Evaluation of silicon neutron resonance parameters in the thermal to 1800 keV energy range
Because silicon is a major constituent of concrete and soil, neutron and gamma ray information on silicon is important for reactor shielding and criticality safety calculations. Therefore, much effort was put into the ENDF/B-VI evaluation for the three stable isotopes of silicon. The neutron capture...
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Veröffentlicht in: | Radiation protection dosimetry 2005-01, Vol.115 (1-4), p.227-231 |
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creator | Derrien, H. Leal, L. C. Guber, K. H. Larson, N. M. |
description | Because silicon is a major constituent of concrete and soil, neutron and gamma ray information on silicon is important for reactor shielding and criticality safety calculations. Therefore, much effort was put into the ENDF/B-VI evaluation for the three stable isotopes of silicon. The neutron capture cross section of natural silicon was recently measured at the Oak Ridge Electron Linear Accelerator (ORELA) in the energy range 1–700 keV. Using the ENDF/B-VI evaluation for initial values, a new evaluation of the resonance parameters was performed by adding the results of the ORELA capture measurements to the experimental database. The computer code SAMMY was used for the analysis of the experimental data; the new version of SAMMY allows accurate calculations of the self-shielding and multiple scattering effects in the capture measurements. The accuracy of the radiative capture widths of the resonances was improved by this analysis. Accurate values of the s-, p- and d-wave neutron strength functions were also obtained. Although the resonance capture component of the present evaluation is 2–3 times smaller than that in ENDF/B-VI, the total capture cross section is much larger, at least for energies >250 keV, because the direct capture component contributes values of the same order of magnitude as the resonance component. The direct component was not taken into account in the ENDF/B-VI evaluation and was calculated for the first time in the present evaluation. |
doi_str_mv | 10.1093/rpd/nci117 |
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C. ; Guber, K. H. ; Larson, N. M.</creator><creatorcontrib>Derrien, H. ; Leal, L. C. ; Guber, K. H. ; Larson, N. M.</creatorcontrib><description>Because silicon is a major constituent of concrete and soil, neutron and gamma ray information on silicon is important for reactor shielding and criticality safety calculations. Therefore, much effort was put into the ENDF/B-VI evaluation for the three stable isotopes of silicon. The neutron capture cross section of natural silicon was recently measured at the Oak Ridge Electron Linear Accelerator (ORELA) in the energy range 1–700 keV. Using the ENDF/B-VI evaluation for initial values, a new evaluation of the resonance parameters was performed by adding the results of the ORELA capture measurements to the experimental database. The computer code SAMMY was used for the analysis of the experimental data; the new version of SAMMY allows accurate calculations of the self-shielding and multiple scattering effects in the capture measurements. The accuracy of the radiative capture widths of the resonances was improved by this analysis. Accurate values of the s-, p- and d-wave neutron strength functions were also obtained. Although the resonance capture component of the present evaluation is 2–3 times smaller than that in ENDF/B-VI, the total capture cross section is much larger, at least for energies >250 keV, because the direct capture component contributes values of the same order of magnitude as the resonance component. The direct component was not taken into account in the ENDF/B-VI evaluation and was calculated for the first time in the present evaluation.</description><identifier>ISSN: 0144-8420</identifier><identifier>EISSN: 1742-3406</identifier><identifier>DOI: 10.1093/rpd/nci117</identifier><identifier>PMID: 16381717</identifier><language>eng</language><publisher>England: Oxford University Press</publisher><subject>Computer Simulation ; Data Interpretation, Statistical ; Energy Transfer ; Isotopes - analysis ; Materials Testing - methods ; Models, Chemical ; Neutron Diffraction - methods ; Neutrons ; Radiation Dosage ; Radiation Protection - instrumentation ; Radiation Protection - methods ; Radiometry - methods ; Silicon - analysis</subject><ispartof>Radiation protection dosimetry, 2005-01, Vol.115 (1-4), p.227-231</ispartof><lds50>peer_reviewed</lds50><woscitedreferencessubscribed>false</woscitedreferencessubscribed><cites>FETCH-LOGICAL-c282t-de8c4d9cf18a82364c1fdff2232becfcbb69580cd49b6111c46707f4988652673</cites></display><links><openurl>$$Topenurl_article</openurl><openurlfulltext>$$Topenurlfull_article</openurlfulltext><thumbnail>$$Tsyndetics_thumb_exl</thumbnail><link.rule.ids>314,780,784,27924,27925</link.rule.ids><backlink>$$Uhttps://www.ncbi.nlm.nih.gov/pubmed/16381717$$D View this record in MEDLINE/PubMed$$Hfree_for_read</backlink></links><search><creatorcontrib>Derrien, H.</creatorcontrib><creatorcontrib>Leal, L. C.</creatorcontrib><creatorcontrib>Guber, K. H.</creatorcontrib><creatorcontrib>Larson, N. M.</creatorcontrib><title>Evaluation of silicon neutron resonance parameters in the thermal to 1800 keV energy range</title><title>Radiation protection dosimetry</title><addtitle>Radiat Prot Dosimetry</addtitle><description>Because silicon is a major constituent of concrete and soil, neutron and gamma ray information on silicon is important for reactor shielding and criticality safety calculations. Therefore, much effort was put into the ENDF/B-VI evaluation for the three stable isotopes of silicon. The neutron capture cross section of natural silicon was recently measured at the Oak Ridge Electron Linear Accelerator (ORELA) in the energy range 1–700 keV. Using the ENDF/B-VI evaluation for initial values, a new evaluation of the resonance parameters was performed by adding the results of the ORELA capture measurements to the experimental database. The computer code SAMMY was used for the analysis of the experimental data; the new version of SAMMY allows accurate calculations of the self-shielding and multiple scattering effects in the capture measurements. The accuracy of the radiative capture widths of the resonances was improved by this analysis. Accurate values of the s-, p- and d-wave neutron strength functions were also obtained. Although the resonance capture component of the present evaluation is 2–3 times smaller than that in ENDF/B-VI, the total capture cross section is much larger, at least for energies >250 keV, because the direct capture component contributes values of the same order of magnitude as the resonance component. The direct component was not taken into account in the ENDF/B-VI evaluation and was calculated for the first time in the present evaluation.</description><subject>Computer Simulation</subject><subject>Data Interpretation, Statistical</subject><subject>Energy Transfer</subject><subject>Isotopes - analysis</subject><subject>Materials Testing - methods</subject><subject>Models, Chemical</subject><subject>Neutron Diffraction - methods</subject><subject>Neutrons</subject><subject>Radiation Dosage</subject><subject>Radiation Protection - instrumentation</subject><subject>Radiation Protection - methods</subject><subject>Radiometry - methods</subject><subject>Silicon - analysis</subject><issn>0144-8420</issn><issn>1742-3406</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2005</creationdate><recordtype>article</recordtype><sourceid>EIF</sourceid><recordid>eNpFkNFKwzAUhoMobk5vfADJtVCXk6ZJeiljOnHoLlTGbkKaJrOua0vSiXt7Ozr04vAf-D_OgQ-hayB3QNJ47Jt8XJkCQJygIQhGo5gRfoqGBBiLJKNkgC5C-CKEijRh52gAPJYgQAzRavqty51ui7rCtcOhKAvTrZXdtb5Lb0Nd6cpY3Givt7a1PuCiwu2nPYzf6hK3NQZJCN7YD2wr69d77HW1tpfozOky2KtjjtD7w_RtMovmr49Pk_t5ZKikbZRbaVieGgdSSxpzZsDlzlEa08waZ7KMp4kkJmdpxgHAMC6IcCyVkieUi3iEbvu7xtcheOtU44ut9nsFRB0EqU6Q6gV18E0PN7tsa_N_9GikA6IeKEJrf_567Teq-yUSNVuu1PNixSFdvKhl_AuMIXG3</recordid><startdate>20050101</startdate><enddate>20050101</enddate><creator>Derrien, H.</creator><creator>Leal, L. 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M.</au><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>Evaluation of silicon neutron resonance parameters in the thermal to 1800 keV energy range</atitle><jtitle>Radiation protection dosimetry</jtitle><addtitle>Radiat Prot Dosimetry</addtitle><date>2005-01-01</date><risdate>2005</risdate><volume>115</volume><issue>1-4</issue><spage>227</spage><epage>231</epage><pages>227-231</pages><issn>0144-8420</issn><eissn>1742-3406</eissn><abstract>Because silicon is a major constituent of concrete and soil, neutron and gamma ray information on silicon is important for reactor shielding and criticality safety calculations. Therefore, much effort was put into the ENDF/B-VI evaluation for the three stable isotopes of silicon. The neutron capture cross section of natural silicon was recently measured at the Oak Ridge Electron Linear Accelerator (ORELA) in the energy range 1–700 keV. Using the ENDF/B-VI evaluation for initial values, a new evaluation of the resonance parameters was performed by adding the results of the ORELA capture measurements to the experimental database. The computer code SAMMY was used for the analysis of the experimental data; the new version of SAMMY allows accurate calculations of the self-shielding and multiple scattering effects in the capture measurements. The accuracy of the radiative capture widths of the resonances was improved by this analysis. Accurate values of the s-, p- and d-wave neutron strength functions were also obtained. Although the resonance capture component of the present evaluation is 2–3 times smaller than that in ENDF/B-VI, the total capture cross section is much larger, at least for energies >250 keV, because the direct capture component contributes values of the same order of magnitude as the resonance component. The direct component was not taken into account in the ENDF/B-VI evaluation and was calculated for the first time in the present evaluation.</abstract><cop>England</cop><pub>Oxford University Press</pub><pmid>16381717</pmid><doi>10.1093/rpd/nci117</doi><tpages>5</tpages></addata></record> |
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source | MEDLINE; Oxford University Press Journals All Titles (1996-Current) |
subjects | Computer Simulation Data Interpretation, Statistical Energy Transfer Isotopes - analysis Materials Testing - methods Models, Chemical Neutron Diffraction - methods Neutrons Radiation Dosage Radiation Protection - instrumentation Radiation Protection - methods Radiometry - methods Silicon - analysis |
title | Evaluation of silicon neutron resonance parameters in the thermal to 1800 keV energy range |
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