Dr Muhammad Hashim, PhD from Harbin Engineering University, - TopicsExpress



          

Dr Muhammad Hashim, PhD from Harbin Engineering University, Herbin, China, will give a talk on ‘Key Technologies on Reliability Monitor Development for Pressurized Water Reactor in a New Concept of Risk Monitor System in PIEAS Colloquium, on Thursday, October 23, 2014, at 2:00 pm in Conference Room, C-Block, PIEAS. Dr. Muhammad Hashim has recently (July 2014) completed PhD in Nuclear Energy Science and Engineering from the College of Nuclear Science and Technology, Harbin Engineering University, Harbin, China. He was sponsored from Chinese Government Scholarship Council. He did MSc (Physics) in nuclear and particle physics from Punjab University, BSc in Physics and Mathematics from Punjab University, and F.Sc from Government College for Boys, Bhakkar, Pakistan. During PhD, he learnt about two-phase flow thermal-hydraulics, nuclear reactor physics, nuclear power plant engineering, nuclear safety and reliability analysis, probabilistic safety assessment (PSA), Living PSA, risk monitor system, reliability monitor and plant DiD risk monitor system, engineering safety systems of conventional pressurized water reactor (PWR) and AP1000. The title of his research work was “Key Technologies on Reliability Monitor Development for Pressurized Water Reactor in a New Concept of Risk Monitor System”. Dr. Hashim has published 17 research papers in international journals and conferences. Summary There are three key technologies for comprising the proposed reliability monitor. They are (i) use of Failure Mode and Effect Analysis (FMEA) for qualitative evaluation, and (ii) use of Fault Tree Analysis (FTA) and (iii) GO-FLOW,both for the quantitative reliability evaluation of static and dynamic aspect, respectively, although the major focus has been given on the utilization of two technologies of FMEA and GO-FLOW. There are three basic issues in the reliability monitor studies. They are (i) how to apply those three methods for comprising effective reliability monitors for the real systems of nuclear power plant, (ii) what will be the precondition for the reliability monitors, and (iii) by what way the proposed methods of reliability monitors will be validated. In this PhD thesis, those three problems were tried to be solved by conducting on two practical evaluation of reliability for the safety systems of conventional PWR plant and AP1000. All are cordially invited.
Posted on: Tue, 21 Oct 2014 07:04:21 +0000

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