bluuebunny/crossref_metadata_2025_split huggingface dataset:
Inexpensive Numerical Method for Heat Transfer Computations Using Excel
Authors: Abdelmessih Amanie N. 
Published: October 2017

Most thermal engineers will model and analyze thermal engineering cases, using any of the numerous thermal analysis software, available in the market. These commercial software need years of continuous use to be fully mastered. Large companies can afford to acquire expensive software available in the market and train their engineers; but small companies do not have the financial means to acquire such expensive software. Thus for modeling and analysis, small companies or private practice need a different alternative. Excel is one of the programs that come with Microsoft Office suite of software, which is installed on any purchased computer. Most users of Microsoft office are proficient in using Word, and can use Excel as a spread sheet to speed up calculations. Technical personnel can easily use the charting capability of Excel, but very few engineers can use Excel for intensive Numerical Analysis. Engineers should be able to use the available inexpensive Excel software to perform numerical analysis at their work place.
In this article three Heat Transfer Numerical cases using Microsoft Excel are discussed in detail. the first case is two dimensional steady state heat transfer with different isothermal boundary conditions. The second shows other boundary conditions: uniform heat flux, adiabatic, and convection. The third case is transient conditions. The results from the three cases are compared with results from Patran Thermal software.
Experimental Validation of Numerical Predictions for the Transient Performance of a Simple Latent Heat Storage Unit (LHSU) Utilizing Phase Change Material (PCM) and 3-D Printing
Authors: Kumar Navin , Banerjee Debjyoti 
Published: October 2017

Experimental validation was performed in this study to verify the efficacy of numerical models for predicting the location of solid-liquid interface in an axi-symmetric configuration during both melting and solidification in a Latent Heat Storage Unit (LHSU). Development of analytical solutions for predicting the location of the solid-liquid interface is often intractable in LHSU due to non-linear temperature distribution in the Phase Change Material (PCM). This is further complicated by the moving boundary problem with free convection within the liquid phase of the PCM. Analytical solutions available in the contemporary literature are based on simplified transient heat conduction models and often fail to reliably predict the charging and discharging time constants for LHSU with complex configurations. This study is designed with the goal of developing more sophisticated numerical models for the estimation of transient thermal performance of an LHSU with a simple configuration involving a shell and tube heat exchanger (HX).
The LHSU utilized in this study is realized by integrating various types of Phase Change Materials (PCM) contained in the shell side of a HX. The LHSU is charged or discharged by pumping hot or cold fluids in the tube side of the HX (i.e., by pumping water at a fixed inlet temperature from a commercial chiller apparatus). This study enabled the characterization of the transient response of a LHSU subjected to conduction and forced convection heat transfer. The PCM used in this material was paraffin wax (PURETEMP 29). The HX in the LHSU consisted of a single pass straight tube (½ inch copper pipe) mounted within a single shell configuration. The shell was fabricated from plastic material using additive manufacturing (i.e., “3D Printing”). The temperature variation during melting and solidification of the PCM were measured at different radial and axial locations within the cylindrical shell that was mounted vertically. Temperature measurements were performed at different mass flowrate ranging from 0.004 Kg/sec to 0.007 Kg/sec for the same fluid temperature. The water bath temperatures were maintained at a constant temperature of 40°C for melting and 15°C for solidification. The experiment results show that the transient response of the LHSU for charging and discharging (i.e., time required for melting and solidification of the PCM) vary significantly. Comparison of the experimental data with analytical results (involving quasi-stationary models for phase change) demonstrate that natural convection is the dominant mode during the melting process, while conduction is the dominant mode during the solidification process.
Preliminary Forensic Engineering Study on the Fukushima Accident
Authors: Saji Genn 
Published: October 2017

Even after 6 years since the accident, the exact accident progression for each unit and location of core debris has not been clarified. Currently efforts are directed towards robotic inspection with remote cameras, as well as dose and temperature measurements of the environment inside of the Primary Containment Vessels (PCV). In spite of their effort, the observed environmental data do not support the existence of a large radiation heat sources attributable to the molten core at the bottom of the Primary Containments.
Under this situation the author has conducted a forensic engineering study (i.e., different fields of science work together to collect and integrate independent evidences) to clarify the most likely accident scenarios of the Fukushima Daiichi accident. Through this study the author found that the environmental contamination and public exposure could have been substantially mitigated should the following vulnerabilities have been removed before the accident:
(1) The threat of hydrogen generation through “radiation-induced electrolysis”.
(2) Potential threat of “internal hydrogen explosion” in the suppression pools. The atmosphere on top of the suppression pool water (cover gas) should have been nitrogen.
(3) Potential threat of “internal hydrogen explosion” in pipes which had occurred in the case of the Hamaoka Unit 1 accident.
(4) The leak rate of PCV should have been testable at its design pressure. Intrinsic safety factor of the containment flanges against effluent leakage should have been rated as a 3 for functional integrity of the PCV.
(5) Spread of hydrogen gas from vent lines through duct networks connected to SGTS. The hardened vent line should be independent and provided with filters for Dry Well venting. No rupture disks should have been installed in the vent lines.
A Method Evaluating Fire Hazard of Multiple-Layer Cable Tray and its Validation
Authors: Huang Xianjia , Bi Kun , Xiao Jun , Peng Lan , Zhu He , Zheng Zihui 
Published: October 2017

Multi-layer cable tray fire has special burning characteristics that the cable flame spreads horizontally along cable tray and propagates vertically from bottom layer to upper layer at the same time. With respect of accuracy and speed of calculation, simulation of multi-layer cable tray fire remains a challenge for fire models. In this paper, a method is proposed to simulate multi-layer cable tray fire. By developing a more accurate fire source description, this method can provide accurate simulation for multi-layer cable tray fire rapidly.
In this method, Firstly, the heat release rate of each burning cable tray is evaluated by FLASH-CAT model. Based on the results from FLASH-CAT, a more accurate fire source definition for multiple lay cable tray is developed for zone model. Taking account of each burning cable tray considered as one fire source point, zone model is applied to predict the fire dynamics process. In order to validate this method, four-layer cable tray fire experiments and replicated experiments were carried out in a confined compartment. The histories of mass loss rate of cable tray and temperatures at the middle of compartment were recorded during the cable fire. From the replicated experimental results of total mass loss rate, it is concluded that the four-layer cable tray fire experiment has good repetition in this scenario. Vertical temperature profile shows that the fire circumstance generated by multiple-layer cable tray burning can be divided into upper hot layer and lower cool layer, which conforms to the basic assumption of zone model. As a consequence, the zone model can be applied to simulating multiple-layer cable tray fire.
By comparing the experimental total heat release rate with predictions, it is found that characteristics of multiple-layer cable tray fire are well captured. On account of good prediction on overall heat release rate for multi-layer cable tray fire, predicted heat release rate for each burning cable layer by FLASH-CAT model is believed to be reliable. Then, each burning cable layer is set as one fire source and the heat release rate of each burning cable layer is input into zone model, respectively. The comparisons between simulations and experimental data show that the predicted upper layer temperature and lower layer temperature agree well with experimental data. As a result, it can be concluded that this method provides reliable prediction for multiple-layer cable tray fire rapidly.
Review of the Content Analysis of Physics School Books Coming From Different European Countries on Radioactivity and Nuclear Energy
Authors: Baumont Genevieve , Perko Tanja , Zakrzewska Grażyna , Kralj Metka , Diaconu Daniela , Železnik Nadja 
Published: October 2017

The EAGLE project was a Euratom FP7 which helped to identify and disseminate good practices in information and communication processes related to ionizing radiation.
For this purpose, the consortium reviewed national and international data, tools and methods as well as institutional work in order to identify education, information and communication needs.
Generally in high school the first concepts on radioactivity and ionizing radiation (IR) are introduced mainly in the subjects of physics or physical chemistry.
There are a number of concepts in relation with IR and nuclear topics, and different ways to teach them: theoretical, mathematical, historical or practical. The question also rose, to what extend the various topics related to ionizing radiation (health, environment, history) are dealt with.
As already mentioned, all these questions let to the idea to compare the content dealing with radioactivity and nuclear topics in different physics school books and more specifically schoolbooks for high school students (in the age 17 to 18). The method was as follows:
- For the review the different partners of EAGLE have sent the schoolbooks used for the target group, or scanned documents.
- Spanish schoolbooks and English schoolbooks were purchased to extend the review to other EU countries.
- IRSN works in partnership with a high school based in the French town Vichy.
- Each book was analyzed in detail to list with precision the content. A matrix helped to compare them.
The paper presents the comparison of the contents of these books and their analysis. Some recommendations coming from the Eagle project will be discussed.
The Development and Application of the Engineering and Design Analyzer of CAP1400 Nuclear Power Plant
Authors: Yuanlei He , Qijiang Zhang , Xiaoyan Li 
Published: October 2017

In the process of research and development for a new nuclear power plant, it is very necessary to develop a dynamic platform and tools to analyze and verify the plant control & protect system and human factor engineering. Therefor, Shanghai Nuclear Engineering Research and Development Institute (SNERDI) developed the Engineering & Design Analyzer of CAP1400 Nuclear Power Plant (CAP1400 EDA) which provides a dynamic platform environment for analyzing and verifying the control system and human factor engineering of the CAP1400 nuclear power plant, a new Gen III passive nuclear power plant.
In this paper, the mechanism and implement approach of the CAP1400 EDA will be mainly introduced, for example, the platform architecture of the EDA, analysis tools integrated in the EDA and CAP1400 nuclear power plant modes based on the EDA.
In the meantime, a typical application case based on the CAP1400 EDA will be demonstrated in this paper, for example the capability of the NSSS control system will be verified in a ramp load down & raise operate transient. In this transient process, the NSSS control system of the plant is assessed whether it has the capability to keep the key parameter and state of the plant in an acceptance condition or range. And also other transients such as step load transient, large load transient can be simulated on CAP1400 EDA to verify whether or not the NSSS control systems are properly designed.
Similar but Different: A Top-Down Benchmarking Approach to Investigate Nuclear Decommissioning Projects
Authors: Invernizzi Diletta Colette , Locatelli Giorgio , Brookes Naomi J. , Grey Martin 
Published: October 2017

Project management literature has, until now, mainly focused on new build and only in the last decades the issues of decommissioning (mega) projects has arisen. To respond to this changing environment, project management will need to understand the challenges of decommissioning projects. Decommissioning projects within Oil & Gas, Chemical and Nuclear sectors are characterized by high costs, long schedules and uncertainty-based risks. The budget for Nuclear Decommissioning Projects and Programmes (NDPs) are subject to well publicized increases and, due to their relatively recent emergence, complexity and variety, key stakeholders lack a full understanding of the key factors influencing these increases.
Benchmarking involves “comparing actual or planned practices [...] to identify best practices, generate ideas for improvement” [1] and offers significant potential to improve the performance of project selection, planning and delivery. However, even if benchmarking is the envisaged methodology to investigate the NDPs characteristics that impact on the NDPs performance, until now, it has only been partially used and there is a huge gap in the literature concerning benchmarking NDPs.
This paper adapts a top-down benchmarking approach to highlight the NDPs characteristics that mostly impact on the NDPs performance. This is exemplified by a systematic quantitative and qualitative cross-comparison of two major “similar-but-different” NDPs: Rocky Flats (US) and Sellafield (UK). Main results concern the understanding of the alternatives of the owner and/or the contractors in relation to (1) the physical characteristics and the end state of the nuclear site, (2) the governance, funding & contracting schemes, and (3) the stakeholders’ engagement.
Particle Deposition by Thermophoresis Under High Temperature Conditions in a Helium-Flow
Authors: Fischer Felix , Andris Andreas , Lippmann Wolfgang , Hurtado Antonio 
Published: October 2017

The continuous generation of graphite dust particles in the core of a High Temperature Reactor (HTR) is one of the key challenges of safety during the operation. The graphite dust particles emerge from relative movements between the fuel elements or from contact to the graphitic reflector structure and could be contaminated by diffused fission products from the fuel elements. They are distributed from the reactor core to the entire reactor coolant system. In case of a depressurisation accident, a release of the contaminated dust into the confinement is possible. In addition, the contaminated graphite dust can decrease the life cycle of the coolant system due to chemical interactions.
On the one hand, the knowledge of the behaviour of graphite dust particles under HTR conditions using helium as the flow medium is a key factor to develop an effective filter system for the discussed issue. On the other hand, it also provides a possibility to access the activity distribution in the reactor. The behaviour can be subdivided into short-term effects like transport, deposition, remobilization and long-term effects like reactions with material surfaces.
The Technische Universität Dresden has installed a new high-temperature test facility to study the short-term effects of deposition of graphite dust particles. The flow channel has a length of 5m and a tube diameter of 0.05m. With helium as the flow medium, the temperature can be up to 950 °C in the channel center and 120 °C on the sample surface, the Reynolds number can be varied from 150 up to 1000. The particles get dispersed into the accelerated and heated flow medium in the flow channel. Next, the aerosol is passing a 3 m long adiabatic section to ensure homogenous flow conditions. After passing the flow straightener, it enters the optically accessible measurement path made from quartz glass.
In particular, this test facility offers the possibility to analyse the influence of the thermophoretic effect separately. For this, an optionally cooled sample can be placed in the measuring area. The thickness of the particle layer on the sample is estimated with a 3D Laser scanning microscope. The particle concentration above the sample is measured with an aerosol particle sizer (APS). Particle Image Velocimetry (PIV) detects the flow-velocity field and provides data to estimate the shear velocity. In combination with the measured temperature-field, all necessary information for the calculation of the particle deposition and particle relaxation time are available.
The measurements are compared to results of theoretical works from the literature. The experimental database is relevant especially for CFD-developers, for model development, and model verification. A wide range of phenomena like particle separation, local agglomeration of particles with a specific particle mass and selective remobilization can be explained in this way. Thus, this work contributes to a realistic analysis of Nuclear Safety.
Development of Prevention Method for Air Ingress During a Pipe Rupture Accident of the VHTR: Effectiveness on Localized Natural Convection
Authors: Tanaka Yudai , Takeda Tetsuaki 
Published: October 2017

A primary pipe rupture accident is one of the design-basis accidents of a Very-High-Temperature Reactor (VHTR). When a primary pipe rupture accident occurs, air is expected to enter into the reactor pressure vessel from the breach and oxidize in-core graphite structures. Therefore, it is important to understand the mixing processes of different kinds of gases in the stable and unstable stratified fluid layers. In particular, it is also important to examine the influence of localized natural convection and molecular diffusion on the mixing process from a safety viewpoint. Therefore, in order to predict or analyze the air ingress phenomena during a pipe rupture accident, it is important to develop a method for the prevention of air ingress during an accident.
We carried out experiments to obtain the mixing process of two-component gases and flow characteristics of localized natural convection. This study also investigated a control method for the natural circulation of air through the injection of helium gas. An experiment has been carried out to investigate a control method of natural circulation of air by injection of helium gas. The experimental apparatus consists of a reverse U-sharped vertical slot and a storage tank. One side-slot consists of the heated and cooled walls. The other side-slot consists of the two cooled walls. The dimensions of the vertical slots are 598 mm in height, 208 mm in depth, and 70 mm in width. Each two vertical slots were connected and were a reverse U-shaped passage. The dimensions of the connecting passage were 16 mm in height, 106 mm in depth, and 210 mm in length. The storage tank was connected to the lower part of the reverse U-shaped passage. The dimensions of the storage tank were 398 mm in length, 398 mm in depth, and 548 mm in width. The reverse U-shaped passage and the storage tank were separated by a partition plate. The wall and gas temperature were measured by a K-type thermocouple.
Experimental results regarding mixing process of two component gases in vertical fluid layer were as follows. The heavy gas was transported to the slot by the molecular diffusion and natural convection. As time elapses, natural circulation of heavy gas suddenly occurs through the reverse U-shaped slot. As a result of experiments, the onset time of natural circulation is affected by not only molecular diffusion coefficient but also the strength of natural convection. When the helium gas is injected into the channel, it is possible to control the natural circulation of air. The onset time of the reproduction of the natural circulation can be varied by changing the injection rate of the helium gas.
Energy Needs and Potential Nuclear Power Development in China
Authors: Zhao Danlu 
Published: October 2017

The harmonious development of economic, energy and environment is an important premise to realize the objective of China’s modernization. Currently, different parts of China have different main energy source, while nuclear power development has many opportunities and challenges. This paper considers the current trends of energy needs in China, and discusses the different influencing factors of energy needs throughout China.
In addition, this paper will focus on the potential nuclear power development in China, which mainly focuses on policy, technology, nuclear security and social attitude. Then it will focus on the application in Shenzhen (Daya Bay). Based on previous analysis, technical/engineering feasibility and site feasibility are considered in this part. Finally, a number of recommendations for nuclear development management in China will be given. These recommendations will help the public to have a basic understanding of nuclear power management, and to improve the social attitude of China’s nuclear energy development.
In all, this paper puts forward the management methodology of nuclear power industry, which has positive significance for the field of nuclear power education. Meanwhile, the paper will play a positive role on popularize the knowledge of nuclear power to the public.
Study on the Performance of a Kind of Corrugated-Plate Separator
Authors: He Wei , Tian Ruifeng , Chen Bowen , Mao Feng 
Published: October 2017

In order to guarantee the safe and economic operation of nuclear power plant, providing the steam of high quality is very important. As the last stage of the steam-water separating device, corrugated-plate separator has low pressure loss and high separation efficiency, so it is widely used in various types of nuclear power plant. Due to the complexity of the flow field inside the corrugated-plate separator and the immaturity of the numerical method, the research on the corrugated-plate separator is mainly based on experiment. In this work, a kind of corrugated-plate separator with new structures are studied by means of experiment.
In this work, test bed was built with plexiglass. The separation characteristics, resistance characteristics and critical inlet flow velocities of the two structures of separators at different inlet velocities were studied respectively. The following conclusions were obtained: With the increase of the inlet-air velocity, the separation efficiency increases, and the pressure loss increases too. But when the critical inlet flow velocity is reached, increasing the air velocity will reduce the separation efficiency. Considering the influence of structural parameters and airflow parameters, the optimum structural parameters of two kinds of wave plates are obtained. By contrast, it is found that the performance of double-hook corrugated-plate is better than that of single-hook corrugated-plate.