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Reactor Dosimetry: 16th International Symposium最新文献

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On the Influence of Biological Shielding on Neutron Flux behind Reactor Pressure Vessel 生物屏蔽对反应堆压力容器后中子通量的影响
Pub Date : 2018-11-01 DOI: 10.1520/STP160820170079
Michal Košt´ál, V. Klupák, V. Rypar, E. Losa, F. Cvachovec, B. Jánský, Davit Harutunyan, M. Schulc, E. Novák, S. Zaritskiy, A. Bresson, Michel Tommy-Martin, Cécile-Aline Gosmain
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引用次数: 0
Comparative Study of Fast Neutron Fluence between RAPTOR-M3G and TORT for Commercial Pressurized Water Reactor Vessel Extended Beltline RAPTOR-M3G与TORT在商用压水堆容器扩展带线快中子通量的比较研究
Pub Date : 2018-11-01 DOI: 10.1520/STP160820170067
Jianwei Chen, G. Fischer
{"title":"Comparative Study of Fast Neutron Fluence between RAPTOR-M3G and TORT for Commercial Pressurized Water Reactor Vessel Extended Beltline","authors":"Jianwei Chen, G. Fischer","doi":"10.1520/STP160820170067","DOIUrl":"https://doi.org/10.1520/STP160820170067","url":null,"abstract":"","PeriodicalId":166400,"journal":{"name":"Reactor Dosimetry: 16th International Symposium","volume":"15 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":"127757670","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
Numerical Experiment to Validate an Advanced Methodology for Dosimetry in French Nuclear Reactors 数值实验验证一种先进的法国核反应堆剂量测定方法
Pub Date : 2018-11-01 DOI: 10.1520/STP160820170057
N. Thiollay, C. Fausser, S. Bourganel, P. Mosca
{"title":"Numerical Experiment to Validate an Advanced Methodology for Dosimetry in French Nuclear Reactors","authors":"N. Thiollay, C. Fausser, S. Bourganel, P. Mosca","doi":"10.1520/STP160820170057","DOIUrl":"https://doi.org/10.1520/STP160820170057","url":null,"abstract":"","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":"129202746","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
The VENUS-F Reactor for Nuclear Data Validation 用于核数据验证的金星- f反应堆
Pub Date : 2018-11-01 DOI: 10.1520/STP160820170078
A. Krása, P. Baeten, L. Fiorito, J. Heyse, A. Kochetkov, S. Kopecky, N. Messaoudi, C. Paradela, P. Schillebeeckx, A. Stankovskiy, G. Eynde, G. Vittiglio, J. Wagemans
{"title":"The VENUS-F Reactor for Nuclear Data Validation","authors":"A. Krása, P. Baeten, L. Fiorito, J. Heyse, A. Kochetkov, S. Kopecky, N. Messaoudi, C. Paradela, P. Schillebeeckx, A. Stankovskiy, G. Eynde, G. Vittiglio, J. Wagemans","doi":"10.1520/STP160820170078","DOIUrl":"https://doi.org/10.1520/STP160820170078","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":"123355982","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: 3
Design of Separated Element Reflector Experiments in CROCUS: PETALE 番红花分离元件反射器实验设计
Pub Date : 2018-11-01 DOI: 10.1520/STP760820170090
V. Lamirand, G. Perret, S. Radman, D. Siefman, P. Frajtag, M. Hursin, A. Gruel, P. Leconte, P. Blaise, A. Pautz
{"title":"Design of Separated Element Reflector Experiments in CROCUS: PETALE","authors":"V. Lamirand, G. Perret, S. Radman, D. Siefman, P. Frajtag, M. Hursin, A. Gruel, P. Leconte, P. Blaise, A. Pautz","doi":"10.1520/STP760820170090","DOIUrl":"https://doi.org/10.1520/STP760820170090","url":null,"abstract":"","PeriodicalId":166400,"journal":{"name":"Reactor Dosimetry: 16th International Symposium","volume":"157 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":"114520889","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: 7
1-MeV Equivalent Silicon Damage Studies at the White Sands Missile Range Fast Burst Reactor 白沙导弹靶场快爆反应堆1-MeV等效硅损伤研究
Pub Date : 2018-11-01 DOI: 10.1520/STP160820170098
T. Flanders, M. Sparks
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引用次数: 1
Advanced Neutron Dosimetry on VVER-440 Aimed to Reactor Equipment Load Evaluation during Lifetime Prolongation VVER-440先进中子剂量法用于延长反应堆设备寿命期间的负荷评估
Pub Date : 2018-11-01 DOI: 10.1520/STP160820170118
P. Borodkin, Azamat Gazetdinov, N. Khrennikov, J. Konheiser, A. Dzhalandinov, A. Sidorov, S. Aleshin, S. Zaritskiy, A. Egorov, V. Kochkin, D. Erak, P. Panferov, D. Makhotin
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引用次数: 0
New Evaluation of Neutron Fluence Measurements by Diamond Detectors 金刚石探测器中子通量测量的新评价
Pub Date : 2018-11-01 DOI: 10.1520/STP160820170050
V. Nikolaenko, S. Zaritskiy, A. L. Egorov, M. Saltykov, I. Bachuchin
{"title":"New Evaluation of Neutron Fluence Measurements by Diamond Detectors","authors":"V. Nikolaenko, S. Zaritskiy, A. L. Egorov, M. Saltykov, I. Bachuchin","doi":"10.1520/STP160820170050","DOIUrl":"https://doi.org/10.1520/STP160820170050","url":null,"abstract":"","PeriodicalId":166400,"journal":{"name":"Reactor Dosimetry: 16th International Symposium","volume":"65 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":"123458643","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
The Effects of Radiation Hardening on the Reusability of CaF2:Mn TLDs 辐射硬化对CaF2:Mn tld可复用性的影响
Pub Date : 2018-11-01 DOI: 10.1520/STP160820170086
J. D. Daniel, D. Henneke, D. Vehar
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引用次数: 0
Simultaneous Measurements of Nuclear Heating and Thermal Neutron Flux Obtained with the CALMOS-2 Measurement Device inside the OSIRIS Reactor OSIRIS反应堆内CALMOS-2测量装置获得的核加热和热中子通量的同时测量
Pub Date : 2018-11-01 DOI: 10.1520/STP160820170049
H. Carcreff, L. Salmon, V. Lepeltier, J. Guyot, E. Bouard
Nuclear heating inside an MTR reactor needs to be known in order to design and to run irradiation experiments which have to fulfill target temperature constraints. To improve the nuclear heating knowledge, an innovative calorimetric system CALMOS has been studied, manufactured and tested for the 70MWth OSIRIS reactor operated by CEA. This device is based on a mobile calorimetric probe which can be inserted in any in-core experimental location and can be moved axially from the bottom of the core to 1000 mm above the core mid-plane. Analysis of obtained results and advantages brought by the first CALMOS-1 mobile equipment have been already presented. However, some difficulties appeared with this first version. A thermal limitation in the cell did not allow to monitor nuclear heating up to the 70 MW nominal power, and some significant discrepancies were observed at high heating rates between results deduced from the calibration and those obtained by the “zero method”. Feedback based, the new CALMOS-2 calorimeter has been designed both for extending the heating range up to 13W.g -1 and improving the “zero method” measurement thanks to a 4-wires technique. In addition, the CALMOS-2 calorimeter has been designed as a real operational measurement system, well suited to characterize and to follow the radiation field evolution throughout the reactor cycle. To meet this requirement, a programmable system associated with a specific software allows automatic complete cell mobility in the core, the data acquisition and the measurements processing. This paper presents the analysis of results collected during the 2015 comprehensive measurement campaign carried out with the new CALMOS-2 prototype. The 4-wires ;technique was tested up to around a 4 W.g -1 heating level and allowed to quantify discrepancies between “zero” and calibration methods. Thermal neutron flux and nuclear heating measurements from CALMOS-1 and CALMOS-2 are compared. Thermal neutron flux distributions, obtained with the Self-Power Neutron Detector suited to the CALMOS-2 calorimetric cell, are compared with those obtained with current devices. Finally, this analysis tends to emphasize advantages brought by the human machine interface automation, which deeply refined the profiles definition.
为了设计和运行必须满足目标温度限制的辐照实验,需要了解MTR反应堆内部的核加热。为了提高对核加热的认识,研究、制造和测试了一种创新的CALMOS量热系统,用于CEA运营的70mth OSIRIS反应堆。该装置基于一个可移动的量热探头,该探头可以插入芯内的任何实验位置,并且可以从芯的底部轴向移动到芯中间平面上方1000毫米。对第一套CALMOS-1移动设备取得的成果和带来的优势进行了分析。然而,第一个版本出现了一些困难。由于电池的热限制,无法监测核加热到70兆瓦的标称功率,并且在高加热速率下,从校准得出的结果与通过“零法”获得的结果之间存在一些显着差异。基于反馈,新的CALMOS-2量热计的设计将加热范围扩展到13W。G -1和改进“零法”测量由于四线技术。此外,CALMOS-2量热计已被设计为一个真正的操作测量系统,非常适合表征和跟踪整个反应堆周期的辐射场演变。为了满足这一要求,与特定软件相关联的可编程系统允许在核心中自动完成细胞移动,数据采集和测量处理。本文介绍了利用新的CALMOS-2原型进行的2015年综合测量活动中收集的结果分析。4线技术在大约4w - g -1的加热水平下进行了测试,并允许量化“零”和校准方法之间的差异。比较了CALMOS-1和CALMOS-2的热中子通量和核加热测量值。用适用于CALMOS-2量热池的自功率中子探测器获得了热中子通量分布,并与现有装置获得的热中子通量分布进行了比较。最后,本分析倾向于强调人机界面自动化带来的优势,从而对轮廓定义进行了深入的细化。
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引用次数: 1
期刊
Reactor Dosimetry: 16th International Symposium
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