| 000 | 02307nam a22001697a 4500 | ||
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_c21844 _d21844 |
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| 005 | 20221006181846.0 | ||
| 008 | 221006b ||||| |||| 00| 0 eng d | ||
| 020 | _ahbk | ||
| 082 |
_a530.1 _bEv132 |
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| 100 |
_aSidra Ghalib, _bM. Phil Physics, _c2015-2017 _dSupervised by Dr. Muhammad Saeed Akhtar |
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| 245 |
_aEvaluation of production data of positron emitter 72AS, an emerging diagnostic radionuclide _c/ Sidra Ghalib |
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| 260 |
_aLahore : _bDivision of Science & Technology, University of Education, _c2018 |
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| 300 |
_ax, 109 p. _eCD |
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| 520 | _aThe radionuclides have wide range of applications in medical, agricultural, industrial, archaeology and research fields. Extensive research is being done on the production of medically used radionuclides due to their vast applications. This work includes compilation and evaluation of experimental nuclear reaction cross-section to produce 72As. 72As has a half-life of 26 hours and it is used in PET and SPECT techniques. The main purpose of this work is to study about the cross-section data evaluation for the non-generator based production of 72As. These cross-section data evaluations will be related to charge particle (proton, deuteron and alpha) induced reaction on isotope of gallium (Ga), germanium (Ge), and Selenium (Se). The production data related to 72As is available in the form of data libraries of IAEA in EXFORE. To check the accuracy of the experimental data normalization of experimental reported data was done by using standard monitor reaction and decay data. Furthermore, nuclear model calculations were performed using theoretical nuclear model codes, EMPIRE, TENDL-2015 and ALICE-IPPE, to compare the experimental and theoretical data. In this work the reactions namely 69Ga(α,n)72As, 71Ga(α,3n)72As, 71Ga(3He,2n)72As, natGe(p,x)72As, natGe(d,x)72As, 70Ge(α,n+p)72As, 70Ge(α,x)72As, 72Ge(p,n)72As, 72Ge(α,x)72As, 73Ge(p,2n)72As, 74Ge(p,3n)72As, natSe(p,x)72As, 74Se(p,x)72As, 74Se(α,x)72As, 76Se(p,n+α)72As, and 76Se(p,x)72As were considered. After the compilation of this work we will check that except for generator based production routes which production route is suitable and can give yield with minimum impurities level. | ||
| 650 | _aPhysics--Evluation--Diagnostic--Radionuclide | ||
| 942 | _cTH | ||