Rubber based neutron shielding material simulation using MCNP5

Rubber-Based Neutron Shielding Material Simulation using MCNP5. The natural rubber-based neutron radiation shielding was simulated using MCNP5 computer code. The attenuation curves of natural rubber, rubber-neoprene, rubber-silicone, natural rubber+5% Vol. Gd2O2S composite, natural rubber+25% Vol. B...

Ausführliche Beschreibung

Gespeichert in:

Bibliographische Detailangaben
Hauptverfasser:	Panitra, M. M., Aziz, F., Rivai, A. K., Sukaryo, S. G., Fisli, A., Sudirman, Parikin
Format:	Tagungsbericht
Sprache:	eng
Schlagworte:	Attenuation Borax Boron carbide Fast neutrons Lithium oxides Natural rubber Neoprene Neutrons Radiation shielding Rubber Simulation Thermal neutrons
Online-Zugang:	Volltext
Tags:	Tag hinzufügen Keine Tags, Fügen Sie den ersten Tag hinzu!

container_end_page
container_issue	1
container_start_page
container_title
container_volume	2381
creator	Panitra, M. M. Aziz, F. Rivai, A. K. Sukaryo, S. G. Fisli, A. Sudirman Parikin
description	Rubber-Based Neutron Shielding Material Simulation using MCNP5. The natural rubber-based neutron radiation shielding was simulated using MCNP5 computer code. The attenuation curves of natural rubber, rubber-neoprene, rubber-silicone, natural rubber+5% Vol. Gd2O2S composite, natural rubber+25% Vol. Borax, natural rubber+ 5% Vol. B4C, natural rubber+5% Vol. Li2O and natural rubber+5% Vol. Gd2O2S composite+Pb layer were made. The half-value layer (HVL) of each shielding was also calculated for both fast and thermal neutron. For the thermal neutron, the smallest HVL was obtained by using a composite of natural rubber+5% Vol. Gd2O2S i.e. 0.23 cm and the biggest was obtained for natural rubber+25% Vol. Borax i.e. 0.92 cm. on the other hand, for fast neutron, the smallest HVL was obtained for the shielding of Natural Rubber+5% Vol Gd2O2S i.e. 0.7 cm and Natural Rubber+25% Vol. Borax i.e. 1.23 cm. Photon was induced when thermal neutrons pass through the shielding of Natural Rubber+5% Vol Gd2O2S due to the (nth,ψ)
doi_str_mv	10.1063/5.0066597
format	Conference Proceeding
fullrecord	<record><control><sourceid>proquest_scita</sourceid><recordid>TN_cdi_proquest_journals_2596161493</recordid><sourceformat>XML</sourceformat><sourcesystem>PC</sourcesystem><sourcerecordid>2596161493</sourcerecordid><originalsourceid>FETCH-LOGICAL-p2037-8837c662d76aca0a0bd435aa8af95249002a4ba50d40bd7249a2acf8ea2cecbf3</originalsourceid><addsrcrecordid>eNp9kFtLxDAQhYMoWFcf_AcF34Suuad5EWRxVVgviIJvYdqmmqU3k1bw35t1F3zzaWC-MzNnDkKnBM8JluxCzDGWUmi1hxIiBMmUJHIfJRhrnlHO3g7RUQhrjKlWKk_Q5fNUFNanBQRbpZ2dRt93afhwtqlc9562MFrvoEmDa6cGRhfpFDbkfvHwJI7RQQ1NsCe7OkOvy-uXxW22ery5W1ytsoFiprI8Z6qUklZKQgkYcFFxJgByqLWgXEc7wAsQuOIRqdgBCmWdW6ClLYuazdDZdu_g-8_JhtGs-8l38aShQscXCdcsqs63qlC68derGbxrwX-br94bYXbZmKGq_xMTbDZh_g2wH8QcZdY</addsrcrecordid><sourcetype>Aggregation Database</sourcetype><iscdi>true</iscdi><recordtype>conference_proceeding</recordtype><pqid>2596161493</pqid></control><display><type>conference_proceeding</type><title>Rubber based neutron shielding material simulation using MCNP5</title><source>AIP Journals Complete</source><creator>Panitra, M. M. ; Aziz, F. ; Rivai, A. K. ; Sukaryo, S. G. ; Fisli, A. ; Sudirman ; Parikin</creator><contributor>Sugono, Irawan ; Mulyani, Emy ; Mujamilah ; Taufik ; Rifai, Muhammad ; Santoso, Muhayatun</contributor><creatorcontrib>Panitra, M. M. ; Aziz, F. ; Rivai, A. K. ; Sukaryo, S. G. ; Fisli, A. ; Sudirman ; Parikin ; Sugono, Irawan ; Mulyani, Emy ; Mujamilah ; Taufik ; Rifai, Muhammad ; Santoso, Muhayatun</creatorcontrib><description>Rubber-Based Neutron Shielding Material Simulation using MCNP5. The natural rubber-based neutron radiation shielding was simulated using MCNP5 computer code. The attenuation curves of natural rubber, rubber-neoprene, rubber-silicone, natural rubber+5% Vol. Gd2O2S composite, natural rubber+25% Vol. Borax, natural rubber+ 5% Vol. B4C, natural rubber+5% Vol. Li2O and natural rubber+5% Vol. Gd2O2S composite+Pb layer were made. The half-value layer (HVL) of each shielding was also calculated for both fast and thermal neutron. For the thermal neutron, the smallest HVL was obtained by using a composite of natural rubber+5% Vol. Gd2O2S i.e. 0.23 cm and the biggest was obtained for natural rubber+25% Vol. Borax i.e. 0.92 cm. on the other hand, for fast neutron, the smallest HVL was obtained for the shielding of Natural Rubber+5% Vol Gd2O2S i.e. 0.7 cm and Natural Rubber+25% Vol. Borax i.e. 1.23 cm. Photon was induced when thermal neutrons pass through the shielding of Natural Rubber+5% Vol Gd2O2S due to the (nth,ψ)</description><identifier>ISSN: 0094-243X</identifier><identifier>EISSN: 1551-7616</identifier><identifier>DOI: 10.1063/5.0066597</identifier><identifier>CODEN: APCPCS</identifier><language>eng</language><publisher>Melville: American Institute of Physics</publisher><subject>Attenuation ; Borax ; Boron carbide ; Fast neutrons ; Lithium oxides ; Natural rubber ; Neoprene ; Neutrons ; Radiation shielding ; Rubber ; Simulation ; Thermal neutrons</subject><ispartof>AIP conference proceedings, 2021, Vol.2381 (1)</ispartof><rights>Author(s)</rights><rights>2021 Author(s). Published by AIP Publishing.</rights><lds50>peer_reviewed</lds50><oa>free_for_read</oa><woscitedreferencessubscribed>false</woscitedreferencessubscribed></display><links><openurl>$$Topenurl_article</openurl><openurlfulltext>$$Topenurlfull_article</openurlfulltext><thumbnail>$$Tsyndetics_thumb_exl</thumbnail><linktohtml>$$Uhttps://pubs.aip.org/acp/article-lookup/doi/10.1063/5.0066597$$EHTML$$P50$$Gscitation$$H</linktohtml><link.rule.ids>309,310,314,776,780,785,786,790,4498,23909,23910,25118,27901,27902,76127</link.rule.ids></links><search><contributor>Sugono, Irawan</contributor><contributor>Mulyani, Emy</contributor><contributor>Mujamilah</contributor><contributor>Taufik</contributor><contributor>Rifai, Muhammad</contributor><contributor>Santoso, Muhayatun</contributor><creatorcontrib>Panitra, M. M.</creatorcontrib><creatorcontrib>Aziz, F.</creatorcontrib><creatorcontrib>Rivai, A. K.</creatorcontrib><creatorcontrib>Sukaryo, S. G.</creatorcontrib><creatorcontrib>Fisli, A.</creatorcontrib><creatorcontrib>Sudirman</creatorcontrib><creatorcontrib>Parikin</creatorcontrib><title>Rubber based neutron shielding material simulation using MCNP5</title><title>AIP conference proceedings</title><description>Rubber-Based Neutron Shielding Material Simulation using MCNP5. The natural rubber-based neutron radiation shielding was simulated using MCNP5 computer code. The attenuation curves of natural rubber, rubber-neoprene, rubber-silicone, natural rubber+5% Vol. Gd2O2S composite, natural rubber+25% Vol. Borax, natural rubber+ 5% Vol. B4C, natural rubber+5% Vol. Li2O and natural rubber+5% Vol. Gd2O2S composite+Pb layer were made. The half-value layer (HVL) of each shielding was also calculated for both fast and thermal neutron. For the thermal neutron, the smallest HVL was obtained by using a composite of natural rubber+5% Vol. Gd2O2S i.e. 0.23 cm and the biggest was obtained for natural rubber+25% Vol. Borax i.e. 0.92 cm. on the other hand, for fast neutron, the smallest HVL was obtained for the shielding of Natural Rubber+5% Vol Gd2O2S i.e. 0.7 cm and Natural Rubber+25% Vol. Borax i.e. 1.23 cm. Photon was induced when thermal neutrons pass through the shielding of Natural Rubber+5% Vol Gd2O2S due to the (nth,ψ)</description><subject>Attenuation</subject><subject>Borax</subject><subject>Boron carbide</subject><subject>Fast neutrons</subject><subject>Lithium oxides</subject><subject>Natural rubber</subject><subject>Neoprene</subject><subject>Neutrons</subject><subject>Radiation shielding</subject><subject>Rubber</subject><subject>Simulation</subject><subject>Thermal neutrons</subject><issn>0094-243X</issn><issn>1551-7616</issn><fulltext>true</fulltext><rsrctype>conference_proceeding</rsrctype><creationdate>2021</creationdate><recordtype>conference_proceeding</recordtype><recordid>eNp9kFtLxDAQhYMoWFcf_AcF34Suuad5EWRxVVgviIJvYdqmmqU3k1bw35t1F3zzaWC-MzNnDkKnBM8JluxCzDGWUmi1hxIiBMmUJHIfJRhrnlHO3g7RUQhrjKlWKk_Q5fNUFNanBQRbpZ2dRt93afhwtqlc9562MFrvoEmDa6cGRhfpFDbkfvHwJI7RQQ1NsCe7OkOvy-uXxW22ery5W1ytsoFiprI8Z6qUklZKQgkYcFFxJgByqLWgXEc7wAsQuOIRqdgBCmWdW6ClLYuazdDZdu_g-8_JhtGs-8l38aShQscXCdcsqs63qlC68derGbxrwX-br94bYXbZmKGq_xMTbDZh_g2wH8QcZdY</recordid><startdate>20211111</startdate><enddate>20211111</enddate><creator>Panitra, M. M.</creator><creator>Aziz, F.</creator><creator>Rivai, A. K.</creator><creator>Sukaryo, S. G.</creator><creator>Fisli, A.</creator><creator>Sudirman</creator><creator>Parikin</creator><general>American Institute of Physics</general><scope>8FD</scope><scope>H8D</scope><scope>L7M</scope></search><sort><creationdate>20211111</creationdate><title>Rubber based neutron shielding material simulation using MCNP5</title><author>Panitra, M. M. ; Aziz, F. ; Rivai, A. K. ; Sukaryo, S. G. ; Fisli, A. ; Sudirman ; Parikin</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-p2037-8837c662d76aca0a0bd435aa8af95249002a4ba50d40bd7249a2acf8ea2cecbf3</frbrgroupid><rsrctype>conference_proceedings</rsrctype><prefilter>conference_proceedings</prefilter><language>eng</language><creationdate>2021</creationdate><topic>Attenuation</topic><topic>Borax</topic><topic>Boron carbide</topic><topic>Fast neutrons</topic><topic>Lithium oxides</topic><topic>Natural rubber</topic><topic>Neoprene</topic><topic>Neutrons</topic><topic>Radiation shielding</topic><topic>Rubber</topic><topic>Simulation</topic><topic>Thermal neutrons</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>Panitra, M. M.</creatorcontrib><creatorcontrib>Aziz, F.</creatorcontrib><creatorcontrib>Rivai, A. K.</creatorcontrib><creatorcontrib>Sukaryo, S. G.</creatorcontrib><creatorcontrib>Fisli, A.</creatorcontrib><creatorcontrib>Sudirman</creatorcontrib><creatorcontrib>Parikin</creatorcontrib><collection>Technology Research Database</collection><collection>Aerospace Database</collection><collection>Advanced Technologies Database with Aerospace</collection></facets><delivery><delcategory>Remote Search Resource</delcategory><fulltext>fulltext</fulltext></delivery><addata><au>Panitra, M. M.</au><au>Aziz, F.</au><au>Rivai, A. K.</au><au>Sukaryo, S. G.</au><au>Fisli, A.</au><au>Sudirman</au><au>Parikin</au><au>Sugono, Irawan</au><au>Mulyani, Emy</au><au>Mujamilah</au><au>Taufik</au><au>Rifai, Muhammad</au><au>Santoso, Muhayatun</au><format>book</format><genre>proceeding</genre><ristype>CONF</ristype><atitle>Rubber based neutron shielding material simulation using MCNP5</atitle><btitle>AIP conference proceedings</btitle><date>2021-11-11</date><risdate>2021</risdate><volume>2381</volume><issue>1</issue><issn>0094-243X</issn><eissn>1551-7616</eissn><coden>APCPCS</coden><abstract>Rubber-Based Neutron Shielding Material Simulation using MCNP5. The natural rubber-based neutron radiation shielding was simulated using MCNP5 computer code. The attenuation curves of natural rubber, rubber-neoprene, rubber-silicone, natural rubber+5% Vol. Gd2O2S composite, natural rubber+25% Vol. Borax, natural rubber+ 5% Vol. B4C, natural rubber+5% Vol. Li2O and natural rubber+5% Vol. Gd2O2S composite+Pb layer were made. The half-value layer (HVL) of each shielding was also calculated for both fast and thermal neutron. For the thermal neutron, the smallest HVL was obtained by using a composite of natural rubber+5% Vol. Gd2O2S i.e. 0.23 cm and the biggest was obtained for natural rubber+25% Vol. Borax i.e. 0.92 cm. on the other hand, for fast neutron, the smallest HVL was obtained for the shielding of Natural Rubber+5% Vol Gd2O2S i.e. 0.7 cm and Natural Rubber+25% Vol. Borax i.e. 1.23 cm. Photon was induced when thermal neutrons pass through the shielding of Natural Rubber+5% Vol Gd2O2S due to the (nth,ψ)</abstract><cop>Melville</cop><pub>American Institute of Physics</pub><doi>10.1063/5.0066597</doi><tpages>11</tpages><oa>free_for_read</oa></addata></record>
fulltext	fulltext
identifier	ISSN: 0094-243X
ispartof	AIP conference proceedings, 2021, Vol.2381 (1)
issn	0094-243X 1551-7616
language	eng
recordid	cdi_proquest_journals_2596161493
source	AIP Journals Complete
subjects	Attenuation Borax Boron carbide Fast neutrons Lithium oxides Natural rubber Neoprene Neutrons Radiation shielding Rubber Simulation Thermal neutrons
title	Rubber based neutron shielding material simulation using MCNP5
url	https://sfx.bib-bvb.de/sfx_tum?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&ctx_tim=2025-01-30T15%3A44%3A29IST&url_ver=Z39.88-2004&url_ctx_fmt=infofi/fmt:kev:mtx:ctx&rfr_id=info:sid/primo.exlibrisgroup.com:primo3-Article-proquest_scita&rft_val_fmt=info:ofi/fmt:kev:mtx:book&rft.genre=proceeding&rft.atitle=Rubber%20based%20neutron%20shielding%20material%20simulation%20using%20MCNP5&rft.btitle=AIP%20conference%20proceedings&rft.au=Panitra,%20M.%20M.&rft.date=2021-11-11&rft.volume=2381&rft.issue=1&rft.issn=0094-243X&rft.eissn=1551-7616&rft.coden=APCPCS&rft_id=info:doi/10.1063/5.0066597&rft_dat=%3Cproquest_scita%3E2596161493%3C/proquest_scita%3E%3Curl%3E%3C/url%3E&disable_directlink=true&sfx.directlink=off&sfx.report_link=0&rft_id=info:oai/&rft_pqid=2596161493&rft_id=info:pmid/&rfr_iscdi=true