Hasil untuk "Nuclear engineering. Atomic power"

G. Currie

Academic integrity in both higher education and scientific writing has been challenged by developments in artificial intelligence. The limitations associated with algorithms have been largely overcome by the recently released ChatGPT; a chatbot powered by GPT-3.5 capable of producing accurate and human-like responses to questions in real-time. Despite the potential benefits, ChatGPT confronts significant limitations to its usefulness in nuclear medicine and radiology. Most notably, ChatGPT is prone to errors and fabrication of information which poses a risk to professionalism, ethics and integrity. These limitations simultaneously undermine the value of ChatGPT to the user by not producing outcomes at the expected standard. Nonetheless, there are a number of exciting applications of ChatGPT in nuclear medicine across education, clinical and research sectors. Assimilation of ChatGPT into practice requires redefining of norms, and re-engineering of information expectations.

Ju Wang, Liang Chen, R. Su et al.

Abstract With the rapid development of nuclear power in China, the disposal of high-level radioactive waste (HLW) has become an important issue for nuclear safety and environmental protection. Deep geological disposal is internationally accepted as a feasible and safe way to dispose of HLW, and underground research laboratories (URLs) play an important and multi-faceted role in the development of HLW repositories. This paper introduces the overall planning and the latest progress for China's URL. On the basis of the proposed strategy to build an area-specific URL in combination with a comprehensive evaluation of the site selection results obtained during the last 33 years, the Xinchang site in the Beishan area, located in Gansu Province of northwestern China, has been selected as the final site for China's first URL built in granite. In the process of characterizing the Xinchang URL site, a series of investigations, including borehole drilling, geological mapping, geophysical surveying, hydraulic testing and in situ stress measurements, has been conducted. The investigation results indicate that the geological, hydrogeological, engineering geological and geochemical conditions of the Xinchang site are very suitable for URL construction. Meanwhile, to validate and develop construction technologies for the Beishan URL, the Beishan exploration tunnel (BET), which is a 50-m-deep facility in the Jiujing sub-area, has been constructed and several in situ tests, such as drill-and-blast tests, characterization of the excavation damaged zone (EDZ), and long-term deformation monitoring of surrounding rocks, have been performed in the BET. The methodologies and technologies established in the BET will serve for URL construction. According to the achievements of the characterization of the URL site, a preliminary design of the URL with a maximum depth of 560 m is proposed and necessary in situ tests in the URL are planned.

Yohan Lee, Byoungil Jeon, Soobin Lim

According to the rapid growth of the Lithium-ion battery (LIB) recycling industry, the demands for rapid and non-destructive analysis of black powder, the key product in this recycling process, has increased to enable effective recovery of valuable materials and the formulation of optimal recycling strategies. This study aims to evaluate the feasibility of a deep learning application that estimates the composition of valuable materials in black powder in prompt gamma-ray activation analysis (PGAA). Reference data for major target materials, Nickel, Cobalt, Manganese, and Iron, were acquired using the Four-circle single-crystal diffractometer at the HANARO research reactor, and synthetic datasets with varying counting statistics were generated for model training. To identify the most suitable model for PGAA-based composition estimation, we conducted a comparative analysis of six machine learning algorithms, including machine learning (Lasso, Decision Tree, XGBoost) and deep learning architectures (MLP, CNN, Transformer). Among them, the Transformer architecture demonstrated best performance, achieving an r2 score of over 0.99 for all components. Furthermore, uncertainty quantification using deep ensembles confirmed that the model provides reliable confidence intervals, essential for industrial decision-making. These results demonstrate the promising potential of the deep learning method for effective and high-throughput battery recycling applications.

XU Dawei, DAI Shoutong, TONG Mengyu, LYU Zheng

Space nuclear reactors have gained increasing importance in deep space exploration missions, with launch abort scenarios leading to ground surface impact representing a core consideration in reactor safety design. However, space nuclear reactors cannot incorporate the same degree of redundancy and diversity as terrestrial nuclear facilities. Throughout their mission lifecycle, space nuclear reactors may experience atmospheric re-entry and subsequent ground surface impact at any stage. During hypervelocity impact events, the extreme kinetic energy induces severe structural deformation in the reactor pressure vessel. This deformation process may compromise safety-critical components such as control drums, fuel pins and restraint mechanisms, potentially affecting the reactor’s neutronics characteristics. Consequently, conducting structural integrity assessments under various impact conditions provides essential data for criticality safety evaluations and serves as the basis for design optimization. This study employed the TOPAZ-Ⅱ space nuclear reactor as the research subject. Finite element simulations of terrestrial and aquatic impact behavior under various accident scenarios were conducted using ANSYS/DYNA and ABAQUS software. Based on finite element principles, Eulerian and Lagrangian methods were utilized to simulate reactor impacts. The structural response, component damage, and the influence of different failure criteria and motion parameters were investigated. The most severe damage to the space nuclear reactor occurs during ground surface impact at 0°. At this orientation, fastener failure initiates at low velocities, causing reflector assembly and control drum detachment. Additionally, safety control rods exhibit ejection propensity within the 16-68 m/s impact velocity range, whereas no ejection is observed at impact angles exceeding 21°. In contrast, water body impacts cause relatively minor damage to the space nuclear reactor, with no ejection risk has been observed. The reactor structure remains largely intact at impact velocities below 100 m/s, whereas fuel element dispersion occurs at velocities exceeding 200 m/s. At impact angles of 45° and 90° with velocities of 100 m/s and 150 m/s, the reactor faces a critical risk scenario. Under these conditions, the reflector layer and control drums detach, safety rods undergo partial destruction, and the reactor core becomes submerged in water body. Complete structural failure of the reactor vessel and fuel element dispersion occur at impact velocities above 200 m/s. The impact of a space nuclear reactor on both ground surface and water body presents critical safety risks. In the case of ground surface impact, the primary hazard arises from the potential ejection of safety rods and the detachment of the reflector layer and control drums. These results deliver fundamental inputs for criticality safety assessments and establish reference frameworks for test parameter definition and experimental configuration design in space nuclear reactor terrestrial impact experiments.

LU Yushun, ZHANG Rui, WEI Jie, ZHANG Jiahao, LIU Jianquan

Plate fuel assemblies are widely used in various small modular reactors and marine reactors due to its compact structural design and high heat transfer efficiency. The deposition of corrosion products on the surfaces of the fuel plates significantly increases the thermal resistance between the coolant and the fuel, thereby increasing the cladding temperature and compromising reactor safety margins. Currently, quantitative investigations of this process in plate fuel assemblies remain limited. This study aimed to establish a corrosion deposition model to investigate the effect of corrosion product deposition on the heat transfer performance of plate fuel assemblies. A predictive mathematical model was developed to estimate the deposition rates of both soluble and insoluble corrosion products on the fuel surfaces, along with the erosion rate induced by the coolant, which were the three main mechanisms governing the deposition process. A thermal resistance model was also established to simulate the evolution of heat transfer resistance caused by deposition over time. The above theoretical models were implemented into the basic equations of computation fluid dynamics (CFD) software Fluent to achieve pseudo-transient coupled computations of deposition, erosion, flow, and heat transfer processes. The proposed model was then validated against experimental data to demonstrate its excellent performance in predicting the deposition amount and the resulting thermal resistance. Subsequently, the deposition behavior and its impact on heat transfer in plate fuel assemblies were investigated, and the influence factors were explored, including different inlet flow velocities and power densities. The results show that the deposition thickness increases gradually over time until a dynamic equilibrium is established between corrosion product deposition and coolant erosion. The deposition rate of soluble ions increases with rising deposition layer temperature and decreasing wall shear stress, while the erosion rate by coolant increases proportionally with both flow velocity and power density. Higher power density will increase the cladding temperature of fuel assemblies, which enhances the deposition of soluble ions and thereby increases the net deposition amount. The inlet flow velocity significantly affects the deposition amount after reaching equilibrium, and the time period to reach the dynamic equilibrium condition. Increased coolant flow velocity accelerates the stabilization of deposition thickness and reduces the equilibrium deposition thickness. The thickness of deposition layer exhibits non-uniform distribution, with localized thickening in high-temperature regions, particularly along the midline of the fuel plate. A significant temperature rise on the fuel surface is observed due to corrosion deposition. At low flow velocity in this paper, the average thickness of corrosion product reaches 20.14 μm, causing a maximum temperature rise of 17.7 K on the cladding surface relative to the non-fouled condition. The simulation methodology and obtained results can provide a valuable reference for the design, safety analysis, and long-term operation of plate fuel assemblies in advanced nuclear reactors.

J. Mailloux, N. Abid, K. Abraham et al.

The JET 2019–2020 scientific and technological programme exploited the results of years of concerted scientific and engineering work, including the ITER-like wall (ILW: Be wall and W divertor) installed in 2010, improved diagnostic capabilities now fully available, a major neutral beam injection upgrade providing record power in 2019–2020, and tested the technical and procedural preparation for safe operation with tritium. Research along three complementary axes yielded a wealth of new results. Firstly, the JET plasma programme delivered scenarios suitable for high fusion power and alpha particle (α) physics in the coming D–T campaign (DTE2), with record sustained neutron rates, as well as plasmas for clarifying the impact of isotope mass on plasma core, edge and plasma-wall interactions, and for ITER pre-fusion power operation. The efficacy of the newly installed shattered pellet injector for mitigating disruption forces and runaway electrons was demonstrated. Secondly, research on the consequences of long-term exposure to JET-ILW plasma was completed, with emphasis on wall damage and fuel retention, and with analyses of wall materials and dust particles that will help validate assumptions and codes for design and operation of ITER and DEMO. Thirdly, the nuclear technology programme aiming to deliver maximum technological return from operations in D, T and D–T benefited from the highest D–D neutron yield in years, securing results for validating radiation transport and activation codes, and nuclear data for ITER.

Lingyan Zhao, Bin Yang, Yuchun Sun

Abstract The accurate evaluation of structural integrity necessitates considering the influence of crack-tip constraints and selecting laboratory test specimens that accurately represent the actual welded structure. In this paper, a constraint parameter Dp covering in-plane constraint and out-of-plane constraint is defined based on the equivalent plastic strain gradient at the adjacent zone of the crack front. The USDFLD (user-defined field) subroutine is employed to correlate the mechanical property parameters of the continuous transition with the geometry of the dissimilar metal-welded joint (DMWJ). The submodel technique is used to study the crack-tip constraint of a typical DMWJ under complex loading conditions. The crack-tip constraints of DMWJs are quantitatively characterized. A comparison and analysis are carried out to determine the suitable test specimens for the DMWJs with various crack lengths and locations. The results show that the cracks located at the center of the specimens are more likely to propagate than surface cracks. The interface of SA508/52Mb is the most dangerous position in DMWJs. The constraint levels of SA508/52Mb cracks match those of the center-cracked tension [CC(T)] specimens with smaller width and thickness. Overly conservative estimation results will be produced if compact tension [C(T)] and single-edge notched bend [SEN(B)] specimens with larger width and thickness are adopted to evaluate the stress corrosion cracking behavior of SA508/52Mb cracks. The constraint levels of 52Mb/52Mw cracks match those of the CC(T) and SEN(B) specimens with smaller width and thickness. The 52Mw/316L cracks match the C(T) specimens with larger width and thickness. Nonconservative results will be produced when the CC(T) and SEN(B) specimens are adopted to evaluate 52Mw/316L cracks. This study provides a more accurate method for the structural integrity assessment of DMWJs that can help improve the safety and reliability of critical engineering welded structures such as nuclear power plants.

Rui Nie, Yu Wang, Ziling Zhou et al.

The failure fraction of tri-structural isotropic (TRISO)-coated particles in the fuel elements of the core is a key indicator for characterizing the radiation safety of a high-temperature gas-cooled reactor (HTGR) and can be determined from accurate measurement of the activity concentrations of noble gas fission products in the primary coolant. However, in the high-temperature gas-cooled reactor pebble-bed module (HTR-PM), the total γ activity concentration in the primary circuit is currently monitored online without individual nuclide resolution. In this study, an online monitoring instrument based on a HPGe detector is proposed to obtain the activity concentration of individual nuclide in real time. Geant4 simulates detection efficiency, background energy spectrum, and minimum detectable activity concentration (MDAC) of the monitoring system, which are key parameters for evaluating the reliability and feasibility of the system for detecting noble gas fission products. In addition, a method for quickly calculating the MDAC using fitting formulas with low and high precisions is proposed, meeting the accuracy requirements for engineering applications. This study promotes application of online nuclide resolution technology in HTGR for fast assessment of fuel-element performance in the core. The proposed rapid MDAC evaluation method for detection systems can also be applied in nuclear emergency monitoring.

M. Morbey, F. Effenberg, S. Abe et al.

Divertor designs involving liquid lithium have been proposed as an alternative to solid designs and wall conditioning techniques. However, Li affinity with tritium poses a risk for the fuel cycle. This study investigates deuterium retention in pre-lithiated samples and Li–D co-deposits in the DIII-D tokamak, making for the first time a direct comparison between Li–D co-deposits and pre-deposited Li films. Samples were exposed to H-mode plasmas in the far scrape-off layer (SOL), and Li powder was injected in-situ with the impurity powder dropper to study the uniformity of Li coatings, and the dependence of fuel retention on Li thickness. The results show that at temperatures below the melting point of lithium, deuterium retention is independent of the thickness of pre-deposited Li layers, with Li–D co-deposits being the primary factor for fuel retention. Both pre-deposited and in-situ deposited Li showed lower erosion than predicted by sputtering yield calculations. These results suggest that fuel retention in fusion reactors using lithium in the divertor will likely be dominated by co-deposits rather than in the divertor itself. If one desires to use Li to achieve flatter temperature profiles, operando Li injection is advantageous over pre-deposited Li films, at least at temperatures below the melting point of lithium.

Herranz Luis E., Jiménez Gonzalo, Kärkelä Teemu

After the Fukushima Daiichi accident, a new wave of research projects aiming at enhancing severe accident (SA) management was launched under different international frameworks. This was the case of MUSA (Management and Uncertainties of Severe Accidents), AMHYCO (Towards and enhanced Accident Management of the H2 and CO combustion risk) and SOCRATES (Assessment of liquid Source Term for accidental post management phase), which under the frame of H2020 and HEUROPE EURATOM were devised to optimize different aspects of Severe Accident management. MUSA explored how bringing uncertainties quantification in the Severe Accident analysis might provide sounder insights into effects and timing of accident management actions. AMHYCO brought new insights into combustion risk management, particularly during the ex-vessel phase of the accident, by combining in a selective manner different analytical approaches and data on recombination and combustion of gas mixtures (i.e., H2/CO/air/steam). SOCRATES is hitting accident management related to liquid source terms, with emphasis in the long-run of the accident. This paper describes the major outcomes of the projects and outlines what should come next for an efficient application of the insights gained in the accident management.

Yoon Soo Chung, Hyung-Joo Choi, Chul Hee Min et al.

The Yonsei Single-photon Emission Computed Tomography version 2 (YSECT v.2) for inspection of spent nuclear fuel in the wet storage facility is currently under development. However, the high radiation fields of the facility can potentially damage the system. In this study, we evaluated radiation damage to the scintillator and silicon photomultiplier (SiPM) and its impact on performance. The facility was modeled using Monte Carlo simulation, and the gamma dose and neutron flux delivered to the detector were calculated. Based on the calculated values, experiments were conducted to evaluate damage by irradiating photons and neutrons to the detector. Radiation damage was assessed by comparing 137Cs spectra obtained before and after irradiation. Additionally, the damage was assessed by comparing the spectra obtained for gamma rays emitted from 252Cf during neutron irradiation. As a result, no detector damage due to photon irradiation was observed. For neutron irradiation, when the neutron fluence reaches approximately 3.0 × 109 neutrons/cm2, the signal gain decreases by 16.66 % due to SiPM damage. Nevertheless, there was no change in the measured counts, which are important for image reconstruction of the system. It is expected that the wet storage environment will not affect the results of YSECT v.2 spent fuel inspection.

Nasir U. Eisty, Jeffrey C. Carver, Johanna Cohoon et al.

In the evolving landscape of scientific and scholarly research, effective collaboration between Research Software Engineers (RSEs) and Software Engineering Researchers (SERs) is pivotal for advancing innovation and ensuring the integrity of computational methodologies. This paper presents ten strategic guidelines aimed at fostering productive partnerships between these two distinct yet complementary communities. The guidelines emphasize the importance of recognizing and respecting the cultural and operational differences between RSEs and SERs, proactively initiating and nurturing collaborations, and engaging within each other's professional environments. They advocate for identifying shared challenges, maintaining openness to emerging problems, ensuring mutual benefits, and serving as advocates for one another. Additionally, the guidelines highlight the necessity of vigilance in monitoring collaboration dynamics, securing institutional support, and defining clear, shared objectives. By adhering to these principles, RSEs and SERs can build synergistic relationships that enhance the quality and impact of research outcomes.

A. Ekidin, K. Antonov, M. Vasyanovich et al.

C. Dubi, A. Prinja

Abstract Modeling and simulation of stochastic fission chains, often referred to as zero power reactor noise or stochastic transport, is a central topic in nuclear science and engineering, with important practical applications in reactor control and measurements. The common mathematical setting for studying reactor noise is through branching processes, typically modeled using forward and backward master equations. Because of the high complexity of the problem, reactor noise is typically studied under the point model approximation and in a linear setting, which neglects any reactivity feedbacks. On the other hand, since reactivity feedbacks are dominant in power reactors, stochastic models and simulations in a nonlinear setting are of great interest. For this reason, there is a constant interest in new mathematical frameworks that will enable modeling and simulation in a complete fashion. In the present study, we look at a branching process with a negative feedback, realized by a linear increase in the per capita death rate. In particular, the outline of the study is to compare two models for the above process. The first is the exact model, based on a forward master equation, and the second is the diffusion scale approximation (or the functional central limit approximation), realized in an Ito-type stochastic differential equation (SDE). The comparison between the two models is done in two levels. First, we show that the dynamics of the first and second moments of both models are governed by the same equations. Then, by realization of each model, we contract a Monte Carlo simulation for sampling the population size distribution. In particular, we show that once the population size is sufficiently large, the SDE approximation allows us to perform accurate simulations in a critical setting, with a dramatic reduction of the CPU time.

Jing Xing, Niav Hughes Green

This paper responds to Skraaning and Jamieson’s target paper “The Failure to Grasp Automation Failure.” We acknowledge that the target paper made important contributions to automation research in the human factors community. It analyzed automation failure events in complex operational systems in contrast to the vast majority of laboratory research on human-automation interaction. The paper presented a taxonomy of automation failure. The analysis and taxonomy demonstrate the integration of approaches to grasping automation failures from system instrumentation and controls, human factors engineering, and human reliability analysis. We reviewed the regulatory framework related to use of automation in nuclear power plants and examined whether the framework elements adequately address “Failure to Grasp Automation Failure” using the taxonomy in the target paper. Overall, we believe that the target paper could enhance the consideration for potential automation failures in the design and regulatory review process of automation technologies.

ZONG Bo, ZENG Deyang, WANG Kaikai et al.

BackgroundFlexible neutron protection composite materials are of great significance for the protection of special-shaped components and personnel. Their performances are closely related to the properties of functional fillers, but the effect of size of 2D functional fillers on the performance of composites is not yet clear.PurposeThis study aims to explore the influence of two-dimensional (2D) functional filler size on the mechanical properties and neutron shielding performance of composite materials.MethodsFirstly, ethylene propylene diene monomer (EPDM) rubber with good performance such as high temperature resistance, weather resistance, radiation stability, mechanical properties, and high hydrogen content was used as flexible substrate material, and layered boron bitride (BN) with a high thermal neutron absorption cross-section was taken as 2D functional filler, and the surface of BN was modified by mercapto group through two-step chemical grafting. BN/EPDM flexible neutron protection composite materials were prepared by the process of plasticizing, mixing and hot pressing and vulcanization, and the content of BN was controlled at 20~100 phr (parts per hundred parts of rubber), and azodiisobutyronitrile (AIBN) acted as an initiator to promote the interfacial bonding between mercaptylated boron nitride (BN-SH) and EPDM substrate. Then, the microstructures of the materials such as functional group and microscopic morphology were characterized and analyzed using Fourier transform infrared spectrum (FTIR) and scanning electron microscope (SEM). Subsequently, the tensile properties including tensile strength and elongation at break were characterized by universal testing machine, according to GB/T 528―2009 standard. The surface hardness was measured by Shore A hardness tester, according to GB/T 531.1―2008 standard. Finally, the neutron shielding performance was tested based on cadmium sheet difference method, where americium-beryllium source with moderation and collimation was used as narrow beam measurement geometry, and 3He detector was used to count neutrons.ResultsThe experimental results indicate that the reduction of BN size is conducive to improving the tensile strength and thermal neutron shielding performance of composite materials. When the thickness of the material is 2 mm, its tensile strength can reach up to 8.13 MPa, and the thermal neutron shielding rate can be increased by up to about 5%, which is related to the amount of nano BN.ConclusionsThis study confirms the size effect of two-dimensional functional fillers in neutron shielding composite materials, and can provide the basis for the design and preparation of polymer-based flexible neutron protection composites.

Liangjie Li, Yanling Cheng, Zhifei Liu

Objective: To investigate the correlation between the characteristic parameters of CT texture in arterial phase of gastric cancer and the expression of HER-2 and Ki-67. Methods: A total of 72 patients with gastric cancer in the First People's Hospital of Kashgar (October 2014 to October 2023) were collected, including 51 males and 21 females, with an average age of 58.9 years. According to the expression of HER-2 and Ki-67, the patients were divided into negative and positive expression group. The CT texture parameters of tumor arterial phase were measured by 3D Slicer-Radiomics CT texture analysis software. Results: Arterial phase CT texture parameters including P90, entropy, quartile, maximum, mean deviation, absolute deviation of gross error, root mean, uniformity and variance were associated with HER-2 expression (P < 0.05). There was no significant correlation between HER-2 expression level and P10, energy, kurtosis, mean, median, minimum, range, skewness and total energy (P > 0.05). Ki-67 expression level was not correlated with the CT texture parameters in arterial phase (P > 0.05). The ROC curve analysis and the results of AUC showed that the diagnostic efficiency of entropy was the highest (AUC = 0.71, P = 0.006). Conclusion: CT arterial phase texture parameters could predict the expression of HER-2 protein in gastric cancer, but could not predict the expression of Ki-67 protein.

Mikael Frosini, Thomas Duguet, Pierre Tamagno et al.

The construction of predictive models of atomic nuclei from first principles is a challenging (yet necessary) task towards the systematic generation of theoretical predictions (and associated uncertainties) to support nuclear data evaluation. The consistent description of the rich phenomenology of nuclear systems indeed requires the introduction of reductionist approaches that construct nuclei directly from interacting nucleons by solving the associated quantum many-body problem. In this context, so-called \textit{ab initio} methods offer a promising route by deriving controlled (and systematically improvable) approximations both to the inter-nucleon interaction and to the solutions of the many-body problem. From a technical point of view, approximately solving the many-body Schrödinger equation in heavy open-shell systems typically requires the construction and contraction of large mode-4 (mode-6) tensors that need to be stored repeatedly. Recently, a new dimensionality reduction method based on randomized singular value decomposition has been introduced to reduce the numerical cost of many-body perturbation theory. This work applies this lightweight formalism to the study of the Germanium isotopic chain, where standard approaches would be too expansive to run. Inclusion of triaxiality is found to improve the overall agreement with experimental data on differential quantities.

Peter Lalor, Areg Danagoulian

To combat the risk of nuclear smuggling, radiography systems are deployed at ports to scan cargo containers for concealed illicit materials. Dual energy radiography systems enable a rough elemental analysis of cargo containers due to the Z-dependence of photon attenuation, allowing for improved material detection. This work presents our initial experimental findings using a novel approach to predict the atomic number of dual energy images of a loaded cargo container. We consider measurements taken by a Rapiscan Sentry Portal scanner, which is a dual energy betatron-based system used to inspect cargo containers and large vehicles. We demonstrate the ability to accurately fit our semiempirical transparency model to a set of calibration measurements. We then use the calibrated model to reconstruct the atomic number of an unknown material by minimizing the chi-squared error between the measured pixel values and the model predictions. We apply this methodology to two experimental scans of a loaded cargo container. First, we incorporate an image segmentation routine to group clusters of pixels into larger, roughly homogeneous objects. By considering groups of pixels, the subsequent atomic number reconstruction step produces a lower noise result. We demonstrate the ability to accurately reconstruct the atomic number of blocks of steel and high density polyethylene. Furthermore, we are able to identify the presence of two high-Z lead test objects, even when embedded within lower-Z organic shielding. These results demonstrate the significant potential of this methodology to yield improved performance characteristics over existing methods when applied to commercial dual energy systems.

Leendert Hayen

For well over half a century, precision studies of neutron and nuclear $β$ decays have been at the forefront of searches for exotic electroweak physics. Recent advances in nuclear ab initio theory and the widespread use of effective field theories means that its modern understanding is going through a transitional phase. This has been propelled by current tensions in the global data set leading to renewed scrutiny of its theoretical ingredients. In parallel, a host of novel techniques and methods are being investigated that are able to sidestep many traditional systematic uncertainties and require a diverse palette of skills and collaboration with material science and condensed matter physics. We highlight the current opportunities and open questions with the aim of facilitating the transition to a more modern understanding of $β$ decay.