{"title":"ENDF/B-VI铍数据对参考ARIES-I毛毯性能的影响","authors":"S. Pelloni, E. Cheng","doi":"10.1109/FUSION.1991.218779","DOIUrl":null,"url":null,"abstract":"The effect of ENDF/B-VI beryllium data on the neutronic characteristics of the reference ARIES-I fusion blanket is investigated. It is found that the total initial tritium breeding ratio (1.2154) calculated with ENDF/B-V is significantly higher, by about 5.7%, than that calculated with ENDF/B-VI beryllium cross sections (1.1504). When using beryllium data from ENDF/B-VI instead of ENDF/B-V, the maximum fast neutron flux above 0.111 MeV in the superconducting magnet calculated assuming a wall loading of 1 MW/m/sup 2/ increases by 4.6% (1.915*10/sup 9/ against 1.830*10/sup 9/ neutrons/cm/sup 2//s), whereas the total blanket energy multiplication decreases by about 3.3% (1.2518 against 1.2937), the average volumetric nuclear heating in the first wall by about 3% (4.8012 against 4.9484 W/cm/sup 3/), the maximum helium production rate in the neutron multiplier after one year irradiation significantly by 11.2% (1535 against 1720 parts per million), and the maximum hydrogen production rate in the first wall by 2.5% (385 against 395 parts per million).<<ETX>>","PeriodicalId":318951,"journal":{"name":"[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering","volume":"54 1","pages":"0"},"PeriodicalIF":0.0000,"publicationDate":"1991-09-30","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"Implications of ENDF/B-VI beryllium data on the performance of the reference ARIES-I blanket\",\"authors\":\"S. Pelloni, E. Cheng\",\"doi\":\"10.1109/FUSION.1991.218779\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"The effect of ENDF/B-VI beryllium data on the neutronic characteristics of the reference ARIES-I fusion blanket is investigated. It is found that the total initial tritium breeding ratio (1.2154) calculated with ENDF/B-V is significantly higher, by about 5.7%, than that calculated with ENDF/B-VI beryllium cross sections (1.1504). When using beryllium data from ENDF/B-VI instead of ENDF/B-V, the maximum fast neutron flux above 0.111 MeV in the superconducting magnet calculated assuming a wall loading of 1 MW/m/sup 2/ increases by 4.6% (1.915*10/sup 9/ against 1.830*10/sup 9/ neutrons/cm/sup 2//s), whereas the total blanket energy multiplication decreases by about 3.3% (1.2518 against 1.2937), the average volumetric nuclear heating in the first wall by about 3% (4.8012 against 4.9484 W/cm/sup 3/), the maximum helium production rate in the neutron multiplier after one year irradiation significantly by 11.2% (1535 against 1720 parts per million), and the maximum hydrogen production rate in the first wall by 2.5% (385 against 395 parts per million).<<ETX>>\",\"PeriodicalId\":318951,\"journal\":{\"name\":\"[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering\",\"volume\":\"54 1\",\"pages\":\"0\"},\"PeriodicalIF\":0.0000,\"publicationDate\":\"1991-09-30\",\"publicationTypes\":\"Journal Article\",\"fieldsOfStudy\":null,\"isOpenAccess\":false,\"openAccessPdf\":\"\",\"citationCount\":\"0\",\"resultStr\":null,\"platform\":\"Semanticscholar\",\"paperid\":null,\"PeriodicalName\":\"[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering\",\"FirstCategoryId\":\"1085\",\"ListUrlMain\":\"https://doi.org/10.1109/FUSION.1991.218779\",\"RegionNum\":0,\"RegionCategory\":null,\"ArticlePicture\":[],\"TitleCN\":null,\"AbstractTextCN\":null,\"PMCID\":null,\"EPubDate\":\"\",\"PubModel\":\"\",\"JCR\":\"\",\"JCRName\":\"\",\"Score\":null,\"Total\":0}","platform":"Semanticscholar","paperid":null,"PeriodicalName":"[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering","FirstCategoryId":"1085","ListUrlMain":"https://doi.org/10.1109/FUSION.1991.218779","RegionNum":0,"RegionCategory":null,"ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"","JCRName":"","Score":null,"Total":0}
Implications of ENDF/B-VI beryllium data on the performance of the reference ARIES-I blanket
The effect of ENDF/B-VI beryllium data on the neutronic characteristics of the reference ARIES-I fusion blanket is investigated. It is found that the total initial tritium breeding ratio (1.2154) calculated with ENDF/B-V is significantly higher, by about 5.7%, than that calculated with ENDF/B-VI beryllium cross sections (1.1504). When using beryllium data from ENDF/B-VI instead of ENDF/B-V, the maximum fast neutron flux above 0.111 MeV in the superconducting magnet calculated assuming a wall loading of 1 MW/m/sup 2/ increases by 4.6% (1.915*10/sup 9/ against 1.830*10/sup 9/ neutrons/cm/sup 2//s), whereas the total blanket energy multiplication decreases by about 3.3% (1.2518 against 1.2937), the average volumetric nuclear heating in the first wall by about 3% (4.8012 against 4.9484 W/cm/sup 3/), the maximum helium production rate in the neutron multiplier after one year irradiation significantly by 11.2% (1535 against 1720 parts per million), and the maximum hydrogen production rate in the first wall by 2.5% (385 against 395 parts per million).<>
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