bluuebunny/crossref_metadata_2025_split huggingface dataset:
Testosterone replacement therapy in blood donors modulates erythrocyte metabolism and susceptibility to hemolysis in cold storage
Authors: Alexander Keisha , Hazegh Kelsey , Fang Fang , Sinchar Derek , Kiss Joseph E. , Page Grier P. , DʼAlessandro Angelo , Kanias Tamir 
Published: October 2020

AbstractBackgroundRed blood cells (RBCs) derived from patients who receive testosterone replacement therapy (TRT) may be considered eligible for component production and transfusion. The aim of this study was to identify testosterone‐dependent changes in RBC metabolism and to evaluate its impact on susceptibility to hemolysis during cold storage.Study Design and MethodsWe characterized stored RBCs from two cohorts of TRT patients who were matched with control donors (no TRT) based upon sex, age, and ethnicity. We further evaluated the impact of testosterone deficiency (orchiectomy) on RBC metabolism in FVB/NJ mice. RBC metabolites were quantified by ultra‐high‐pressure liquid chromatography‐mass spectrometry. RBC storage stability was determined in RBC units from TRT and controls by quantifying storage, osmotic, and oxidative hemolysis.ResultsOrchiectomy in mice was associated with significant (P < 0.05) changes in RBC metabolism as compared with intact males including increased levels of acyl‐carnitines, long‐chain fatty acids (eg, docosapentaenoic acids), arginine, and dopamine. Stored RBCs from TRT patients exhibited higher levels of pentose phosphate pathway metabolites, glutathione, and oxidized purines (eg, hypoxanthine), suggestive of increased activation of antioxidant pathways in this group. Further analyses indicated significant changes in free fatty acids and acyl‐carnitines in response to testosterone therapies. With regard to hemolysis, TRT was associated with enhanced susceptibility to osmotic hemolysis. Correlation analyses identified acyl‐carnitines as significant modifiers of RBC predisposition to osmotic and oxidative hemolysis.ConclusionsThese observations provide new insights into testosterone‐mediated changes in RBC metabolome and biology that may impact the storage capacity and posttransfusion efficacy of RBCs from TRT donors.
Early metformin treatment improves pancreatic function and prevents metabolic dysfunction in early overfeeding male rats at adulthood
Authors: Previate Carina , Malta Ananda , Miranda Rosiane Aparecida , Martins Isabela Peixoto , Pavanello Audrei , de Oliveira Júlio Cezar , Prates Kelly Valério , Alves Vander Silva , Francisco Flávio Andrade , Moreira Veridiana Mota , Matiusso Camila Cristina Ianoni , de Moraes Ana Maria Praxedes , Mathias Paulo Cezar de Freitas , Franco Claudinéia Conationi da Silva 
Published: October 2020

New Findings
What is the central question of this study?Studies reported the efficacy of metformin as a promising drug for preventing or treating of metabolic diseases. Nutrient stresses during neonatal life increase long‐term risk for cardiometabolic diseases. Can early metformin treatment prevent the malprogramming effects of early overfeeding?
What is the main finding and its importance?Neonatal metformin treatment prevented early overfeeding‐induced metabolic dysfunction in adult rats. Inhibition of early hyperinsulinaemia and adult hyperphagia might be associated with decreased metabolic disease risk in these animals. Therefore, interventions during infant development offer a key area for future research to identify potential strategies to prevent the long‐term metabolic diseases. We suggest that metformin is a potential tool for intervention.
AbstractGiven the need for studies investigating the possible long‐term effects of metformin use at crucial stages of development, and taking into account the concept of metabolic programming, the present work aimed to evaluate whether early metformin treatment might program rats to resist the development of adult metabolic dysfunctions caused by overnutrition during the neonatal suckling phase. Wistar rats raised in small litters (SLs, three pups per dam) and normal litters (NLs, nine pups per dam) were used as models of early overfeeding and normal feeding, respectively. During the first 12 days of suckling, animals from SL and NL groups received metformin, whereas the controls received saline injections. Food intake and body weight were monitored from weaning until 90 days of age, when biometric and biochemical parameters were assessed. The metformin treatment decreased insulin concentrations in pups from SL groups, and as adults, these animals showed improvements in glucose tolerance, insulin sensitivity, body weight gain, white fat pad stores and food intake. Low‐glucose insulinotrophic effects were observed in pancreatic islets from both NL and SL groups. These results indicate that early postnatal treatment with metformin inhibits early overfeeding‐induced metabolic dysfunctions in adult rats.
Creatine supplementation attenuates the rate of fatigue development during intermittent isometric exercise performed above end‐test torque
Authors: Abdalla Leonardo Henrique Perinotto , Broxterman Ryan Michael , Greco Camila Coelho , Denadai Benedito Sérgio 
Published: October 2020

New Findings
What is the central question of this study?Does creatine supplementation augment the total torque impulse accumulated above end‐test torque (IET) during severe‐intensity knee‐extensor exercise by attenuating the rate of decrease in peak potentiated twitch torque (PT)?
What is the main finding and its importance?Creatine augmented the IET and attenuated the rate of decrease in both voluntary activation and PT during severe‐intensity exercise. The IET was related to the rate of decrease in PT. These findings reveal an important role for the rates of neuromuscular fatigue development as key determinants of exercise tolerance within the severe domain.
AbstractThis study investigated the effect of creatine supplementation on exercise tolerance, total torque impulse accumulated above end‐test torque (total IET) and neuromuscular fatigue development of the knee extensors during severe‐intensity intermittent isometric exercise. Sixteen men were randomly allocated into Creatine (n = 8, 20 g day−1 for 5 days) or Placebo (n = 8) groups and performed knee‐extensor maximal voluntary contraction (MVC) testing, all‐out testing to determine end‐test torque (ET) and the finite torque impulse accumulated above end‐test torque (IETʹ), and three submaximal tests at ET + 10%: (i) time to task failure without supplementation (Baseline); (ii) time to task failure after creatine or placebo supplementation; and (iii) time matched to Baseline after creatine (Creatine‐Isotime) or placebo (Placebo‐Isotime) supplementation. Creatine supplementation significantly increased the time to task failure (Baseline = 572 ± 144 s versus Creatine = 833 ± 221 s) and total IET (Baseline = 5761 ± 1710 N m s versus Creatine = 7878 ± 1903 N m s), but there were no significant differences within the Placebo group. The percentage change pre‐ to postexercise in MVC, voluntary activation, peak potentiated twitch torque and integrated EMG during MVC were not significantly different between Baseline and Creatine but were all significantly attenuated in Creatine‐Isotime compared with Baseline. There were no significant differences in these variables within the placebo group. The total IET was significantly correlated with the rates of change in potentiated twitch torque peak (r = 0.83–0.87) and rate of torque development (r = −0.83 to −0.87) for the submaximal tests to task failure. These findings reveal an important role for the rates of neuromuscular fatigue development as key determinants of exercise tolerance during severe‐intensity intermittent isometric exercise.
Study on Breakdown Features and Characteristics of Film at the Corrugated Plate Corner
Authors: Wang Bo , Chen Bowen , Ke Bingzheng , Li Ru , Wang Gongqing , Tian Ruifeng , Lu Chuan 
Published: October 2020

Abstract
Corrugated plate dryer is a extremely vital equipment for steam-water separation in the fields of heat transfer and nuclear engineering. The corrugated plate is also a commonly used steam-water separator in steam generators in nuclear power plants. It is meaningful to study the breakdown characteristics and mechanism of the water film on corrugated plate wall. Water film thickness of steady flow is measured based on plane laser induced fluorescence (PLIF) technique and time series and its fitted equation of water film thickness are obtained, respectively. Besides, fluctuation characteristics of water film are analyzed by probability density function (PDF). Based on the dimensionless approach, the water film breakdown model at the corner of the corrugated plate is established. And the calculation equation of the relative position of the water film breakdown at the corner is deprived. The specific conclusions are as follows. The theoretical equation agrees well with the relative position of the water film breakdown at the corrugated plate corner. The evolution of the surface wave of water film is carried out in time and space. The PDF curve have no significant peak characteristics. Therefore, the spectrum has no characteristic frequency, that is, the water film has multi-frequency characteristics. Gravity of water film can be ignored in the water film model. The thickness sequences for falling film is measured and fitted. The two-dimensional model of water film breakdown at the corner is set up. The equation for the film thickness when the water film is just ruptured is obtained. Relative position of the water film rupture at the corner of the corrugated plate is theoretically related only to the structural parameters of the corrugated plate, the parameters of the gas phase and the liquid phase, and the Reynolds number of the liquid film. However, in the low Reynolds number region, the airflow velocity is extremely large, which causes certain fluctuations and nonlinear characteristics of the water film boundary position. Therefore, the theoretical formula is not particularly good at predicting the relative position of the breakdown in this region. I think that this nonlinear feature has obvious chaotic characteristics. The study of the chaotic characteristics generated by shearing the liquid film by high velocity flow airflow at the corner of the corrugated plate may become a prospect for future research.
A New Safety Margin Evaluation Method: Quality Margin Method
Authors: Minfu Zhao , Minghui Duan , Yufeng Lv 
Published: October 2020

Abstract
Departure from nucleate boiling (DNB) may occur in the process of reactor accident. The departure from nucleate boiling (DNB) design basis is one of the most important bases for reactor core thermo-hydraulic design. In order to evaluate whether the DNB design basis meets the demand of thermal hydraulic design, the departure from nucleate boiling ratio (DNBR) should be calculated. The traditional DNBR calculation method is the direct substitution method (DSM). However, the research has pointed out that the DSM was inaccurate and non-conservative to represent the real safety margin. There is also a modified DNBR method by combining with the heat balance equation, which was called heat balance condition method (HBM). The essence of both DNBR methods is to evaluate the reactor safety margin by the difference between the heat fluxes of the actual condition and the critical condition. So the critical heat flux (CHF) value needs to be measured by CHF tests in actual condition parameters, which results in high heating power. To avoid this deficiency of DNBR methods, a new safety margin evaluation method has been developed in the research, which was called quality margin method. In this method, the safety margin of the reactor was evaluated by the difference between the critical quality and the actual quality. The method required lower test power, so greatly decreased the difficulty and cost of CHF experiments.
Reforms and Innovations in a Nuclear Engineering Course: Nuclear Power Plant Systems and Equipment
Authors: Huang Shanfang , Wang Jiageng , Hao Yisheng , Liu Guodong , Liu Minyun , Ma Yugao 
Published: October 2020

Abstract
The Fukushima nuclear accident in Japan caused a significant impact on the nuclear power industry and public attitudes towards nuclear energy. The decreased public acceptance and the regulatory authorities’ stricter requirements of nuclear safety lead to the popularity of advanced safety technologies in scientific research and engineering projects. The demand for highly qualified human resources increases by the gradual recovery of the nuclear power field in China. In order to meet this demand, a series of course innovations are taken at Tsinghua University. Focusing on the course “Nuclear Power Plant Systems and Equipment,” the paper discusses the innovations of the course stimulated by the current industry trends and demands.
A brief introduction to the special commissioned-student program at Tsinghua University is given. The paper investigates the meaning and function of the course in the frame of the curriculum plan for nuclear engineering students at Tsinghua University. The personal career plan, the industry outlook, and even the public attitudes contribute to senior students’ attitudes and demands for the course, which is tied closely to the effect of teaching. The paper addresses that the objective of the innovations is to develop a course fixing different students’ demands and help them build their ability to solve practical engineering problems in their future professional careers. The selection of teaching contents and the teaching strategy are discussed. This course takes Westinghouse AP1000 as the major point. And the nuclear power plant systems are taught in a divided way. One is the operation system, and the other is the safety system. This separation is based on the different functions and roles of these two parts and could have advantages in teaching effect. The paper explains the critical points of the systems and innovations of how to deal with course difficulties. There is a corresponding part of the safety system, and this part gets more challenges due to the industry trends. Lectures, group discussions, homework, and presentation projects are discussed. Besides, the paper considers possible efforts for further development of nuclear engineering courses.
Public Engagement of Nuclear Energy in China: The Characteristics of Public Knowledge, Risk Perception, Trust Perception and Environmental Concern
Authors: Oforiwaa Priscilla Obeng , Chao Zhang , Manchun Liang , Guofeng Su , Jiahao Wang 
Published: October 2020

Abstract
Nuclear energy has been regarded as a controversial energy option to reduce carbon emissions, alleviate global warming and build a low-carbon society due to the public perception of nuclear energy. Public perception and acceptance are vital to the development of nuclear energy. However, the public has many misunderstandings and misconceptions about nuclear energy. To change the way that the public view nuclear energy, this paper attempts to build an engagement model that shifts from a oneway information transfer with a focus on changing people’s minds in a single interaction, to a two-way dialogue rooted in listening, respect, and building long-term relationships that would shift understanding on a scientific issue over time. Based on a survey conducted on residents in China, we offer a research hypothesis that describes the connection between public engagement, public knowledge, perceived risk, perceived trust and environmental concern. This study indicated that public knowledge is positively related to environmental concern and public engagement but not significantly related to perceived risks. Meanwhile, this study also demonstrated the positive effect of environmental concern, perceived trust on public engagement. Centered on the results, we make corresponding policy to increase public engagement.
Corrosion of High Temperature Alloys in the Primary Coolant of HTGR Under Very-High Temperature Operation
Authors: Wang Qiuhao , Zheng Wei , Yin Huaqiang , Li Shengqiang , He Xuedong , Ma Tao 
Published: October 2020

Abstract
The primary coolant loop of the high temperature gas-cooled reactor contains trace impurities that could cause some corrosion to the materials. When the HTGR operates at a very high temperature, the impurities in the coolant have significant influence on the properties of the alloys used in steam generators. Corrosion tests were conducted on the Inconel 800H, Inconel 617 and Hastelloy X, and the alloys are commonly used in the steam generator of HTGR. They were corroded for up to 48 hours at 950 °C in a given helium atmosphere with trace impurities, and the corrosion results were observed. The SEM with EDX system was utilized for the metallographic examination and surface oxide composition analysis. The AES was used to verify the EDS analysis results. Due to severe internal oxidation and surface carbon transfer, Inconel 800H has the worst corrosion resistance, but Hastelloy X with the dense oxide layer has the best corrosion resistance. For Inconel617, the Cr element depletion occurs near the corrosion layer, which is very consistent with the theory. Since a certain amount of manganese in Hastelloy X may contribute to the formation of a dense oxide layer, thus an appropriate increase of the manganese content may enhance the alloy’s corrosion resistance.
Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors: Kinetic Study of Boron Carbide-Stainless Steel Eutectic Melting by Differential Thermal Analysis
Authors: Kikuchi Shin , Yamano Hidemasa , Nakamura Kinya 
Published: October 2020

Abstract
In a postulated severe accidental condition of sodium-cooled fast reactor (SFR), eutectic melting between boron carbide (B4C) as control rod element and stainless steel (SS) as control rod cladding or related structure may take place. Thus, kinetic behavior of B4C-SS eutectic melting is one of the important phenomena to be considered when evaluating the core disruptive accidents in SFR.
In this study, for the first step to obtain the fundamental information on kinetic feature of B4C-SS eutectic melting and compare the pervious findings, the thermal analysis using the pellet type samples of B4C and Type 316L SS as different experimental technique was performed up to 1773 K at different heating rates of 2.5–10 K/min. The differential thermal analysis (DTA) endothermic peaks for the B4C-SS eutectic melting appeared from 1483K to 1534K and systematically shifted to higher temperatures when increasing heating rate. Based on this kinetic feature, apparent activation energy and pre-exponential factor for the B4C-SS eutectic melting were determined by Kissinger method. It was found that the kinetic parameters obtained by thermal analysis were comparable to the literature values of thinning experiment at high temperatures.
In addition, the microstructure and element distribution formed in the interdiffusion layer composed of the B4C / SS system were analyzed by the electron probe microanalyzer (EPMA), which can provide key validation data on elemental interdiffusion behavior in the early stage of the eutectic melting.
Study on Methodology and Application of Seismic-Induced Flood Level 2 PSA for PWR in China
Authors: Yu Liu , Wenjing Li , Yun Yu 
Published: October 2020

Abstract
Level 2 (L2) PSA is focused on the severe accident phenomenon, progression and source terms release to generally evaluate the containment response after core damage takes place. Fukushima accident was caused by seismic and tsunami which are beyond design basis. It indicates that evaluating the risk for extremely external hazards is vitally important. Therefore, how to perform the study on L2 PSA for external events (especially seismic and flood) has become a crucial problem needed to be considered deeply for both regulators and operators. In this paper, the methodology of flood and seismic-induced flood L2 PSA was developed and applied for a Gen III NPP in China. The key factors include:
(1) Focusing on crucial elements of L2 PSA in view of seismic and flood characteristics, including PSA interfaces, design features, severe accident phenomenon and progression, containment performance analysis, etc.
(2) Building integrated internal flood and seismic L2 PSA models.
(3) Developing an analytical method to evaluate seismic-induced flood L2 PSA.
IHSI Effectiveness for Crack Propagation Observed at Hamaoka PLR Piping
Authors: Yuya Hideki , Yamada Kouji , Sasayama Takao 
Published: October 2020

Abstract
Indications of Ultrasonic Testing (UT) of 4 weld joints in Primary Loop Recirculation (PLR) piping in Hamaoka unit-2 had been identified during the 20th outage (2004). Metallurgical investigation after cutting from 2 weld joins had been conducted because of its accessibility etc. The 4 weld joins had been welded at the plant construction (1978), operated and IHSI (Induction Heat Stress Improvement) had been performed during the 1st outage (1979). 25 years passed by until the metallurgical investigation. As a result of the investigation, crack growth retardation by the IHSI was confirmed since crack tip was round and plastically deformed.
Demonstration of Multi-Physics Evaluation of Fuel Rod Burst Probability With Burnup Extension Under LBLOCA Conditions
Authors: Zhang Hongbin , Blakely Cole , Yu Jianguo 
Published: October 2020

Abstract
Extending the fuel discharge burnup level, e.g., from the current limit of rod averaged discharge burnup limit of 62 GWD/MT to a proposed new limit of 75 GWD/MT, can provide significant economic benefits to the current fleet of operating light water reactors (LWRs). It allows for longer operating cycles and improved resource utilization. The major economic gain of longer operating cycles is attributable to the increased capacity factor resulting from decreased refueling time as a fraction of total operating time, as well as fewer assemblies to be discharged for a given amount of energy produced. The main licensing challenges for higher burnup fuel are to ensure fuel rod safety under design basis accident conditions, especially under large-break loss-of-coolant accident (LBLOCA) and reactivity insertion accident (RIA). In this work, two-year cycle core design for a typical 4-loop pressurized water reactor (PWR) is performed with enrichment increased up to 6% and burnup extended to 75 GWD/MT. The fuel rod burst potential evaluations under large-break loss-of-coolant accident (LBLOCA) conditions are subsequently performed using the multi-physics best estimate plus uncertainty analysis framework LOTUS (LOCA Toolkit for the U.S. LWRs) and the preliminary results are presented.
Periodic Tests Improvement of Emergency Diesel Generator Units in Nuclear Power Plant
Authors: Fei Liu 
Published: October 2020

Abstract
Domestic diesel-generator units of M310 reactor nuclear power plants at present adopt the French standard RCC-E 2005 emergency for periodic tests. During low-power periodic tests, the diesel-generators are not adequately protected, and there is a risk of serious damage to equipment. This article analyzes in detail the provisions of the IEEE 387 standard for the periodic tests of emergency diesel-generator unit, improves the periodic tests of the emergency diesel-generator unit according to the IEEE 387 standard, cancels the original low-power tests, and uses the test during the normal operation of the unit in order to solve this problem. The grid-connected test method and detailed analysis of the improved test content make the EDG periodic test method more economical and safe. The improvement has been approved by the nuclear safety regulatory agency, which provides an important reference for the related periodic test improvement of nuclear power plants.