We explore the concept of folklore within software engineering, drawing from folklore studies to define and characterize narratives, myths, rituals, humor, and informal knowledge that circulate within software development communities. Using a literature review and thematic analysis, we curated exemplar folklore items (e.g., beliefs about where defects occur, the 10x developer legend, and technical debt). We analyzed their narrative form, symbolic meaning, occupational relevance, and links to knowledge areas in software engineering. To ground these concepts in practice, we conducted semi-structured interviews with 12 industrial practitioners in Sweden to explore how such narratives are recognized or transmitted within their daily work and how they affect it. Synthesizing these results, we propose a working definition of software engineering folklore as informally transmitted, traditional, and emergent narratives and heuristics enacted within occupational folk groups that shape identity, values, and collective knowledge. We argue that making the concept of software engineering folklore explicit provides a foundation for subsequent ethnography and folklore studies and for reflective practice that can preserve context-effective heuristics while challenging unhelpful folklore.
The fission neutron will show a certain angular correlation due to the momentum enhancement of fission fragments. Neutron-neutron angular correlation is related to the intrinsic characteristics of the nucleus and can be applied to the characterization of nuclear materials. Currently, the mechanism related to the influence of matrix effects on neutron-neutron angular correlation of nuclear materials is not clear, which leads to the deviation. In this paper, a liquid scintillation detection system was built by Geant4 to investigate the matrix effects of nuclear materials. It is found that the change of neutron-neutron angular correlation mainly comes from the effect of induced fission and neutron scattering. Meanwhile, this paper also investigates the neutron anisotropy in different energy regions and the change of neutron-neutron angular correlation, and obtains the distribution of neutron-neutron energy-angle correlation, which further reveals the nature of neutron energy angular correlation. It is shown that neutron-neutron angular correlation is strongly affected by the matrix effect of nuclear materials and cannot be used to characterize the properties of nuclear materials. The neutron-neutron energy-angle correlation achieves feature enhancement by coupling the angle and energy information of fission neutrons, and has great potential in the radionuclide identification. The findings of this study on the matrix effect and the proposed energy-angle correlation analysis have significant potential for application in nuclear security and safeguards.
This study presents a material-density engineering approach to further miniaturize gamma-ray imaging systems for unmanned platforms with strict payload limitations. Three coded-aperture masks were fabricated with identical geometry but different densities: pure tungsten (19.3 g/cm3) and tungsten filament composites (7.8 g/cm3 and 4.0 g/cm3). These masks were integrated into a miniature gamma camera and systematically evaluated in terms of spectroscopic and imaging performance, with results benchmarked against the commercial Energetic Particle Sensor for the Identification and Localization of Originating Nuclei-Gamma (EPSILON-G) system. Spectroscopic tests with a 137Cs source demonstrated an energy resolution of 6.35 %, representing an improvement of about 2 % compared with EPSILON-G, along with favorable peak-to-Compton ratio (PCR) and peak-to-Valley ratio (PVR) values. Imaging results showed that lower mask density generally reduced field of view, angular resolution, and sensitivity. However, the 7.8 g/cm3 tungsten filament mask achieved the optimal balance, yielding 5.6° angular resolution and sensitivity 2–3 times higher than EPSILON-G. Notably, EPSILON-G required up to 150 s for image reconstruction under the same dose-rate conditions, whereas the miniature system localized sources more rapidly due to additional shielding suppressing background radiation. The 7.8 g/cm3 mask reduced weight by 57 % relative to pure tungsten, and the complete miniature gamma camera weighed only ∼700 g, underscoring its suitability for unmanned deployment.
This study investigates the sorption behavior of Re(VII) onto bulk solid and colloidal phases of Bentonil-WRK bentonite under various reducing conditions. Reducing systems were established with Na2S2O4, disodium anthraquinone-2,6-disulfonate, and DB-3 groundwater from the KAERI Underground Research Tunnel (KURT). Batch sorption experiments were conducted for 2500 h with an initial Re(VII) concentration of 10−6.5 M and a solid-to-liquid ratio of 0.5 g/L. Measured pH and Eh values indicated the reduction of Re(VII) to Re(IV), consistent with thermodynamic predictions and confirmed by X-ray photoelectron spectroscopy. Sorption efficiency increased markedly after 500 h, highlighting the governing role of Re redox chemistry in such conditions. Faster sorption occurred in the DB-3 system, where Fe(II) ions and sulfur-bearing colloids enhanced Re retention. Sorption kinetic analysis indicated a redox-controlled sorption behavior of Re(VII) onto bulk solid and colloidal bentonite under the investigated reducing conditions. The results are expected to support more reliable predictions of the migration and retardation of redox-sensitive anionic radionuclides (e.g., Tc, for which Re serves as a chemical surrogate) in the reducing subsurface environment.
While mastered by some, good scientific writing practices within Empirical Software Engineering (ESE) research appear to be seldom discussed and documented. Despite this, these practices are implicit or even explicit evaluation criteria of typical software engineering conferences and journals. In this pragmatic, educational-first document, we want to provide guidance to those who may feel overwhelmed or confused by writing ESE papers, but also those more experienced who still might find an opinionated collection of writing advice useful. The primary audience we had in mind for this paper were our own BSc, MSc, and PhD students, but also students of others. Our documented advice therefore reflects a subjective and personal vision of writing ESE papers. By no means do we claim to be fully objective, generalizable, or representative of the whole discipline. With that being said, writing papers in this way has worked pretty well for us so far. We hope that this guide can at least partially do the same for others.
The natural removal coefficient directly affects the amounts of radioactive iodine and aerosols released into the containment after the accident. The radioactivity calculation models in LOCA were established, and the impact of natural removal coefficients on the release of elemental iodine and aerosols into containment was quantitatively analyzed. The results showed that due to the comprehensive influence of factors such as core release type, release time, natural removal effect, nuclide decay, and containment leakage, the radioactivity of each nuclide in the containment reached its maximum value after 40 min of the accident, and then gradually decreased over time. During the effective natural removal time, there was a significant difference in the radioactivity of elemental iodine in the containment under different natural removal coefficients. Taking 131I as an example, the radioactivity ratio of elemental 131I in containment corresponding to the two natural removal coefficients decreased first and then increased over time. Finally, the radioactivity of elemental 131I under different natural removal coefficients was basically the same. The change of aerosol radioactivity in the containment was obviously affected by the value of natural removal coefficients. Under two different natural removal coefficients, the maximum radioactivity ratio of the aerosol nuclides in the containment was about 2.3.
General radiography has the highest usage among diagnostic radiology in Korea, resulting in high radiation dose by general radiography. For the medical radiation safety of patients, it is necessary to evaluate Korean population dose by general radiography. In this study, collective dose and per capita effective dose from general radiography in the Korean population were calculated. To this end, the raw data on the usage of general radiography in Korea as of 2017 was analyzed. Moreover, information on radiation dose from domestic general radiography was collected and PCXMC was used to evaluate the effective dose for patients during general radiography. As of 2017, the usage rate for lower extremity and chest examinations was high, accounting for more than 20 % of the total general radiography examinations. The effective dose depending on the examination type was the highest for whole-spine AP (1.06 mSv), followed by whole-spine LAT (0.61 mSv), and lumbar spine AP (0.51 mSv). As a result of evaluating Korean population dose by general radiography, the collective dose was 22,066 man∙Sv and the per capita effective dose was 0.43 mSv. The evaluation results of the Korea population dose obtained from this study can contribute to patient dose management in general radiography.
Ethnography has become one of the established methods for empirical research on software engineering. Although there is a wide variety of introductory books available, there has been no material targeting software engineering students particularly, until now. In this chapter we provide an introduction to teaching and learning ethnography for faculty teaching ethnography to software engineering graduate students and for the students themselves of such courses. The contents of the chapter focuses on what we think is the core basic knowledge for newbies to ethnography as a research method. We complement the text with proposals for exercises, tips for teaching, and pitfalls that we and our students have experienced. The chapter is designed to support part of a course on empirical software engineering and provides pointers and literature for further reading.
High boron steels containing 2 wt% and 3.3 wt% boron were fabricated using hot isostatic pressing (HIP). The enhanced shielding performance of the steel with higher boron content was quantitatively evaluated through Monte Carlo simulations using software Fluka. The steels were studied with XRD and the phase ratio were calculated using Rietveld refinement method. The microstructure of the materials was investigated using electron backscatter diffraction (EBSD). Comprehensive thermal property measurements, complemented by Hamilton thermal conductivity model analysis, were conducted on high boron steels. The results revealed that the decreased overall thermal conductivity in these materials is primarily attributed to two factors: the increased volume fraction of the boride phase and the enhanced interconnectivity among boride particles. These findings provide crucial insights into the thermal behavior of high boron steels. Room temperature tensile tests indicate that high boron content can cause the fracture mode of the material to transition from ductile to brittle. This study provides a detailed analysis of the effects of boron content on various properties of high boron steels, which can serve as shielding materials in fusion reactors. Advances were proposed for optimizing the thermal performance of high boron steels in this study.
BackgroundDeveloping electronic devices, such as metal oxide semiconductor field effect transistor (MOSFET) amplifiers with high radiation resistance, is crucial for robots working in nuclear environments.PurposeThis study aims to test the irradiation resistance performance of commercial MOSFET amplifiers and reveal the corresponding irradiation failure mechanism.MethodsAn in-situ gamma rays irradiation experiment platform was employed to conduct irradiation test on three trench MOSFET amplifiers using a 60Co source. Response to different doses, and the electrical properties of these MOSFET amplifiers were investigated before and after irradiation. The failure analysis methods including electrical characteristics tests, thermal emission microscopy (EMMI) for failure location determination, focused ion beam (FIB) sample preparation, scanning electron microscope (SEM), and transmission electron microscope (TEM) characterization were employed to reveal the irradiation failure mechanism.ResultsExperimental results showed that the three MOSFET amplifiers failed after irradiation by absorbed doses of 982.6 Gy, 986.2 Gy, and 1 082.4 Gy, respectively. The drain-source breakdown voltage BVDSS of the MOSFET decreases from 110.5 V to 0.96 V, while the gate-source drive current IGSS increases from 2.9 nA to 81.3 mA, as well as the threshold voltage VGS(th) is not be detected due to the short circuit.ConclusionsWhen the MOSFET amplifiers are irradiated in a charged operating state, the accumulation of captured charges in the gate oxide will lead to a decrease in the threshold voltage and breakdown voltage. Electron-hole pairs generated by high-energy and high-dose gamma-ray irradiation may continue to accumulate under the action of the circuit electric field, resulting in local high electric fields and high heat areas. The superposition of these high electric fields and high heat areas will cause the source aluminum metal to melt and ablate, causing a short circuit between the gate and the source.
Experimental isomeric ratios of light (A$\le$4) particle-induced nuclear reactions were compiled for the product nuclides having metastable states with half-lives longer than 0.1 sec. The experimental isomeric ratio data were taken from the EXFOR library and reviewed. When an experiment reports isomer production cross sections instead of isomeric ratios, the cross sections taken from the EXFOR library were converted to the isomeric ratios by us. During compilation, questionable data (e.g.,preliminary data compiled in EXFOR in parallel with their final data, sum of isomer production cross sections larger than the total production cross sections) were excluded. As an application of the new compilation, goodness-of-fit was studied for the isomeric ratios predicted by the reaction model code TALYS-1.96.
BackgroundWith the increase of complexity of reactor core design, the core modeling and calculation have brought challenges.PurposeThis study aims to implement the accurate modeling and calculation of unstructured geometry core.MethodsBased on discrete ordinate nodal method for arbitrary triangular-z geometry, the precise modeling and mesh generation of unstructured core were established by constructive solid geometry (CSG), and Block-Jacobi parallel algorithm was employed to reduce calculation time of reactor core. Finally, based on the developed SARAX program, core physics calculations for new complex geometries of a space reactor and a heat pipe reactor were performed for accuracy verification by using Block-Jacobi parallel algorithm combining with established precise model and mesh.ResultsThe verification results show that the effective multiplication factor and radial power distribution agree with that of multi-group Monte-Carlo calculation. The calculation deviation of eigenvalues is less than 3.00×10-3, and the relative deviation of radial power distribution is less than 1.5%.ConclusionsResults of this study show that SARAX code has the ability of modeling and higher accuracy in the calculation of unstructured geometry core.
Objective: IgA nephropathy (IgAN) is the most common primary glomerular disease worldwide, with heterogeneous clinical and pathological manifestations, and is a common cause of end-stage renal disease. Early detection and effective intervention measures are essential for improving the outcome of IgAN. Machine learning methods can make the pathological analysis, early detection and diagnosis, and prognosis prediction of IgAN more automated and accurate. This article discusses the application of machine learning methods in IgAN, from optimizing pathological diagnosis to discovering non-invasive specific biomarkers, predicting disease progression, and evaluating prognosis. It is the key to reducing the incidence rate and mortality of end-stage renal disease by relying on intelligent image analysis of VGG16 for accurate detection and diagnosis of IgA nephropathy to enable clinical to take effective prevention and treatment measures. Methods: A total of 452 cases of kidney disease admitted to the nephrology department of our hospital from January 2018 to February 2023 were selected, and it was ruled out that pathological diagnosis could not be made due to the small number of samples submitted for renal puncture; After excluding suspected cases of renal biopsy pathology diagnosis and patients who did not undergo immunofluorescence examination, a total of 135 confirmed IgA nephropathy patients were subjected to image analysis. The internationally recognized 5-level semi-quantitative method was used for evaluation, and traditional image processing methods were selected to segment and extract fluorescence deposition areas. Transform the input image into color space and generate a binary image using the adaptive threshold method in the two feature dimensions of color and brightness. Then, VGG16 regions were separated and merged to obtain independent sedimentary regions. VGG16 was used to add BN layers and SE visual attention to fully extract sensitive features with high inter-class similarity and significant intra-class differences in the IgA nephropathy image classification task. The contour, area, and average brightness of each sedimentary region were calculated, and automatic computer recognition of fluorescence deposition intensity and shape was obtained to improve the accuracy of IgA nephropathy image classification. Results: The artificial intelligence image analysis based on VGG16 can achieve the interpretation of IgA nephropathy immunofluorescence results with a higher coincidence rate compared to the results of pathological diagnostic doctors. IgA reaches 88.9%, IgG reaches 85.8%, IgM reaches 83.8%, and C3 reaches 88.6%. Therefore, it can assist pathological diagnostic doctors in interpreting IgA nephropathy immunofluorescence. Conclusion: By fully utilizing computer and network technologies to change the pathological workflow, improve the work efficiency of pathological diagnostic doctors, reduce the misdiagnosis rate caused by fatigue during film reading, and make pathological diagnosis more accurate and objective.
Medical physics. Medical radiology. Nuclear medicine, Nuclear engineering. Atomic power
Quarkonium production has long been regarded as a potential signature of deconfinement in nucleus-nucleus collisions. Recently, the production of J/$ψ$ via regeneration within the quark-gluon plasma (QGP) or at the phase boundary has been identified as an important ingredient for the interpretation of quarkonium production results from lead-lead collisions at the Large Hadron Collider (LHC). Quarkonium polarization could also be used to investigate the properties of the hot and dense medium created at the LHC energies. In this contribution, the latest ALICE results on quarkonium will be presented and discussed. These include, among others, the nuclear modifications of (prompt and non-prompt) J/$ψ$ and $ψ$(2S) production, and the J/$ψ$ polarisation, all measured with lead-lead collisions at the LHC. The results will be compared with available theoretical model calculations.
Neutron-induced reactions with charged particle emission play an important role in a variety of research fields ranging from fundamental nuclear physics and nuclear astrophysics to applications of nuclear technologies to energy production and material science. Recently, the capability to study reactions with radioactive targets has become important to significantly advance research in explosive nucleosynthesis and nuclear applications. To achieve the relevant research goals and study (n,x) reactions over a broad neutron beam energy range, the Low Energy Neutron-induced charged-particle (Z) chamber (LENZ) at Los Alamos Neutron Science Center (LANSCE) was developed along with varied ancillary instrumentation to enable the aforementioned research program. For the (n,x) reactions of interest at low energies, a precise simulation of the discrete spectrum of emitted charged particles is essential. In addition, since LANSCE is a user facility, a simulation application that can be easily accessible by users has high value. With these goals in mind, we have developed a detailed simulation using the GEANT4 toolkit. In this work, we present the implementation and the validation of the simulation using experimental data from recent campaigns with the LENZ instrument. Specifically, we benchmark the simulation against a similar MCNP-based tool and determine the realistic range of applicability for the probability biasing technique used. We describe our implementation of an evaluated library with angular distribution and partial cross-section data, and we perform a validation of the application based on comparisons of simulated spectra with the experimental ones, for a number of targets used in previous experimental campaigns. Last, we discuss the limitations, caveats, and assets of the simulation code and techniques used.
As the residual interaction of quantum chromodynamics in low-energy region, the nucleon-nucleon (NN) potential can only be exactly described by the model picture now. In the Bonn potential, one of the most well-known NN interaction models, the nucleons interact with each other through exchanging the pion and several heavier mesons, where the pion plays an essential role. It provides a partial contribution of tensor force in the intermediate-range region and the main component in the long-range region in NN potential. However, it is very difficult to be treated in the nuclear many-body system due to its pseudovector or pseudoscalar property. Recently, three high-precision charge-dependent Bonn potentials were proposed with pseudovector coupling types and different pion-nucleon coupling strengths and applied them to study the properties of nuclear matter and neutron stars in the non-relativistic and relativistic frameworks. Furthermore, to properly deal with the strong short-range repulsion and tensor force of the NN potential, some new relativistic {\it ab initio} methods have also been developed in the past decade to discuss the role of pion and relativistic effects in nuclear matter.
Gennady G. Kulikov, Anatoly N. Shmelev, Vladimir A. Apse
et al.
For a comprehensive assessment of the protection of uranium against proliferation due to the presence of uranium-232 in it, the authors of the article propose and substantiate an integral protection criterion for this material. The criterion is based on the physical barriers against the proliferation of uranium created by uranium-232, namely: (1) the radiolysis of uranium hexafluoride, which hinders attempts to re-enrich uranium and, as a result, a significant critical mass; (2) hard γ-radiation, which leads to incapacity and death of those who try to handle this material without radiation protection; (3) increased heat release, which disables the components of a nuclear explosive device; and (4) a significant source of neutrons that causes predetonation and thereby reduces the energy yield of a nuclear explosive device. These barriers appear at various stages of uranium handling not only in the indicated order but also act simultaneously, mutually reinforcing one another.
In the present study, iodine-131 S values (rT ← thyroid) were calculated for 30 target organs and tissues using the most recently developed Korean reference computational phantoms. The calculated S values were then compared with those of the International Commission on Radiological Protection (ICRP) reference computational phantoms to investigate the dosimetric impact of the Korean S values against those of the ICRP reference phantoms. The results showed significant differences in the S values due to the different anatomical/morphological characteristics between the Korean and ICRP reference phantoms. Most target organs/tissues showed that the S values of the Korean reference phantoms are lower than those of the ICRP reference phantoms, by up to about 4 times (male spleen and female thymus). Exceptionally, three target organs/tissues (gonads, thyroid, and extrathoracic region) showed that the S values of the Korean reference phantoms are greater, by 1.5–3.7 times. We expect that the S values calculated in the present study will be beneficially used to estimate organ/tissue doses of Korean patients under radioiodine therapy.