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2012 American Control Conference (ACC), 2012
Self Powered Neutron Detectors (SPNDs), which are widely used in a nuclear reactor for flux measurement, typically have different types of dynamics based on their emitter material: one delayed, second prompt and possibly nonlinear response characteristics. The measurement from the SPNDs hence need compensation to obtain the actual input flux.
Krishnan Srinivasarengan +6 more
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Self Powered Neutron Detectors (SPNDs), which are widely used in a nuclear reactor for flux measurement, typically have different types of dynamics based on their emitter material: one delayed, second prompt and possibly nonlinear response characteristics. The measurement from the SPNDs hence need compensation to obtain the actual input flux.
Krishnan Srinivasarengan +6 more
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Numerical analysis of the space charge effect in SPNDs based on the charge conservation principle
Journal of InstrumentationAbstract Low-energy electrons emitted from self-powered neutron detectors(SPNDs) typically induce the space charge effect, attributed to the intrinsically high resistivity of insulator materials. As a pivotal phenomenon in SPND theoretical simulations, this effect directly impacts both the prediction accuracy of the response
Y. Zhou +6 more
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Annals of Nuclear Energy, 2016
Abstract This paper deals with delay compensation of vanadium Self Powered Neutron Detectors (SPNDs) using Linear Matrix Inequality (LMI) based H-infinity filtering method and compares the results with Kalman filtering method. The entire study is established upon the framework of neutron flux estimation in large core Pressurized Heavy Water Reactor ...
TAMBOLI, PK, DUTTAGUPTA, SP, ROY, K
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Abstract This paper deals with delay compensation of vanadium Self Powered Neutron Detectors (SPNDs) using Linear Matrix Inequality (LMI) based H-infinity filtering method and compares the results with Kalman filtering method. The entire study is established upon the framework of neutron flux estimation in large core Pressurized Heavy Water Reactor ...
TAMBOLI, PK, DUTTAGUPTA, SP, ROY, K
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2011 2nd National Conference on Emerging Trends and Applications in Computer Science, 2011
This paper aims to denoise a neutron power sensor data which is the output of Self Powered Neutron Detector (SPND) in each of the Liquid Zone Compartments (LZC) in a nuclear reactor core. Noisy data measured over long period is analyzed with different types of wavelets by one dimensional Discrete Wavelet Transform (DWT) technique to investigate the ...
Basudev Majumder +4 more
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This paper aims to denoise a neutron power sensor data which is the output of Self Powered Neutron Detector (SPND) in each of the Liquid Zone Compartments (LZC) in a nuclear reactor core. Noisy data measured over long period is analyzed with different types of wavelets by one dimensional Discrete Wavelet Transform (DWT) technique to investigate the ...
Basudev Majumder +4 more
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Simulation of SPND Beta-Current in AP1000 Core
International Conference on Physics of Reactors 2022 (PHYSOR 2022), 2022Ruizhi Shao +7 more
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Sensitivity analysis of AHWR flux mapping system for unavailability of SPNDs
Nuclear Engineering and Design, 2022B. Anupreethi +4 more
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Journal of Nuclear Engineering and Radiation Science, 2017
The advanced lead fast reactor European demonstrator (ALFRED) is a European research initiative into the framework of the Generation IV International Forum facilities. ALFRED is a scaled down reactor compared to the industrial prototype European lead fast reactor proposed in lead-cooled European advanced demonstration reactor.
LEPORE, LUIGI, REMETTI, Romolo
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The advanced lead fast reactor European demonstrator (ALFRED) is a European research initiative into the framework of the Generation IV International Forum facilities. ALFRED is a scaled down reactor compared to the industrial prototype European lead fast reactor proposed in lead-cooled European advanced demonstration reactor.
LEPORE, LUIGI, REMETTI, Romolo
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Analysis of WIRE-21 SPND and Optical Fiber Sensor Measurements
2023Daniel Sweeney +2 more
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Steady and Transient Analysis of Flow and Heat Transfer in SPND Assembly
2014This thesis presents the analysis of flow and heat transfer for the SPND (Self-Powered Neutron Detector) system used within the nuclear reactor core in the U.S. Evolutionary Power Reactor developed by AREVA. The SPND system is composed of six individual detectors which are used for in-core measurement of thermal neutron flux.
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