{"title":"GTES: A GNDS format nuclear data processing code interfacing AXSP","authors":"Wenming Yi , Xubo Ma , Kui Hu","doi":"10.1016/j.pnucene.2024.105567","DOIUrl":null,"url":null,"abstract":"<div><div>The Generalized Nuclear Data Structure (GNDS) is a new evaluated nuclear data format designed to replace the traditional ENDF-6 format. GNDS offers improved readability and easier expandability compared to ENDF-6. In this study, a new nuclear data processing code, GTES, written in the object-oriented language C#, has been developed for converting between GNDS and ENDF-6 formats. GTES interfaces with the advanced cross-section processing code AXSP, transforming GNDS-2.0 and generating ENDF-6 format structure files, which can be used for further calculations with AXSP. To verify the correctness of the GTES processing, the generated files have been processed into ACE format cross-sections by AXSP, and the Monte Carlo transport code RMC is used for criticality calculations to verify the accuracy of the results. The calculation results indicate that GTES can successfully process ENDF/B-VIII.0 evaluated nuclear data in GNDS-2.0 format. The cross-section data and criticality benchmark calculation results processed by AXSP are in good agreement with experimental results, although there are certain differences in some data when compared to the ENDF/B-VIII.0 evaluated nuclear data in ENDF-6 format. However, the calculation results are in excellent agreement with the results of transforming GNDS-2.0 format to ENDF/B-VIII.0 using FUDGE.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"180 ","pages":"Article 105567"},"PeriodicalIF":3.3000,"publicationDate":"2025-02-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Progress in Nuclear Energy","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0149197024005171","RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q1","JCRName":"NUCLEAR SCIENCE & TECHNOLOGY","Score":null,"Total":0}
引用次数: 0
Abstract
The Generalized Nuclear Data Structure (GNDS) is a new evaluated nuclear data format designed to replace the traditional ENDF-6 format. GNDS offers improved readability and easier expandability compared to ENDF-6. In this study, a new nuclear data processing code, GTES, written in the object-oriented language C#, has been developed for converting between GNDS and ENDF-6 formats. GTES interfaces with the advanced cross-section processing code AXSP, transforming GNDS-2.0 and generating ENDF-6 format structure files, which can be used for further calculations with AXSP. To verify the correctness of the GTES processing, the generated files have been processed into ACE format cross-sections by AXSP, and the Monte Carlo transport code RMC is used for criticality calculations to verify the accuracy of the results. The calculation results indicate that GTES can successfully process ENDF/B-VIII.0 evaluated nuclear data in GNDS-2.0 format. The cross-section data and criticality benchmark calculation results processed by AXSP are in good agreement with experimental results, although there are certain differences in some data when compared to the ENDF/B-VIII.0 evaluated nuclear data in ENDF-6 format. However, the calculation results are in excellent agreement with the results of transforming GNDS-2.0 format to ENDF/B-VIII.0 using FUDGE.
期刊介绍:
Progress in Nuclear Energy is an international review journal covering all aspects of nuclear science and engineering. In keeping with the maturity of nuclear power, articles on safety, siting and environmental problems are encouraged, as are those associated with economics and fuel management. However, basic physics and engineering will remain an important aspect of the editorial policy. Articles published are either of a review nature or present new material in more depth. They are aimed at researchers and technically-oriented managers working in the nuclear energy field.
Please note the following:
1) PNE seeks high quality research papers which are medium to long in length. Short research papers should be submitted to the journal Annals in Nuclear Energy.
2) PNE reserves the right to reject papers which are based solely on routine application of computer codes used to produce reactor designs or explain existing reactor phenomena. Such papers, although worthy, are best left as laboratory reports whereas Progress in Nuclear Energy seeks papers of originality, which are archival in nature, in the fields of mathematical and experimental nuclear technology, including fission, fusion (blanket physics, radiation damage), safety, materials aspects, economics, etc.
3) Review papers, which may occasionally be invited, are particularly sought by the journal in these fields.