bluuebunny/crossref_metadata_2025_split huggingface dataset:
Designing a Knowledge-Centric Plant Information Model by Integrating Tacit Knowledge
Authors: Mosler Pascal , Rüppel Uwe 
Published: November 2024

Abstract
In knowledge-centric plant information models (K-PIMs) for nuclear power plants, the focus is not on documents or data, but on knowledge. Since knowledge is much more difficult to document and transfer than data and information, the design of a K-PIM requires a new approach and a rethinking of existing routines and processes. First, this paper identifies the technological and organizational requirements for a K-PIM. Two particular anchor points here are tacit knowledge in the context of knowledge management as well as the decommissioning phase. The effects of knowledge gaps and inadequate knowledge management become clear in the decommissioning phase at the latest and are expressed in additional work for data collection and in the question of how to deal with legacy data. For this reason, the approach chosen here is to think about the requirements for a K-PIM “from the end”, i.e. from decommissioning and the explicit and tacit knowledge required there. Although tacit knowledge plays a significant role in routine operation, it is currently only inadequately mapped in information models and is difficult to access for other people, not to mention future generations. Based on these findings, a K-PIM is proposed in which knowledge is spatially located and can therefore be experienced holistically. Three technologies play a central role in the proposed concept: building information modeling, extended reality (including virtual reality and augmented reality), and semantic technologies. Together, they create a possible basis for the successful incorporation and transfer of both explicit and implicit knowledge.
Study of Jet Characteristics and Structural Fatigue in the Upper Chamber of a Lead-Bismuth Eutectic Cooled Reactor Based on Fluid-Structure Coupling Methods
Authors: Zhang Ji , Wang Mingjun , Tian Wenxi , Qiu Suizheng , Su Guanghui 
Published: November 2024

Abstract
To evaluate the impact of temperature fluctuations caused by jet mixing in the upper plenum of a lead-bismuth eutectic (LBE) reactor on the fatigue damage of internal structural components, this paper conducts a study on the stress distribution of the operation head and the central column based on a fluid-solid coupling calculation method. On this basis, a fatigue damage assessment method under thermal stress for the solid domain is established. The fatigue damage of the operation head and the central column under typical working conditions, as well as the influence of the flow parameters at the operation head inlet on fatigue damage, are analyzed. The results indicate that the fatigue damage at the monitoring points on the side of the operation head is significantly higher than that in the central column and should be given special attention. Compared to velocity, fatigue damage is more sensitive to temperature distribution, and the degree of fatigue damage decreases with the reduction of temperature difference. The research in this paper can provide reference and guidance for the design and operation of LBE reactors.
Analysis and Research on Control Strategy of Supercritical Carbon Dioxide Recompression System
Authors: Liu Xiuting , Huang Yanping , Zhou Yuan , Liu Minyun , Yang Jun , Qin Bitan , Liu Ruilong 
Published: November 2024

Abstract
This article takes the supercritical carbon dioxide recompression cycle system as the research object, and analyzes different control methods such as speed control (including compressor speed regulation and turbine speed regulation), volume control (including changing compressor inlet pressure and compressor inlet temperature), and throttling control under established thermodynamic parameters. Based on the characteristics of the cycle and the characteristics of a single control method, a control strategy combining multiple control methods with different load intervals and mobility requirements is proposed. The research results indicate that speed control has the highest efficiency under partial load conditions among various methods, followed by volume control and throttling control. There are depth limits for load reduction in a single control method, and compressor surge and outlet pressure over pressure may occur in different load ranges. Based on the characteristics of different load intervals and regulation methods, we propose a combination control strategy scheme. When 0% FP ≤ load level &lt; 20% FP, a combined control scheme of throttling control and bypass control is adopted; When 20% FP ≤ load level &lt; 90% FP, the most efficient speed control scheme is adopted, which adopts speed gear adjustment to avoid frequent equipment actions. When 90% FP ≤ load level ≤ 100% FP, volume control is adopted.
Digital Twin and Surrogate Model for Long-Term Geochemical Processes in Nuclear Waste Management
Authors: Hu Guang , Miron George Dan , Pfingsten Wilfried , Dähn Rainer 
Published: November 2024

Abstract
This study presents an advance in predicting long-term stability in waste containment systems. Employing a surrogate model based on the 25 GEMS Python scripts, we simulate geochemical interactions within waste degradation processes over 100 years. The model simplifies complex full-scale geochemical models using a mixing tank approach, primarily examining the evolution of material properties influenced by uncertain surface characteristics and reaction kinetics. 1 million cases are generated using the neural network-based surrogate model, drastically reducing computational time (∼1.9 seconds) compared to traditional methods (∼78.4 days). The model evaluates the deterioration mechanisms of various materials like iron, aluminum, zinc, and brass, in cementitious waste packages, crucial for assessing their impact on the integrity of waste containment over extended periods.
Our findings with the neural network-based surrogate model, including ion concentrations and mass changes in materials like iron, brass, aluminum, and copper, offer detailed insights into chemical changes in the system. Incorporating a sensitivity analysis with 1 million cases generated by the surrogate model, the study underscores the interplay between chemical reactions and material properties, establishing a digital twin that links reaction rates to the stability of nuclear waste repositories. This study presents key indicators of potential integrity threats due to material expansion, contraction, or gas-induced pressure variations.
Visual Analysis of the Research Status, Hotspots, and Trends of International Nuclear Industry Internet Platforms
Authors: Xianying Liu , Jing Yinggang , Cheng Minmin , Fang Huajian 
Published: November 2024

Abstract
The Industrial Internet can improve the production efficiency of the energy industry through technologies such as intelligent control technology, remote monitoring technology, predictive maintenance technology, intelligent risk management and system security control, and is the core of promoting efficient allocation of manufacturing resources. As an important part of the energy field, nuclear power has higher requirements on safety and energy utilization than other conventional energy sources. Nuclear energy enterprises also need to rely on intelligent information management systems to improve the efficiency and safety of nuclear power production.
This article uses bibliometrics, combined with visual charts, to comparatively analyze the current situation, hot spots, and trends in the use of industrial Internet platform technology in the field of nuclear energy in major nuclear power countries, and combines the future development trends of international nuclear energy with the construction of industrial Internet platforms for nuclear power enterprises in the field of nuclear energy, planning, and provide brief reference suggestions.
General Outline of the Decommissioning of the Prototype Fast Breeder Reactor MONJU
Authors: Kobayashi Hideharu , Naruse Keiji , Hirako Kazuhito , Sawazaki Hiromasa , Goto Takehiro , Obata Ikuhito , Matsui Kazuaki 
Published: November 2024

Abstract
The prototype fast breeder reactor “MONJU” is a loop-type sodium-cooled nuclear reactor under decommissioning in Japan. Japan Atomic Energy Agency (JAEA) started its decommissioning in 2018, and will complete the four phases of decommissioning in about 30 years.
The phase I is already over. It was the “Fuel unloading” stage during which secondary sodium was drained, the fuel assemblies in the reactor core were removed and put in storage in the spent fuel pool, while the distribution of radioactive contamination in buildings, components, equipment, etc. was evaluated.
The phase II is ongoing. It is focused on the “Preparation for dismantling the plant”. We have been removing the neutron shields in the reactor core and putting them in storage in the spent fuel pool in preparation for the dismantling of the sodium-adhered equipment. We will also transport sodium, dismantle and remove the power-generating facility such as water/steam systems. In addition, we continue to assess the distribution of radioactive contamination in buildings, components, equipment, etc.
The phase III will be started in 2032. This phase, the “Decommissioning Period I” is focused on the dismantling and removing of sodium-adhered equipment, the transport of spent fuel, and the removal of the water and steam power generation system.
The final Phase is the “Decommissioning Period II” during which the radiation-controlled area will be lifted and all the buildings will be dismantled and removed.
This paper presents an overview of MONJU decommissioning, the results of the phase I, and details of the phase II currently ongoing.
Uncertainty and Sensitivity Analysis of Phebus FPT-1 Experiment Based on Severe Accident Analysis Code ISAA
Authors: Yang Hao , Zhang Bin , Li Jishen , Gao Pengcheng , Zhang Zhiran , Miao Fan 
Published: November 2024

Abstract
Since the Three Mile Island nuclear accident, international research on severe accidents has advanced through a combination of experimental studies and numerical simulations. The intricate physical processes and chemical phenomena involved in severe reactor accidents have led to a heavy reliance on empirical parameters in existing severe accident analysis programs, generating significant uncertainties. As a result, there is growing interest in applying systematic analysis programs combined with uncertainty quantification methods to evaluate potential severe accident consequences, a topic receiving considerable attention among researchers in severe accident analysis. In 2019, Europe initiated the MUSA project, an international collaboration focusing on severe accident management and uncertainty. The project centers on a series of severe accident uncertainty analysis studies based on the Phebus FPT1 experiment. This serves as a valuable tool for assessing severe accident analysis code effectiveness in simulating severe reactor accident progression and offers an opportunity to analyze and enhance code physical models. Previous numerical analysis studies using the integrated severe accident analysis program ISAA for the FPT experiment revealed the necessity for significant estimations, particularly in core degradation and source term release. This underscores the importance of conducting uncertainty and sensitivity studies on parameters affecting numerical simulation results using advanced uncertainty analysis methods. In this study, we employed a self-developed uncertainty analysis tool to conduct random sampling analysis based on Latin hypercube sampling for various uncertainty parameters, including experimental modeling data and code model parameters. Utilizing the Wilks theory, the study conducted uncertainty quantification studies on the thermal-hydraulic results and hydrogen production in the FPT1 experiment. Data comparison shows the current oxidation model of ISAA overestimates the hydrogen production rate during oxidation, but overall agrees well with experimental measurements. Local sensitivity analysis was also conducted for hydrogen production, further quantifying the impact of uncertainty parameters on numerical simulations. Sensitivity analysis shows the radial radiation heat transfer factor, power, and fuel rod failure criterion significantly impact numerical calculations during loss of coolant accident. A more mechanistic fuel rod failure model is crucial for numerical simulation of severe accident processes. The research not only contributes to refining and improving numerical models within analysis codes but also plays a significant role in reducing uncertainty associated with numerical simulations.
Effect of Neutron Leakage on Equilibrium U-Pu and Th-U Cycles for 16 Selected Reactors
Authors: Sabol Josef , Křepel Jiří 
Published: November 2024

Abstract
Three papers related to the equilibrium fuel cycle in 16 selected reactors were submitted to ICONE 31 conference. In this last part, the effect of neutron leakage from a finite core is evaluated.
This work deals with three main issues. The first goal is to verify when and how the modified one-group critical equation can be used to estimate the neutron leakage. Secondly, as the spectrum is changing together with the neutron leakage, it was another task to find how these changes would affect the equilibrium. And thirdly, because some of the reactors are supercritical in an infinite lattice, their minimal critical volume can be found and compared.
It was found that the critical equation cannot be used for fast reactors, especially for the U-Pu cycle, because due to the neutron leakage, the spectrum is harder and migration area with infinite multiplication factor are changing. Much better results were obtained with thermal reactors and for the Th-U cycle. When using new values obtained from a finite volume, the results match the reality more closely.
The same applies to the equilibrium calculation, where the largest differences were obtained for systems with large changes in the neutron spectrum. At the same time, it was found that the smaller the migration area, the smaller the volume is needed to show the change in the spectrum.
All results were obtained using the EQL0D v4 procedure and with ENDF/B-VIII.0 nuclear data library.
LES of Twin High-Re Rectangular Jets for Benchmarking Model Order Reduction Methods
Authors: Acierno John , Merzari Elia , Petrov Victor , Manera Annalisa 
Published: November 2024

Abstract
The study of turbulent mixing in non-isothermal coolant streams is crucial in understanding thermal striping, an oscillatory mixing pattern that can lead to thermal fatigue and degradation of internal components in advanced nuclear reactors. Thermal striping is linked closely to local 3D fine scales associated with turbulence. Historically, Large Eddy Simulation (LES) or Direct Numerical Simulation (DNS) were required to resolve these scales. Our investigation centers on the mixing dynamics within the Reactor Cavity Cooling System (RCCS) separate effects test facility. We study the interaction of two parallel-planar jets within a confined plenum to uncover flow mixing characteristics. Initially, LES simulations are employed to generate velocity and temperature statistics and time series data for comparison against future ROM approaches. Analysis of the velocity time series data using Power Spectrum Density (PSD) reveals a distinct low frequency mixing mode indicative of thermal striping. Subsequently, we utilize Proper Orthogonal Decomposition (POD) to extract dominant flow structures from 600 high-fidelity instantaneous velocity snapshots. These POD modes are utilized to construct a reduced-order model (ROM) capable of replicating the low frequency mode associated with thermal striping. By leveraging LES data with ROM techniques, we can efficiently and accurately predict the low frequency mode.
Experimental Studies on Two-Layer Stratified Molten Pool Heat Transfer With Water and 1-Octanol
Authors: Quan Fengyang , Pei Jie , Li Wei , Yuan Yidan 
Published: November 2024

Abstract
In the framework of severe accident studies, huge amount of tests have been carried out for molten pool’s heat transfer behavior in IVR configurations. However, there are still uncertainties in the range of high Rayleigh number (1016 to 1017). Besides, the impact of the metallic layer cannot be quantified. To analyze the influence of different simulants and the metallic layer, high temperature Stratified Molten POol Experiment facility (SAMPO), which designed by China Nuclear Power Engineering Co., LTD, is presented in this paper. The system plans to conduct melt pool tests on two-layer melt pools of different simulants working in low (below 100 °C), medium (around 300 °C), and high temperatures (above 500 °C) respectively. The effect of different heat release rates of different pool volumes on the internal Rayleigh number and heat transfer at the pool boundary under the same pool height conditions. The The low temperature test result with water and 1-octanol is presented in this study, meanwhile, the reliability of the experimental system has been verified through low-temperature testing.
Study on Thermal-Hydraulic Characteristics of Horizontal Lead-Based Reactor Whole Core
Authors: Gui Minyang , Wu Di , Zhang Hangyuan , Zhang Senmiao , Cheng Hui 
Published: November 2024

Abstract
Lead-based Fast Reactor (LFR) has high power density, strong inherent safety, and excellent maneuverability, which can meet the requirements of the multi-purpose nuclear power plant. In some specific scenarios, due to space constraints, the reactor core needs to be positioned horizontally, and the thermal-hydraulic characteristics will be different from those under vertical conditions.
According to the special structure and operational characteristics of horizontal LFR, the subchannel analysis code SACOS-HLFR was developed in this paper. With the subchannel code, the thermal-hydraulic evaluation of the whole core in horizontal LFR was conducted, mainly focusing on the flow and temperature distribution of the hottest assembly. In the whole core analysis, the outlet coolant temperature of the hottest assembly increases first and then decreases along the gravity direction. In contrast to the single assembly analysis, the flow and temperature difference between the upper and lower of the hottest assembly is significantly reduced due to the crossflow mixing with adjacent assemblies. At the same time, the position of the hottest channel is moved from the upper region of the assembly to the lower region. For the hottest rod, the maximum temperature of the cladding and pellet does not exceed the corresponding limit value, the reactor code can operate safely.
Elevated incidence of infant botulism in a 17-county area of the Mid-Atlantic region in the United States, 2000–2019, including association with soil types
Authors: Dabritz Haydee A. , Friberg Ingrid K. , Payne Jessica R. , Moreno-Gorrin Camille , Lunquest Kristy , Thomas Deepam , Newman Alexandra P. , Negrón Elizabeth A. , Drohan Patrick J. 
Published: October 2024

ABSTRACT

We sought to identify counties in the northeastern United States where the incidence of infant botulism (IB) is elevated compared to the nationwide incidence and to assess associations with soil type at the case residence. IB cases were identified through the distribution of the orphan drug Human Botulism Immune Globulin Intravenous for treatment of IB by state and national surveillance systems and were subsequently confirmed by laboratory testing. IB incidence by county was calculated as the number of IB cases divided by the number of live births in the county from 2000 to 2019. Cases were spatially mapped and assigned to soil types using the US Department of Agriculture’s online soils database. Possible association with soil type was evaluated with the Chi-squared test. We identified a rectangular area consisting of 17 contiguous counties in Delaware, Maryland, New Jersey, New York, and Pennsylvania, approximately 80 km by 250 km, in which the 20-year incidence of IB was nearly seven times greater than that of the remaining counties in those five states. Within this area, case residences were strongly associated with certain soil types (
P
≤ 0.003). From 2000 to 2019, IB occurred with disproportionate incidence in a rectangular area encompassing the lower Delaware and Raritan River Valley and parts of five adjacent states. Further investigation of the soils in counties from this area could assess whether
C. botulinum
is more prevalent in certain soil types and whether isolation of
C. botulinum
is more common in counties with higher IB incidence.

IMPORTANCE
Infant botulism occurs more frequently in 17 counties within and adjacent to the Delaware and Raritan River watersheds. This study should alert physicians and pediatricians in the area to the higher likelihood of encountering cases of this otherwise rare disease that manifests with constipation, poor feeding, loss of head control, weak suck/cry, generalized weakness, and descending bilateral paralysis.
A type VI secretion system in
Burkholderia
species
cenocepacia
and
orbicola
triggers distinct macrophage death pathways independent of the pyrin inflammasome
Authors: Loeven Nicole A. , Dabi Clarrisa , Pennington Joseph P. , Reuven Arianna D. , McGee Abigail P. , Mwaura Bethany W. , Bliska James B. 
Published: October 2024

ABSTRACT

The
Burkholderia cepacia
complex contains opportunistic pathogens that cause chronic infections and inflammation in the lungs of people with cystic fibrosis. Two closely related species within this complex are
Burkholderia cenocepacia
and the recently classified
Burkholderia orbicola. B. cenocepacia
and
B. orbicola
encode a type VI secretion system and the effector TecA, which is detected by the pyrin/caspase-1 inflammasome, and triggers macrophage inflammatory death. We previously showed that the pyrin inflammasome was dispensable for lung inflammation in mice infected with
B. orbicola
AU1054
,
indicating this species activates an alternative pathway of macrophage inflammatory death. Notably,
B. cenocepacia
strains J2315 and K56-2 can damage macrophage phagosomes, and K56-2 triggers activation of the caspase-11 inflammasome, which detects cytosolic lipopolysaccharide. Here, we investigated inflammatory cell death in pyrin- (
Mefv
-/-
) or caspase-1/caspase-11- (

Casp1/11
-/-

) deficient mouse macrophages infected with
B. cenocepacia
J2315 or K56-2 or
B. orbicola
AU1054 or PC184. Macrophage inflammatory death was measured by cleavage of gasdermin D protein, the release of cytokines IL-1α and IL-1β, and plasma membrane rupture. We found that J2315 and K56-2 are detected by the caspase-11 inflammasome in
Mefv
-/-
macrophages, resulting in IL-1β release. By contrast, inflammasome activation was not detected in
Mefv
-/-
macrophages infected with AU1054 or PC184. Instead, AU1054 triggered an alternative macrophage inflammatory death pathway that required TecA and resulted in plasma membrane rupture and IL-1α release. Structural modeling of TecA orthologs in
B. cenocepacia
and
B. orbicola
suggested that amino acid changes in the latter may underlie its ability to trigger a non-inflammasome macrophage death pathway.