bluuebunny/crossref_metadata_2025_split huggingface dataset:
Macro‐micro imaging of cardiac–neural circuits in co‐cultures from normal and diseased hearts
Authors: Bub Gil , Burton Rebecca‐Ann B. 
Published: November 2014

AbstractThe autonomic nervous system plays an important role in the modulation of normal cardiac rhythm, but is also implicated in modulating the heart's susceptibility to re‐entrant ventricular and atrial arrhythmias. The mechanisms by which the autonomic nervous system is pro‐arrhythmic or anti‐arrhythmic is multifaceted and varies for different types of arrhythmia and their cardiac substrates. Despite decades of research in this area, fundamental questions related to how neuron density and spatial organization modulate cardiac wave dynamics remain unanswered. These questions may be ill‐posed in intact tissues where the activity of individual cells is often experimentally inaccessible. Development of simplified biological models that would allow us to better understand the influence of neural activation on cardiac activity can be beneficial. This Symposium Review summarizes the development of in vitro cardiomyocyte cell culture models of re‐entrant activity, as well as challenges associated with extending these models to include the effects of neural activation.
Power Cycles of Generation III and III+ Nuclear Power Plants
Authors: Dragunov Alexey , Saltanov Eugene , Pioro Igor , Kirillov Pavel , Duffey Romney 
Published: November 2014

It is well known that the electrical-power generation is the key factor for advances in any other industries, agriculture and level of living. In general, electrical energy can be generated by: 1) non-renewable-energy sources such as coal, natural gas, oil, and nuclear; and 2) renewable-energy sources such as hydro, wind, solar, biomass, geothermal and marine. However, the main sources for electrical-energy generation are: 1) thermal - primary coal and secondary natural gas; 2) “large” hydro and 3) nuclear. The rest of the energy sources might have visible impact just in some countries.
Modern advanced thermal power plants have reached very high thermal efficiencies (55–62%). In spite of that they are still the largest emitters of carbon dioxide into atmosphere. Due to that, reliable non-fossil-fuel energy generation, such as nuclear power, becomes more and more attractive. However, current Nuclear Power Plants (NPPs) are way behind by thermal efficiency (30–42%) compared to that of advanced thermal power plants. Therefore, it is important to consider various ways to enhance thermal efficiency of NPPs.
The paper presents comparison of thermodynamic cycles and layouts of modern NPPs and discusses ways to improve their thermal efficiencies.
Separation of Nuclides by Different Types of Zeolites in the Presence of Boric Acid
Authors: Fujita Natsuki , Mimura Hitoshi , Kobayashi Takaaki , Sekino Kazuyuki , Nagamine Kunitaka 
Published: November 2014

The development of selective adsorbents has become very important for the effective multi-nuclide decontamination. In this study, the selective adsorption properties of 26 nuclides for different types of zeolites (A, L, natural mordenite (NM), Ag-NM) were examined in the presence of boric acid.
The batch adsorption experiments were carried out using four kinds of test solutions containing boric acid and calcium hydroxide; (1)DW (distilled water) + H3BO4: 3,000 ppm + LiOH: 10 ppb, (2)DW + Ca(OH)2: 500 ppm + H3BO4: 3,000 ppm + LiOH: 10 ppb, (3)Seawater (30% diluted) + H3BO4: 3,000 ppm, (4)Seawater + H3BO4: 3,000ppm. The uptake (%) of Sr2+ for zeolite A (A-51J), Cs+ for natural mordenite (NM, 2460#, Ayashi, Sendai), and I− for Ag-NM was determined under the following conditions; Concentration of Sr2+, Cs+ and I− ions: 10 ppm, V/m = 100 cm3/g, 25°C, 24 h. The uptake (%) of Sr2+, Cs+ and I− ions was estimated to be above 90%, while tended to decrease in the presence of seawater. Especially, the uptake (%) of I− ions for Ag-NM markedly decreased in the presence of seawater.
As for the zeolites A and L, the uptake (%) of 26 elements was determined by using two kinds of test solutions; (1)DW (distilled water) + H3BO4: 3,000 ppm + LiOH: 10 ppb + 26 nuclides: 10 ppm, (2)Seawater (30% diluted) + H3BO4: 3,000 ppm + 26 nuclides: 10 ppm.
Zeolite A has relatively large uptake percentage for Sr, Co, Ni and Zn, and zeolite L has high adsorbability to lanthanoid group of Eu, Ce and Pr. The increase in pH led to the enhancement of uptake (%), while the hydrolysis of metal ions should be also considered. The multi-nuclides separation is thus expected by considering the difference in uptake properties of zeolite A, L and natural mordenite.
Selective Uptake of Sr and Stable Solidification Using Potassium Titanates
Authors: Kanda Hitoshi , Mimura Hitoshi , Niibori Yuichi , Iwasaki Mamoru , Mori Koichi , Itoi Nobuki , Goto Toshiki 
Published: November 2014

The development of selective adsorbents for radioactive Sr ions is one of the most important subjects for the safety decontamination in Fukushima NPP-1[1]. In this study, the selective adsorption properties of Sr, characterization and stable solidification were clarified by using the novel adsorbent of potassium titanates (KT-1).
The adsorption properties of Sr2+ ions for original and calcined specimens were examined by batch method under the following conditions; V/m = 100 cm3/g, Mixed solution: 10,000 ppm Na+, 10 ppm Cs+, 10 ppm Ca2+, 1 ppm Mg2+ and 1 ppm Sr2+, 85Sr tracer: 5,000 cpm/cm3, centrifugation: 2,500 rpm, 25°C, shaking time: 1∼24 h, calcination temp.: 300∼900°C. Relatively large uptake percentage above 90% was obtained for the original and calcined specimens below 800°C, while the Sr uptake for calcined specimens above 900°C was lowered due to the thermal decomposition of K2Ti2O5·xH2O.
The Sr distribution in the column was examined by flowing the mixed solution through the columns packed with KT-1. The Sr distribution profiles were obtained by the measurement of γ-activity in the column at 5 mm intervals. In either case, no breakthrough of Sr was observed. The distribution profile tended to smooth with increasing flow rate; Sr adsorption band and flow rate have a linear relationship.
The leachability of Sr for the solid forms was further examined under the following leaching conditions; leachant: pure water and 1 M HCl; leachant temp.: 25°C and 90°C, leaching period: 4 weeks; calcining temp.: 500∼1,100°C. The leached percentage of Sr in pure water was less than the detection limit of ICP-AES, and that in 0.1 M HCl tended to markedly decrease with calcining temperature; the formation of SrTiO3 phase above 800°C was effective for the lowering of leachability.
The novel adsorbent of KT-1 is thus effective for the selective decontamination and stable solidification of Sr in Fukushima NPP-1.
Transient Analysis of CP300 Based on RELAP5/MOD3.4
Authors: Liu Jianchang , Nina Yue , Xie Xu , Ducheng Sun , Tian Wenxi , Su Guanghui , Qiu Suizheng 
Published: November 2014

The thermal-hydraulic characteristics of Nuclear Power Plant (NPP) during Steam Generator Tube Rupture (SGTR) accident are of great concern. In this paper, the thermal-hydraulic characteristics of CP300 during SGTR accident with no operator actionsduring the first 30 min are investigated using the best estimate RELAP5/MOD3.4.
Modeling and nodalization of CP300 was executed, including the vessel, pumps, pressurizer, steam generations and necessary auxiliary systems. Some main transient parameters were obtained, such as Reactor Coolant Pump (RCP) coolant temperature and pressure, steam generator flow rate and pressure. The calculation results gives the sequences of the NPP during the SGTR as described below. As the tube rupture occurs, the primary pressure drops and secondary pressure increases. When the primary pressure drops down to the set-point of the scram, the control rods drop down and the power of the NPP begins to decrease, causing the primary coolant temperature to decrease. The primary pressure continues to drop. When it drops down to 10.78MPa, the High pressure Safety Injection System is put into operation and the accident is mitigated, even without operator’s actions.
In conclusion, the calculated results indicate that the key thermal hydraulic parameters of CP300 during the SGTR accident are in acceptable ranges and the accident is effectively controlled.
CFD Analysis of the Flow in Crud-Coated Nuclear Rod Bundles
Authors: Cinosi Nicolas , Walker Simon P. , Bluck Mike , Issa Raad I. 
Published: November 2014

This paper presents a methodology to assess the effects of crud surface roughnesses on the normal operation of a PWR reactor.
A CFD methodology based on the use of RANS models and the implementation of roughness embedded in STAR-CCM+ CFD code has been developed and applied.
A typical PWR reactor case is investigated in details.
Results show how the presence of crudded rough rods induces a modification of the flow distribution as compared to the ideal case with clean smooth rods.
Notably, these modifications reflect a reduction of the mass flow rate, which in turn has a deteriorating consequence on the efficiency of the fuel-to-coolant heat transfer.
Study on a Small Power Reactor With Compact Pressure Vessel and Natural Circulation
Authors: Takiwaki Kenya , Sakurai Shungo , Takeuchi Yutaka , Yamamoto Yasushi 
Published: November 2014

There is movement which is developing the small reactor for the small electricity grid in place of a big power reactor which requires the high capital cost. This paper introduces a small power reactor whose purpose is to achieve high economic competitiveness and advanced safety. In order to attain high economic competitiveness, it is designed to be small and simple and uses natural circulation and high pressure. A steam generator is integrated into the reactor pressure vessel (RPV), thus dispensing with a primary system and preventing radiation leakage from the reactor core. The small core is designed to have a high power density (100 MW/m3, almost twice that of a conventional boiling water reactor). The concept of a 300 MWt (100 MWe) core design is established by introducing a boiling heat transfer system. By boiling cooling water, the cooling-water circulating flow quantity in a reactor core is enlarged.
By increasing a flow, the minimum critical power ratio is improved, which is an important core characteristic. Furthermore, using a burnable poison (Gd2O3), the excess reactivity of a reactor core is reduced and excess reactivity is controlled only by the control rod.
Moreover, the maximum linear power density is improved and the critical power ratio is minimized by optimizing the burnable poison arrangement and the control rod pattern.
In order to attain high safety, our small reactor has an advanced decay heat removal system that can cool the core without external support. This decay heat removal system is part of the secondary cooling system and combined with a cooling tower. As a result, the quantity of cooling water stored in the decay heat removal system is reduced, and longtime decay heat removal is possible by small equipment.
Advancement of Reactor Coolant Pump (RCP) Performance Verification Test in KAERI
Authors: Cho Yun-Je , Kim Yeon-Sik , Cho Seok , Kim Seok , Bae Byoung-Uhn , Chung Heung-June , Youn Young-Jung , Park Jong-Kuk , Choi Hae-Seob , Jeon Woo-Jin , Kim Bok-Deuk , Kwon Tae-Soon , Song Chul-Hwa 
Published: November 2014

Korea Atomic Energy Research Institute (KAERI) has designed and constructed a test facility for reactor coolant pumps (RCPs). The RCP Test Facility (RCPTF) has the capability to test a RCP under the operation condition of an Advanced Power Reactor 1400 MW (APR1400). The design values of the facility are 17.2 MPa, 343 °C, 11.7 m3/s, and 13 MW in maximum pressure, temperature, flow rate, and electrical power, respectively. In the facility, it is possible to perform a type test for a newly-developed RCP as well as a production test for a RCP before its installation in a nuclear power plant. For the production test, H-Q curves under the cold and hot conditions are acquired. For the type test, various transient tests are additionally performed including four types of seal transient tests, a thrust bearing transient test, a cost down test, and so on.
To acquire H-Q curves of a RCP, the flow rate should be controlled by varying the flow resistance in the test loop. The RCPTF uses a Variable Restriction Orifice (VRO) whose flow area can be controlled by moving the two orifice plates installed in-parallel. The need for flow control valves and bypass lines was eliminated using the VRO such that the flow disturbance was minimized. The flow rate in the main loop of the RCPTF is measured by a standard venture flow meter. The flow rate in the RCPTF is very high and thus the venture flow meter could not be calibrated in the entire range of Reynolds number corresponding to the operating condition in the APR1400. The calibration was conducted at the Colorado Experiment Engineering Station Inc. (CEESI) in the USA where natural gas is used for a working fluid. If a discharge coefficient calibrated with the gas is applied in the test results performed using the water as a working fluid, a discrepancy can occur due to the static hole error. Therefore, the static hole error was compensated in the test results and the result shows the improvement.
The effect of the temperature on the pressure pulsation amplitude was also evaluated. During a cold performance test and heat-up phase to the condition of a hot performance test, an abnormal increase in the pressure pulsation amplitude was observed near the specific temperature range. This is acoustic resonance phenomena that occur when a blade passing frequency of the RCP is proportional to the harmonic resonance frequency of the RCPTF.
Decommissioning of Obsolete Nuclear Facilities in the UJV Rez, a. s.
Authors: Tous Milan , Podlaha Josef 
Published: November 2014

More than 55 years of activities in the company UJV Rez, a. s. (Nuclear Research Institute Rez a.s. in the past) which is a leading institution in all areas of nuclear R&D in the Czech Republic and had a dominant position in the nuclear program since it was established (1955), there are several obsolete nuclear facilities that shall be decommissioned.
The total amount of radioactive waste (RAW) resulting from decommissioning for the next processing will be ∼ 1500 m3 and the expected amount RAW for releasing into the environment is 240 tons after the decontamination. For the RAW processing several decontamination methods such as high press water jetting, chemical treating in ultrasonic bath, dry ice blasting and abrasive blasting were performed.
Decommissioning started in 2003 and will be finished in 2016. This decommissioning of nuclear facilities in UJV is the only ongoing decommissioning project in the Czech Republic.
Security Informed Safety Assessment of NPP I&C Systems: GAP-IMECA Technique
Authors: Kharchenko Vyacheslav S. , Illiashenko Oleg A. , Kovalenko Andriy A. , Sklyar Vladimir V. , Boyarchuk Artem V. 
Published: November 2014

The application of complex electronic components such as systems-on-chips (including systems-on-programmable-chips using field programmable gate arrays (FPGAs)) in industrial instrumentation and control systems (I&Cs) causes risks for ensuring of safety. Nuclear power plant (NPP) I&C projects on FPGA are complex solutions which include both software and hardware components.
Information security (system’s ability to protect the information and data from unauthorized access and modification) is a subordinate property with respect to safety of many I&Cs, primarily to the NPP reactor trip systems. Such hierarchy may be taken into account by implementation of security informed safety (SIS) approach.
Recent events like Stuxnet or Duqu showed vulnerabilities in industrial embedded IT-Systems. In order to remove or reduce security risks, which could increase overall safety risk, the holistic analytical technique are necessary.
The goal of the paper is to present the technique for of SIS-based assessment of the NPP I&C systems. The proposed SIS-oriented method of NPP I&C systems assessment includes the models and techniques.
To decrease the risk of manual errors, the tool for the SIS-oriented assessment automation is described. The tool is based on joint use of abovementioned models and techniques, is proposed.
The tool allows conducting the joint use of the following analysis techniques: GAP and IMECA.
Nearly Complete Genome Sequence of Curionopolis Virus, a
Culicoides
-Related Rhabdovirus Isolated in the Brazilian Amazon Region
Authors: Medeiros Daniele Barbosa de Almeida , Diniz Júnior José Antonio P. , Cardoso Jedson F. , Silva Sandro Patroca , da Silva Daisy Elaine Andrade , de Oliveira Layanna F. , é Vasconcelos Janaina M. , Chiang Jannifer O. , Dias Amarilis Aragão , Nunes Márcio R. T. , Vianez Júnior João Lídio da S. G. , Vasconcelos Pedro F. C. 
Published: November 2014

ABSTRACT

We report here the first nearly complete genome sequence related to curionopolis virus (CURV), that of strain AR440009, isolated from a pool of
Culicoides
sp. midges in Serra Norte, Pará State, northern Brazil. All genes showed similarities to those belonging to members of the family
Rhabdoviridae
.
Draft Genome Sequence of
Microvirga
sp. Strain BSC39, Isolated from Biological Soil Crust of Moab, Utah
Authors: Bailey Alexis C. , Kellom Matthew , Poret-Peterson Amisha T. , Noonan Kathryn , Hartnett Hilairy E. , Raymond Jason 
Published: November 2014

ABSTRACT

Microvirga
sp. BSC39 was isolated from a biological soil crust near Moab, Utah. The strain appears to be capable of chemotaxis and exopolysaccharide synthesis for biofilm adhesion. The BSC39 genome contains iron siderophore uptake and hydrolysis enzymes; however, it lacks siderophore synthesis pathways, suggesting the uptake of siderophores produced by neighboring microbes.
Draft Genome Sequence of
Massilia
sp. Strain BSC265, Isolated from Biological Soil Crust of Moab, Utah
Authors: Bailey Alexis C. , Kellom Matthew , Poret-Peterson Amisha T. , Noonan Kathryn , Hartnett Hilairy E. , Raymond Jason 
Published: November 2014

ABSTRACT

Massilia
sp. BSC265 was isolated from a biological soil crust near Moab, Utah. The strain appears to be capable of chemotaxis and exopolysaccharide synthesis for biofilm adhesion. The BSC265 genome contains a complete dissimilatory nitrate reduction pathway as well as a TCA cycle, making it a facultative anaerobe.
Cardiovascular evaluation of middle-aged individuals engaged in high-intensity sport activities: implications for workload, yield and economic costs
Authors: Menafoglio Andrea , Di Valentino Marcello , Porretta Alessandra Pia , Foglia Pietro , Segatto Jeanne-Marie , Siragusa Patrick , Pezzoli Reto , Maggi Mattia , Romano Gian Antonio , Moschovitis Giorgio , Gallino Augusto 
Published: November 2014

BackgroundThe European Association of Cardiovascular Prevention and Rehabilitation (EACPR) recommends cardiovascular evaluation of middle-aged individuals engaged in sport activities. However, very few data exist concerning the impact of such position stand. We assessed the implications on workload, yield and economic costs of this preventive strategy.MethodsIndividuals aged 35–65 years engaged in high-intensity sports were examined following the EACPR protocol. Athletes with abnormal findings or considered at high-cardiovascular risk underwent additional examinations. The costs of the overall evaluation until diagnosis were calculated according to Swiss medical rates.Results785 athletes (73% males, 46.8±7.3 years) were enrolled over a 13-month period. Among them, 14.3% required additional examinations: 5.1% because of abnormal ECG, 4.7% due to physical examination, 4.1% because of high-cardiovascular risk and 1.6% due to medical history. A new cardiovascular abnormality was established in 2.8% of athletes, severe hypercholesterolaemia in 1% and type 2 diabetes in 0.1%. Three (0.4%) athletes were considered ineligible for high-intensity sports, all of them discovered through an abnormal ECG. No athlete was diagnosed with significant coronary artery disease on the basis of a high-risk profile or an exercise ECG. The cost was US$199 per athlete and US$5052 per new finding.ConclusionsCardiovascular evaluation of middle-aged athletes detected a new cardiovascular abnormality in about 3% of participants and a high-cardiovascular risk profile in about 4%. Some of these warranted exclusion of the athlete from high-intensity sport. The overall evaluation seems to be feasible at reasonable costs.
Ibritumomab consolidation after 3 cycles of CHOP plus radiotherapy in high-risk limited-stage aggressive B-cell lymphoma: SWOG S0313
Authors: Persky Daniel O. , Miller Thomas P. , Unger Joseph M. , Spier Catherine M. , Puvvada Soham , Stea B. Dino , Press Oliver W. , Constine Louis S. , Barton Kevin P. , Friedberg Jonathan W. , LeBlanc Michael , Fisher Richard I. 
Published: November 2014

Key PointsLimited-stage diffuse large B-cell lymphoma has good outcomes with CHOP followed by radiotherapy but has a pattern of continuous relapses. Adding radioimmunotherapy consolidation results in outcomes that are at least as good as with rituximab added to CHOP and radiotherapy.
von Willebrand factor is a cofactor in complement regulation
Authors: Feng Shuju , Liang Xiaowen , Kroll Michael H. , Chung Dominic W. , Afshar-Kharghan Vahid 
Published: November 2014

Key PointsNormal plasma VWF multimers act as a cofactor in the factor I–mediated cleavage of C3b to iC3b and inhibit complement activation. Large VWF multimers, including ultra-large VWF multimers, do not have factor I cofactor activity and permit complement activation.
Fungal transformation of androsta-1,4-diene-3,17-dione by Aspergillus brasiliensis
Authors: Hosseinabadi Tahereh , Vahidi Hossein , Nickavar Bahman , Kobarfard Farzad 
Published: November 2014

Abstract

Background
The biotransformation of steroids by fungal biocatalysts has been recognized for many years. There are numerous fungi of the genus Aspergillu s which have been shown to transform different steroid substances. The possibility of using filamentous fungi Aspergillus brasiliensis cells in the biotransformation of androsta-1,4-diene-3,17-dione, was evaluated.

Methods
The fungal strain was inoculated into the transformation medium which supplemented with androstadienedione as a substrate and fermentation continued for 5 days. The metabolites were extracted and isolated by thin layer chromatography. The structures of these metabolites were elucidated using 1H-NMR, broadband decoupled 13C-NMR, EI Mass and IR spectroscopies.

Results
The fermentation yielded one reduced product: 17β-hydroxyandrost-1,4-dien-3-one and two hydroxylated metabolites: 11α-hydroxyandrost-1,4-diene-3,17-dione and 12β-hydroxyandrost-1,4-diene-3,17-dione.

Conclusions
The results obtained in this study show that A. brasiliendsis could be considered as a biocatalyst for producing important derivatives from androstadienedione.