Characteristics of the neutron field of the facility at DIN-UPM
A new source facility (241Am–Be) has been installed in a bunker-type room of large dimensions. To characterise the neutron fields in the facility, detailed calculations have been made with MCNP-4C, showing the different components of the neutron radiation reaching the reference points (direct, insca...
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| Veröffentlicht in: | Radiation protection dosimetry 2004-01, Vol.110 (1-4), p.73-79 |
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| container_title | Radiation protection dosimetry |
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| creator | Gallego, E. Lorente, A. Vega-Carrillo, H.R. |
| description | A new source facility (241Am–Be) has been installed in a bunker-type room of large dimensions. To characterise the neutron fields in the facility, detailed calculations have been made with MCNP-4C, showing the different components of the neutron radiation reaching the reference points (direct, inscattered, backscattered). The contribution from neutrons scattered in the walls to the total ambient dose equivalent remains reasonably low ( |
| doi_str_mv | 10.1093/rpd/nch199 |
| format | Article |
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To characterise the neutron fields in the facility, detailed calculations have been made with MCNP-4C, showing the different components of the neutron radiation reaching the reference points (direct, inscattered, backscattered). The contribution from neutrons scattered in the walls to the total ambient dose equivalent remains reasonably low (<10%) in the reference points. Additionally, spectra measurements have been performed with a Bonner spheres spectrometer with a 6LiI(Eu) scintillator (0.4 ∅ × 0.4 cm2), UTA4 response matrix and BUNKIUT unfolding code. The calculated and experimentally obtained spectra are compared, with small differences found in the epithermal and thermal region, attributable to the concrete composition used in the calculations. The H*(10) rate has been determined from the spectra, and then compared to the reading of an active dosemeter (LB6411), with differences found lower than 8%.</description><identifier>ISSN: 0144-8420</identifier><identifier>EISSN: 1742-3406</identifier><identifier>DOI: 10.1093/rpd/nch199</identifier><identifier>PMID: 15353625</identifier><language>eng</language><publisher>England: Oxford University Press</publisher><subject>Algorithms ; Americium - analysis ; Beryllium - analysis ; Computer Simulation ; Equipment Failure Analysis - methods ; Equipment Failure Analysis - standards ; Japan ; Models, Chemical ; Monte Carlo Method ; Neutrons ; Radiation Dosage ; Radiation Protection - methods ; Radiation Protection - standards ; Radioisotopes - analysis ; Radiometry - methods ; Radiometry - standards ; Reference Standards ; Scattering, Radiation ; Spain</subject><ispartof>Radiation protection dosimetry, 2004-01, Vol.110 (1-4), p.73-79</ispartof><lds50>peer_reviewed</lds50><woscitedreferencessubscribed>false</woscitedreferencessubscribed><citedby>FETCH-LOGICAL-c387t-cbdb77cebf5e18883a014393237f420642f8e24232641b615a18e1cfb3b14bcc3</citedby><cites>FETCH-LOGICAL-c387t-cbdb77cebf5e18883a014393237f420642f8e24232641b615a18e1cfb3b14bcc3</cites></display><links><openurl>$$Topenurl_article</openurl><openurlfulltext>$$Topenurlfull_article</openurlfulltext><thumbnail>$$Tsyndetics_thumb_exl</thumbnail><link.rule.ids>314,780,784,27915,27916</link.rule.ids><backlink>$$Uhttps://www.ncbi.nlm.nih.gov/pubmed/15353625$$D View this record in MEDLINE/PubMed$$Hfree_for_read</backlink></links><search><creatorcontrib>Gallego, E.</creatorcontrib><creatorcontrib>Lorente, A.</creatorcontrib><creatorcontrib>Vega-Carrillo, H.R.</creatorcontrib><creatorcontrib>International Organization for Standardization</creatorcontrib><title>Characteristics of the neutron field of the facility at DIN-UPM</title><title>Radiation protection dosimetry</title><addtitle>Radiat Prot Dosimetry</addtitle><description>A new source facility (241Am–Be) has been installed in a bunker-type room of large dimensions. To characterise the neutron fields in the facility, detailed calculations have been made with MCNP-4C, showing the different components of the neutron radiation reaching the reference points (direct, inscattered, backscattered). The contribution from neutrons scattered in the walls to the total ambient dose equivalent remains reasonably low (<10%) in the reference points. Additionally, spectra measurements have been performed with a Bonner spheres spectrometer with a 6LiI(Eu) scintillator (0.4 ∅ × 0.4 cm2), UTA4 response matrix and BUNKIUT unfolding code. The calculated and experimentally obtained spectra are compared, with small differences found in the epithermal and thermal region, attributable to the concrete composition used in the calculations. The H*(10) rate has been determined from the spectra, and then compared to the reading of an active dosemeter (LB6411), with differences found lower than 8%.</description><subject>Algorithms</subject><subject>Americium - analysis</subject><subject>Beryllium - analysis</subject><subject>Computer Simulation</subject><subject>Equipment Failure Analysis - methods</subject><subject>Equipment Failure Analysis - standards</subject><subject>Japan</subject><subject>Models, Chemical</subject><subject>Monte Carlo Method</subject><subject>Neutrons</subject><subject>Radiation Dosage</subject><subject>Radiation Protection - methods</subject><subject>Radiation Protection - standards</subject><subject>Radioisotopes - analysis</subject><subject>Radiometry - methods</subject><subject>Radiometry - standards</subject><subject>Reference Standards</subject><subject>Scattering, Radiation</subject><subject>Spain</subject><issn>0144-8420</issn><issn>1742-3406</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2004</creationdate><recordtype>article</recordtype><sourceid>EIF</sourceid><recordid>eNpFkEtLAzEUhYMotlY3_gCZtRCbd2ZWIqO2hfoAWxA3IckkdLQvkhTsvzcyPriLC_d8XM45AJxjdIVRRYdh2wzXdoGr6gD0sWQEUobEIegjzBgsGUE9cBLjO0JEVpwdgx7mlFNBeB9c1wsdtE0utDG1NhYbX6SFK9Zul8JmXfjWLZvfo9e2XbZpX-hU3E4e4fz54RQceb2M7uxnD8D8_m5Wj-H0aTSpb6bQ0lImaE1jpLTOeO5wWZZUZ2-0ooRKn_0JRnzpCCOUCIaNwFzj0mHrDTWYGWvpAFx2f23YxBicV9vQrnTYK4zUdwsqt6C6FjJ80cHbnVm55h_9iZ0B2AE5tPv803X4UEJSydX49U3N6pkY5VEv9AtjZmbj</recordid><startdate>20040101</startdate><enddate>20040101</enddate><creator>Gallego, E.</creator><creator>Lorente, A.</creator><creator>Vega-Carrillo, H.R.</creator><general>Oxford University Press</general><scope>BSCLL</scope><scope>CGR</scope><scope>CUY</scope><scope>CVF</scope><scope>ECM</scope><scope>EIF</scope><scope>NPM</scope><scope>AAYXX</scope><scope>CITATION</scope></search><sort><creationdate>20040101</creationdate><title>Characteristics of the neutron field of the facility at DIN-UPM</title><author>Gallego, E. ; Lorente, A. ; Vega-Carrillo, H.R.</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c387t-cbdb77cebf5e18883a014393237f420642f8e24232641b615a18e1cfb3b14bcc3</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>2004</creationdate><topic>Algorithms</topic><topic>Americium - analysis</topic><topic>Beryllium - analysis</topic><topic>Computer Simulation</topic><topic>Equipment Failure Analysis - methods</topic><topic>Equipment Failure Analysis - standards</topic><topic>Japan</topic><topic>Models, Chemical</topic><topic>Monte Carlo Method</topic><topic>Neutrons</topic><topic>Radiation Dosage</topic><topic>Radiation Protection - methods</topic><topic>Radiation Protection - standards</topic><topic>Radioisotopes - analysis</topic><topic>Radiometry - methods</topic><topic>Radiometry - standards</topic><topic>Reference Standards</topic><topic>Scattering, Radiation</topic><topic>Spain</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>Gallego, E.</creatorcontrib><creatorcontrib>Lorente, A.</creatorcontrib><creatorcontrib>Vega-Carrillo, H.R.</creatorcontrib><creatorcontrib>International Organization for Standardization</creatorcontrib><collection>Istex</collection><collection>Medline</collection><collection>MEDLINE</collection><collection>MEDLINE (Ovid)</collection><collection>MEDLINE</collection><collection>MEDLINE</collection><collection>PubMed</collection><collection>CrossRef</collection><jtitle>Radiation protection dosimetry</jtitle></facets><delivery><delcategory>Remote Search Resource</delcategory><fulltext>fulltext</fulltext></delivery><addata><au>Gallego, E.</au><au>Lorente, A.</au><au>Vega-Carrillo, H.R.</au><aucorp>International Organization for Standardization</aucorp><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>Characteristics of the neutron field of the facility at DIN-UPM</atitle><jtitle>Radiation protection dosimetry</jtitle><addtitle>Radiat Prot Dosimetry</addtitle><date>2004-01-01</date><risdate>2004</risdate><volume>110</volume><issue>1-4</issue><spage>73</spage><epage>79</epage><pages>73-79</pages><issn>0144-8420</issn><eissn>1742-3406</eissn><abstract>A new source facility (241Am–Be) has been installed in a bunker-type room of large dimensions. To characterise the neutron fields in the facility, detailed calculations have been made with MCNP-4C, showing the different components of the neutron radiation reaching the reference points (direct, inscattered, backscattered). The contribution from neutrons scattered in the walls to the total ambient dose equivalent remains reasonably low (<10%) in the reference points. Additionally, spectra measurements have been performed with a Bonner spheres spectrometer with a 6LiI(Eu) scintillator (0.4 ∅ × 0.4 cm2), UTA4 response matrix and BUNKIUT unfolding code. The calculated and experimentally obtained spectra are compared, with small differences found in the epithermal and thermal region, attributable to the concrete composition used in the calculations. The H*(10) rate has been determined from the spectra, and then compared to the reading of an active dosemeter (LB6411), with differences found lower than 8%.</abstract><cop>England</cop><pub>Oxford University Press</pub><pmid>15353625</pmid><doi>10.1093/rpd/nch199</doi><tpages>7</tpages></addata></record> |
| fulltext | fulltext |
| identifier | ISSN: 0144-8420 |
| ispartof | Radiation protection dosimetry, 2004-01, Vol.110 (1-4), p.73-79 |
| issn | 0144-8420 1742-3406 |
| language | eng |
| recordid | cdi_crossref_primary_10_1093_rpd_nch199 |
| source | MEDLINE; Oxford Journals |
| subjects | Algorithms Americium - analysis Beryllium - analysis Computer Simulation Equipment Failure Analysis - methods Equipment Failure Analysis - standards Japan Models, Chemical Monte Carlo Method Neutrons Radiation Dosage Radiation Protection - methods Radiation Protection - standards Radioisotopes - analysis Radiometry - methods Radiometry - standards Reference Standards Scattering, Radiation Spain |
| title | Characteristics of the neutron field of the facility at DIN-UPM |
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