Life prediction model

Xem 1-4 trên 4 kết quả Life prediction model

Master's thesis of Engineering: Development of life prediction models for rolling contact wear in ceramic and steel ball bearings

In this thesis, the rolling contact wear of 52100 bearing steel and Over-aged Magnesia-Partially-Stabilised Zirconia (OA-Mg-PSZ) ceramic are examined using a newly developed rolling contact wear test rig. The new wear test rig simulates the system geometry of an un-lubricated hybrid (ceramic and steel) ball bearing. The new wear test rig is versatile in that it allows low cost samples to be utilised resulting in a larger number of samples that can be tested.

165p runthenight05 01-03-2023 8 3 Download

Summary of Doctoral thesis Transport construction engineering: Durability assessment of concrete by water permeability and chloride diffusion with consideration to the stress factor, application in bridge structure

Determine the coefficient of water permeability, waterproofing marks, chloride ion diffusion coefficients of some types of concrete commonly used in bridge construction subjected to pre-compressive and direct-compression loads. Develop a predictive model for life expectancy using reinforced concrete bridges taking into consideration the effect of the load according to the criteria of initial corrosion of reinforcement in concrete. Application of life expectancy for the structure of reinforced concrete bridges.

27p kequaidan7 01-09-2020 30 2 Download

Experimental investigation and numerical prediction for the fatigue life durability of austenitic stainless steel at room temperature

This work investigated and predicted the fatigue life durability of Austenitic Stainless Steel 316L at room temperature due to its importance in plant industries worldwide. Modelling and simulations were performed to clarify the fracture as well as stress distribution using integrated mechanism.

10p tohitohi 19-05-2020 16 1 Download
Comparison of applicability of current transition temperature shift models to SA533B-1 reactor pressure vessel steel of Korean nuclear reactors

The precise prediction of radiation embrittlement of aged reactor pressure vessels (RPVs) is a prerequisite for the long-term operation of nuclear power plants beyond their original design life. The expiration of the operation licenses for Korean reactors the RPVs of which are made from SA533B-1 plates and welds is imminent. Korean regulatory rules have adopted the US Nuclear Regulatory Commission's transition temperature shift (TTS) models to the prediction of the embrittlement of Korean reactor pressure vessels.

4p minhxaminhyeu4 26-06-2019 19 1 Download