Simulation of creep tests with French or German RPV-steel and investigation of a RPV-support against failure

Willschütz, H.-G.; Altstadt, E.; Sehgal, B.R.; Weiß, Frank-Peter

doi:10.1016/s0306-4549(03)00036-7

Cited by 26 publications

(4 citation statements)

References 3 publications

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“…To represent the plastic deformation, a concept of the multi-linear isotropic hardening model is used, in which plasticity is represented by a function of stress over strain consisting of six linear sections. At each temperature, the six points of the stress-strain curves are defined as follows (Willschütz et al, 2003):…”

Section: Elastic Deformation and Plasticitymentioning

confidence: 99%

A thermal structural analysis tool for RPV lower head behavior during severe accidents with core melt

Madokoro

Miassoedov

Schulenberg

2018

Mechanical Engineering Letters

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The Fukushima Daiichi Nuclear Power Plant accident showed a significant effect on the environment due to the release of a large amount of radioactive material. To prevent the damage of the reactor pressure vessel (RPV), an in-vessel melt retention (IVR) by external reactor vessel cooling is considered to be a key severe accident management strategy. For its success, investigation of the thermal-mechanical behavior of the RPV lower head is of importance. The main objective of this study is the development of a thermal structural calculation tool for simulating the failure process and the visco-plastic behavior of the RPV lower head wall during the late phase of a core-melt severe accident. OpenFOAM, an open-source toolbox for developing numerical solvers, was used for the calculation platform. Thermal behavior of the molten pool in the RPV lower head is simulated by the phasechange effective convectivity model (PECM). One of the LIVE (Late In-Vessel Phase Experiments) experiments was analyzed for an evaluation purpose and reasonable results were obtained. The solver was then extended to couple PECM with a structural analysis model that considers thermal expansion, plasticity, creep and material damage. Two FOREVER (Failure Of Reactor Vessel Retention) tests, each of which uses different type of steel, were analyzed: EC-FOREVER-2 with French RPV steel 16MND5 and EC-FOREVER-4 with American RPV steel SA533B1. The deformation and failure time agreed reasonably well with the measured data. In addition, the failure mode was also well predicted qualitatively. The numerical analysis showed that the developed tool has a capability of simulating the lower head thermal structural behavior.

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Section: Elastic Deformation and Plasticitymentioning

confidence: 99%

A thermal structural analysis tool for RPV lower head behavior during severe accidents with core melt

Madokoro

Miassoedov

Schulenberg

2018

Mechanical Engineering Letters

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“…The lower vessel head was modelled with 2D-structural elements considering the temperature dependent material behaviour (Willschütz et al, 2003). The model embraced only the remaining (not melted) part of the vessel wall.…”

Section: Structure-mechanical Analysismentioning

confidence: 99%

Investigations on in-vessel melt retention by external cooling for a generic VVER-1000 reactor

Tusheva

Altstadt

Willschütz

et al. 2015

Annals of Nuclear Energy

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“…7 The creep behaviors of different RPV materials, 16MND5 (French) and 20MnMoNi5-5 (Germany), were compared in details and the creep life was evaluated by a damage model. 8 As for SA508 Gr.3 steel, the creep data at 450-1000 C with various stresses were analyzed by the classical Norton-Bailey power-law equation with nonlinear regression parameters. [9][10][11] The creep properties and behaviors of RPV materials usually exhibited a remarkably different tendency when the temperature was increased above the phasetransformation temperature, for example, 700-800 C, from that below for the SA508 Gr.3 steel.…”

Section: Introductionmentioning

confidence: 99%

“…Creep tests of SA533B1 and SA508 CL‐2 steels have been carried out over the temperature range of 627–1100°C, in order to evaluate the effect of temperature on the creep rupture life 7 . The creep behaviors of different RPV materials, 16MND5 (French) and 20MnMoNi5‐5 (Germany), were compared in details and the creep life was evaluated by a damage model 8 . As for SA508 Gr.3 steel, the creep data at 450–1000°C with various stresses were analyzed by the classical Norton‐Bailey power‐law equation with nonlinear regression parameters 9–11 .…”

Section: Introductionmentioning

confidence: 99%

Creep behavior and life prediction of a reactor pressure vessel steel above phase‐transformation temperature via a deformation mechanism‐based creep model

Wang

Zheng

et al. 2023

Fatigue Fract Eng Mat Struct

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For nuclear power generation as a carbon‐neutral energy source, in‐vessel retention (IVR) must be implemented to maintain the structural integrity of nuclear reactor pressure vessel (RPV) for more than 72 h under severe accidental conditions. This technology requires accurate prediction of creep deformation and life of RPV material being operated under pressure and extremely high‐temperature gradient. The current work develops a simplified deformation‐mechanism‐based true‐stress (DMTS) model for creep behavior/life‐prediction of SA508 Gr.3 steel, a typical RPV material, above the phase transformation temperatures (800–1000°C). This model is used to evaluate the time to specific creep strain (t3% and t5%) and rupture (tr), in comparison with popular empirical methods such as Orr–Sherby–Dorn (OSD) and Larson–Miller (LM). The simplified DMTS model achieves an excellent agreement with the experimental observations. The controlling deformation mechanisms are also discussed by metallurgical examinations, which provide the physical premise for the model development and application.

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Simulation of creep tests with French or German RPV-steel and investigation of a RPV-support against failure

Cited by 26 publications

References 3 publications

A thermal structural analysis tool for RPV lower head behavior during severe accidents with core melt

A thermal structural analysis tool for RPV lower head behavior during severe accidents with core melt

Investigations on in-vessel melt retention by external cooling for a generic VVER-1000 reactor

Creep behavior and life prediction of a reactor pressure vessel steel above phase‐transformation temperature via a deformation mechanism‐based creep model

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