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Design Development Characterization And Application Of A New Neutron Imaging Facility At The Penn State Breazeale Reactor
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Book Synopsis Design, Development, Characterization, and Application of a New Neutron Imaging Facility at the Penn State Breazeale Reactor by : Alibek Kenges
Download or read book Design, Development, Characterization, and Application of a New Neutron Imaging Facility at the Penn State Breazeale Reactor written by Alibek Kenges and published by . This book was released on 2023 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: Neutron imaging is a powerful tool in the field of non-destructive testing that utilizes unique attenuation properties of neutrons allowing through-images of some high-density objects. The Radiation Science and Engineering Center (RSEC) has had a neutron imaging facility for the last several decades. With the installation of a new core moderator assembly and new beam ports at the RSEC -- the Penn State Breazeale Reactor (PSBR) in 2018, a dedicated neutron beam port became available for a new neutron imaging facility at RSEC (RSEC -- NIF). The initial design of the beam port designated for the RSEC -- NIF was of divergent type that needed to be upgraded by means of collimator components and filters. After a thorough investigation of existing neutron imaging facilities around the world, it has been decided to collimate the beam port with convergent and divergent collimators and to filter the gamma and neutron content with the single crystal bismuth and sapphire filters. A set of system characterization experiments were conducted at the RSEC -- NIF that confirmed the system's correspondence to a Category I facility by ASTM standards. In addition to that, the collimation ratio of the new system was measured following the procedures given in the ASTM protocols and resulted in the effective L/D ratio value between 107 and 115. The thermal flux across the exit surface from the beam port at the biological shield was measured to be equal to 5.4E+06 n/cm^2-s at 1MWth reactor power. The application of the RSEC -- NIF's capabilities in neutron radiography (NR) and tomography (NT) techniques were demonstrated imaging different types of environmental samples for the presence and visualization of microplastic particles. Preliminary results of NT experiments conducted at the RSEC -- NIF have shown that this technique can be used as an intermediary step to visualize the content and spatial distribution of microplastics in the sand columns. Additionally, the NR capabilities of the RSEC -- NIF were utilized to visualize the microplastic particles in the sediment samples and used water filters. All obtained results and the continuation of research in this direction can potentially shed some light in the general research of microplastic transport mechanisms in different terrestrial and aquatic ecosystems.
Book Synopsis Design of an Epithermal Neutron Chopper for the Penn State Breazeale Reactor and Its Applications for Nuclear Forensics and Fundamental Nuclear Data by : Nicholas Grenci
Download or read book Design of an Epithermal Neutron Chopper for the Penn State Breazeale Reactor and Its Applications for Nuclear Forensics and Fundamental Nuclear Data written by Nicholas Grenci and published by . This book was released on 2022 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: There is a need for fast, nondestructive techniques to monitor nuclear materials and associated manufacturing processes throughout the traditional nuclear fuel cycle. Accurately analyzing unique elemental and isotopic signatures can enhance the ability to monitor and verify nuclear-material related activities. Epithermal neutron activation analysis (ENAA) allows for additional information to be extracted when compared to thermal or typical nuclear reactor spectrum neutron activation analysis. Many isotopes of many elements have similar radiative capture cross-sections at thermal neutron energies, whereas cross-sections among isotopes in the epithermal energy regime can span orders of magnitude at resonant energies. It is therefore desirable to have a nearly monochromatic, tunable source of neutrons to preferentially activate isotopes of interest at their resonant energies, thereby enhancing the experimental signal to noise ratio. A comprehensive review of the nuclear fuel cycle was performed to analyze elemental and isotopic compositions of samples throughout the traditional fuel cycle. To complement the existing nuclear forensics science, industrial processing variability was investigated in an attempt to identify unique signatures that are indicative of specific industrial processing techniques or materials utilized. Variations in techniques, industrial equipment, and processing of nuclear material have been investigated for the front end of the nuclear fuel cycle, namely: mining, milling, conversion, enrichment, and fuel fabrication. A holistic review of the nuclear fuel cycle was used to make inferences regarding relevant criteria for a nondestructive assay technique to monitor nuclear material processing. Time correlated prompt gamma activation analysis (PGAA) was selected as the nondestructive assay technique, and the advantages, methodologies, and instrumentation required for these measurements were investigated. PGAA will be used as a fast interrogation technique to verify nuclear material manufacturing processes. To utilize PGAA, a series of mechanical neutron choppers to be used as both a time-of-flight (TOF) and velocity selection system have been developed for use at the Penn State Breazeal Reactor (PSBR). The design goals of this system were intended to effectively pulse epithermal neutrons in the energy range of 0.5 - 40 eV with 2% or better neutron energy resolution, and a neutron transmission of 1E-6 or better. The operating energy range and resolution for the mechanical neutron chopper system were determined after evaluating characteristics of many isotopic resonances of interest. Specifically, it was observed that many resonances in the energy range of 0.5 - 40 eV have a full width half maximum (FWHM) of 1 eV or less. Four different chopper geometries have been evaluated for their utility as mechanical neutron choppers for the proposed chopper system. In particular, Fermi, ring, piston, and disc choppers have been assessed for their potential neutronics performance and mechanical durability and constructability. In addition, simulations were performed to quantitatively assess different neutron absorbing materials. A series of high-speed disc choppers was selected for the final design, and optimization work was performed to maximize the neutron pulse intensity. Analytical calculations regarding the neutron transmission and time structure of the pulse were verified with Monte Carlo simulations. It has been estimated that the optimized system will produce an epithermal neutron intensity of 2.2E4 n/MW*s where the simulated energy bounds are 0.5 and 43.1 eV. These energy bounds correspond to the simulated energy bin from MCNP6.2 at the upper limit of the operating range of the mechanical neutron chopper. This facility can also be operated in a TOF configuration such that the neutrons arriving at the source have a white (continuous energy) spectrum. This can be accomplished by holding the second stage of choppers stationary (or removing it from the beam completely). The unique source of epithermal neutrons capable of being produced by this facility will have applications in both prompt and delayed ENAA, as well as neutron resonance transmission analysis (NRTA) and fundamental nuclear data measurements. A data tool has also been created to estimate the material response for time correlated PGAA measurements. The creation of this tool serves three main purposes. The first is to evaluate sample sensitivity to the mechanical neutron chopper system. Second, the data tool is used to identify unique signatures relevant for nuclear forensics. Lastly, the data tool complements the design of the mechanical neutron chopper to provide a sample dependent set of optimal set of operating parameters based on the sensitivity and unique signature analysis. To do this, all isotopic cross-sections contained in a release of MCNP6.2 were evaluated for resonance structure. A hypothetical reference sample library is under development based on inductively coupled plasms mass spectrometry (ICP-MS) data found in literature and ASTM standards. The elemental composition, natural abundances, and microscopic cross-section data are used to construct complex macroscopic cross-sections of samples as a function of neutron energy between the operating energy range of the chopper system. The macroscopic cross-sections were analyzed for unique signature identification and isotopic sensitivity based on concentration. This analysis presented is used to provide an optimal set of operating parameters for the neutron chopper instrument. The review of variability within nuclear fuel cycle industrial processing as well as the data analysis tool provides a novel, systematic approach to identify unique, observable signatures relevant to nuclear forensic science.
Book Synopsis Design and Characterization of a Facility for Fast Neutron Irradiation of Semiconductors at Penn State by : B. Petrovic
Download or read book Design and Characterization of a Facility for Fast Neutron Irradiation of Semiconductors at Penn State written by B. Petrovic and published by . This book was released on 2001 with total page 8 pages. Available in PDF, EPUB and Kindle. Book excerpt: This paper describes the design and characterization of a fast neutron irradiation facility (FNI) at the Penn State Breazeale Reactor. The facility was designed to provide a hard neutron spectrum with a minimum of contamination by thermal neutrons and gamma rays, and to accommodate semiconductor wafers of up to 8 inches (~20 cm) in diameter. The design was effected through two-step Monte Carlo simulations that included (i) core criticality simulations, and (ii) FNI shielding analysis. A rectangular FNI shape was selected to improve the neutronic coupling between the FNI and the core. Analysis was performed to determine an optimum combination of materials and their dimensions. The FNI was constructed and it has been in use for about two years now. A set of activation foils was irradiated to obtain the FNI neutron spectrum andevaluate spatial flux distribution. The neutron spectrum was unfolded using the SAND-II code. Good agreement was observed between the calculated and measured data.
Download or read book Neutron Radiography written by Garbe,U. and published by Materials Research Forum LLC. This book was released on 2020-02-05 with total page 316 pages. Available in PDF, EPUB and Kindle. Book excerpt: Neutron radiography represents a powerful non-destructive testing technique that is still very much in development. The book reveals the amazing diversity of scientific and industrial applications of this technique, the advancements of the state-of-art neutron facilities, the latest method developments, and the expected future of neutron imaging.
Book Synopsis Design, Construction and Characterization of an External Neutron Beam Facility at The Ohio State University Nuclear Reactor Laboratory by : Danyal J. Turkoglu
Download or read book Design, Construction and Characterization of an External Neutron Beam Facility at The Ohio State University Nuclear Reactor Laboratory written by Danyal J. Turkoglu and published by . This book was released on 2012 with total page 93 pages. Available in PDF, EPUB and Kindle. Book excerpt: Abstract: The objective of this research was to bring a thermal neutron beam facility to the Ohio State University Nuclear Reactor Laboratory for the purposes of neutron-based research. The neutron beam is extracted from the reactor core through a neutron collimator emplaced in Beam Port #2, the radial beam port facing the core at a 30° angle. The collimator is an aluminum tube containing components designed to filter and shape the neutron beam. The filters are poly-crystalline bismuth (10.16 cm thickness, 12.7 cm diameter) for significantly reducing gamma ray content and single-crystal sapphire (12.7 cm thickness, 10.16 cm diameter) for preferentially passing thermal neutrons while scattering more energetic neutrons out of the beam. The thermal neutron beam is defined by multiple 3.0 cm diameter apertures in borated aluminum. Apertures in polyethylene-based disks and in Pb disks provide shielding for fast neutrons and gamma rays, respectively, in the neutron collimator. Characterization of the beam was performed using foil activation analysis to find the neutron flux and a low-cost digital neutron imaging apparatus to "see" the beam profile. The neutron collimator delivers the filtered thermal neutron beam with a 3.5 cm diameter umbra and a thermal neutron equivalent flux of (8.55 +̲ 0.19) x 106 cm−2s−1 at 450 kW reactor power (90% of rated limit) to the sample location. The beam is highly thermalized with a cadmium ratio of 266 +̲ 13. The facility was designed for neutron depth profiling, a nondestructive analytical technique for finding the concentration versus depth in the near surface (tens of microns) for isotopes that undergo charged particle emitting reactions, such as 10B(n, 4He)7Li, 6Li (n, 3H)4He, and 3He (n, 1H)3H, to name a few.
Book Synopsis Use of Neutron Beams for Materials Research Relevant to the Nuclear Energy Sector by : International Atomic Energy Agency
Download or read book Use of Neutron Beams for Materials Research Relevant to the Nuclear Energy Sector written by International Atomic Energy Agency and published by . This book was released on 2015 with total page 82 pages. Available in PDF, EPUB and Kindle. Book excerpt: "This publication is a compilation of the main results and findings of an IAEA coordinated research project (CRP) on development, characterization and testing of materials of relevance to nuclear energy sector using neutron beams. The document contains joint research results from nineteen institutions, which can be grouped into the main six technical areas: investigation of oxide dispersion-strengthened steels, research on zirconium based materials (including hydrogen uptake), investigations of welded structures and objects, results with irradiated materials, optimization of instruments for residual strain/stress measurements, and efforts towards standardization of neutron imaging. Particular emphasis was placed on variable environments during material characterization and testing as required by some applications such as intensive irradiation load, high temperature and high pressure conditions, and the presence of strong magnetic fields. The publication also includes some additional materials supplied by the international experts along with nineteen individual contributions describing the current status of use of diverse neutron beam techniques for materials research targeting the nuclear energy sector. These nineteen individual reports are available on CD-ROM attached to this publication. The publication will be of interest to physicists and engineers in the area of materials research, neutron beam scientists and personnel responsible for instruments, managers of neutron beam facilities, nuclear reactor designers and nuclear industry representatives."--Publisher's description.
Book Synopsis Neutron Beam Design, Development, and Performance for Neutron Capture Therapy by : Otto K. Harling
Download or read book Neutron Beam Design, Development, and Performance for Neutron Capture Therapy written by Otto K. Harling and published by Springer Science & Business Media. This book was released on 2013-03-08 with total page 340 pages. Available in PDF, EPUB and Kindle. Book excerpt: For this Workshop, the organizers have attempted to invite experts from all known centers which are engaged in neutron beam development for neutron capture therapy. The Workshop was designed around a series of nineteen invited papers which dealt with neutron source design and development and beam characterization and performance. Emphasis was placed on epithermal beams because they offer clinical advantages and are more challenging to implement than thermal beams. Fission reactor sources were the basis for the majority of the papers; however three papers dealt with accelerator neutron sources. An additional three invited papers provided a summary of clinical results of Ncr therapy in Japan between 1968 and 1989 and overviews of clinical considerations for neutron capture therapy and of the status of tumor targeting chemical agents for Ncr. Five contributed poster papers dealing with NCT beam design and performance were also presented. A rapporteurs' paper was prepared after the Workshop to attempt to summarize the major aspects, issues, and conclusions which resulted from this Workshop. Many people contributed to both the smooth functioning of the Workshop and to the preparation of these proceedings. Special thanks are reserved for Ms. Dorothy K.
Book Synopsis Development of a Thermal Neutron Imaging Facility at the N.C. State University PULSTAR Reactor by : Kaushal Kishor Mishra
Download or read book Development of a Thermal Neutron Imaging Facility at the N.C. State University PULSTAR Reactor written by Kaushal Kishor Mishra and published by . This book was released on 2005 with total page 108 pages. Available in PDF, EPUB and Kindle. Book excerpt: Keywords: Neutron Imaging.
Book Synopsis Development of a Thermal Neutron Imaging Facility at the N.C. State University PULSTAR Reactor by :
Download or read book Development of a Thermal Neutron Imaging Facility at the N.C. State University PULSTAR Reactor written by and published by . This book was released on 2004 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Analytical Techniques in Forensic Science by : Rosalind Wolstenholme
Download or read book Analytical Techniques in Forensic Science written by Rosalind Wolstenholme and published by John Wiley & Sons. This book was released on 2021-01-26 with total page 464 pages. Available in PDF, EPUB and Kindle. Book excerpt: An in-depth text that explores the interface between analytical chemistry and trace evidence Analytical Techniques in Forensic Science is a comprehensive guide written in accessible terms that examines the interface between analytical chemistry and trace evidence in forensic science. With contributions from noted experts on the topic, the text features a detailed introduction analysis in forensic science and then subsequent chapters explore the laboratory techniques grouped by shared operating principles. For each technique, the authors incorporate specific theory, application to forensic analytics, interpretation, forensic specific developments, and illustrative case studies. Forensic techniques covered include UV-Vis and vibrational spectroscopy, mass spectrometry and gas and liquid chromatography. The applications reviewed include evidence types such as fibers, paint, drugs and explosives. The authors highlight data collection, subsequent analysis, what information has been obtained and what this means in the context of a case. The text shows how analytical chemistry and trace evidence can problem solve the nature of much of forensic analysis. This important text: Puts the focus on trace evidence and analytical science Contains case studies that illustrate theory in practice Includes contributions from experts on the topics of instrumentation, theory, and case examples Explores novel and future applications for analytical techniques Written for undergraduate and graduate students in forensic chemistry and forensic practitioners and researchers, Analytical Techniques in Forensic Science offers a text that bridges the gap between introductory textbooks and professional level literature.
Book Synopsis Analysis and Design of an Improved Neutron Radiography Facility at the M.I.T. Research Reactor by : Robert Henry Smith
Download or read book Analysis and Design of an Improved Neutron Radiography Facility at the M.I.T. Research Reactor written by Robert Henry Smith and published by . This book was released on 1981 with total page 150 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Development of a Neutron Radiography and Computed Tomography System at a University Research Reactor by : Derek Anderson Haas
Download or read book Development of a Neutron Radiography and Computed Tomography System at a University Research Reactor written by Derek Anderson Haas and published by . This book was released on 2006 with total page 130 pages. Available in PDF, EPUB and Kindle. Book excerpt: Neutron radiography is a non-destructive analysis tool that complements X-ray transmission radiography. The use of neutrons provides the ability to image the interior of an object that has a metal core of steel or lead that would shield the interior from X-ray inspection. Neutron tomography is the use of a set of images of a single sample taken at various angles to produce a three dimensional rendition of the sample that greatly increases the effectiveness of neutron radiography as a non-destructive testing tool. A neutron radiography and tomography system has been built at the 1.1 MW TRIGA Mark II nuclear research reactor at The University of Texas at Austin in the Nuclear Engineering Teaching Lab. The Texas Neutron Imaging Facility is located on beam port five of the reactor and is housed in a shielding cave made of concrete to minimize radiation dose to users. The system itself integrates a sample positioning system and neutron sensitive camera through the use of a control code written in National Instruments Labview software. The code was written to increase the efficiency of the imaging process and to provide flexibility in the system. Precise sample positioning and timing of image acquisition provided by the code allows for the collection of data that can be used in computed tomography. The system has produced results in the form of radiographs and 3-D reconstructions of sample objects.
Book Synopsis Neutron Imaging and Applications by : Ian S. Anderson
Download or read book Neutron Imaging and Applications written by Ian S. Anderson and published by Springer. This book was released on 2011-09-08 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: Neutron Imaging and Applications offers an introduction to the basics of neutron beam production in addition to the wide scope of techniques that enhance imaging application capabilities. An instructional overview of neutron sources, detectors, optics and spin-filters allows readers to delve more deeply into the discussions of radiography, tomography and prospective applications available in neutron holography techniques. A section devoted to current applications describes imaging single grains in polycrystalline materials, neutron imaging of geological materials and other materials science and engineering areas. Coverage of thermal neutron imaging of biological tissues, plant physiology, Homeland Security and contraband detection explore the future prospects of this cutting-edge research. Written by key experts in the field, researchers and engineers involved with imaging technologies will find Neutron Imaging and Applications a valuable reference.
Book Synopsis Design, Construction, and Characterization of a Fast Neutron Beam Port Facility at the University of Texas at Austin TRIGA Reactor by : Daniel Caldwell Barron
Download or read book Design, Construction, and Characterization of a Fast Neutron Beam Port Facility at the University of Texas at Austin TRIGA Reactor written by Daniel Caldwell Barron and published by . This book was released on 2018 with total page 518 pages. Available in PDF, EPUB and Kindle. Book excerpt: A fast neutron irradiation facility has been designed, modeled, and constructed in the beam port 4 facility at The University of Texas at Austin’s TRIGA Mark-II Reactor. This facility targets the Watt-fission neutron spectrum in a controlled environment by reducing the present thermal and epithermal flux while preserving the fast neutron flux. The present facility will open new avenues in nuclear non-proliferation for fast-fission yields in addition to measuring radionuclide migration. The filter system was designed using MCNP and Solidworks and consists of a lead plug to stop gamma-rays, filter elements of natural boron and 96% enriched B10, collimation elements of borated polyethylene and natural boron, and an exit filter of boron nitride. A beam stop was constructed to reduce the ambient dose rate using borated paraffin wax, polyethylene, cadmium, and lead. Sensitivity studies were performed to configure an economic facility by optimizing the amounts and configurations of materials used in the filter. The filter is modular to allow for rearrangement of elements and the ability to change the materials used as needed should higher efficiencies be desired or a higher total flux. Initial results indicate the facility produces a 10 cm diameter beam with an integrated flux of 6.63x105 n/cm2/s at a reactor power of 950 kW and resembles the Watt-fission spectrum well with a slightly elevated epithermal neutron flux. The fast neutron flux above 0.1 MeV constitutes 98.77% of the total flux and the thermal neutron flux only 0.0014% of the total flux. STAYSL PNNL was used to unfold the neutron spectrum from 9 measurable reactions in 5 flux foils. Results suggest that the fast neutron flux is higher than anticipated in all STAYSL runs although the total flux is lower than anticipated.
Book Synopsis The Characterization and Monte Carlo Simulation of the Neutron Radiography Facility at Sandia National Laboratories by : Roger James Kapsimalis
Download or read book The Characterization and Monte Carlo Simulation of the Neutron Radiography Facility at Sandia National Laboratories written by Roger James Kapsimalis and published by . This book was released on 2010 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Neutron radiography has proven itself to be an invaluable research tool in the field of nuclear engineering. There are a great many applications that utilize neutron imaging, and further research continues to increase its applicability to a growing number of fields. Many new facilities have been built over the past several years, and an even greater number of existing facilities have been upgraded to more sophisticated neutron sensory equipment. The Sandia National Laboratories has been home to a neutron imaging facility for several decades. Over this time, it has been used with great success in a number of applications. However, with the great advances in neutron collimation and neutron detection in the recent years, it is not unlikely that the facility may soon be retrofitted with more up-to-date technologies. As such, the neutron and gamma ray parameters of the facility must be well-established. This work sought to characterize the neutron beam for the neutron radiography facility at Sandia National Laboratory in Albuquerque, New Mexico. Furthermore, a model of the neutron radiography tube assembly, experiment chamber, and collimator assembly was written and amalgamated to the existing MCNP core deck. The validity of the MCNP model will ultimately be confirmed by performing a number of experiments. These experiments will consist of flux foil calculations at the imaging surface and along various points within the experiment chamber and radiography tube assembly. Additionally, L/D collimation ratios will be found using the ASTM standard method.
Book Synopsis Transactions of the American Nuclear Society by : American Nuclear Society
Download or read book Transactions of the American Nuclear Society written by American Nuclear Society and published by . This book was released on 2002 with total page 1096 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Design and Development of an External Fast Neutron Beam Facility at the Ohio State University Research Reactor by : Andrew M. Zapp
Download or read book Design and Development of an External Fast Neutron Beam Facility at the Ohio State University Research Reactor written by Andrew M. Zapp and published by . This book was released on 2019 with total page 112 pages. Available in PDF, EPUB and Kindle. Book excerpt: The ability of the Ohio State University Research Reactor, OSURR, to conduct experiments from the generation of the neutron flux is important in conducting research by the University and external entities that require a flux of this magnitude. In particular, research involving a fast neutron flux is of interest due to the different interactions fast neutrons have as opposed to thermal neutrons. The OSURR is able to operate up to 500 kW, which creates a neutron flux in the order of 1013 n/cm2-s. Currently, Beam Port 2 provides a thermal neutron beam profile of 30 mm in diameter for experimentation such as neutron depth profiling, activation analysis, and evaluation of radiation damage to electronics. Beam Port 1 uses a sample area located adjacent and perpendicular to the fuel plates of the reactor for in-core irradiation. During experimentation, the remainder of Beam Port 1 must be plugged with removable concrete shielding to prevent radiation exposure that can be upwards of 1x104 rem/hr. The upgrade to Beam Port 1 consists of a collimator to shape the neutron flux from the reactor into a beam of fast neutrons, similar in diameter to Beam Port 2, in order to irradiate samples external to the reactor. In addition, mobile external shielding is designed to prevent exceeding the exposure limits of 5 rem/yr when the facility is in use. With this upgrade the research reactor has the ability to conduct simultaneous experiments with a fast and thermal neutron beam, external to the biological shielding, without releasing any harmful exposure.
