<?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>1391</year>
	<month>10</month>
	<day>1</day>
</pubdate>
<pubdate>
	<type>gregorian</type>
	<year>2013</year>
	<month>1</month>
	<day>1</day>
</pubdate>
<volume>11</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>Comparison of (Th-233U) O2 and (Th-235U) O2 fuel burn up into a thermal research reactor using MCNPX 2.6 code </title>
	<subject_fa>Radiation Biology</subject_fa>
	<subject>Radiation Biology</subject>
	<content_type_fa>تحقيق بديع</content_type_fa>
	<content_type>Original Research</content_type>
	<abstract_fa></abstract_fa>
	<abstract>&lt;p&gt;&lt;strong&gt;Background:&lt;/strong&gt; Decrease of economically accessible uranium resources motivates consideration of breeding of fertile elements such as thorium. &lt;strong&gt;Material and Method:&lt;/strong&gt; Thorium oxide fuel burn up calculation of a simulated research reactor cooled heavy water has been proposed in the present work using MCNPX 2.6 code. Two &lt;sup&gt;233&lt;/sup&gt;U and &lt;sup&gt;235&lt;/sup&gt;U isotopes have been used as fissile element of thorium oxide fuel. &lt;sup&gt;135&lt;/sup&gt;Xe and &lt;sup&gt;149&lt;/sup&gt;Sm reactivity variations has been studied in the core loaded (Th- &lt;sup&gt;233&lt;/sup&gt;U)O&lt;sub&gt;2&lt;/sub&gt; or (Th- &lt;sup&gt;235&lt;/sup&gt;U)O&lt;sub&gt;2&lt;/sub&gt; fuel matrixes during 3 months burn up process. &lt;strong&gt;Results:&lt;/strong&gt; Thorium oxide having 4% &lt;sup&gt;233&lt;/sup&gt;U burned 1 MW power results in less &lt;sup&gt;149&lt;/sup&gt;Sm reactivity than thorium oxide having 4% &lt;sup&gt;235&lt;/sup&gt;U burned in 0.5 MW power. &lt;sup&gt;135&lt;/sup&gt;Xe reactivity has an overestimated shift by 15 days in the core operated in 0.5 MW than the other, after 15 days both the cores behave similarly. 480 g of &lt;sup&gt;235&lt;/sup&gt;U burns into the core using 0.5 MW power and 364 g of &lt;sup&gt;233&lt;/sup&gt;U invents after 3 months. Burn up calculation of the modeled core of (Th-&lt;sup&gt;233&lt;/sup&gt;U)O&lt;sub&gt;2&lt;/sub&gt; fuel shows a fissile mass reduction by 60 days while the consumed fissile mass reaches to its initial value after 120 days. The core flux is constant during 3 months for both modeled cores. A considerable negative reactivity occurs up to 15 days in both cores which can be refer to xenon inventory during this time and then neutron multiplication factor is steadier up 3 months. &lt;strong&gt;Conclusion:&lt;/strong&gt; Breeder thorium fuel enriched &lt;sup&gt;233&lt;/sup&gt;U make several advantages of good neutronic economy, &lt;sup&gt;233&lt;/sup&gt;U inventory and less inventory of long-lived alpha emitter wastes.&lt;/p&gt;
</abstract>
	<keyword_fa></keyword_fa>
	<keyword>Thorium oxide fuel, neutronic parameters, fuel burn up, 233U fissile material, 233U fissile material</keyword>
	<start_page>29</start_page>
	<end_page>33</end_page>
	<web_url>http://ijrr.com/browse.php?a_code=A-10-1-451&amp;slc_lang=en&amp;sid=1</web_url>


<author_list>
	<author>
	<first_name>S.A.H.</first_name>
	<middle_name></middle_name>
	<last_name>Feghhi</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>790031947532846007466</code>
	<orcid>790031947532846007466</orcid>
	<coreauthor>No</coreauthor>
	<affiliation>Department of Rays Applications, Nuclear Engineering Faculty, Shahid Beheshti University, Tehran, Iran</affiliation>
	<affiliation_fa></affiliation_fa>
	 </author>


	<author>
	<first_name>Z.</first_name>
	<middle_name></middle_name>
	<last_name>Gholamzadeh</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>Cadmium_109@yahoo.com</email>
	<code>790031947532846007467</code>
	<orcid>790031947532846007467</orcid>
	<coreauthor>Yes
</coreauthor>
	<affiliation>Department of Physics, Talca University, Chile </affiliation>
	<affiliation_fa></affiliation_fa>
	 </author>


	<author>
	<first_name>L.</first_name>
	<middle_name></middle_name>
	<last_name>Soltani</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>790031947532846007468</code>
	<orcid>790031947532846007468</orcid>
	<coreauthor>No</coreauthor>
	<affiliation>Nuclear Science &amp;Technology Research Institute, AEOI, Tehran, Iran</affiliation>
	<affiliation_fa></affiliation_fa>
	 </author>


	<author>
	<first_name>C.</first_name>
	<middle_name></middle_name>
	<last_name>Tenreiro</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>790031947532846007469</code>
	<orcid>790031947532846007469</orcid>
	<coreauthor>No</coreauthor>
	<affiliation>Department of Energy Science, Sungkyunkwan University, 300 Cheoncheon-dong, Suwon, Korea</affiliation>
	<affiliation_fa></affiliation_fa>
	 </author>


</author_list>


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