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Shahs Regime 1941-79

Thesis Info

Author

Fatima Hussain

Department

Deptt. of International Relations, QAU.

Program

MSc

Institute

Quaid-i-Azam University

Institute Type

Public

City

Islamabad

Province

Islamabad

Country

Pakistan

Thesis Completing Year

1990

Thesis Completion Status

Completed

Page

42

Subject

International Relations

Language

English

Other

Call No: DISS/M.Sc IR/75

Added

2021-02-17 19:49:13

Modified

2023-01-06 19:20:37

ARI ID

1676715985070

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سلطان کھاروی دی حمد نگاری

سلطان کھاروی دی نعت نگاری

نعت بھانویں کہ عربی زبان دا شبد ہے تے ایس دے معنے تعریف کرنایاں وصف بیان کرن دے نیں۔ عربی وچ ایس مقصدلئی مدح شبد دی ورتوں کیتی جاندی اے۔ پر ادبی اصطلاح وچ لفظ نعت ،رسول اکرم ﷺ دی مدح تے تعریف واسطے ورتیا جاندا اے۔

نعت وچ رسول ﷺ دی ذات تے ذات نال سمبندھ رکھن والیاں شیواں نال عقیدت، محبت تے ارادت دے نال نال آپ ؐ دے ارشادات ، پیغامات، نبوت دے مقصدنبیؐپاک دی بعثت نوں وی موضوع بنایا جاندا ے۔ ایہناں سرنانویاں اتے نعت لکھن لئی نعت نگار دا اسلامی اتہاس اتے عبورہونا، قرآن و احادیث اتے ڈونگھی نظر، سیرت رسولﷺ بارے جانکاری تے علم عمرانیات دا ماہر ہونا ات ضروری اے۔فیر ای اوہدی نعت وچ ڈونگھیائی تے اثر پیدا ہوسکدا اے۔ کیوں جے نعت وچ سیرت دا جے کوئی واقعہ بیان کیتا جاوے تے اوہدی سند یاحوالہ نہایت احترام نال پیش کیتاجاوے، پئی نعت دی روح پھٹر نہ ہووے تے تاثیر وی دونی ہوجاوے۔

نعت و چ لفظاں دی ورتوں بہوں سوچ سمجھ کے کیتی جاندی اے ، ایس لئی نعت وچ اک اک شبد اُتے غور کیتا جاندا اے پئی اوہ جذبے تے خیال دے نال نال موزوں تے مناسب وی اے یاں نہیں، کدھرے اوہدی ور توں نال لغت وچ بے ادبی یاں گستاخی دا کوئی پہلو تاں نہیں نکلدا۔ اجہیا اک وی شبد پوری لغت دے تقدس نوں پھٹر کر دیندا اے تے ثواب دی تھاں گناہ جھولی وچ پہ جاندے نیں ۔ ایس لئی کئی کوی ہرقسم دیاں شعری صلاحیتاں رکھن دے باوجود نعت آکھن توں کنب جاندے نیں ۔ پئی کدھرے کوئی بے ادبی دے مرتکب نہ ہوجاون، کیوں جے نعت آکھنا کوئی سوکھا کم نہیں سگوں والوں نکی پل صراط توں...

تعمیر شخصیت کے بنیادی اصول قرآن و سنت کی روشنی میں

Considering the context of this sermon one can see how Hazrat has adapted to the general tendencies of society. Where people are completely immersed in worldlinees. Today our situation is that every one is engaged in the pursuit of wealth and the worldliness has become the target of all. Hazrat Ali (RA) introduced the Quran as a guide in such a case. Calling Quran the book of life, he called it a solution of all the problems of the human society.

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.