scholarly journals WIDE-RANGE (10 DECADE) NEUTRON FLUX MONITORING CHANNEL.

1971 ◽  
Author(s):  
Not Given Author
Keyword(s):  
Neutron Flux ◽  
Wide Range ◽  
Flux Monitoring

Development of a wide-range neutron flux monitoring system in EAST

2020 ◽  
Vol 15 (05) ◽  
pp. P05011-P05011
Author(s):  
G.Q. Zhong ◽  
K. Li ◽  
L.Q. Hu ◽  
H.R. Cao ◽  
R.J. Zhou ◽  
...  
Keyword(s):  
Neutron Flux ◽  
Monitoring System ◽  
Wide Range ◽  
Flux Monitoring

scholarly journals Digitalization of the Ex-Core Neutron Flux Monitoring System for APR1400 Nuclear Power Plant

2020 ◽  
Vol 10 (23) ◽  
pp. 8331
Author(s):  
Young Baik Kim ◽  
Felipe P. Vista ◽  
Seung Bin Cho ◽  
Kil To Chong
Keyword(s):  
Neutron Flux ◽  
Monitoring System ◽  
Nuclear Power ◽  
Power Plants ◽  
Gamma Ray ◽  
Reactor Power ◽  
Power Calculation ◽  
Wide Range ◽  
Flux Monitoring ◽  
And Performance

This work studied the feasibility of digitalizing the analog Ex-Core Neutron Flux Monitoring System (ENFMS) being used for APR1400 nuclear power plants (NPPs) and as to which strategies and steps must be taken. A fission chamber neutron flux detection and instrumentation model were designed. Its accuracy was evaluated and proven by comparing the model data with data gathered from tests and plant operations. A conceptual design was proposed through a combined structure that digitalizes only part of the system. The detector signal pre-amplification remains in analog form while the other functions such as reactor power calculation as well as signal conditioning and processing will be digitalized. Simulations showed that the true mean squared voltage (MSV) of the digitalized ENFMS maintained a linear relationship between real and estimated reactor power in the wide range compared to averaged magnitude squared value of analog ENFMS. Extended Kalman Filter (EKF) was also utilized for estimating reactor power and reactor period from measurement signals that are contaminated with gamma ray interaction and electric noise. This study proved that the ENFMS can be successfully digitalized as proposed wherein all functional and performance requirements are satisfied. Simulations results demonstrated that the functions and performance can be improved through the use of digital processing algorithms such as EKF and MSV.

Algorithm for the Correction of the Power Reading for Neutron Flux Monitoring Channels

2013 ◽  
Vol 4 (8) ◽  
pp. 758-764
Author(s):  
A. A. Semenov ◽  
A. A. Druzhaev ◽  
I. A. Sergeev ◽  
N. V. Shchukin ◽  
V. I. Strikovskii
Keyword(s):  
Neutron Flux ◽  
Flux Monitoring

Nuclear Instrumentation Systems in Prototype Fast Breeder Reactor

2004 ◽  
Author(s):  
P. M. Vijayakumaran ◽  
C. P. Nagaraj ◽  
C. Paramasivan Pillai ◽  
R. Ramakrishnan ◽  
M. Sivaramakrishna
Keyword(s):  
Neutron Flux ◽  
Early Warning System ◽  
Warning System ◽  
Radiation Monitoring ◽  
Fast Breeder Reactor ◽  
Delayed Neutrons ◽  
The Core ◽  
Flux Monitoring ◽  
Nuclear Instrumentation ◽  
Fission Chambers

The nuclear instrumentation systems of the Prototype Fast Breeder Reactor (PFBR) primarily comprise of global Neutron Flux Monitoring, Failed Fuel Detection & Location, Radiation Monitoring and Post-Accident Monitoring. High temperature fission chambers are provided at in-vessel locations for monitoring neutron flux. Failed fuel detection and location is by monitoring the cover gas for fission gases and primary sodium for delayed neutrons. Signals of the core monitoring detectors are used to initiate SCRAM to protect the reactor from various postulated initiating events. Radiation levels in all potentially radioactive areas are monitored to act as an early warning system to keep the release of radioactivity to the environment and exposure to personnel well below the permissible limits. Fission Chambers and Gamma Ionisation Chambers are located in the reactor vault concrete for monitoring the neutron flux and gamma radiation levels during and after an accident.

Neutron Flux Monitoring Apparatus for Gen-3+, 4 NPP

Atomic Energy ◽  
2018 ◽  
Vol 125 (1) ◽  
pp. 18-22
Author(s):  
Yu. S. Koptelov
Keyword(s):  
Neutron Flux ◽  
Flux Monitoring

scholarly journals Characterization and localization of partial-discharge-induced pulses in fission chambers designed for sodium-cooled fast reactors

2018 ◽  
Vol 170 ◽  
pp. 03002
Author(s):  
G. Galli ◽  
H. Hamrita ◽  
C. Jammes ◽  
M.J. Kirkpatrick ◽  
E. Odic ◽  
...  
Keyword(s):  
High Temperature ◽  
Neutron Flux ◽  
Electrical Discharge ◽  
Partial Discharge ◽  
Electrical Signal ◽  
Fast Reactors ◽  
Electrode Gap ◽  
Fission Chamber ◽  
Flux Monitoring ◽  
Fission Chambers

During the operation of the Superphenix and Phenix reactors, an aberrant electrical signal was detected from the fission chambers used for neutron flux monitoring. This signal, thought to be due to partial electrical discharge (PD) is similar to the signal resulting from neutron interactions, and is generated in fission chambers at temperatures above 400 °C. This paper reports work on the characterization and localization of the source of this electrical signal in a High Temperature Fission Chamber (HTFC). The relation between the shape of the PD signal and various parameters (nature and pressure of the chamber filling gas, electrode gap distance, and fission chamber geometry) are first described. Next, experiments designed to identify the location within the chambers where the PD are being generated are presented. After verification and refinement of the results of these localization studies, it should be possible to propose changes to the fission chamber in order to reduce or eliminate the PD signal.

scholarly journals On Capabilities and Limitations of Current Fast Neutron Flux Monitoring Instrumentation for the Demo LFR ALFRED

2016 ◽  
Vol 2 (4) ◽  
Author(s):  
Luigi Lepore ◽  
Romolo Remetti ◽  
Mauro Cappelli
Keyword(s):  
Monte Carlo ◽  
Neutron Flux ◽  
Fast Reactor ◽  
Nuclear Power ◽  
Power Plants ◽  
Fuel Cycle ◽  
Signal To Noise Ratio ◽  
Reactor Power ◽  
Fast Reactors ◽  
Flux Monitoring

Among GEN IV projects for future nuclear power plants, lead-cooled fast reactors (LFRs) seem to be a very interesting solution due to their benefits in terms of fuel cycle, coolant safety, and waste management. The novelty of this matter causes some open issues about coolant chemical aspects, structural aspects, monitoring instrumentation, etc. Particularly, hard neutron flux spectra would make traditional neutron instrumentation unfit to all reactor conditions, i.e., source, intermediate, and power range. Identification of new models of nuclear instrumentation specialized for LFR neutron flux monitoring asks for an accurate evaluation of the environment the sensor will work in. In this study, thermal hydraulics and chemical conditions for the LFR core environment will be assumed, as the neutron flux will be studied extensively by the Monte Carlo transport code MCNPX (Monte Carlo N-Particles X-version). The core coolant’s high temperature drastically reduces the candidate instrumentation because only some kinds of fission chambers and self-powered neutron detectors can be operated in such an environment. This work aims at evaluating the capabilities of the available instrumentation (usually designed and tailored for sodium-cooled fast reactors) when exposed to the neutron spectrum derived from the Advanced Lead Fast Reactor European Demonstrator, a pool-type LFR project to demonstrate the feasibility of this technology into the European framework. This paper shows that such a class of instrumentation does follow the power evolution, but is not completely suitable to detect the whole range of reactor power, due to excessive burnup, damages, or gamma interferences. Some improvements are possible to increase the signal-to-noise ratio by optimizing each instrument in the range of reactor power, so to get the best solution. The design of some new detectors is proposed here together with a possible approach for prototyping and testing them by a fast reactor.

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