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Reactor Dosimetry: 16th International Symposium最新文献

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Methodology Qualification for the 3D RAPTOR-M3G Discrete Ordinates Transport Code on Traditional Beltline 传统腰带上三维RAPTOR-M3G离散坐标运输代码的方法学鉴定
Reactor Dosimetry: 16th International Symposium Pub Date : 2018-11-01 DOI: 10.1520/STP160820170068
Jianwei Chen, G. Fischer, Byoung Chul Kim
{"title":"Methodology Qualification for the 3D RAPTOR-M3G Discrete Ordinates Transport Code on Traditional Beltline","authors":"Jianwei Chen, G. Fischer, Byoung Chul Kim","doi":"10.1520/STP160820170068","DOIUrl":"https://doi.org/10.1520/STP160820170068","url":null,"abstract":"","PeriodicalId":166400,"journal":{"name":"Reactor Dosimetry: 16th International Symposium","volume":"2012 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2018-11-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"121677563","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}
引用次数: 0
Study of Epithermal-Neutron Spectrum Variation versus Depth in Water Phantoms 水影中低温中子谱随深度变化的研究
Reactor Dosimetry: 16th International Symposium Pub Date : 2018-11-01 DOI: 10.1520/STP160820170053
G. Gambarini, D. Bettega, A. Gebbia, E. Artuso, M. Felisi, D. Giove, E. Durisi, V. Monti, V. Klupák, L. Viererbl, M. Vinš
{"title":"Study of Epithermal-Neutron Spectrum Variation versus Depth in Water Phantoms","authors":"G. Gambarini, D. Bettega, A. Gebbia, E. Artuso, M. Felisi, D. Giove, E. Durisi, V. Monti, V. Klupák, L. Viererbl, M. Vinš","doi":"10.1520/STP160820170053","DOIUrl":"https://doi.org/10.1520/STP160820170053","url":null,"abstract":"","PeriodicalId":166400,"journal":{"name":"Reactor Dosimetry: 16th International Symposium","volume":"63 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2018-11-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"114344189","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}
引用次数: 0
Analysis of the FLUOLE-2 Program: UOX/MOX Core Loading Configurations FLUOLE-2程序分析:UOX/MOX堆芯加载配置
Reactor Dosimetry: 16th International Symposium Pub Date : 2018-11-01 DOI: 10.1520/STP160820170047
S. Bourganel, N. Thiollay, P. Mosca
{"title":"Analysis of the FLUOLE-2 Program: UOX/MOX Core Loading Configurations","authors":"S. Bourganel, N. Thiollay, P. Mosca","doi":"10.1520/STP160820170047","DOIUrl":"https://doi.org/10.1520/STP160820170047","url":null,"abstract":"","PeriodicalId":166400,"journal":{"name":"Reactor Dosimetry: 16th International Symposium","volume":"56 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2018-11-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"132082700","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}
引用次数: 1
Exploration of the 1 keV–1 MeV Neutron Energy Range Using Zirconium Dosimeters 用锆剂量计探测1千兆电子伏- 1兆电子伏中子能量范围
Reactor Dosimetry: 16th International Symposium Pub Date : 2018-11-01 DOI: 10.1520/STP160820170045
N. Thiollay, V. Sergeyeva, A. Lyoussi, C. Domergue, C. Destouches
{"title":"Exploration of the 1 keV–1 MeV Neutron Energy Range Using Zirconium Dosimeters","authors":"N. Thiollay, V. Sergeyeva, A. Lyoussi, C. Domergue, C. Destouches","doi":"10.1520/STP160820170045","DOIUrl":"https://doi.org/10.1520/STP160820170045","url":null,"abstract":"","PeriodicalId":166400,"journal":{"name":"Reactor Dosimetry: 16th International Symposium","volume":"422 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2018-11-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"133836218","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}
引用次数: 0
Experimental and Computational Validation of RAPID RAPID的实验与计算验证
Reactor Dosimetry: 16th International Symposium Pub Date : 2018-11-01 DOI: 10.1520/STP160820170094
Nathan J. Roskoff, A. Haghighat, V. Mascolino
{"title":"Experimental and Computational Validation of RAPID","authors":"Nathan J. Roskoff, A. Haghighat, V. Mascolino","doi":"10.1520/STP160820170094","DOIUrl":"https://doi.org/10.1520/STP160820170094","url":null,"abstract":"ABSTRACT The RAPID (Real-time Analysis for Particle transport and In-situ Detection) code system utilizes the Multi-stage Response-function Transport (MRT) approach with the Fission Matrix (FM) method for neutronics simulation of nuclear systems. RAPID performs real-time calculations by utilizing pre-calculated databases for different enrichments, burnups, and cooling times. This paper discusses the validation of RAPID using the U.S. Naval Academy’s subcritical reactor (USNA-SCR) facility. Computational validation is performed by detailed comparison with an MCNP reference calculation and experimental validation is performed using both in-core and excore neutron measurements with different He proportional counters. These measurements, and associated calculations have demonstrated that RAPID achieves accurate results in real-time.","PeriodicalId":166400,"journal":{"name":"Reactor Dosimetry: 16th International Symposium","volume":"17 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2018-11-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"134470915","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}
引用次数: 4
Deterministic Model of PWR Fast Fluence for Uncertainty Propagations with the Code APOLLO3® 不确定性传播的压水堆快通量确定性模型与代码APOLLO3®
Reactor Dosimetry: 16th International Symposium Pub Date : 2018-11-01 DOI: 10.1520/STP160820170048
P. Mosca, Laura Clouvel, Théophile Lacaze, S. Lahaye, J. Lautard, A. Baudron
{"title":"Deterministic Model of PWR Fast Fluence for Uncertainty Propagations with the Code APOLLO3®","authors":"P. Mosca, Laura Clouvel, Théophile Lacaze, S. Lahaye, J. Lautard, A. Baudron","doi":"10.1520/STP160820170048","DOIUrl":"https://doi.org/10.1520/STP160820170048","url":null,"abstract":"The fast neutron fluence and the corresponding uncertainty are important parameters for reactor pressure vessel life time. This article presents one model, under development at CEA (Commissariat à l’Energie Atomique et aux Energies Alternatives), to carry out with the deterministic code APOLLO3 ® uncertainty calculations of the fast fluence for PWR irradiation surveillance. All calculations are made by MINARET, a 3D-SN solver of the APOLLO3 ® code which uses the discontinuous Galerkin finite elements approximation. The spatial mesh is unstructured and the transport calculations are parallelized with respect to the angular directions. In this numerical scheme, the multigroup cross-sections are sub-group self-shielded and collapsed over a dedicated energy mesh optimized by the Adaptive Energy Mesh Constructor (AEMC). Results from this model are encouraging with respect to the Monte Carlo reference TRIPOLI-4 ® . The integral of the flux over 1 MeV in the locations of interest (surveillance capsule and vessel) is calculated in less than 20 minutes with an error lower than 1%. Some examples of uncertainty calculations associated to design parameters in which the MINARET solver is coupled to the CEA uncertainty and sensitivity platform URANIE are also provided.","PeriodicalId":166400,"journal":{"name":"Reactor Dosimetry: 16th International Symposium","volume":"1 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2018-11-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"124038797","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}
引用次数: 1
Monte Carlo Calculation Procedure and Its Implementation for Radiation Load Estimation on Russian VVER Reactor Equipment 俄罗斯VVER反应堆设备辐射负荷估计的蒙特卡罗计算程序及其实现
Reactor Dosimetry: 16th International Symposium Pub Date : 2018-11-01 DOI: 10.1520/STP160820170074
S. Baier, J. Konheiser, P. Borodkin, Azamat Gazetdinov, N. Khrennikov
{"title":"Monte Carlo Calculation Procedure and Its Implementation for Radiation Load Estimation on Russian VVER Reactor Equipment","authors":"S. Baier, J. Konheiser, P. Borodkin, Azamat Gazetdinov, N. Khrennikov","doi":"10.1520/STP160820170074","DOIUrl":"https://doi.org/10.1520/STP160820170074","url":null,"abstract":"","PeriodicalId":166400,"journal":{"name":"Reactor Dosimetry: 16th International Symposium","volume":"38 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2018-11-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"122139791","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}
引用次数: 0
Design and Response Testing of Boron-Diffused Silicon Carbide Neutron Detectors for Dosimetry and Monitoring Applications 用于剂量测定和监测应用的硼扩散碳化硅中子探测器的设计和响应测试
Reactor Dosimetry: 16th International Symposium Pub Date : 2018-11-01 DOI: 10.1520/STP160820170042
K. Mandal, Towhid A. Chowdhury, Cihan Oner, F. Ruddy
{"title":"Design and Response Testing of Boron-Diffused Silicon Carbide Neutron Detectors for Dosimetry and Monitoring Applications","authors":"K. Mandal, Towhid A. Chowdhury, Cihan Oner, F. Ruddy","doi":"10.1520/STP160820170042","DOIUrl":"https://doi.org/10.1520/STP160820170042","url":null,"abstract":"","PeriodicalId":166400,"journal":{"name":"Reactor Dosimetry: 16th International Symposium","volume":"39 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2018-11-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"127214997","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}
引用次数: 4
Derivation of Ex-Core Detector Response Functions for Sizewell B Sizewell B的前芯探测器响应函数的推导
Reactor Dosimetry: 16th International Symposium Pub Date : 2018-11-01 DOI: 10.1520/STP160820170051
C. Murphy, G. A. Wright, D. Thornton, Simon E. Shaw, P. Bryce
{"title":"Derivation of Ex-Core Detector Response Functions for Sizewell B","authors":"C. Murphy, G. A. Wright, D. Thornton, Simon E. Shaw, P. Bryce","doi":"10.1520/STP160820170051","DOIUrl":"https://doi.org/10.1520/STP160820170051","url":null,"abstract":"","PeriodicalId":166400,"journal":{"name":"Reactor Dosimetry: 16th International Symposium","volume":"73 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2018-11-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"126110315","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}
引用次数: 0
Retrospective Dosimetry Analysis of Top Support Plug Samples from Scrap Surveillance Capsule Material for Qualifying Calculations in the Extended Beltline Region of PWRS 用于PWRS扩展腰带区域合格计算的报废监视胶囊材料顶部支撑塞样品的回顾性剂量学分析
Reactor Dosimetry: 16th International Symposium Pub Date : 2018-11-01 DOI: 10.1520/STP160820170073
G. Fischer, Byoung Chul Kim
{"title":"Retrospective Dosimetry Analysis of Top Support Plug Samples from Scrap Surveillance Capsule Material for Qualifying Calculations in the Extended Beltline Region of PWRS","authors":"G. Fischer, Byoung Chul Kim","doi":"10.1520/STP160820170073","DOIUrl":"https://doi.org/10.1520/STP160820170073","url":null,"abstract":"","PeriodicalId":166400,"journal":{"name":"Reactor Dosimetry: 16th International Symposium","volume":"18 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2018-11-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"116846599","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}
引用次数: 0
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