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فائر ایریا

فائر ایریا

                ایسا ہی ایک ناول جس میں پس ماندگی کے مظاہرنظر آتے ہیں۔اس میں ’’فائر ایریا‘‘ازالیاس احمد گدی بھی اپنی مثال آپ ہے۔ناول میں مصنف نے مزدوروں کے ساتھ ہونے والے سلوک کو پیش کیاہے۔بھوک کو موضوع بنایا ہے یہ بھوک ہی ہے جو اس قدرتڑپ پیدا کرتی ہے کہ ایک انسان مفید اور مضر کے معنی بھول جاتا ہے۔وہ بس یہی خیال کرتاہے کہ کس طرح سے انھیں اپنے پیٹ کی آگ کو بجھانا ہے۔بغور مطالعہ کیا جائے توہندوستان میں صدیوں سے ذات پات کا نظام چلتا آرہا ہے۔آج کے دور میں بھی ذات پات کا نظام اور اس کے اثرات  دیہات اور خاص طور پر نچلے اور مڈل کلاس طبقے میں نظر آتے ہیں اور اسی نظام نے زندگی کو خاشیے پہ لا کھڑا کیا ہے۔مزدوروں کے ساتھ خصوصاً  نارواسلوک رکھا جاتا ہے۔اگر کہیں کوئی آواز بلند کی بھی گئی تو ان آوازوں کو دبا دیا گیا۔یوں کہاجائے تو غلط نہ ہوگاکہ یہ آوازیں انھی طبقوں نے بلند کی تھیں جنہوں نے خود مزدوروں کا استحصال کرنے میں کوئی کسر نہ اٹھا رکھی تھی اور آج جب ان آوازوں کو دبا دیا گیا تو قلم کی طاقت سے ہی یہ حق ادا کرنے کی کوشش کی گئی ہے۔اردوادب میں بھی متوسط اور نچلے طبقوں پر مزدوروں کے ساتھ ہونے والے اس برے سلوک اور خاص طور پر کس مپرسی کی زندگی پر آواز بلند کی گئی ہے۔مختلف افسانے لکھے گئے اور ڈراموں میں بھی اس موضوع پر بحث کرتے ہوئے اداکار نظر آئے مگر بات اداکاری پہ ہی ختم ہوگئی۔لوگوںکے دلوں میں خلش ہی رہ گئی۔اس سلسلے کی ایک کڑی ہمیں ’’فائر ایریا‘‘کی صورت میں نظر آئی۔ناول پڑھتے ہوئے قاری اس زندگی کو محسوس کرتا ہے جہاں ایک عام انسان اپنا دم گھٹتا محسوس کرتا ہے اور ناول میں...

مولانا ابو الکلام آزاد‌ کا تفسیری اسلوب: سورة الکہف کا خصوصی مطالعہ

Since about the middle of the 19th century, numerous attempts have been made by Muslim  scholars to interpret the Qur’ān  to the modern world. By far the largest output of literature produced in this connection, whether in the form of commentaries, critiques or articles in periodical, has been in Urdu, English and Arabic. But whatever the medium of expression employed, the net result is still is far from satisfactory.               Moulana Abul Kalam Azad (1888-1958) was one of the most notable Muslim figures in Sub-continent. The Tarjuman-al-Qur’ān  is regarded on all hands as his main contribution to Islamic learning. His original plan was to prepare side by side two companion volumes to this great of his, one entitled Tafsir-al-Bayana affording a detailed commentary of the Qur’ān, the other entitled Muqaddima, to serve as prolegomena to the Tarjuman -al-Qur’ān. The circumstances of his life did not allow him the time that he needed to execute the two projects. Moulana Azad, s thinking and philosophy about commentary of the Qur’ān  is very clear: ''Explain the Qur’ān  in the manner of the Qur’ān ''.                This paper attempts to enlighten many aspects of Moulana Azad, s commentary of Surat-al-Kahaf and explores his contribution and Comparative Analysis for other selected Urdu Tafasir of his era.

Static and Dynamic Simulation of Heu and Leu Cores of Research Reactors Using Multi-Group and Coupled Space-Time Thermal Hydraulic Approach

Sadaf Waqar, PhD, Department of Physics & Applied Mathematics, PIEAS, June 2008." Static and Dynamic Simulation of HEU and LEU Cores of Research Reactors using Multi- group and Coupled Space-Time Thermal Hydraulic Approach”; Supervisor: Dr. Nasir M. Mirza; Co-Supervisor: Dr. Sikander M. Mirza; Department of Physics & Applied Mathematics, PIEAS, Nilore 45650, Islamabad. A comparative study has been performed for neutronic analysis of HEU and potential LEU cores for the Pakistan Research Reactor-2 (PARR-2) taken as a typical MNSR system. The group constant generation has been carried out using transport theory code WIMS-D4 and a detailed five-group RZ-model has been used in the CITATION code for multigroup diffusion theory analysis. The neutronic analysis of the 90% HEU (reference fuel) and potential LEU alternative fuels: UO2, U3Si2 and U9Mo, has been carried out yielding 11%, 20.7% and 14.25% enrichments with corresponding values of excess reactivity: 4.33, 4.30 and 4.07 mk. These results have been found in good agreement with recently reported Monte Carlo based transport theory calculations. The diffusion theory based calculated values of thermal flux profiles for axial as well as for radial directions have been found to agree well with the corresponding experimental measurements. The UO2 based LEU core has been found having flux spectrum closest to the reference core while U9Mo core has significantly harder flux spectrum at irradiation site. Fuel burn-up study and buildup of actinides and fission products for potential LEU fuels (UO2 and U9Mo) with existing HEU fuel (UAl4-Al, 90% enriched) for a typical Miniature Neutron Source Reactor (MNSR) has been carried out using the WIMSD4 computer program. For the complete burnup, the UAl4-Al, UO2 and U9Mo based systems show a total consumption of 6.89, 6.83 and 6.88 g of Relative to 0.042 g 235 U respectively. 239 Pu produced in case of UAl4-Al HEU core, UO2 and U9Mo based cores have been found to yield 0.793 and 0.799 g respectively indicating much larger values of conversion-ratios and correspondingly high values of fuel utilization factor. The end-of-cycle activity of the HEU core has been found to be 2284 Ci which agrees well with the value found by Khattab [48], where as for UO2 based and U9Mo based LEU cores show 1.8% and 4.8% increase with values of 2326 and 2394 Ci respectively. A two-group, three dimensional diffusion theory based methodology coupled with one-dimensional single-phase heat transfer calculations has been developed for the transient analysis of typical material test reactors (MTRs). This methodology has been implemented in a Fortran based computed program MTRAP3. It uses the CITATION computer program for static neutronic calculations while the group constant generation is performed by employing the WIMS-D/4 code. The MTRAP3 program uses Cranck- Nicolson (CN) based numerical scheme for solution of time dependent neutron diffusion calculations while time-implicit strategy is employed for detailed heat-transfer calculations. The CN-scheme has been found to remain stable for much larger time steps (∆t~10-5 s) as compared with the time-explicit scheme which remains stable for very small time steps only (∆t~10-10 s). For step as well as for ramp reactivity induced transients, the predicted values of core integrated reactor power and core average temperatures has been found to agree well with the corresponding values found by using the PARET computer program. The assembly-wise power profile as found by the MTRAP3 program has been found consistent with the corresponding experimental measurements.
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