{"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}
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}
{"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}
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}
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.
摘要/ ABSTRACT摘要:RAPID (Real-time Analysis for Particle transport and situ Detection)编码系统利用多阶段响应函数输运(MRT)方法和裂变矩阵(FM)方法进行核系统的中子模拟。RAPID通过利用预先计算的数据库对不同的富集、燃烧和冷却时间进行实时计算。本文讨论了使用美国海军学院的亚临界反应堆(USNA-SCR)设施对RAPID进行验证。通过与MCNP参考计算的详细比较进行计算验证，并使用不同He比例计数器进行核内和核外中子测量进行实验验证。这些测量和相关计算表明，RAPID可以实时获得准确的结果。
{"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}
P. Mosca, Laura Clouvel, Théophile Lacaze, S. Lahaye, J. Lautard, A. Baudron
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.
{"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}
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}
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}
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}
{"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}
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