Production Cycle for Large Scale Fission Mo-99 Separation by the Processing of Irradiated LEU Uranium Silicide Fuel Element Targets

المؤلف

Sameh, Abdel-Hadi Ali

المصدر

Science and Technology of Nuclear Installations

العدد

المجلد 2013، العدد 2013 (31 ديسمبر/كانون الأول 2013)، ص ص. 1-14، 14ص.

الناشر

Hindawi Publishing Corporation

تاريخ النشر

2013-10-30

دولة النشر

مصر

عدد الصفحات

14

التخصصات الرئيسية

العلوم الهندسية و تكنولوجيا المعلومات

الملخص EN

Uranium silicide fuels proved over decades their exceptional qualification for the operation of higher flux material testing reactors with LEU elements.

The application of such fuels as target materials, particularly for the large scale fission Mo-99 producers, offers an efficient and economical solution for the related facilities.

The realization of such aim demands the introduction of a suitable dissolution process for the applied U3Si2 compound.

Excellent results are achieved by the oxidizing dissolution of the fuel meat in hydrofluoric acid at room temperature.

The resulting solution is directly behind added to an over stoichiometric amount of potassium hydroxide solution.

Uranium and the bulk of fission products are precipitated together with the transuranium compounds.

The filtrate contains the molybdenum and the soluble fission product species.

It is further treated similar to the in-full scale proven UAlx process.

The generated off gas stream is handled also as experienced before after passing through KOH washing solution.

The generated alkaline fluoride containing waste solution is noncorrosive.

Nevertheless fluoride can be selectively bonded as in soluble CaF2 by addition of a mixture of solid calcium hydroxide calcium carbonate to the sand cement mixture used for waste solidification.

The generated elevated amounts of LEU remnants can be recycled and retargeted.

The related technology permits the minimization of the generated fuel waste, saving environment, and improving processing economy.

نمط استشهاد جمعية علماء النفس الأمريكية (APA)

Sameh, Abdel-Hadi Ali. 2013. Production Cycle for Large Scale Fission Mo-99 Separation by the Processing of Irradiated LEU Uranium Silicide Fuel Element Targets. Science and Technology of Nuclear Installations،Vol. 2013, no. 2013, pp.1-14.
https://search.emarefa.net/detail/BIM-491951

نمط استشهاد الجمعية الأمريكية للغات الحديثة (MLA)

Sameh, Abdel-Hadi Ali. Production Cycle for Large Scale Fission Mo-99 Separation by the Processing of Irradiated LEU Uranium Silicide Fuel Element Targets. Science and Technology of Nuclear Installations No. 2013 (2013), pp.1-14.
https://search.emarefa.net/detail/BIM-491951

نمط استشهاد الجمعية الطبية الأمريكية (AMA)

Sameh, Abdel-Hadi Ali. Production Cycle for Large Scale Fission Mo-99 Separation by the Processing of Irradiated LEU Uranium Silicide Fuel Element Targets. Science and Technology of Nuclear Installations. 2013. Vol. 2013, no. 2013, pp.1-14.
https://search.emarefa.net/detail/BIM-491951

نوع البيانات

مقالات

لغة النص

الإنجليزية

الملاحظات

Includes bibliographical references

رقم السجل

BIM-491951