پرنس نجم الدین
پرنس نجم الدین کی وفات کا حادثہ اتنا الم ناک اورصدمہ انگیز ہے کہ ہمیں اس کے دوررس اثرات کے تصور ہی سے وحشت ہورہی ہے ان جیسا دردمند مسلمان، ان جیسا عالم وفاضل اورذہین شخص،ان جیسا سوشل ریفارمر،ان جیسا ماہر تعلیم اوران جیسا اعلیٰ دماغ منتظم ایک مدت سے مسلمانوں میں کوئی دوسرا نہیں تھا ،کہنے کو وہ بوہرہ فرقہ کے مسلمانوں کے روحانی پیشواؤں کے خاندان کے اہم ترین فرد تھے لیکن حقیقتاً ان کے فکر ونظر کی اڑان آفاقی تھی۔جہاں کہیں مسلمانوں کی صف میں کسی بدنظمی کے آثار ظاہر ہوتے،جہاں کہیں کسی مسلم تحریک کو مشکل درپیش ہوتی،جہاں کہیں کسی مسلم ادارہ کورہنمائی، تعاون اورمدد کی ضرورت ہوتی، ان کا دل دردمندی اوربے قراری کی شدت سے دھڑکنے لگتا اوروہ پوری توجہ اور فراخ دلی کے ساتھ اس کی طرف متوجہ ہوتے۔کتنے مسلم رہنماؤں نے ان کی دل سوزی اورہمدردی سے فیض اٹھایا،کتنے اداروں نے ان کی فیاضی اور سیر چشمی سے استحکام حاصل کیا،کتنی تحریکوں نے ان کے تعاون اورخاموش امداد سے قوت اور حوصلہ پایا۔کتنے صاحب علم وفن ان کی قدردانی اورسرپرستی سے سیراب اور فیض یاب ہوئے ان کی لامتناہی اورطویل داستان، اب ان ہی کے ساتھ خاموش ہوگئی۔
وہ مسلمانوں کی فلاحی تحریکوں کے روح رواں آدھی صدی سے زیادہ عرصے تک بنے رہے لیکن ان کی سمندروں جیسی گہرائی،ان کی فطرت کاخاموش جوہر، ان کی منکسرمزاجی نے کبھی بھی اپنے کوکھولنے اورواشگاف کرنے کے سطحی انداز کے قریب نہیں آنے دیا۔مسلمانوں کی ملّی سرگرمیوں کی سرزمین پران کا وجود سورج کی طرح تھا، جس کی کرنوں کا فیض خاص وعام کے امتیاز اورفرق کے بغیر ہرایک کے لیے دستیاب تھا۔
وہ بوہرہ فرقہ کی فلاحی اورجماعتی سرگرمیوں کاایک ایسا محور تھے کہ بلاشبہ اس کے معاشی،علمی، دینی اور سماجی امنگوں کے سارے سوتے ان...
Qasmi family has delivered uncountable services in the field of patriotism, religious norms and social reforms. Contemporarily, Muslim society seems in doldrums. Therefore, in these poor conditions, efforts done by the Qasmi family are praise worthy. In this contact. Hafiz Said Ameer Qadri Qasmi (1883-1945), Allama Muhammad Shafi Qadri Qasmi (1923-1976), Ahmad Nadeem Qasmi (1916-2006), Allama Haider Shah Qadri Qasmi (1942-2012), Sahibzada Muhammad Ahmad Qadri Qasmi (1973-2012) are the beacon of light in the list of great personalities. Therefore, to fulfill their ancestor's dreams The Al-Qasim Trust is playing an effective role in the society. In this Paper the Services of Qasmi Faimaly will be discus briefly.
The effects of change in fuel density, change in clad material and change in fuel material on the inherent safety features of a typical material test reactor were analyzed. The International Atomic Energy Agency’s 10 MW benchmark reactor was selected for the study. Standard computer codes WIMS-D4 and CITATION were used to perform neutronics calculations while PARET was used to carryout the steady state and transient thermal hydraulic analysis. In all, seven thermal hydraulic simulations were performed for each configuration. They were the steady state analysis, four controlled transients i.e. fast reactivity insertion, slow reactivity insertion, fast loss of flow and slow loss of flow transients, and two uncontrolled reactivity insertion transients, i.e. small reactivity insertion and large reactivity insertion transients. Two families of the high density dispersion fuels were analyzed to see the effect of changed uranium density on the inherent safety features of the reactor. These families were U 3 Si 2 -Al (having uranium densities of 4.10, 4.80 and 5.66 g/cm 3 ) on the lower side and U9Mo-Al (having uranium densities of 6.57, 7.74 and 8.90 g/cm 3 ) on the upper side. It was observed that the steady state thermodynamic behaviour of all the fuels was same, only the fuel temperatures of U 3 Si 2 -Al fuels showed some differences. During the fast reactivity insertion transient, the maximum reactor power achieved increased by about 29% for U 3 Si 2 fuel-family while the increase was 45% for U9Mo fuel-family. This resulted in increased maximum temperatures of fuel, clad and coolant outlet, achieved during the transient. This increase for U 3 Si 2 fuels was 32 K, 21.1 K and 5.1 K respectively, while for U9Mo fuels it was 27.7 K, 19.7 K and 7.9 K respectively for maximum fuel, clad and coolant outlet temperatures. During the slow reactivity insertion and loss of flow transients, no appreciable difference in the reactor power and temperature profiles was observed. For small reactivity insertion transient, the new power level increased as uranium density increased. The increase was 8.1% for U 3 Si 2 fuel-family while it was 5.8% for U9Mo fuel-family. In uncontrolled large reactivity insertion transient, the feedback reactivities were unable to control the reactor which resulted in the coolant boiling; the one with the highest fuel density was the first to reach the ONB. xxviiIn order to see the effects of different fuel materials, the original aluminide (UAl x -Al) fuel of the reactor was replaced with silicide (U 3 Si-Al and U 3 Si 2 -Al) and oxide (U 3 O 8 -Al) dispersion fuels having the same uranium density of 4.40 g/cm 3 as of the original fuel. The oxide fuel had higher fuel temperatures during steady state and transients. During fast reactivity insertion transient, the maximum power reached for oxide fuel was 0.35 MW lesser than that of aluminide fuel, but its maximum fuel temperature was 13 K higher. With respect to the UAl x -Al fuel, the maximum powers of U 3 Si-Al and U 3 Si 2 -Al fuels were higher by 2.11 MW and 1.82 MW respectively, while the maximum fuel temperatures were lower by 5.7 K and 4.5 K respectively. During slow reactivity insertion and loss of flow transients, the power and temperature profiles of all the fuels were almost the same only fuel temperatures varying; the maximum fuel temperature of the oxide fuel being 8 K to 12 K higher than that of the other fuels. During uncontrolled small reactivity insertion transient, the maximum fuel temperature attained by the oxide fuel was almost 16 K higher than that of the others at the new steady state. During uncontrolled large reactivity insertion transient, the coolant of oxide fuel was the last to reach the ONB but again at the cost of higher fuel temperature. In order to see the effects of different clad materials, only the Al clad and side plates of the reactor fuel were replaced by stainless steel (clad of a fast reactor) and zircaloy-4 (clad of a PWR). The zircaloy-4 clad gave a positive clad temperature feedback coefficient. The very high absorption cross section of stainless steel made it a very unlikely choice for clad material. Out of the remaining two, the main difference was in the fuel temperatures with zircaloy-4 cladded fuel having higher fuel temperatures. The temperature of zircaloy-4 cladded fuel was 20 K to 40 K higher than that of Al cladded fuel during different transients.