Considering the hypothetical core melt down scenario for a light water reactor (LWR) a possible failure mode of the reactor pressure vessel (RPV) and its failure time has to be investigated for a determination of the loadings on the containment. Numerous experiments have been performed accompanied with material properties evaluation, theoretical, and numerical work /REM 1993/, /THF 1997/, /CHU 1999/. For pre- and post-test calculations of Lower Head Failure experiments like OLHF or FOREVER it is necessary to model creep and plasticity processes. Therefore a Finite Element Model is developed at the FZR using a numerical approach which avoids the use of a single creep law employing constants derived from the data for a limited stress and temp...
After the Fukushima Daiichi nuclear power plant accident due to the pacific coast of Tohoku earthqua...
The paper presents test results for the mechanical and creep properties of the European steel grade ...
In existing severe accident codes such as MELCOR and THALES2, rupture of reactor pressure vessel (RP...
Considering the hypothetical core melt down scenario for a light water reactor (LWR) a possible fail...
Considering the unlikely core melt down scenario for a light water reactor (LWR) a possible failure ...
Considering the late in-vessel phase of an unlikely core melt down scenario in a light water reactor...
AbstractTime-dependent loads may significantly affect on structural integrity of RPV (Reactor Pressu...
A severe accident in a nuclear power plant could result in the relocation of large quantities of mol...
International audienceIn the event of a severe core meltdown accident in a pressurised water reactor...
To get an improved understanding and knowledge of the processes and phenomena during the late phase ...
International audienceIn the event of a severe core meltdown accident in a pressurized water reactor...
To get an improved understanding and knowledge of the processes and phenomena during the late phase ...
International audienceIn PWR severe accident scenarios, involving a relocation of corium (core melt)...
The paper presents the results of the determination the creep strength properties and both the micro...
The development of next generation nuclear fission reactors, needed to replace or supplement the cur...
After the Fukushima Daiichi nuclear power plant accident due to the pacific coast of Tohoku earthqua...
The paper presents test results for the mechanical and creep properties of the European steel grade ...
In existing severe accident codes such as MELCOR and THALES2, rupture of reactor pressure vessel (RP...
Considering the hypothetical core melt down scenario for a light water reactor (LWR) a possible fail...
Considering the unlikely core melt down scenario for a light water reactor (LWR) a possible failure ...
Considering the late in-vessel phase of an unlikely core melt down scenario in a light water reactor...
AbstractTime-dependent loads may significantly affect on structural integrity of RPV (Reactor Pressu...
A severe accident in a nuclear power plant could result in the relocation of large quantities of mol...
International audienceIn the event of a severe core meltdown accident in a pressurised water reactor...
To get an improved understanding and knowledge of the processes and phenomena during the late phase ...
International audienceIn the event of a severe core meltdown accident in a pressurized water reactor...
To get an improved understanding and knowledge of the processes and phenomena during the late phase ...
International audienceIn PWR severe accident scenarios, involving a relocation of corium (core melt)...
The paper presents the results of the determination the creep strength properties and both the micro...
The development of next generation nuclear fission reactors, needed to replace or supplement the cur...
After the Fukushima Daiichi nuclear power plant accident due to the pacific coast of Tohoku earthqua...
The paper presents test results for the mechanical and creep properties of the European steel grade ...
In existing severe accident codes such as MELCOR and THALES2, rupture of reactor pressure vessel (RP...