<?xml version="1.0" encoding="UTF-8"?>
<!DOCTYPE ArticleSet PUBLIC "-//NLM//DTD PubMed 2.7//EN" "https://dtd.nlm.nih.gov/ncbi/pubmed/in/PubMed.dtd">
<ArticleSet>
<Article>
<Journal>
				<PublisherName>Springer</PublisherName>
				<JournalTitle>Iranian Journal of Science and Technology (Sciences)</JournalTitle>
				<Issn>1028-6276</Issn>
				<Volume></Volume>
				<Issue>Articles in Press</Issue>
				<PubDate PubStatus="epublish">
					<Year>2017</Year>
					<Month>01</Month>
					<Day>25</Day>
				</PubDate>
			</Journal>
<ArticleTitle>Computation of neutron dose buildup factors for ordinary concrete in the fast range of energy: A comparative study</ArticleTitle>
<VernacularTitle></VernacularTitle>
			<FirstPage></FirstPage>
			<LastPage></LastPage>
			<ELocationID EIdType="pii">3950</ELocationID>
			
<ELocationID EIdType="doi">10.22099/ijsts.2017.3950</ELocationID>
			
			<Language>EN</Language>
<AuthorList>
<Author>
					<FirstName>Danial</FirstName>
					<LastName>Salehi</LastName>
<Affiliation>Department of radiological and Nuclear Engineering, Science and Research Branch, Islamic Azad University, Tehran, Iran</Affiliation>

</Author>
<Author>
					<FirstName>Dariush</FirstName>
					<LastName>Sardari</LastName>
<Affiliation>Department of Radiological and Nuclear Engineering, Science and Research Branch, Islamic Azad University, Tehran, Iran.</Affiliation>

</Author>
<Author>
					<FirstName>Milad</FirstName>
					<LastName>S Jozani</LastName>
<Affiliation>Faculty of Engineering, Islamic Azad University, South Tehran Branch, Tehran, Iran.</Affiliation>

</Author>
</AuthorList>
				<PublicationType>Journal Article</PublicationType>
			<History>
				<PubDate PubStatus="received">
					<Year>2015</Year>
					<Month>08</Month>
					<Day>19</Day>
				</PubDate>
			</History>
		<Abstract>In this work we calculated neutron dose buildup factor at energy interval 80-120 MeV for the calcareous type of ordinary concrete (i.e., one made of sand and aggregate composed basically of limestone) by using the data from the literature and an improved empirical fitting formula for estimating neutron buildup factors. We could estimate the removal macroscopic cross section of neutron (ƩR) in this range of energy (80-120 MeV) at various mass thicknesses (0˂X˂550) for this type of concrete. The results are compared with the Monte Carlo method.</Abstract>
		<ObjectList>
			<Object Type="keyword">
			<Param Name="value">Neutron buildup factor</Param>
			</Object>
			<Object Type="keyword">
			<Param Name="value">Mass attenuation coefficient</Param>
			</Object>
			<Object Type="keyword">
			<Param Name="value">macroscopic removal cross section</Param>
			</Object>
			<Object Type="keyword">
			<Param Name="value">Ordinary concrete</Param>
			</Object>
		</ObjectList>
</Article>
</ArticleSet>
