Optimization of material testing research (MTR) reactors for isotope production / Rani Osama Abdalaziz ; Supervised Sayed Saleh Abdelaziz , Esmat Hanim Ali Amin , Walaa Mohamed Seif
Material type: TextLanguage: English Publication details: Cairo : Rani Osama Abdalaziz , 2016Description: 165 P. : charts , facsimiles ; 25cmOther title:- أمثلة تحميل وقود مفاعلات الأبحاث وإختبارات المواد لإنتاج النظائر المشعة [Added title page title]
- Issued also as CD
Item type | Current library | Home library | Call number | Copy number | Status | Date due | Barcode | |
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Thesis | قاعة الرسائل الجامعية - الدور الاول | المكتبة المركزبة الجديدة - جامعة القاهرة | Cai01.12.20.Ph.D.2016.Ra.O (Browse shelf(Opens below)) | Not for loan | 01010110070456000 | |||
CD - Rom | مخـــزن الرســائل الجـــامعية - البدروم | المكتبة المركزبة الجديدة - جامعة القاهرة | Cai01.12.20.Ph.D.2016.Ra.O (Browse shelf(Opens below)) | 70456.CD | Not for loan | 01020110070456000 |
Thesis (Ph.D.) - Cairo University - Faculty of Science - Department of Physics
The key parameter in radio-isotopes production in research reactors is the neutron flux. Also the long/short term plans for operation basically designed according to economical balance between utilization and cost, which made the key parameter in this balance is the consumption rate. On the other hand, the safety operation limits and condition should be satisfied in all cases. In this study searching procedures for the optimum core of Pakistan Research Reactor 1 (PARR-1) that provide neutron flux suitable for isotopes production is investigated. All cores proposed are based on the configuration of the first equilibrium core of (PARR-1). The objectives of this optimization process is to maximize the neutron flux or minimizing the consumption rate, under the constraints of the maximum discharge burnup and the maximum power peaking factor limitations. To reach the desired objectives three modifications are examined; change of the fuel density, change of the reflector configuration and change of the fuel shuffling strategy. The results show that, by increasing fuel density neutron flux decreased in the in-core irradiation positions, while by changing the reflector configuration the neutron flux increased in in-core irradiation positions, and by modifying the fuel shuffling strategy neutron flux is not clearly changed but the fuel burnup and power density distribution be better than the original one from the safety point of view
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