<?xml version="1.0" encoding="utf-8"?>
<journal>
<title>International Journal of Radiation Research</title>
<title_fa>نشریه پرتو پژوه</title_fa>
<short_title>Int J Radiat Res</short_title>
<subject>Basic Sciences</subject>
<web_url>http://ijrr.com</web_url>
<journal_hbi_system_id>79</journal_hbi_system_id>
<journal_hbi_system_user>journal79</journal_hbi_system_user>
<journal_id_issn>2322-3243</journal_id_issn>
<journal_id_issn_online>2345-4229</journal_id_issn_online>
<journal_id_pii></journal_id_pii>
<journal_id_doi>10.61882/ijrr</journal_id_doi>
<journal_id_iranmedex></journal_id_iranmedex>
<journal_id_magiran></journal_id_magiran>
<journal_id_sid></journal_id_sid>
<journal_id_nlai></journal_id_nlai>
<journal_id_science></journal_id_science>
<language>en</language>
<pubdate>
	<type>jalali</type>
	<year>1400</year>
	<month>10</month>
	<day>1</day>
</pubdate>
<pubdate>
	<type>gregorian</type>
	<year>2022</year>
	<month>1</month>
	<day>1</day>
</pubdate>
<volume>20</volume>
<number>1</number>
<publish_type>online</publish_type>
<publish_edition>1</publish_edition>
<article_type>fulltext</article_type>
<articleset>
	<article>


	<language>en</language>
	<article_id_doi></article_id_doi>
	<title_fa></title_fa>
	<title>Estimation of human absorbed dose of 68-Ga-Citrate based on biodistribution data in rats: Comparison with 67-Ga-Citrate</title>
	<subject_fa>Radiobiology</subject_fa>
	<subject>Radiobiology</subject>
	<content_type_fa>تحقيق بديع</content_type_fa>
	<content_type>Original Research</content_type>
	<abstract_fa></abstract_fa>
	<abstract>&lt;div style=&quot;text-align: justify;&quot;&gt;Background: In recent years, Gallium-68 citrate has become known as an alternative radioisotope in nuclear medicine. As for its influences, &lt;sup&gt;68&lt;/sup&gt;Ga-based tracers have already been proposed as agents for positron emission tomography. In this research, the values of human absorbed dose for &lt;sup&gt;68&lt;/sup&gt;Ga-citrate and &lt;sup&gt;67&lt;/sup&gt;Ga-citrate were estimated using the medical internal radiation dose method based on biodistribution data in rats. Materials and Methods: &lt;sup&gt;68&lt;/sup&gt;Ga/&lt;sup&gt;67&lt;/sup&gt;Ga-citrate was prepared from eluted &lt;sup&gt;68&lt;/sup&gt;Ga/&lt;sup&gt;67&lt;/sup&gt;Ga-Cl&lt;sub&gt;3&lt;/sub&gt; &amp;shy;and sodium citrate under multiple reaction forms. The biodistribution of &lt;sup&gt;68&lt;/sup&gt;Ga/&lt;sup&gt;67&lt;/sup&gt;Ga&amp;ndash;citrate radiolabeled compounds was investigated by dissection of five male rats at specific times after injection. The organs of the rats were removed and counted. Percentage of injected dose per gram was determined for each rat organ and the human absorbed dose was extrapolated using the rats&amp;rsquo; data. Results: The results of estimating the human absorbed dose illustrate that &lt;sup&gt;68&lt;/sup&gt;Ga-citrate caused a much lower human absorbed dose compared with &lt;sup&gt;67&lt;/sup&gt;Ga-citrate. Conclusion: According to the results, it may be concluded that &lt;sup&gt;68&lt;/sup&gt;Ga-citrate, despite the better quality of PET imaging, is much safer in terms of absorption dose compared with &lt;sup&gt;67&lt;/sup&gt;Ga-&amp;shy;citrate, and from this point of view, it is a more appropriate agent for imaging applications.&lt;/div&gt;
&amp;nbsp;</abstract>
	<keyword_fa></keyword_fa>
	<keyword>Internal radiation dose, MIRD, 68-Ga-citrate, 67-Ga-citrate.</keyword>
	<start_page>151</start_page>
	<end_page>156</end_page>
	<web_url>http://ijrr.com/browse.php?a_code=A-10-2188-75&amp;slc_lang=en&amp;sid=1</web_url>


<author_list>
	<author>
	<first_name>F. </first_name>
	<middle_name></middle_name>
	<last_name>Habibi</last_name>
	<suffix></suffix>
	<first_name_fa></first_name_fa>
	<middle_name_fa></middle_name_fa>
	<last_name_fa></last_name_fa>
	<suffix_fa></suffix_fa>
	<email></email>
	<code>7900319475328460020850</code>
	<orcid>7900319475328460020850</orcid>
	<coreauthor>No</coreauthor>
	<affiliation>Shiraz University, Nuclear Engineering Department, Shiraz, Iran</affiliation>
	<affiliation_fa></affiliation_fa>
	 </author>


	<author>
	<first_name>R. </first_name>
	<middle_name></middle_name>
	<last_name>Faghihi</last_name>
	<suffix></suffix>
	<first_name_fa></first_name_fa>
	<middle_name_fa></middle_name_fa>
	<last_name_fa></last_name_fa>
	<suffix_fa></suffix_fa>
	<email></email>
	<code>7900319475328460020851</code>
	<orcid>7900319475328460020851</orcid>
	<coreauthor>No</coreauthor>
	<affiliation>Shiraz University, Nuclear Engineering Department, Shiraz, Iran</affiliation>
	<affiliation_fa></affiliation_fa>
	 </author>


	<author>
	<first_name>S. </first_name>
	<middle_name></middle_name>
	<last_name>Zolghadri</last_name>
	<suffix></suffix>
	<first_name_fa></first_name_fa>
	<middle_name_fa></middle_name_fa>
	<last_name_fa></last_name_fa>
	<suffix_fa></suffix_fa>
	<email></email>
	<code>7900319475328460020852</code>
	<orcid>7900319475328460020852</orcid>
	<coreauthor>No</coreauthor>
	<affiliation>Radiation Application Research School, Nuclear Science and Technology Research Institute (NSTRI), Tehran, Iran</affiliation>
	<affiliation_fa></affiliation_fa>
	 </author>


	<author>
	<first_name>H. </first_name>
	<middle_name></middle_name>
	<last_name>Yousefnia</last_name>
	<suffix></suffix>
	<first_name_fa></first_name_fa>
	<middle_name_fa></middle_name_fa>
	<last_name_fa></last_name_fa>
	<suffix_fa></suffix_fa>
	<email>hyousefnia@aeoi.org.ir </email>
	<code>7900319475328460020853</code>
	<orcid>7900319475328460020853</orcid>
	<coreauthor>Yes
</coreauthor>
	<affiliation>Radiation Application Research School, Nuclear Science and Technology Research Institute (NSTRI), Tehran, Iran</affiliation>
	<affiliation_fa></affiliation_fa>
	 </author>


	<author>
	<first_name>S. </first_name>
	<middle_name></middle_name>
	<last_name>Sina</last_name>
	<suffix></suffix>
	<first_name_fa></first_name_fa>
	<middle_name_fa></middle_name_fa>
	<last_name_fa></last_name_fa>
	<suffix_fa></suffix_fa>
	<email></email>
	<code>7900319475328460020854</code>
	<orcid>7900319475328460020854</orcid>
	<coreauthor>No</coreauthor>
	<affiliation>Shiraz University, Radiation Research Center, Shiraz, Iran</affiliation>
	<affiliation_fa></affiliation_fa>
	 </author>


	<author>
	<first_name>F. i</first_name>
	<middle_name></middle_name>
	<last_name>Mohammadpour-Ghaz</last_name>
	<suffix></suffix>
	<first_name_fa></first_name_fa>
	<middle_name_fa></middle_name_fa>
	<last_name_fa></last_name_fa>
	<suffix_fa></suffix_fa>
	<email></email>
	<code>7900319475328460020855</code>
	<orcid>7900319475328460020855</orcid>
	<coreauthor>No</coreauthor>
	<affiliation>Radiation Application Research School, Nuclear Science and Technology Research Institute (NSTRI), Tehran, Iran</affiliation>
	<affiliation_fa></affiliation_fa>
	 </author>


</author_list>


	</article>
</articleset>
</journal>
