On line neutron flux mapping in fuel coolant channels of a research reactor-Reference-Cited by-同舟云学术

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On line neutron flux mapping in fuel coolant channels of a research reactor

Published:2013-06 Issue: Volume: Page:
ISSN:
Container-title:2013 3rd International Conference on Advancements in Nuclear Instrumentation, Measurement Methods and their Applications (ANIMMA)
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Author:

Barbot Loic,Domergue Christophe,Villard Jean-Francois,Destouches Christophe,Braoudakis George,Wassink David,Sinclair Bradley,Osborn John C.,Huayou Wu ,Blandin Christophe,Thevenin Mathieu,Corre Gwenole,Normand Stephane

Publisher

IEEE

Link

http://xplorestaging.ieee.org/ielx7/6717173/6727869/06727951.pdf?arnumber=6727951

Cited by 5 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Qualification of the Industrialized Libera MONACO 3 Digital Acquisition System dedicated to Fission/Ion Chamber Measurements in Research Reactors;EPJ Web of Conferences;2023

2. MONACO v2: Multipurpose and Integrated Data Acquisition System for On-line Neutron and Gamma Measurements;EPJ Web of Conferences;2020

3. Digital Real-Time Multiple Channel Multiple Mode Neutron Flux Estimation on FPGA-based Device;EPJ Web of Conferences;2016

4. Validation of neutron flux redistribution factors in JSI TRIGA reactor due to control rod movements;Applied Radiation and Isotopes;2015-10

5. Validation of the neutron and gamma fields in the JSI TRIGA reactor using in-core fission and ionization chambers;Applied Radiation and Isotopes;2015-02

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