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Neutron imaging

Neutron imaging is a non-destructive radiographic that utilizes a of neutrons to visualize the internal structure and composition of materials by detecting variations in neutron transmission through the sample. Unlike imaging, which interacts primarily with electrons and is more effective for dense, high-atomic-number elements, neutron imaging relies on interactions between neutrons and atomic nuclei, enabling high sensitivity to light elements such as , , , and carbon, as well as superior penetration through like lead and . This complementary capability makes it invaluable for applications where traditional methods fall short, such as imaging hydrogenous materials or dense metallic components. The principles of neutron imaging are grounded in the Beer-Lambert law, which describes the exponential of the beam due to and as it passes through the object, with the transmitted intensity captured by detectors to form spatially resolved images. In practice, a or beam from sources like nuclear reactors or facilities is directed through the sample, where it is converted into visible light using scintillation screens (e.g., lithium-6 doped ) and recorded by digital cameras such as or sensors, achieving resolutions typically around 100–600 micrometers. The technique encompasses both two-dimensional for projection images and three-dimensional computed , reconstructed from multiple angular projections to map internal density and elemental distributions. Historically, neutron imaging emerged shortly after James Chadwick's in , with the first successful radiographies demonstrated by Hartmut Kallmann and Ernst Kuhn in the late using early nuclear sources. Over decades, advancements in neutron sources, detectors, and computational reconstruction have expanded its scope, from initial and industrial uses to modern research in , geomechanics, and preservation. Key applications include non-destructive evaluation of , tracking lithium-ion diffusion in batteries, analyzing in metals, and studying in fuel cells and geological samples, leveraging neutrons' unique sensitivity and penetration power. Ongoing developments aim for sub-micrometer and enhanced time-resolved to address emerging challenges in and engineering.

History

Early development

The discovery of the neutron by British physicist James Chadwick in 1932 revolutionized nuclear physics and paved the way for neutron imaging, as the particle's neutrality allowed it to penetrate materials opaque to X-rays, enabling unique contrast in radiographic applications. Just three years later, in 1935, German physicists Hartmut Kallmann and Ernst Kuhn achieved the first successful neutron radiographs in Berlin, imaging simple objects such as pressure gauges, fire hydrants, and test tubes using a low-flux radium-beryllium isotopic neutron source supplemented by a small deuterium-tritium accelerator; their work, which continued through the late 1930s, earned a U.S. patent in 1940. These pioneering experiments highlighted neutrons' potential for non-destructive testing but were constrained by extremely low neutron fluxes—on the order of 10^3 to 10^4 neutrons per second—necessitating exposure times of hours or days. In the 1940s, progress stalled amid , with early detection relying on indirect methods like nuclear emulsions sensitive to charged particles from neutron interactions and conversion screens (e.g., or compounds) to produce visible tracks on photographic films; these techniques suffered from poor , high background noise from gamma rays, and the scarcity of neutron sources beyond isotopic ones. Following the war, the advent of nuclear reactors spurred significant expansion in the , with facilities like initiating systematic neutron radiography programs to leverage higher fluxes for materials inspection, exemplified by early experiments at reactors such as the BEPO at Harwell and the at , —where the first dedicated imaging was established in 1956 to support quantitative imaging advancements.

Key advancements and facilities

The introduction of scintillation screens and image intensifiers in the 1960s and 1970s marked a pivotal shift toward neutron imaging capabilities. During this period, neutron imaging gained traction with the availability of nuclear reactors, enabling the use of gadolinium oxysulfide scintillators coupled to electrostatic image intensifiers for dynamic observations, such as motion studies in materials. By the mid-1970s, commercial systems based on these technologies became available, allowing for neutron television-like imaging with improved sensitivity over static film methods. The 1980s and 1990s witnessed a transition to digital detectors, fundamentally enabling high-speed, real-time neutron imaging and expanding applications beyond static . Advancements in (CCD) cameras, paired with neutron-sensitive screens, allowed for low-light detection and digital data acquisition, initiating rapid growth in neutron tomography and radioscopy. This era's progress in computer processing and memory storage facilitated the widespread adoption of these systems, with micro-channel plate detectors emerging for time-resolved techniques. The development of spallation neutron sources provided brighter, pulsed beams essential for high-flux imaging, overcoming limitations of reactor-based systems. The ISIS facility in the UK, operational since 1984, introduced pulsed neutron beams that supported time-resolved imaging experiments. Similarly, the at , commissioned in 2006, delivered megawatt-class proton power for enhanced neutron intensity, enabling ultrafast and with sub-millisecond . Key events in the included the optimization of CCD-based systems for neutron imaging, achieving spatial resolutions down to 50-100 micrometers and supporting via computed . In the 2010s, integration of revolutionized image processing, with algorithms applied for noise reduction, super-resolution enhancement, and automated feature extraction in neutron datasets. Pioneering works demonstrated models for reconstructing high-fidelity images from sparse projections, improving efficiency in data analysis for complex materials. Global facilities continue to drive neutron imaging advancements through specialized beamlines. At the Institut () in , the NEUTRA utilizes a spectrum with fluxes exceeding 5 × 10^6 s cm⁻² s⁻¹ mA⁻¹, supporting and of objects up to 30 cm × 30 cm , including dual / modalities and setups for highly radioactive samples via the NEURAP extension; upgrades under NEUTRA 2.0, approved post-2020, enhance resolution to below 50 μm. The Institut Laue-Langevin (ILL) in features the NeXT , optimized for high-speed with fields of view from 4.1 mm² to 170 mm², enabling radiographic projections in 10 ms and full tomographies with 155 projections, incorporating polarized capabilities for magnetic structure studies as of 2024. In the United States, the NIST Center for Neutron Research's Neutron Imaging Facility (NIF) offers a plug-and-play setup for in operando of devices like cells and batteries, with recent 2025 developments in curved Airy beams improving scan resolution and reducing artifacts for industrial applications.

Fundamentals

Neutron interactions with matter

Neutrons interact with matter primarily through nuclear forces, as they carry no , allowing deep penetration compared to s or . The main types of interactions relevant to neutron imaging are , where neutrons pass through without interacting; , involving capture by atomic nuclei leading to reactions such as (n,γ) radiative capture or (n,α) emission; and , which includes (conserving neutron kinetic energy while changing direction) and (transferring energy to excite the ). These interactions determine the and contrast in neutron images, with and reducing the beam intensity as it traverses the sample. The probability of these interactions is quantified by cross-sections, with the microscopic cross-section σ (in barns, 1 barn = 10^{-28} m²) representing the effective interaction area per nucleus, and the macroscopic cross-section Σ (in cm^{-1}) describing the material's overall attenuation, given by Σ = ∑ n_i σ_i, where n_i is the number density of the i-th isotope; the linear attenuation coefficient μ is equivalent to Σ in this context. Unlike X-rays, which depend strongly on atomic number Z due to photoelectric effects, neutron interactions are isotope-specific and show little correlation with Z, enabling high contrast for light elements and specific isotopes. For example, boron-10 has a thermal neutron absorption cross-section of approximately 3840 barns, making it highly attenuating, while cadmium-113 exhibits a capture cross-section of about 20,000 barns, often used in shielding. Hydrogen, despite a low absorption cross-section (~0.33 barns), provides strong contrast through its high incoherent scattering cross-section of 80 barns, which scatters neutrons isotropically and reduces transmitted intensity effectively. The transmitted neutron intensity I through a sample of thickness t follows the Beer-Lambert law:
I = I_0 e^{-\mu t}
where I_0 is the incident intensity and μ incorporates both and contributions. This exponential attenuation forms the basis for radiographic , with variations in μ across the sample creating spatial contrast. Neutron energy significantly influences these interactions: fast neutrons (energies >1 MeV) primarily undergo with relatively uniform cross-sections across elements, yielding lower contrast; thermal neutrons (energies ~0.025 ), obtained via , exhibit highly varied isotope-dependent cross-sections, enhancing sensitivity to elemental composition.

Contrast formation and imaging principles

In neutron imaging, contrast arises from the differential attenuation of neutrons as they pass through a sample, where variations in material composition and density lead to measurable differences in transmitted neutron intensity. This attenuation is particularly pronounced for light elements such as hydrogen, which exhibits a high neutron scattering cross-section due to its nuclear interactions, enabling clear visualization of hydrogen-rich organics, water, or voids within denser structures. In contrast, heavy metals like lead or uranium often appear more transparent to neutrons compared to lighter materials, allowing for effective imaging of metallic components embedded in organic matrices. The core imaging principle is radiographic , which produces a two-dimensional of the sample by projecting a collimated neutron beam through it onto a detector, capturing the of attenuated neutrons. This process follows the application of the Beer-Lambert law, where the transmitted intensity decreases exponentially with length and material-specific coefficients, providing a direct map of integrated neutron interactions along each . Unlike three-dimensional techniques, this projection method yields a planar image that integrates sample thickness, emphasizing macroscopic features like internal voids or material boundaries. Neutron imaging offers complementary to methods, excelling in the detection of hydrogenous materials such as plastics, fuels, or biological tissues, where X-rays provide poor due to similar densities. Additionally, neutrons penetrate more effectively than X-rays, which are strongly by high elements, making neutron imaging ideal for inspecting metallic assemblies with embedded light materials. These advantages stem from neutrons' interaction with nuclei rather than electrons, reversing typical attenuation hierarchies observed in imaging. However, practical limitations include the inherently low from available sources, often on the order of 10^6 to 10^7 neutrons per square centimeter per second, necessitating long exposure times that can extend to hours or days for high-resolution images. safety concerns also arise from the need for shielding against fast neutrons and gamma rays produced in facilities, requiring robust like enclosures. Quantitative imaging in neutron radiography enables mapping by leveraging multi-energy neutron beams to isolate contributions from specific isotopes or phases, allowing reconstruction of material distributions without destructive sampling. For instance, energy-selective imaging can differentiate content in composites by varying beam spectra, providing calibrated maps of variations with accuracies suitable for applications.

Experimental Setup

Neutron sources

Neutron sources for imaging are critical for generating beams with sufficient and appropriate spectra to penetrate materials and produce high-contrast images. These sources produce s primarily through , , or and alpha-induced reactions, with the choice depending on the required intensity, portability, and neutron energy range. Reactor-based sources rely on controlled in fuel to generate s, which are then moderated to thermal energies suitable for . Facilities like the (HFIR) at operate at 85 megawatts thermal power, providing the highest steady-state among U.S. reactor sources, with beams directed through beam tubes for and applications. These sources deliver continuous neutron output, enabling long exposure times for detailed imaging of dense or large samples. Accelerator-based sources, particularly spallation neutron sources, produce s by directing high-energy proton beams onto heavy metal targets, such as liquid mercury at the Spallation Neutron Source (SNS) at . In this process, protons strike the target at energies around 1 GeV, ejecting s through reactions, yielding up to 25 s per proton. The resulting pulsed beams offer high peak brightness, advantageous for time-resolved imaging techniques, though they require to shift s from fast to or spectra. Isotopic sources, such as californium-252 (Cf-252) and (Am-Be), have historically enabled portable neutron imaging systems where high-flux facilities are unavailable. Cf-252 undergoes to emit neutrons at an average energy of 2.1 MeV, with sources like those from QSA Global providing activities up to several micrograms for field radiography of explosives or materials. Am-Be sources, using alpha particles from to induce (α,n) reactions in , offer lower flux but greater accessibility for non-laboratory settings. Typical neutron fluxes for imaging range from 10^6 to 10^9 neutrons per square centimeter per second, with neutrons (0.01–0.5 ) being most common for standard due to their with light elements like . Cold neutrons (below 0.01 ) enhance in certain materials by increasing lengths, while epithermal neutrons (0.5 to 10 keV) are used for energy-specific to avoid resonance absorption. Beam , often using materials like or , tailors these spectra post-production. Modern developments in the 2020s focus on pulsed sources for higher brightness, exemplified by the () in , which is under construction as of 2025 with initial operations expected later in the year, and delivers proton pulses to a target for neutron production. achieves peak brightness up to 100 times greater than existing sources, supporting advanced imaging instruments like for dynamic studies.

Beam preparation and collimation

In neutron imaging, beam preparation begins with to slow down fast neutrons produced at the source to energies, typically around 0.025 eV, which is optimal for imaging applications due to enhanced interaction probabilities with . moderator materials include (D₂O) and , which efficiently reduce neutron kinetic energy through while minimizing absorption. For cold neutron imaging, or at temperatures of 25-30 K is employed to achieve even lower energies (a few meV), extending the for improved in certain materials. These processes occur in dedicated moderator assemblies adjacent to the , such as cores or targets, ensuring a usable flux for downstream imaging. Collimation shapes the moderated beam into a well-defined , either or divergent, to achieve the desired and while reducing scattered . This is accomplished using , often lined with to absorb stray neutrons and prevent beam halo effects, with the typically constructed from aluminum or other low-absorption materials. The key parameter governing is the L/D , where L is the distance from the source (or ) to the object and D is the ; higher (e.g., 90-100) produce more beams with reduced , enhancing image sharpness at the cost of . simulations, such as those using MCNP code, are routinely applied to optimize for specific facilities. Filters are integrated into the beamline to purify the neutron flux by removing unwanted gamma radiation and selecting specific energy bands. Cadmium or boron filters are used to attenuate thermal neutrons due to their high absorption cross-sections, often placed as thin foils or coatings within the collimator. For energy-selective imaging, mechanical velocity selectors—rotating disk or helical devices—monochromatize the beam by transmitting neutrons of a narrow velocity (energy) range, typically 0.5-40 eV for epithermal applications, enabling contrast based on material-specific scattering. Bismuth filters, such as 10 cm thick single crystals, are also used to further suppress gamma rays without significantly affecting the neutron flux. Beam divergence, inherent to non-ideal collimation, introduces geometric unsharpness that blurs the image, quantified by the U = f \left( \frac{t}{d} \right), where f is the source-to-object , t is the object thickness, and d is the object-to-detector . This effect is mitigated by maximizing the L/D ratio, as lower angles (smaller D/L) minimize penumbral blurring, particularly for thick objects where paths amplify the blur. Safety considerations in beam preparation emphasize shielding to protect personnel from neutron and gamma radiation. Polyethylene, often borated for enhanced neutron capture, is used to slow and absorb neutrons through hydrogenous scattering, typically in layers of 15-40 cm thickness. Concrete provides robust gamma shielding and structural support, with thicknesses of 1-2 m common around beam ports, while lead (9-15 cm) targets high-energy photons. These materials are layered in biological shields surrounding the collimator and beam path to ensure radiation levels remain below regulatory limits during operation.

Sample handling and positioning

In neutron imaging, samples must meet specific material and dimensional criteria to ensure compatibility with the neutron and facility constraints. Materials are typically selected to be non-magnetic to prevent interference in setups involving or polarized beams, and sample holders are constructed from radiation-resistant alloys or composites to withstand prolonged exposure without degradation. Size limitations vary by facility but generally accommodate objects from a few centimeters to up to 60 cm in diameter and 200 kg in weight, constrained by beam and , with larger scales (up to 1 m) possible in specialized industrial setups. Positioning systems enable precise manipulation of samples within the beam path, critical for achieving high . Motorized translation stages provide sub-millimeter accuracy in x, y, and z directions, while rotary stages facilitate 360° rotation with increments as fine as 0.1° for , allowing acquisition of hundreds of projections over a full . is achieved using fiducial markers, such as or boron-based inserts, which serve as reference points for co-registering multi-modal images or correcting for misalignment in complex geometries. Environmental controls allow in-situ imaging under controlled conditions to study dynamic processes. Setups include temperature-regulated cryostats or furnaces spanning -200°C to 1500°C, vessels up to several megapascals, and gas flow systems for reactive atmospheres, enabling real-time observation of phenomena like lithium plating in during charge-discharge cycles. For example, airtight aluminum chambers prevent while supporting electrochemical operation in battery cells. To minimize imaging artifacts, particularly from neutron scatter, the sample is positioned close to the detector (typically 5-50 mm) to reduce geometric blurring, though increasing this distance can blur scattered neutrons out of , lowering their contribution to the . Beam collimation, with ratios up to 550:1, further aids by limiting effects on positioning accuracy. Radioactive samples require specialized handling, including lead or boron-shielded containers, remote manipulators, and encapsulation to mitigate risks during transport and . Historically, early neutron imaging relied on manual sample placement using simple fixtures, as seen in initial film-based setups from the mid-20th century. Over time, this evolved to automated systems, with robotic handlers introduced in the for high-throughput operations, featuring six-axis manipulators for precise, remote exchange in cryogenic or radioactive environments. Modern facilities now employ retrofitted industrial robots to quadruple sample throughput and reduce manual intervention, enhancing efficiency for large-scale experiments.

Detection Systems

Film-based methods

Film-based methods represent the foundational approach to neutron imaging, relying on analog photographic techniques to capture neutron attenuation patterns through samples. These methods, pioneered in and 1940s, utilize photographic films or emulsions that record the spatial distribution of s transmitted through an object, forming a two-dimensional radiograph based on material-specific differences. Historically significant for enabling the first practical neutron radiographs, such methods transitioned from qualitative visual inspections to by the mid-20th century, particularly in and industrial applications. Direct exposure involves emulsions, such as silver halide-based photographic , that are inherently sensitive to neutrons through interactions producing charged particles in the grains. However, these emulsions exhibit low detection efficiency, typically on the order of 1-10% for neutrons, necessitating prolonged exposures to achieve adequate image density. Early demonstrations, including the patent by Kallmann and Kuhn, highlighted this approach's potential despite its inefficiencies, which limited its use to high-flux reactor environments. Indirect methods address the low efficiency of direct exposure by employing converter screens containing high neutron cross-section materials like gadolinium (Gd) or boron (B), which capture neutrons and emit secondary charged particles—alphas from boron-10 reactions or conversion electrons from gadolinium—to expose the adjacent film. In the direct transfer variant, the screen and film are exposed simultaneously, while the indirect transfer method involves post-irradiation contact to transfer the latent image, reducing geometric blurring. These screens, often 25-50 μm thick, enhance sensitivity by factors of 10-100 compared to bare film, making imaging feasible at moderate neutron fluxes. The imaging process requires positioning the film (or screen-film cassette) downstream of the sample in the beam, with exposures typically lasting minutes to hours depending on source intensity and desired — for instance, around 20 minutes for gadolinium-based systems at fluxes of 10^8-10^9 n/cm²/s. Following exposure, the film undergoes chemical development to reveal the as a negative pattern, where darker regions correspond to higher neutron transmission. Quantification is achieved through , scanning the developed film to measure optical and convert it to neutron fluence via curves, enabling quantitative assessment of coefficients. Film-based systems offer spatial resolutions up to 50 μm, limited primarily by emulsion grain size, screen thickness, and beam collimation, which supports detailed visualization of fine structures like welds or voids. A key advantage is their , often exceeding 100:1 in greyscale levels, allowing capture of both low- and high-attenuation features in a single exposure without saturation. By the , film-based methods declined in favor of detectors due to the labor-intensive process, long exposure times, and difficulties in imaging, though they remain viable in low-flux scenarios or resource-limited settings where high resolution and are paramount.

Track-etch and indirect conversion

The track-etch method employs solid-state nuclear track detectors, such as polymer foils, to capture neutron-induced damage trails for imaging purposes. Neutrons interact with a converter layer, typically a thin foil where thermal neutrons trigger fission, generating heavy charged fragments that penetrate the adjacent detector material and create latent damage tracks. These tracks are enlarged through chemical etching in a like , forming visible conical pits that reveal the neutron attenuation pattern through the sample when viewed microscopically or digitized via optical scanning. This technique is particularly advantageous in high gamma-ray environments, as the foils are insensitive to gamma radiation, and it has been used in facilities like the Plum Brook Reactor for neutron radiography of complex structures. Alternative converters, such as boron-10 or layers, enable detection via reactions that produce lighter charged particles like alpha particles, which similarly etch tracks in the detector. conditions, including time and temperature, control track density and contrast, achieving spatial resolutions of 20-30 μm in optimized setups with scanning, though overall remains low due to prolonged times and non-linear response, limiting quantitative applications. This bridges analog and early neutron imaging by allowing track for post-processing. Indirect conversion techniques transform neutrons into detectable secondary signals, primarily or amplified electrons, using converter-scintillator assemblies. Key reactions include neutron in lithium-6, n + ^6\text{Li} \to ^4\text{He} + ^3\text{H} (releasing 4.78 MeV), or in boron-10, n + ^{10}\text{B} \to ^7\text{Li} + \alpha (releasing 2.79 MeV), where the emitted charged particles excite materials like ZnS-doped LiF to produce visible photons. These photons are then relayed via optical components—such as mirrors, lenses, or fiber optic bundles—to a sensor for image formation, enabling real-time or near-real-time capture in controlled environments. Systems like those at the demonstrate this approach's versatility for . Detection efficiencies in these indirect setups typically range from 10-20% for thermal neutrons, constrained by converter thickness and light collection losses, while spatial resolutions are generally 100-200 μm due to scintillator grain size and optical coupling, though refined configurations achieve down to 50 μm. Microchannel plates, doped with neutron-sensitive materials like oxide, can amplify signals from thin converters, improving in low-flux scenarios and supporting the shift from to digital detection in early neutron imaging experiments.

Digital and direct detection methods

Digital detection methods in neutron imaging have revolutionized the field by enabling acquisition, higher dynamic ranges, and with computational , surpassing traditional analog techniques. These systems typically employ sensors that convert neutron interactions into measurable electrical signals, often via intermediate or direct charge collection. Key advantages include rapid readout capabilities and reduced times, facilitating dynamic studies of materials under load or in operational conditions. Flat-panel detectors, commonly based on arrays coupled with layers such as LiF/ZnS(Ag), provide imaging with frame rates of 10-30 at full resolution. These detectors offer spatial resolutions ranging from 127 to 750 μm, depending on pixel pitch and , and are widely used for their large field-of-view (up to 30 cm × 40 cm) and direct digital output. For instance, the Varian PaxScan 2520, employed at facilities like NIST, achieves 127 μm pixel pitch with binned modes for faster acquisition. Imaging plates utilize photostimulable storage phosphors, such as BaFBr:Eu²⁺ doped with neutron converters like oxide, to store latent images that are later scanned with readout for high-sensitivity detection. These plates exhibit exceptional dynamic ranges up to 10⁵ and spatial resolutions of 25-100 μm, making them ideal for high-contrast, quantitative despite requiring offline processing. Their sensitivity surpasses radiographic films by factors of 10² to 10³, enabling exposures as low as 20 seconds for thermal s. Direct detection methods employ neutron-sensitive semiconductors, such as boron-10 coated sensors, which capture charged particles from neutron reactions (e.g., ¹⁰B(n,α)⁷Li) without intermediaries, minimizing light-scattering losses. These systems achieve spatial s below 50 μm, with examples like monolithic CMOS-MEMS pixels at 35 × 40 μm² granularity and event-centroiding techniques yielding ~15 μm . Such detectors are compact and radiation-hard, suitable for high-resolution mapping in low-flux environments. Neutron cameras based on multi-anode arrays, such as segmented () Anger cameras, handle high neutron fluxes by distributing signals across numerous anodes (e.g., 1024 in a 116 mm × 116 mm area) for position reconstruction. These enable real-time with resolutions around 1 mm or better, particularly in dynamic scenarios like diagnostics or industrial flows. Advancements in the 2020s have integrated for denoising neutron images, enhancing signal-to-noise ratios in low-dose acquisitions through models like convolutional neural networks. These techniques, applied to both and , reduce noise variability and enable previously limited by statistics. Additionally, detector quantum efficiencies have reached up to 50% for thermal neutrons, as seen in microchannel plate (MCP) systems with optimized converters, improving overall throughput without sacrificing resolution. As of 2025, further progress includes event-based detectors, such as optical Timepix systems and neuromorphic sensors, enabling high-resolution event-mode with superior (down to nanoseconds) and counting rates for dynamic studies. Facilities like have advanced time-resolved detectors, improving , to sub-100 μm in some configurations, and acquisition modes for energy-resolved .

Advanced Techniques

Neutron radiography

Neutron radiography is a two-dimensional projection imaging technique that utilizes a collimated beam of neutrons to penetrate and form an image of an object's internal structure based on neutron attenuation differences. The procedure involves positioning the sample in the neutron beam path and exposing it for a single projection, typically lasting from 10 seconds to several minutes depending on the neutron flux, sample thickness, and desired image quality. For instance, at thermal neutron fluxes around 10^6 n cm^{-2} s^{-1}, exposure times of 10 to 60 seconds are common for standard specimens. This method relies on the fundamental principle of neutron attenuation, where materials with high neutron absorption cross-sections, such as boron or cadmium, appear dark on the radiograph, while low-absorbing materials like metals transmit more neutrons and appear lighter. Spatial resolution in neutron radiography typically ranges from 50 to 200 μm, influenced by factors such as beam collimation, detector characteristics, and geometric unsharpness. Facilities qualify their systems using standards like ASTM E545, which assesses image quality through metrics including , , and via test phantoms with known features like holes and wires. Qualitative applications focus on defect detection, such as identifying cracks, voids, or inclusions in materials where visual highlights discontinuities without precise measurement. In , quantitative radiography enables measurements and thickness by analyzing profiles, often calibrated against known standards to derive material properties like content or . The experimental setup integrates beam collimation with precise sample and detector positioning to achieve controlled . The factor is determined by the of the source-to-detector distance to the source-to-object distance, allowing enhancement of feature visibility—typically up to 2-5 times—while minimizing , though it increases exposure requirements due to . Historically, neutron radiography evolved from static film-based methods in the mid-20th century to dynamic imaging in the late , enabled by electronic detectors that capture sequential projections for observing transient processes like fluid flow. This shift expanded applications from archival inspections to in-situ monitoring.

Neutron tomography

Neutron tomography extends imaging to three-dimensional volumetric by acquiring multiple two-dimensional projections of a sample as it rotates, enabling the visualization of internal structures with high contrast for hydrogenous materials. This technique relies on the principles of computed (), where the sample is typically rotated over 360° to capture a series of radiographic projections that serve as input for algorithmic . These projections build upon basic by providing angular diversity, allowing the inversion of projection data to recover the map. Data acquisition in neutron tomography involves continuous or step-wise rotation of the sample, often collecting 500 to 2000 projections evenly spaced over 360° to ensure sufficient sampling for accurate . Exposure times per projection range from seconds to minutes, depending on and sample thickness, resulting in total acquisition durations of several hours to days for high-quality datasets. For instance, systems at facilities like the Institut have demonstrated scans with 625 projections taking approximately 14 hours. Pulsed neutron sources facilitate faster acquisitions by leveraging time-of-flight methods, reducing times to under 3 hours for 360 projections in some setups. Reconstruction algorithms invert the projection data to produce the 3D image, with filtered back-projection (FBP) being a widely used analytical method due to its efficiency and implementation in neutron contexts. FBP addresses the , which models projections as line integrals through the object: p(t, \theta) = \int_{-\infty}^{\infty} f(x, y) \delta(t - x \cos\theta - y \sin\theta) \, dx \, dy where p(t, \theta) is the projection at distance t and angle \theta, and f(x, y) is the 2D attenuation function. The inverse, via the Fourier slice theorem, yields the reconstructed : f(x, y) = \int_0^\pi \int_{-\infty}^{\infty} S(\omega, \theta) e^{j 2\pi \omega (x \cos\theta + y \sin\theta)} \, d\omega \, d\theta with S(\omega, \theta) as the 1D Fourier transform of the filtered projections. This approach has been applied successfully in neutron tomography systems using software like MATLAB for discrete Fourier transforms. Common artifacts in neutron tomography include beam hardening, arising from the polychromatic neutron spectrum causing non-linear attenuation, and scatter, which introduces blurring from neutrons deflected within the sample. Beam hardening is corrected analytically by linearizing effective cross-sections or through pre-filtering, while scatter effects are mitigated by subtracting estimated scattered components from projections. Ring artifacts, often due to detector inconsistencies or uncorrected scatter, are addressed using ring filters that identify and smooth circular patterns in sinograms before reconstruction. These corrections are essential for quantitative analysis, as demonstrated in test object studies at beamlines like NEUTRA and ICON. Achieved voxel resolutions in neutron tomography typically range from 10 to 100 μm, enabling detailed mapping of microstructures such as voids in dense materials where X-rays fail due to high . For example, microtomography of samples has resolved voids as small as 10 μm using voxel sizes of 5.4 μm, quantifying non-destructively. This resolution supports applications in void analysis for , revealing distribution and connectivity that inform defect formation. At facilities like Oak Ridge National Laboratory's CG-1D , routine resolutions of 25-100 μm balance field-of-view and acquisition time. Recent advancements leverage pulsed neutron sources for fast tomography, enabling 4D imaging that captures dynamic processes by adding a temporal dimension. High-speed setups acquire 300-400 projections in 40 seconds to 1 minute per tomogram, allowing real-time tracking of fluid flow or phase changes. For instance, 4D neutron CT at reactor-based high-flux beamlines has quantified water dynamics in fuel cells with <300 μm resolution, while pulsed facilities like those at ISIS support energy-resolved dynamics over minutes. These developments expand applications to in operando studies of transient phenomena.

Phase and energy-selective imaging

Phase-contrast neutron imaging enhances visibility in materials with low absorption by exploiting the wave nature of neutrons, where phase shifts induced by the sample's create patterns that can be converted into . Propagation-based phase-contrast imaging relies on free-space of the neutron beam after interaction with the sample, leading to effects that amplify edges and interfaces, particularly useful for hydrogen-rich or light-element materials like polymers or biological tissues. This method has been revisited in recent studies to incorporate algorithms, improving signal-to-noise ratios by up to a factor of 23 through techniques. interferometry, another key approach, uses absorption gratings to create a periodic pattern, enabling that quantifies local phase gradients with sub-micrometer . Energy-selective neutron imaging tunes the beam to exploit material-specific interactions, such as Bragg diffraction from crystal lattices, allowing contrast based on crystallographic texture or rather than mere . Crystal monochromators, often double-crystal setups, select narrow bands (e.g., 0.2–0.6 nm with resolutions of Δλ/λ ≈ 1–2%), enabling imaging around Bragg edges where sharply changes due to lattice plane reflections. This reveals microstructural details like grain orientations or residual stresses in polycrystalline metals, with applications in additive manufacturing . At facilities like the Institut (PSI), energy-selective methods integrate with to map phase distributions in three dimensions, distinguishing phases in multi-material composites. Talbot-Lau interferometry extends phase-contrast capabilities by incorporating a source grating for partially coherent beams, facilitating dark-field imaging that detects ultra-small-angle scattering from sub-micron microstructures like pores or cracks. This setup generates visibility maps sensitive to scattering lengths below 1 μm, without requiring perfect beam coherence, and has been implemented at reactors like for quantitative microstructure analysis. Dark-field in Talbot-Lau systems provides advantages over absorption imaging by visualizing defects invisible to traditional methods, such as microcracks in composites, enabling non-destructive evaluation without agents and achieving resolutions down to 10–50 μm for scattering features. These techniques collectively offer enhanced sensitivity to low-Z elements and internal interfaces, with reported improvements in defect detection by factors of 5–10 in signal clarity for materials like additively manufactured alloys. In the 2020s, hybrid approaches combining phase-contrast with methods have emerged at 's NEUTRA beamline, enabling bimodal imaging that leverages complementary contrasts— for light elements and for high-density features—in a single setup. This integration, operational since 2015 and refined through 2021, supports simultaneous phase-sensitive acquisitions for studies and porous media, reducing experimental time while enhancing interpretive accuracy. Such developments at highlight the potential for multi-modal phase imaging in real-time monitoring of dynamic processes, like battery degradation, where energy-selective data complements propagation-based contrast.

Applications

Industrial non-destructive testing

Neutron imaging serves as a powerful tool in industrial non-destructive testing (NDT), enabling the inspection of complex components without disassembly or damage, particularly where traditional methods fall short due to material contrasts. It excels in detecting defects in dense metallic structures by leveraging neutrons' high penetration through heavy elements and with light elements like , which enhances visibility of voids, inclusions, and moisture-related issues. In and , neutron radiography is widely applied for weld inspections, where it reveals subsurface flaws such as cracks, lack of fusion, and that may not be apparent in images due to similar coefficients of weld materials. For monitoring in pipelines, combined neutron and gamma radiography techniques allow for the depiction of corrosion-born defects, including wall thinning and deposit accumulation, by exploiting differential neutron scattering from in corrosion products. These methods provide quantitative data on defect depth and extent, aiding in for oil and gas infrastructure. Additionally, neutron imaging supports screening for explosives detection, where fast neutron radiography identifies materials like narcotics and explosives through their unique neutron signatures, offering higher specificity than gamma-based systems. Specific examples highlight neutron imaging's value in high-stakes industries. In , it is used to inspect turbine blades for internal flaws, such as cooling channel blockages or inhomogeneities in TiAl alloys, which are critical for operational safety and cannot be reliably visualized by routine techniques. In the automotive sector, neutron imaging evaluates electrolyte cells by exploiting the high contrast from in and , allowing visualization of liquid water distribution during operation to optimize performance and durability. Portable neutron radiography systems, utilizing isotopic sources like californium-252 or compact D-T neutron generators, enable field deployments for on-site inspections, such as assessments in remote locations, where reactor-based facilities are impractical. These systems achieve sufficient resolution for defect detection while maintaining mobility, with collimators and detectors facilitating real-time . In the 2020s, neutron imaging has seen increased adoption for analyzing in additively manufactured components, as demonstrated in case studies of laser powder-bed fusion parts, where it reveals hidden sites and variations that contribute to failure, complementing methods for comprehensive . This application supports the growing demand for reliable NDT in advanced manufacturing, with resolutions typically achieving sub-millimeter defect detection as detailed in detection system capabilities.

Materials science and engineering

Neutron imaging plays a crucial role in and by enabling non-destructive, in-situ visualization of internal structures and dynamic processes within materials, particularly those involving light elements like or that are challenging to observe with methods. This technique leverages the high penetration of neutrons through dense materials and their with isotopes such as hydrogen-1, allowing researchers to study microstructural evolution, phase changes, and at scales from micrometers to centimeters. In-situ studies using neutron imaging have provided insights into real-time material behaviors, such as water distribution in operating polymer electrolyte membrane fuel cells (PEMFCs), where reveals liquid accumulation in gas layers and channels, informing designs to mitigate flooding and improve . Similarly, in lithium-ion batteries, tracks electrode evolution, including lithium plating and degradation in graphite anodes during fast charging, highlighting transport limitations and informing development. For additive manufacturing, time-resolved captures melt pool dynamics and porosity formation in processes like powder bed fusion, enabling optimization of build parameters for metallic components. Hydrogen mapping via neutron imaging is essential for analyzing and embrittlement in metals, as neutrons' to allows quantitative tracking of concentration gradients in materials like steels and under load. In studies, in-situ imaging visualizes delayed crack propagation in high-strength steels exposed to gaseous , correlating ingress with and trap site occupancy. This approach has quantified coefficients in at temperatures from 300 K to 500 K, revealing temperature-dependent pathways that influence material durability in energy applications. Representative examples include the 3D evolution of voids in fiber-reinforced composites, where reveals coalescence and growth during loading, linking defect distributions to mechanical failure modes. In alloys, Bragg-edge monitors transitions, such as austenite-to-martensite shifts in steels during cycling, providing spatially resolved lattice strain data. These observations, often combined with for volumetric reconstruction, elucidate how microstructural changes drive property variations. Quantitatively, neutron attenuation-based imaging determines porosity fraction p through the relation p = 1 - \frac{\mu}{\mu_0}, where \mu is the measured linear attenuation coefficient of the sample and \mu_0 is that of the fully dense material, enabling non-destructive assessment of void content in ceramics and metals. This method establishes critical thresholds, such as porosity levels exceeding 5% correlating with reduced tensile strength in additively manufactured parts. Facilities like the NIST Neutron Imaging Facility (NIF) and the Paul Scherrer Institut (PSI) ICON beamline support time-resolved experiments, achieving frame rates up to 30 frames per second for dynamics studies using flat panel detectors.

Cultural heritage and archaeology

Neutron imaging has emerged as a vital non-invasive in and , enabling the revelation of hidden structures within artifacts without causing damage. In paintings, it uncovers underlying layers and alterations, such as preparatory sketches or overpaints, by exploiting the differential of neutrons by organic pigments and binders. Similarly, for and sarcophagi, neutron penetrates wrappings and casings to visualize internal compositions, including materials and skeletal remains, providing insights into ancient practices. This technique is particularly effective for organic-rich samples due to neutrons' high sensitivity to , which highlights light elements often invisible in imaging. The sensitivity of neutron imaging proves invaluable for detecting inks, adhesives, and residues in ancient texts and manuscripts, where it reveals faint traces of carbon-based writings or binding materials on or that might otherwise remain undetected. In archaeological wood from shipwrecks, it assesses degradation patterns, such as microbial attack or salt ingress, by mapping moisture content and structural voids in waterlogged timbers, aiding strategies to prevent further deterioration upon exposure to air. For instance, in the , researchers at the Institut Laue-Langevin (ILL) employed neutron to examine sarcophagi, identifying internal voids and fillings within sealed containers. Likewise, neutron imaging has been applied to statues, revealing layers and internal cavities that inform efforts, as demonstrated in studies of bronzes where it delineated flaws and development. A key advantage of neutron imaging lies in its ability to penetrate dense encrustations, such as corrosion products or mineral deposits on artifacts, without requiring surface preparation or disassembly, thus preserving the object's integrity during analysis. This non-destructive penetration is especially beneficial for fragile or encrusted items from marine or burial contexts. International collaborations, including IAEA-coordinated research coordinated projects, have advanced these applications through harmonized neutron imaging protocols for cultural heritage, with ongoing programs as of 2025 supporting global preservation efforts by training experts and facilitating access to facilities.

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