Results 21 to 30 of about 4,934 (261)

Ten springs of experiments in CROCUS [PDF]

EPJ Web of Conferences, 2023
Around a decade ago, a new team rebuilt experimental research at EPFL’s nuclear facilities, and in particular in the CROCUS nuclear reactor. After a broad investigation and open discussions with colleagues from the nuclear community, a number of ...
Lamirand Vincent
doaj   +1 more source

APPLICATION OF CALCULATED MSM FACTORS USING TRIPOLI4® SEQUENCE ON BORON LINED PROPORTIONAL COUNTER ROD WORTH MEASUREMENT [PDF]

EPJ Web of Conferences, 2021
The topic addressed deals with the determination of adjoint parameters for instrumentation relevance. This is a crucial subject for comprehension of subcritical levels in the frame of safety analysis.
Couybes J., Nicolas S., Chabert L., Manifacier L., Barbosa T., Gerlier R.   +5 more
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Reactor performance, system reliability, instrumentation and control

EPJ Nuclear Sciences & Technologies, 2020
We present a cross-cutting review of three on-going Horizon 2020 projects (ADVISE, NOMAD, TEAM CABLES) and one already finished FP7 project (HARMONICS), which address the reliability of safety-relevant components and systems in nuclear power plants, with
Schumm Andreas, Rabung Madalina, Marque Gregory, Hamalainen Jary   +3 more
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Nuclear reactor vessel water level prediction during severe accidents using deep neural networks

Nuclear Engineering and Technology, 2019
Acquiring instrumentation signals generated from nuclear power plants (NPPs) is essential to maintain nuclear reactor integrity or to mitigate an abnormal state under normal operating conditions or severe accident circumstances.
Young Do Koo, Ye Ji An, Chang-Hwoi Kim, Man Gyun Na   +3 more
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Nuclear heating rate measurement in the MIT research reactor using a new compact CALORRE differential calorimeter [PDF]

EPJ Web of Conferences
This paper presents experimental results obtained thanks to a new compact prototype of CALORRE calorimeter during an irradiation campaign inside the MIT Research Reactor (MITR) in October 2024 within the framework of the CALOR-I research program led by ...
Reynard-Carette C., Volte A., Kohse G., Carpenter D., Ostrovsky Y., Ames M., Hauptman S., Lyoussi A., Carette M.   +8 more
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Extending the panel of inelastic scattering reactions availaible for dosimetry: Definition of the experimental campaign at the JSI TRIGA reactor [PDF]

EPJ Web of Conferences
The epithermal to fast neutron domain lacks reactions to enhance the knowledge of spectrum in this energy range (1 keV to 1 MeV). Previous studies on this topic focused on 94Zr(n, γ) capture and 117Sn(n, n′) inelastic reactions.
Grégoire Gilles, Radulovic Vladimir, Žerovnic Gasper, Domergue Christophe, Philibert Hervé, Fausser Clément, Tisseur David, Thiollay Nicolas, Barbot Loic, Destouches Christophe   +9 more
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New Neutron Imaging Facility NIFFLER at Very Low Power Reactor VR-1

Journal of Imaging, 2023
The paper describes the construction of the neutron imaging facility at the very low-power research reactor VR-1. The training reactor VR-1 is operated by the Czech Technical University in Prague, Czech Republic.
Jana Matouskova, Burkhard Schillinger, Lubomir Sklenka   +2 more
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Enhanced In-Pile Instrumentation at the Advanced Test Reactor [PDF]

IEEE Transactions on Nuclear Science, 2011
Many of the sensors deployed at materials and test reactors cannot withstand the high flux/high temperature test conditions often requested by users at U.S. test reactors, such as the Advanced Test Reactor (ATR) at the Idaho National Laboratory. To address this issue, an instrumentation development effort was initiated as part of the ATR National ...
Rempe, Joy, Knudson, Darrell, Daw, Joshua, Unruh, Troy, Chase, Benjamin, Davis, Kurt, Schley, Robert, Taylor, Steven   +7 more
openaire   +1 more source

Cherenkov reactor power meter: Development of an innovative and cost-effective technique for reactor power monitoring

Nuclear Engineering and Technology
This study investigates the development and application of a Cherenkov power meter as an innovative alternative for the power monitoring of nuclear reactors.
Julijan Peric, Luka Snoj, Vladimir Radulović   +2 more
doaj   +1 more source

Development of neutron flux measurement module for research reactors based on FPGA. Part-1-Model development and generic verification

Alexandria Engineering Journal, 2020
Many Instrumentation and Control (I&C) systems of Research reactors experience aging difficulties that necessitate optimizing operations and safety systems. Therefore, great attention paid to FPGA-based I&C use particularly in safety systems; this is due
Mjzoob I. Ibrahim, Magdy M. Zaky, Mohamed H. Hassan, Mohammad Nagy   +3 more
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