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Muhammad ILYAS
Muhammad ILYAS
Associate Professor, Department of Nuclear Engineering, Pakistan Institute of Engineering and
Verified email at pieas.edu.pk
Title
Cited by
Cited by
Year
Assessment of passive safety system of a Small Modular Reactor (SMR)
FA Hassan Nawaz Butt, Muhammad Ilyas, Masroor Ahmad
Annals of Nuclear Energy 98, 191–199, 2016
322016
Steam generator performance improvements for integral small modular reactors
M Ilyas, F Aydogan
Nuclear Engineering and Technology 49 (8), 1669-1679, 2017
262017
Design of a passive safety system for a nuclear thermal rocket
J Khatry, F Aydogan, M Ilyas, M Houts
Annals of Nuclear Energy 111, 536-553, 2018
112018
Implementation of the batch composition preserving genetic algorithm for burn up extension of a typical PWR
PD Muhammad ILYAS, MS Abdul RAUFF, MS Muhammad G Zia, ...
Progress in Nuclear Energy 88, 257–263, 2016
82016
The rewetting of PWR fuel cladding during post-LOCA reflood: a proposed physical explanation for the micro-scale high-frequency sputtering observed
SP Walker, M Ilyas, GF Hewitt
Proceedings of the Institution of Mechanical Engineers, Part A: Journal of …, 2012
82012
Optimization of PWR design parameters for implementation in SMRs
SIA M Ashiq, M Ilyas
Annals of Nuclear Energy 94, 123-128, 2016
72016
Severe accident analysis of the Qinshan Nuclear Power Plant and evaluation of boundary conditions for ex-vessel heat transfer
NH Hengra, M Ilyas, MH Inayat
Progress in Nuclear Energy 143, 104032, 2022
62022
Analysis of loss of residual heat removal system during mid-loop operation of a 300 MWe PWR
M Shakil, M Ilyas, F Zahid, M Ahmad, F Aydogan
Progress in Nuclear Energy 112, 1-6, 2019
62019
Pressurized water reactor core thermal-hydraulics model for flow coastdown transient
I Ahmad, M Ilyas, Z Akram
Proceedings of the Institution of Mechanical Engineers, Part A: Journal of …, 2014
52014
A new dimensionless thermal hydraulics parameter for the heat exchangers
M Ilyas, F Aydogan
Annals of Nuclear Energy 118, 154-164, 2018
42018
Rewetting process during top/bottom re-flooding of heated vertical surfaces
I Muhammad, A Masroor, PH Colin, SP Walker, GF Hewitt
ASME/JSME 2011 8th Thermal Engineering Joint Conference, T10187-T10187, 2011
42011
Numerical investigation of thermal-hydraulic design of a printed circuit steam generator
MA Khan, SA Sohail, K Waheed, W Siddique, M Ilyas, F Aydogan, ...
Annals of Nuclear Energy 186, 109736, 2023
32023
Modeling of corrosion-induced blockages on radiation heat transfer by using RELAP5-3D
J Khatry, F Aydogan, M Ilyas, M Houts
Progress in Nuclear Energy 112, 123-134, 2019
32019
Study of gamma irradiation effects on coaxial cables
AH Malik, M Ahmad, R Hussain, M Ilyas, N Irfan
2015 Power Generation System and Renewable Energy Technologies (PGSRET), 1-4, 2015
32015
Rewetting processes during top/bottom re-flooding of heated vertical surfaces
M Ilyas, M Ahmad, CP Hale, SP Walker, GF Hewitt
ASME/JSME Thermal Engineering Joint Conference 38921, T10187, 2011
22011
Modelling Rewetting of Heated Surfaces as Intermittently Bursting Liquid-Metal Contacts
M Ilyas, SP Walker, GF Hewitt
International Conference on Nuclear Engineering 49323, 1163-1169, 2010
22010
Thermal-Hydraulic Investigation of Steady-State Single-Phase Natural Circulation of an Integral PWR-Type SMR Test Rig (iPSTR)
M Ishaq, M Ilyas, ANK Wardag, M Zaman, MH Inayat
Nuclear Science and Engineering 197 (6), 1071-1099, 2023
12023
Assessment of corium concrete interaction and impact of water ingression mechanism using top flooding strategy for a small PWR with MELCOR 2.2
NH Hengra, CH Song, SJ Kim, M Ilyas
Annals of Nuclear Energy 182, 109601, 2023
12023
Evaluation of the success of in-vessel corium retention using external reactor vessel cooling mechanism for a small PWR
NH Hengra, M Ilyas, MH Mushtaq, MH Inayat
Progress in Nuclear Energy 150, 104286, 2022
12022
Experimental and numerical study of an innovative twined tube HX design
MA Khan, MD Khalid, M Ilyas, MD Nauman, M Asim, K Waheed, ...
Annals of Nuclear Energy 195, 110185, 2024
2024
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