) model of the Atucha II...
A numerical modelling of pressurised thermal shock (PTS) accidents has been performed. Crack growth ...
We describe the model developed for integrity assessment of a reactor pressure vessel (RPV) subjecte...