ATOM INDONESIA JOURNAL
Referee’s Report
Article No. : # 465
Title of Paper : Development of 99Mo/99mTc generator column using Zirconium Based Material (ZBM) for the production of 99mTc radioisotope
Referee Name :
Comment on Descriptions 1. Title
[ ] Appropriate [ x ] Should be changed
2. Abstract
Yes[x ] No[ ] Is the length reasonable?
Yes[ ] No[ x ] Is it an appropriate summary of the content?
3. Main Text
Yes[x ] No[ ] Is there anything new in this work?
Yes[ x ] No[ ] Is the relation to previous studies adequately stated?
Yes[x ] No[ ] Are the assumption(s) and/or method(s) described comprehensively?
Yes[x ] No[ ] Are the new results adequately emphasized?
Line # Referee’s Comments
10 - 11
The abstract might need to be reconstructed as a) It has not showed any introduction b) The method need to be simplified
Mo-99 produced from fission of U-235 is the most desirable precursor for 99Mo/99mTc generator system as it is non-carrier added and has high specific activity. However, in the last decade there has been short supply of 99Mo due to some constrains. Therefore, there have been many works performed for development of 99Mo/99mTc generator system using
99Mo which is not produced from either LEU or HEU. This report deals with development of 99Mo/99mTc generator system where zirconium based material (ZBM) used as adsorbent of neutron-activated 99Mo. The system was prepared by firstly irradiating natural Mo in G.A. Siwabessy Reactor to produce neutron activated 99Mo. The target was dissolved in NaOH 4N and then neutralized with 12 M HCl. The 99Mo solution was then mixed with a certain amount of ZBM followed by heating at 90oC for three hours to allow the 99Mo adsorbed on ZBM. The 99Mo-ZBM (9.36 GBq of 99Mo was Mo/ 4.2 g ZBM) was packed on a fritz-glass column. This column was then fitted serially with an alumina column for trapping 99Mo breakthrough. The columns were then eluted daily with saline solution for up to one week. The yield of 99mTc was found to be between 53.7 – 74% (n= 5). All 99mTc eluates were clear solutions with pH of 5. Breakthrough of 99Mo in 99mTc eluates was found to be 0.031 ± 0.019 Ci 99Mo/ mCi 99mTc (n= 5) which was less than the maximum activity of Mo allowed in 99mTc solution (< 1 µCi 99Mo/mCi 99mTc). Aluminum breakthrough in
99mTc eluates was found to be less than 5 ppm. The radiochemical purity of 99mTc in form of Na99mTcO4 was > 99 %. Radiolabeling of this 99mTc towards kit methylene diphosphonate (MDP) gave radiolabelling efficiencies of 99%. In summary, a new 99Mo/99mTc generator system which used neutron-activated 99Mo and ZBM as its adsorbent has been successfully prepared. The 99mTc produced from this new 99Mo/99mTc generator system conformed to the quality of 99mTc required for medical purposes.
31 …by eluting the 99Mo/99mTc generator system 39 …results in a high
57 ….included the use of…
87 ….in terms of pasca irradiation…
90 …used as a target.
109 - 110
In sort, 0.21 mol zirconium ………..0.27 mol tetrahydrofurane …..0.43 mol isopropyl alcohol.
Note: remove all ‘of”
137 …dose calibrator (Atom Lab 100 plus).
164 ….radionuclide…
196 ….using ZBM as absorbent of 99Mo….
261 ….decay after 22.89 hours of growing time.
Note: remove is 270 -
271
It is reported that Mo adsorption and release on ZBM occur through ion exchange cycle mechanism as shown in Figure3 [x].
Note: This statement requires a reference….
275 ……replace chloride ion…
318 - 324
Figure 4
a. It is suggested these four graphs could be present in one combined-graph (3 dimensions) so the data could be easily compared
b. It is suggested to use MatLab software in order to have more presentable graph.
378 ….used in nuclear medicine (<1Ci 99Mo/mCi 99mTc) [14???]
Note: This statement requires a reference….
380 - 390
Alumina….
This section has to be put in a new paragraph
The use of aluminum column in order to hold the 99Mo breakthrough might result in a breakthrough of aluminum in Na99TcO4 solution. Therefore the aluminum content in Na99TcO4 solution has to be determine. Aluminum content……. Na99TcO4 solution used in nuclear medicine [14???].
401 -
402 Figure 5 need to be moved to…..just after paragraph The use of aluminum…
410-
419 This paragraph has to be removed/ deleted as the same paragraph already appeared on 391- 400.
436-
437 Figure 6 has to be moved to …just after paragraph The radiochemical purity of the….
421 …on Na99TcO4 solution retrieved….
431
….1) the adsorption process of 99Mo toward ZBM for formation of 99Mo-ZMB was time consuming;
2) the activity was much lower compared to the 99Mo/99mTc generator system where 99Mo used from a fission of HEU/ LEU.
451-
452 Figure 7…..Please use MatLab software in order to have more presentable graph.
492 ….with a quality which conforms to the….
Final comments and recommendations:
The suggested title “Development 99Mo/99mTc generator system for production of medical radionuclide
99mTc using a neutron-activated 99Mo and Zirconium Based Material (ZBM) as its adsorbent”
This paper is recommended to be [ ] Accepted without further revision [x ] Accepted with minor revision [ ] Major Revision is required [ ] Rejected
