Martin Schulc , Evžen Novák , Jan Šimon , Alena Krechlerová , Michal Košťál , Roberto Capote
{"title":"验证 252Cf(s.f.) 中子场中的俘获反应截面。","authors":"Martin Schulc , Evžen Novák , Jan Šimon , Alena Krechlerová , Michal Košťál , Roberto Capote","doi":"10.1016/j.apradiso.2024.111586","DOIUrl":null,"url":null,"abstract":"<div><div>We have investigated following capture reactions: <sup>197</sup>Au(n,g)<sup>198</sup>Au, <sup>63</sup>Cu(n,g)<sup>64</sup>Cu, <sup>45</sup>Sc(n,g)<sup>46</sup>Sc, <sup>181</sup>Ta(n,g)<sup>182</sup>Ta, <sup>140</sup>Ce(n,g)<sup>141</sup>Ce, <sup>139</sup>La(n,g)<sup>140</sup>La, <sup>176</sup>Yb(n,g)<sup>177</sup>Yb, <sup>55</sup>Mn(n,g)<sup>56</sup>Mn, and <sup>141</sup>Pr(n,g)<sup>142</sup>Pr in a standard <sup>252</sup>Cf(s.f.) neutron field. The experimentally derived reaction rates were compared with calculations using state-of-the-art libraries IRDFF-II, ENDF/B-VIII.0, JENDL-5 and JEFF-3.3 performed in MCNP6.2 transport code. The experiment was focused on capture reactions in high energy neutron range. To suppress scattered low energy neutrons, all activation materials were enclosed by a spherical cadmium surface of 30 cm in diameter. Experimentally derived reaction rates of <sup>197</sup>Au(n,g)<sup>198</sup>Au, <sup>63</sup>Cu(n,g)<sup>64</sup>Cu reactions agree with calculations using all state-of-the-art nuclear data libraries. The highest discrepancies were found when evaluating <sup>139</sup>La(n,g)<sup>140</sup>La and <sup>55</sup>Mn(n,g)<sup>56</sup>Mn reactions utilizing all libraries. Experimental reaction rates applying data from the JENDL-5 library agree very well with the results of other reactions except for the <sup>45</sup>Sc(n,g)<sup>46</sup>Sc reaction. <sup>181</sup>Ta(n,g)<sup>182</sup>Ta reaction rate does not agree within uncertainties using any library. The <sup>176</sup>Yb(n,g)<sup>177</sup>Yb reaction rate agrees reasonably well only when performing calculation using JENDL-5 and ENDF/B-VIII.0 libraries, unlike JEFF-3.3 library. <sup>140</sup>Ce(n,g)<sup>141</sup>Ce and <sup>141</sup>Pr(n,g)<sup>142</sup>Pr reaction rates applying JEFF-3.3 and ENDF/B-VIII.0 libraries do not agree within uncertainties.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"215 ","pages":"Article 111586"},"PeriodicalIF":1.6000,"publicationDate":"2024-11-10","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"Validation of capture reactions cross sections in 252Cf(s.f.) neutron field\",\"authors\":\"Martin Schulc , Evžen Novák , Jan Šimon , Alena Krechlerová , Michal Košťál , Roberto Capote\",\"doi\":\"10.1016/j.apradiso.2024.111586\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"<div><div>We have investigated following capture reactions: <sup>197</sup>Au(n,g)<sup>198</sup>Au, <sup>63</sup>Cu(n,g)<sup>64</sup>Cu, <sup>45</sup>Sc(n,g)<sup>46</sup>Sc, <sup>181</sup>Ta(n,g)<sup>182</sup>Ta, <sup>140</sup>Ce(n,g)<sup>141</sup>Ce, <sup>139</sup>La(n,g)<sup>140</sup>La, <sup>176</sup>Yb(n,g)<sup>177</sup>Yb, <sup>55</sup>Mn(n,g)<sup>56</sup>Mn, and <sup>141</sup>Pr(n,g)<sup>142</sup>Pr in a standard <sup>252</sup>Cf(s.f.) neutron field. The experimentally derived reaction rates were compared with calculations using state-of-the-art libraries IRDFF-II, ENDF/B-VIII.0, JENDL-5 and JEFF-3.3 performed in MCNP6.2 transport code. The experiment was focused on capture reactions in high energy neutron range. To suppress scattered low energy neutrons, all activation materials were enclosed by a spherical cadmium surface of 30 cm in diameter. Experimentally derived reaction rates of <sup>197</sup>Au(n,g)<sup>198</sup>Au, <sup>63</sup>Cu(n,g)<sup>64</sup>Cu reactions agree with calculations using all state-of-the-art nuclear data libraries. The highest discrepancies were found when evaluating <sup>139</sup>La(n,g)<sup>140</sup>La and <sup>55</sup>Mn(n,g)<sup>56</sup>Mn reactions utilizing all libraries. Experimental reaction rates applying data from the JENDL-5 library agree very well with the results of other reactions except for the <sup>45</sup>Sc(n,g)<sup>46</sup>Sc reaction. <sup>181</sup>Ta(n,g)<sup>182</sup>Ta reaction rate does not agree within uncertainties using any library. The <sup>176</sup>Yb(n,g)<sup>177</sup>Yb reaction rate agrees reasonably well only when performing calculation using JENDL-5 and ENDF/B-VIII.0 libraries, unlike JEFF-3.3 library. <sup>140</sup>Ce(n,g)<sup>141</sup>Ce and <sup>141</sup>Pr(n,g)<sup>142</sup>Pr reaction rates applying JEFF-3.3 and ENDF/B-VIII.0 libraries do not agree within uncertainties.</div></div>\",\"PeriodicalId\":8096,\"journal\":{\"name\":\"Applied Radiation and Isotopes\",\"volume\":\"215 \",\"pages\":\"Article 111586\"},\"PeriodicalIF\":1.6000,\"publicationDate\":\"2024-11-10\",\"publicationTypes\":\"Journal Article\",\"fieldsOfStudy\":null,\"isOpenAccess\":false,\"openAccessPdf\":\"\",\"citationCount\":\"0\",\"resultStr\":null,\"platform\":\"Semanticscholar\",\"paperid\":null,\"PeriodicalName\":\"Applied Radiation and Isotopes\",\"FirstCategoryId\":\"5\",\"ListUrlMain\":\"https://www.sciencedirect.com/science/article/pii/S0969804324004147\",\"RegionNum\":3,\"RegionCategory\":\"工程技术\",\"ArticlePicture\":[],\"TitleCN\":null,\"AbstractTextCN\":null,\"PMCID\":null,\"EPubDate\":\"\",\"PubModel\":\"\",\"JCR\":\"Q3\",\"JCRName\":\"CHEMISTRY, INORGANIC & NUCLEAR\",\"Score\":null,\"Total\":0}","platform":"Semanticscholar","paperid":null,"PeriodicalName":"Applied Radiation and Isotopes","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0969804324004147","RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q3","JCRName":"CHEMISTRY, INORGANIC & NUCLEAR","Score":null,"Total":0}
Validation of capture reactions cross sections in 252Cf(s.f.) neutron field
We have investigated following capture reactions: 197Au(n,g)198Au, 63Cu(n,g)64Cu, 45Sc(n,g)46Sc, 181Ta(n,g)182Ta, 140Ce(n,g)141Ce, 139La(n,g)140La, 176Yb(n,g)177Yb, 55Mn(n,g)56Mn, and 141Pr(n,g)142Pr in a standard 252Cf(s.f.) neutron field. The experimentally derived reaction rates were compared with calculations using state-of-the-art libraries IRDFF-II, ENDF/B-VIII.0, JENDL-5 and JEFF-3.3 performed in MCNP6.2 transport code. The experiment was focused on capture reactions in high energy neutron range. To suppress scattered low energy neutrons, all activation materials were enclosed by a spherical cadmium surface of 30 cm in diameter. Experimentally derived reaction rates of 197Au(n,g)198Au, 63Cu(n,g)64Cu reactions agree with calculations using all state-of-the-art nuclear data libraries. The highest discrepancies were found when evaluating 139La(n,g)140La and 55Mn(n,g)56Mn reactions utilizing all libraries. Experimental reaction rates applying data from the JENDL-5 library agree very well with the results of other reactions except for the 45Sc(n,g)46Sc reaction. 181Ta(n,g)182Ta reaction rate does not agree within uncertainties using any library. The 176Yb(n,g)177Yb reaction rate agrees reasonably well only when performing calculation using JENDL-5 and ENDF/B-VIII.0 libraries, unlike JEFF-3.3 library. 140Ce(n,g)141Ce and 141Pr(n,g)142Pr reaction rates applying JEFF-3.3 and ENDF/B-VIII.0 libraries do not agree within uncertainties.
期刊介绍:
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