M. Annor-Nyarko

ORCID: 0000-0003-2906-4879
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About
Contact & Profiles
Research Areas
  • Nuclear Materials and Properties
  • Fault Detection and Control Systems
  • Nuclear reactor physics and engineering
  • Fatigue and fracture mechanics
  • Machine Fault Diagnosis Techniques
  • Engineering Diagnostics and Reliability
  • Nuclear Engineering Thermal-Hydraulics
  • High-Velocity Impact and Material Behavior
  • Mineral Processing and Grinding
  • Non-Destructive Testing Techniques
  • Oil and Gas Production Techniques
  • Spectroscopy and Chemometric Analyses
  • Material Properties and Failure Mechanisms
  • Nuclear and radioactivity studies
  • Thermodynamic and Structural Properties of Metals and Alloys
  • Image and Signal Denoising Methods
  • Nuclear materials and radiation effects
  • Risk and Safety Analysis
  • Probabilistic and Robust Engineering Design
  • Numerical methods in engineering

Ministry of Industry and Information Technology
2021-2022

Harbin Engineering University
2019-2022

Ghana Atomic Energy Commission
2019-2022

University of Ghana
2014

Bearings are widely applied in rotating machinery of nuclear power plants (NPPs). Data-driven fault diagnosis technology is critical to ensuring the reliable operation machinery. Aiming at problem poor model generalization ability caused by discrepant data distribution monitoring signals under various working conditions, a deep transfer learning method based on fully categorized alignment subdomain adaptation (FCA-SAN) proposed this paper. Firstly, bearing vibration source and target...

10.1080/00223131.2021.1953630 article EN Journal of Nuclear Science and Technology 2021-08-13

The reactor pressure vessel (RPV) is subjected to many cyclic loadings critical of which the integrity risk posed by pressurized thermal shock (PTS) induced one most frequent anticipated operational occurrences - inadvertent operation safety injection system (SIS). In this paper, fracture mechanics analysis for an ageing water PTS actuation SIS performed using a proposed simplified Abaqus-FRANC3D co-simulation method. A three-dimensional (3-D) finite element half-symmetric model typical...

10.1016/j.prostr.2022.01.078 article EN Procedia Structural Integrity 2022-01-01

The damage induced pressurized thermal shock (PTS) may pose to a reactor pressure vessel (RPV) is critical safety requirement assessed as part of the ageing management programme water reactors (PWRs). A number researches have studied PTS initiated mainly by postulated accidents such loss coolant (LOCAs). However, investigations on PTS-induced threat RPV caused inadvertent actuation injection, frequent anticipated transient, not been thoroughly studied. In this paper, simplified multistep...

10.1155/2022/5886583 article EN cc-by Science and Technology of Nuclear Installations 2022-02-02

The safety-risk pressurized thermal shock (PTS) have on a reactor pressure vessel (RPV) is one of the most important studies for lifetime ageing management reactor. Several investigated PTS induced by postulated accidents and other anticipated transients. However, there no study that analyzes effect frequent operational occurrences—inadvertent operation safety injection system. In this paper, sequential Abaqus-FRANC3D simulation method proposed to integrity status an water subjected...

10.1155/2021/7035787 article EN cc-by Science and Technology of Nuclear Installations 2021-09-06

In this work, molecular dynamics (MD) simulation was utilized in relation to access the thermal conductivity of UO2, PuO2 and (U, Pu)O2 temperature range 500–3000 K. Diffusion study on mixed oxide (MOX) also performed assess effect radiation damage by heavy ions at burnup temperatures. Analysis lattice irradiated MOX its microstructure carried out enhance irradiation defects with how high hinders fuel properties pellet-cladding interaction. Fission gas diffusion as determined mainly modelled...

10.4028/www.scientific.net/ssp.318.39 article EN Diffusion and defect data, solid state data. Part B, Solid state phenomena/Solid state phenomena 2021-05-24
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