مرزا نیاز احمد بیگ
افسوس ہے کہ ۷؍ فروری کو دارالمصنفین کے ایک قدیم رکن مرزا نیاز احمد بیگ بھی رحلت فرماگئے، وہ اعظم گڑھ کے ممتاز اور کامیاب وکیل اور شہر کے عمائد میں تھے، مولانا شبلیؒ اور ان سے نسبت رکھنے والے تمام اداروں سے ان کو بڑا تعلق تھا، شبلیؒ نیشنل پوسٹ گریجویٹ کالج کی مجلس انتظامیہ کے برسوں رکن اور نائب صدر رہے، اب ان کی تمام تر توجہ دارالمصنفین کی طرف مرکوز ہوگئی تھی جس کی مجلس انتظامیہ کے وہ آخر دم تک رکن رہے، دارالمصنفین کے نازک اور بحرانی دور میں ان کے مفید قانونی مشوروں سے اس کو بڑا فائدہ پہنچا، اب وہ اپنے ایک سچے بہی خیرخواہ اور مخلص ہمدرد سے محروم ہوگیا، وہ صوم و صلوٰۃ کے ہمیشہ سے پابند رہے، حج بیت اﷲ سے بھی مشرف ہوئے، آخر عمر میں ان کی دینداری زیادہ بڑھ گئی تھی، علماء و صلحاء سے بھی تعلق رکھتے تھے، حضرت مولانا سید ابوالحسن علی ندوی سے خاص عقیدت تھی، اﷲ تعالےٰ ان کی بشری لغزشوں سے درگذر فرمائے۔ اور انھیں اپنے جوار رحمت میں جگہ دے۔
(ضیاء الدین اصلاحی، فروری ۱۹۸۸ء)
The world has been changing ever since its creation, yet the pace of change in the last one hundred years or so has been the most rapid ever. The effects of these changes were beyond the limitations of time and region and therefore they directly affected the Muslim world as well. Muslim scholars did not ignore these changes and realized their responsibilities and wrote books of Sīrah which provided guidance in connection with these rapid changes and conditions. This research has highlight an important issue of the conflict between religions, its inception, history and primarily focused on the opinions of the authors of selected books of Sῑrah written in recent past. This research has also elaborated the modern approaches in Sῑrah writing. The study has mainly focused on significant Sῑrah books of three languages i.e. Arabic, English and Urdu. These books include Fiqh Al Sῑrah by Muḥammad Sa’īd Ramaḍān Al Būtī, Fiqh Al Sῑrah by Muḥammad Al Ghazālī, Madnī Mu‘āshrah by Akram Ḍīā Al ‘Umrī, The Life and the Work of the Prophet by Dr. Muḥammad Ḥamīdullāh, The Spirit of Islam by Sayīd Amīr ‘Alī, Muhammad A Biography of Prophet by Karen Armstrong, Sīrah Al Nabī by ‘Allāmah Shiblī Nu’mānī, Aṣaḥ Al Sῑyar by ‘Abdul Raūf Dānāpūrī, Ḍīā Al Nabī by Pīr Muḥammad Karam Shāh, Sīrati Sarwari ‘Alam by Abūl A‘lā Mūdūdī, Raḥmatullil'ālamīn by Qāḍī Muhammad Sulymān Manṣūrpūrī and Muḥammad Rasūlallāh by Sayīd Muḥammad Mīyān.
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.