{"title":"Application of MATLAB PDE Toolbox for the IAEA-3D PWR Benchmark","authors":"A. Ajirotutu, Xue Yang","doi":"10.13182/t32626","DOIUrl":"https://doi.org/10.13182/t32626","url":null,"abstract":"","PeriodicalId":223521,"journal":{"name":"Transactions of the American Nuclear Society - Volume 122","volume":"24 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2020-06-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"114457353","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
{"title":"Development of Coupled Monte Carlo Transport-burnup and CFD Simulations in SuperMC","authors":"Lei Wang, Bin Wu, Shengpeng Yu, Pengcheng Long","doi":"10.13182/t32067","DOIUrl":"https://doi.org/10.13182/t32067","url":null,"abstract":"","PeriodicalId":223521,"journal":{"name":"Transactions of the American Nuclear Society - Volume 122","volume":"27 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2020-06-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"117020476","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
B. Garrison, R. Lowden, M. Cinbiz, N. Brown, K. Linton
{"title":"Failure Behavior of Nuclear-grade FeCrAl Cladding under Simulated Pellet-cladding Mechanical Interaction Conditions","authors":"B. Garrison, R. Lowden, M. Cinbiz, N. Brown, K. Linton","doi":"10.13182/t32352","DOIUrl":"https://doi.org/10.13182/t32352","url":null,"abstract":"","PeriodicalId":223521,"journal":{"name":"Transactions of the American Nuclear Society - Volume 122","volume":"18 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2020-06-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"115462976","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
1 This manuscript has been authored by UT-Battelle, LLC, under contract DE-AC05-00OR22725 with the US Department of Energy (DOE). The US government retains and the publisher, by accepting the article for publication, acknowledges that the US government retains a nonexclusive, paid-up, irrevocable, worldwide license to publish or reproduce the published form of this manuscript, or allow others to do so, for US government purposes. DOE will provide public access to these results of federally sponsored research in accordance with the DOE Public Access Plan (http://energy.gov/downloads/doepublic-access-plan INTRODUCTION
{"title":"In Situ Mechanical Testing of AM 316L Steel-TCR Core Material","authors":"M. Gussev, T. Byun, R. Dehoff, K. Terrani","doi":"10.13182/t32484","DOIUrl":"https://doi.org/10.13182/t32484","url":null,"abstract":"1 This manuscript has been authored by UT-Battelle, LLC, under contract DE-AC05-00OR22725 with the US Department of Energy (DOE). The US government retains and the publisher, by accepting the article for publication, acknowledges that the US government retains a nonexclusive, paid-up, irrevocable, worldwide license to publish or reproduce the published form of this manuscript, or allow others to do so, for US government purposes. DOE will provide public access to these results of federally sponsored research in accordance with the DOE Public Access Plan (http://energy.gov/downloads/doepublic-access-plan INTRODUCTION","PeriodicalId":223521,"journal":{"name":"Transactions of the American Nuclear Society - Volume 122","volume":"92 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2020-06-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"122444714","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Aman Gupta, Paul D. Armatis, P. Sabharwall, V. Utgikar, B. Fronk
{"title":"System Efficiency and Dynamic Study of Ca(OH)2/CaO Chemical Heat Pump","authors":"Aman Gupta, Paul D. Armatis, P. Sabharwall, V. Utgikar, B. Fronk","doi":"10.13182/t32447","DOIUrl":"https://doi.org/10.13182/t32447","url":null,"abstract":"","PeriodicalId":223521,"journal":{"name":"Transactions of the American Nuclear Society - Volume 122","volume":"1 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2020-06-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"129755941","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
{"title":"Improving Convergence via Removal of Scattering Ratio Threshold in Discrete Diffusion Monte Carlo","authors":"Alexis Maldonado, M. Cleveland, K. Thompson","doi":"10.13182/t31934","DOIUrl":"https://doi.org/10.13182/t31934","url":null,"abstract":"","PeriodicalId":223521,"journal":{"name":"Transactions of the American Nuclear Society - Volume 122","volume":"1 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2020-06-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"129835100","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
{"title":"Flawless Fusion in Less Than 60 Seconds Over Similar or Dissimilar Material","authors":"P. Cheng","doi":"10.13182/t32139","DOIUrl":"https://doi.org/10.13182/t32139","url":null,"abstract":"","PeriodicalId":223521,"journal":{"name":"Transactions of the American Nuclear Society - Volume 122","volume":"96 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2020-06-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"127544090","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
C. Chapman, Xunxiang Hu, Jesse M. Brown, G. Arbanas, A. Kolesnikov, Yongqiang Q. Cheng, L. Daemen
The Transformational Challenge Reactor (TCR) targets application of advances in manufacturing, materials, and computational sciences to accelerate development of new nuclear reactor technologies as well as their adoption by the U.S. industry [1]. The TCR leverages advanced manufacturing capabilities at Oak Ridge National Laboratory (ORNL) to facilitate an agile reactor design with the ability to take advantage of advanced materials and data science-informed certification schemes. Since TCR is gas-cooled a thermal reactor, the choice of neutron moderating material is of crucial importance. To achieve a highly efficient and compact core while minimizing the amount of high assay low enriched uranium required [2], a hydrogen-bearing moderator that is stable to high temperatures is required. This initially led to the selection of metal hydrides (i.e., ZrHx and YHx) for the TCR demonstration core. ZrHx has been extensively studied and used in previous reactor designs since the 1950s due to its low absorption cross section and general availability [3]. However, during the same period, the unavailability of high-purity yttrium as an industrial metal barred it from being considered as another candidate although it exhibits advantageous thermal stability compared to ZrHx [4, 5]. Today yttrium metal of high purity is available as an industrial metal and therefore, YHx was chosen as the moderator material for the TCR. However, a complete thermal scattering library is currently lacking and is needed for an accurate representation of TCR core neutronics properties. This paper details the first step towards the evaluation of a YHx thermal scattering library through the conduct of thermal neutron scattering experiments for various hydrogen atomic concentrations x = 1.62, 1.74, 1.85, 1.90 at 5 Kelvin and room temperature at the Spallation Neutron Source (SNS) at ORNL. This information supplies the necessary data for TCR’s YHx moderator while providing basic information that is necessary for design and deployment of any other reactor taking advantage of this high performance moderator.
{"title":"Thermal Neutron Scattering Measurements of YHx for the Transformational Challenge Reactor","authors":"C. Chapman, Xunxiang Hu, Jesse M. Brown, G. Arbanas, A. Kolesnikov, Yongqiang Q. Cheng, L. Daemen","doi":"10.13182/t32422","DOIUrl":"https://doi.org/10.13182/t32422","url":null,"abstract":"The Transformational Challenge Reactor (TCR) targets application of advances in manufacturing, materials, and computational sciences to accelerate development of new nuclear reactor technologies as well as their adoption by the U.S. industry [1]. The TCR leverages advanced manufacturing capabilities at Oak Ridge National Laboratory (ORNL) to facilitate an agile reactor design with the ability to take advantage of advanced materials and data science-informed certification schemes. Since TCR is gas-cooled a thermal reactor, the choice of neutron moderating material is of crucial importance. To achieve a highly efficient and compact core while minimizing the amount of high assay low enriched uranium required [2], a hydrogen-bearing moderator that is stable to high temperatures is required. This initially led to the selection of metal hydrides (i.e., ZrHx and YHx) for the TCR demonstration core. ZrHx has been extensively studied and used in previous reactor designs since the 1950s due to its low absorption cross section and general availability [3]. However, during the same period, the unavailability of high-purity yttrium as an industrial metal barred it from being considered as another candidate although it exhibits advantageous thermal stability compared to ZrHx [4, 5]. Today yttrium metal of high purity is available as an industrial metal and therefore, YHx was chosen as the moderator material for the TCR. However, a complete thermal scattering library is currently lacking and is needed for an accurate representation of TCR core neutronics properties. This paper details the first step towards the evaluation of a YHx thermal scattering library through the conduct of thermal neutron scattering experiments for various hydrogen atomic concentrations x = 1.62, 1.74, 1.85, 1.90 at 5 Kelvin and room temperature at the Spallation Neutron Source (SNS) at ORNL. This information supplies the necessary data for TCR’s YHx moderator while providing basic information that is necessary for design and deployment of any other reactor taking advantage of this high performance moderator.","PeriodicalId":223521,"journal":{"name":"Transactions of the American Nuclear Society - Volume 122","volume":"18 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2020-06-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"120995427","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
{"title":"CFD Analysis of PRHR-Heat Exchanger Using Euler Multiphase Model","authors":"Soumitra Vadnerkar, Xue Yang","doi":"10.13182/t32121","DOIUrl":"https://doi.org/10.13182/t32121","url":null,"abstract":"","PeriodicalId":223521,"journal":{"name":"Transactions of the American Nuclear Society - Volume 122","volume":"10 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2020-06-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"126374758","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
{"title":"Study on Selecting Conservative Axial Power Shape for DNBR Design Limit","authors":"Shane Park","doi":"10.13182/t32385","DOIUrl":"https://doi.org/10.13182/t32385","url":null,"abstract":"","PeriodicalId":223521,"journal":{"name":"Transactions of the American Nuclear Society - Volume 122","volume":"41 5 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2020-06-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"125884341","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
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