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Neutron Radiography

Neutron Radiography
Author: John P. Barton
Publisher: Springer Science & Business Media
Total Pages: 902
Release: 2013-06-29
Genre: Science
ISBN: 9400938713

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Proceedings of the Second World Conference, Paris, France, June 16-20, 1986


Design, Development, Characterization, and Application of a New Neutron Imaging Facility at the Penn State Breazeale Reactor

Design, Development, Characterization, and Application of a New Neutron Imaging Facility at the Penn State Breazeale Reactor
Author: Alibek Kenges
Publisher:
Total Pages: 0
Release: 2023
Genre: Imaging systems
ISBN:

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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.


Neutron Radiography

Neutron Radiography
Author: Harold Berger
Publisher:
Total Pages: 102
Release: 1998
Genre: Neutron radiography
ISBN:

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Neutron Radiography

Neutron Radiography
Author: Garbe,U.
Publisher: Materials Research Forum LLC
Total Pages: 316
Release: 2020-02-05
Genre: Technology & Engineering
ISBN: 1644900572

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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.


The Design of a Fast Neutron Radiography System for Non-destructive Analysis of Thick, Dense Objects

The Design of a Fast Neutron Radiography System for Non-destructive Analysis of Thick, Dense Objects
Author: Alicia Lauren Swift
Publisher:
Total Pages: 568
Release: 2016
Genre: Neutron optics
ISBN:

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This dissertation describes the development of a novel time-of-flight (TOF) fast neutron radiography system, TiGReSSE ("Time Gating to Reject Scatter and Select Energy"), for non-destructive analysis of thick, dense objects, such as a spent nuclear fuel cask. Such objects create large scatter fields that mask interior flaws in an image, and are impenetrable with traditional x-ray or low-energy neutron radiography. By using a fast pulsed, high-energy monoenergetic neutron source with TiGReSSE, TOF methods may be employed to completely reject this problematic scatter. If using TOF methods with a fast pulsed, high-energy polyenergetic neutron source instead, partial scatter rejection is possible, as is the variation of image contrast by selecting the neutron interrogation energy(ies). To accomplish scatter rejection and energy selection, the system uses a fast plastic scintillator to convert neutrons to visible light, which then enter an intensified charge coupled device camera to form a radiograph. The camera shutter is opened and closed at specific times to apply TOF methods. Experiments were conducted using a deuterium-tritium generator, as well as with polyenergetic spallation neutrons in two Los Alamos Neutron Science Center accelerator flight paths. These experiments were carried out to improve system design and determine system characteristics, while demonstrating that TiGReSSE could partially reject scatter and select energy in novel neutron energy ranges up to 600 MeV (i.e., 80% of the speed of light). It was also shown that optimal neutron radiography energies vary between objects. Simulations were also conducted using Los Alamos National Laboratory's radiation transport code, MCNP6, to further support system design and characterization, modeling properties including detector efficiency, dose to radiography objects during imaging, and direct-to-scatter ratios. MCNP6 was also used to design an optimal shielding configuration for the camera. Based on all work conducted, it is recommended that a pulsed monoenergetic neutron source with energy from 10 to 14 MeV be used for scatter rejection, and that a spallation target be used to create a polyenergetic pulsed source to also enable energy selection, while being mindful that other objects may exist that require higher energy neutrons.


Characterization of a Neutron Imaging Platform Utilizing a Compact Electronic Neutron Generator for Evaluation of Analog and Digital Neutron Imaging Methods and Techniques

Characterization of a Neutron Imaging Platform Utilizing a Compact Electronic Neutron Generator for Evaluation of Analog and Digital Neutron Imaging Methods and Techniques
Author: Michael James Taylor
Publisher:
Total Pages: 266
Release: 2019
Genre:
ISBN:

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Unlike X-Rays that interact strongly with the electron cloud surrounding atoms, neutrons interact very weakly with these electrons, but quite strongly with the nucleus of the atom. X-Rays follow a nearly linear trend of decreasing transmission as the atomic number of the element increases. Neutrons follow no such behavior and certain isotopes of elements such as lithium, boron, cadmium, and gadolinium interact very strongly with neutrons, unlike dense elements such as lead or tungsten. This gives neutrons a unique probing capability where X-Rays do not suffice. Neutron imaging is widely used in the commercial sector for munitions and critical aerospace component inspection as well as in the research realm for biological forensics, cultural heritage providence studies, and capturing repetitive processes such as cyclical fluid motion in rotating motors. Current neutron sources are typically nuclear reactors and spallation sources that provide incredibly high neutron yields and flux for the images, leading to reduced image times and/or high spatial resolution as well as new imaging techniques such as computed tomography, polarized neutron imaging, and phase contrast imaging. However, such sources are very expensive, require thorough regulatory oversight, and pose biological hazards from spent nuclear materials. Smaller sources such as sealed tube deuterium-deuterium or deuterium-tritium sources can allow for in-field inspection at a fraction of the cost of a reactor, but don't necessarily provide fast image acquisitions or adequate image quality. This thesis explores a system that is intended to fill the space between weak portable devices and strong, costly, immobile ones. An accelerator-based neutron generator has been designed and manufactured by Phoenix LLC in Madison, WI. This system operates on the principle of deuterium-deuterium fusion, which releases a free 2.45MeV (nominal) neutron in the fusion process. The system can be installed and commissioned in different locations throughout its lifetime and provides for in-field or commercial inspection of components. It has a neutron yield several orders of magnitude higher than sealed-tube neutron sources. The goal herein was to: enhance the performance of the neutron generator through careful beamline design from the source to the target to obtain the maximum neutron yield, optimize the geometry of the neutron moderator and collimator to maximize the imaging metrics of a thermalized and collimated neutron beam free of background gamma and fast neutron radiation contamination, and find efficient neutron detector solutions that can capture high-quality neutron images. Monte Carlo simulations were extensively employed for these optimization efforts. The system has been shown to produce high quality neutron radiographs in terms of contrast, noise, and resolution, using many different techniques for imaging. Many materials were explored for moderation and shielding, and many neutron detectors were researched and experimented with to demonstrate advantages and disadvantages for their use on the Phoenix neutron imaging system. Sample images will be shown and discussed including conventional radiography using medical, industrial, and photographic film, 2-dimension digital imaging using pixelated cameras such as Charge Coupled Devices (CCD), Complementary Metal Oxide Semiconductors (CMOS), amorphous Silicon (aSi), and Computed Radiography (CR). Neutron Computed Tomography (nCT) is demonstrated as a 3-dimensional imaging technique as well. Case studies will be discussed and options for further optimization for collimator, moderator, and detector designs will be outlined. Recommendations for future research will be discussed in the final chapter.