bluuebunny/crossref_metadata_2025 huggingface dataset:
LBLOCA Analysis of CPR1000 NPP With Advanced Accumulator
Authors: Hu Hongwei , Shan Jianqiang , Gou Junli , Zhang Bo , Wang Haitao , Yang Zijiang
Published: February 2014

Large break LOCA (LBLOCA) is one of the limit design basic accidents in nuclear power plant. The large flow water in the advanced accumulator is injected into primary loop in early short time. When the vessel pressure drops and reactor core is re-flooded, the advanced accumulator provides a small injection flow to keep the reactor core in flooded condition. Thus, the startup grace time of the low pressure safety injection pump is extended, and the core still stays in a long-term cooling state. By deducing the original accumulator model in RELAP5 accident analysis code, a new model combining the advanced and the traditional accumulator is obtained and coupled into RELAP5/ MOD 3.3. Simulation results show that there is a large flow in the advanced accumulator at the initial stage. When the accumulator water level is lower than the stand pipe, a vortex appears in the damper, resulting in a large pressure drop and small flow. The phenomenon meets the demand of the advanced accumulator design and the simulation of the advanced accumulator is accomplished successfully. Based on this, the primary coolant loop cold leg double-ended guillotine break LBLOCA in CPR1000 is analyzed with the modified RELAP5 code. When the double ended cold leg guillotine accident with 200s delayed startup of the low pressure safety injection occurs, maximum cladding temperature in the core with traditional accumulator is 1860K which seriously exceeded the safety temperature (1477K)[1] prescribed limits while the maximum cladding temperature with advanced accumulator has the security temperature-1277K. From this point of view, adopting passive advanced accumulator can strive a longer grace time for LPSI. Thus the reliability, security and economy of reactor system were improved.
Study on SPMO Management of Contractor Special Process Personnel Qualification Under EPC Mode
Authors: Shen Hongwei , Sun Zhiyou , Shen Yang
Published: February 2014

Under the background of Sanmen AP1000 NPP Project, World’s First AP1000 Project, this article looks into SPMO management over contractor special process personnel qualification under EPC mode.

The project management mode is briefed and the theory basis of the study is discussed, in terms of nuclear safety regulation ASME NQA-1, HAF003 and industrial safety regulations, as well as quality management theory. Contractor special process personnel qualification is generally unmanageable, mainly resulting in negative chain quality problems, objective of the study aims at solving the problems and managerial dilemmas of contractor special process personnel qualification management on site.

Quality assurance system is maintained according to ASME NQA-1, and special process is implemented in compliance with the specification of special process control procedures developed for particular special processes, such as welding, NDE, painting, etc. Personnel training, authorization, certificate, operation experiences and pertinent requirements are specified in personnel qualification procedures. The method and process of special process personnel qualification management is created under SPMO quality assurance system, in the scope of SPMO management, while detailed and comprehensive classification of special process personnel qualification is defined with originality. On the basis of ingenious classification and management practice, the author summarizes a systematic management methodology of contractor special process personnel qualification under EPC mode. Classification management, standardized checklist implementation, and site surveillance are integrated for special process personnel management. Outstanding effect and performance are achieved by demonstrating the systematic management methodology, providing effective experience for follow-up AP1000 project which has significant meaning for enhancing contractor special process control and ensuring AP1000 construction quality.
Loss of Cooling Thermal Analysis for the Spent Fuel Pool of the Chinshan Nuclear Power Plant
Authors: Yuann Yng-Ruey , Chen Yen-Shu , Lin Ansheng
Published: February 2014

The Chinshan Nuclear Power Plant owned and operated by the Taiwan Power Company is a twin-unit BWR-4 plant. Unit 1 and unit 2 began their commercial operation in 1978 and 1979, respectively. Since commercial operation, all the fuels discharged from reactor core at each cycle are stored in the spent fuel pool (SFP). An engineering analysis is performed to predict the SFP water temperature and pool water level during a postulated loss of forced cooling accident. A full-core discharged loading is considered, and the fuel assemblies are moved to the SFP just after 7 days of cooling. The pool temperature and level are calculated using lumped energy and mass balances. Calculation results show that the water temperature reaches the saturation temperature at 9.4 hours after the onset of the accident, and the pool level drops to the top of the active fuels at 76.8 hours. After the pool level drops to the top of the active fuels, the cladding temperature increases dramatically because the convective heat transfer of steam is much weaker than that of liquid water. The peak cladding temperature after fuel uncovery is calculated by detailed CFD simulations, and the results show that the peak cladding temperature reaches 600°C in 3 hours and 1200°C in 9.5 hours after the fuels are uncovered. Additionally, the check-board arrangement for fuels is also investigated. Through enhanced the radiation heat transfer, the check-board fuel arrangement can have slower heating rate for the fuels. For the Chinshan SFP, extra 2.5 hours can be gained by employing such an arrangement for necessary actions.
Sustainable Progression of Technology Education for Atomic Energy Engineering in Tsuyama National College of Technology
Authors: Kobayashi T. , Kato M. , Sori H. , Sasai Y. , Sato M. , Inada T. , Harada K. , Okada T.
Published: February 2014

This study describes the achievements of a program that provides technology education about low-level radiation to develop practical core engineers. An education program starting at an early age and continuous and consistent educational agendas through seven years of college has been constructed in collaboration with regional organizations. Subjects relating to atomic energy or nuclear engineering were regrouped as “Subjects Related to Atomic Power Education” for most grades in each department. These subjects were included in the syllabus and the student guide book to emphasize a continuous and consistent policy throughout the seven-year period of college study, comprising the five-year system and the additional two-year advanced course. Furthermore, the content of lectures, experiments, and internships was enriched and realigned in collaboration with the Japan Atomic Energy Agency (JAEA), Okayama University, and Chugoku Electric Power Co., Inc. Additional educational materials were developed from inspection visits by teaching staff to atomic energy facilities were also used in the classes. Two student experiment textbooks were developed to promote two of the subjects related to atomic energy: “Cloud Chamber Experiment” and “A Test of γ-ray Inverse Square Law.” In addition to the expansion and rearrangement of atomic power education, research on atomic power conducted for graduation thesis projects was undertaken to enhance educational and research activities. Some examples are as follows: “Study on the Relation between γ Dose Rate and Rainfall in Northern Okayama Area,” “Remote Sensing of Radiation Dose Rate by Customizing an Autonomous Robot,” and “Nuclear Reaction Analysis for Composition Measurement of BN Thin Films.” It should be noted that an atomic-energy-related education working group has been in place officially to continue the above activities in the college since 2011. In consequence, although government subsidy has been decreasing, both human and material resources have been enhanced, and many students with a satisfactory understanding of atomic energy are being developed. This program was partially funded by the Ministry of Education, Culture, Sports, Science and Technology in Japan.
Proposal of the Estimation Equation of Flow Accelerated Corrosion Under Water-Steam Two-Phase Flow
Authors: Satake Masaaki , Yoneda Kimitoshi , Morita Ryo , Inada Fumio
Published: February 2014

Flow accelerated corrosion (FAC) is one of the pipe wall thinning phenomena. There are a few prediction equations for FAC under the two-phase flow condition, but their accuracy is uncertain. In this study, these equations are summarized. A new prediction equation is proposed, in which the liquid film velocity near the wall is taken into account. Also, FAC experiments with water-steam two-phase flow are performed. The thinning rate is predicted by calculation and compared with the experimental value.
Thermal Hydraulics Characteristics Simulation of CPR1000 Using CFD Method
Authors: Chao Yanmeng , Zhai Yujia , Yang Lixin , Zhang Mingqian , Duan Yuangang
Published: February 2014

The CPR1000 is built and operated by the China Guangdong Nuclear Power Company (CGNPC). The flow features are very complicated and asymmetrical in three dimensions. In this study, we calculated the completed model without symmetry simplification using CFD method. 3-dimensional, global and localized flow distributions of full vessel of CPR1000 PWR including top plenum, upper plenum, lower plenum and flow features under different working conditions for safety analyses have been obtained. Unsymmetrical flow field indicates the necessarily of intact vessel mode calculation and simplifications of guide tubes and core make it possible under the condition of our lab. Thermal hydraulics characteristics are obtained to give reference to safety operation under various operating conditions.
Microstructural Evolution of Self-Ion Irradiation HT9
Authors: Beckett Elizabeth , Hackett Micah , Jiao Zhijie , Sun Kai , Was Gary S.
Published: February 2014

Ferritic/martensitic steels are candidates for fast reactors because of their sodium compatibility, superior resistance to corrosion and radiation damage, including swelling, and excellent thermal conductivity and thermal expansion coefficient. One significant limitation of any cladding material is its susceptibility to swelling at high doses. While HT9 has neutron irradiation performance data up to ∼200 dpa, dose requirements for the Traveling Wave Reactor (TWR) may be much higher. Obtaining higher-dose data will take many years, but in the interim, heavy ion irradiation could provide a useful tool toward predicting the swelling trends beyond 200 dpa. In this study, HT9 was irradiated from 440–480°C using 5 MeV Fe++ ions. The samples are compared to a portion of HT9 fuel assembly duct from FFTF, which was characterized after neutron irradiation at 440°C with an accumulated dose of 155 dpa. Comparisons are made of the void size and density using transmission electron microscopy (TEM). The increase in dose from 280 dpa to 375 dpa increased void size, number density and swelling at 440°C, while swelling was generally lower at 480°C for the same helium pre-implantation conditions. Helium generally enhanced the nucleation of voids, as measured by the void density.
Lifting Operation Safety Management in AP1000 Nuclear Plant Project
Authors: He Xiaogang , Shortes Shell
Published: February 2014

As a third-generation nuclear power plant design, construction of the Westinghouse AP1000 incorporates the characteristics of modular construction and the “Open-Top” lifting method, which results in many kinds of lifting operations, whose potential failure creates increased risk to key equipment and construction personnel. Lifting by its very nature is high risk. Based on traditional safety management practices utilized at the project, lift operation characteristics were analyzed, and procedures and processes developed to manage the risk. These developed aspects included: lifting operation procedures; a construction scheme review/approval process; work planning/risk mitigation; equipment inspections; personnel certification requirements; training; crew management; special inspections; lessons learned utilization; discipline management; emergency management; and safety culture development. The authors believe that the safety management approaches discussed in this paper can provide guidance in conducting safe lift operations in other nuclear power plant projects.
Shaking Table Tests and Numerical Simulation Analysis of a 1:15 Scale Model Reinforced Concrete Containment Vessel
Authors: Wang Xiaolei , Lu Dagang , Hou Gangling
Published: February 2014

In order to verify the seismic capacity of reinforced concrete containment vessel (RCCV) under the design earthquake level of SL-2 (peak acceleration 0.25g), shaking table tests of a 1:15 model RCCV are carried out. The El Centro earthquake motion record, the Taft earthquake motion record as well as an artificial earthquake acceleration are employed as the input excitations. There are three load cases for each test stage, with the peak ground acceleration (PGA) being 0.1g, 0.2g and 0.3g, respectively, corresponding to 0.088g, 0.175g and 0.263g for the prototype RCCV structure because of the acceleration ratio of 1.14. The test results indicate that under the earthquake excitation of the acceleration peak 0.1g, 0.2g and 0.3g, the tensile strains at monitoring points on the cylinder don’t reach the cracking level. Using the general-purpose nonlinear finite element analysis program ANSYS, a three-dimensional (3D) model of the scaled model reinforced concrete containment vessel is modeled. The numerical simulation analysis results could match the results of the tests very well. It is shown by the results of the shaking table tests that the model RCCV is still within the elastic range as a whole. In order to analyze the yield displacement of the RCCV, a static nonlinear pushover analysis of the RCCV is carried out. The result shows that the RCCV had sufficient seismic safety margin.
Architecting “Maintenance Program” for Piping and Pipe Support
Authors: Tsumori Koichi , Fukuhara Yoshizumi , Terunuma Hiroyuki , Yamamoto Koji , Momiyama Satoshi
Published: February 2014

A new inspection standard that enhanced quality of operating /maintenance management of the nuclear power plant was introduced in 2009. After the Fukushima Daiichi nuclear disaster (Mar. 11th 2011), the situation surrounding the nuclear industry has dramatically changed, and the requirement for maintenance management of nuclear power plants is pushed for more stringent nuclear safety regulations.

The new inspection standard requires enhancing equipment maintenance. It is necessary to enhance maintenance of not only equipment but also piping and pipe support. In this paper, we built the methodology for enhancing maintenance plan by rationalizing and visualizing of piping and pipe support based on the “Maintenance Program” in cooperating with 3D-CAD system.
Study on Formation and Development of Surface Wave of Liquid Metal Lithium Jet for IFMIF
Authors: Hoashi Eiji , Yoshihashi-Suzuki Sachiko , Okita Takafumi , Kanemura Takuji , Kondo Hiroo , Yamaoka Nobuo , Horiike Hiroshi
Published: February 2014

The international fusion materials irradiation facility (IFMIF) presents an intense neutron source to develop fusion reactor materials. The liquid metal Lithium (Li) jet with a free surface is planned as a target irradiated by two deuteron beam to generate intense neutrons and it is thus important to obtain information on the surface wave characteristic for the safety and the efficiency of system in the IFMIF. We have been studying on surface wave characteristics experimentally using the liquid metal Li circulation facility at Osaka University (Li loop) and numerically using computational fluid dynamics (CFD) code, FLUENT.

The CFD simulation has been used in order to establish the mechanism of the formation and development of the surface wave of the liquid Li jet. The introduction of a two-staged contraction nozzle is planned in the IFMIF and the 1/2.5 size of the IFMIF’s nozzle has been also used and tested in our Li loop. These nozzles have a concave wall at each contraction part, and it was then predicted that Görtler vortices in the boundary layer inside the nozzle was generated and flowed out from the nozzle exit at the high velocity condition in our previous simulation. The Li free surface flow simulation including the flow inside the nozzle set in our Li loop was conducted to compare simulation results with experimental results and to evaluate the influence of Görtler vortices on the surface wave formation and development. In our simulation, large eddy simulation and volume of fluid models are used as turbulence model and interface tracking method, respectively. Our simulation result indicates that both transverse vortices due to gas-liquid shear stress and longitudinal vortices induced by Görtler vortices downstream the nozzle exit contribute to the formation of three-dimensional wave of the Li free surface flow at the velocity of 15 m/s. It was found that the vortex structure and the flow pattern under the free surface due to the flow inside the nozzle strongly contributed the development of the surface wave of the liquid Li jet.
Multiphysics Analysis System for Tube Failure Accident in Steam Generator of Sodium-Cooled Fast Reactor
Authors: Uchibori Akihiro , Kikuchi Shin , Kurihara Akikazu , Hamada Hirotsugu , Ohshima Hiroyuki
Published: February 2014

Multiphysics analysis system was newly developed to evaluate possibility of failure propagation occurrence under heat transfer tube failure accident in a steam generator of sodium-cooled fast reactors. The analysis system consists of the computer codes, SERAPHIM, TACT, RELAP5, which are based on the mechanistic numerical models. The SERAPHIM code calculates the multicomponent multiphase flow involving sodium-water chemical reaction. In this study, numerical models for the chemical reaction about production of a sodium monoxide and its transport process were constructed to enable evaluation of a wastage environment. The TACT code was developed to calculate heat transfer from the reacting jet to the adjacent tube and to predict the tube failure occurrence. The TACT code was integrated by the numerical models of the fluid-structure thermal coupling, the temperature and stress evaluation, the wastage evaluation and the failure judgment. The RELAP5 code evaluates thermal hydraulic behavior of water inside the tube. The original heat transfer correlations were corrected for the rapidly heated tube in the present work.
CANDU Position and Prospect in Chinese Nuclear Fuel Cycle
Authors: Zhang Zhenhua , Chen Mingjun , Zhou Peide , Li Qing , Meng Zhiliang , Zhang Guowei
Published: February 2014

To manage climate challenge and optimize energy supply structure, China has decided to develop more nuclear power in a safe and high-efficiency manner. On a nuclear sustainable development perspective, it is necessary to develop a closed fuel cycle (CFC) system and also take great efforts to improve natural uranium (NU) utilization ratio of thermal reactor. CANDU is great certainty to play an important role in this strategy. This paper presents CNNC Third Qinshan Nuclear Power Company Limited (TQNPC) efforts of being develop the engineering technologies of recycling reprocessed uranium (RU) and nuclear use of thorium (Th) resource in CANDU type reactor and finding the CANDU’s position in Chinese CFC system. Also this paper provides a proposal of implementation plan for Chinese CFC system development and also for application of the related CANDU engineering technologies.
Evolution of Crystal Orientations in Plastically Deformed Steels: Role of Constitutive Models Used in Finite Element Simulations
Authors: El Shawish Samir , Cizelj Leon , Simonovski Igor
Published: February 2014

Stainless steel is a commonly used material in safety-important components of nuclear power plants. In order to study degradation mechanisms in stainless steels, like crack initiation and propagation, it is important to characterize the degree of plastic strain on microstructural level. One way to estimate local plastic strain is by measuring local crystal orientations of the scanned surfaces: the electron backscatter diffraction (EBSD) measurements on stainless steel revealed a strong correlation between the spread of crystal orientations within the individual grains and the imposed macroscopic plastic strain. Similar behavior was also reproduced by finite element simulations where stainless steel was modeled by an anisotropic elasto-plastic constitutive model. In that model the anisotropic Hill’s plasticity function for yield criteria was used and calibrated against the EBSD measurements and macroscopic tensile curve.

In this work the Hill’s phenomenological model is upgraded to a more sophisticated crystal plasticity model where plastic deformation is assumed to be a sum of crystalline slips in all activated slip systems. The hardening laws of Peirce, Asaro and Needleman and of Bassani and Wu are applied in crystal plasticity theory and implemented numerically within the user subroutine in ABAQUS. The corresponding material parameters are taken from literature for 316L stainless steel. Finite element simulations are conducted on the analytical Voronoi tessellation with 100 grains and initial random crystallographic orientations. From the simulations, crystal and modified crystal deformation parameters are calculated, which quantify mean and median spread of crystal orientations within individual grains with respect to central grain orientation. The results are compared to EBSD measurements and previous simulations performed with Hill’s plasticity model.
Towards the Development of Shutdown Emergency Operating Procedures for Power Nuclear Reactors
Authors: Malgas Isaac
Published: February 2014

Virtually all operating nuclear plants have a well-developed suite of accident procedures which can be used in the event of an accident while the unit is at power. The procedures guide the operators through optimal recovery strategies to place the plant in a safe stable shutdown state. These procedures cater for design basis accidents as well as certain accidents which are not considered design basis accidents, but may be included in the plant’s licensing basis.

Generally procedures used for accidents during power operation can also be used for initiating accidents which occur while the unit is shutdown while the core is cooled with steam generators. When the unit is in lower shutdown states and the residual heat removal system is in service, however, the procedure scope becomes somewhat constrained. With the reactor coolant system in an open or closed configuration, the state/configuration specific procedure guidance provided by Emergency Operating Procedures for power operation is often deficient.

There is ample literature on developing emergency operating procedures for plant states where the energy (as a function of pressure and temperature) in reactor coolant system is high. However, much fewer sources of literature exist for shutdown plant states when the energy in the reactor coolant system is lower. This paper attempts to bridge this gap by proposing a framework for the development of shutdown emergency operating procedures using the plant specific Probabilistic Safety Assessment (PSA) model.

The paper provides an initial framework for the development of Shutdown Emergency Operating Procedures (SD-EOPs) using the PSA. It describes the process of identifying event sequences for which restoration strategies are required from the PSA and briefly explains the analysis that should be performed to demonstrate that restoration strategies are successful in mitigating event consequences.
Off-Gas Nuclide Analysis System
Authors: Sakakibara Yoshinobu , Kuwabara Hitoshi , Tadokoro Takahiro , Koyama Mikio
Published: February 2014

In the nuclear power plant, the off gas linear monitor had been installed for the purpose of a detection of fuel leakage. However, its sensitivity to detect the early stage of fuel leakage was not enough, because it measured only the gross gamma-ray. So a high sensitive off gas monitor has been desired. HITACHI, Ltd., is commercialized the Off-Gas Nuclide Analysis System which can be accurately detected radioactive noble gases as a index to fuel leakage, and delivered it in 19 plants since 2002. It has been continuously working well and able to detect the early stage of fuel leakage 7 times. It can be detected the minute fuel leakage, so it is possible to operate the plant till next periodic check of the plant by executing PST*. And even if it is the case in which the plant must be stopped, the extent of pollution by fuel failure can be minimized.

Main features of the Off-Gas Nuclide Analysis System are followings: (1) Maintenance-free continuous measurement is enabled by adopting electricity cooling system for a Ge detector. By attempting the miniaturization of the system, a compact field implementation plan is realized and also a periodic check can be simplified. (2) Thickness of a Ge detector is optimized to detect Xe-133 (80keV) as a main index nuclide to fuel leakage, so detection sensitivity is improved. (3) By adopting the mass flow control system wcich can control the flow stably in low, it is possible to reduce a volume and length of a decay tube for 13N which is the main interference nuclide, then a installation of the system is able to be simplified. (4) Moving average method which is effective to reduce noise is applied to a trend display of nuclides measured value, and it can be set at optimum time for the PST execution by flexibly setting a moving average time.

*PST: Power Supression Test
Fire PRA Insights
Authors: Chapman James R.
Published: February 2014

Scientech has recently developed Fire PRAs (FPRAs) for about 20% of the units in the US transitioning to an NFPA-805 licensing basis. This paper provides a summary of insights gained in conducting these studies. A summary of the methods, results and insights is provided. These evaluations are identifying cost beneficial enhancements and identifying the need for improvements in methods and data. The identification of plant enhancements should not be surprising, as the mitigation portion of the fire protection design basis provides for a single safe shutdown path. Most design basis events, e.g., loss of coolant accidents (LOCAs) require at least 2 safe shutdown paths. There are credible fire scenarios which can either fail both trains or result in the need for local manual actions to bypass fire induced failures to align a safe shutdown path. In addition, the safe shutdown path may have lower than expected reliability, if several actions are needed, actions have limited time margin, or the resulting safe shutdown path is subject to single failures, such as failure of an emergency diesel generator.

The paper will discuss insights, plant modifications, and defense in depth. Further, key uncertainties which point to the desirability of methods and data enhancement will be discussed. The paper concludes that fire risk is not low and defense in depth can be compromised.
Overview on the Design Approach for the CVCS I & C of the EPR™ Nuclear Power Plant in Taishan
Authors: Ciriello Antonio , Kohler Daniela , Morton Terry , Lang Thomas
Published: February 2014

The I & C (Instrumentation and Control) design of the CVCS (Chemical and Volume Control System) for the EPR™ nuclear power plant in Taishan (TSN NPP) is shortly introduced and the corresponding I & C module assignment procedure, according to the functional safety class principle, is described.

An example of the I & C module assignment procedure is given for a control loop of the CVCS. In addition, the corresponding advantages and drawbacks are described and discussed.

The approach described introduces a new method for the concerned I & C design by improving the interface between the system, process, and I & C engineering design.

In fact, a fruitful collaboration was reached between the system and I & C design for the EPR™ project in Taishan, for the concerned interface.
Measurement of periodicity and strain in arrays of single crystal silicon and pseudomorphic Si1−xGex/Si fin structures using x-ray reciprocal space maps
Authors: Medikonda Manasa , Muthinti Gangadhara R. , Fronheiser Jody , Kamineni Vimal , Wormington Matthew , Matney Kevin , Adam Thomas N. , Karapetrova Evguenia , Diebold Alain C.
Published: February 2014

Characterization of the periodicity and strain state of an array of lithographically patterned silicon and silicon-germanium alloy on silicon fins using reciprocal space mapping of Bragg diffraction peaks is presented. Various patterned structures with different pitch values of 90 nm, 65 nm, and 42 nm have been studied and data for the 42 nm pitch sample is discussed in this paper. Diffraction from fin arrays is treated kinematically analogous to periodic surface grating structures. Diffraction from the symmetric 004 planes is used to calculate pitch and analyze the pitch walking pattern which appears as harmonic peaks on either side of the fin peaks. Pitch walking refers to the presence of two periodicities in the array due to the lithographic process. Longitudinal scans are evaluated at the fin peak positions to probe into the shape of the fin structure. Nonrectangular fin shapes resulted in peak splitting of the longitudinal scans of higher order fin peaks indicating a finite sidewall slope. Asymmetric 224 planes were analyzed to study the quality and strain-relaxation of the fin structures both parallel and perpendicular to the fin length using reciprocal space mapping techniques.
MBE growth of P-doped 1.3 μm InAs quantum dot lasers on silicon
Authors: Liu Alan Y. , Zhang Chong , Snyder Andrew , Lubyshev Dmitri , Fastenau Joel M. , Liu Amy W. K. , Gossard Arthur C. , Bowers John E.
Published: February 2014

The authors report on the growth of InAs/GaAs quantum dots lasers on silicon emitting in the 1.3 μm wavelength regime with p-doped active regions. A growth optimization procedure guided by a combination of high and low excitation photoluminescence is presented for the InAs quantum dot growth. Growth conditions derived from this procedure are used to produce high optical quality quantum dots embedded in a GaAs/AlxGa1−xAs graded index separate confinement heterostructure waveguide. Ridge waveguide lasers fabricated from the as-grown material achieve room temperature continuous wave lasing at low thresholds, with high output power and elevated T0.
Reliability of a Novel Testing Protocol to Assess Upper-Body Strength Qualities in Elite Athletes
Authors: Young Kieran P. , Haff G. Gregory , Newton Robert U. , Sheppard Jeremy M.
Published: February 2014

Purpose:

The purpose of this study was to evaluate the reliability of an isometric-bench-press (IBP) test performed across 4 elbow angles and a ballistic bench throw (BBT) using a relative load, as well as evaluating the reliability of the dynamic strength index (DSI: BBT peak force/IBP peak force).

Methods:

Twenty-four elite male athletes performed the IBP and a 45% 1-repetition-maximum BBT on 2 separate days with 48 h between testing occasions. Peak force, peak power, peak velocity, peak displacement, and peak rate of force development (PRFD) were assessed using a force plate and linear position transducer. Reliability was assessed by intraclass correlation (ICC), coefficient of variation (%CV) and typical error.

Results:

Performance measures in the BBT, such as peak force, peak velocity, peak power, and peak displacement, were considered reliable (ICC = .85–.92, %CV = 1.7–3.3), while PRFD was not (ICC = .43, %CV = 4.1). Similarly, for the IBP, peak force across all angles was considered reliable (ICC = .89–.97, %CV = 1.2–1.6), while PRFD was not (ICC = .56–.65, %CV = 0.5–7.6). The DSI was also reliable (ICC = .93, %CV = 3.5).

Conclusions:

Performance measures such as peak force in the IBP and BBT are reliable when assessing upper-body pressing-strength qualities in elite male athletes. Furthermore, the DSI is reliable and could potentially be used to detect qualities of relative deficiency and guide specific training interventions.
Measuring Acceleration and Deceleration in Soccer-Specific Movements Using a Local Position Measurement (LPM) System
Authors: Stevens Tom G.A. , de Ruiter Cornelis J. , van Niel Cas , van de Rhee Roxanne , Beek Peter J. , Savelsbergh Geert J.P.
Published: February 2014

Purpose:

A local position measurement (LPM) system can accurately track the distance covered and the average speed of whole-body movements. However, for the quantification of a soccer player’s workload, accelerations rather than positions or speeds are essential. The main purpose of the current study was therefore to determine the accuracy of LPM in measuring average and peak accelerations for a broad range of (maximal) soccerspecific movements.

Methods:

Twelve male amateur soccer players performed 8 movements (categorized in straight runs and runs involving a sudden change in direction of 90° or 180°) at 3 intensities (jog, submaximal, maximal). Position-related parameters recorded with LPM were compared with Vicon motion-analysis data sampled at 100 Hz. The differences between LPM and Vicon data were expressed as percentage of the Vicon data.

Results:

LPM provided reasonably accurate measurements for distance, average speed, and peak speed (differences within 2% across all movements and intensities). For average acceleration and deceleration, absolute bias and 95% limits of agreement were 0.01 ± 0.36 m/s2 and 0.02 ± 0.38 m/s2, respectively. On average, peak acceleration was overestimated (0.48 ± 1.27 m/s2) by LPM, while peak deceleration was underestimated (0.32 ± 1.17 m/s2).

Conclusion:

LPM accuracy appears acceptable for most measurements of average acceleration and deceleration, but for peak acceleration and deceleration accuracy is limited. However, when these error margins are kept in mind, the system may be used in practice for quantifying average accelerations and parameters such as summed accelerations or time spent in acceleration zones.
Validation of a Novel Intermittent W′ Model for Cycling Using Field Data
Authors: Skiba Philip F. , Clarke David , Vanhatalo Anni , Jones Andrew M.
Published: February 2014

Recently, an adaptation to the critical-power (CP) model was published, which permits the calculation of the balance of the work capacity available above the CP remaining (W′bal) at any time during intermittent exercise. As the model is now in use in both amateur and elite sport, the purpose of this investigation was to assess the validity of the W′bal model in the field. Data were collected from the bicycle power meters of 8 trained triathletes. W′bal was calculated and compared between files where subjects reported becoming prematurely exhausted during training or competition and files where the athletes successfully completed a difficult assigned task or race without becoming exhausted. Calculated W′bal was significantly different between the 2 conditions (P < .0001). The mean W′bal at exhaustion was 0.5 ± 1.3 kJ (95% CI = 0–0.9 kJ), whereas the minimum W′bal in the nonexhausted condition was 3.6 ± 2.0 kJ (95% CI = 2.1–4.0 kJ). Receiver-operator-characteristic (ROC) curve analysis indicated that the W′bal model is useful for identifying the point at which athletes are in danger of becoming exhausted (area under the ROC curve = .914, SE .05, 95% CI .82–1.0, P < .0001). The W′bal model may therefore represent a useful new development in assessing athlete fatigue state during training and racing.
Postural Stability of Older Female Scottish Country Dancers in Comparison With Physically Active Controls
Authors: Dewhurst Susan , Peacock Leslie , Bampouras Theodoros M.
Published: February 2014

Physical activity assists older individuals’ functional ability and postural stability. Recently, Scottish country dance (SCD) was reported as being a beneficial form of physical activity for functional ability in older females. This study aims to examine the effect of SCD on postural stability. Scottish country dancers (n = 20) were compared with physically active controls (n = 33) for static postural sway measured on a force platform. The Romberg and Tandem stances were used under ‘eyes open’ and ‘eyes closed’ conditions. Ninety-five percent ellipse area and sway velocity were calculated from the center of pressure displacement. Ninety-five percent ellipse area was the same for both groups in all tests. The control group had greater sway velocity for all tests (P < .01) except Tandem eyes closed. SCD participation resulted in similar postural sway as participation in other physical activities, however nondancers may need a greater amount of regulatory activity to maintain balance.
Mapping the Epigenetic Basis of Complex Traits
Authors: Cortijo Sandra , Wardenaar René , Colomé-Tatché Maria , Gilly Arthur , Etcheverry Mathilde , Labadie Karine , Caillieux Erwann , Hospital Fréderic , Aury Jean-Marc , Wincker Patrick , Roudier François , Jansen Ritsert C. , Colot Vincent , Johannes Frank
Published: February 2014

Quantifying the impact of heritable epigenetic variation on complex traits is an emerging challenge in population genetics. Here, we analyze a population of isogenic
Arabidopsis
lines that segregate experimentally induced DNA methylation changes at hundreds of regions across the genome. We demonstrate that several of these differentially methylated regions (DMRs) act as bona fide epigenetic quantitative trait loci (QTL
epi
), accounting for 60 to 90% of the heritability for two complex traits, flowering time and primary root length. These QTL
epi
are reproducible and can be subjected to artificial selection. Many of the experimentally induced DMRs are also variable in natural populations of this species and may thus provide an epigenetic basis for Darwinian evolution independently of DNA sequence changes.
Whole-Genome Shotgun Sequence of Bacillus amyloliquefaciens Strain UASWS BA1, a Bacterium Antagonistic to Plant Pathogenic Fungi
Authors: Lefort F. , Calmin G. , Pelleteret P. , Farinelli L. , Osteras M. , Crovadore J.
Published: February 2014

We report here the whole-genome shotgun sequence of
Bacillus amyloliquefaciens
strain UASWS BA1, isolated from inner wood tissues of a decaying
Platanus
×
acerifolia
tree. This strain proved to be antagonistic to several plant pathogenic fungi and oomycetes and can be developed as a biological control agent in agriculture.
Draft Genome Sequence of the Polyextremophilic
Halorubrum
sp. Strain AJ67, Isolated from Hyperarsenic Lakes in the Argentinian Puna
Authors: Burguener Germán F. , Maldonado Marcos J. , Revale Santiago , Fernández Do Porto Darío , Rascován Nicolás , Vázquez Martín , Farías María Eugenia , Marti Marcelo A. , Turjanski Adrián Gustavo
Published: February 2014

Halorubrum
sp. strain AJ67, an extreme halophilic UV-resistant archaeon, was isolated from Laguna Antofalla in the Argentinian Puna. The draft genome sequence suggests the presence of potent enzyme candidates that are essential for survival under multiple environmental extreme conditions, such as high UV radiation, elevated salinity, and the presence of critical arsenic concentrations.
Draft Genome Sequence of Kocuria palustris PEL
Authors: Sharma Gaurav , Khatri Indu , Subramanian Srikrishna
Published: February 2014

We report the 2.9-Mb draft genome sequence of an actinobacterium,
Kocuria palustris
PEL, of the family
Micrococcaceae
.
Widespread bullous fixed drug eruption
Authors: Patell Rushad D , Dosi Rupal V , Shah Purav C , Joshi Harshal S
Published: February 2014

A 53-year-old man developed a widespread erythematous eruption which rapidly evolved into fluid-filled bulla mostly involving the distal areas of all four limbs and erosions on the oral as well as anogenital mucosa. Based on clinical presentation, chronology of drug exposure, past events and histopathology as diagnosis of widespread bullous fixed drug eruption was made over Steven Johnson-toxic epidermal necrolysis syndrome. Steroids were deferred and the lesions healed with minimal pigmentation within a week. Differentiating between the two entities has been historically difficult, and yet can have significant therapeutic and prognostic implications.
Bevacizumab in vitreous haemorrhage secondary to radiation retinopathy
Authors: Montero Javier Antonio , Yanez-Castro Giovanni , Sanchis-Merino Maria Eugenia , Ruiz-Moreno Jose Maria
Published: February 2014

Radiation retinopathy is a delayed-onset side effect of radiation exposure caused by retinal ischaemia that may induce proliferative retinopathy with neovascularisation, vitreous haemorrhage and macular oedema. An otherwise healthy, 51-year-old male patient who had been diagnosed with olfactory neuroblastoma and undergone complete surgical removal of the lesion followed by cranial irradiation developed bilateral cataracts and radiation retinopathy. The patient was treated by panretinal photocoagulation (PRP), followed by three-port pars-plana vitrectomy. Recurrent episodes of vitreous haemorrhages occurred following surgery and the patient was successfully treated by one intravitreal injection of bevacizumab with resolution of vitreous blood. Vitreous haemorrhage recurred 6 months later and a scheduled treatment with intravitreal bevacizumab every 4 months was established, preventing further haemorrhagic episodes. Six months after the last injection, a new episode of vitreous haemorrhage occurred.

Scheduled intravitreal bevacizumab injections may help prevent recurrent vitreous haemorrhages in vitrectomised patients with radiation retinopathy.
The experiences of professionals with using information from patient-reported outcome measures to improve the quality of healthcare: a systematic review of qualitative research
Authors: Boyce Maria B , Browne John P , Greenhalgh Joanne
Published: February 2014

Objectives

To synthesise qualitative studies that investigated the experiences of healthcare professionals with using information from patient-reported outcome measures (PROMs) to improve the quality of care.

Design

A qualitative systematic review was conducted by searching PubMed, PsycINFO and CINAHL with no time restrictions. Hand searching was also performed. Eligible studies were evaluated using the Critical Appraisal Skills Programme toolkit for qualitative studies. A thematic synthesis identified common themes across studies. Study characteristics were examined to explain differences in findings.

Setting

All healthcare settings.

Participants

Healthcare professionals.

Outcomes

Professionals’ views of PROMs after receiving PROMs feedback about individual patients or groups of patients.

Results

Sixteen studies met the inclusion criteria. Barriers and facilitators to the use of PROMs emerged within four main themes: collecting and incorporating the data (practical), valuing the data (attitudinal), making sense of the data (methodological) and using the data to make changes to patient care (impact).

Conclusions

Professionals value PROMs when they are useful for the clinical decision-making process. Practical barriers to the routine use of PROMs are prominent when the correct infrastructure is not in place before commencing data collection and when their use is disruptive to normal work routines. Technology can play a greater role in processing the information in the most efficient manner. Improvements to the interpretability of PROMs should increase their use. Attitudes to the use of PROMs may be improved by engaging professionals in the planning stage of the intervention and by ensuring a high level of transparency around the rationale for data collection.
Consent in the endoscopy department
Authors: Mohanaruban Aruchuna , Flanders Lucy , Dor Riaz
Published: February 2014

The demand for endoscopic procedures continues to increase and is likely to continue to do so for the foreseeable future. Alongside elective diagnostic procedures, the number of complex and therapeutic procedures is increasing. It is therefore vital that the consent process is comprehensive, and high standards in consenting patients are maintained.

Consent is defined as a patient's agreement to treatment or an intervention proposed by a health professional. Careful patient selection is required when proposing endoscopic procedures with an appreciation of the risks and complications that are involved. This paper addresses the various components of gaining informed consent and the legal issues surrounding this process. Additionally, this article reviews legislation and focuses upon specific instances where further considerations have to be made; in a patient who lacks capacity, in children, in percutaneous endoscopic gastrostomy and in the patient who is a Jehovah's Witness.
The PennHIP method of predicting canine hip dysplasia
Authors: Guilliard Mike
Published: February 2014

Perfect hip joints are rarely found in the dog population as some degree of canine hip dysplasia is present in most dogs. In this article, the theory and methodology of the PennHIP technique is described and compared with the British Veterinary Association/Kennel Club Hip Dysplasia Scheme.
Bacterial leaf glands in Styrax camporum (Styracaceae): first report for the family
Authors: Machado Silvia Rodrigues , Teixeira Simone de Pádua , Rodrigues Tatiane Maria
Published: February 2014

In this study, we recorded, for the first time, the occurrence of leaf glands in a member of Styracaceae and their association with bacteria. Samples of Styrax camporum Pohl shoot apices and leaves at different developmental stages were prepared according to the conventional techniques for light and electron microscopy. Glands are emergences constituted by epidermal and parenchyma cells and are differentiated into a secretory body on a short nonsecretory stalk supplied with phloem. Actively secreting glands occur from leaf primordia to mature leaves and produce mucilage that accumulates inside schizogenous intercellular spaces. The epidermal secretory cells have abundant cytoplasm rich in hyperactive dictyosomes, an extensive endoplasmic reticulum, and modified plastids. Bacteria enter the gland via the intact surface and proliferate in the intercellular spaces of the glands. Once inside the intercellular spaces of the glands, bacteria enter the cells owing to the weakening of the anticlinal and inner periclinal cell walls and by phagocytosis. Strands of actin filaments occur near the endocytical vesicles containing degenerating bacteria. Accumulations of phenolic compounds and callose could explain the absence of bacteria in the stalk cells. The presence of bacteria inside the leaf glands of S. camporum is a regular and cyclic trait. The significance of the bacteria (not yet identified) and the type of interaction between these two organisms remain unknown.
Nonstationary Gabor frames — Existence and construction
Authors: Dörfler Monika , Matusiak Ewa
Published: February 2014

Nonstationary Gabor frames were recently introduced in adaptive signal analysis. They represent a natural generalization of classical Gabor frames by allowing for adaptivity of windows and lattice in either time or frequency. In this paper, we show a general existence result for this family of frames. Then, we give a perturbation result for nonstationary Gabor frames and construct nonstationary Gabor frames with non-compactly supported windows from a related painless nonorthogonal expansion. Finally, the theoretical results are illustrated by two examples of practical relevance.