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Dr. Masood Iqbal
Dr. Masood Iqbal
Researcher PINSTECH
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Title
Cited by
Cited by
Year
Atmospheric dispersion modeling for an accidental release from the Pakistan Research Reactor-1 (PARR-1)
SS Raza, M Iqbal
Annals of Nuclear Energy 32 (11), 1157-1166, 2005
652005
Model validation and higher order sliding mode controller design for a research reactor
SH Qaiser, AI Bhatti, M Iqbal, R Samar, J Qadir
Annals of Nuclear Energy 36 (1), 37-45, 2009
422009
Fault diagnosis of Pakistan Research Reactor-2 with data-driven techniques
F Jamil, M Abid, I Haq, AQ Khan, M Iqbal
Annals of Nuclear Energy 90, 433-440, 2016
342016
Estimation of precursor concentration in a research reactor by using second order sliding mode observer
SH Qaiser, AI Bhatti, M Iqbal, R Samar, J Qadir
Nuclear Engineering and Design 239 (10), 2134-2140, 2009
312009
Measurements of radionuclides in coal samples from two provinces of Pakistan and computation of External γ ray dose rate in coal mines
K Jamil, S Ali, M Iqbal, AA Qureshi, HA Khan
Journal of environmental radioactivity 41 (2), 207-216, 1998
281998
Neutronic analysis for core conversion (HEU–LEU) of Pakistan research reactor-2 (PARR-2)
T Mahmood, S Pervez, M Iqbal
Annals of Nuclear Energy 35 (8), 1440-1446, 2008
262008
Neutronic and thermal hydraulic analysis for production of fission molybdenum-99 at Pakistan Research Reactor-1
A Mushtaq, M Iqbal, IH Bokhari, T Mahmood, T Mahmood, Z Ahmad, ...
Annals of Nuclear Energy 35 (2), 345-352, 2008
252008
Study of the void coefficients of reactivity in a typical pool type research reactor
M Iqbal, NM Mirza, SM Mirza, SK Ayazuddin
Annals of Nuclear Energy 24 (3), 177-186, 1997
251997
Management of radioactive waste from molybdenum-99 production using low enriched uranium foil target and modified CINTICHEM process
A Mushtaq, M Iqbal, A Muhammad
Journal of radioanalytical and nuclear chemistry 281 (3), 379, 2009
232009
Uncertainty quantification, sensitivity analysis, and data assimilation for nuclear systems simulation
H Abdel-Khalik, P Turinsky, M Jessee, J Elkins, T Stover, M Iqbal
Nuclear Data Sheets 109 (12), 2785-2790, 2008
182008
Flow of kinetic parameters in a typical swimming pool type research reactor
M Iqbal, T Mahmood, S Pervez
Annals of Nuclear Energy 35 (3), 518-524, 2008
182008
Low enriched uranium foil plate target for the production of fission Molybdenum-99 in Pakistan Research Reactor-1
A Mushtaq, M Iqbal, IH Bokhari, T Mahmood
Nuclear Instruments and Methods in Physics Research Section B: Beam …, 2009
172009
Fission MOLY production at PARR-1 using LEU plate type target
A Mohammad, T Mahmood, M Iqbal
Nuclear Engineering and Design 239 (3), 521-525, 2009
172009
A comparative study to investigate burnup in research reactor fuel using two independent experimental methods
M Iqbal, T Mehmood, SK Ayazuddin, A Salahuddin, S Pervez
Annals of Nuclear Energy 28 (17), 1733-1744, 2001
162001
Critical and power experiments on the low-enriched uranium core of the upgraded Pakistan Research Reactor-1
SA Ansari, M Iqbal, L Ali, NM Butt
Nuclear technology 108 (1), 13-23, 1994
121994
Parametric tests and measurements after shimming of a beryllium reflector in a miniature neutron source reactor (MNSR)
M Iqbal, M Abdullah, S Pervez
Annals of Nuclear Energy 29 (13), 1609-1624, 2002
112002
On comparison of experimental and calculated neutron energy flux spectra at miniature neutron source reactor (MNSR)
M Iqbal, A Muhammad, T Mahmood, N Ahmed
Annals of Nuclear Energy 35 (2), 209-215, 2008
102008
System identification and robust controller design for pool type research reactor
SH Qaiser, AI Bhatti, M Iqbal, J Qadir
Proceedings of 13th IEEE/IFAC International Conference on Methods and Models …, 2007
102007
Optimization study and neutronic design calculations of LEU fuelled homogeneous aqueous solution nuclear reactors for the production of short lived fission product isotopes
T Mahmood, M Iqbal
Annals of Nuclear Energy 42, 175-178, 2012
82012
Defect sizing of post-irradiated nuclear fuels using grayscale thresholding in their radiographic images
UK Chaudhary, M Iqbal, M Ahmad
Nuclear Engineering and Design 240 (10), 3455-3461, 2010
82010
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