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| Content Provider | IEEE Xplore Digital Library |
|---|---|
| Author | Shirazi, S.A.M. Iilehkouhi, M.S.S. |
| Copyright Year | 2012 |
| Abstract | Whereas nowadays production and reprocessing the radionuclides are very significant and urgent, so in this paper according to operation of Isfahan Miniature Neutron Source Reactor (MNSR) that is a pool-tank reactor, the values of some radionuclides such as: 99Mo and 99mTc which are applied as radiomedicines and other radionuclides including fission products and actinides which are either fissile or fertile, within one year continues operation of reactor with the neutron flux: 10^9n/cm^2.sec have been computed. In order to calculate the values of produced radionuclides the changes of nucleuses densities through all the differential equations of atoms density variation have been written and then by solving them by numerical method and also by using the MATLAB software, according to the kind of applied fuel and its enrichment percent (UAL4 with 90.2 percent), the values of the mentioned produced radionuclides at the core of this reactor have been computed during one year. In addition based on the obtained results, the burnup of reactor's fuel has also been defined. |
| Starting Page | 1 |
| Ending Page | 4 |
| File Size | 571461 |
| Page Count | 4 |
| File Format | |
| ISBN | 9781457705458 |
| ISSN | 21574839 |
| e-ISBN | 9781457705472 |
| DOI | 10.1109/APPEEC.2012.6307050 |
| Language | English |
| Publisher | Institute of Electrical and Electronics Engineers, Inc. (IEEE) |
| Publisher Date | 2012-03-27 |
| Publisher Place | China |
| Access Restriction | Subscribed |
| Rights Holder | Institute of Electrical and Electronics Engineers, Inc. (IEEE) |
| Subject Keyword | Atomic measurements Radioactive materials Zirconium Neutrons Fuels Inductors Niobium |
| Content Type | Text |
| Resource Type | Article |
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