Overview of fatigue life assessment of baffles in Wendelstein 7-X

作者: Joris Fellinger , Roberto Citarella , Venanzio Giannella , Marcello Lepore , Raffaele Sepe

DOI: 10.1016/J.FUSENGDES.2018.02.011

关键词: BaffleMechanical loadHeat shieldFinite element methodParis' lawStress intensity factorWendelstein 7-XComposite materialMaterials scienceBending

摘要: Abstract Wendelstein 7-X (W7-X), the world’s largest nuclear fusion experiment of modular stellarator type, started operation in 2015 and will be upgraded with a water cooled first wall for steady state 2020. The consists CFC armored island divertors, adjacent baffles, heat shields, stainless steel panels. Baffle shield segments consist graphite tiles, bolted low pre-stress onto sinks CuCrZr that are turn brazed pipes. Cracks were detected before installation baffles root seam over 100 locations. Such cracks attributed to imposed plastic deformation pipes bring them into final shape following complex 3D geometry plasma vessel. This paper gives an overview experimental numerical work using finite element method (FEM) dual boundary (DBEM), including sub-modeling assess risk leak during operation. Details is published Giannella et al. (2017), Lepore (2017) Citarella (2018). First fatigue crack growth experiments carried out on pipe material thermal-mechanical predictions made FEM DBEM. It appeared Stress Intensity Factor (SIF) threshold ductile only reached when large strains occur, thus violating field application linear elastic fracture mechanics forecast growth. Afterwards, representative samples manufactured subjected initial causing 11 12 samples. Some tested up 60,000 bending load cycles. Two four failed after ∼35,000 Before test, was measured computer tomography scans. Equivalence between thermal W7-X mechanical cyclic test determined models allow prediction life W7X. Additional modeling showed also zones away from can limit life.

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