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Development Of A High Flux Neutron Radiation Detection System For In Core Temperature Monitoring
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Book Synopsis Development of a High Flux Neutron Radiation Detection System for In-core Temperature Monitoring by : Thifhelimbilu Daphney Singo
Download or read book Development of a High Flux Neutron Radiation Detection System for In-core Temperature Monitoring written by Thifhelimbilu Daphney Singo and published by . This book was released on 2012 with total page 164 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis The Development of a High Count Rate Neutron Flux Monitoring Channel Using Silicon Carbide Semiconductor Radiation Detectors by : Mehdi Reisi Fard
Download or read book The Development of a High Count Rate Neutron Flux Monitoring Channel Using Silicon Carbide Semiconductor Radiation Detectors written by Mehdi Reisi Fard and published by . This book was released on 2006 with total page 298 pages. Available in PDF, EPUB and Kindle. Book excerpt: Abstract: In this dissertation, a fast neutron flux monitoring channel, which is based on the use of SiC semiconductor detectors is designed, modeled and experimentally evaluated as a power monitor for the Gas Turbine Modular Helium Reactors. A detailed mathematical model of the SiC diode detector and the electronic processing channel is developed using TRIM, MATLAB and PSpice simulation codes. The flux monitoring channel is tested at the OSU Research Reactor. The response of the SiC neutron-monitoring channel to neutrons is in close agreement to simulation results. Linearity of the channel response to thermal and fast neutron fluxes, pulse height spectrum of the channel, energy calibration of the channel and the detector degradation in a fast neutron flux are presented. Along with the model of the neutron monitoring channel, a Simulink model of the GT-MHR core has been developed to evaluate the power monitoring requirements for the GT-MHR that are most demanding for the SiC diode power monitoring system. The Simulink model is validated against a RELAP5 model of the GT-MHR. This dyanamic model is used to simulate reactor transients at the full power and at the start up, in order to identify the response time requirements of the GT-MHR. Based on the response time requirements that have been identified by the Simulink model and properties of the monitoring channel, several locations in the central reflector and the reactor cavity are identified to place the detector. The detector lifetime and dynamic range of the monitoring channel at the detector locations are calculated. The channel dynamic range in the GT-MHR central reflector covers four decades of the reactor power. However, the detector does not survive for a reactor refueling cycle in the central reflector. In the reactor cavity, the detector operates sufficiently long; however, the dynamic range of the channel is smaller than the dynamic range of the channel in the central reflector.
Book Synopsis Development of a Semirad Detection System for High-intensity Neutron Radiation by : F. C. Riggin
Download or read book Development of a Semirad Detection System for High-intensity Neutron Radiation written by F. C. Riggin and published by . This book was released on 1967 with total page 91 pages. Available in PDF, EPUB and Kindle. Book excerpt: The design, fabrication and testing of a detection system to measure pulses of high intensity neutron radiation is discussed. The system includes a neutron detecting component operating on the SEMIRAD principle and a 'stretcher' amplifier component capable of accepting the output pulse from the detector, shaping and amplifying the pulse so that the time-integral of the pulse waveform is proportional to the neutron dose. The system was made to operate over the temperature range of -28C to +65C by modification of the detector design to permit constant vac-ion pumping even during burst time. This was considered necessary because of the hydrogenous liner outgassing as a result of elevated operating temperatures as well as the high intensity neutron pulses. The design goal of a unity gamma to neutron response ratio was achieved for fission spectrum neutrons. The amplifier itself generates a noise signal which is proportional to the incident burst yield and should be operated remotely from the detector (20 to 40 ft. cable lengths) and shielded if possible. Sufficient radiation hardness was demonstrated in the selection of amplifier components from exposure of one 'stretcher' amplifier to a total dose of 26,600 rads with no detectable change in operability. (Author).
Book Synopsis LCRE Neutron Sensor Development Program by : R. C. Harrison
Download or read book LCRE Neutron Sensor Development Program written by R. C. Harrison and published by . This book was released on 1964 with total page 54 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Development of a Solid State Neutron Detector for SNAP 10A by : A. Chesavage
Download or read book Development of a Solid State Neutron Detector for SNAP 10A written by A. Chesavage and published by . This book was released on 1966 with total page 46 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis The Development of a Thermal-neutron-flux Measuring Instrument by :
Download or read book The Development of a Thermal-neutron-flux Measuring Instrument written by and published by . This book was released on 1956 with total page 20 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Nuclear Science Abstracts written by and published by . This book was released on 1976-05 with total page 912 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Scientific and Technical Aerospace Reports by :
Download or read book Scientific and Technical Aerospace Reports written by and published by . This book was released on 1972 with total page 220 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis A Neutron Measurement System Design for Pulsed Triga Reactor Experiment at Texas A&M University by : Sophit Pongpun
Download or read book A Neutron Measurement System Design for Pulsed Triga Reactor Experiment at Texas A&M University written by Sophit Pongpun and published by . This book was released on 2016 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: This thesis focuses on designing, building, and analyzing a neutron detection system to measure neutron fluxes of a TRIGA reactor at Texas A&M University to verify newly developed simulation codes. Such a system must be designed to cover a wide range of neutron fluxes in transient power surges (up to 1015 neutrons/cm2/s, lasting 20 to 50 ms) and in steady-state operations (1013 neutrons/cm2/s at full power of one megawatt). The size of the detector is limited to a maximum of 9.525 mm outer diameter including housing. The detection system consisted of slow neutron detectors, associated electronics, data acquisition and storage equipment, and an analysis software. The detector used boron- 10 to capture slow neutrons, generating charged particles within an ionization chamber filled with air. Due to the low Q-value of the reaction, a high gain charge-sensitive preamplifier, which was a part of a miniature 16.9 mm x 298.5 mm electronic package, was placed within 1.7 m of the detector to minimize noise level. The preamplifier was designed to offer pulse mode, current mode, and high voltage current mode of operation. Experimental data were acquired at 20 MHz using a solid-state drive for data storage and were subjected to 250 MHz for up to eight-hour continuous operation using an array of five three-TB hard drives. Data analysis software was programmed using MATLAB. In addition to analysis using the shaping amplifier's output, an algorithm to generate a radiation pulse from the directly digitized preamplifier signal was proposed and tested with test pulses simulating neutron events. The detection system was tested with isotopic sources and in a dry tube located near the TRIGA reactor. The latter showed an increase in the number of gamma events with the reactor power, whereas the number of neutron events was also proportional to the power. In addition, a trial run of in-core measurements was performed. The results suggested that high gamma radiation present in the core interfered with the neutron signal. Suggestions was made for modification of the mechanical assembly of the system, compensation for gamma signals, and additional tests to improve analysis of the neutron signal.
Book Synopsis Deutsches Syllabirbuch zur Erleichterung des gleichzeitigen Lese-und Erstes lesebuch für Kinder by :
Download or read book Deutsches Syllabirbuch zur Erleichterung des gleichzeitigen Lese-und Erstes lesebuch für Kinder written by and published by . This book was released on 1862 with total page 98 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Development of a High-count-rate Neutron Detector with Position Sensitivity and High Efficiency by :
Download or read book Development of a High-count-rate Neutron Detector with Position Sensitivity and High Efficiency written by and published by . This book was released on 2006 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: While the neutron scattering community is bombarded with hints of new technologies that may deliver detectors with high-count-rate capability, high efficiency, gamma-ray insensitivity, and high resolution across large areas, only the time-tested, gas-filled [sup 3]He and scintillation detectors are in widespread use. Future spallation sources with higher fluxes simply must exploit some of the advanced detector schemes that are as yet unproved as production systems. Technologies indicating promise as neutron detectors include pixel arrays of amorphous silicon, silicon microstrips, microstrips with gas, and new scintillation materials. This project sought to study the competing neutron detector technologies and determine which or what combination will lead to a production detector system well suited for use at a high-intensity neutron scattering source.
Book Synopsis Micro-pocket Fission Detectors: Development of Advanced, Real-time In-core, Neutron-flux Sensors by : Michael Anthony Reichenberger
Download or read book Micro-pocket Fission Detectors: Development of Advanced, Real-time In-core, Neutron-flux Sensors written by Michael Anthony Reichenberger and published by . This book was released on 2017 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Advancements in nuclear reactor core modeling and computational capability have encouraged further development of in-core neutron sensors. Measurement of the neutron-flux distribution within the reactor core provides a more complete understanding of the operating conditions in the reactor than typical ex-core sensors. Micro-Pocket Fission Detectors (MPFDs) have been developed and tested previously but have been limited to single-node operation and have utilized highly specialized designs. The development of a widely deployable, multi-node MPFD assembly will enhance nuclear research capabilities. In-core neutron flux measurements include many challenges because of the harsh environment within the reactor core. Common methods of in-core neutron measurement are also limited by geometry and other physical constraints. MPFDs are designed to be small and robust while offering a real-time, spatial measurement of neutron flux. Improvements to the MPFD design were developed based on shortcomings of prior research in which many of the theoretical considerations for MPFDs were examined. Fabrication techniques were developed for the preparation of MPFD components and electrodeposition of fissile material. Numerous arrays of MPFDs were constructed for test deployments at the Kansas State University TRIGA Mk. II research nuclear reactor, University of Wisconsin Nuclear Reactor, Transient REActor Test facility at the Idaho National Laboratory (INL), and Advanced Test Reactor at INL. Preliminary testing of a single MPFD sensor at KSU yielded a linear response to reactor power between 10 kWth and 750 kWth and followed both positive and negative reactivity insertions in real-time. A $1.50 reactor pulse was monitored from the Intra-Reflector Irradiation System, located in reflector region of the KSU TRIGA Mk. II core with 1-ms time resolution. Improved multi-node MPFD arrays were then designed, fabricated, and deployed in flux ports between fuel rods and within an iron-wire flux port which was inserted into the central thimble of the KSU TRIGA Mk. II research nuclear reactor. Work continues to develop MPFDs for deployment at research reactors at INL and elsewhere. Results from the MPFD measurements will be useful for future validation of computational modeling and as part of advanced nuclear fuel development efforts.
Book Synopsis Design and Testing of Long-lifetime Active Sensor Arrays for In-core Multi-dimensional Flux Measurements by : Tyrel Daniel Frank George
Download or read book Design and Testing of Long-lifetime Active Sensor Arrays for In-core Multi-dimensional Flux Measurements written by Tyrel Daniel Frank George and published by . This book was released on 2016 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Fission chambers are a common type of detector used to determine the neutron flux and power of a nuclear reactor. Due to the limited space and high neutron flux in a reactor core, it is difficult to perform real-time flux measurements with present-day in-core instrumentation. Micro-pocket fission detectors, or MPFDs, are relatively small in size and have low neutron sensitivity while retaining a large neutron to gamma ray discrimination ratio, thereby, allowing them to be used as active neutron flux monitors inside a nuclear reactor core. The micro-pocket fission chamber allows for multiple detectors to be inserted into a flux port or other available openings within the nuclear reactor core. Any material used to construct the MPFD must be rugged and capable of sustaining radiation damage for long periods of time. Each calibrated MPFD provides measurements of the flux for a discrete location. The size of these detectors allows for a spatial map of the flux to be developed, enabling real-time analysis of core burnup, power peaking, and rod shadowing. Small diameter thermocouples can be included with the array to also measure the temperature at each location. The following document details the research and development of MPFDs for long term use in nuclear power reactors. Previous MPFD designs were improved, miniaturized, and optimized for long term operations in reactor test ports designed for passive measurements of fluence using iron wires. Detector chambers with dimensions of 0.08 in x 0.06 in x 0.04 in were attached to a common cathode and individual anodes to construct an array of the MPFDs. Each array was tested at the Kansas State University TRIGA Mark II nuclear reactor to demonstrate functionality. The linear response in reactor power was measured. These arrays have also demonstrated reactor power tracking by following reactivity changes in steady state operations and reactor pulsing events. Stability testing showed consistent operation at 100 kW for several hours. The MPFDs have been demonstrated to be a viable technology for in-core measurements.
Book Synopsis A High Temperature-tolerant and Radiation-resistant In-core Neutron Sensor for Advanced Reactors by :
Download or read book A High Temperature-tolerant and Radiation-resistant In-core Neutron Sensor for Advanced Reactors written by and published by . This book was released on 2015 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The objectives of this project are to develop a small and reliable gallium nitride (GaN) neutron sensor that is capable of withstanding high neutron fluence and high temperature, isolating gamma background, and operating in a wide dynamic range. The first objective will be the understanding of the fundamental materials properties and electronic response of a GaN semiconductor materials and device in an environment of high temperature and intense neutron field. To achieve such goal, an in-‐situ study of electronic properties of GaN device such as I-‐V, leakage current, and charge collection efficiency (CCE) in high temperature using an external neutron beam will be designed and implemented. We will also perform in-‐core irradiation of GaN up to the highest yet fast neutron fluence and an off-‐line performance evaluation.
Download or read book INIS Atomindex written by and published by . This book was released on 1980 with total page 960 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Near-Core and In-Core Neutron Radiation Monitors for Real Time Neutron Flux Monitoring and Reactor Power Level Measurements by : Paul Nelson
Download or read book Near-Core and In-Core Neutron Radiation Monitors for Real Time Neutron Flux Monitoring and Reactor Power Level Measurements written by Paul Nelson and published by . This book was released on 2006 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: MPFDs are a new class of detectors that utilize properties from existing radiation detector designs. A majority of these characteristics come from fission chamber designs. These include radiation hardness, gamma-ray background insensitivity, and large signal output.
Book Synopsis Detectors for Reactor In-core Measurement of Fast Neutron Flux by : Donald P. Brown
Download or read book Detectors for Reactor In-core Measurement of Fast Neutron Flux written by Donald P. Brown and published by . This book was released on 1973 with total page 45 pages. Available in PDF, EPUB and Kindle. Book excerpt:
