Resume

Educational and Professional Portfolio

Sumary

Awais Zahur

Assistant Professor and Researcher with 7 years of teaching experience in PIEAS with relevant projects in Core Neutronics and Thermal Hydraulics as supervisor and PhD in Reactor Multiphysics framework design and analysis. I want to design real time nuclear safety applications using computational techniques. Nuclear Safety require the solution of neutronics and thermal hydraulics simultaneously to deal the issues of local hotspot, long burnup cycles and efficient fuel utilization.

  • DNE, PIEAS
  • (+9251) 959-3600
  • awais@pieas.edu.pk

Education

PhD in Nuclear Engineering

2020 - 2023

Ulsan National Institute of Science and Technology, Ulsan, Republic of Korea

Development of Reactor Multiphysics framework to analyze the effect of crossflow and dynamic gHTC for Depletion and REA transient

MS in Nuclear Engineering

2012 - 2014

Pakistan Institute of Engineering and Applied Sciences, Nilore, Islamabad

An Implementation of Highly Accurate Scheme for Solution of the Point Reactor Kinetic Equation

BS in Computer & Information Sciences

2008 - 2012

Pakistan Institute of Engineering and Applied Sciences, Nilore, Islamabad

Predicting Protein Subcellular Location of Bacteria using Machine Learning Techniques

Professional Experience

Assistant Professor

2023 - Present

DNE, PIEAS

  • Development of an Anomaly Detection System for Nuclear Power Plants using the Transformer Model
  • Deep Learning-Based Simulation of Nuclear Reactor Transients for Desired Power Control
  • Enhancing Safety and Lifespan of small modular Pressurized Water Reactor Advanced Design and Verification
  • Neutronics Analysis of High Temperature Gas Cooled Reactor

Lecturer

2014 - 2020

DNE, PIEAS

  • Shield design of the KANUPP reactor using MCBEND computer code.
  • Development of a Scheme for Coupled Thermal-Hydraulics/ Neutronics Analysis of PARR-1.
  • Development of a comprehensive post processor for RELAP5.
  • Radiation Shield Design of PWR primary loop using MCBEND.
  • Simulation of a thermal–hydraulic passive system in post LOCA scenario.
  • Solution of Flow Coast down in a Pressurized Water Reactor using Polynomial Fit.
  • Solution of Reactor Kinetic equations using SCM Algorithm.