1982-83 Texas College and University Real Estate Course Survey.

Science.gov (United States)

Lyon, Robert

In 1983, the Texas Real Estate Research Center conducted its eighth annual survey of the real estate offerings of the state's two- and four-year colleges. Survey findings, based on a 90% response rate, included the following: (1) 90 institutions (46 community colleges and 44 four-year colleges) offered real estate courses during the 1982-83…

How Community Colleges in Texas Prioritize Resources for Latino Men

Science.gov (United States)

Rodriguez, Sarah L.; Garbee, Kelty T.; Miller, Ryan A.; Saenz, Victor B.

2018-01-01

This study explored how administrators at community colleges conceptualized change related to resource allocation and managing competing priorities to support targeted programming for Latino men. The study included the perspectives of 39 administrators from seven community colleges across Texas using concepts associated with institutional change…

Minority and female training programs at the Ford Nuclear Reactor, University of Michigan

International Nuclear Information System (INIS)

Burn, R.R.

1992-01-01

Nuclear power industry operations staffs are composed predominantly of white males because most of the personnel come from the nuclear submarine and surface branches of the U.S. Navy. The purpose of the minority and female training programs sponsored by the Ford Nuclear Reactor at the University of Michigan is to provide a path for minorities and women to enter the nuclear industry as operators, technicians, and, in the long term, as graduate engineers. The training programs are aimed at high school students, preferably juniors. While the training is directed toward operation of a nuclear reactor, it is equally applicable to careers in most other technical fields. It is hoped that some of the participants will remain at the Ford Nuclear Reactor as reactor operators, enter college, and obtain college degrees, after which they will enter the nuclear industry as graduate engineers

Training a Green Workforce With Stem Initiatives at the Alamo Colleges District

Science.gov (United States)

Reyes, R.; Strybos, J.

2017-12-01

The Alamo Colleges District (ACD) includes minority serving institutions successfully incorporating climate science and sustainability-related projects to engage students in STEM courses. This network of five community colleges is based around San Antonio, Texas, and has a student population of approximately 60,000 that reflects the diversity of the community. San Antonio residents are familiar with recent extreme weather conditions, such as extreme droughts and intensified annual rainfalls, and the colleges understand the importance of education about climate science, climate change and sustainable solutions. This presentation will discuss initiatives to engage students in STEMS program while providing them with tools to solve climate change problems at a local level. ACD's innovative tools to train a green workforce is focused on engaging students in courses provided toward accredited certificates and degrees. Example of these courses include Wind Power Generation, Wind Turbine Troubleshooting, Solar Photovoltaics Systems, Wastewater Minimization and Waste Water Treatment. Students have access to a 400-kW PV system installed at the Center for Excellence that is used as a training tool in solar panel installation and maintenance. Also, solar panels on the rooftop of the Scobee Education Center and adjacent bus stops are connected to an eGauge system and used as simulation training about energy and space science. At Eco Centro, students have worked on solar hydroponic projects, the refurbishment of a shipping container for food production in a controlled atmosphere, and the installation of a shipping container home that will be used as a teaching facility about sustainable design and construction. Finally, a recent project to convert an old trailer into a Mobile Weather Station will be used as a STEM classroom to prepare students to understand weather data and its local applicability.

Reactor Physics Training

International Nuclear Information System (INIS)

Baeten, P.

2007-01-01

University courses in nuclear reactor physics at the universities consist of a theoretical description of the physics and technology of nuclear reactors. In order to demonstrate the basic concepts in reactor physics, training exercises in nuclear reactor installations are also desirable. Since the number of reactor facilities is however strongly decreasing in Europe, it becomes difficult to offer to students a means for demonstrating the basic concepts in reactor physics by performing training exercises in nuclear installations. Universities do not generally possess the capabilities for performing training exercises. Therefore, SCK-CEN offers universities the possibility to perform (on a commercial basis) training exercises at its infrastructure consisting of two research reactors (BR1 and VENUS). Besides the organisation of training exercises in the framework of university courses, SCK-CEN also organizes theoretical courses in reactor physics for the education and training of nuclear reactor operators. It is indeed a very important subject to guarantee the safe operation of present and future nuclear reactors. In this framework, an understanding of the fundamental principles of nuclear reactor physics is also necessary for reactor operators. Therefore, the organisation of a basic Nuclear reactor physics course at the level of reactor operators in the initial and continuous training of reactor operators has proven to be indispensable. In most countries, such training also results from the direct request from the safety authorities to assure the high level of competence of the staff in nuclear reactors. The objectives this activity are: (1) to provide training and education activities in reactor physics for university students and (2) to organise courses in nuclear reactor physics for reactor operators

Training and teaching with SILOETTE reactor and associated simulators at the Nuclear Research Centre of Grenoble

International Nuclear Information System (INIS)

Destot, M.

1983-10-01

Thanks to its three reactors SILOE (35 MW), MELUSINE (8 MW) and SILOETTE (100 KW), the Reactor Department of the Nuclear Research Centre of Grenoble has gained a considerable experience in the operation and utilization of research and material testing reactors. Inside of this general framework, the Reactor Department of Grenoble has built up a training and teaching centre that has been permanently active since 1975, with the aim of satisfying the considerable needs arising from the development of electro-nuclear power stations. The course is mainly intended for engineers and technicians who will be responsible for running power stations. A thorough series of practical exercices, carried out in the SILOETTE training reactor and in a PWR or in a Gas Cooled Reactor Simulator, desmonstrates the application of the theorical courses and familiarises the trainees with the behaviour of reactors and power stations

Future plans for the Imperial College CONSORT research reactor

International Nuclear Information System (INIS)

Franklin, S.J.

1999-01-01

The Imperial College (IC) research reactor was designed jointly by GEC and the IC Mechanical Engineering Department. It first went critical on 9 April 1965 and has been operating successfully for over 33 years. The reactor provides a service to both academia and industry for neutron activation analysis, reactor and applied nuclear physics training, neutron detector calibration, isotope production and irradiations. The reactor has strategic importance for the UK, as it is now the only remaining research reactor in the country. It is therefore important to put in place refurbishment programmes and to maintain and upgrade the safety case. This paper describes the current facilities, applications and users of the research reactor and outlines both the recent and the planned developments. (author)

Texas Academy of Mathematics and Science: 25 Years of Early College STEM Opportunities

Science.gov (United States)

Sayler, Michael F.

2015-01-01

The University of North Texas's Texas Academy of Mathematics and Science began admitting students to its 2-year early college entrance science, technology, engineering, and mathematics (STEM) program in the fall of 1988. This program provided accelerated entry for top students in Texas in the areas of mathematics and science. Approximately 200…

Nuclear Power Reactor simulator - based training program

International Nuclear Information System (INIS)

Abdelwahab, S.A.S.

2009-01-01

nuclear power stations will continue playing a major role as an energy source for electric generation and heat production in the world. in this paper, a nuclear power reactor simulator- based training program will be presented . this program is designed to aid in training of the reactor operators about the principles of operation of the plant. also it could help the researchers and the designers to analyze and to estimate the performance of the nuclear reactors and facilitate further studies for selection of the proper controller and its optimization process as it is difficult and time consuming to do all experiments in the real nuclear environment.this program is written in MATLAB code as MATLAB software provides sophisticated tools comparable to those in other software such as visual basic for the creation of graphical user interface (GUI). moreover MATLAB is available for all major operating systems. the used SIMULINK reactor model for the nuclear reactor can be used to model different types by adopting appropriate parameters. the model of each component of the reactor is based on physical laws rather than the use of look up tables or curve fitting.this simulation based training program will improve acquisition and retention knowledge also trainee will learn faster and will have better attitude

College credit for in-house training

International Nuclear Information System (INIS)

Reilly, K.; Getty, C.; Knief, R.

1981-01-01

The Program on Non-Collegiate Sponsored Instruction (PONSI) and similar organizations may be of considerable help to the industry to the extent that college credit can be awarded for certain activities in reactor site training programs. The credit recommendations generally may be used at local colleges. They also may be applied (along with credit for college-level activities such as correspondence and on-campus courses, proficiency testing, and other evaluations) to degrees granted by the Regent's External Degree Program (REX) and other organizations. This paper describes the principle features of the PONSI and REX programs. PONSI's first credit evaluation at a nuclear plant - Consolidated Edison's Indian Point 2 - is summarized. Recent proposals for an explicit nuclear degree through REX are also described briefly

Defense Base Realignment and Closure Budget Data for Naval Air Stations Dallas, Texas, and Memphis, Tennessee, Realigning to Carswell Air Reserve Base, Texas

National Research Council Canada - National Science Library

Granetto, Paul

1994-01-01

.... This report provides the results of the audit of 16 projects, valued at $122 million, for the realignment of the Naval Air Stations Memphis, Tennessee, and Dallas, Texas, to Carswell Air Reserve Base, Texas...

Technology, safety and costs of decommissioning nuclear reactors at multiple-reactor stations

International Nuclear Information System (INIS)

Wittenbrock, N.G.

1982-01-01

Safety and cost information is developed for the conceptual decommissioning of large (1175-MWe) pressurized water reactors (PWR) and large (1155-MWe) boiling water reactors (BWR) at multiple-reactor stations. Three decommissioning alternatives are studied: DECON (immediate decontamination), SAFSTOR (safe storage followed by deferred decontamination), and ENTOMB (entombment). Safety and costs of decommissioning are estimated by determining the impact of probable features of multiple-reactor-station operation that are considered to be unavailable at a single-reactor station, and applying these estimated impacts to the decommissioning costs and radiation doses estimated in previous PWR and BWR decommissioning studies. The multiple-reactor-station features analyzed are: the use of interim onsite nuclear waste storage with later removal to an offsite waste disposal facility, the use of permanent onsite nuclear waste disposal, the dedication of the site to nuclear power generation, and the provision of centralized services

SILOETTE, a training centre for reactor physics at the Nuclear Research Centre of Grenoble

International Nuclear Information System (INIS)

Destot, M.

1983-10-01

The Reactor Department of Grenoble has created, based on Siloette, an activity of training in reactor physics, wich is running since 1975 to meet the important needs generated by the development of electronuclear power stations. Its essential goal is to provide an initiation to the basic physical phenomena which determine the operation of the reactors. For that purpose, a rather comprehensive program of practical works on reactor (SILOETTE) and on nuclear power station simulators (PWR, UNGG) is proposed besides lectures and conferences, general and specialized teaching on the reactor operation principle, kinetics, dynamics and thermics

Ten years of TRIGA reactor research at the University of Texas

International Nuclear Information System (INIS)

O'Kelly, Sean

2002-01-01

The 1 MW TRIGA Research Reactor at the Nuclear Engineering Teaching Laboratory is the second TRIGA at the University of Texas at Austin (UT). A small (10 kW-1963, 250 kW-1968) TRIGA Mark I was housed in the basement of the Engineering Building until is was shutdown and decommissioned in 1989. The new TRIGA Mark II with a licensed power of 1.1 MW reached initial criticality in 1992. Prior to 1990, reactor research at UT usually consisted of projects requiring neutron activation analysis (NAA) but the step up to a much larger reactor with neutron beam capability required additional personnel to build the neutron research program. The TCNS is currently used to perform Prompt Gamma Activation Analysis to determine hydrogen and boron concentrations of various composite materials. The early 1990s was a very active period for neutron beam projects at the NETL. In addition to the TCNS, a real-time neutron radiography facility (NIF) and a high-resolution neutron depth profiling facility (NDP) were installed in two separate beam ports. The NDP facility was most recently used to investigate alpha damage on stainless steel in support of the U.S. Nuclear Weapons Stewardship programs. In 1999, a sapphire beam filter was installed in the NDP system to reduce the fast neutron flux at the sample location. A collaborative effort was started in 1997 between UT-Austin and the University of Texas at Arlington to build a reactor-based, low-energy positron beam (TIPS). The limited success in obtaining funding has placed the project on hold. The Nuclear and Radiation Engineering Program has grown rapidly and effectively doubled in size over the past 5 years but years of low nuclear research funding, an overall stagnation in the U.S. nuclear power industry and a persuasive public distrust of nuclear energy has caused a precipitous decline in many programs. Recently, the U.S. DOE has encouraged University Research Reactors (URR) in the U.S. to collaborate closely together by forming URR

77 FR 39996 - Department of Mechanical Engineering, Texas A&M University, Notice of Decision on Application for...

Science.gov (United States)

2012-07-06

... DEPARTMENT OF COMMERCE International Trade Administration Department of Mechanical Engineering, Texas A&M University, Notice of Decision on Application for Duty-Free Entry of Scientific Instruments...: Department of Mechanical Engineering, Texas A&M University, College Station, TX 77843-3123. Instrument: Arc...

Development of Reactor TRIGA PUSPATI Simulator for Education and Training

International Nuclear Information System (INIS)

Mohd Sabri Minhat; Zarina Masood; Muhammad Rawi Mohamed Zin

2016-01-01

The real-time simulator for Reactor TRIGA PUSPATI (RTP) which is under development. The main purpose of this simulator is operator training and a dynamic test bed (DTB) to test and validate the control logics in reactor regulating system (RRS) of RTP. The simulator configuration is divided into hardware and software. The simulator hardware consists of a host computer, operator station, a network switch, control rod drive mechanism and a large display panel. The RTP hardwired panel is replicated similar to real console. The software includes a mathematical model includes reactor kinetics and thermal-hydraulics that implements plant dynamics in real-time using LabVIEW, an instructor station module work as host computer that manages user instructions, and a human machine interface module as a graphical user interface which is used in the real RTP plant. The developed TRIGA reactor simulators are installed in the Malaysian Nuclear Agency nuclear training center for reactor operator training. To use the simulator as a dynamic test-bed, the reactor regulating system modeling software of the simulator was replaced by actual RRS cabinet which is consist of Programmable Logic Controller (PLC) S7-1500, and was interfaced using a hard-wired and network-based interface. RRS cabinet generates control signals for reactor power control based on the various feedback signals from DTB such as neutron detector signal and control rod positions, and the DTB runs plant dynamics based on the RRS control signals. Thus the Hardware-In-the-Loop Simulation between RRS and the emulated plant (DTB) has been implemented and tested in this configuration. Normal and abnormal case test have been emulated for this project. In conclusion, the functions and the control performance of the developed RTP dynamic test bed simulator have been tested showing reasonable and acceptable results. (author)

Methods of selection and training of personnel for the Rajasthan atomic power station

International Nuclear Information System (INIS)

Sarma, M.S.R.; Wagadarikar, V.K.

1975-01-01

Personnel selected to work in a nuclear electric generating station rarely have the necessary knowledge and experience in all the related fields. A station can be operated and maintained and at the same time radiation doses absorbed by station personnel can be kept to a minimum only if the operating personnel are familiar with, and can be used for, all phases of station operation and the maintainers have more than one skill or trade. More technical knowledge and more diversified skills, in addition to those required in other industries, are needed because of the nature of the nuclear reactor and the associated radiation environment and high automation. A training programme has been developed at the Nuclear Training Centre (NTC) near the Rajasthan Atomic Power Station (RAPS), Kota, India, to cater to the needs of the operation and maintenance personnel for nuclear power stations including the Madras Atomic Power Station. This programme has been in operation for the last five years. The paper describes the method of recruitment/selection of various categories of personnel and the method of training them to meet the job requirements. (author)

Obtaining college credit for licensed operator courses at the Wolf Creek Generating Station

International Nuclear Information System (INIS)

Russo, C.W.; Coulthard, R.C.

1985-01-01

The presentation examined alternatives to formal college courses as a means to obtain college credit toward a baccalaureate degree for station operations personnel. The focus is on the American Council on Education (ACE-PONSI) program which evaluates and makes credit recommendations for courses sponsored by organizations, like utilities, whose primary function is not education. Significant elements of the licensed operator program were prepared for an ACE-PONSI review and determined to be equivalent to college level nuclear engineering technology course work. The ACE-PONSI evaluation provides a good foundation and a significant amount of the training program evaluation required prior to the INPO accreditation effort

ISIS Training Reactor: A Reactor Dedicated to Education and Training for Students and Professionals

International Nuclear Information System (INIS)

Foulon, F.

2014-01-01

Conclusion: • INSTN strategy: complete theoretical courses by practical courses on the ISIS research reactor. • Training courses integrated both in Academic degree programs and continuing education. • 27 hours of training courses have been developed focusing on the practical and safety aspects of reactor operation. • The Education and Training activity became the main activity of ISIS reactor: 400 trainees/year; 360 hours/year; 40% in English. • Remote access to the Training courses: Internet Reactor Laboratory under development to be started from 2014 to broadcast training courses from ISIS reactor to guest institutions

Effect of fungicides on sorghum anthracnose and grain mold in Burleson County, Texas, 2013

Science.gov (United States)

The experiment was conducted at the Texas AgriLife Experiment Station near College Station. The hybrids BH3822 and BH 5566 were planted in replicated plots and treatment arranged in a randomized, blocked factorial design. Each replicate consisted of four, 20 ft rows, with 30-in. row spacing and a ...

Effect of fungicides on sorghum anthracnose and grain mold in Burleson County, Texas, 2014

Science.gov (United States)

The experiment was conducted at the Texas A&M AgriLife Experiment Station near College Station (Burleson County), using the hybrids BH3822 and BH 5566. The seed was planted 10 Apr in a Belk clay soil. There were four replicates per treatment arranged in a randomized, blocked factorial design. Tre...

Differences in Persistence and Graduation Rates of Hispanic Students in Texas Community Colleges: A Texas Statewide Study

Science.gov (United States)

Stagg, Danielle R.

2017-01-01

Purpose: The purpose of this journal-ready dissertation was to examine the 1-year persistence rates of Hispanic community college students in Texas for the 2007-2008 through the 2013-2014 academic years. Specifically, the relationship of the 1-year persistence rates for Hispanic students as a function of their institutional status (i.e., stayed or…

Estimating Pedestrian flows at train stations using the Station Transfer Model

NARCIS (Netherlands)

Van den Heuvel, J.P.A.; Dekkers, K.; De Vos, S.

2012-01-01

Train stations play a vital role in the door to door travel experience of train passengers. From the passengers’ value of time perspective, the station is the weakest link in total time value of the journey. Within the station the transfer function – moving between the various transport modes and

An aerial radiological survey of the South Texas Project Electric Generating Station and surrounding area, Bay City, Texas

International Nuclear Information System (INIS)

Thompson, J.M.

1988-12-01

An aerial radiological survey was conducted over the South Texas Project Electric Generating Station (STPEGS) near Bay City, Texas, during the period 25 March to 4 April 1988. The purpose of the 259-square-kilometer (100-square-mile) survey was to document the terrestrial gamma environment of the plant and surrounding area. An exposure rate contour map at 1 meter above ground level (AGL) was constructed from the gamma data and overlaid on an aerial photograph and map of the area. Exposure rates were observed up to 10μR/h over land. No areas of enhanced exposure rates were observed. Ground-based exposure rate measurements and soil samples were obtained to support the aerial data. Oblique aerial photographs of the plant were also acquired during the survey. 9 refs., 4 figs., 1 tab

Training courses at VR-1 reactor

International Nuclear Information System (INIS)

Sklenka, L.; Kropik, M.

2006-01-01

This paper describes one of the main purposes of the VR-1 training reactor utilization - i.e. extensive educational program. The educational program is intended for the training of university students and selected nuclear power plant personnel. The training courses provide them experience in reactor and neutron physics, dosimetry, nuclear safety and operation of nuclear facilities. At present, the training course participants can go through more than 20 standard experimental exercises; particular exercises for special training can be prepared. Approximately 200 university students become familiar with the reactor (lectures, experiments, experimental and diploma works, etc.) every year. About 12 different faculties from Czech universities use the reactor. International co-operation with European universities in Germany, Hungary, Austria, Slovakia, Holland and UK is frequent. The VR-1 reactor takes also part in Eugene Wigner Course on Reactor Physics Experiments in the framework of European Nuclear Educational Network (ENEN) association. Recently, training courses for Bulgarian research reactor specialists supported by IAEA were carried out. An attractive program including demonstration of reactor operation is prepared also for high school students. Every year, more than 1500 high school students come to visit the reactor, as do many foreigner visitors. (author)

A facility for training Space Station astronauts

Science.gov (United States)

Hajare, Ankur R.; Schmidt, James R.

1992-01-01

The Space Station Training Facility (SSTF) will be the primary facility for training the Space Station Freedom astronauts and the Space Station Control Center ground support personnel. Conceptually, the SSTF will consist of two parts: a Student Environment and an Author Environment. The Student Environment will contain trainers, instructor stations, computers and other equipment necessary for training. The Author Environment will contain the systems that will be used to manage, develop, integrate, test and verify, operate and maintain the equipment and software in the Student Environment.

Called to Teach: Percy and Anna Pennybacker's Contributions to Education in Texas, 1880-1899

Science.gov (United States)

King, Kelley M.

2012-01-01

In 1879, with aid from the Peabody fund, Texas's first tax-supported teacher training institution, Sam Houston State Normal Institute (SHNI), opened on the site of the old Austin College in Huntsville (Richmond 1941, 37). The need for qualified educators in Texas was growing as the state struggled to make up for decades of neglect of and antipathy…

Training and Certification of Research Reactor Personnel

International Nuclear Information System (INIS)

Zarina Masood

2011-01-01

The safe operation of a research reactor requires that reactor personnel be fully trained and certified by the relevant authorities. Reactor operators at PUSPATI TRIGA Reactor underwent extensive training and are certified, ever since the reactor first started its operation in 1982. With the emphasis on enhancing reactor safety in recent years, reactor operator training and certification have also evolved. This paper discusses the changes that have to be implemented and the challenges encountered in developing a new training programme to be in line with the national standards. (author)

20 years of power station master training

International Nuclear Information System (INIS)

Schwarz, O.

1977-01-01

In the early fifties, the VGB working group 'Power station master training' elaborated plans for systematic and uniform training of power station operating personnel. In 1957, the first power station master course was held. In the meantime, 1.720 power station masters are in possession of a master's certificate of a chamber of commerce and trade. Furthermore, 53 power station masters have recently obtained in courses of the 'Kraftwerksschule e.V.' the know-how which enables them to also carry out their duty as a master in nuclear power stations. (orig.) [de

Safety Evaluation Report related to the construction permit and operating license for the research reactor at the University of Texas (Docket No. 50-602)

International Nuclear Information System (INIS)

1985-05-01

This Safety Evaluation Report for the application filed by the University of Texas for a construction permit and operating license to construct and operate a TRIGA research reactor has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is owned and operated by the University of Texas and is located at the university's Balcones Research Center, about 7 miles (11.6 km) north of the main campus in Austin, Texas. The staff concludes that the TRIGA reactor facility can be constructed and operated by the University of Texas without endangering the health and safety of the public

Training of research reactor personnel

International Nuclear Information System (INIS)

Cherruau, F.

1980-01-01

Research reactor personnel operate the reactor and carry out the experiments. These two types of work entail different activities, and therefore different skills and competence, the number of relevant staff being basically a function of the size, complexity and versatility of the reactor. Training problems are often reactor-specific, but the present paper considers them from three different viewpoints: the training or retraining of new staff or of personnel already employed at an existing facility, and training of personnel responsible for the start-up and operation of a new reactor, according to whether local infrastructure and experience already exist or whether they have to be built up from scratch. On-the-spot experience seems to be an essential basis for sound training, but requires teaching abilities and aids often difficult to bring together, and the availability of instructors that does not always fit in smoothly with current operational and experimental tasks. (author)

Energy balance and efficiency of power stations with a pulsed Tokamak reactor

International Nuclear Information System (INIS)

Davenport, P.A.; Mitchell, J.T.D.; Darvas, J.; Foerster, S.; Sack, B.

1976-06-01

The energy balance of a fusion power station based on the TOKAMAK concept is examined with the aid of a model comprising three distinct elements: the reactor, the energy converter and the reactor operation equipment. The efficiency of each element is expressed in terms of the various energy flows and the product of these efficiencies gives the net station efficiency. The analysis takes account of pulsed operation and has general applicability. Numerical values for the net station efficiency are derived from detailed estimates of the energy flows for a TOKAMAK reactor and its auxiliary equipment operating with advanced energy converters. The derivation of these estimates is given in eleven appendices. The calculated station efficiencies span ranges similar to those quoted for the current generation of fission reactors, though lower than those predicted for HTGR and LMFBR stations. Credible parameter domains for pulsed TOKAMAK operation are firmly delineated and factors inimical to improved performance are indicated. It is concluded that the net thermal efficiency of a TOKAMAK reactor power station based on present designs and using advanced thermal converters will be approximately 0.3 and is unlikely to exceed 0.33. (orig.) [de

Innovations and Enhancements for a Consortium of Big-10 University Research and Training Reactors. Final Report

International Nuclear Information System (INIS)

Brenizer, Jack

2011-01-01

The Consortium of Big-10 University Research and Training Reactors was by design a strategic partnership of seven leading institutions. We received the support of both our industry and DOE laboratory partners. Investments in reactor, laboratory and program infrastructure, allowed us to lead the national effort to expand and improve the education of engineers in nuclear science and engineering, to provide outreach and education to pre-college educators and students and to become a key resource of ideas and trained personnel for our U.S. industrial and DOE laboratory collaborators.

Hazardous materials emergency response training program at Texas A ampersand M University

International Nuclear Information System (INIS)

Stirling, A.G.

1989-01-01

The Texas Engineering Extension Service (TEEX) as the engineering vocational training arm of the Texas A ampersand M University system has conducted oil-spill, hazardous-material, and related safety training for industry since 1976 and fire suppression training since 1931. In 1987 TEEX conducted training for some 66,000 persons, of which some 6000 were in hazardous-materials safety training and 22,000 in fire suppression or related fields. Various laws and regulations exist relative to employee training at an industrial facility, such as the Hazard Communication Act, the Resource Conservation and Recovery Act (RCRA), the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA or more commonly Superfund), the Community Right to Know Law, and the Superfund Amendments and Reauthorization Act (SARA), Titles I and III. The TEEX programs developed on the foundation emphasize the hands-on approach (60% field exercises) to provide a comprehensive training curriculum resulting in regulatory compliance, an effective emergency response capability, a prepared community, and a safe work environment

Distance Education Programs in Texas Community & Technical Colleges: Assessing Student Support Services in a Virtual Environment.

Science.gov (United States)

Luedtke, Cherry Beth

This project evaluates the status of distance learning at 54 public, two-year community, and technical colleges in Texas. Data was collected from the Web sites of each of the institutions. The Web site data indicted that 44 of the colleges refer specifically to distance education courses offered. To assess what student support services are…

Associations between tobacco and nicotine product use and depressive symptoms among college students in Texas.

Science.gov (United States)

Bandiera, Frank C; Loukas, Alexandra; Wilkinson, Anna V; Perry, Cheryl L

2016-12-01

There is a well-established link between cigarette smoking and depression; less is known about the potential association between alternative tobacco products, such as hookah, cigars, smokeless tobacco, and electronic cigarette (e-cigarette use) with depression. The Food and Drug Administration (FDA) is now regulating tobacco products and is interested in tobacco product use among those with mental health problems and other special populations such as college students. Cross-sectional statewide convenience sample study of 5438 college students in 24 colleges and universities in Texas. Past 30-day use of hookah, cigar, smokeless tobacco, cigarette, and e-cigarette use were measured by self-report. Depressive symptoms were measured by the 10-item short form of the Center for Epidemiologic Studies scale. Only e-cigarette use was positively associated with depressive symptoms, even after accounting for all other tobacco products and socio-demographics. There were no significant interactions between race/ethnicity or gender with each of the tobacco products on depressive symptoms. E-cigarette use was positively associated with depressive symptoms among college students in Texas. Further research is needed to determine causality, which may inform FDA regulatory planning. Copyright © 2016 Elsevier Ltd. All rights reserved.

Texas Community College Graduation and Persistence Rates as a Function of Student Ethnicity

Science.gov (United States)

Spangler, J. Mark; Slate, John R.

2015-01-01

In this investigation, the graduation and persistence rates of Texas community college students by ethnic membership (i.e., White, Black, Hispanic, and Asian) for the 2000, 2004, 2005, 2006, 2007, 2008, 2009, and 2010 academic years were examined. Statistically significant differences were present between the 2000 and the 2010 graduation and…

INDUSTRIAL RADIOGRAPHY COURSE, INSTRUCTOR'S GUIDE, VOLUME 1.

Science.gov (United States)

Texas A and M Univ., College Station. Engineering Extension Service.

THE PURPOSE OF THE GUIDE IS TO GIVE MAXIMUM ASSISTANCE TO INSTRUCTORS IN PLANNING THE TRAINING OF LICENSED INDUSTRIAL RADIOGRAPHERS. IT WAS DEVELOPED BY THE ENGINEERING EXTENSION SERVICE, TEXAS AGRICULTURAL AND MECHANICAL UNIVERSITY, COLLEGE STATION, TEXAS. THE 21 UNITS INCLUDE (1) INDUSTRIAL APPLICATIONS, (2) NONDESTRUCTIVE TESTING METHODS, (3)…

Guiding Math Students to Campus Services: An Impact Evaluation of the Beacon Program at South Texas College

Science.gov (United States)

Visher, Mary; Butcher, Kristin F.; Cerna, Oscar S.

2011-01-01

This research rigorously evaluates whether a low-cost intervention can improve students' performance in developmental math. The "Beacon Mentoring Program" was developed at South Texas College by professors, administrators, and staff at the college. Surveys of students revealed that many did not have someone on campus whom they felt they…

Experience in using a research reactor for the training of power reactor operators

International Nuclear Information System (INIS)

Blotcky, A.J.; Arsenaut, L.J.

1972-01-01

A research reactor facility such as the one at the Omaha Veterans Administration Hospital would have much to offer in the way of training reactor operators. Although most of the candidates for the course had either received previous training in the Westinghouse Reactor Operator Training Program, had operated nuclear submarine reactors or had operated power reactors, they were not offered the opportunity to perform the extensive manipulations of a reactor that a small research facility will allow. In addition the AEC recommends 10 research reactor startups per student as a prerequisite for a cold operator?s license and these can easily be obtained during the training period

A history of effluent releases from the Texas A and M University reactor

Energy Technology Data Exchange (ETDEWEB)

Bates, E F; Neff, R D; Sandel, P S; Schoenbucher, B [Texas A and M University (United States)

1974-07-01

Since 1966 records of radioactive effluents releases from the Texas A and M University Research Reactor have been compiled. These data include particulate activity, noble gases, and liquid effluent releases. Particulate activity releases with half-lives greater than eight days were negligible and are not included in this presentation. Conversion from an MTR plate reactor to a TRIGA fueled reactor was completed in August 1968. Records of effluent releases of Argon-4l and liquids for the past, five years are summarized, in this presentation. These release data are compared to the current limits specified: in 10 CPR 20 and the limits appearing in proposed Appendix.

Typhus in Texas

Centers for Disease Control (CDC) Podcasts

Dr. Kristy Murray, an associate professor in pediatrics and assistant dean of the National School of Tropical Medicine at Baylor College of Medicine and Texas Children's Hospital, discusses increased cases of typhus in southern Texas.

Treasured Texas Theaters

Science.gov (United States)

Horton, Anita

2012-01-01

Dallas artist Jon Flaming's deep love of Texas is evident in his paintings and sculpture. Although he has created one sculptural Texas theater, his work primarily showcases old Texas barbershops, vacant homes, and gas stations. In this article, the author describes how her students, inspired by Flaming's works, created three-dimensional historical…

College and Career Counseling Training Initiative

Science.gov (United States)

Southern Regional Education Board (SREB), 2014

2014-01-01

The Southern Regional Education Board's (SREB) College and Career Counseling Training Initiative works to increase the knowledge and skills of counselors who advise students on their postsecondary aspirations. Membership in the initiative provides access to Strategies in College and Career Counseling, a series of online training modules that can…

Safety evaluation report related to the construction permit and operating license for the research reactor at the University of Texas (Docket No. 50-602)

International Nuclear Information System (INIS)

1992-01-01

The Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission (NRC) has prepared Supplement 1 to NUREG-1135, ''Safety Evaluation Report Related to the Construction Permit and Operating License for the Research Reactor at the University of Texas'' (SER) May 1985. The reactor facility is owned by The University of Texas at Austin (UT, the applicant) and is located at the University's Balcones Research Center in Austin, Texas. This supplement to the SER (SSER) describes the changes to the reactor facility design from the description in the SER. The SER and SSER together reflect the facility as built. The SSER also documents the reviews that the NRC has completed regarding the applicant's emergency plan, security plan, and technical specifications that were identified as open in the SER

Station blackout with reactor coolant pump seal leakage

International Nuclear Information System (INIS)

Evinay, A.

1993-01-01

The U.S. Nuclear Regulatory Commission (NRC) amended its regulations in 10CFR50 with the addition of a new section, 50.63, open-quotes Loss of All Alternating Current Power.close quotes The objective of these requirements is to ensure that all nuclear plants have the capability to withstand a station blackout (SBO) and maintain adequate reactor core cooling and containment integrity for a specified period of time. The NRC also issued Regulatory Guide (RG) 1.155, open-quotes Station Blackout,close quotes to provide guidance for meeting the requirements of 10CFR50.63. Concurrent with RG-1.155, the Nuclear Utility Management and Resources Council (NUMARC) has developed NUMARC 87-00 to address SBO-coping duration and capabilities at light water reactors. Licensees are required to submit a topical report based on NUMARC 87-00 guidelines, to demonstrate compliance with the SBO rule. One of the key compliance criteria is the ability of the plant to maintain adequate reactor coolant system (RCS) inventory to ensure core cooling for the required coping duration, assuming a leak rate of 25 gal/min per reactor coolant pump (RCP) seal in addition to technical specification (TS) leak rate

Station Stopping of Freight Trains with Pneumatic Braking

OpenAIRE

Yun Bai; Baohua Mao; Tinkin Ho; Yu Feng; Shaokuan Chen

2014-01-01

In Chinese mainline railway, freight trains need to stop within passenger stations at times because of the delayed passenger trains. Without any decision-support system, it is very difficult for drivers to stop trains within stations with consistency in one braking action. The reasons are that braking performance of train changes with the conditions of braking equipment and the drivers’ subjective evaluations of track profiles and braking distance are vague and imprecise. This paper presents ...

Safety operation of training reactor VR-1

International Nuclear Information System (INIS)

Matejka, K.

2001-01-01

There are three nuclear research reactors in the Czech Republic in operation now: light water reactor LVR-15, maximum reactor power 10 MW t , owner and operator Nuclear Research Institute Rez; light water zero power reactor LR-0, maximum reactor power 5 kW t , owner and operator Nuclear Research Institute Rez and training reactor VR-1 Sparrow, maximum reactor power 5 kW t , owner and operate Faculty of Nuclear Sciences and Physical Engineering, CTU in Prague. The training reactor VR-1 Vrabec 'Sparrow', operated at the Faculty of Nuclear Sciences and Physical Engineering, Czech Technical University in Prague, was started up on December 3, 1990. Particularly it is designed for training the students of Czech universities, preparing the experts for the Czech nuclear programme, as well as for certain research work, and for information programmes in the nuclear programme, as well as for certain research work, and for information programmes in sphere of using the nuclear energy (public relations). (author)

Differences in Texas Community College Certificate Completion Rates by Ethnicity/Race, Gender, and Institution Enrollment

Science.gov (United States)

Godley, Scott

2017-01-01

Purpose: The purpose of the first study within this journal-ready dissertation was to determine the extent to which ethnicity/race-based differences were present in Texas community college completion rates specifically within workforce certificate programs. Regarding the second study, the purpose was to determine the extent to which gender…

Education and Training on ISIS Research Reactor

International Nuclear Information System (INIS)

Foulon, F.; Badeau, G.; Lescop, B.; Wohleber, X.

2013-01-01

In the frame of academic and vocational programs the National Institute for Nuclear Science and Technology uses the ISIS research reactor as a major tool to ensure a practical and comprehensive understanding of the nuclear reactor physics, principles and operation. A large set of training courses have been developed on ISIS, optimising both the content of the courses and the pedagogical approach. Programs with duration ranging from 3 hours (introduction to reactor operation) to 24 hours (full program for the future operators of research reactors) are carried out on ISIS reactor. The reactor is operated about 350 hours/year for education and training, about 40 % of the courses being carried out in English. Thus, every year about 400 trainees attend training courses on ISIS reactor. We present here the ISIS research reactor and the practical courses that have been developed on ISIS reactor. Emphasis is given to the pedagogical method which is used to focus on the operational and safety aspects, both in normal and incidental operation. We will present the curricula of the academic and vocational courses in which the practical courses are integrated, the courses being targeted to a wide public, including operators of research reactors, engineers involved in the design and operation of nuclear reactors as well as staff of the regulatory body. We address the very positive impact of the courses on the development of the competences and skills of participants. Finally, we describe the Internet Reactor Laboratories (IRL) that are under development and will consist in broadcasting the training courses via internet to remote facilities or institutions

Education and Training on ISIS Research Reactor

Energy Technology Data Exchange (ETDEWEB)

Foulon, F.; Badeau, G.; Lescop, B.; Wohleber, X. [French Atomic Energy and Alternative Energies Commission, Paris (France)

2013-07-01

In the frame of academic and vocational programs the National Institute for Nuclear Science and Technology uses the ISIS research reactor as a major tool to ensure a practical and comprehensive understanding of the nuclear reactor physics, principles and operation. A large set of training courses have been developed on ISIS, optimising both the content of the courses and the pedagogical approach. Programs with duration ranging from 3 hours (introduction to reactor operation) to 24 hours (full program for the future operators of research reactors) are carried out on ISIS reactor. The reactor is operated about 350 hours/year for education and training, about 40 % of the courses being carried out in English. Thus, every year about 400 trainees attend training courses on ISIS reactor. We present here the ISIS research reactor and the practical courses that have been developed on ISIS reactor. Emphasis is given to the pedagogical method which is used to focus on the operational and safety aspects, both in normal and incidental operation. We will present the curricula of the academic and vocational courses in which the practical courses are integrated, the courses being targeted to a wide public, including operators of research reactors, engineers involved in the design and operation of nuclear reactors as well as staff of the regulatory body. We address the very positive impact of the courses on the development of the competences and skills of participants. Finally, we describe the Internet Reactor Laboratories (IRL) that are under development and will consist in broadcasting the training courses via internet to remote facilities or institutions.

Role of higher education in training of university and college graduates for Czechoslovak nuclear programme

International Nuclear Information System (INIS)

Urbanek, J.; Nemec, J.

1983-01-01

The mechanical engineering faculty of the College of Mechanical and Electrical Engineering in Plzen trains students in the field ''Thermal and nuclear power machines and equipment''. The study field is subdivided into two specializations: ''Nuclear power facilities'' and ''Thermal power facilities''. The former specialization provides students with knowledge in the foundations of calculations and design of nuclear reactors and accessories, of heat transfer with application to nuclear reactors, the foundations of nuclear physics, reactor physics, calculations of shielding and reactor control. The specialization ''Thermal power facilities'' acquaints the students with the foundations of computations and the design of steam and gas turbines and turbocompressors, production technology, assembly and operation, defects and their removal, the foundations of nuclear power facilities and the design of thermal power plants. At the electrical engineering faculty of the College the study field ''Electrical power engineering'' includes the specialization ''Nuclear power plants''. New study fields have been suggested following consultations with the SKODA production enterprise. It has been found that the immediate increased demand for nuclear power specialists, namely for the assembly, commissioning and operation of nuclear power plants, will have to be met by the redeployment of engineers inside the respective enterprises. (E.S.)

Institutional Researchers' Use of Qualitative Research Methods for Institutional Accountability at Two Year Colleges in Texas

Science.gov (United States)

Sethna, Bishar M.

2011-01-01

This study examined institutional researchers' use of qualitative methods to document institutional accountability and effectiveness at two-year colleges in Texas. Participants were Institutional Research and Effectiveness personnel. Data were collected through a survey consisting of closed and open ended questions which was administered…

Station blackout core damage frequency in an advanced nuclear reactor

International Nuclear Information System (INIS)

Carvalho, Luiz Sergio de

2004-01-01

Even though nuclear reactors are provided with protection systems so that they can be automatically shut down in the event of a station blackout, the consequences of this event can be severe. This is because many safety systems that are needed for removing residual heat from the core and for maintaining containment integrity, in the majority of the nuclear power plants, are AC dependent. In order to minimize core damage frequency, advanced reactor concepts are being developed with safety systems that use natural forces. This work shows an improvement in the safety of a small nuclear power reactor provided by a passive core residual heat removal system. Station blackout core melt frequencies, with and without this system, are both calculated. The results are also compared with available data in the literature. (author)

Impact of Providing Information to Parents in Texas about the Role of Algebra II in College Admission. REL 2018-290

Science.gov (United States)

Stoker, Ginger; Mellor, Lynn

2018-01-01

This study examines the impact of providing parents with an informational brochure about the role of algebra II in college access on students' grade 11 algebra II completion rates in Texas. One hundred nine schools, covering all 20 Educational Service Center regions in Texas, participated in the study. Parents in the 54 treatment schools were…

Final environmental statement related to the operation of Comanche Peak Steam Electric Station, Units 1 and 2: (Docket Nos. 50-445 and 50-446)

International Nuclear Information System (INIS)

1981-09-01

The proposed action is the issuance of operating licenses to the Texas Utilities Generating Company for the startup and operation of Units 1 and 2 of the Comanche Peak Steam Electric Station located on Squaw Creek Reservoir in Somervell County, Texas, about 7 km north-northeast of Glen Rose, Texas, and about 65 km southwest of Fort Worth in north-central Texas. The information in this environmental statement represents the second assessment of the environmental impact associated with the Comanche Peak Steam Electric Station pursuant to the guidelines of the National Environmental Policy Act of 1969 (NEPA) and 10 CFR Part 51 of the Commission's Regulations. After receiving an application to construct this station, the staff carried out a review of impact that would occur during its construction and operation. This evaluation was issued as a Final Environmental Statement -- Construction Phase. After this environmental review, a safety review, an evaluation by the Advisory Committee on Reactor Safeguards, and public hearings in Glen Rose, Texas, the US Atomic Energy Commission (now US Nuclear Regulatory Commission) issued construction permits for the construction of Units 1 and 2 of the Comanche Peak Steam Electric Station. 16 figs., 34 tabs

Comparative analysis of a nontraditional general chemistry textbook and selected traditional textbooks used in Texas community colleges

Science.gov (United States)

Salvato, Steven Walter

The purpose of this study was to analyze questions within the chapters of a nontraditional general chemistry textbook and the four general chemistry textbooks most widely used by Texas community colleges in order to determine if the questions require higher- or lower-order thinking according to Bloom's taxonomy. The study employed quantitative methods. Bloom's taxonomy (Bloom, Engelhart, Furst, Hill, & Krathwohl, 1956) was utilized as the main instrument in the study. Additional tools were used to help classify the questions into the proper category of the taxonomy (McBeath, 1992; Metfessel, Michael, & Kirsner, 1969). The top four general chemistry textbooks used in Texas community colleges and Chemistry: A Project of the American Chemical Society (Bell et al., 2005) were analyzed during the fall semester of 2010 in order to categorize the questions within the chapters into one of the six levels of Bloom's taxonomy. Two coders were used to assess reliability. The data were analyzed using descriptive and inferential methods. The descriptive method involved calculation of the frequencies and percentages of coded questions from the books as belonging to the six categories of the taxonomy. Questions were dichotomized into higher- and lower-order thinking questions. The inferential methods involved chi-square tests of association to determine if there were statistically significant differences among the four traditional college general chemistry textbooks in the proportions of higher- and lower-order questions and if there were statistically significant differences between the nontraditional chemistry textbook and the four traditional general chemistry textbooks. Findings indicated statistically significant differences among the four textbooks frequently used in Texas community colleges in the number of higher- and lower-level questions. Statistically significant differences were also found among the four textbooks and the nontraditional textbook. After the analysis of

Advances in commercial heavy water reactor power stations

International Nuclear Information System (INIS)

Brooks, G.L.

1987-01-01

Generating stations employing heavy water reactors have now firmly established an enviable record for reliable, economic electricity generation. Their designers recognize, however, that further improvements are both possible and necessary to ensure that this reactor type remains attractively competitive with alternative nuclear power systems and with fossil-fuelled generation plants. This paper outlines planned development thrusts in a number of important areas, viz., capital cost reduction, advanced fuel cycles, safety, capacity factor, life extension, load following, operator aida, and personnel radiation exposure. (author)

New training reactor at Dresden Technical University

International Nuclear Information System (INIS)

Hansen, W.; Knorr, J.; Wolf, T.

2006-01-01

A total of 14 low-power (up to 10 W) training reactors have been operated at German universities, 9 of them officially classified as being operational in 2004, though for very different uses. This number is expected to drop sharply. The only comprehensive upgrading of a training reactor took place at Dresden Technical University: AKR-2, the most modern facility in Germany, started routine operation in April 2005, under a newly granted license pursuant to Sec. 7, Subsec. 1 of the German Atomic Energy Act, for training students in nuclear technology, for suitable research projects, and a a center of information about reactor technology and nuclear technology for the interested public. One special aspect of this refurbishment was the installation of digital safety I and C systems of the TELEPERM XS line, which are used also in other modern plants. This fact, plus the easy possibility to use the plant for many basic experiments in reactor physics and radiation protection, make the AKR-2 attractive also to other users (e.g. for training reactor personnel or other persons working in nuclear technology). (orig.)

Basic training of nuclear power reactor personnel

International Nuclear Information System (INIS)

Palabrica, R.J.

1981-01-01

The basic training of nuclear power reactor personnel should be given very close attention since it constitutes the foundation of their knowledge of nuclear technology. Emphasis should be given on the thorough understanding of basic nuclear concepts in order to have reasonable assurance of successful assimilation by those personnel of more specialized and advanced concepts to which they will be later exposed. Basic training will also provide a means for screening to ensure that those will be sent for further spezialized training will perform well. Finally, it is during the basic training phase when nuclear reactor operators will start to acquire and develop attitudes regarding reactor operation and it is important that these be properly founded. (orig.)

IAEA Activities supporting education and training at research reactors

International Nuclear Information System (INIS)

Peld, N.D.; Ridikas, D.

2013-01-01

Full-text: Through the provision of neutrons for experiments and their historical association with universities, research reactors have played a prominent role in nuclear education and training of students, scientists and radiation workers. Today education and training remains the foremost application of research reactors, involving close to 160 facilities out of 246 operational. As part of its mandate to facilitate and expand the contribution of atomic energy to peace, health and prosperity throughout the world, the IAEA administers a number of activities intended to promote nuclear research and enable access to nuclear technology for peaceful purposes, one of which is the support of various education and training measures involving research reactors. In the last 5 years, education and training has formed one pillar for the creation of research reactor coalitions and networks to pool their resources and offer joint programmes, such as the on-going Group Fellowship Training Course. Conducted mainly through the Eastern European Research Reactor Initiative, this programme is a periodic sic week course for young scientists and engineers on nuclear techniques and administration jointly conducted at several member research reactor institutes. Organization of similar courses is under consideration in Latin America and the Asia-Pacific Region, also with support from the IAEA. Additionally, four research reactor institutes have begun offering practical education courses through virtual reactor experiments and operation known as the Internet Reactor Laboratory. Through little more than an internet connection and projection screens, university science departments can be connected regionally or bilaterally with the control room o a research reactor for various training activities. Finally, two publications are being prepared, namely Hands-On Training Courses Using Research Reactors and Accelerators, and Compendium on Education and training Based on Research Reactors. These

Incorporating Six Sigma Methodology Training into Chemical Engineering Education

Science.gov (United States)

Dai, Lenore L.

2007-01-01

Six Sigma is a buzz term in today's technology and business world and there has been increasing interest to initiate Six Sigma training in college education. We have successfully incorporated Six Sigma methodology training into a traditional chemical engineering course, Engineering Experimentation, at Texas Tech University. The students have…

The Design of Management Practices To Improve the Physical Plant Maintenance of Southwest Texas Junior College.

Science.gov (United States)

Box, Wilford Winston

A study was conducted of the physical plant maintenance department (PPMD) of Southwest Texas Junior College (SWTJC), in order to determine if the department was structured as a functional organization, if maintenance control procedures were in place, and if efficient management practices were being used. Consultations with the director of the PPMD…

Typhus in Texas

Centers for Disease Control (CDC) Podcasts

2017-07-06

Dr. Kristy Murray, an associate professor in pediatrics and assistant dean of the National School of Tropical Medicine at Baylor College of Medicine and Texas Children’s Hospital, discusses increased cases of typhus in southern Texas.  Created: 7/6/2017 by National Center for Emerging and Zoonotic Infectious Diseases (NCEZID).   Date Released: 7/6/2017.

RELAP/SCDAPSIM Reactor System Simulator Development and Training for University and Reactor Applications

International Nuclear Information System (INIS)

Hohorst, J.K.; Allison, C.M.

2010-01-01

The RELAP/SCDAPSIM code, designed to predict the behaviour of reactor systems during normal and accident conditions, is being developed as part of an international nuclear technology development program called SDTP (SCDAP Development and Training Program). SDTP involves more than 60 organizations in 28 countries. One of the important applications of the code is for simulator training of university faculty and students, reactor analysts, and reactor operations and technical support staff. Examples of RELAP/SCDAPSIM-based system thermal hydraulic and severe accident simulator packages include the SAFSIM simulator developed by NECSA for the SAFARI research reactor in South Africa, university-developed simulators at the University of Mexico and Shanghai Jiao Tong University in China, and commercial VISA and RELSIM packages used for analyst and reactor operations staff training. This paper will briefly describe the different packages/facilities. (authors)

RELAP/SCDAPSIM Reactor System Simulator Development and Training for University and Reactor Applications

Energy Technology Data Exchange (ETDEWEB)

Hohorst, J.K.; Allison, C.M. [Innovative Systems Software, 1242 South Woodruff Avenue, Idaho Falls, Idaho 83404 (United States)

2010-07-01

The RELAP/SCDAPSIM code, designed to predict the behaviour of reactor systems during normal and accident conditions, is being developed as part of an international nuclear technology development program called SDTP (SCDAP Development and Training Program). SDTP involves more than 60 organizations in 28 countries. One of the important applications of the code is for simulator training of university faculty and students, reactor analysts, and reactor operations and technical support staff. Examples of RELAP/SCDAPSIM-based system thermal hydraulic and severe accident simulator packages include the SAFSIM simulator developed by NECSA for the SAFARI research reactor in South Africa, university-developed simulators at the University of Mexico and Shanghai Jiao Tong University in China, and commercial VISA and RELSIM packages used for analyst and reactor operations staff training. This paper will briefly describe the different packages/facilities. (authors)

Ready Texas: Stakeholder Convening. Proceedings Report

Science.gov (United States)

Intercultural Development Research Association, 2016

2016-01-01

With the adoption of substantial changes to Texas high school curricula in 2013 (HB5), a central question for Texas policymakers, education and business leaders, families, and students is whether and how HB5 implementation impacts the state of college readiness and success in Texas. Comprehensive research is needed to understand the implications…

Training reactor deployment. Advanced experimental course on designing new reactor cores

International Nuclear Information System (INIS)

Skoda, Radek

2009-01-01

Czech Technical University in Prague (CTU) operating its training nuclear reactor VR1, in cooperation with the North West University of South Africa (NWU), is applying for accreditation of the experimental training course ''Advanced experimental course on designing the new reactor core'' that will guide the students, young nuclear engineering professionals, through designing, calculating, approval, and assembling a new nuclear reactor core. Students, young professionals from the South African nuclear industry, face the situation when a new nuclear reactor core is to be build from scratch. Several reactor core design options are pre-calculated. The selected design is re-calculated by the students, the result is then scrutinized by the regulator and, once all the analysis is approved, physical dismantling of the current core and assembling of the new core is done by the students, under a close supervision of the CTU staff. Finally the reactor is made critical with the new core. The presentation focuses on practical issues of such a course, desired reactor features and namely pedagogical and safety aspects. (orig.)

Rural southeast Texas air quality measurements during the 2006 Texas Air Quality Study.

Science.gov (United States)

Schade, Gunnar W; Khan, Siraj; Park, Changhyoun; Boedeker, Ian

2011-10-01

The authors conducted air quality measurements of the criteria pollutants carbon monoxide, nitrogen oxides, and ozone together with meteorological measurements at a park site southeast of College Station, TX, during the 2006 Texas Air Quality Study II (TexAQS). Ozone, a primary focus of the measurements, was above 80 ppb during 3 days and above 75 ppb during additional 8 days in summer 2006, suggestive of possible violations of the ozone National Ambient Air Quality Standard (NAAQS) in this area. In concordance with other air quality measurements during the TexAQS II, elevated ozone mixing ratios coincided with northerly flows during days after cold front passages. Ozone background during these days was as high as 80 ppb, whereas southerly air flows generally provided for an ozone background lower than 40 ppb. Back trajectory analysis shows that local ozone mixing ratios can also be strongly affected by the Houston urban pollution plume, leading to late afternoon ozone increases of as high as 50 ppb above background under favorable transport conditions. The trajectory analysis also shows that ozone background increases steadily the longer a southern air mass resides over Texas after entering from the Gulf of Mexico. In light of these and other TexAQS findings, it appears that ozone air quality is affected throughout east Texas by both long-range and regional ozone transport, and that improvements therefore will require at least a regionally oriented instead of the current locally oriented ozone precursor reduction policies.

Extensive utilization of training reactor VR-1

International Nuclear Information System (INIS)

Matejka, Karel; Sklenka, Lubomir

2003-01-01

Full text: The training reactor VR-1 Vrabec ('Sparrow'), operated at the Faculty of Nuclear Sciences and Physical Engineering, Czech Technical University in Prague, was started up on December 3, 1990. Particularly, it is designed and operated for training of students from Czech universities, preparing of experts for the Czech nuclear programme, as well as for certain research and development work, and for information programmes in the sphere of non-military nuclear energy use (public relation). The VR-1 training reactor is a pool-type light-water reactor based on enriched uranium with maximum thermal power 1kWth and short time period up to 5kW th . The moderator of neutrons is light demineralized water (H 2 O) that is also used as a reflector, a biological shielding, and a coolant. Heat is removed from the core with natural convection. The reactor core contains 14 to 18 fuel assemblies IRT-3M, depending on the geometric arrangement and kind of experiments to be performed in the reactor. The core is accommodated in a cylindrical stainless steel vessel - pool, which is filled with water. UR-70 control rods serve the reactor control and safe shutdown. Training of the VR-1 reactor provides students with experience in reactor and neutron physics, dosimetry, nuclear safety, and nuclear installation operation. Students from technical universities and from natural sciences universities come to the reactor for training. Approximately 200 university students are introduced to the reactor (lectures, experiments, experimental and diploma works, etc.) every year. About 12 different faculties from Czech universities use the reactor. International co-operation with European universities in Germany, Hungary, Austria, Slovakia, Holland and UK is frequent. Practical Course on Reactor Physics in Framework of European Nuclear Engineering Network has been newly introduced. Currently, students can try out more than 20 experimental exercises. Further training courses have been included

U.S. NRC training for research and training reactor inspectors

International Nuclear Information System (INIS)

Sandquist, G.M.; Kunze, J.F.

2011-01-01

Currently, a large number of license activities (Early Site Permits, Combined Operating License, reactor certifications, etc.), are pending for review before the United States Nuclear Regulatory Commission (US NRC). Much of the senior staff at the NRC is now committed to these review and licensing actions. To address this additional workload, the NRC has recruited a large number of new Regulatory Staff for dealing with these and other regulatory actions such as the US Fleet of Research and Test Reactors (RTRs). These reactors pose unusual demands on Regulatory Staff since the US Fleet of RTRs, although few (32 Licensed RTRs as of 2010), they represent a broad range of reactor types, operations, and research and training aspects that nuclear reactor power plants (such as the 104 LWRs) do not pose. The US NRC must inspect and regulate all these entities. This paper addresses selected training topics and regulatory activities provided US NRC Inspectors for US RTRs. (author)

Texas A and M University Nuclear Science Center. Twenty-first progress report, January 1-December 31, 1984

International Nuclear Information System (INIS)

Krohn, J.; Petesch, J.E.; Rogers, R.D.; Sandel, P.; Stasny, G.S.

1985-03-01

The Nuclear Science Center is operated by the Texas Engineering Experiment Station as a service to the Texas A and M University System and the State of Texas. The facility is available to the University, other educational institutions, governmental agencies, and private organizations and individuals. Reactor utilization decreased from 1983 as indicated by a slightly smaller number of samples irradiated and of total irradiations. Core VIII, established in December 1982, was used throughout 1984. Several major facility projects modifications, and improvements were completed during the past year. Experimentally the Beam Port No. 4 reflector and shutter was improved, the pulsing instrumentation is being expanded, and the pneumatic system controller developed for Lab No. 4 is now in use in the Center for Trace Characterization (CTC) and Shell Development labs. Several operational problems occurred in 1984 but did not result in a significant loss of reactor operating time. During this reporting period there were no changes made to the site area; however, there has been made a proposal to extend the runway at nearby Easterwood Airport such tha larger aircraft can be accommodated. This extension should occur in 1985 and should have no affect on the air traffic patterns relative to the NSC. Administratively during 1984 efforts have been made to stabilize the reactor operations staff following the mid year resignations of both a Reactor Supervisor and Manager of Reactor Operations. A long term replacement has been hired to fill the vacated Reactor Supervisor position; however, the manager position has not yet been filled and those duties have been assumed by the Assistant Director

Forests of east Texas, 2016

Science.gov (United States)

Kerry Dooley

2018-01-01

This resource update provides an overview of forest resources in east Texas based on an inventory conducted by the U.S. Forest Service, Forest Inventory and Analysis (FIA) program at the Southern Research Station (SRS) in cooperation with Texas A&M Forest Service. The 254 counties of Texas are consolidated into seven FIA survey units—Southeast (unit 1),...

Culham conceptual Tokamak reactor MkII. Conceptual layout of buildings for a twin reactor power station

International Nuclear Information System (INIS)

Guthrie, J.A.S.; Harding, N.H.

1981-01-01

This paper discusses the conceptual design of the nuclear complex of a 2400 MWe twin fusion reactor power station utilising common services and a single containment building. The design is based upon environmental and maintenance logistical requirements, the provision of adequate storage, workshop and construction facilities and the constraints imposed by the geometry of the main and auxiliary reactor coolant systems. (author)

Development of Safety Review Guidance for Research and Training Reactors

International Nuclear Information System (INIS)

Oh, Kju-Myeng; Shin, Dae-Soo; Ahn, Sang-Kyu; Lee, Hoon-Joo

2007-01-01

The KINS already issued the safety review guidance for pressurized LWRs. But the safety review guidance for research and training reactors were not developed. So, the technical standard including safety review guidance for domestic research and training reactors has been applied mutates mutandis to those of nuclear power plants. It is often difficult for the staff to effectively perform the safety review of applications for the permit by the licensee, based on peculiar safety review guidance. The NRC and NSC provide the safety review guidance for test and research reactors and European countries refer to IAEA safety requirements and guides. The safety review guide (SRG) of research and training reactors was developed considering descriptions of the NUREG- 1537 Part 2, previous experiences of safety review and domestic regulations for related facilities. This study provided the safety review guidance for research and training reactors and surveyed the difference of major acceptance criteria or characteristics between the SRG of pressurized light water reactor and research and training reactors

Extensive utilization of training reactor VR-1

International Nuclear Information System (INIS)

Karel, Matejka; Lubomir, Sklenka

2005-01-01

This paper describes one of the main purposes of the VR-1 training reactor utilisation - i.e. extensive educational programme. The educational programme is intended for the training of university students (all technical universities in Czech Republic) and selected nuclear power plant personnel. At the present, students can go through more than 20 different experimental exercises. An attractive programme including demonstration of reactor operation is prepared also for high school students. Moreover, research and development works and information programmes proceed at the VR-1 reactor as well

Floods in Central Texas, September 7-14, 2010

Science.gov (United States)

Winters, Karl E.

2012-01-01

Severe flooding occurred near the Austin metropolitan area in central Texas September 7–14, 2010, because of heavy rainfall associated with Tropical Storm Hermine. The U.S. Geological Survey, in cooperation with the Upper Brushy Creek Water Control and Improvement District, determined rainfall amounts and annual exceedance probabilities for rainfall resulting in flooding in Bell, Williamson, and Travis counties in central Texas during September 2010. We documented peak streamflows and the annual exceedance probabilities for peak streamflows recorded at several streamflow-gaging stations in the study area. The 24-hour rainfall total exceeded 12 inches at some locations, with one report of 14.57 inches at Lake Georgetown. Rainfall probabilities were estimated using previously published depth-duration frequency maps for Texas. At 4 sites in Williamson County, the 24-hour rainfall had an annual exceedance probability of 0.002. Streamflow measurement data and flood-peak data from U.S. Geological Survey surface-water monitoring stations (streamflow and reservoir gaging stations) are presented, along with a comparison of September 2010 flood peaks to previous known maximums in the periods of record. Annual exceedance probabilities for peak streamflow were computed for 20 streamflow-gaging stations based on an analysis of streamflow-gaging station records. The annual exceedance probability was 0.03 for the September 2010 peak streamflow at the Geological Survey's streamflow-gaging stations 08104700 North Fork San Gabriel River near Georgetown, Texas, and 08154700 Bull Creek at Loop 360 near Austin, Texas. The annual exceedance probability was 0.02 for the peak streamflow for Geological Survey's streamflow-gaging station 08104500 Little River near Little River, Texas. The lack of similarity in the annual exceedance probabilities computed for precipitation and streamflow might be attributed to the small areal extent of the heaviest rainfall over these and the other gaged

Use of the VR-1 ''Vrabec'' training reactor

International Nuclear Information System (INIS)

Matejka, K.; Kolros, A.; Krops, S.; Polach, S.; Sklenka, L.

1994-01-01

An overview is presented of the extent and ways of using the VR-1 training reactor, which is operated by the Faculty of Nuclear Science and Physical Engineering, Czech Technical University in Prague. A list and the characteristics of 16 problems developed for teaching purposes is given, and the 14 faculties and 2 research institutes participating in the teaching activities are listed. The reactor is used in the education and training of nuclear scientists and engineers. The instrumentation, experimental, handling and operating tools, as well as documentation and texts relating to the reactor are described. The following examples of the teaching activities are included: a guided visit to the operating reactor site, reactor dynamics study and delayed neutron measurement, training course, and the basic criticality experiment. Nuclear safety aspects (hypothetical accidents, quality control and system qualification demonstration, safety culture) are stressed during the education. The reactor department is involved in international cooperation projects. (J.B.). 3 refs

Safety Evaluation Report related to the renewal of the operating license for the research reactor at Manhattan College (Docket No. 50-199)

International Nuclear Information System (INIS)

1985-02-01

This Safety Evaluation Report for the application filed by Manhattan College (MC) for a renewal of Operating License R-94 to continue to operate the MC 0.1-W open-pool training reactor has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is owned and operated by MC and is located two blocks away from the MC main campus in the Riverdale area of New York City, New York. The staff concludes that the reactor facility can continue to be operated by MC without endangering the health and safety of the public

Virginia power nuclear power station engineer training program

International Nuclear Information System (INIS)

Williams, T.M.; Haberstroh-Timpano, S.

1987-01-01

In response to the Institute of Nuclear Power Operations (INPO) accreditation requirements for technical staff and manager, Virginia Power developed the Nuclear Power Station Engineer Training Programs (NPSETP). The NPSETP is directed toward enhancing the specific knowledge and skills of company engineers, especially newly hired engineers. The specific goals of the program are to promote safe and reliable plant operation by providing engineers and appropriate engineering technicians with (1) station-specific basic skills; (2) station-specific specialized skills in the areas of surveillance and test, plant engineering, nuclear safety, and in-service inspection. The training is designed to develop, maintain, and document through demonstration the required knowledge and skills of the engineers in the identified groups at North Anna and Surry Power Stations. The program responds to American National Standards Institute, INPO, and US Nuclear Regulatory Commission standards

The Texas Ten Percent Plan's Impact on College Enrollment

Science.gov (United States)

Daugherty, Lindsay; Martorell, Paco; McFarlin, Isaac, Jr.

2014-01-01

The Texas Ten Percent Plan (TTP) provides students in the top 10 percent of their high-school class with automatic admission to any public university in the state, including the two flagship schools, the University of Texas at Austin and Texas A&M. Texas created the policy in 1997 after a federal appellate court ruled that the state's previous…

An A BWR demonstration simulator for training and developing technical staff

International Nuclear Information System (INIS)

Powers, J.; Yonezawa, H.; Aoyagi, Y.; Kataoka, K.

2015-09-01

The US-Advanced Boiling Water Reactor (A BWR), certified by the US NRC, is a third generation, evolutionary boiling water reactor design which is the reference for the South Texas Project Units 3 and 4 (STP3-4) Combined License Application (Cola). Nuclear Innovation North America (Nina) is the License Applicant for this new build project, and Toshiba is the selected primary technology contractor. Toshiba has developed a Demonstration Simulator of the A BWR control room that provides a realistic experience for training and education on BWR principles and operations fundamentals. The Demonstration Simulator is located in the Toshiba America Nuclear Energy (Tane) office in Charlotte, North Carolina and is composed of standard office computer equipment set up in a specific arrangement that is representative of the layout of an A BWR control room. The Demonstration Simulator is not intended for licensed operator training, but can provide a framework for encouraging entry level technically oriented nuclear workers to enter the operations field; strengthening the linkage between university energy field curricula and real-life application of theory; and, improving understanding of integrated plant operations for developing station technical staff. This paper describes the A BWR Demonstration Simulator and its applications for training and educating future nuclear workers. (Author)

An A BWR demonstration simulator for training and developing technical staff

Energy Technology Data Exchange (ETDEWEB)

Powers, J. [Toshiba America Nuclear Energy, Charlotte, North Carolina (United States); Yonezawa, H.; Aoyagi, Y.; Kataoka, K., E-mail: jim.powers@toshiba.com [Toshiba Corporation, Kawasaki, Kanagawa (Japan)

2015-09-15

The US-Advanced Boiling Water Reactor (A BWR), certified by the US NRC, is a third generation, evolutionary boiling water reactor design which is the reference for the South Texas Project Units 3 and 4 (STP3-4) Combined License Application (Cola). Nuclear Innovation North America (Nina) is the License Applicant for this new build project, and Toshiba is the selected primary technology contractor. Toshiba has developed a Demonstration Simulator of the A BWR control room that provides a realistic experience for training and education on BWR principles and operations fundamentals. The Demonstration Simulator is located in the Toshiba America Nuclear Energy (Tane) office in Charlotte, North Carolina and is composed of standard office computer equipment set up in a specific arrangement that is representative of the layout of an A BWR control room. The Demonstration Simulator is not intended for licensed operator training, but can provide a framework for encouraging entry level technically oriented nuclear workers to enter the operations field; strengthening the linkage between university energy field curricula and real-life application of theory; and, improving understanding of integrated plant operations for developing station technical staff. This paper describes the A BWR Demonstration Simulator and its applications for training and educating future nuclear workers. (Author)

A Demonstration Training Program for Potential School Dropouts. A Service Station Training School for Dropout-Prone Students.

Science.gov (United States)

Rull, Marvin H.; Moore, Richard O.

One phase of the curriculum demonstration program sponsored jointly by the Quincy Public Schools and Southern Illinois University is the Service Station Training School described within this report. The Service Station Training School was one of several sheltered work stations which were developed to provide preemployment experiences and training…

Radiation-hygienic estimation of training reactors location

International Nuclear Information System (INIS)

Konstantinov, Yu.O.; Fedorin, Eh.V.

1978-01-01

The radiation exposure conditions are provided during the normal operation (excluding emergency situations) of four training pool type reactors. Radiation monitoring of the environment near the reactors do not show any increase in external irradiation or in radioactive contamination over what is considered normal radiation background in the locality. Therefore it is possible to judge the potential levels of additional exposure of the population to radiation from the reactors only by means of theoretic modeling of the radiation conditions. Tabular data on maximal levels of this additional radiation are presented, and it is concluded from these data that it is permissible to install training and research reactors up to 3000 kilowatts within large cities, including dwelling areas

Safety evaluation report related to the renewal of the operating license for the training and research reactor at the University of Maryland (Docket No. 50-166)

International Nuclear Information System (INIS)

1984-03-01

This Safety Evaluation Report for the application filed by the University of Maryland (UMD) for a renewal of operating license R-70 to continue to operate a training and research reactor facility has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is owned and operated by the University of Maryland and is located at a site in College Park, Prince Georges County, Maryland. The staff concludes that this training reactor facility can continue to be operated by UMD without endangering the health and safety of the public

Nuclear power station with nuclear reactor accommodated largely secure against catastrophes

International Nuclear Information System (INIS)

Rosen, O.

1987-01-01

If the nuclear reactor is installed underground near the power station unit, then danger to the environment due to radiation contamination can be largely or nearly completely prevented by a covering of constant thickness or by a covering which can be installed by a catastrophic accident. The extinguishing of a burning reactor is also relatively simple for a reactor accommodated in a pit. The above-mentioned measures can be used individually or combined. (orig./HP) [de

Imperial College Reactor Centre annual report. 1984

International Nuclear Information System (INIS)

1985-01-01

The following new equipment is noted; for atomic absorption spectrometry to supplement the neutron activation analysis, and an additional nuclear data analysis system to improve the quality and speed of the service to users of the Centre's facilities. Users include undergraduates from the University of London, outside bodies such as the British Musueum, as well as departments of Colleges of the University of London. The reactor lost only three days through failures or faults. Two replacement fuel elements were put into the reactor during the year. The report contains brief accounts of 34 research programmes at the Centre. (U.K.)

Reactor coolant pump shaft seal stability during station blackout

International Nuclear Information System (INIS)

Rhodes, D.B.; Hill, R.C.; Wensel, R.G.

1987-05-01

Results are presented from an investigation into the behavior of Reactor Coolant Pump shaft seals during a potential station blackout (loss of all ac power) at a nuclear power plant. The investigation assumes loss of cooling to the seals and focuses on the effect of high temperature on polymer seals located in the shaft seal assemblies, and the identification of parameters having the most influence on overall hydraulic seal performance. Predicted seal failure thresholds are presented for a range of station blackout conditions and shaft seal geometries

Reactor coolant pump shaft seal stability during station blackout

Energy Technology Data Exchange (ETDEWEB)

Rhodes, D B; Hill, R C; Wensel, R G

1987-05-01

Results are presented from an investigation into the behavior of Reactor Coolant Pump shaft seals during a potential station blackout (loss of all ac power) at a nuclear power plant. The investigation assumes loss of cooling to the seals and focuses on the effect of high temperature on polymer seals located in the shaft seal assemblies, and the identification of parameters having the most influence on overall hydraulic seal performance. Predicted seal failure thresholds are presented for a range of station blackout conditions and shaft seal geometries.

Development and evaluation of a genomics training program for community health workers in Texas.

Science.gov (United States)

Chen, Lei-Shih; Zhao, Shixi; Stelzig, Donaji; Dhar, Shweta U; Eble, Tanya; Yeh, Yu-Chen; Kwok, Oi-Man

2018-01-04

PurposeGenomics services have the potential to reduce incidence and mortality of diseases by providing individualized, family health history (FHH)-based prevention strategies to clients. These services may benefit from the involvement of community health workers (CHWs) in the provision of FHH-based genomics education and services, as CHWs are frontline public health workers and lay health educators, who share similar ethnicities, languages, socioeconomic statuses, and life experiences with the communities they serve. We developed, implemented, and evaluated the FHH-based genomics training program for CHWs.MethodsThis theory- and evidence-based FHH-focused genomics curriculum was developed by an interdisciplinary team. Full-day workshops in English and Spanish were delivered to 145 Texas CHWs (91.6% were Hispanic/black). Preworkshop, postworkshop, and 3-month follow-up data were collected.ResultsCHWs significantly improved their attitudes, intention, self-efficacy, and knowledge regarding adopting FHH-based genomics into their practice after the workshops. At 3-month follow-up, these scores remained higher, and there was a significant increase in CHWs' genomics practices.ConclusionThis FHH-based genomics training successfully educated Texas CHWs, and the outcomes were promising. Dissemination of training to CHWs in and outside of Texas is needed to promote better access to and delivery of personalized genomics services for the lay and underserved communities.GENETICS in MEDICINE advance online publication, 4 January 2018; doi:10.1038/gim.2017.236.

Texas Real Estate Curriculum Workshop Summary Report.

Science.gov (United States)

Lyon, Robert

The Texas Real Estate Research Center-Texas Education Agency (TRERC-TEA) curriculum workshop was attended by over 40 participants representing 26 Texas community colleges. These participants divided into eight small groups by real estate specialty area and developed curriculum outlines and learning objectives for the following real estate courses:…

Restaurant Training Recipe At Triton College

Science.gov (United States)

Quagliano, Joseph

1974-01-01

The successful restaurant training program at Triton College (Illinois) involves a broadly based, two-year curriculum offering practical training in nearly all the areas associated with a comprehensive food operation--management, food preparation, menu planning, nutrition, personnel vending, dining room service, and cost control. (Author/EA)

Jordan Research and Training Reactor (JRTR) Utilization Facilities

International Nuclear Information System (INIS)

Xoubi, N.

2013-01-01

Jordan Research and Training Reactor (JRTR) is a 5 MW light water open pool multipurpose reactor that serves as the focal point for Jordan National Nuclear Centre, and is designed to be utilized in three main areas: Education and training, nuclear research, and radioisotopes production and other commercial and industrial services. The reactor core is composed of 18 fuel assemblies, MTR plate type 19.75% enriched uranium silicide (U 3 Si 2 ) in aluminium matrix, and is reflected on all sides by beryllium and graphite. The reactor power is upgradable to 10 MW with a maximum thermal flux of 1.45×10 14 cm -2 s -1 , and is controlled by a Hafnium control absorber rod and B 4 C shutdown rod. The reactor is designed to include laboratories and classrooms that will support the establishment of a nuclear reactor school for educating and training students in disciplines like nuclear engineering, reactor physics, radiochemistry, nuclear technology, radiation protection, and other related scientific fields where classroom instruction and laboratory experiments will be related in a very practical and realistic manner to the actual operation of the reactor. JRTR is designed to support advanced nuclear research as well as commercial and industrial services, which can be preformed utilizing any of its 35 experimental facilities. (author)

Study of basic-life-support training for college students.

Science.gov (United States)

Srivilaithon, Winchana; Amnaumpatanapon, Kumpon; Limjindaporn, Chitlada; Imsuwan, Intanon; Daorattanachai, Kiattichai

2015-03-01

To study about attitude and knowledge regarding basic-life-support among college students outside medical system. The cross-sectional study in the emergency department of Thammasat Hospital. The authors included college students at least aged 18 years old and volunteers to be study subjects. The authors collected data about attitudes and knowledge in performing basic-life-support by using set of questionnaires. 250 college students participated in the two hours trainingprogram. Most ofparticipants (42.4%) were second-year college students, of which 50 of 250 participants (20%) had trained in basic-life-support program. Twenty-seven of 250 participants (10.8%) had experience in basic-life-support outside the hospital. Most of participants had good attitude for doing basic-life-support. Participants had a significant improved score following training (mean score 8.66 and 12.34, respectively, pbasic-life-support to cardiac arrest patient. The training program in basic-life-support has significant impact on knowledge after training.

Differences in Persistence and Graduation Rates of Black Students in Texas Community Colleges: A Multiyear, Statewide Study

Science.gov (United States)

Moss, Sheldon

2017-01-01

Purpose: The purpose of this journal-ready dissertation was to examine the 1-year and 2-year persistence rates of Black students in Texas community colleges for the 2007-2008 through the 2014-2015 academic years. Specifically, the relationship of the 1-year and 2-year persistence rates for Black students as a function of their institutional status…

78 FR 12010 - Radio Broadcasting Services; Pearsall, Texas

Science.gov (United States)

2013-02-21

... Broadcasting Services; Pearsall, Texas AGENCY: Federal Communications Commission. ACTION: Proposed rule... (``Petitioner''), licensee of FM Station KSAG, Channel 277A, Pearsall, Texas. Petitioner proposes to amend the... be allotted at Pearsall, Texas, in compliance with the Commission's minimum distance separation...

Development, Implementation, and Evaluation of a Strategic Plan for Improving Physical Plant Management at Southwest Texas Junior College.

Science.gov (United States)

Box, Wilford Winston

A study was conducted at Southwest Texas Junior College (STJC) to assess current management practices used by the physical plant maintenance department (PPMD) and to develop a strategic plan for physical plant management. Procedures included an analysis of current management practices and systems that affect physical resources, and periodic and…

The Effect of Math Anxiety on the Academic Success of Developmental Mathematics Students at a Texas Community College

Science.gov (United States)

Fannin-Carroll, Kristen D.

2014-01-01

The purpose of this study was to examine the relationship between math anxiety and academic success of developmental mathematics students at a Texas community college based on age, gender, and level of developmental mathematics program. A quantitative, casual-comparative design was used to determine relationships. A total of 185 developmental…

Networked simulation for team training of Space Station astronauts, ground controllers, and scientists - A training and development environment

Science.gov (United States)

Hajare, Ankur R.; Wick, Daniel T.; Bovenzi, James J.

1991-01-01

The purpose of this paper is to describe plans for the Space Station Training Facility (SSTF) which has been designed to meet the envisioned training needs for Space Station Freedom. To meet these needs, the SSTF will integrate networked simulators with real-world systems in five training modes: Stand-Alone, Combined, Joint-Combined, Integrated, and Joint-Integrated. This paper describes the five training modes within the context of three training scenaries. In addition, this paper describes an authoring system which will support the rapid integration of new real-world system changes in the Space Station Freedom Program.

Furthering Medical Education in Texas.

Science.gov (United States)

Varma, Surendra K; Jennings, John

2016-02-01

Medical education in Texas is moving in the right direction. The Texas Medical Association has been a major partner in advancing medical education initiatives. This special symposium issue on medical education examines residency training costs, the Next Accreditation System, graduate medical education in rural Texas, Texas' physician workforce needs, the current state of education reform, and efforts to retain medical graduates in Texas.

Multipurpose epithermal neutron beam on new research station at MARIA research reactor in Swierk-Poland

Energy Technology Data Exchange (ETDEWEB)

Gryzinski, M.A.; Maciak, M. [National Centre for Nuclear Research, Andrzeja Soltana 7, 05-400 Otwock-Swierk (Poland)

2015-07-01

planned to create fully equipped complex facility possible to perform various experiments on the intensive neutron beam. Epithermal neutron beam enables development across the full spectrum of materials research for example shielding concrete tests or electronic devices construction improvement. Due to recent reports on the construction of the accelerator for the Boron Neutron Capture Therapy (BNCT) it has the opportunity to become useful and successful method in the fight against brain and other types of cancers not treated with well known medical methods. In Europe there is no such epithermal neutron source which could be used throughout the year for training and research for scientist working on BNCT what makes the stand unique in Europe. Also our research group which specializes in mixed radiation dosimetry around nuclear and medical facilities would be able to carry out research on new detectors and methods of measurements for radiological protection and in-beam (therapeutic) dosimetry. Another group of scientists from National Centre for Nuclear Research, where MARIA research reactor is located, is involved in research of gamma detector systems. There is an idea to develop Prompt-gamma Single Photon Emission Computed Tomography (Pg- SPECT). This method could be used as imaging system for compounds emitting gamma rays after nuclear reaction with thermal neutrons e.g. for boron concentration in BNCT. Inside the room, where H2 channel is located, there is another horizontal channel - H1 which is also unused. Simultaneously with the construction of the H2 stand it will be possible to create special pneumatic horizontal mail inside the H1 channel for irradiation material samples in the vicinity of the core i.e. in the distal part of the H1 channel. It might expand the scope of research at the planned neutron station. Secondly it is planned to equip both stands with moveable positioning system, video system and facilities to perform animal experiments (anaesthesia, vital

Training and research reactor facility longevity extension program

International Nuclear Information System (INIS)

Carriveau, G.W.

1991-01-01

Since 1943, over 550 training and research reactors have been in operation. According to statistics from the International Atomic Energy Agency, ∼325 training and research reactors are currently in service. This total includes a wide variety of designs covering a range of power and research capabilities located virtually around the world. A program has been established at General Atomics (GA) that is dedicated to the support of extended longevity of training and research reactor facilities. Aspects of this program include the following: (1) new instrumentation and control systems; (2) improved and upgraded nuclear monitoring and control channels; (3) facility testing, repair and upgrade services that include (a) pool or tank integrity, (b) cooling system, and (c) water purification system; (4) fuel element testing procedures and replacement; (5) control rod drive rebuilding and upgrades; (6) control and monitoring system calibration and repair service; (7) training services, including reactor operations, maintenance, instrumentation calibration, and repair; and (8) expanded or new uses such as neutron radiography and autoradiography, isotope production, nuclear medicine, activation analysis, and material properties modification

Examination policy concerning the additional installation of No. 3 and No. 4 reactors in Takahama Nuclear Power Station and No. 3 and No. 4 reactors in Fukushima No. 2 Nuclear Power Station

International Nuclear Information System (INIS)

1980-01-01

The Nuclear Safety Commission decided the annual examination policy on the modification of reactor installation in Takahama Nuclear Power Station to construct No. 3 and No. 4 reactors inquired under date of November 26, 1979, by the Minister of International Trade and Industry, so that the examination results of the accident in Three Mile Island nuclear power station are reflected to the examination for the purpose of improving reactor safety. The examination results of the accident in Three Mile Island power station are being investigated by the Committee on Examination of Reactor Safety, based on the policy shown in ''On the second report of the special committee examining the accident in a nuclear power station in the U.S.'' determined by the Nuclear Safety Commission under date of September 13, 1979. Though the Committee will further clarify the past guideline about the items concerning the criteria, design and operation management, the Committee decided the tentative policy to reflect it to safety examination. Further, a table is attached, in which 52 items to be reflected to the security measures are classified from the viewpoint of necessity to reflect them to the final examination. This table includes 13 items of criteria and examination, 7 items related to design, 10 items related to operation management, 10 antidisaster items, and 12 items related to safety research. (Wakatsuki, Y.)

Extensive utilisation of VR-1 reactor for nuclear education and training

International Nuclear Information System (INIS)

Rataj, J.

2010-01-01

The paper presents utilisation of the VR-1 reactor for nuclear education and training at national and international level. VR-1 reactor has been operating by the Czech Technical University since December 1990. The reactor is a pool-type light water reactor based on enriched uranium (19.7% 235 U) with maximum thermal power 1kW and for short time period up to 5kW. The moderator of neutrons is light water, which is also used as a reflector, a biological shielding and a coolant. Heat is removed from the core by natural convection. The pool disposition of the reactor facilitates access to the core, setting and removing of various experimental samples and detectors, easy and safe handling of fuel assemblies. The reactor core can contain from 17 to 21 fuel assemblies IRT-4M, depending on the geometric arrangement and kind of experiments to be performed in the reactor. The reactor is equipped with several experimental devices; e.g. horizontal, radial and tangential channels used to take out a neutron beam, reactivity oscillator for dynamics study and bubble boiling simulator. The reactor has been used very efficiently especially for education and training of university students and NPP's specialists for more than 18 years. The VR-1 reactor is utilised within various national and international activities such as Czech Nuclear Education Network (CENEN), European Nuclear Education Network and also Eastern European Research Reactor Initiative (EERRI). The reactor is well equipped for education and training not only by the experimental facility itself but also by incessant development of training methods and improvement of education experiments. The education experiments can be combined into training courses attended by students according to their study specialization and knowledge level. The training programme is aimed to the reactor and neutron physics, dosimetry, nuclear safety, and control of nuclear installations. Every year, approximately 250 university students undergo

INTELLECTUAL MODEL FORMATION OF RAILWAY STATION WORK DURING THE TRAIN OPERATION EXECUTION

Directory of Open Access Journals (Sweden)

O. V. Lavrukhin

2014-11-01

Full Text Available Purpose. The aim of this research work is to develop an intelligent technology for determination of the optimal route of freight trains administration on the basis of the technical and technological parameters. This will allow receiving the operational informed decisions by the station duty officer regarding to the train operation execution within the railway station. Metodology. The main elements of the research are the technical and technological parameters of the train station during the train operation. The methods of neural networks in order to form the self-teaching automated system were put in the basis of the generated model of train operation execution. Findings. The presented model of train operation execution at the railway station is realized on the basis of artificial neural networks using learning algorithm with a «teacher» in Matlab environment. The Matlab is also used for the immediate implementation of the intelligent automated control system of the train operation designed for the integration into the automated workplace of the duty station officer. The developed system is also useful to integrate on workplace of the traffic controller. This proposal is viable in case of the availability of centralized traffic control on the separate section of railway track. Originality. The model of train station operation during the train operation execution with elements of artificial intelligence was formed. It allows providing informed decisions to the station duty officer concerning a choice of rational and a safe option of reception and non-stop run of the trains with the ability of self-learning and adaptation to changing conditions. This condition is achieved by the principles of the neural network functioning. Practical value. The model of the intelligent system management of the process control for determining the optimal route receptionfor different categories of trains was formed.In the operational mode it offers the possibility

Remerschen nuclear power station with BBR pressurized water reactor

International Nuclear Information System (INIS)

Hoffmann, J.P.

1975-01-01

On the basis of many decades of successful cooperation in the electricity supply sector with the German RWE utility, the Grand Duchy of Luxemburg and RWE jointly founded Societe Luxembourgeoise d'Energie Nucleaire S.A. (SENU) in 1974 in which each of the partners holds a fifty percent interest. SENU is responsible for planning, building and operating this nuclear power station. Following an international invitation for bids on the delivery and turnkey construction of a nuclear power station, the consortium of the German companies of Brown, Boveri and Cie. AG (BBC), Babcock - Brown Boveri Reaktor GmbH (BBR) and Hochtief AG (HT) received a letter of intent for the purchase of a 1,300 MW nuclear power station equipped with a pressurized water reactor. The 1,300 MW station of Remerschen will be largely identical with the Muelheim-Kaerlich plant under construction by the same consortium near Coblence on the River Rhine since early 1975. According to present scheduling, the Remerschen nuclear power station could start operation in 1981. (orig.) [de

Development of Research Reactor Simulator and Its Application to Dynamic Test-bed

International Nuclear Information System (INIS)

Kwon, Kee Choon; Park, Jae Chang; Lee, Seung Wook; Bang, Dane; Bae, Sung Won

2014-01-01

We developed HANARO and the Jordan Research and Training Reactor (JRTR) real-time simulator for operating staff training. The main purpose of this simulator is operator training, but we modified this simulator as a dynamic test-bed to test the reactor regulating system in HANARO or JRTR before installation. The simulator configuration is divided into hardware and software. The simulator hardware consists of a host computer, 6 operator stations, a network switch, and a large display panel. The simulator software is divided into three major parts: a mathematical modeling module, which executes the plant dynamic modeling program in real-time, an instructor station module that manages user instructions, and a human machine interface (HMI) module. The developed research reactors are installed in the Korea Atomic Energy Research Institute nuclear training center for reactor operator training. To use the simulator as a dynamic test-bed, the reactor regulating system modeling software of the simulator was replaced by a hardware controller and the simulator and target controller were interfaced with a hard-wired and network-based interface

Development of Research Reactor Simulator and Its Application to Dynamic Test-bed

Energy Technology Data Exchange (ETDEWEB)

Kwon, Kee Choon; Park, Jae Chang; Lee, Seung Wook; Bang, Dane; Bae, Sung Won [KAERI, Daejeon (Korea, Republic of)

2014-08-15

We developed HANARO and the Jordan Research and Training Reactor (JRTR) real-time simulator for operating staff training. The main purpose of this simulator is operator training, but we modified this simulator as a dynamic test-bed to test the reactor regulating system in HANARO or JRTR before installation. The simulator configuration is divided into hardware and software. The simulator hardware consists of a host computer, 6 operator stations, a network switch, and a large display panel. The simulator software is divided into three major parts: a mathematical modeling module, which executes the plant dynamic modeling program in real-time, an instructor station module that manages user instructions, and a human machine interface (HMI) module. The developed research reactors are installed in the Korea Atomic Energy Research Institute nuclear training center for reactor operator training. To use the simulator as a dynamic test-bed, the reactor regulating system modeling software of the simulator was replaced by a hardware controller and the simulator and target controller were interfaced with a hard-wired and network-based interface.

Training and research on the nuclear reactor VR-1

International Nuclear Information System (INIS)

Matejka, K.

1998-01-01

The VR-1 training reactor is a light water reactor of the pool type using enriched uranium as the fuel. The moderator is demineralized light water, which also serves as the neutron reflector, biological shielding, and coolant. Heat evolved during the fission process is removed by natural convection. The reactor is used in the education of students in the field of reactor and neutron physics, dosimetry, nuclear safety, and instrumentation and control systems for nuclear facilities. Although primarily intended for students in various branches of technology (power engineering, nuclear engineering, physical engineering), this specialized facility is also used by students of faculties educating future natural scientists and teachers. Typical tasks trained at the VR-1 reactor include: measurement of delayed neutrons; examination of the effect of various materials on the reactivity of the reactor; measurement of the neutron flux density by various procedures; measurement of reactivity by various procedures; calibration of reactor control rods by various procedures; approaching the critical state; investigation of nuclear reactor dynamics; start-up, control and operation of a nuclear reactor; and investigation of the effect of a simulated nucleate boil on reactivity. In addition to the education of university-level students, training courses are also organized for specialists in the Czech nuclear programme

Training simulator for advanced gas-cooled reactor (AGR) shutdown sequence equipment

International Nuclear Information System (INIS)

Shankland, J.P.; Nixon, G.L.

1978-01-01

Successful shutdown of nuclear plant is of prime importance for both safety and economic reasons and large sums of money are spent on equipment to make shutdowns fully automatic, thus removing the possibility of operator errors. While this aim can largely be realized, one must consider the possibility of automatic equipment or plant failures when operators are required to take manual action, and off-line training facilities should be available to operating staff to minimize the risk of incorrect actions being taken. This paper presents the practice adopted at Hunterston 'B' Nuclear Power Station to solve this problem and concerns the computer-based training simulator for the Reactor Shutdown Sequence Equipment (RSSE) which was commissioned in January 1977. The plant associated with shutdown is briefly described and the reasoning which shows the need for a simulator is outlined. The paper also gives details of the comprehensive facilities available on the simulator and goes on to describe the form that shutdown training takes and the experience gained at this time. (author)

Connecting strangers at a train station

DEFF Research Database (Denmark)

Serafin, Stefania; Böttcher, Niels; Pellarin, Lars

2005-01-01

In this paper we describe a virtual instrument or a performance space, placed at Høje Tåstrup train station in Denmark, which is meant to establish communicative connections between strangers, by letting users of the system create soundscapes together across the rails. We discuss mapping...

Development of the fuel-cycle costs in nuclear power stations with light-water reactors

International Nuclear Information System (INIS)

Brosch, R.; Moraw, G.; Musil, G.; Schneeberger, M.

1976-01-01

The authors investigate the fuel-cycle costs in nuclear power stations with light-water reactors in the Federal Republic of Germany in the years 1966 to 1976. They determine the effect of the price development for the individual components of the nuclear fuel cycle on the fuel-cycle costs averaged over the whole power station life. Here account is taken also of inflation rates and the change in the DM/US $ parity. In addition they give the percentage apportionment of the fuel-cycle costs. The authors show that real fuel-cycle costs for nuclear power stations with light-water reactors in the Federal Republic of Germany have risen by 11% between 1966 and 1976. This contradicts the often repeated reproach that fuel costs in nuclear power stations are rising very steeply and are no longer competitive. (orig.) [de

Forests of East Texas, 2014

Science.gov (United States)

Thomas J. Brandeis

2015-01-01

This resource update provides an overview of forest resources in east Texas derived from an inventory conducted by the U.S. Forest Service, Forest Inventory and Analysis (FIA) Program at the Southern Research Station in cooperation with the Texas A&M Forest Service. These estimates are based on field data collected using the FIA annualized sample design and are...

Forests of east Texas, 2013

Science.gov (United States)

K.J.W. Dooley; T.J. Brandeis

2014-01-01

This resource update provides an overview of forest resources in east Texas based on an inventory conducted by the U.S. Forest Service, Forest Inventory and Analysis (FIA) program at the Southern Research Station in cooperation with the Texas A&M Forest Service. Forest resource estimates are based on field data collected using the FIA annualized sample design and...

Reactor Vessel and Reactor Vessel Internals Segmentation at Zion Nuclear Power Station - 13230

Energy Technology Data Exchange (ETDEWEB)

Cooke, Conrad; Spann, Holger [Siempelkamp Nuclear Services: 5229 Sunset Blvd., (Suite M), West Columbia, SC, 29169 (United States)

2013-07-01

Zion Nuclear Power Station (ZNPS) is a dual-unit Pressurized Water Reactor (PWR) nuclear power plant located on the Lake Michigan shoreline, in the city of Zion, Illinois approximately 64 km (40 miles) north of Chicago, Illinois and 67 km (42 miles) south of Milwaukee, Wisconsin. Each PWR is of the Westinghouse design and had a generation capacity of 1040 MW. Exelon Corporation operated both reactors with the first unit starting production of power in 1973 and the second unit coming on line in 1974. The operation of both reactors ceased in 1996/1997. In 2010 the Nuclear Regulatory Commission approved the transfer of Exelon Corporation's license to ZionSolutions, the Long Term Stewardship subsidiary of EnergySolutions responsible for the decommissioning of ZNPS. In October 2010, ZionSolutions awarded Siempelkamp Nuclear Services, Inc. (SNS) the contract to plan, segment, remove, and package both reactor vessels and their respective internals. This presentation discusses the tools employed by SNS to remove and segment the Reactor Vessel Internals (RVI) and Reactor Vessels (RV) and conveys the recent progress. SNS's mechanical segmentation tooling includes the C-HORCE (Circumferential Hydraulically Operated Cutting Equipment), BMT (Bolt Milling Tool), FaST (Former Attachment Severing Tool) and the VRS (Volume Reduction Station). Thermal segmentation of the reactor vessels will be accomplished using an Oxygen- Propane cutting system. The tools for internals segmentation were designed by SNS using their experience from other successful reactor and large component decommissioning and demolition (D and D) projects in the US. All of the designs allow for the mechanical segmentation of the internals remotely in the water-filled reactor cavities. The C-HORCE is designed to saw seven circumferential cuts through the Core Barrel and Thermal Shield walls with individual thicknesses up to 100 mm (4 inches). The BMT is designed to remove the bolts that fasten the Baffle

Pressurized-water-reactor station blackout

International Nuclear Information System (INIS)

Dobbe, C.A.

1983-01-01

The purpose of the Severe Accident Sequence Analysis (SASA) Program was to investigate accident scenarios beyond the design basis. The primary objective of SASA was to analyze nuclear plant transients that could lead to partial or total core melt and evaluate potential mitigating actions. The following summarizes the pressurized water reactor (PWR) SASA effort at the Idaho National Engineering Laboratory (INEL). The INEL is presently evaluating Unresolved Safety Issue A-44 - Station Blackout from initiation of the transient to core uncovery. The balance of the analysis from core uncovery until fission product release is being performed at Sandia National Laboratory (SNL). The current analyses involve the Bellefonte Nuclear Steam Supply System (NSSS), a Babcock and Wilcox (B and W) 205 Fuel Assembly (205-FA) raised loop design to be operated by the Tennessee Valley Authority

Station Blackout Analysis of HTGR-Type Experimental Power Reactor

Science.gov (United States)

Syarip; Zuhdi, Aliq; Falah, Sabilul

2018-01-01

The National Nuclear Energy Agency of Indonesia has decided to build an experimental power reactor of high-temperature gas-cooled reactor (HTGR) type located at Puspiptek Complex. The purpose of this project is to demonstrate a small modular nuclear power plant that can be operated safely. One of the reactor safety characteristics is the reliability of the reactor to the station blackout (SBO) event. The event was observed due to relatively high disturbance frequency of electricity network in Indonesia. The PCTRAN-HTR functional simulator code was used to observe fuel and coolant temperature, and coolant pressure during the SBO event. The reactor simulated at 10 MW for 7200 s then the SBO occurred for 1-3 minutes. The analysis result shows that the reactor power decreases automatically as the temperature increase during SBO accident without operator’s active action. The fuel temperature increased by 36.57 °C every minute during SBO and the power decreased by 0.069 MW every °C fuel temperature rise at the condition of anticipated transient without reactor scram. Whilst, the maximum coolant (helium) temperature and pressure are 1004 °C and 9.2 MPa respectively. The maximum fuel temperature is 1282 °C, this value still far below the fuel temperature limiting condition i.e. 1600 °C, its mean that the HTGR has a very good inherent safety system.

Education and training by utilizing irradiation test reactor simulator

International Nuclear Information System (INIS)

Eguchi, Shohei; Koike, Sumio; Takemoto, Noriyuki; Tanimoto, Masataka; Kusunoki, Tsuyoshi

2016-01-01

The Japan Atomic Energy Agency, at its Japan Materials Testing Reactor (JMTR), completed an irradiation test reactor simulator in May 2012. This simulator simulates the operation, irradiation test, abnormal transient change during operation, and accident progress events, etc., and is able to perform operation training on reactor and irradiation equipment corresponding to the above simulations. This simulator is composed of a reactor control panel, process control panel, irradiation equipment control panel, instructor control panel, large display panel, and compute server. The completed simulator has been utilized in the education and training of JMTR operators for the purpose of the safe and stable operation of JMTR and the achievement of high operation rate after resuming operation. For the education and training, an education and training curriculum has been prepared for use in not only operation procedures at the time of normal operation, but also learning of fast and accurate response in case of accident events. In addition, this simulator is also being used in operation training for the purpose of contributing to the cultivation of human resources for atomic power in and out of Japan. (A.O.)

Research reactor facilities, recent developments at Imperial College, London

International Nuclear Information System (INIS)

Franklin, S.J.; Goddard, A.J.H.; O Connell, J.

1998-01-01

The 100 kW CONSORT pool-type reactor is now the only Research Reactor in the UK. Because of its strategic importance, Imperial College is continuing and accelerating a programme of refurbishment of the control system, and planning for a further fuel charge. These plans are described and the progress to date discussed. To this end, a description of the enhanced Safety Case being written is provided here and refueling plans discussed. The current range of facilities available is described, and future plans highlighted. (author)

Pre-license team training at San Onofre Nuclear Generating Station

International Nuclear Information System (INIS)

Freers, S.M.; Hyman, M.

1987-01-01

Team Training at San Onofre Nuclear Generating Station (SONGS) Units 2 and 3 has been developed to enhance the performance of station operations personnel. The FACT Training Program (Formality, Attention to Detail, Consistency and Team Effort) is the common denominator for operations team training. Compliance with good operating practices is enhanced by operators working as a team toward the same goal, using the same language, practicing the same operating and communication skills, possessing a clear understanding of individual roles and responsibilities of team members and practicing attention to detail in every task. These elements of effective teamwork are emphasized by the processes and criteria used in the Pre-License Operator Training Program at SONGS

Risk impact of planned maintenance configuration at South Texas Project Electric Generating Station

International Nuclear Information System (INIS)

Loh, W.T.; Fleming, K.N.; Grantom, C.R.

2004-01-01

This paper is based on a study done for the Houston Lighting and Power Company. The purpose of this study is to estimate the risk impact of planned maintenance configurations at South Texas Project Electric Generating Station (STPEGS). To date, the focus of the STP probabilistic safety assessment (PSA) program has been to analyze risk in terms of estimates of accident frequencies that are expressed on a time-averaged basis. Thus, estimates of quantities such as severe core damage frequency have been made such that the temporal variations of this frequency with changing plant configurations are averaged out over time. The only condition that has been imposed on these estimates is that the plant is initially operating at full power when potential initiating events might occur. (author)

Spirituality in Teacher Training at an Islamic College in Israel

Science.gov (United States)

Erdreich, Lauren

2016-01-01

This article looks at an Islamic teacher training college in Israel in an attempt to understand how religious revival shapes women's understandings of being Muslim women professionals in Israel. The college grew out of Islamic revival in Israel; its teacher training program reflects the sensibilities that Islamic revival hopes to foster in women…

Fuel Cell Stations Automate Processes, Catalyst Testing

Science.gov (United States)

2010-01-01

Glenn Research Center looks for ways to improve fuel cells, which are an important source of power for space missions, as well as the equipment used to test fuel cells. With Small Business Innovation Research (SBIR) awards from Glenn, Lynntech Inc., of College Station, Texas, addressed a major limitation of fuel cell testing equipment. Five years later, the company obtained a patent and provided the equipment to the commercial world. Now offered through TesSol Inc., of Battle Ground, Washington, the technology is used for fuel cell work, catalyst testing, sensor testing, gas blending, and other applications. It can be found at universities, national laboratories, and businesses around the world.

New human machine interface for VR-1 training reactor

International Nuclear Information System (INIS)

Kropik, M.; Matejka, K.; Sklenka, L.; Chab, V.

2002-01-01

The contribution describes a new human machine interface that was installed at the VR-1 training reactor. The human machine interface update was completed in the summer 2001. The human machine interface enables to operate the training reactor. The interface was designed with respect to functional, ergonomic and aesthetic requirements. The interface is based on a personal computer equipped with two displays. One display enables alphanumeric communication between a reactor operator and the control and safety system of the nuclear reactor. Messages appear from the control system, the operator can write commands and send them there. The second display is a graphical one. It is possible to represent there the status of the reactor, principle parameters (as power, period), control rods' positions, the course of the reactor power. Furthermore, it is possible to set parameters, to show the active core configuration, to perform reactivity calculations, etc. The software for the new human machine interface was produced in the InTouch developing environment of the WonderWare Company. It is possible to switch the language of the interface between Czech and English because of many foreign students and visitors at the reactor. The former operator's desk was completely removed and superseded with a new one. Besides of the computer and the two displays, there are control buttons, indicators and individual numerical displays of instrumentation there. Utilised components guarantee high quality of the new equipment. Microcomputer based communication units with proper software were developed to connect the contemporary control and safety system with the personal computer of the human machine interface and the individual displays. New human machine interface at the VR-1 training reactor improves the safety and comfort of the reactor utilisation, facilitates experiments and training, and provides better support of foreign visitors.(author)

The decommissioning of commercial magnox gas cooled reactor power stations in the United Kingdom

International Nuclear Information System (INIS)

Holt, G.

1998-01-01

There are nine commercial Magnox gas-cooled reactor power stations in the United Kingdom. Three of these stations have been shutdown and are being decommissioning, and plans have also been prepared for the eventual decommissioning of the remaining operational stations. The preferred strategy for the decommissioning of the Magnox power stations has been identified as 'Safestore' in which the decommissioning activities are carried out in a number of steps separated by quiescent periods of care and maintenance. The final clearance of the site could be deferred for up to 135 years following station shutdown so as to obtain maximum benefit from radioactive decay. The first step in the decommissioning strategy is to defuel the reactors and transport all spent and new fuel off the site. This work has been completed at all three shutdown stations. Decommissioning work is continuing on the three sites and has involved activities such as dismantling, decontamination, recycling and disposal of some plant and structures, and the preparation of others for retention on the site for a period of care and maintenance. Significant experience has been gained in the practical application of decommissioning, with successful technologies and processes being identified for a wide range of activities. For example, large and small metallic and concrete structures, some with complex geometries, have been successfully decontaminated. Also, the reactors have been prepared for a long period of care and maintenance, with instrumentation and sampling systems having been installed to monitor their continuing integrity. All of this work has been done under careful safety, technical, and financial control. (author)

Crustal deformation and seismic measurements in the region of McDonald Observatory, West Texas. [Texas and Northern Chihuahua, Mexico

Science.gov (United States)

Dorman, H. J.

1981-01-01

The arrival times of regional and local earthquakes and located earthquakes in the Basin and Range province of Texas and in the adjacent areas of Chihuahua, Mexico from January 1976 to August 1980 at the UT'NASA seismic array are summarized. The August 1931 Texas earthquake is reevaluated and the seismicity and crustal structure of West Texas is examined. A table of seismic stations is included.

Use of the Oregon State University TRIGA reactor for education and training

International Nuclear Information System (INIS)

Dodd, B.

1989-01-01

This paper summarizes the recent use of the Oregon State University TRIGA Reactor (OSTR) for education and training. In particular, data covering the last 5 yr are presented, which cover education through formal university classes, theses, public information, and school programs. Training is covered by presenting data on domestic and foreign reactor operator training, health physics training, and neutron activation analysis training. While education and training only occupy ∼16% of the OSTR's total use time, nevertheless, this is an important mission of all nonpower reactors that cannot be performed effectively in any other way

Integrating Faculty Led Service Learning Training to Quantify Height of Natural Resources from a Spatial Science Perspective

Science.gov (United States)

Unger, Daniel R.; Kulhavy, David L.; Busch-Petersen, Kai; Hung, I.-Kuai

2016-01-01

Arthur Temple College of Forestry and Agriculture (ATCOFA) faculty members were trained how to integrate service learning activities within senior level classes at Stephen F. Austin State University (SFASU) in Nacogdoches, Texas. The service learning training, taught under the acronym Mentored Undergraduate Scholarship (MUGS), involved meeting…

Preparedness of fire safety in underground train station: Comparison between train operators in Malaysia with other operators from the developed countries

Science.gov (United States)

Tajedi, Noor Aqilah A.; Sukor, Nur Sabahiah A.; Ismail, Mohd Ashraf M.; Shamsudin, Shahrul A.

2017-10-01

The purpose of this paper is to compare the fire evacuation plan and preparation at the underground train stations in the different countries. The methodology for this study was using the extended questionnaire survey to investigate the Rapid Rail Sdn Bhd, Malaysia's fire safety plan and preparation at the underground train stations. There were four sections in the questionnaire which included (i) background of the respondents, (ii) the details on the train stations, safety instruction and fire evacuation exercises (iii) technical systems, installation and equipment at the underground stations and (iv) procedures and technical changes related to fire safety that had been applied by the operators. Previously, the respondents from the different train operator services in the developed countries had completed the questionnaires. This paper extends the response from the Rapid Rail Sdn Bhd to compare the emergency procedures and preparation for fire event with the developed countries. As a result, this study found that the equipment and facilities that provided at the underground train stations that operated by Rapid Rail are relevant for fire safety procedures and needs. The main advantage for Rapid Rail is the underground stations were designed with two or more entrances/exits that may perform better evacuation compare to one main entrance/exit train stations in the other developed countries.

E-cigarette Use and Cigarette Smoking Cessation among Texas College Students.

Science.gov (United States)

Mantey, Dale S; Cooper, Maria R; Loukas, Alexandra; Perry, Cheryl L

2017-11-01

We examined the relationships between e-cigarette use and subsequent cigarette smoking behaviors at 6- and 12-month follow-ups among young adults. Participants were 18-29 year-old current and former cigarette smokers (N = 627) at 24 Texas colleges, participating in a 3-wave study. Multi-level, multivariable logistic regression models, accounting for school clustering, examined the impact of self-reported use of e-cigarettes on cigarette smoking status at 6- and 12-month follow-ups. Two mutually-exclusive groups of e-cigarette users were examined: those that used for cigarette smoking cessation and those that used for reasons other than cessation. Baseline covariates included socio-demographics, past quit attempts, nicotine dependence, cigarettes per day, and other tobacco use. Use of e-cigarettes for cigarette smoking cessation was associated with increased odds of cigarette smoking cessation at 6- and 12-month follow-ups, while using e-cigarettes for other reasons was not, when adjusting for covariates. Use of e-cigarettes for cigarette smoking cessation may reduce cigarette smoking rates in young adult college students. Additional research is needed examining e-cigarettes as a complement to evidence-based cessation resources that are associated with cigarette smoking cessation among young adults.

Computer based training simulator for Hunterston Nuclear Power Station

International Nuclear Information System (INIS)

Bowden, R.S.M.; Hacking, D.

1978-01-01

For reasons which are stated, the Hunterston-B nuclear power station automatic control system includes a manual over-ride facility. It is therefore essential for the station engineers to be trained to recognise and control all feasible modes of plant and logic malfunction. A training simulator has been built which consists of a replica of the shutdown monitoring panel in the Central Control Room and is controlled by a mini-computer. This paper highlights the computer aspects of the simulator and relevant derived experience, under the following headings: engineering background; shutdown sequence equipment; simulator equipment; features; software; testing; maintenance. (U.K.)

Radiation protection personnel training in Research Reactors

International Nuclear Information System (INIS)

Fernandez, Carlos Dario; Lorenzo, Nestor Pedro de

1996-01-01

The RA-6 research reactor is considering the main laboratory in the training of different groups related with radiological protection. The methodology applied to several courses over 15 years of experience is shown in this work. The reactor is also involved in the construction, design, start-up and sell of different installation outside Argentina for this reason several theoretical and practical courses had been developed. The acquired experience obtained is shown in this paper and the main purpose is to show the requirements to be taken into account for every group (subjects, goals, on-job training, etc) (author)

Maximizing the use of research reactors in training power reactor operating staff with special reference to US experience

International Nuclear Information System (INIS)

Cox, J.A.

1976-01-01

Research reactors have been used in training nuclear power plant personnel for many years. Using the experience in the United States of America a programme is proposed that will maximize the training conducted at a research reactor and lessen the time that the staff must spend training elsewhere. The programme is adaptable to future training of replacement staff and for staff retraining. (author)

VR-1 training reactor in use for twelve years to train experts for the Czech nuclear power sector

International Nuclear Information System (INIS)

Matejka, K.; Sklenka, L.

2003-01-01

The VR-1 training reactor has been serving students of the Faculty of Nuclear Science and Physical Engineering, Czech Technical University in Prague, for more than 12 years now. The operation history of the reactor is highlighted. The major changes made at the VR-1 reactor are outlined and the main experimentally verified core configurations are shown. Some components of the new equipment installed on the VR-1 reactor are described in detail. The fields of application are shown: the reactor serves not only the training of university students within whole Czech Republic but also the training of specialists, research activities, and information programmes in the nuclear power domain. (P.A.)

A Role for Community Colleges in Navy Training.

Science.gov (United States)

Golfin, Peggy A.; White, John D.; Curtin, Lisa A.

This document from the Center for Naval Analysis (CNA) discusses the role of community colleges in Navy training. CNA conducted a study to discover whether outsourcing courses such as air conditioning and refrigeration and information systems administration to community colleges was feasible and cost effective. Analyses focused on two community…

Rising Above the Storm: DIG TEXAS

Science.gov (United States)

Ellins, K. K.; Miller, K. C.; Bednarz, S. W.; Mosher, S.

2011-12-01

For a decade Texas educators, scientists and citizens have shown a commitment to earth science education through planning at the national and state levels, involvement in earth science curriculum and teacher professional development projects, and the creation of a model senior level capstone Earth and Space Science course first offered in 2010 - 2011. The Texas state standards for Earth and Space Science demonstrate a shift to rigorous content, career relevant skills and use of 21st century technology. Earth and Space Science standards also align with the Earth Science, Climate and Ocean Literacy framework documents. In spite of a decade of progress K-12 earth science education in Texas is in crisis. Many school districts do not offer Earth and Space Science, or are using the course as a contingency for students who fail core science subjects. The State Board for Educator Certification eliminated Texas' secondary earth science teacher certification in 2009, following the adoption of the new Earth and Space Science standards. This makes teachers with a composite teacher certification (biology, physics and chemistry) eligible to teach Earth and Space Science, as well other earth science courses (e.g., Aquatic Science, Environmental Systems/Science) even if they lack earth science content knowledge. Teaching materials recently adopted by the State Board of Education do not include Earth and Space Science resources. In July 2011 following significant budget cuts at the 20 Education Service Centers across Texas, the Texas Education Agency eliminated key staff positions in its curriculum division, including science. This "perfect storm" has created a unique opportunity for a university-based approach to confront the crisis in earth science education in Texas which the Diversity and Innovation in the Geosciences (DIG) TEXAS alliance aims to fulfill. Led by the Texas A&M University College of Geosciences and The University of Texas Jackson School of Geosciences, with

Education and research at the VR-1 Vrabec training reactor facility

International Nuclear Information System (INIS)

Matejka, K.

1993-01-01

The results of 12 years' efforts devoted to the construction of the VR-1 ''Vrabec'' training reactor at the Faculty of Nuclear Science and Physical Engineering, Czech Technical University in Prague and to establishing the training reactor department, as well as the contribution of the training reactor facility to the teaching and scientific activities of the Faculty are presented in a comprehensive manner. The thesis is divided into 2 parts: (i) preconditions, reactor construction and commissioning, and constituting the reactor department, and (ii) basic and comprehensive information concerning the current utilization of the reactor for the benefit of students from various university level institutions. The prospects of scientific activities of the department are also outlined. Attention is paid to selected nuclear safety aspects of the reactor during operation and teaching of students, as well as to its innovated digital control system whose implementation is planned. The results achieved are compared with the initial goals and with similar experience abroad. (P.A.)

Nuclear renaissance in the reactor training of Areva

International Nuclear Information System (INIS)

De Braquilanges, Bertrand; Napior, Amy; Schoenfelder, Christian

2010-01-01

Because of the perspectives of new builds, a significant increase in the number of design, construction and management personnel working in AREVA, their clients and sub-contractors has been estimated for the next future. In order to cope with the challenge to integrate newly hired people quickly and effectively into the AREVA workforce, a project - 'Training Task Force (TTF)' - was launched in 2008. The objective was to develop introductory and advanced courses and related tools harmonized between AREVA Training Centers in France, Germany and USA. First, a Global Plants Introductory Session (GPIS) was developed for newly hired employees. GPIS is a two weeks training course introducing in a modular way AREVA and specifically the activities and the reactors technical basics. As an example, design and operation of a nuclear power plant is illustrated on EPRTM. Since January 2009, these GPIS are held regularly in France, Germany and the US with a mixing of employees from these 3 regions. Next, advanced courses for more experienced employees were developed: - Advanced EPR TM , giving a detailed presentation of the EPR TM reactor design; - Codes and Standards; - Technical Nuclear Safety. Finally, feasibility studies on a Training Material Management (TMM) system, able to manage the training documentation, and on a worldwide training administration tool, were performed. The TTF project was completed mid of 2009; it transferred their recurrent activities to a new AREVA training department. This unit now consists of the French, German and US Reactors Training Centers. In particular, all courses developed by the TTF are now implemented worldwide with an opening to external trainees. The current worldwide course catalogue includes training courses for operation and maintenance personnel as well as for managers, engineers and non technical personnel of nuclear operators, suppliers, safety authorities and expert organizations. Training delivery is supported effectively by tools

French experience in operating pressurized water reactor power stations. Ten years' operation of the Ardennes power station

International Nuclear Information System (INIS)

Teste du Bailler, A.; Vedrinne, J.F.

1978-01-01

In the paper the experience gained over ten years' operation of the Ardennes (Chooz) nuclear power station is summarized from the point of view of monitoring and control equipment. The reactor was the first pressurized water reactor to be installed in France; it is operated jointly by France and Belgium. The equipment, which in many cases consists of prototypes, was developed for industrial use and with the experience that has now been gained it is possible to evaluate its qualities and defects, the constraints which it imposes and the action that has to be taken in the future. (author)

The Utilization of Dalat nuclear research reactor for education and training purposes

International Nuclear Information System (INIS)

Luong, Ba Vien; Nguyen, Nhi Dien; Le, Vinh Vinh; Nguyen, Xuan Hai

2017-01-01

The Dalat Nuclear Research Reactor (DNRR) with the nominal power of 500 kWt is today the unique one in Vietnam. It was designed for the purposes of radioisotope production, neutron activation analysis, basic and applied researches, and nuclear education and training. With the rising demand in development of human resources for utilization of atomic energy in the country, the DNRR has been playing an important role in the nuclear education and training for students from universities and professionals who are interested in reactor engineering. At present, the Dalat Nuclear Research Institute (DNRI) offers two types of training course utilizing the research reactor: an one-week practical training course is applied for undergraduate students and a two-week training course on reactor engineering is applied for the professionals. This paper presents the reactor facility and experiments performed at the DNRR for education and training purposes. In addition, the co-operation between the DNRI with national and international educational organizations for nuclear human resource development for national and regional demands is also mentioned in the paper. (author)

Nuclear training facilities at the Royal Naval College, Greenwich

International Nuclear Information System (INIS)

Head, J.L.; Lowther, C.A.; Marsh, J.R.W.

1986-01-01

The paper describes some of the nuclear training facilities at the Royal Naval College and the way the facilities are used in the training of personnel for the Naval nuclear propulsion programme. (author)

A small-scale experimental reactor combined with a simulator for training purposes

International Nuclear Information System (INIS)

Destot, M.; Hagendorf, M.; Vanhumbeeck, D.; Lecocq-Bernard, J.

1981-01-01

The authors discuss how a small-scale reactor combined to a training simulator can be a valuable aid in all forms of training. They describe the CEN-based SILOETTE reactor in Grenoble and its combined simulator. They also take a look at prospects for the future of the system in the light of experience acquired with the ARIANE reactor and the trends for the development of simulators for training purposes [fr

Improving the interview skills of college students using behavioral skills training.

Science.gov (United States)

Stocco, Corey S; Thompson, Rachel H; Hart, John M; Soriano, Heidi L

2017-07-01

Obtaining a job as a college graduate is partly dependent on interview performance. We used a multiple baseline design across skills to evaluate the effects of behavioral skills training with self-evaluation for five college students. Training effects were evaluated using simulated interviews as baseline and posttraining assessments. All participants acquired targeted skills, but we observed some individual differences. Participants were satisfied with training outcomes and rated the procedures as acceptable. Furthermore, ratings from university staff who provide interview training indicated that training improved performance across several skills for the majority of participants. © 2017 Society for the Experimental Analysis of Behavior.

Training of technical staff for nuclear power station operation

International Nuclear Information System (INIS)

Haire, T.P.; Myerscough, P.B.

1981-01-01

The statutory training requirements covering the technical staff in the CEGB (Central Electricity Generating Board) are discussed. Details of the training programmes emphasize the importance of the staff having a thorough understanding of the nuclear processes involved in the station operation and not relying solely upon a mechanistic approach to operating procedures. The impact of this philosophy on the design of training simulators is examined and a brief comparison is made with the training philosophies in other countries. (U.K.)

Assessing aquifer storage and recovery feasibility in the Gulf Coastal Plains of Texas

Directory of Open Access Journals (Sweden)

W. Benjamin Smith

2017-12-01

Full Text Available Study region: The Gulf Coast and Carrizo-Wilcox aquifer systems in the Gulf Coastal Plains of Texas. Study focus: Aquifer storage and recovery is a water storage alternative that is underutilized in Texas, a state with both long periods of drought and high intensity storms. Future water storage plans in Texas almost exclusively rely on surface reservoirs, subject to high evaporative losses. This study seeks to identify sites where aquifer storage and recovery (ASR may be successful, especially in recovery of injected waters, by analyzing publicly-available hydrogeologic data. Transmissivity, hydraulic gradient, well density, depth to aquifer, and depth to groundwater are used in a GIS-based index to determine feasibility of implementing an ASR system in the Gulf Coast and Carrizo-Wilcox aquifer systems. New hydrological insights for the region: Large regions of the central and northern Gulf Coast and the central and southern Carrizo-Wilcox aquifer systems are expected to be hydrologically feasible regions for ASR. Corpus Christi, Victoria, San Antonio, Bryan, and College Station are identified as possible cities where ASR would be a useful water storage strategy. Keywords: Aquifer storage and recovery (ASR, GIS, Gulf coast, Carrizo-Wilcox, Managed aquifer recharge (MAR

Instructional Technology Practices in Developmental Education in Texas

Science.gov (United States)

Martirosyan, Nara M.; Kennon, J. Lindsey; Saxon, D. Patrick; Edmonson, Stacey L.; Skidmore, Susan T.

2017-01-01

The purpose of this study was to examine the current state of technology integration in developmental education in Texas higher education. Analyzing survey data from developmental education faculty members in 70 2- and 4-year colleges in Texas, researchers identified instructor-reported best instructional technology practices in developmental…

Antecedents of positive self-disclosure online: an empirical study of US college students’ Facebook usage

OpenAIRE

Chen H

2017-01-01

Hongliang Chen Department of Communication, Texas A&M University, College Station, TX, USA Abstract: This study investigates the factors predicting positive self-disclosure on social networking sites (SNSs). There is a formidable body of empirical research relating to online self-disclosure, but very few studies have assessed the antecedents of positive self-disclosure. To address this literature gap, the current study tests the effects of self-esteem, life satisfact...

AN EXPLORATORY ANALYSIS OF FAMILIARITY AND WILLINGNESS TO USE ONLINE FOOD SHOPPING SERVICES IN A LOCAL AREA OF TEXAS

OpenAIRE

Hiser, Jennifer; Nayga, Rodolfo M., Jr.; Capps, Oral, Jr.

1999-01-01

Online food shopping is not only one of the newest innovations in grocery shopping but also one of the many services integrating the changing needs of consumers and the increasing use of modern technology. A survey was conducted in the Bryan/College Station area of Texas to determine a quantitative profile of consumers, via logit analysis, who are familiar with the concept of online food shopping and who are willing to use an online food shopping service. Older people, females, major shoppers...

Use of research reactors for training and teaching nuclear sciences

International Nuclear Information System (INIS)

Safieh, J.; Gless, B.

2002-01-01

Training activities on reactors are organized by Cea on 2 specially dedicated reactors Ulysse (Saclay) and Siloette (Grenoble) and 2 research reactors Minerve (Cadarache) and Azur (Cadarache, facility managed by Technicatome). About 4000 students have been trained on Ulysse since its commissioning more than 40 years ago. The concept that led to the design of Ulysse was to build a true reactor dedicated to teaching and training activities and that was able to operate with great flexibility and under high conditions of safety, this reactor is inspired from the Argonaut-type reactor. The main specificities of Ulysse are: a nominal power of 100 kW, a maximal thermal neutron flux of 1.4 10 12 n.cm -2 .s -1 , a 90 % enriched fuel, a graphite reflector, the use of water as coolant and moderator, and 6 cadmium plates as control rods. Ulysse allows students to get practical experience on a large range of topics: approach to criticality, effect of the starting neutron source, calibration of control rods, distribution of the neutron flux in the thermal column, temperature coefficient, radiation detectors, neutron activation analysis, and radioprotection. (A.C.)

Study on vibration characteristics and fault diagnosis method of oil-immersed flat wave reactor in Arctic area converter station

Science.gov (United States)

Lai, Wenqing; Wang, Yuandong; Li, Wenpeng; Sun, Guang; Qu, Guomin; Cui, Shigang; Li, Mengke; Wang, Yongqiang

2017-10-01

Based on long term vibration monitoring of the No.2 oil-immersed fat wave reactor in the ±500kV converter station in East Mongolia, the vibration signals in normal state and in core loose fault state were saved. Through the time-frequency analysis of the signals, the vibration characteristics of the core loose fault were obtained, and a fault diagnosis method based on the dual tree complex wavelet (DT-CWT) and support vector machine (SVM) was proposed. The vibration signals were analyzed by DT-CWT, and the energy entropy of the vibration signals were taken as the feature vector; the support vector machine was used to train and test the feature vector, and the accurate identification of the core loose fault of the flat wave reactor was realized. Through the identification of many groups of normal and core loose fault state vibration signals, the diagnostic accuracy of the result reached 97.36%. The effectiveness and accuracy of the method in the fault diagnosis of the flat wave reactor core is verified.

Texstar: The all-Texas educational satellite system

Science.gov (United States)

1990-01-01

Longhorn Satellite Company (LSC) has designed Texstar, and educational satellite communications system which will be considered as a means of equalizing the distribution of educational resources throughout the state of Texas. Texstar will be capable of broadcasting live lectures and documentaries in addition to transmitting data from a centralized receiving-transmitting station. Included in the design of Texstar is the system and subsystem design for the satellite and the design of the ground stations. The launch vehicle used will be the Texas-built Conestoga 421-48. The Texstar system incorporates three small satellites in slightly inclined geosynchronous orbits. Due to the configuration and spacing of these satellites, the system will be accessed as if it were one large, geostationary satellite. Texstar is shown to be a viable option to the educational crisis in the state of Texas.

Cooling of nuclear power stations with high temperature reactors and helium turbine cycles

International Nuclear Information System (INIS)

Foerster, S.; Hewing, G.

1977-01-01

On nuclear power stations with high temperature reactors and helium turbine cycles (HTR-single circuits) the residual heat from the energy conversion process in the primary and intermediate coolers is removed from cycled gas, helium. Water, which is circulated for safety reasons through a closed circuit, is used for cooling. The primary and intermediate coolers as well as other cooling equipment of the power plant are installed within the reactor building. The heat from the helium turbine cycle is removed to the environment most effectively by natural draught cooling towers. In this way a net plant efficiency of about 40% is attainable. The low quantities of residual heat thereby produced and the high (in comparison with power stations with steam turbine cycles) cooling agent pressure and cooling water reheat pressure in the circulating coolers enable an economically favourable design of the overall 'cold end' to be expected. In the so-called unit range it is possible to make do with one or two cooling towers. Known techniques and existing operating experience can be used for these dry cooling towers. After-heat removal reactor shutdown is effected by a separate, redundant cooling system with forced air dry coolers. The heat from the cooling process at such locations in the power station is removed to the environment either by a forced air dry cooling installation or by a wet cooling system. (orig.) [de

Initiating Training Stations As Clusters of Learning in Fashion Merchandising

Science.gov (United States)

Garber, Jayne

1974-01-01

A Chicago business school offers fashion merchandising as one of several business curriculums that combines on-the-job training and classroom instruction. Instruction is organized around the occupational cluster concept which requires training stations that provide a wide variety of learning experiences. (EA)

Music training and semantic clustering in college students.

Science.gov (United States)

Hogan, David E; Huesman, Thomas

2008-12-01

College students with 5 or more years of music training recalled significantly more words from a 16-item word list than did students with 0-4 years of training. The superior recall of the extensively trained students linked to better application of a semantic-clustering strategy across a series of 3 test trials. Music education and language experience may have similar influences on the development of verbal memory.

The organization and administration of community college non-credit workforce education and training cuts

Science.gov (United States)

Kozachyn, Karen P.

Community colleges are struggling financially due to underfunding. Recent state budget cuts coupled with the elimination of federal stimulus money has exacerbated the issue as these funding streams had contributed to operating costs (Moltz, 2011). In response to these budget cuts, community colleges are challenged to improve, increase, and develop revenue producing programs. These factors heighten the need for community colleges to examine their non-credit workforce organizations. The community college units charged with delivering non-credit workforce education and training programs are historically ancillary to the academic divisions that deliver certificate, technical degree, and transfer degree programs. The perceptions of these units are that they are the community college's 'step child' (Grubb, Bradway, and Bell, 2002). This case study examined the organization and administration of community college non-credit workforce education and training units, utilizing observation, interviews, and document analysis. Observational data focused on the physical campus and the unit. Interviews were conducted onsite with decision-making personnel of the division units that deliver non-credit workforce education and training within each community college. Document analysis included college catalogues, program guides, marketing material, and website information. The study was grounded in the review of literature associated with the evolution of the community college, as well as the development of workforce education and training including funding, organizational structure and models, management philosophies, and effectiveness. The findings of the study report that all five units were self-contained and were organized and operated uniquely within the organization. Effectiveness was measured differently by each institution. However, two common benchmarks were revenue and student evaluations. Another outcome of this study is the perceived lack of college-wide alignment between

Nuclear renaissance in the reactor training of Areva

Energy Technology Data Exchange (ETDEWEB)

De Braquilanges, Bertrand [Reactor Training Center/France Manager, La Tour Areva - 1, place Jean Millier - 92084 Paris - La Defense (France); Napior, Amy [Reactor Training Center/USA Manager, 1300 Old Graves Mill Road - Lynchburg VA, 2450 (United States); Schoenfelder, Christian [Reactor Training Center/Germany Manager, Kaiserleistrasse 29 - 63067 Offenbach (Germany)

2010-07-01

Because of the perspectives of new builds, a significant increase in the number of design, construction and management personnel working in AREVA, their clients and sub-contractors has been estimated for the next future. In order to cope with the challenge to integrate newly hired people quickly and effectively into the AREVA workforce, a project - 'Training Task Force (TTF)' - was launched in 2008. The objective was to develop introductory and advanced courses and related tools harmonized between AREVA Training Centers in France, Germany and USA. First, a Global Plants Introductory Session (GPIS) was developed for newly hired employees. GPIS is a two weeks training course introducing in a modular way AREVA and specifically the activities and the reactors technical basics. As an example, design and operation of a nuclear power plant is illustrated on EPRTM. Since January 2009, these GPIS are held regularly in France, Germany and the US with a mixing of employees from these 3 regions. Next, advanced courses for more experienced employees were developed: - Advanced EPR{sup TM}, giving a detailed presentation of the EPR{sup TM} reactor design; - Codes and Standards; - Technical Nuclear Safety. Finally, feasibility studies on a Training Material Management (TMM) system, able to manage the training documentation, and on a worldwide training administration tool, were performed. The TTF project was completed mid of 2009; it transferred their recurrent activities to a new AREVA training department. This unit now consists of the French, German and US Reactors Training Centers. In particular, all courses developed by the TTF are now implemented worldwide with an opening to external trainees. The current worldwide course catalogue includes training courses for operation and maintenance personnel as well as for managers, engineers and non technical personnel of nuclear operators, suppliers, safety authorities and expert organizations. Training delivery is supported

The Flight Service Station Training Program : 1981-1985.

Science.gov (United States)

1986-06-01

This report describes the performance of the ATC classes in the Flight Service Station Training Program 1981 to 1985 on the skills tests and laboratory exercises in Preflight (pilot briefing), Inflight, and Emergency Services. Over 80% of the final g...

Relation of Mental Health to Alcohol and Substance Use Among Texas College Students.

Science.gov (United States)

Shafer, Alan B; Koenig, Jessica A; Becker, Emilie A

2017-04-01

We examined the effect of mental health problems and difficulties on alcohol, tobacco, and other drug (ATOD) use among college students by using the 2013 Texas College Survey of Substance Use (n=11,216), which includes the K6 screening scale for severe mental illness (SMI). Students' K6 scores were used to classify them into 3 groups: those likely to have SMI (9% with scores ≥ 13), those with some mental health problems (36%), and those without mental health issues (55% with scores ≤ 4). Questions regarding ATOD use were analyzed using these 3 groups. Alcohol use was not significantly associated with K6 scores, although problematic alcohol behaviors as measured by the CAGE test were. Higher cigarette use was significantly associated with higher K6 scores. Finally, both higher marijuana and higher drug use (across 9 other individual drugs) were significantly associated with higher K6 scores. Although higher K6 scores were associated with higher rates of drug use, most students with high K6 scores did not use drugs. However, given the higher level of risk, drug and alcohol interventions should be made available for those students who receive mental health counseling.

A charge regulating system for turbo-generator gas-cooled high-temperature reactor power stations

International Nuclear Information System (INIS)

Braytenbah, A.S.; Jaegtnes, K.O.

1975-01-01

The invention relates to a regulating system for gas-cooled high-temperature reactors power stations (helium coolant), equipped with several steam-boilers, each of which deriving heat from a corresponding cooling-gas flow circulating in the reactor, so as to feed superheated steam into a main common steam-manifold and re-superheated steam into a re-superheated hot common manifold [fr

System Definition Document: Reactor Data Necessary for Modeling Plutonium Disposition in Catawba Nuclear Station Units 1 and 2

International Nuclear Information System (INIS)

Ellis, R.J.

2000-01-01

The US Department of Energy (USDOE) has contracted with Duke Engineering and Services, Cogema, Inc., and Stone and Webster (DCS) to provide mixed-oxide (MOX) fuel fabrication and reactor irradiation services in support of USDOE's mission to dispose of surplus weapons-grade plutonium. The nuclear station units currently identified as mission reactors for this project are Catawba Units 1 and 2 and McGuire Units 1 and 2. This report is specific to Catawba Nuclear Station Units 1 and 2, but the details and materials for the McGuire reactors are very similar. The purpose of this document is to present a complete set of data about the reactor materials and components to be used in modeling the Catawba reactors to predict reactor physics parameters for the Catawba site. Except where noted, Duke Power Company or DCS documents are the sources of these data. These data are being used with the ORNL computer code models of the DCS Catawba (and McGuire) pressurized-water reactors

Research and Analysis of SWOT on Connection between Vocational College Education and Vocational Training

Institute of Scientific and Technical Information of China (English)

Yingjie Zhang[1

2016-01-01

The connection between vocational college education and vocational training is a new way for vocational colleges and enterprises to develop together. At present, vocational college education focusing on the education level of talent training, however, it ignores the needs of workers’ vocational training based on enterprise development planning and training of professional career development. Therefore, we should strengthen the connection between vocational training and vocational education. For the establishment of modern vocational education system, we should enhance the value of human capital of workers in order to adapt to the new economic norm with important practical signifi cance.

Application of Surface Geophysical Methods, With Emphasis on Magnetic Resonance Soundings, to Characterize the Hydrostratigraphy of the Brazos River Alluvium Aquifer, College Station, Texas, July 2006 - A Pilot Study

Science.gov (United States)

Shah, Sachin D.; Kress, Wade H.; Legchenko, Anatoly

2007-01-01

The U.S. Geological Survey, in cooperation with the Texas Water Development Board, used surface geophysical methods at the Texas A&M University Brazos River Hydrologic Field Research Site near College Station, Texas, in a pilot study, to characterize the hydrostratigraphic properties of the Brazos River alluvium aquifer and determine the effectiveness of the methods to aid in generating an improved ground-water availability model. Three non-invasive surface geophysical methods were used to characterize the electrical stratigraphy and hydraulic properties and to interpret the hydrostratigraphy of the Brazos River alluvium aquifer. Two methods, time-domain electromagnetic (TDEM) soundings and two-dimensional direct-current (2D-DC) resistivity imaging, were used to define the lateral and vertical extent of the Ships clay, the alluvium of the Brazos River alluvium aquifer, and the underlying Yegua Formation. Magnetic resonance sounding (MRS), a recently developed geophysical method, was used to derive estimates of the hydrologic properties including percentage water content and hydraulic conductivity. Results from the geophysics study demonstrated the usefulness of combined TDEM, 2D-DC resistivity, and MRS methods to reduce the need for additional boreholes in areas with data gaps and to provide more accurate information for ground-water availability models. Stratigraphically, the principal finding of this study is the relation between electrical resistivity and the depth and thickness of the subsurface hydrostratigraphic units at the site. TDEM data defined a three-layer electrical stratigraphy corresponding to a conductor-resistor-conductor that represents the hydrostratigraphic units - the Ships clay, the alluvium of the Brazos River alluvium aquifer, and the Yegua Formation. Sharp electrical boundaries occur at about 4 to 6 and 20 to 22 meters below land surface based on the TDEM data and define the geometry of the more resistive Brazos River alluvium aquifer

Integrated initial training program for a CEGB operations engineer

International Nuclear Information System (INIS)

Tompsett, P.A.

1987-01-01

This paper considers the overall training programs undertaken by a newly appointed Operations Engineer at one of the Central Electricity Generating Board's (CEGB) Advanced Gas Cooled Reactor (AGR) nuclear power stations. The training program is designed to equip him with the skills and knowledge necessary for him to discharge his duties safely and effectively. In order to assist the learning process and achieve and integrated program, aspects of reactor technology and operation, initially the subject of theoretical presentations at the CEGB's Nuclear Power Training Center (NPTC) are reinforced by either simulation and/or practical experience on site. In the later stages plant-specific simulators, operated by trained tutors, are incorporated into the training program to provide the trainee with practical experience of plant operation. The trainee's performance is assessed throughout the program to provide feedback to the trainee, the trainers and station management

Launching Early College Districtwide: Pharr-San Juan-Alamo's "College for All" Strategy

Science.gov (United States)

Le, Cecilia

2012-01-01

Across the nation, early college schools are creating a path to college success for young people underrepresented in higher education. For a decade, these innovative public schools blending high school and college have proven that, with the right support, all high school students can tackle college work. Now, a Texas school district near the…

Suicide Intervention Training for College Staff: Program Evaluation and Intervention Skill Measurement

Science.gov (United States)

Shannonhouse, Laura; Lin, Yung-Wei Dennis; Shaw, Kelly; Wanna, Reema; Porter, Michael

2017-01-01

Objective: Suicide remains a pressing issue for college communities. Consequently, gatekeeper trainings are often provided for staff. This study examines the effect of one such program, Applied Suicide Intervention Skills Training (ASIST). Participants: 51 college employees received ASIST in August of 2014 and were compared to 30 wait-list control…

WWER-1000 reactor simulator. Material for training courses and workshops. 2. ed

International Nuclear Information System (INIS)

2005-01-01

The International Atomic Energy Agency (IAEA) has established an activity in nuclear reactor simulation computer programs to assist its Member States in education. The objective is to provide, for a variety of advanced reactor types, insight and practice in their operational characteristics and their response to perturbations and accident situations. To achieve this, the IAEA arranges for the development and distribution of simulation programs and educational material and sponsors courses and workshops. The workshops are in two parts: techniques and tools for reactor simulator development; and the use of reactor simulators in education. Workshop material for the first part is covered in the IAEA publication: Training Course Series No.12, Reactor Simulator Development (2001). Course material for workshops using a pressurized water reactor (PWR) simulator developed for the IAEA by Cassiopeia Technologies Inc. of Canada is presented in the IAEA publication, Training Course Series No. 22, 2nd edition, Pressurized Water Reactor Simulator (2005) and Training Course Series No.23, 2nd edition, Boiling Water Reactor Simulator (2005). This report consists of course material for workshops using the WWER-1000 Reactor Department Simulator from the Moscow Engineering and Physics Institute, Russian Federation

Installation of the Light-Water Breeder Reactor at the Shippingport Atomic Power Station (LWBR Development Program)

International Nuclear Information System (INIS)

Massimino, R.J.; Williams, D.A.

1983-05-01

This report summarizes the refueling operations performed to install a Light Water Breeder Reactor (LWBR) core into the existing pressurized water reactor vessel at the Shippingport Atomic Power Station. Detailed descriptions of the major installation operations (e.g., primary system preconditioning, fuel installation, pressure boundary seal welding) are included as appendices to this report; these operations are of technical interest to any reactor servicing operation, whether the reactor is a breeder or a conventional light water non-breeder core

Installation of the Light-Water Breeder Reactor at the Shippingport Atomic Power Station (LWBR Development Program)

Energy Technology Data Exchange (ETDEWEB)

Massimino, R.J.; Williams, D.A.

1983-05-01

This report summarizes the refueling operations performed to install a Light Water Breeder Reactor (LWBR) core into the existing pressurized water reactor vessel at the Shippingport Atomic Power Station. Detailed descriptions of the major installation operations (e.g., primary system preconditioning, fuel installation, pressure boundary seal welding) are included as appendices to this report; these operations are of technical interest to any reactor servicing operation, whether the reactor is a breeder or a conventional light water non-breeder core.

Training of maintenance personnel

International Nuclear Information System (INIS)

Rabouhams, J.

1986-01-01

This lecture precises the method and means developed by EDF to ensure the training of maintenance personnel according to their initial educational background and their experience. The following points are treated: General organization of the training for maintenance personnel in PWR and GCR nuclear power stations and in Creys Malville fast breeder reactor; Basic nuclear training and pedagogical aids developed for this purpose; Specific training and training provided by contractors; complementary training taking into account the operation experience and feedback; Improvement of velocity, competence and safety during shut-down operations by adapted training. (orig.)

Music Teaching in Botswana Secondary Teacher Training Colleges: A Case of Molepolole College of Education.

Directory of Open Access Journals (Sweden)

Otukile Sindiso Phibion

2017-02-01

Full Text Available The purpose of this study is to find out facts on music teaching in Botswana Secondary Teacher Training Colleges. The authors conducted a formal study with regard to the Diploma in Secondary Education with a component of Music Education Training in Botswana. The study was conducted in Botswana at Molepolole College of Education (MCE which is the only government Secondary Teacher Training College, offering music in the whole country. Data were collected over a period of time by the three authors through meetings with staff and students surveys. The process was informed by involving all three authors. The leading author consecutively moderated this college for twelve years whilst the other two have been lecturers at the research college. This experience facilitated a further exploration of the competence frameworks in music education that they believed offered a narrow and technical view that neglected personal attributes and qualities. Apart from observations, research information was obtained through external examination/moderation reports review compiled consecutively over a number of years. Some of the information was obtained through consultation of government documents such as: The National Development Plan 10 (NDP 10, Vision 2016, Revised National Policy on Education (RNPE and Education for Kagisano with regard to prospects of music teaching in Botswana. In addition, Colleges of Education documents such as syllabuses, regulations, and prospectus were also consulted. It became evident through this research that music is accorded low status hence termed a minor subject as compared to other subjects called major. This research revealed that the admission process is also biased towards “Major” subjects. Initially there used to be interviews for “minor” opting students selection which have been since abandoned. The review found that lecturers at MCE were committed to serving for excellence yet strong criticism was made of perceived

Safety Evaluation Report related to the operation of Comanche Peak Steam Electric Station, Unit 2 (Docket No. 50-446)

International Nuclear Information System (INIS)

1992-09-01

This document supplement 25 to the Safety Evaluation Report related to the operation of the Comanche Peak Steam Electric Station (CPSES), Unit 2 (NUREG-0797), has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission (NRC). The facility is located in Somervell County, Texas, approximately 40 miles southwest of Fort Worth, Texas. This supplement reports the status of certain issues that had not been resolved when the Safety Evaluation Report and Supplements 1, 2, 3, 4, 6, 12, 21, 22, 23, and 24 to that report were published. This supplement deals primarily with Unit 2 issues; however, it also references evaluations for several Unit 1 licensing items resolved since Supplement 24 was issued

DOE University Reactor Sharing Program. Final technical report for 1996--1997

International Nuclear Information System (INIS)

Chappas, W.J.; Adams, V.G.

1998-01-01

The Department of Energy University Reactor Sharing Program at University of Maryland, College Park (UMCP) has, once again, stimulated a broad use of the reactor and radiation facilities by undergraduate and graduate students, visitors, and professionals. Participants are exposed to topics such as nuclear engineering, radiation safety, and nuclear reactor operations. This information is presented through various means including tours, slide presentations, experiments, and discussions. Student research using the MUTR is also encouraged. In addition, the Reactor Sharing Program here at the University of Maryland does not limit itself to the confines of the TRIGA reactor facility. Incorporated in the program are the Maryland University Radiation Effects Laboratory, and the UMCP 2 x 4 Thermal Hydraulic Loop. These facilities enhance and give an added dimension to the tours and experiments. The Maryland University Training Reactor (MUTR) and the associated laboratories are made available to any interested institution six days a week on a scheduled basis. Most institutions are scheduled at the time of their first request--a reflection of their commitment to the Reactor Sharing Program. The success of the past years by no means guarantees future success. Therefore, the reactor staff is more aggressively pursuing its outreach program, especially with junior colleges and universities without reactor or radiation facilities; more aggressively developing demonstration and training programs for students interested in careers in nuclear power and radiation technology; and more aggressively up-grading the reactor facilities--not only to provide a better training facility but to prepare for relicensing in the year 2000

A Cost-Benefit Analysis of Federal Job Training Investments in Community Colleges

Science.gov (United States)

Eyster, Lauren

2017-01-01

Community colleges, which are public, two-year institutions of higher education, have become a major provider of education and training that directly leads to a job in a particular occupation. To help community colleges build capacity to provide job training, the federal government has funded several grant programs over the past 15 years. Recent…

Development of research reactor simulator and its application to dynamic test-bed

International Nuclear Information System (INIS)

Kwon, Kee-Choon; Baang, Dane; Park, Jae-Chang; Lee, Seung-Wook; Bae, Sung Won

2014-01-01

We developed a real-time simulator for 'High-flux Advanced Neutron Application ReactOr (HANARO), and the Jordan Research and Training Reactor (JRTR). The main purpose of this simulator is operator training, but we modified this simulator into a dynamic test-bed (DTB) to test the functions and dynamic control performance of reactor regulating system (RRS) in HANARO or JRTR before installation. The simulator hardware consists of a host computer, 6 operator stations, a network switch, and a large display panel. The software includes a mathematical model that implements plant dynamics in real-time, an instructor station module that manages user instructions, and a human machine interface module. The developed research reactor simulators are installed in the Korea Atomic Energy Research Institute nuclear training center for reactor operator training. To use the simulator as a dynamic test-bed, the reactor regulating system modeling software of the simulator was replaced by actual RRS cabinet, and was interfaced using a hard-wired and network-based interface. RRS cabinet generates control signals for reactor power control based on the various feedback signals from DTB, and the DTB runs plant dynamics based on the RRS control signals. Thus the Hardware-In-the-Loop Simulation between RRS and the emulated plant (DTB) has been implemented and tested in this configuration. The test result shows that the developed DTB and actual RRS cabinet works together simultaneously resulting in quite good dynamic control performances. (author)

Design of a redundant meteorological station for a BWR reactor

International Nuclear Information System (INIS)

Ramirez S, R.; Celis del Angel, L.; Bucio, F.; Rivero, T.; Palacios, J.

2008-01-01

In this work the design of a meteorological station for a reactor type BWR is proposed. Two independent channels of data acquisition that allow him to have a bigger readiness is exposed. It is incorporate sensors without mobile parts to measure speed, wind direction and pluvial precipitation. It also counts, with sensors of global solar radiation, net radiation, barometric pressure, relative humidity and ambient temperature; with them they are possible to be calculated, moreover, other variables as temperature differential, dew point and atmospheric stability. The sensors are placed on a tower to different heights and send their information (each second) to a local registration system, the one which in turn, it remits the data to the monitoring office so that a computer is linked with the system, display and management the information in real time and automatic way. The redundant structure allows that in the event of maintenance the data acquisition is not interrupted, even if the information is transferred to another place. In all the station sections it is used protocols of standard communication to allow that a great quantity of devices can be connected without major problem. The above-mentioned would allow to the operators in the control room to have reliable information during the whole time of the reactor operation. (Author)

Thermohydraulic and safety analysis on China advanced research reactor under station blackout accident

International Nuclear Information System (INIS)

Tian Wenxi; Qiu Suizheng; Su Guanghui; Jia Dounan; Liu Xingmin; Zhang Jianwei

2007-01-01

A thermohydraulic and safety analysis code-TSACC has been developed using Fortran90 language to evaluate the transient thermohydraulic behavior of the China advanced research reactor (CARR) under station blackout accident (SBA). For the development of TSACC, a series of corresponding mathematical and physical models were applied. Point reactor neutron kinetics model was adopted for solving the reactor power. All possible flow and heat transfer conditions under station blackout accident were considered and the optional correlations were supplied. The usual finite difference method was abandoned and the integral technique was adopted to evaluate the temperature field of the plate type fuel elements. A new simple and convenient equation was proposed for the resolution of the transient behaviors of the main pump instead of the complicated four-quadrant model. Gear method and Adams method were adopted alternately for a better solution to the stiff differential equations describing the dynamic behavior of the CARR. The computational result of TSACC showed the adequacy of the safety margin of CARR under SBA. For the purpose of Verification and Validation (V and V), the simulated results of TSACC were compared with those of RELAP5/MOD3 and a good agreement was obtained. The adoption of modular programming techniques enables TASCC to be applied to other reactors by easily modifying the corresponding function modules

Occupational radiation exposures at Canadian CANDU nuclear power stations

International Nuclear Information System (INIS)

LeSurf, J.E.; Taylor, G.F.

1982-09-01

In Canada, methods to reduce the radiation exposure to workers at nuclear power reactors have been studied and implemented since the early days of the CANDU reactor program. Close collaboration between the designers, the operators, and the manufacturers has reduced the total exposure at each station, the dose requirement to operate and maintain each successive station compared with earlier stations, and the average annual exposure per worker. Specific methods developed to achieve dose reduction include water chemistry; corrosion resistant materials; low cobalt materials; decontamination; hot filtration, improved equipment reliability, maintainability, and accessibility; improved shielding design and location; planning of work for low exposure; improved operating and maintenance procedures; removal of tritium from D 2 O systems and work environments; improved protective clothing; on-power refuelling; worker awareness and training; and many other small improvements. The 1981 occupational dose productivity factors for Pickering A and Bruce A nuclear generating stations were respectively 0.43 and 0.2 rem/MW(e).a

Simulation and computation in health physics training

International Nuclear Information System (INIS)

Lakey, S.R.A.; Gibbs, D.C.C.; Marchant, C.P.

1980-01-01

The Royal Naval College has devised a number of computer aided learning programmes applicable to health physics which include radiation shield design and optimisation, environmental impact of a reactor accident, exposure levels produced by an inert radioactive gas cloud, and the prediction of radiation detector response in various radiation field conditions. Analogue computers are used on reduced or fast time scales because time dependent phenomenon are not always easily assimilated in real time. The build-up and decay of fission products, the dynamics of intake of radioactive material and reactor accident dynamics can be effectively simulated. It is essential to relate these simulations to real time and the College applies a research reactor and analytical phantom to this end. A special feature of the reactor is a chamber which can be supplied with Argon-41 from reactor exhaust gases to create a realistic gaseous contamination environment. Reactor accident situations are also taught by using role playing sequences carried out in real time in the emergency facilities associated with the research reactor. These facilities are outlined and the training technique illustrated with examples of the calculations and simulations. The training needs of the future are discussed, with emphasis on optimisation and cost-benefit analysis. (H.K.)

IAEA-RCA training course on in-service inspection of research reactors

International Nuclear Information System (INIS)

2002-01-01

Bhabha Atomic Research Centre (BARC) has acquired a wide range of experience for over four decades in design, construction, operation and maintenance of research reactors. The two-week training course on In-Service Inspection of Research Reactors (ISI) has greatly increased the awareness in the field of ISI of Research Reactors. The training course has been formulated so as to cover most of the topics relevant to ISI of research reactors. Important topics such as rationale for in-service inspection, material degradation mechanisms, non-destructive examination techniques, design evaluation of flaws and radiological, codal and regulatory aspects of ISI for research reactors were covered. Lectures on ISI of elastomeric materials and concrete structures, which are generally used in the construction of reactors have also been included in the course. Papers relevant to INIS are indexed separately

Technology, safety and costs of decommissioning a reference boiling water reactor power station: Comparison of two decommissioning cost estimates developed for the same commercial nuclear reactor power station

International Nuclear Information System (INIS)

Konzek, G.J.; Smith, R.I.

1990-12-01

This study presents the results of a comparison of a previous decommissioning cost study by Pacific Northwest Laboratory (PNL) and a recent decommissioning cost study of TLG Engineering, Inc., for the same commercial nuclear power reactor station. The purpose of this comparative analysis on the same plant is to determine the reasons why subsequent estimates for similar plants by others were significantly higher in cost and external occupational radiation exposure (ORE) than the PNL study. The primary purpose of the original study by PNL (NUREG/CR-0672) was to provide information on the available technology, the safety considerations, and the probable costs and ORE for the decommissioning of a large boiling water reactor (BWR) power station at the end of its operating life. This information was intended for use as background data and bases in the modification of existing regulations and in the development of new regulations pertaining to decommissioning activities. It was also intended for use by utilities in planning for the decommissioning of their nuclear power stations. The TLG study, initiated in 1987 and completed in 1989, was for the same plant, Washington Public Supply System's Unit 2 (WNP-2), that PNL used as its reference plant in its 1980 decommissioning study. Areas of agreement and disagreement are identified, and reasons for the areas of disagreement are discussed. 31 refs., 3 figs., 22 tabs

Reactor coolant pump shaft seal behavior during station blackout

International Nuclear Information System (INIS)

Kittmer, C.A.; Wensel, R.G.; Rhodes, D.B.; Metcalfe, R.; Cotnam, B.M.; Gentili, H.; Mings, W.J.

1985-04-01

A testing program designed to provide fundamental information pertaining to the behavior of reactor coolant pump (RCP) shaft seals during a postulated nuclear power plant station blackout has been completed. One seal assembly, utilizing both hydrodynamic and hydrostatic types of seals, was modeled and tested. Extrusion tests were conducted to determine if seal materials could withstand predicted temperatures and pressures. A taper-face seal model was tested for seal stability under conditions when leaking water flashes to steam across the seal face. Test information was then used as the basis for a station blackout analysis. Test results indicate a potential problem with an elastomer material used for O-rings by a pump vendor; that vendor is considering a change in material specification. Test results also indicate a need for further research on the generic issue of RCP seal integrity and its possible consideration for designation as an unresolved safety issue

Reactor handbook. 2. rev. ed.

International Nuclear Information System (INIS)

Lederer, B.J.; Wildberg, D.W.

1992-01-01

On the basis of the guidelines on expert knowledge, the book discusses the subjects of atomic physics, heat transfer, nuclear power plants, reactor materials, radiation protection, reactor safety, reactor instrumentation, and reactor operation, with special regard to nuclear power plants with LWR-type reactors. The book is intended for shift personnel, especially gang bosses, reactor operators, and control station operators: for this reason a practical and rather popular style has been chosen. However, the book will also be a manual for other operating personnel, personnel of producer companies, expert organisations, authorities, and students. It can be used as a textbook for staff training, a manual for the practice, and as accompanying book for teaching at nuclear engineering schools. (orig.) With 173 figs [de

Comprehensive College Plan for 2000-2001.

Science.gov (United States)

San Antonio Coll., TX.

The document describes San Antonio College's (Texas) strategic goals and objectives for 2000-2001. San Antonio College's comprehensive planning and evaluation process monitors the achievement of college-wide goals and initiatives supporting the college's Vision and Mission Statement and the Alamo Community College District's Strategic Plan. The…

A dedicated program for the extended longevity of research and training reactors

International Nuclear Information System (INIS)

Carriveau, G.W.

1992-01-01

In the past 49 years, over 555 research and training reactors have been in operation, with approximately 325 currently in service. The age distribution of operating research reactors shows that the average age is about 24 years; about 74% are 20 years old or older and about 33% are 30 years old or older. This group of reactors represents a very large investment in capital expense with replacement costs in 1990's prices much higher than when they were originally constructed. Furthermore, decommissioning costs may be much greater than the original investments. General Atomics has been directly involved for the better part of the nearly fifty year history of research and training reactors. This paper will describe a General Atomics program illustrating a dedicated commitment to the full service support of extended and improved use for all types of research and training reactors. (author)

Who Is Going to College? Predicting Education Training from Pre-VR Consumer Characteristics

Science.gov (United States)

Boutin, Daniel L.; Wilson, Keith B.

2012-01-01

The relationship of receiving college and university training within the state vocational rehabilitation (VR) program to pre-VR consumer characteristics was investigated with a multiple direct logistic regression technique. A model containing 11 pre-VR characteristics predict the reception of college and university training for a multidisability…

Experiments with the SUR 100 training reactor

International Nuclear Information System (INIS)

Milicic, B.

1984-06-01

This paper contains a compilation of various experiments using the SUR - 100 reactor for training purposes, which have been widly proved in practical work at the School for Nuclear Technology of the Karlsruhe Research Center. (orig.) [de

U.S. Domestic Reactor Conversion Programs

International Nuclear Information System (INIS)

Woolstenhulme, Eric

2008-01-01

The Conversion Projects Include: the revision of the facilities safety basis documents and supporting analysis, the fabrication of new LEU fuel, the change-out of the reactor core, and the removal of the used HEU fuel (by INL University Fuels Program or DOE-NE). The major entities involved are: the U.S. Nuclear Regulatory Commission, the University reactor department, the fuel and hardware fabricators, the Spent fuel receipt facilities, the Spent fuel shipping services, and the U.S. Department of Energy and their subcontractors. Three major Reactor Conversion Program milestones have been accomplished since 2006: the conversion of the TRIGA reactor at Texas A and M University Nuclear Science Center, the conversion of the University of Florida Training Reactor, and the conversion of the Purdue University Reactor. Four Reactor Conversion Program milestones yet to be accomplished in 2008 and 2009: the Washington State University Nuclear Radiation Center reactor, the Oregon State University TRIGA Reactor, the University of Wisconsin Nuclear Reactor, and the Neutron Radiography Reactor Facility. NNSA is committed to doing things cheaper, better, smarter, safer through a 'Lessons Learned' process. The conversion team assessed each major activity grouping: Project Initiation, Conversion Proposal Development, Fuel Fabrication and Hardware, Core Conversion, and Spent Nuclear Fuel Removal. Issues were identified and recommendations were given

Simple simulation training system for short-wave radio station

Science.gov (United States)

Tan, Xianglin; Shao, Zhichao; Tu, Jianhua; Qu, Fuqi

2018-04-01

The short-wave radio station is a most important transmission equipment of our signal corps, but in the actual teaching process, which exist the phenomenon of fewer equipment and more students, making the students' short-wave radio operation and practice time is very limited. In order to solve the above problems, to carry out shortwave radio simple simulation training system development is very necessary. This project is developed by combining hardware and software to simulate the voice communication operation and signal principle of shortwave radio station, and can test the signal flow of shortwave radio station. The test results indicate that this system is simple operation, human-machine interface friendly and can improve teaching more efficiency.

The Reforming of Vocational Teacher Training Colleges in Turkey

Science.gov (United States)

Çavuşoğlu, Abdullah; Günay, Durmuş

In Turkey, for many decades college level technical education has been in the form of two main tracks: namely the "Faculty of Engineering" and the "Faculty of Technical Education". The Faculties of Engineering are very similar to engineering schools and colleges around the world; they train engineering students. The "Faculties of Technical Education" are similar to the "Schools of Applied Sciences" that many European countries have. The graduates of these schools are either employed at high schools as teachers at technical or vocational high schools, self employed or employed at other governmental organizations as technical staff. Due to the employability problems that the graduates of these schools have faced in recent years and the suggestions made by the The Council of the Higher Education of Turkey (CoHE), Turkish parliament has recently took a decision to close down these colleges and open new colleges called "Faculty of Technology" in November of 2009. According to the CoHE, these new faculties will train engineering students. The graduates of these faculties can also become teachers at the technical or vocational high schools if they get teaching certificate. This paper discusses the content, outlook, and prospects of this recent reform.

Future plans for the design and construction of fast reactor power stations in the Federal Republic of Germany

International Nuclear Information System (INIS)

Kempken, M.; Koehler, M.; Wolff, M.

1978-01-01

Some important design features of future fast reactors in the Federal Republic of Germany (FRG) are presented, in particular for the demonstration plant SNR 2 which is to follow the prototype SNR 300, presently under construction in Kalkar. The SNR 2 conceptual design will be based on the SNR 300 design as far as possible. Programmes for the introduction of fast breeder reactor power stations on the part of the governments, the utilities and suppliers are based on broad international co-operation. The FRG is a country which imports a high proportion of its primary energy and it has rather small resources of natural uranium. The natural uranium realistically available to the FRG will allow nuclear energy to play a substantial role in the long-term energy supply only if present uranium utilization based on LWRs is supplemented and replaced by breeder reactor utilization later. To maintain this option, efforts towards the development, design and construction of fast breeder reactors have to be intensively continued in the FRG. The construction of the first large power station with a fast breeder reactor, SNR 2, will, according to present planning, start in the middle of the 80s. Operation can be expected to start at the beginning of the 90s. The present fast breeder programme in the FRG promises to develop reactors, reprocessing and fuel manufacturing plants to such a degree that by the end of this century the introduction of a substantial number of fast reactor power stations will be possible. (author)

The design and use of proficiency based BWR reactor maintenance and refuelling training mockups

International Nuclear Information System (INIS)

Ford, G.J.

1996-01-01

The purpose of this paper is to describe the ABB experience with the design and use of boiling water reactor training facilities. The training programs were developed and implemented in cooperation with the nuclear utilities. ABB operates two facilities, the ABB ATOM Light Water Reactor Service Center located in Vasteras, Sweden, and the ABB Combustion Engineering Nuclear Operations BWR Training Center located in Chattanooga, Tennessee, USA. The focus of the training centers are reactor maintenance and refueling activities plus the capability to develop and qualify tools, procedures and repair techniques

Aging management program of the reactor building concrete at Point Lepreau Generating Station

Science.gov (United States)

Aldea, C.-M.; Shenton, B.; Demerchant, M. M.; Gendron, T.

2011-04-01

In order for New Brunswick Power Nuclear (NBPN) to control the risks of degradation of the concrete reactor building at the Point Lepreau Generating Station (PLGS) the development of an aging management plan (AMP) was initiated. The intention of this plan was to determine the requirements for specific structural components of concrete of the reactor building that require regular inspection and maintenance to ensure the safe and reliable operation of the plant. The document is currently in draft form and presents an integrated methodology for the application of an AMP for the concrete of the reactor building. The current AMP addresses the reactor building structure and various components, such as joint sealant and liners that are integral to the structure. It does not include internal components housed within the structure. This paper provides background information regarding the document developed and the strategy developed to manage potential degradation of the concrete of the reactor building, as well as specific programs and preventive and corrective maintenance activities initiated.

Education and training of operators and maintenance staff at Hamaoka Nuclear Power Stations

International Nuclear Information System (INIS)

Makido, Hideki; Hayashi, Haruhisa

1999-01-01

At Hamaoka Nuclear Power Station, in order to ensure higher safety and reliability of plant operation, education and training is provided consistently, on a comprehensive basis, for all operating, maintenance and other technical staff, aimed at developing more capable human resources in the nuclear power division. To this end, Hamaoka Nuclear Power Station has the 'Nuclear Training Center' on its site. The training center provides the technical personnel including operators and maintenance personnel with practical training, utilizing simulators for operation training and the identical facilities with those at the real plant. Thus, it plays a central role in promoting comprehensive education and training concerning nuclear power generation. Our education system covers knowledge and skills necessary for the safe and stable operation of nuclear power plant, targeting new employees to managerial personnel. It is also organized systematically in accordance with experience and job level. We will report the present education and training of operators and maintenance personnel at Hamaoka Nuclear Training Center. (author)

Changing College Students' Conceptions of Autism: An Online Training to Increase Knowledge and Decrease Stigma

Science.gov (United States)

Gillespie-Lynch, Kristen; Brooks, Patricia J.; Someki, Fumio; Obeid, Rita; Shane-Simpson, Christina; Kapp, Steven K.; Daou, Nidal; Smith, David Shane

2015-01-01

College students with autism may be negatively impacted by lack of understanding about autism on college campuses. Thus, we developed an online training to improve knowledge and decrease stigma associated with autism among college students. Participants (N = 365) completed a pre-test, online training, and post-test. Women reported lower stigma…

Approach to training the operators of WWER-440 reactors

International Nuclear Information System (INIS)

Pironkov, L.; Minakova, R.

2002-01-01

The paper has three parts. (1) Personnel Training and Qualifications (2) Description of Kozloduy NPP Training and Qualification System (TQS) built in the last 7 years and its interfaces with the Certification System and (3) Application of the TQS for the Senior Reactor Operator (SRO). (author)

Safety Evaluation Report related to the operation of Comanche Peak Steam Electric Station, Unit 2 (Docket No. 50-446)

International Nuclear Information System (INIS)

1993-02-01

Supplement 26 to the Safety Evaluation Report related to the operation of the Comanche Peak Steam Electric Station (CPSES), Unit 2, has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission (NRC). The facility is located in Somervell County, Texas, approximately 40 miles southwest of Fort Worth, Texas. This supplement reports the status of certain issues that had not been resolved when the Safety Evaluation Report and Supplements 1, 2, 3, 4, 6, 12, 21, 22, 23, 24, and 25 to that report were published. This supplement deals primarily with Unit 2 issues; however, it also references evaluations for several licensing issues that relate to Unit 1, which have been resolved since Supplement 25 was issued

Study on reactor power transient characteristics (reactor training experiments). Control rod reactivity calibration by positive period method and other experiment

International Nuclear Information System (INIS)

Ozaki, Yoshihiko; Sunagawa, Takeyoshi

2014-01-01

In this paper, it is reported about some experiments that have been carried out in the reactor training that targets sophomore of the department of applied nuclear engineering, FUT. Reactor of Kinki University Atomic Energy Research Institute (UTR-KINKI) was used for reactor training. When each critical state was achieved at different reactor output respectively in reactor operating, it was confirmed that the control rod position at that time does not change. Further, control rod reactivity calibration experiments using positive Period method were carried out for shim safety rod and regulating rod, respectively. The results were obtained as reasonable values in comparison with the nominal value of the UTR-KINKI. The measurement of reactor power change after reactor scram was performed, and the presence of the delayed neutron precursor was confirmed by calculating the half-life. The spatial dose rate measurement experiment of neutrons and γ-rays in the reactor room in a reactor power 1W operating conditions were also performed. (author)

Nuclear analytical techniques with neutron beams at the Univ. of Texas at Austin

International Nuclear Information System (INIS)

Uenlue, K.; Wehring, B.W.

1996-01-01

Neutron beams produced by nuclear research reactors can be used for analytical chemical analysis by measuring nuclear radiation produced by neutron capture. Prompt gamma activation analysis (PGAA) and neutron depth profiling (NDP) are two such analytical techniques. For the last three decades, these techniques have been applied at a number of research reactors around the world. Within the last 4 yr, we have developed NDP and PGAA facilities at The University of Texas at Austin research reactor, a 1-MW TRIGA Mark II reactor. Brief descriptions of the facilities and summaries of activities for these analytical techniques at the University of Texas at Austin are provided in this paper

The construction of a PWR power station reactor building liner

International Nuclear Information System (INIS)

Skirving, N.; Goulding, J.S.; Gibson, J.A.

1991-01-01

Cleveland Bridge and Engineering Co Ltd (CBE) are constructing the Reactor Building Liner Plate containment of the Sizewell 'B' Power Station for Nuclear Electric Ltd. This has entailed extensive offsite prefabrication of components and their subsequent erection at Sizewell. It has been necessary to engineer temporary supporting mechanisms to enable manufacture and erection to proceed, yet also to withstand wet concrete forces during the progressive construction. The Reactor Building Liner Plate is a safety related system and as such, in addition to strict compliance with the ASME code, the Quality Assurance (QA) requirements of BS 5882 are applicable. A dedicated Project Team was established by CBE to control and direct the work. Equally important as satisfying the rigorous Q.A. requirements has been the need to meet programme and budget. This paper details CBE execution of the Project. (author)

Hands-on Training Courses Using Research Reactors and Accelerators

International Nuclear Information System (INIS)

2014-01-01

The enhancement of nuclear science education and training in all Member States is of interest to the IAEA since many of these countries, particularly in the developing world, are building up and expanding their scientific and technological infrastructures. Unfortunately, most of these countries still lack sufficient numbers of well-educated and qualified nuclear specialists and technologists. This may arise from, amongst other things: a lack of candidates with sufficient educational background in nuclear science who would qualify to receive specialized training; a lack of institutions available for training nuclear science specialists; a lack of lecturers in nuclear related fields; and a lack of suitable educational and teaching materials. A related concern is the potential loss of valuable knowledge accumulated over many decades due to the ageing workforce. An imperative for Member States is to develop and offer suitable graduate and postgraduate academic programmes which combine study and project work so that students can attain a prerequisite level of knowledge, abilities and skills in their chosen subject area. In nearly all academic programmes, experimental work forms an essential and integral component of study to help students develop general and subject specific skills. Experimental laboratory courses and exercises can mean practical work in a conventional laboratory or an advanced facility with an operational particle accelerator or research reactor often accompanied by computer simulations and theoretical exercises. In this context, available or newly planned research reactors and particle accelerators should be seen as extremely important and indispensable components of nuclear science and technology curricula. Research reactors can demonstrate nuclear science and technology based on nuclear fission and the interaction of neutrons and photons with matter, while particle accelerators can demonstrate nuclear science and technology based on charged particle

Relap5 Analysis of Processes in Reactor Cooling Circuit and Reactor Cavity in Case of Station Blackout in RBMK-1500

International Nuclear Information System (INIS)

Kaliatka, A.

2007-01-01

Ignalina NPP is equipped with channel-type boiling-water graphite-moderated reactor RBMK-1500. Results of the level-1 probabilistic safety assessment of the Ignalina NPP have shown that in topography of the risk, the transients with failure of long-term core cooling other than LOCA are the main contributors to the core damage frequency. The total loss of off-site power with a failure to start any diesel generator, that is station blackout, is the event which could lead to the loss of long-term core cooling. Such accident could lead to multiple ruptures of fuel channels with severe consequences and should be analyzed in order to estimate the timing of the key events and the possibilities for accident management. This paper presents the results of the analysis of station blackout at Ignalina NPP. Analysis was performed using thermal-hydraulic state-of-the-art RELAP5/MOD3.2 code. The response of reactor cooling system and the processes in the reactor cavity and its venting system in case of a few fuel-channel ruptures due to overheating were demonstrated. The possible measures for prevention of the development of this beyond design basis accident (BDBA) to a severe accident are discussed

Diagnosis of electric equipment at the Dalat Nuclear Research Reactor

International Nuclear Information System (INIS)

Nguyen Truong Sinh

1999-01-01

The Dalat Nuclear Research Reactor (DNRR) is a pool type of its kind in the world: Soviet-designed core and control system harmoniously integrated into the left-over infrastructure of the former American-made TRIGA MARK II reactor, which includes the reactor tank and shielding, graphite reflector, beam tubes and thermal column. The reactor is mainly used for radioisotope and radiopharmaceutical production, elemental analysis using neutron activation techniques, neutron beam exploitation, silicon doping, and reactor physics experimentation. For safe operation of the reactor maintenance work has been carried out for the reactor control and instrumentation, reactor cooling, ventilation, radiomonitoring, mechanical, normal electric supply systems as well as emergency electric diesel generators and the water treatment station. Technical management of the reactor includes periodical maintenance as required by technical specifications, training, re-training and control of knowledge for reactor staff. During recent years, periodic preventive maintenance (PPM) has been carried out for the electric machines of the technological systems. (author)

University Reactor Sharing Program. Final report, September 30, 1992--September 29, 1994

International Nuclear Information System (INIS)

Wehring, B.W.

1995-01-01

Over the past 20 years, the number of nuclear reactors on university campuses in the US declined from more than 70 to less than 40. Contrary to this trend, The University of Texas at Austin constructed a new reactor facility at a cost of $5.8 million. The new reactor facility houses a new TRIGA Mark II reactor which replaces an in-ground TRIGA Mark I reactor located in a 50-year old building. The new reactor facility was constructed to strengthen the instruction and research opportunities in nuclear science and engineering for both undergraduate and graduate students at The University of Texas. On January 17, 1992, The University of Texas at Austin received a license for operation of the new reactor. Initial criticality was achieved on March 12, 1992, and full power operation, on March 25, 1992. The UT-TRIGA research reactor provides hands-on education, multidisciplinary research and unique service activities for academic, medical, industrial, and government groups. Support by the University Reactor Sharing Programs increases the availability of The University of Texas reactor facility for use by other educational institutions which do not have nuclear reactors

Assessment of the effectiveness of training technology transfer activities at soviet-designed reactors

International Nuclear Information System (INIS)

Haber, S.; Shurberg, D.; Yoder, J.; Draper, D.

2003-01-01

The U.S. Department of Energy (DOE) has been working with personnel at Soviet-Designed Reactors (SDRs) to enhance management and operational safety by upgrading many areas of plant operations to levels that meet established international standards. Since 1992 this work has included activities related to training. The work initially focussed on the establishment of nuclear training centers in Russia and Ukraine and the transfer of U.S. training methodologies but has since expanded to include all Russian and Ukrainian nuclear power stations and training centers as well as SDRs within other countries. A key component to the work has been the determination of programmatic effectiveness. Of specific interest has been the success of the transfer of U.S. training methodologies to SDRs so the capability exists for independent expansion of training efforts. Of equal importance has been the question of whether the training programs being developed are having the desired impact on facility safety performance. While progress has been made in the evaluation of the impact of training on facility safety performance, the question has not yet been fully answered. The issue has been further confounded due to wide-ranging and concurrent changes being made beyond training to many aspects of facility operations and maintenance. This paper focuses on the selection of a strategy to upgrade and, as necessary, develop training programs to assist in the improvement of SDR safety. Difficulties encountered in the development of assessment strategies across all SDRs that are being worked with are discussed. In addition, measures collected related to the success of the overall program efforts and data indicating the success of the DOE efforts in the transfer and adoption by SDRs of an effective training methodology are outlined. (author)

Derailing healthy choices: an audit of vending machines at train stations in NSW.

Science.gov (United States)

Kelly, Bridget; Flood, Victoria M; Bicego, Cecilia; Yeatman, Heather

2012-04-01

Train stations provide opportunities for food purchases and many consumers are exposed to these venues daily, on their commute to and from work. This study aimed to describe the food environment that commuters are exposed to at train stations in NSW. One hundred train stations were randomly sampled from the Greater Sydney Metropolitan region, representing a range of demographic areas. A purpose-designed instrument was developed to collect information on the availability, promotion and cost of food and beverages in vending machines. Items were classified as high/low in energy according to NSW school canteen criteria. Of the 206 vending machines identified, 84% of slots were stocked with high-energy food and beverages. The most frequently available items were chips and extruded snacks (33%), sugar-sweetened soft drinks (18%), chocolate (12%) and confectionery (10%). High energy foods were consistently cheaper than lower-energy alternatives. Transport sites may cumulatively contribute to excess energy consumption as the items offered are energy dense. Interventions are required to improve train commuters' access to healthy food and beverages.

Alteration in reactor installations (Unit 1 and 2 reactor facilities) in the Hamaoka Nuclear Power Station of The Chubu Electric Power Co., Inc. (report)

International Nuclear Information System (INIS)

1982-01-01

A report by the Nuclear Safety Commission to the Ministry of International Trade and Industry concerning the alteration in Unit 1 and 2 reactor facilities in the Hamaoka Nuclear Power Station, Chubu Electric Power Co., Inc., was presented. The technical capabilities for the alteration of reactor facilities in Chubu Electric Power Co., Inc., were confirmed to be adequate. The safety of the reactor facilities after the alteration was confirmed to be adequate. The items of examination made for the confirmation of the safety are as follows: reactor core design (nuclear design, mechanical design, mixed reactor core), the analysis of abnormal transients in operation, the analysis of various accidents, the analysis of credible accidents for site evaluation. (Mori, K.)

Preliminary Analysis of Ex-Vessel Steam Explosion using TEXAS-V code for APR1400

International Nuclear Information System (INIS)

Song, Sung Chu; Lee, Jung Jae; Cho, Yong Jin; Hwang, Taesuk

2013-01-01

The purpose of this study is to explore input development and the audit calculation using TEXAS-V code for ex-vessel steam explosion for a flooded reactor cavity of APR1400. TEXAS computational models are one of the simplified tools for simulations of fuel-coolant interaction during mixing, triggering and explosion phase. The models of TEXAS code were validated by performing the fundamental experimental investigation in the KROTOS facility at JRC, Ispra. The experiments such as KROTOS and FARO experiment are aimed at providing benchmark data to examine the effect of fuel-coolant initial conditions and mixing on explosion energetics with alumina and prototypical core material. TEXAS-V code used in this study was to analyze and predict the ex-vessel steam explosion for a reactor scale. The input deck to simulate the flooded reactor cavity of APR1400 is developed and base case calculation is performed. This study will provide a base for further study. The code will be of use for the evaluation and sensitivity study of ex-vessel steam explosion for ERVC strategy in the future studies. Analysis result of this study is similar to the result of other study. Through this study, it is found that TEXAS-V could be the used as a tool for predicting the steam explosion load on a reactor scale, as fast running computer code. In addition, TEXAS-V code could be to evaluate the impact of various uncertainties, which are not clearly understood yet, to provide a conservative envelope for the steam explosion

Preliminary Analysis of Ex-Vessel Steam Explosion using TEXAS-V code for APR1400

Energy Technology Data Exchange (ETDEWEB)

Song, Sung Chu; Lee, Jung Jae; Cho, Yong Jin; Hwang, Taesuk [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

2013-10-15

The purpose of this study is to explore input development and the audit calculation using TEXAS-V code for ex-vessel steam explosion for a flooded reactor cavity of APR1400. TEXAS computational models are one of the simplified tools for simulations of fuel-coolant interaction during mixing, triggering and explosion phase. The models of TEXAS code were validated by performing the fundamental experimental investigation in the KROTOS facility at JRC, Ispra. The experiments such as KROTOS and FARO experiment are aimed at providing benchmark data to examine the effect of fuel-coolant initial conditions and mixing on explosion energetics with alumina and prototypical core material. TEXAS-V code used in this study was to analyze and predict the ex-vessel steam explosion for a reactor scale. The input deck to simulate the flooded reactor cavity of APR1400 is developed and base case calculation is performed. This study will provide a base for further study. The code will be of use for the evaluation and sensitivity study of ex-vessel steam explosion for ERVC strategy in the future studies. Analysis result of this study is similar to the result of other study. Through this study, it is found that TEXAS-V could be the used as a tool for predicting the steam explosion load on a reactor scale, as fast running computer code. In addition, TEXAS-V code could be to evaluate the impact of various uncertainties, which are not clearly understood yet, to provide a conservative envelope for the steam explosion.

The impact of weather conditions on response of sorghum genotypes to anthracnose (Colletotrichum sublineola) infection

Science.gov (United States)

Rainfall is a major climatic factor influencing anthracnose development and in this study, 68 sorghum accessions were evaluated for anthracnose resistance under dry and wet growing conditions at the Texas A&M Agricultural Experiment Station, near College Station, Texas. Accessions, planted in a ran...

Operations of a TRIGA reactor at a small private liberal arts college

International Nuclear Information System (INIS)

Church, L.B.

1978-01-01

A small private liberal arts college is not a very representative place to have a TRIGA reactor. Reed is a wholly undergraduate institution with a strong emphasis in the traditional liberal arts and fundamental sciences. Many of the larger state universities provide an excellence in nuclear science which is often presented to students in a somewhat distant manner. By providing a reactor that was immediately accessible to undergraduate students it has been realized that the excitement attendant with nuclear science would be available to them in an immediate hands-on manner

Aging management program of the reactor building concrete at Point Lepreau Generating Station

Directory of Open Access Journals (Sweden)

Gendron T.

2011-04-01

Full Text Available In order for New Brunswick Power Nuclear (NBPN to control the risks of degradation of the concrete reactor building at the Point Lepreau Generating Station (PLGS the development of an aging management plan (AMP was initiated. The intention of this plan was to determine the requirements for specific structural components of concrete of the reactor building that require regular inspection and maintenance to ensure the safe and reliable operation of the plant. The document is currently in draft form and presents an integrated methodology for the application of an AMP for the concrete of the reactor building. The current AMP addresses the reactor building structure and various components, such as joint sealant and liners that are integral to the structure. It does not include internal components housed within the structure. This paper provides background information regarding the document developed and the strategy developed to manage potential degradation of the concrete of the reactor building, as well as specific programs and preventive and corrective maintenance activities initiated.

Nuclear Education and Training Courses as a Commercial Product of a Low Power Research Reactor

International Nuclear Information System (INIS)

Böck, H.; Villa, M.; Steinhauser, G.

2013-01-01

The Vienna University of Technology (VUT) operates a 250 kW TRIGA Mark II research reactor at the Atominstitut (ATI) since March 1962. This reactor is uniquely devoted to nuclear education and training with the aim to offer an instrument to perform academic research and training. During the past decade a number of requests to the Atominstitut asked for the possibility to offer this reactor for external training courses. Over the years, such courses have been developed as regular courses for students during their academic curricula at the VUT/ATI. The courses cover such subjects as “Reactor physics and kinetics”, and “Reactor instrumentation and control”, in total about 20 practical exercises. Textbooks have been developed in English language for both courses. Target groups for commercial courses are other universities without an access to research reactors (i.e., the Technical University of Bratislava, Slovak Republic, or the University of Manchester, UK), international organisations (i.e., IAEA Dept of Safeguards, training section), research centres (ie. Mol, Belgium) for retraining of their reactor staff or nuclear power plants for staff retraining. These courses have been very successful during the past five years in such a manner that the Atominstitut has now to decline new course applications as the reactor is also used for Masters thesis and PhD work which requires full power operation while courses require low power operation. The paper describes typical training programs, target groups and possible transfers of these courses to other reactors. (author)

Effects of Aerobic Training on Primary Dysmenorrhea Symptomatology in College Females.

Science.gov (United States)

Israel, Richard G.; And Others

1985-01-01

This study investigated the effects of a 12-week aerobic training program on menstrual distress symptoms in college females with clinically diagnosed primary dysmenorrhea. The findings suggest that aerobic training can significantly reduce the symptoms associated with primary dysmenorrhea. (Author/MT)

Education and training of operators and maintenance staff at commercial nuclear power stations in Japan

International Nuclear Information System (INIS)

Takahashi, M.; Kataoka, H.

1998-01-01

Safe and stable operation of a nuclear power station requires personnel fostering. In Japan, with the objectives of systematically securing qualified people for a long period of time, and maintaining and improving their skills and knowledge, the utilities have created strict personnel training plans, for continuous education and training. Concrete examples of education and training for operators and maintenance personnel at commercial nuclear power stations in Japan, such as education systems training, facility and contents of curriculum, are detailed including some related matters. Recent activities to catch up with environment changes surrounding education and training of operators and maintenance staff are also mentioned. (author)

Culham Conceptual Tokamak Mark II. Design study of the layout of a twin-reactor fusion power station

International Nuclear Information System (INIS)

Guthrie, J.A.S.; Harding, N.H.

1981-07-01

This report describes the building layout and outline design for the nuclear complex of a fusion reactor power station incorporating two Culham Conceptual Tokamak Reactors Mk.II. The design incorporates equipment for steam generation, process services for the fusion reactors and all facilities for routine and non-routine servicing of the nuclear complex. The design includes provision of temporary facilities for on site construction of the major reactor components and shows that these facilities may be used for disassembly of the reactors either for major repair and/or decommissioning. Preliminary estimates are included, which indicate the cost benefits to be obtained from incorporating two reactors in one nuclear complex and from increased wall loading. (author)

Training the theatre arts teacher in Nigerian colleges of education ...

African Journals Online (AJOL)

This article seeks to identify and proffer solutions to the problems confronting the theatre arts teacher training in Nigerian colleges of education. It also advances the prospects of effective theatre arts teacher training in the educational sector and the society at large. In doing these, the researcher adopts the interview, focus ...

Neuroplasticity-based Cognitive and Linguistic Skills Training Improves Reading and Writing Skills in College Students

Directory of Open Access Journals (Sweden)

Beth eRogowsky

2013-03-01

Full Text Available This study reports an evaluation of the effect of computer-based cognitive and linguistic training on college students’ reading and writing skills. The computer-based training included a series of increasingly challenging software programs that were designed to strengthen students’ foundational cognitive skills (memory, attention span, processing speed, and sequencing in the context of listening and higher level reading tasks. Twenty-five college students (12 native English language; 13 English Second Language who demonstrated poor writing skills participated in the training group. The training group received daily training during the spring semester (11 weeks with the Fast ForWord Literacy (FFW-L and upper levels of the Fast ForWord Reading series (Levels 3, 4 and 5. The comparison group (n=28 selected from the general college population did not receive training. Both the training and comparison groups attended the same university. All students took the Gates MacGinitie Reading Test (GMRT and the Oral and Written Language Scales (OWLS Written Expression Scale at the beginning (Time 1 and end (Time 2 of the spring college semester. Results from this study showed that the training group made a statistically greater improvement from Time 1 to Time 2 in both their reading skills and their writing skills than the comparison group. The group who received training began with statistically lower writing skills before training, but exceeded the writing skills of the comparison group after training.

Simulator training and licensing examination for nuclear power station operator

International Nuclear Information System (INIS)

Xu Pingsheng

2007-01-01

For the recruitment, training and position qualification of the simulator instructors and feedback of training effect, the management approaches are formulated in 'The System for Simulator Training and Licensing Examination of Daya Bay Nuclear Power Station Operators'. The concrete requirements on the professional knowledge, work experience and foreign language ability of a simulator instructor are put forward. The process of instructor training is designed. The training items include the trainer training, pedagogy training, time management training, operation activities training during outage of unit, 'shadow' training and on-the-jot training on simulator courses. Job rotation is realized between simulator instructor and licensing personnel on site. New simulator instructor must pass the qualification identification. After a duration of 2 years, re-qualification has to be carried out. On the basis of the operator training method introduced from EDF (electricite De France), some new courses are developed and the improvement on the initial training, retaining courses, the technical support and the experience feedback by using the simulator is done also. (authors)

United States Department of Energy breeder reactor staff training domestic program

International Nuclear Information System (INIS)

1984-01-01

Two US DOE projects in the Pacific Northwest offer unique on-the-scene training opportunities at sodium-cooled fast-reactor plants: the Fast Flux Test Facility (FFTF) near Richland, Washington, which has operated successfully in a wide range of irradiation test programs since 1980; and the Experimental Breeder Reactor II (EBR-II) near Idaho Falls, Idaho, which has been in operation for approximately 20 years. Training programs have been especially designed to take advantage of this plant experience. Available courses are described

Training courses on neutron detection systems on the ISIS research reactor: on-site and through internet training

Energy Technology Data Exchange (ETDEWEB)

Lescop, B.; Badeau, G.; Ivanovic, S.; Foulon, F. [National Institute for Nuclear science and Technology French Atomic Energy and Alternative Energies Commission (CEA), Saclay Research Center, 91191 Gif-sur-Yvette (France)

2015-07-01

Today, ISIS research reactor is an essential tool for Education and Training programs organized by the National Institute for Nuclear Science and Technology (INSTN) from CEA. In the field of nuclear instrumentation, the INSTN offers both, theoretical courses and training courses on the use of neutron detection systems taking advantage of the ISIS research reactor for the supply of a wide range of neutron fluxes. This paper describes the content of the training carried out on the use of neutron detectors and detection systems, on-site or remote. The ISIS reactor is a 700 kW open core pool type reactor. The facility is very flexible since neutron detectors can be inserted into the core or its vicinity, and be used at different levels of power according to the needs of the course. Neutron fluxes, typically ranging from 1 to 10{sup 12} n/cm{sup 2}.s, can be obtained for the characterisation of the neutron detectors and detection systems. For the monitoring of the neutron density at low level of power, the Instrumentation and Control (I and C) system of the reactor is equipped with two detection systems, named BN1 and BN2. Each way contains a fission chamber, type CFUL01, connected to an electronic system type SIREX.The system works in pulse mode and exhibits two outputs: the counting rate and the doubling time. For the high level of power, the I and C is equipped with two detection systems HN1 and HN2.Each way contain a boron ionization chamber (type CC52) connected to an electronics system type SIREX. The system works in current mode and has two outputs: the current and the doubling time. For each mode, the trainees can observe and measure the signal at the different stages of the electronic system, with an oscilloscope. They can understand the role of each component of the detection system: detector, cable and each electronic block. The limitation of the detection modes and their operating range can be established from the measured signal. The trainees can also

Training courses on neutron detection systems on the ISIS research reactor: on-site and through internet training

International Nuclear Information System (INIS)

Lescop, B.; Badeau, G.; Ivanovic, S.; Foulon, F.

2015-01-01

Today, ISIS research reactor is an essential tool for Education and Training programs organized by the National Institute for Nuclear Science and Technology (INSTN) from CEA. In the field of nuclear instrumentation, the INSTN offers both, theoretical courses and training courses on the use of neutron detection systems taking advantage of the ISIS research reactor for the supply of a wide range of neutron fluxes. This paper describes the content of the training carried out on the use of neutron detectors and detection systems, on-site or remote. The ISIS reactor is a 700 kW open core pool type reactor. The facility is very flexible since neutron detectors can be inserted into the core or its vicinity, and be used at different levels of power according to the needs of the course. Neutron fluxes, typically ranging from 1 to 10 12 n/cm 2 .s, can be obtained for the characterisation of the neutron detectors and detection systems. For the monitoring of the neutron density at low level of power, the Instrumentation and Control (I and C) system of the reactor is equipped with two detection systems, named BN1 and BN2. Each way contains a fission chamber, type CFUL01, connected to an electronic system type SIREX.The system works in pulse mode and exhibits two outputs: the counting rate and the doubling time. For the high level of power, the I and C is equipped with two detection systems HN1 and HN2.Each way contain a boron ionization chamber (type CC52) connected to an electronics system type SIREX. The system works in current mode and has two outputs: the current and the doubling time. For each mode, the trainees can observe and measure the signal at the different stages of the electronic system, with an oscilloscope. They can understand the role of each component of the detection system: detector, cable and each electronic block. The limitation of the detection modes and their operating range can be established from the measured signal. The trainees can also modify the

Integrated Basic Education and Skills Training (I-BEST). Washington's Community and Technical Colleges

Science.gov (United States)

Washington State Board for Community and Technical Colleges, 2014

2014-01-01

Washington's Integrated Basic Education and Skills Training Program (I-BEST) quickly teaches students literacy, work, and college-readiness skills so they can move through school and into living wage jobs faster. Pioneered by Washington's community and technical colleges, I-BEST uses a team-teaching approach to combine college-readiness classes…

Maneuvering the Role as a Community College Artist-Educator: Scholarship Assessed

Science.gov (United States)

Gibson, John R.; Murray, John P.

2009-01-01

This study examined how Texas community college artist-educators balance artistic productivity with their teaching responsibilities. The 98 survey respondents represented 76.6% of a stratified random sample of the full-time instructors in visual arts departments within the 50 Texas public community college districts. Access to studio space and…

Assertion Training with Korean College Students: Effects on Self-Expression and Anxiety.

Science.gov (United States)

Hong, Kyung-Ja; Cooker, Philip G.

1984-01-01

Examined the effects of assertiveness training on the self-expression skills of 65 Korean college students. Results showed the treatment group scored significantly higher on the College Self Expression Scale than placebo or control groups, and males scored significantly higher than females. (JAC)

Monitoring the Performance of the Pedestrian Transfer Function of Train Stations Using Automatic Fare Collection Data

NARCIS (Netherlands)

Van den Heuvel, J.P.A.; Hoogenraad, J.H.

2014-01-01

Over the last years all train stations in The Netherlands have been equipped with automatic fare collection gates and/or validators. All public transport passengers use a smart card to pay their fare. In this paper we present a monitor for the performance of the pedestrian function of train stations

Assertion Training and Cognitive Restructuring With College Women.

Science.gov (United States)

Terrill, Marilyn J.

The process of assertive behavior change of college women who received assertion training (AT) and cognitive restructuring was examined to assess the relative effects of different durations of exposure to cognitive restructuring. Undergraduate and graduate women students (N=27) at a state university volunteered and were screened for AT groups.…

Zero-Based Budgeting: The Texas Experience.

Science.gov (United States)

Boyd, William L.

1982-01-01

Zero-based budgeting was instituted in all Texas state-funded agencies in 1975-76, including colleges. The first two years of using this procedure are reviewed and its applicability to higher education institutions is examined in light of the need to consider educational quality as well as costs. (MSE)

Training nuclear power plant personnel on SR-O reactor

International Nuclear Information System (INIS)

Cerny, K.; Boucek, F.; Kveton, M.; Prokopec, Z.; Fleischhans, J.

1983-01-01

The SR-O reactor is an experimental pool-type reactor with a maximum output of 1 MW and maximum thermal neutron flux density of 5.3x10 13 m -2 s -1 . The reactor is described in detail and its specifications are given. The protection and control systems of the reactor permit both manual and automatic operation. The reactor is used for training courses for nuclear power plant operators and for post-graduate study courses for other specialists. Intensive courses for 4 to 6 persons take 15 to 20 days. The course is adjusted to the results of introductory theoretical tests. An optimal teaching method has been developed based on the flowchart algorithmic method, dividing activities into operations (manipulations with controls, issuing commands, making records, etc.) and decision making (information reception and processing). (M.D.)

USE OF MULTIMEDIA TOOLS IN THE TRAINING OF PEDAGOGICAL COLLEGES STUDENTS

Directory of Open Access Journals (Sweden)

Olga M. Naumenko

2010-08-01

Full Text Available Current questions concerning the introduction of information and communication technologies tools into the pedagogical college teacher training using the essentially new ways of informative activity are considered. On the basis of the researches having been spent in the pedagogical colleges of Kyiv, there are analyzed possible scenarios of use of such multimedia tools in educational process.

USE OF MULTIMEDIA TOOLS IN THE TRAINING OF PEDAGOGICAL COLLEGES STUDENTS

OpenAIRE

Olga M. Naumenko

2010-01-01

Current questions concerning the introduction of information and communication technologies tools into the pedagogical college teacher training using the essentially new ways of informative activity are considered. On the basis of the researches having been spent in the pedagogical colleges of Kyiv, there are analyzed possible scenarios of use of such multimedia tools in educational process.

Recovery Act: Training Program Development for Commercial Building Equipment Technicians

Energy Technology Data Exchange (ETDEWEB)

Leah Glameyer

2012-07-12

The overall goal of this project has been to develop curricula, certification requirements, and accreditation standards for training on energy efficient practices and technologies for commercial building technicians. These training products will advance industry expertise towards net-zero energy commercial building goals and will result in a substantial reduction in energy use. The ultimate objective is to develop a workforce that can bring existing commercial buildings up to their energy performance potential and ensure that new commercial buildings do not fall below their expected optimal level of performance. Commercial building equipment technicians participating in this training program will learn how to best operate commercial buildings to ensure they reach their expected energy performance level. The training is a combination of classroom, online and on-site lessons. The Texas Engineering Extension Service (TEEX) developed curricula using subject matter and adult learning experts to ensure the training meets certification requirements and accreditation standards for training these technicians. The training targets a specific climate zone to meets the needs, specialized expertise, and perspectives of the commercial building equipment technicians in that zone. The combination of efficient operations and advanced design will improve the internal built environment of a commercial building by increasing comfort and safety, while reducing energy use and environmental impact. Properly trained technicians will ensure equipment operates at design specifications. A second impact is a more highly trained workforce that is better equipped to obtain employment. Organizations that contributed to the development of the training program include TEEX and the Texas Engineering Experiment Station (TEES) (both members of The Texas A&M University System). TEES is also a member of the Building Commissioning Association. This report includes a description of the project

Considerations for increasing the competences and capacities of the public health workforce: assessing the training needs of public health workers in Texas.

Science.gov (United States)

Borders, Stephen; Blakely, Craig; Quiram, Barbara; McLeroy, Kenneth

2006-07-26

Over the last two decades, concern has been expressed about the readiness of the public health workforce to adequately address the scientific, technological, social, political and economic challenges facing the field. A 1988 report from the Institute of Medicine (IOM) served as a catalyst for the re-examination of the public health workforce. The IOM's call to increase the relevance of public health education and training prompted a renewed effort to identify competences needed by public health personnel and the organizations that employ them. A recent evaluation sought to address the role of the 10 essential public health services in job services among the Texas public health workforce. Additionally, the evaluation examined the Texas public health workforce's need for training in the 10 essential public health services. Overall, the level of perceived training needs varied dramatically by job category and health department type. When comparing aggregate training needs, public health workers with greater day-to-day contact (nurses, health educators) indicated a greater need for training than their peers who did not, such as those working in administrative positions. When prioritizing and designing future training modules regarding the 10 essential public health services, trainers should consider the effects of job function, location and contact with the public.

Operation characteristics and conditions of training reactor VR-1

International Nuclear Information System (INIS)

Matejka, K.; Kolros, A.; Polach, S.; Sklenka, L.

1994-01-01

The first 3 years of operation of the VR-1 training reactor are reviewed. This period includes its physical start-up (preparation, implementation, results) and operation development as far as the current operating configuration of the reactor core. The physical start-up was commenced using a reactor core referred to as AZ A1, whose physical parameters had been verified by calculation and whose configuration was based on data tested experimentally on the SR-0 reactor at Vochov. The next operating core, labelled AZ A2, was already prepared during the test operation of the VR-1 reactor. Its configuration was such that both of the main horizontal channels, radial and tangential, could be employed. The configuration that followed, AZ A3, was an intermediate step before testing the graphite side reflector. The current reactor core, labelled AZ A3 G, was obtained by supplementing the previous core with a one-sided graphite side reflector. (Z.S.). 2 tabs., 11 figs., 2 refs

Uncertainty and sensitivity analysis for the simulation of a station blackout scenario in the Jules Horowitz Reactor

International Nuclear Information System (INIS)

Ghione, Alberto; Noel, Brigitte; Vinai, Paolo; Demazière, Christophe

2017-01-01

Highlights: • A station blackout scenario in the Jules Horowitz Reactor is analyzed using CATHARE. • Input and model uncertainties relevant to the transient, are considered. • A statistical methodology for the propagation of the uncertainties is applied. • No safety criteria are exceeded and sufficiently large safety margins are estimated. • The most influential uncertainties are determined with a sensitivity analysis. - Abstract: An uncertainty and sensitivity analysis for the simulation of a station blackout scenario in the Jules Horowitz Reactor (JHR) is presented. The JHR is a new material testing reactor under construction at CEA on the Cadarache site, France. The thermal-hydraulic system code CATHARE is applied to investigate the response of the reactor system to the scenario. The uncertainty and sensitivity study was based on a statistical methodology for code uncertainty propagation, and the ‘Uncertainty and Sensitivity’ platform URANIE was used. Accordingly, the input uncertainties relevant to the transient, were identified, quantified, and propagated to the code output. The results show that the safety criteria are not exceeded and sufficiently large safety margins exist. In addition, the most influential input uncertainties on the safety parameters were found by making use of a sensitivity analysis.

Training Tribal Lay Advocates at Sitting Bull College

Science.gov (United States)

Shelley, W. L.

2015-01-01

Students in Sitting Bull College's lay advocate program develop a well-rounded understanding of the law, enabling them to represent defendants in tribal courts. The program offers legal training for its students--and illustrates how American Indian nations can broaden legal representation for Native defendants in tribal courts. It is one of only…

The Emergence of Marketing and Communications Strategy in South African Further Education and Training Colleges

Science.gov (United States)

McGrath, Simon; Akoojee, Salim

2007-01-01

South African further education and training (FET) colleges have been enjoined to become more responsive to their external environment, in keeping with international trends in public vocational education and training (VET) reform. One mechanism for achieving this goal is to market colleges and communicate more effectively to future students,…

Education program at the Massachusetts Institute of Technology research reactor for pre-college science teachers

International Nuclear Information System (INIS)

Hopkins, G.R.; Fecych, W.; Harling, O.K.

1989-01-01

A Pre-College Science Teacher (PCST) Seminar program has been in place at the Massachusetts Institute of Technology (MIT) Nuclear Reactor Laboratory for 4 yr. The purpose of the PCST program is to educate teachers in nuclear technology and to show teachers, and through them the community, the types of activities performed at research reactors. This paper describes the background, content, and results of the MIT PCST program

Comprehensive College Plan for 2002-2003.

Science.gov (United States)

San Antonio Coll., TX.

This plan for San Antonio College (SAC) (Texas), a college of the Alamo Community College District (ACCD), offers vision and mission statements for both ACCD and SAC. In addition, it details the Institutional Effectiveness process and philosophy for SAC. The document also includes SAC strategic goals and initiatives, and unit strategic objectives,…

Development of operator training programmes for Sizewell B

International Nuclear Information System (INIS)

Birnie, S.

1988-01-01

In accordance with existing practice, it is the Central Electricity Generating Board's (CEGB's) intention that the station manager of Sizewell B and future pressurized water reactor (PWR) stations will be responsible for ensuring that his staff perform their designated duties competently. To assist the station managers in fulfilling these responsibilities, the CEGB ensures that all nuclear training needs are identified, effective training strategies are developed and training programmes provided. The management, operation and development of the CEGB Nuclear Power Training Centre is integrated with nuclear power training activities conducted on site and at other locations. A systematic approach to training must be used so that the training is effective, i.e. that the staff can operate the plant safely and economically. To aid in the systematic production of PWR training programmes in general, but in particular for shift operations engineers, a PWR section was established in 1983 at the CEGB Nuclear Power Training Centre. A condition in the site licence for Sizewell B states that a suitable simulator must be available for training operations staff at least one year before fuel loading commences. The work of this section in operations engineer training is summarized. (author)

Contract Training and Computer-Assisted Instruction at Santa Fe Community College.

Science.gov (United States)

Ortego, Sheila; Richards, Beverly

In summer 1993, Santa Fe Community College, New Mexico, created the External Programs Division (EPD) under its credit instruction program to serve the needs of non-traditional students. The EPD encompasses contract training, the Flex Lab, distance education, the AutoDesk Training Center, an Alternative Fuels program, and the corrections training…

Maintenance experience on reactor recirculation pumps at Tarapur Atomic Power Station

International Nuclear Information System (INIS)

Singh, A.K.

1995-01-01

Reactor recirculation pumps at Tarapur Atomic Power Station (TAPS) are vertical, single stage centrifugal pumps having mechanical shaft seals and are driven by vertical mounted 3.3 kV, 3 phase, 1500 h.p. electric motors. During these years of operation TAPS has gained enough experience and expertise on the maintenance of reactor recirculation pumps which are dealt in this article. Failure of mechanical shaft seals, damage on pump carbon bearings, motor winding insulation failures and motor shaft damage have been the main areas of concern on recirculation pump. A detailed procedure step by step with component sketches has helped in eliminating errors during shaft seal assembly and installation. Pressure breakdown devices in seal assembly were rebuilt. Additional coolant water injection for shaft seal cooling was provided. These measures have helped in extending the reactor recirculation pump seal life. Pump bearing problems were mainly due to failure of anti-rotation pins and dowel pins of bearing assembly. These pins were redesigned and strengthened. Motor stator winding insulation failures were detected. Stator winding replacement program has been taken up on regular basis to avoid winding insulation failure due to aging. 3 refs., 2 tabs., 7 figs

Guideline related to training and re-training of research reactor personnel

International Nuclear Information System (INIS)

1983-01-01

The guideline, which entered into force on 1 July 1983, lays down training and re-training requirements to be met by research reactor personnel in the framework of the Radiation Protection Ordinance of 26 November 1969, the Regulation related to the Licensing of Nuclear Facilities of 21 June 1979, and the Regulation related to Further Education in the Field of Radiation Protection 27 January 1975. It contains the scope of application; the principles and objectives; the minimum requirements relating to technical qualification of plant managers, shift personnel, and responsible radiation protection officers; appointment and certification; the preservation of the technical qualification; and exceptional and transitional regulations

Training and education

International Nuclear Information System (INIS)

Bauer, E.; Oria, M.

1977-01-01

The paper deals essentially with problems of training and education in a developing country that has made the decision to launch a nuclear programme. All teaching has a double aim: to transfer knowledge, and to form responsible individuals. In a state each pedagogic action has a relatively definite aim. In the nuclear field this aim can be construction of a research or power reactor (or participation in its construction) or the operation of these reactors. There are no well-defined borders between these various aims and for each aim the overall needs should be defined. The personnel needs can be expressed by a series of desired outlines for each function. The starting point should be the students or the active population (in particular those who have already been employed in a conventional power station). The means to proceed from the original state to the desired situation will be sought. The number of people trained should be at least twice that needed (accidents, holidays, resignations). For technicians and engineers a good basic knowledge of fundamental science is necessary in every case. It should be kept in mind that the government ought to be informed beforehand on the alternate choices by advisers trained in specialized courses, i.e. IAEA courses for decision-makers. First, the local educational means shall be used. For very specialized functions the supplier of the power station will provide an adequate training. Specialized teaching centres abroad will provide additional knowledge to those who already have the required fundamental education. Theoretical learning can be useful only after a long period of training in a reactor department in the country itself or abroad. This training should tend to actual integration in a team. A certain amount of information should be given preferably in situ, in particular in the field of health physics, as each member of the staff must be fully aware of its importance. (author)

Top 10% Admissions in the Borderlands: Access and Success of Borderland Top Students at Texas Public Universities

Science.gov (United States)

Rodríguez, Cristóbal

2016-01-01

This study focuses on Texas Borderland students admitted through the Texas Top 10% admissions policy, which assumes that Top 10% students are college ready for any public university and provides Top 10% high school graduates automatic admission to any 4-year public university in Texas. Using descriptive and inferential statistics, results…

The reconstruction of the training reactor of the Budapest Technical University

International Nuclear Information System (INIS)

Viragh, E.

1981-01-01

The reconstruction of the training reactor between 1978 and 1981 did not hinder the education and training activities of the University. Dosimetric measurements during the test run revealed no additional hazard from the elevation of power from 10 to 100 kW. (author)

"Fisher v. Texas": Strictly Disappointing

Science.gov (United States)

Nieli, Russell K.

2013-01-01

Russell K. Nieli writes in this opinion paper that as far as the ability of state colleges and universities to use race as a criteria for admission goes, "Fisher v. Texas" was a big disappointment, and failed in the most basic way. Nieli states that although some affirmative action opponents have tried to put a more positive spin on the…

Pilot program: NRC severe reactor accident incident response training manual: Severe reactor accident overview

International Nuclear Information System (INIS)

McKenna, T.J.; Martin, J.A.; Miller, C.W.; Hively, L.M.; Sharpe, R.W.; Giitter, J.G.; Watkins, R.M.

1987-02-01

This pilot training manual has been written to fill the need for a general text on NRC response to reactor accidents. The manual is intended to be the foundation for a course for all NRC response personnel. Severe Reactor Accident Overview is the second in a series of volumes that collectively summarize the US Nuclear Regulatory Commission (NRC) emergency response during severe power reactor accidents and provide necessary background information. This volume describes elementary perspectives on severe accidents and accident assesment. Each volume serves, respectively, as the text for a course of instruction in a series of courses. Each volume is accompanied by an appendix of slides that can be used to present this material. The slides are called out in the text

Human-factor operating concept for Borssele Nuclear Power Station

International Nuclear Information System (INIS)

Wieman, J.L.

1995-01-01

The safety level in the operation of a reactor is determined basically by human beings. The Borssele Nuclear Power Station has carried out measures for improving the man-machine interface through training and operating instructions for the shift personnel. The retrofitting of control technology relevant to safety engineering should avoid operating instructions which can cause potential failures. A safety study has shown that the remaining risk following all retrofitting measures remains dependent to the extent of 80% on human factors and that human factors as a whole have a positive effect on reactor safety. (orig.) [de

Alteration in reactor installation (addition of Unit 2) in Shimane Nuclear Power Station, Chugoku Electric Power Co., Inc. (inquiry)

International Nuclear Information System (INIS)

1983-01-01

An inquiry was made by the Ministry of International Trade and Industry to Nuclear Safety Commission on the addition of Unit 2 in Shimane Nuclear Power Station of The Chugoku Electric Power Co., Inc., concerning the technical capability of Chugoku Electric Power Co., Inc., and the plant safety. The NSC requested the Committee on Examination of Reactor Safety to make a deliberation on this subject. Both the technical capability and the safety of Unit 1 were already confirmed by MITI. Unit 2 to be newly added in the Shimane Nuclear Power Station is a BWR power plant with electric output of 820 MW. The examination made by MITI is described: the technical capability of Chugoku Electric Power Co., Inc., the safety of Unit 2 about its siting, reactor proper, reactor cooling system, radioactive waste management, etc. (J.P.N.)

Nuclear energy in Texas: major issues and policy recommendations

International Nuclear Information System (INIS)

1979-01-01

On December 15, 1978 the Texas Energy Advisory Council (TEAC) adopted the Texas Energy Policy, 1978 Update. The Council recognized the great complexity of technical, economic, social, and political issues which have an impact on nuclear power, and therefore decided that a special committee was needed to examine in greater detail the nuclear energy issues facing Texas. This report summarizes the work of the Advisory Committee on Nuclear energy. Topics discussed include: biological affects of low levels of radiation; transportation of radioactive material in Texas; uranium mining and milling; severance tax on uranium mining; alternate reactor designs and fuel cycles; financing nuclear plant construction; cost of disposing of nuclear wastes and decommissioning nuclear plants; low-level wastes; disposal of high-level wastes; commercial spent nuclear fuel reprocessing; and transmutation of radioactive wastes

[Commentary on self-compiled teaching materialsby Singapore Chinese Physician Training College].

Science.gov (United States)

Chen, S H; Cai, H X

2017-05-28

The Singapore Chinese Physician Training College has been playing a role in the development of traditional Chinese medicine (TCM) and the training of TCM talents in modern and contemporary Singapore not to be ignored. Due to the limitations of the objective condition, the College had to creatively compile by themselves 115 volumes of teaching materials with rather complete subjects, which did pay attention to applying theory to practice, ran through the thought of Chinese integrating with western medicine, and is of literature and cultural significance.As a carrier of educational contents and methods, these teaching materials not only embodied the educational idea of the editor, but also reflected the status of TCM development in modern Singapore.

Characteristics and personal exposures of carbonyl compounds in the subway stations and in-subway trains of Shanghai, China.

Science.gov (United States)

Feng, Yanli; Mu, Cuicui; Zhai, Jinqing; Li, Jian; Zou, Ting

2010-11-15

Carbonyl compounds including their concentrations, potential sources, diurnal variations and personal exposure were investigated in six subway stations and in-subway trains in Shanghai in June 2008. The carbonyls were collected onto solid sorbent (Tenax TA) coated with pentafluorophenyl hydrazine (PFPH), followed by solvent extraction and gas chromatography (GC)/mass spectrometry (MS) analysis of the PFPH derivatives. The total carbonyl concentrations of in-subway train were about 1.4-2.5 times lower than in-subway stations. A significant correlation (R>0.5, psubway stations. The diurnal variations in both the subway station and in-subway train showed that the concentrations of most carbonyls were much higher in the morning rush hour than in other sampling periods. Additionally, pronounced diurnal variations of acetaldehyde concentration before and after the evening peak hour in the subway train suggested that passengers contributed to high acetaldehyde levels. The personal exposure showed that the underground subway stations were important microenvironment for exposure to formaldehyde and acetaldehyde. Copyright © 2010 Elsevier B.V. All rights reserved.

[STEM on Station Education

Science.gov (United States)

Lundebjerg, Kristen

2016-01-01

The STEM on Station team is part of Education which is part of the External Relations organization (ERO). ERO has traditional goals based around BHAG (Big Hairy Audacious Goal). The BHAG model is simplified to a saying: Everything we do stimulates actions by others to advance human space exploration. The STEM on Station education initiate is a project focused on bringing off the earth research and learning into classrooms. Educational resources such as lesson plans, activities to connect with the space station and STEM related contests are available and hosted by the STEM on Station team along with their partners such as Texas Instruments. These educational activities engage teachers and students in the current happenings aboard the international space station, inspiring the next generation of space explorers.

Considerations for increasing the competences and capacities of the public health workforce: assessing the training needs of public health workers in Texas

Directory of Open Access Journals (Sweden)

Quiram Barbara

2006-07-01

Full Text Available Abstract Background Over the last two decades, concern has been expressed about the readiness of the public health workforce to adequately address the scientific, technological, social, political and economic challenges facing the field. A 1988 report from the Institute of Medicine (IOM served as a catalyst for the re-examination of the public health workforce. The IOM's call to increase the relevance of public health education and training prompted a renewed effort to identify competences needed by public health personnel and the organizations that employ them. Methods A recent evaluation sought to address the role of the 10 essential public health services in job services among the Texas public health workforce. Additionally, the evaluation examined the Texas public health workforce's need for training in the 10 essential public health services. Results and conclusion Overall, the level of perceived training needs varied dramatically by job category and health department type. When comparing aggregate training needs, public health workers with greater day-to-day contact (nurses, health educators indicated a greater need for training than their peers who did not, such as those working in administrative positions. When prioritizing and designing future training modules regarding the 10 essential public health services, trainers should consider the effects of job function, location and contact with the public.

Technical limits on performance reserves and life expectancy in nuclear power stations with light water reactors

International Nuclear Information System (INIS)

Wanner, R.; Brosi, S.; Duijvestijn, G.

1990-01-01

The safety margin (i.e. the difference between the loads equipment can take and those actually imposed on components) in a reactor pressure vessel is a major factor in the life expectancy of a nuclear power station. This safety margin is reduced considerably by reductions in the toughness of equipment caused by neutron irradiation and growth of cracks. Once the minimum safety margin is infringed, the nuclear power station is at the end of its working life. 13 figs., 11 refs

AKR-1 nuclear training reactor of Dresden Technical University turns twenty-five

International Nuclear Information System (INIS)

Hansen, W.

2003-01-01

Twenty-five years ago, in the night of July 27 to 28, 1978, the AKR-1 nuclear training reactor of the Dresden Technical University went critical for the first time and was commissioned. On the occasion of this anniversary, a colloquy was arranged with representatives from science, politics and industry, at which the reactor's history, the excellent achievements in research and training with the reactor, and the status and perspectives of this research facility were described. The AKR-1 had been built within the framework of the Nuclear Development Program of the then German Democratic Republic (GDR). The Nuclear Power Scientific Division of the Dresden Technical University had been entrusted with the responsibility, among other things, to train university personnel for the GDR Nuclear Power Program. The review by an expert group in 1996 of this plant had resulted in a recommendation in favor of long-term plant operation. A nuclear licensing procedure to this effect was initiated, and the necessary technical backfitting measures were implemented. The AKR-1 plant now equally serves for the specialized training of students and for research. (orig.) [de

Training methods and facilities on reactor and simulators at the Grenoble Nuclear Research Centre

International Nuclear Information System (INIS)

Destot, M.; Siebert, S.

1987-01-01

Siloette is a CEA unit with a threshold vocation: operation of the Siloette 100 KW pool-type research reactor; basic training in reactor physics for nuclear power plant operators; and production of nuclear power plant simulators: PWR, GCR and more generally of all types of industrial unit simulators, thermal power plant, network, chemical plant, etc. From this experience, they would emphasize in particular the synergy arising from these complementary activities, the essential role of training in basic principles as a complement to operation training, and the ever-increasing importance of design ergonomics of the training means

Computerized training program usage at the Fort Calhoun Nuclear Power Station

International Nuclear Information System (INIS)

Ruzic, D.H.; Reed, W.H.; Lawton, R.K.; Fluehr, J.J.

1987-01-01

The increased US Nuclear Regulatory Commission and Institute of Nuclear Power Operations (INPO) interest in the nuclear power industry training programs resulted in the Omaha Public Power District staff at the Fort Calhoun Nuclear Power Station investigating the potential for computerizing their recently accredited training records, student training requirements, and the process of determining student certification status. Additional areas that were desirable were a computerized question data bank with random test generation, maintaining history of question usage, and tracking of the job task analysis process and course objectives. SCI Software's online personnel training information management system (OPTIM) was selected, subsequent to a bid evaluation, to provide these features while operating on the existing corporate IBM mainframe

Study of dietary supplements compositions by neutron activation analysis at the VR-1 training reactor

Science.gov (United States)

Stefanik, Milan; Rataj, Jan; Huml, Ondrej; Sklenka, Lubomir

2017-11-01

The VR-1 training reactor operated by the Czech Technical University in Prague is utilized mainly for education of students and training of various reactor staff; however, R&D is also carried out at the reactor. The experimental instrumentation of the reactor can be used for the irradiation experiments and neutron activation analysis. In this paper, the neutron activation analysis (NAA) is used for a study of dietary supplements containing the zinc (one of the essential trace elements for the human body). This analysis includes the dietary supplement pills of different brands; each brand is represented by several different batches of pills. All pills were irradiated together with the standard activation etalons in the vertical channel of the VR-1 reactor at the nominal power (80 W). Activated samples were investigated by the nuclear gamma-ray spectrometry technique employing the semiconductor HPGe detector. From resulting saturated activities, the amount of mineral element (Zn) in the pills was determined using the comparative NAA method. The results show clearly that the VR-1 training reactor is utilizable for neutron activation analysis experiments.

Microdosimetric studies using a Filtered Fast Neutron Irradiation System of research reactor to application in radiation biology

International Nuclear Information System (INIS)

Rodrigues, Pedro Pereira

2007-01-01

In this work, microdosimetric measurements were performed using a Wall-less Tissue Equivalent Proportional Counter - TEPC with spherical cavity with an inner diameter of 1.27 cm. The TEPC was tilled with pure propane gas, C 3 H 8 at 5.6 kPa (42 Torr) pressure, which is equivalent to 1.3 μm in diameter of unit density tissue. The microdosimetric measurement device was irradiated with fast neutron radiation from Texas A and M University Nuclear Science Center research reactor, in College Station, Texas. The fast neutron beams were emitted with three different power values, 0.5, 1.0 and 2.0 kW. during 1h for both high gain and low gain, totalizing two hours for each power with 0.0083 Gy/min of dose rate. The neutron was filtered using the heavily filtered fast neutron irradiation system (FNIS). from Nuclear Science Center, to obtain a decrease of neutron radiation contamination by gamma ray and so, to gain the neutron microdosimetric spectra as. frequency distribution of lineal energy, dose distribution of lineal energy with good precision, and another quantities as frequency-mean of lineal energy, dose- mean of lineal energy, absorbed dose, equivalent dose and average quality factor of fast neutron. The obtained results were satisfactory, with the neutron microdosimetric spectra showing a gamma ray contamination under 5 %, especially to dose distribution of lineal energy. The results obtained in this work were in agreement when compared with another results from scientific literature, which used another procedure to reduce the neutron contamination by gamma ray. (author)

Station Blackout Analysis for a 3-Loop Westinghouse PWR Reactor Using Trace

International Nuclear Information System (INIS)

El-Sahlamy, N.M.

2017-01-01

One of the main concerns in the area of severe accidents in nuclear reactors is that of station blackout (SBO). The loss of offsite electrical power concurrent with the unavailability of the onsite emergency alternating current (AC) power system can result in loss of decay heat removal capability, leading to a potential core damage which may lead to undesirable consequences to the public and the environment. To cope with an SBO, nuclear reactors are provided with protection systems that automatically shut down the reactor, and with safety systems to remove the core residual heat. This paper provides a best estimate assessment of the SBO scenario in a 3-loop Westinghouse PWR reactor. The evaluation is performed using TRACE, a best estimate computer code for thermal-hydraulic calculations. Two sets of scenarios for SBO analyses are discussed in the current work. The first scenario is the short term SBO where it is assumed that in addition to the loss of AC power, there is no DC power; i.e., no batteries are available. In the second scenario, a long term SBO is considered. For this scenario, DC batteries are available for four hours. The aim of the current SBO analyses for the 3-loop pressurized water reactor presented in this paper is to focus on the effect of the availability of a DC power source to delay the time to core uncovers and heatup

Cycling for Transportation in Sao Paulo City: Associations with Bike Paths, Train and Subway Stations.

Science.gov (United States)

Florindo, Alex Antonio; Barrozo, Ligia Vizeu; Turrell, Gavin; Barbosa, João Paulo Dos Anjos Souza; Cabral-Miranda, William; Cesar, Chester Luiz Galvão; Goldbaum, Moisés

2018-03-21

Cities that support cycling for transportation reap many public health benefits. However, the prevalence of this mode of transportation is low in Latin American countries and the association with facilities such as bike paths and train/subway stations have not been clarified. We conducted a cross-sectional analysis of the relationship between bike paths, train/subway stations and cycling for transportation in adults from the city of Sao Paulo. We used data from the Sao Paulo Health Survey ( n = 3145). Cycling for transportation was evaluated by a questionnaire and bike paths and train/subway stations were geocoded using the geographic coordinates of the adults' residential addresses in 1500-m buffers. We used multilevel logistic regression, taking account of clustering by census tract and households. The prevalence of cycling for transportation was low (5.1%), and was more prevalent in males, singles, those active in leisure time, and in people with bicycle ownership in their family. Cycling for transportation was associated with bike paths up to a distance of 500 m from residences (OR (Odds Ratio) = 2.54, 95% CI (Confidence interval) 1.16-5.54) and with the presence of train/subway stations for distances >500 m from residences (OR = 2.07, 95% CI 1.10-3.86). These results are important to support policies to improve cycling for transportation in megacities such as Sao Paulo.

Moroccan TRIGA nuclear reactor, an important tool for the development of research, education and training

International Nuclear Information System (INIS)

Caoui, A.

2011-01-01

Full text: The construction of the Nuclear Research Center of Maamora (NRCM) will enable to the National Center for Nuclear Energy, Sciences and Techniques (CNESTEN) to fulfill its missions for promotion of nuclear techniques in socioeconomic fields, act as technical support for the authorities, and contribute to the introduction of nuclear power for electricity generation considered in the new energy strategy as alternative option for the period 2020-2030. The CNESTEN has commisioned its nuclear research reactor Triga Mark II of 2000 KW on 2007 for wich the operating authorization was delivered on 2009. This research reactor is the keystone structure of the NRCM, its existing and planed utilization include: production of radioisotopes for medical use, neutron activation analysis, non-destructive examination techniques, neutron scattering, reactor physics research and training. In term of human ressources development, CNESTEN is more focusing on education and training for wich an international training Center is under development. The TRIGA research reactor will be an important component of this center. In order to promote the utilization of the reserch reactor in socio-economical sectors at national level, CNESTEN organizea meetings, schools and conferences around each of the reactor applications, and offers the opportunity to researchers, students, socio-economic operators to know more about reactor utilization within scientific visits, courses and training programs. At the international level, CNESTEN strengthens its international partenership. The regional and international cooperation with IAEA, AFRA and bilateral parteners (USA, France), constitutes the platform for capacity building in different areas of CNESTEN RIGA research reactor utilization

SARIE upgrade: Nuclear reactor and water systems 'engineering and training' simulator

International Nuclear Information System (INIS)

Roth, P.

2006-01-01

Confronted as of its origins with the on-board layout constraints of the French Navy ships, TECHNICATOME integrates, as of the design, the ergonomics and the risks control related to the human factors. During more than 30 years, TECHNICATOME demonstrated a one of a kind know-how from the design to the execution of powerful, flexible and highly available nuclear compact reactors. A total control which includes up to the supervision and monitoring systems, the acoustic discreetly of the systems and its components, implemented on on-board reactors, testing reactors as well as experimental reactors. The functionalities of simulation were right from the start used by TECHNICATOME during the design phase of these installations to carry out operation engineering analyses on the thermal hydraulic and neutron aspects, to validate the principles of operation of the supervision systems like by the use of digital models in 3D CAD to validate the kinematics of operation or the interactions between systems. More recently, and starting from the end of the Nineties, a thought needs was launched to determine the interests related to the development of a training simulator associated with these installations with objectives, among others, to ensure the phase of initial training of the new operators, to widen the field of the training to the accidental situations, the management of crisis and crews behaviour supervision, the possibilities of replay which support the consolidation of the acquired knowledge(debriefing) with situation resume, and to increase the overall training capacity. An upgrade and modernisation project of these various simulation means was thus launched since 2001 with the objective to optimize the whole of the tasks supported by these means. (author)

Development of remote decontamination technologies improving internal environment of reactor buildings at Fukushima Daiichi Nuclear Power Station

International Nuclear Information System (INIS)

Hotta, Koji; Hayashi, Hirotada; Sakai, Hitoshi

2016-01-01

The reactor buildings at the Fukushima Daiichi Nuclear Power Station of Tokyo Electric Power Co., Inc., which was seriously damaged by the Great East Japan Earthquake of March 11, 2011, have been highly contaminated by radioactive materials. To safely and efficiently advance the processes related to the forthcoming decommissioning of the reactors, it is necessary to improve the hazardous environment inside the reactor buildings. During the more than four years that have elapsed since the Great East Japan Earthquake, Toshiba has been implementing various measures to reduce the ambient dose rates inside the reactor buildings through decontamination work and participation in a national project for the development of remote decontamination technologies for reactor buildings. A variety of vehicles and technologies to support decontamination work have been developed through these activities, and are significantly contributing to improvement of the environment inside the reactor buildings. (author)

Online Contract Training: Applying Organization Theory to Reconcile Competing Missions within Community Colleges

Science.gov (United States)

Ghosh, Rajashi; Githens, Rod P.

2011-01-01

Community colleges in the United States have become major providers of human resource development services, particularly through offering workforce development training to local employers. The addition of workforce development services to community colleges is a fairly recent phenomenon. Some see workforce development efforts as diluting community…

At the Intersection of College & Community

Science.gov (United States)

Pierce, Dennis

2016-01-01

By purchasing abandoned facilities and transforming them into vibrant hubs for culture and education, community colleges are fulfilling one of their key missions: revitalizing their communities. But these types of projects can be fraught with challenges as well. Here's how Austin Community College (Texas), Manchester Community College…

Surgical Residency Training in Developing Countries: West African College of Surgeons as a Case Study.

Science.gov (United States)

Ajao, Oluwole Gbolagunte; Alao, Adekola

2016-01-01

In 1904, William Halsted introduced the present model of surgical residency program which has been adopted worldwide. In some developing countries, where surgical residency training programs are new, some colleges have introduced innovations to the Halsted's original concept of surgical residency training. These include 1) primary examination, 2) rural surgical posting, and 3) submission of dissertation for final certification. Our information was gathered from the publications on West African College of Surgeons' (WACS) curriculum of the medical schools, faculty papers of medical schools, and findings from committees of medical schools. Verbal information was also gathered via interviews from members of the WACS. Additionally, our personal experience as members and examiners of the college are included herein. We then noted the differences between surgical residency training programs in the developed countries and that of developing countries. The innovations introduced into the residency training programs in the developing countries are mainly due to the emphasis placed on paper qualifications and degrees instead of performance. We conclude that the innovations introduced into surgical residency training programs in developing countries are the result of the misconception of what surgical residency training programs entail. Published by Elsevier Inc.

NCATE and Texas Eyeball to Eyeball: Who Will Blink?

Science.gov (United States)

Watts, Doyle

1989-01-01

The National Council for Accreditation of Teacher Education (NCATE) and Texas teacher training institutions are squaring off because of Texas SB 994, a law that eliminates undergraduate degrees in education and caps required credit hours in undergraduate teacher education courses. This article interviews Carl Parker, Hendrik Gideonse, Mary…

Safety Evaluation Report related to the operation of Comanche Peak Steam Electric Station, Units 1 and 2 (Docket Nos. 50-445 and 50-446). Supplement No. 7

International Nuclear Information System (INIS)

1985-01-01

Supplement 7 to the Safety Evaluation Report for the Texas Utilities Electric Company application for a license to operate Comanche Peak Steam Electric Station, Units 1 and 2 (Docket Nos. 50-445, 50-446), located in Somervell County, Texas, has been jointly prepared by the Office of Nuclear Reactor Regulation and the Comanche Peak Technical Review of the US Nuclera Regulatory Commission. This supplement provides the results of the staff's evaluation and resolution of approximately 80 technical concerns and allegations in the areas of Electric/Instrumentation and Test Programs regarding construction and plant readiness testing practices at the Comanche Peak facility. Issues raised during Atomic Safety and Licensing Board hearings will be dealt with in future supplements to the Safety Evaluation Report

Safety Evaluation Report related to the operation of Comanche Peak Steam Electric Station, Units 1 and 2 (Docket Nos. 50-445 and 50-446). Supplement No. 8

International Nuclear Information System (INIS)

1985-02-01

Supplement 8 to the Safety Evaluation Report for the Texas Utilities Electric Company application for a license to operate Comanche Peak Steam Electric Station, Units 1 and 2 (Docket Nos. 50-445, 50-446), located in Somervell County, Texas, has been jointly prepared by the Office of Nuclear Reactor Regulation and the Comanche Peak Technical Review Team of the US Nuclear Regulatory Commission. This Supplement provides the results of the staff's evaluation and resolution of approximately 80 technical concerns and allegations relating to civil and structural and miscellaneous issues regarding construction and plant readiness testing practices at the Comanche Peak facility. Issues raised during recent Atomic Safety and Licensing Board hearings will be dealt with in future supplements to the Safety Evaluation Report

Safety evaluation report related to the operation of Comanche Peak Steam Electric Station, Units 1 and 2 (Docket Nos. 50-445 and 50-446): Supplement No. 21

International Nuclear Information System (INIS)

1989-04-01

Supplement 21 to the Safety Evaluation Report related to the operation of the Comanche Peak Steam Electric Station (CPSES), Units 1 and 2 (NUREG-0797), has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission (NRC). The facility is located in Somervell County, Texas, approximately 40 miles southwest of Fort Worth, Texas. This supplement reports the status of certain issues that had not been resolved when the Safety Evaluation Report and Supplements 1, 2, 3, 4, 6, and 12 to that report were published. This supplement also lists the new issues that have been identified since Supplement 12 was issued and includes the evaluations for licensing items resolved in this interim period. 21 refs

EAC training and medical support for International Space Station astronauts.

Science.gov (United States)

Messerschmid, E; Haignere, J P; Damian, K; Damann, V

2000-11-01

The operation of the International Space Station (ISS) will be a global multilateral endeavour. Each International Partner will be responsible for the operation of its elements and for providing a crew complement proportional to its share of the overall resources. The preparations of the European Astronaut Centre to furnish training and medical support for the ISS astronauts are described.

Dose management programmes at Kaiga Generating Station

International Nuclear Information System (INIS)

Vijayan, P.; Prabhakaran, V.; Managavi, Sadashiv B.; Danannavar, Veerendra; Biju, P.; Manoj Kumar, M.; Shrikrishna, U.V.

2001-01-01

Kaiga Generating Station (KGS) has two units of pressurized heavy water reactors of 220 MWe each capacity. KGS-2 started power generation since 1999 and KGS-1 since 2000. Several programmes such as assessment of radioactive condition, training on radiological safety aspects, job planning in radioactive areas, etc. are conducted periodically to implement an effective dose control programmes in KGS. These efforts are briefly discussed in this report. Facilities and techniques to implement ALARA programs are also highlighted in this report. (author)

Atmospheric boundary layer evening transitions over West Texas

Science.gov (United States)

A systemic analysis of the atmospheric boundary layer behavior during some evening transitions over West Texas was done using the data from an extensive array of instruments which included small and large aperture scintillometers, net radiometers, and meteorological stations. The analysis also comp...

Training of operating personnel for nuclear ships

International Nuclear Information System (INIS)

Lakey, J.R.A.; Gibbs, D.C.C.

1983-01-01

Training for Nuclear Power Plant Operators is provided by the Royal Navy in support of the Nuclear Submarine Programme which is based on the Pressurised Water Reactor. The Royal naval college has 21 years of experience in this training field in which the core is the preparation of graduate electro-mechanical engineers to assume the duties of marine engineer in command of a team of supporting Engineer Officers of the Watch and Fleet Chief Petty Officers. The paper describes the training programme and shows how it is monitored by academic, professional and naval authorities and indicates the use of feedback from the user. The lynch pin of the programme is a post-graduate diploma course in Nuclear Reactor Technology attended by graduates after gaining some practical experience at sea. The course which is described in detail makes use of simplified simulators and models to develop the principles, these are applied on the JASON Training Reactor with the emphasis on in-core experiments demonstrating reactivity effects and instrumentation interpretation. The training programme provides for interaction between academic education, practical experience, applied education, full plant simulation training and on-the-job training in which boards or examinations have to be successfully passed at each stage. (author)

Development of a national sport event risk management training program for college command groups.

Science.gov (United States)

Hall, Stacey A

2013-01-01

The US Department of Homeland Security identified college sport venues as terrorist targets due to the potential for mass casualties and catastrophic social and economic impact. Therefore, it is critical for college sport safety and security personnel to implement effective risk management practices. However, deficiencies have been identified in the level of preparedness of college sport event security personnel related to risk management training and effective emergency response capabilities. To address the industry need, the National Center for Spectator Sports Safety and Security designed, developed, and evaluated a national sport event risk management training program for National Collegiate Athletic Association command groups. The purpose of this article was to provide an overview of the design, development, and evaluation process.

Lead-cooled flexible conversion ratio fast reactor

International Nuclear Information System (INIS)

Nikiforova, Anna; Hejzlar, Pavel; Todreas, Neil E.

2009-01-01

Lead-cooled reactor systems capable of accepting either zero or unity conversion ratio cores depending on the need to burn actinides or operate in a sustained cycle are presented. This flexible conversion ratio reactor is a pool-type 2400 MWt reactor coupled to four 600 MWt supercritical CO 2 (S-CO 2 ) power conversion system (PCS) trains through intermediate heat exchangers. The cores which achieve a power density of 112 kW/l adopt transuranic metallic fuel and reactivity feedbacks to achieve inherent shutdown in anticipated transients without scram, and lead coolant in a pool vessel arrangement. Decay heat removal is accomplished using a reactor vessel auxiliary cooling system (RVACS) complemented by a passive secondary auxiliary cooling system (PSACS). The transient simulation of station blackout (SBO) using the RELAP5-3D/ATHENA code shows that inherent shutdown without scram can be accommodated within the cladding temperature limit by the enhanced RVACS and a minimum (two) number of PSACS trains. The design of the passive safety systems also prevents coolant freezing in case all four of the PSACS trains are in operation. Both cores are also shown able to accommodate unprotected loss of flow (ULOF) and unprotected transient overpower (UTOP) accidents using the S-CO 2 PCS.

Annual compilation and analysis of hydrologic data for urban studies in the Bryan, Texas, metropolitan area, 1969

Science.gov (United States)

Robbins, W.D.

1972-01-01

Hydrologic investigations of urban areas in Texas were begun by the U.S. Geological Survey in 1954. These studies are now in progress in Austin, Houston, Dallas, Dallas County, Fort Worth, San Antonio, and Bryan. Hydrologic investigations of urban areas in Texas were begun by the U.S. Geological Survey in 1954. These studies are now in progress in Austin, Houston, Dallas, Dallas County, Fort Worth, San Antonio, and Bryan. 1. To determine, on the basis of historical data and hydrologic analyses, the magnitude and frequency of floods. 2. To document and define the areal extent of floods of greater than ordinary magnitude. 3. To determine the effect of urban development on flood peaks and volume. 4. To provide applied research facilities for studies at Texas A & M University at College Stations. This report, the first in a series of reports to be published annually, is primarily applicable to objectives 2, 3, and 4. The report presents the basic hydrologic data collected in two study areas during the 1969 water year (October 1, 1968, to September 30, 1969) and basic hydrologic data collected during part of the 1968 water year (April 5, 1968, to September 30, 1968). The locations of the two basins within the study area, Burton Creek and Hudson Creek, are shown on figure 1.

A feasibility assessment of nuclear reactor power system concepts for the NASA Growth Space Station

Science.gov (United States)

Bloomfield, H. S.; Heller, J. A.

1986-01-01

A preliminary feasibility assessment of the integration of reactor power system concepts with a projected growth Space Station architecture was conducted to address a variety of installation, operational, disposition and safety issues. A previous NASA sponsored study, which showed the advantages of Space Station - attached concepts, served as the basis for this study. A study methodology was defined and implemented to assess compatible combinations of reactor power installation concepts, disposal destinations, and propulsion methods. Three installation concepts that met a set of integration criteria were characterized from a configuration and operational viewpoint, with end-of-life disposal mass identified. Disposal destinations that met current aerospace nuclear safety criteria were identified and characterized from an operational and energy requirements viewpoint, with delta-V energy requirement as a key parameter. Chemical propulsion methods that met current and near-term application criteria were identified and payload mass and delta-V capabilities were characterized. These capabilities were matched against concept disposal mass and destination delta-V requirements to provide a feasibility of each combination.

A feasibility assessment of nuclear reactor power system concepts for the NASA growth Space Station

International Nuclear Information System (INIS)

Bloomfield, H.S.; Heller, J.A.

1986-01-01

A preliminary feasibility assessment of the integration of reactor power system concepts with a projected growth space station architecture was conducted to address a variety of installation, operational, disposition and safety issues. A previous NASA sponsored study, which showed the advantages of space station related concepts, served as the basis for this study. A study methodology was defined and implemented to assess compatible combinations of reactor power installation concepts, disposal destinations, and propulsion methods. Three installation concepts that met a set of integration criteria were characterized from a configuration and operational viewpoint, with end-of-life disposal mass identified. Disposal destinations that met current aerospace nuclear safety criteria were identified and characterized from an operational and energy requirements viewpoint, with delta-V energy requirement as a key parameter. Chemical propulsion methods that met current and near-term application criteria were identified and payload mass and delta-V capabilities were characterized. These capabilities were matched against concept disposal mass and destination delta-V requirements to provide a feasibility of each combination

Establishing a Research and Evaluation Capability for the Joint Medical Education and Training Campus.

Science.gov (United States)

Kirby, Sheila Nataraj; Marsh, Julie A; Thie, Harry J

2011-01-01

In calling for the transformation of military medical education and training, the 2005 Base Realignment and Closure Commission recommended relocating basic and specialty enlisted medical training to a single site to take advantage of economies of scale and the opportunity for joint training. As a result, a joint medical education and training campus (METC) has been established at Fort Sam Houston, Texas. Two of METC's primary long-term goals are to become a high-performing learning organization and to seek accreditation as a community college. Such goals require a clear model of organizational improvement with well-defined metrics for measuring its performance and using research and evaluation to assess and improve that performance. Lessons learned from a review of practices at institutions with similar missions-such as community colleges, corporate universities, the UK's Defence Medical Education and Training Agency, and other federal agencies, such as the Veterans Health Administration-establish a clear need for an office of institutional research to help METC attain its organizational goals. They also provide useful recommendations regarding the METC office's structure, scope, and governance.

Reactor training simulator for the Replacement Research Reactor (RRR)

International Nuclear Information System (INIS)

Etchepareborda, A; Flury, C.A; Lema, F; Maciel, F; Alegrechi, D; Damico, M; Ibarra, G; Muguiro, M; Gimenez, M; Schlamp, M; Vertullo, A

2004-01-01

The main features of the ANSTO Replacement Research Reactor (RRR) Reactor Training Simulator (RTS) are presented.The RTS is a full-scope and partial replica simulator.Its scope includes a complete set of plant normal evolutions and malfunctions obtained from the plant design basis accidents list.All the systems necessary to implement the operating procedures associated to these transients are included.Within these systems both the variables connected to the plant SCADA and the local variables are modelled, leading to several thousands input-output variables in the plant mathematical model (PMM).The trainee interacts with the same plant SCADA, a Foxboro I/A Series system.Control room hardware is emulated through graphical displays with touch-screen.The main system models were tested against RELAP outputs.The RTS includes several modules: a model manager (MM) that encapsulates the plant mathematical model; a simulator human machine interface, where the trainee interacts with the plant SCADA; and an instructor console (IC), where the instructor commands the simulation.The PMM is built using Matlab-Simulink with specific libraries of components designed to facilitate the development of the nuclear, hydraulic, ventilation and electrical plant systems models [es

NORA project offers unique reactor research and advanced training opportunities

International Nuclear Information System (INIS)

1961-01-01

An international program for reactor research and advanced training for a period of three years has been established in connection with the Norwegian critical assembly NORA. The aim of the project is to determine, through integral experiments, the basic reactor physics data for lattices moderated with light-water, heavy-water or mixtures of heavy and light water, with fuels of different sizes and spacing, three different enrichments and compositions. The objectives, programme, and facilities are described in details

Principles of education and training of industrial engineers for nuclear power plants

International Nuclear Information System (INIS)

Ackermann, G.; Meyer, K.; Brune, W.

1977-01-01

The report gives a short account of the development and experience of the education and advanced professional training system for engineers for the nuclear power stations of the GDR. The basic education for engineers is carried out at universities and colleges. Graduate engineers who have been working in industrial establishments outside nuclear power stations for a longer time get their basic education in nuclear engineering through postgraduate studies. Graduate engineers with a basic knowledge of nuclear engineering are trained at the Nuclear Power Plant School of the nuclear power station Rheinsberg and at the nuclear power stations of the GDR under practical conditions relating to their future job. In addition to basic theoretical knowledge, training at a nuclear power plant simulator plays an important role. This permits the training of the staff under regular operating conditions including transient processes and under unusual conditions. Further particular modes of advanced professional training such as courses in radiation protection and further postgraduate studies are described. This system of education has proved successful. It will be developed further to meet the growing demands. (author)

Education and training at the Rensselaer Polytechnic Institute reactor critical facility

International Nuclear Information System (INIS)

Harris, D.R.

1989-01-01

The Rensselaer Polytechnic Institute (RPI) Reactor Critical Facility (RCF) has provided hands-on education and training for RPI and other students for almost a quarter of a century. The RCF was built in the 1950s by the American Locomotive Company (ALCO) as a critical facility in which to carry out experiments in support of the Army Package power Reactor (APPR) program. A number of APPRs were built and operated. In the middle 1960s, ALCO went out of business and provided the facility to RPI. Since that time, RPI has operated the RCF primarily in a teaching mode in the nuclear engineering department, although limited amounts of reactor research, activation analysis, and reactivity assays have been carried out as well. Recently, a U.S. Department of Energy (DOE) upgrade program supported refueling the RCF with 4.81 wt% enriched UO 2 high-density pellets clad in stainless steel rods. The use of these SPERT (F1) fuel rods in the RCF provided a cost-effective approach to conversion from high-enrichment bombgrade fuel to low-enrichment fuel. More important, however, is the fact that the new fuel is of current interest for light water power reactors with extended lifetime fuel. Thus, not only are critical reactor experiments being carried out on the fuel but, more importantly, the quality of the education and training has been enhanced

State Level Review of Doctoral Programs in Texas.

Science.gov (United States)

Whittington, Nil

Review of doctoral degree programs in Texas public colleges and universities is discussed. Attention is directed to review procedures and strengths and weaknesses in the state's doctoral programs in educational psychology, counseling and guidance, and student personnel services. Doctoral programs were reviewed because of their high cost and a…

Investigation of slightly forced buoyant flow in a training reactor

International Nuclear Information System (INIS)

Legradi, G.; Aszodi, A.; Por, G.

2001-01-01

A measurement based on the temperature noise analysis method was carried out in the Training Reactor of the Budapest University of Technology and Economics. The main goals were the estimation of the flow velocity immediately above the reactor core and investigation of the thermal-hydraulical conditions of the reactor, mainly in the core. Subsequently 2D and 3D computations were carried out with the aid of the code CFX- 4.3. The main objective of the 2D calculation was to clarify the thermal-hydraulical conditions of the whole reactor tank with a reasonable computing demand. It was also necessary to accomplish 3D numerical investigations of the reactor core and the space above since three dimensional effects of the flow could only be studied in this way. In addition, obtaining certain boundary conditions of the 3D computations was another significant aim of the 2D investigations. It is important that the results of the noise analysis and the operational measuring system of the reactor gave us a basis for verifying our computations.(author)

Building Employment Training Partnerships between Vocational Rehabilitation and Community Colleges

Science.gov (United States)

Lindstrom, Lauren E.; Flannery, K. Brigid; Benz, Michael R.; Olszewski, Brandon; Slovic, Roz

2009-01-01

This article examined the implementation of an occupational skills training partnership developed between the Oregon Office of Vocational Rehabilitation Services and four local community colleges. Case study methods were used to describe the pattern of services provided to rehabilitation consumers and document the resulting changes in the…

Reactor Safety Commission Code of Practice for Pressurized Water Reactors

International Nuclear Information System (INIS)

1990-01-01

The Reactor Safety Commission of the Federal German Republic has summarized in the form of Official Guidelines the safety requirements which, in the Commission's view, have to be met in the design, construction and operation of a nuclear power station equipped with a pressurized water reactor. The Third Edition of the RSK Guidelines for pressurized water reactors dated 14.10.81. is a revised and expanded version of the Second Edition dated 24.1.79. The Reactor Safety Commission will with effect from October 1981 use these Guidelines in consultations on the siting of and safety concept for the installation approval of future pressurized water reactors and will assess these nuclear power stations during their erection in the light of these Guidelines. They have not however been immediately conceived for the adaptation of existing nuclear power stations, whether under construction or in operation. The scope of application of these Guidelines to such nuclear power stations will have to be examined for each individual case. The main aim of the Guidelines is to simplify the consultation process within the reactor Safety Commission and to provide early advice on the safety requirements considered necessary by the Commission. (author)

Short-term performance effects of three different low-volume strength-training programmes in college male soccer players

DEFF Research Database (Denmark)

Brito, João; Vasconcellos, Fabrício; Oliveira, José

2014-01-01

This study aimed to analyse the short-term performance effects of three in-season low-volume strength-training programmes in college male soccer players. Fifty-seven male college soccer players (age: 20.31.6 years) were randomly assigned to a resistance-training group (n=12), plyometric training.......001) compared with the control group. No differences were observed in 5-m sprint and agility performances (p>0.05). Overall, the results suggest that in-season low-volume strength training is adequate for developing strength and speed in soccer players....

Setting-up of remote reactor LAB and tapping into CARRN for distance education and training in nuclear field

Energy Technology Data Exchange (ETDEWEB)

Park, Eugene [The Nelson Mandeal African Institute of Science and Technology, Arusha (Tanzania, United Republic of)

2013-07-01

For a developing country embarking on a research reactor project, building adequate human resource capacity is one of the biggest challenges. Tanzania has been considering a research reactor for some time. The success of future research reactor project impinges on vigorous education and training of necessary personnel to operate and fully utilize the facility. In Africa, underutilization of research reactors is a chronic issue. It is not only misuse of valuable resources but also poses potential safety and security concerns. To mitigate such concerns and to promote education and training, Central African Research Reactor Network (CARRN) was formed in June of 2011. Borrowing from Jordan's success, this paper presents customised curricula to take advantage of CARRN for distance education and training in nuclear field.

Setting-up of remote reactor LAB and tapping into CARRN for distance education and training in nuclear field

International Nuclear Information System (INIS)

Park, Eugene

2013-01-01

For a developing country embarking on a research reactor project, building adequate human resource capacity is one of the biggest challenges. Tanzania has been considering a research reactor for some time. The success of future research reactor project impinges on vigorous education and training of necessary personnel to operate and fully utilize the facility. In Africa, underutilization of research reactors is a chronic issue. It is not only misuse of valuable resources but also poses potential safety and security concerns. To mitigate such concerns and to promote education and training, Central African Research Reactor Network (CARRN) was formed in June of 2011. Borrowing from Jordan's success, this paper presents customised curricula to take advantage of CARRN for distance education and training in nuclear field

Nuclear reactor physics course for reactor operators

International Nuclear Information System (INIS)

Baeten, P.

2006-01-01

The education and training of nuclear reactor operators is important to guarantee the safe operation of present and future nuclear reactors. Therefore, a course on basic 'Nuclear reactor physics' in the initial and continuous training of reactor operators has proven to be indispensable. In most countries, such training also results from the direct request from the safety authorities to assure the high level of competence of the staff in nuclear reactors. The aim of the basic course on 'Nuclear Reactor Physics for reactor operators' is to provide the reactor operators with a basic understanding of the main concepts relevant to nuclear reactors. Seen the education level of the participants, mathematical derivations are simplified and reduced to a minimum, but not completely eliminated

Invasive plants found in east Texas forests, 2009 forest inventory and analysis factsheet

Science.gov (United States)

Sonja N. Oswalt; Christopher M. Oswalt

2011-01-01

This science update provides information on the presence and cover of nonnative invasive plants found in forests of the eastern region of the State of Texas based on an annual inventory conducted by the Forest Inventory and Analysis (FIA) Program at the Southern Research Station of the U.S. Department of Agriculture Forest Service in cooperation with the Texas Forest...

Reactor physics studies at the Zittau Training and research reactor ZLFR

Energy Technology Data Exchange (ETDEWEB)

Konschak, K.; Horche, W.; Honisch, H.; Berger, J. (Ingenieurhochschule Zittau (German Democratic Republic). Sektion Kraftwerksanlagenbau und Energieumwandlung); Doerschel, B. (Technische Univ., Dresden (German Democratic Republic). Sektion Physik)

1982-04-01

It is reported on experimental studies during the start-up period of the Zittau training and research reactor ZLFR. The critical mass obtained is in good agreement with the calculated value. It corresponds to a core charge of 90 fuel assemblies ECH-1. The shutdown reactivity of the safety rod and of the three control rods is 3.2% in total. The reactivity effects due to shuffling, internals, and configuration modifications as well as to intentional or unintentional changes in the operating conditions have been analyzed from the viewpoint of safe operation.

Light Water Reactor Sustainability Program: Analysis of Pressurized Water Reactor Station Blackout caused by external flooding using the RISMC toolkit

International Nuclear Information System (INIS)

2014-01-01

The existing fleet of nuclear power plants is in the process of extending its lifetime and increasing the power generated from these plants via power uprates. In order to evaluate the impacts of these two factors on the safety of the plant, the Risk Informed Safety Margin Characterization project aims to provide insights to decision makers through a series of simulations of the plant dynamics for different initial conditions (e.g., probabilistic analysis and uncertainty quantification). This paper focuses on the impacts of power uprate on the safety margin of a boiling water reactor for a flooding induced station black-out event. Analysis is performed by using a combination of thermal-hydraulic codes and a stochastic analysis tool currently under development at the Idaho National Laboratory, i.e. RAVEN. We employed both classical statistical tools, i.e. Monte-Carlo, and more advanced machine learning based algorithms to perform uncertainty quantification in order to quantify changes in system performance and limitations as a consequence of power uprate. Results obtained give a detailed investigation of the issues associated with a plant power uprate including the effects of station black-out accident scenarios. We were able to quantify how the timing of specific events was impacted by a higher nominal reactor core power. Such safety insights can provide useful information to the decision makers to perform risk informed margins management.

CAREER TRAINING IN HOTEL AND RESTAURANT OPERATION...AT CITY COLLEGE OF SAN FRANCISCO.

Science.gov (United States)

BATMALE, LOUIS F.; MULLANY, GEORGE G.

THE HOTEL AND RESTAURANT PROGRAM, ONE OF 35 SEMIPROFESSIONAL TRAINING PROGRAMS AT CITY COLLEGE OF SAN FRANCISCO, COMBINES GENERAL EDUCATION, RELATED BUSINESS INSTRUCTION, HOTEL AND RESTAURANT CLASSES, FOOD PREPARATION AND SERVICE TRAINING, AND WORK EXPERIENCE. THIS DESCRIPTION OF THE PROGRAM INCLUDES (1) PURPOSES AND OBJECTIVES, (2) CURRICULUM,…

Pilot randomized controlled trial of dialectical behavior therapy group skills training for ADHD among college students.

Science.gov (United States)

Fleming, Andrew P; McMahon, Robert J; Moran, Lyndsey R; Peterson, A Paige; Dreessen, Anthony

2015-03-01

ADHD affects between 2% and 8% of college students and is associated with broad functional impairment. No prior randomized controlled trials with this population have been published. The present study is a pilot randomized controlled trial evaluating dialectical behavior therapy (DBT) group skills training adapted for college students with ADHD. Thirty-three undergraduates with ADHD between ages 18 and 24 were randomized to receive either DBT group skills training or skills handouts during an 8-week intervention phase. ADHD symptoms, executive functioning (EF), and related outcomes were assessed at baseline, post-treatment, and 3-month follow-up. Participants receiving DBT group skills training showed greater treatment response rates (59-65% vs. 19-25%) and clinical recovery rates (53-59% vs. 6-13%) on ADHD symptoms and EF, and greater improvements in quality of life. DBT group skills training may be efficacious, acceptable, and feasible for treating ADHD among college students. A larger randomized trial is needed for further evaluation. © 2014 SAGE Publications.

Radiation conditions at the training IRT-2000 and IR-100 reactors

International Nuclear Information System (INIS)

Fedorin, Eh.V.; Bronshtejn, I.Eh; Martynov, Yu.N.; Chistyakov, N.I.

1978-01-01

The experience is reviewed of radiation hygiene surveys and radiation safety provision during instructional processes on two training and research nuclear reactors of the IRT-2000 type (No. 1 and No. 2) and on an IR-200 reactor. From an analysis of individual dosimetry data the conclusion is made that the trainees and personnel are exposed mainly to external gamma-radiation and also, to a minor degree, to thermal neutrons and beta-radiation. It has been found that a high level of radiation safety is ensured on the training and research so that research and instruction activities are conducted at annual levels of exposure substantially lower than 0.5 rem in the case of trainees and 5 rem in the case of personnel

New control and safety rod unit for the training reactor of the Dresden Technical University

International Nuclear Information System (INIS)

Adam, E.; Schab, J.; Knorr, J.

1983-01-01

The extension of the experimental training of students at the training reactor AKR of the Dresden Technical University requires the reconstruction of the reactor with a new control and safety rod unit. The specific conditions at the AKR led to a new variant. Results of preliminary experiments, design and mode of operation of the first unit as well as hitherto gained operation experiences are presented. (author)

Technical Basis for Physical Fidelity of NRC Control Room Training Simulators for Advanced Reactors

Energy Technology Data Exchange (ETDEWEB)

Minsk, Brian S.; Branch, Kristi M.; Bates, Edward K.; Mitchell, Mark R.; Gore, Bryan F.; Faris, Drury K.

2009-10-09

The objective of this study is to determine how simulator physical fidelity influences the effectiveness of training the regulatory personnel responsible for examination and oversight of operating personnel and inspection of technical systems at nuclear power reactors. It seeks to contribute to the U.S. Nuclear Regulatory Commission’s (NRC’s) understanding of the physical fidelity requirements of training simulators. The goal of the study is to provide an analytic framework, data, and analyses that inform NRC decisions about the physical fidelity requirements of the simulators it will need to train its staff for assignment at advanced reactors. These staff are expected to come from increasingly diverse educational and experiential backgrounds.

Purification and solidification of reactor wastes at a Canadian nuclear generating station

International Nuclear Information System (INIS)

Buckley, L.P.; Burt, D.A.

1981-06-01

Chalk River Nuclear Laboratories are developing methods to condition power reactor wastes and to immobilize their radionuclides. Evaporation alone and combined with bituminization has been an important part of the program. After testing at the laboratories a 0.5 m 2 wiped-film evaporator was sent to the Douglas Point Nuclear Generating Station (220 MWe) to demonstrate its suitability to handle typical reactor liquid wastes. Two specific tasks undertaken with the wiped-film evaporator were successfully completed. The first was purification of contaminated heavy water which had leaked from the moderator circuit. The heavy water is normally recovered, cleaned by filters and ion-exchange resin and then upgraded by electrolysis. Cleaning the heavy water with the wiped-film evaporator produced better quality water for upgrading than had been achieved by any previous method and at much lower operating cost. The second task was to concentrate and immobilize a decontamination waste. The waste was generated from the decontamination of pump bowls used in the primary heat transport circuit. The simultaneous addition of the liquid waste and bitumen emulsion to the wiped-film evaporator produced a solid containing 30 wt% waste solids in a bitumen matrix. The volume reduction achieved was 16:1 based on the volumes of initial liquid waste and the final product generated. The quantity sent to storage was 20 times less than had the waste been immobilized in a cement matrix. The successful demonstration has resulted in a proposal to install a wiped-film evaporator at the station to clean heavy water and immobilize decontamination wastes. (author)

Nuclear power training programmes in Spain

International Nuclear Information System (INIS)

Tanarro, A.; Izquierdo, L.

1977-01-01

The introduction of nuclear power in Spain is developing very rapidly. At present 1.1GW(e) are installed in Spain and this is expected to increase to 8GW(e) in 1980 and to 28GW(e) in 1990. Spanish industry and technology are also rapidly increasing their participation in building nuclear stations, in manufacturing the necessary components and in the activities related to the nuclear fuel cycle. All of this requires properly trained personnel, which is estimated to become approximately 1200 high-level technicians, 1100 medium-level technicians and 1500 technical assistants by 1980. This personnel is trained: (a) in engineering schools; (b) in the Nuclear Studies Institute; (c) in the electric companies with nuclear programmes. The majority of the high-level engineering schools in the country include physics and basic nuclear technology courses in their programmes. Some of them have an experimental low-power nuclear reactor. The Nuclear Studies Institute is an official organism dependent on the Nuclear Energy Commission and responsible, among other subjects, for training personnel for the peaceful use and development of nuclear energy in the country. The electric companies also participate in training personnel for future nuclear stations and they plan to have advanced simulators of PWR and BWR type stations for operator training. The report deals with the personnel requirement forecasts and describes the training programmes. (author)

Nucleoelectric energy training programs in Spain

International Nuclear Information System (INIS)

Tanarro, A.; Izquierdo, L.

1977-01-01

The introduction of nucleoelectric energy in Spain is developing very rapidly. The nuclear power installed in Spain at the present time is 1,1 GWe and it is expected to increase to 8 GWe in 1980 and to 28 GWe in 1990. Spanish industry and technology are also rapidly increasing their participation in building nuclear stations, in manufacturing the necessary components and in the activities related to the nuclear fuel cycle. All of this requires properly trained personnel which is estimated at approximately 1200 high-level technicians, 1100 medium-level technicians and 1500 technical assistants by 1980. This personnel is trained: a) In engineering schools; b) In the Nuclear Studies Institute; and c) In the electric companies with nuclear programs. The majority of the high-level engineering schools in the Country include physics and basic nuclear technology courses in their programs. Some of them have an experimental low-power nuclear reactor. The Nuclear Studies Institute is an official organism depending on the Nuclear Energy Commission responsible, among other subjects, of training personnel for the peaceful use and development of nuclear energy in the Country. The electric companies also participate in training personnel for future nuclear stations and they plan to have advanced simulators of the PWR and BWR type stations for operator training. The report deals with the personnel requirement forecasts and describes the personnel training programs [es

Synthetic fuel production using Texas lignite and a very high temperature reactor for process heat

International Nuclear Information System (INIS)

Ross, M.A.; Klein, D.E.

1982-01-01

Two approaches for synthetic fuel production from coal are studied using Texas lignite as the feedstock. First, the gasification and liquefaction of coal are accomplished using Lurgi gasifiers and Fischer-Tropsch synthesis. A 50 000 barrel/day facility, consuming 13.7 million tonne/yr (15.1 million ton/yr) of lignite, is considered. Second, a nuclear-assisted coal conversion approach is studied using a very high temperature gas-cooled reactor with a modified Lurgi gasifier and Fischer-Tropsch synthesis. The nuclear-assisted approach resulted in a 35% reduction in coal consumption. In addition, process steam consumption was reduced by one-half and the oxygen plants were eliminated in the nuclear assisted process. Both approaches resulted in a synthetic oil price higher than the March 1980 imported price of $29.65 per barrel: $36.15 for the lignite-only process and $35.16 for the nuclear-assisted process. No tax advantage was assumed for either process and the utility financing method was used for both economic calculations

New measuring and protection system at VR-1 training reactor

International Nuclear Information System (INIS)

Kropik, M.; Jurickova, M.

2006-01-01

The contribution describes the new measuring and protection system of the VR-1 training reactor. The measuring and protection system upgrade is an integral part of the reactor I and C upgrade. The new measuring and protection system of the VR-1 reactor consists of the operational power measuring and the independent power protection systems. Both systems measure the reactor power and power rate, initiate safety action if safety limits are exceeded and send data (power, power rate, status, etc.) to the reactor control system. The operational power measuring system is a full power range system that receives signal from a fission chamber. The signal is evaluated according to the reactor power either in the pulse or current mode. The current mode utilizes the DC current and Campbell techniques. The new independent power protection system operates in the two highest reactor power decades. It receives signals from a boron chamber and evaluates it in the pulse mode. Both systems are computer based. The operational power measuring and independent power protection systems are diverse - different types and location of chambers, completely different hardware, software algorithms for the power and power rate calculations, software development tools and teems for the software manufacturing. (author)

Purification and solidification of reactor wastes at a Canadian nuclear generating station

International Nuclear Information System (INIS)

Buckley, L.P.; Burt, D.A.

1981-01-01

The study aimed at development and demonstration of volume reduction and solidification of CANDU reactor wastes has been underway at Chalk River Nuclear Laboratories in the Province of Ontario, Canada. The study comprises membrane separation processes, evaporator appraisal and immobilization of concentrated wastes in bitumen. This paper discusses the development work with a wiped-film evaporator and the successful completion of demonstration tests at Douglas Point Nuclear Generating Station. Heavy water from the moderator system was purified and wastes arising from pump bowl decontamination were immobilized in bitumen with the wiped-film evaporator that was used in the development tests at Chalk River

Relationship Between Pretraining Subjective Wellness Measures, Player Load, and Rating-of-Perceived-Exertion Training Load in American College Football.

Science.gov (United States)

Govus, Andrew D; Coutts, Aaron; Duffield, Rob; Murray, Andrew; Fullagar, Hugh

2018-01-01

The relationship between pretraining subjective wellness and external and internal training load in American college football is unclear. To examine the relationship of pretraining subjective wellness (sleep quality, muscle soreness, energy, wellness Z score) with player load and session rating of perceived exertion (s-RPE-TL) in American college football players. Subjective wellness (measured using 5-point, Likert-scale questionnaires), external load (derived from GPS and accelerometry), and s-RPE-TL were collected during 3 typical training sessions per week for the second half of an American college football season (8 wk). The relationship of pretraining subjective wellness with player load and s-RPE training load was analyzed using linear mixed models with a random intercept for athlete and a random slope for training session. Standardized mean differences (SMDs) denote the effect magnitude. A 1-unit increase in wellness Z score and energy was associated with trivial 2.3% (90% confidence interval [CI] 0.5, 4.2; SMD 0.12) and 2.6% (90% CI 0.1, 5.2; SMD 0.13) increases in player load, respectively. A 1-unit increase in muscle soreness (players felt less sore) corresponded to a trivial 4.4% (90% CI -8.4, -0.3; SMD -0.05) decrease in s-RPE training load. Measuring pretraining subjective wellness may provide information about players' capacity to perform in a training session and could be a key determinant of their response to the imposed training demands American college football. Hence, monitoring subjective wellness may aid in the individualization of training prescription in American college football players.

A research reactor simulator for operators training and teaching

International Nuclear Information System (INIS)

De Carvalho, R. P.; Maiorino, J. R.

2006-01-01

This work describes a training simulator of Research Reactors (RR). The simulator is an interactive tool for teaching and operator training of the bases of the RR operation, reactor physics and thermal hydraulics. The Brazilian IEA-R1 RR was taken as the reference (default configuration). The implementation of the simulator consists of the modeling of the process and system (neutronics, thermal hydraulics), its numerical solution, and the implementation of the man-machine interface through visual interactive screens. The point kinetics model was used for the nuclear process and the heat and mass conservation models were used for the thermal hydraulic feed back in the average core channel. The heat exchanger and cooling tower were also modeled. The main systems were: the reactivity control system, including the automatic control, and the primary and secondary coolant systems. The Visual C++ was used to codes and graphics lay-outs. The simulator is to be used in a PC with Windows XP system. The simulator allows simulation in real time of start up, power maneuver, and shut down. (authors)

Utilization of nuclear research reactors

International Nuclear Information System (INIS)

1980-01-01

prior to the beginning of the course was of particular value. Interesting scientific visits and demonstrations at the Isotope Institute and at the Central Research Institute for Physics (IFKI), both of the Hungarian Academy of Sciences, were also arranged. During the Study Tour at the Central Institute for Nuclear Research in Rossendorf near Dresden, German Democratic Republic, the participants had the opportunity to observe the organization of a 10 MW nuclear reactor where radioisotopes and radiopharmaceuticals are produced on a commercial scale. Lectures were delivered by local scientists on some of their programmes in applied research in solid state physics and material sciences. At the Technical University of Dresden, the group visited the homogeneous solid-moderated zero-power training reactor (AKR), primarily dedicated to nuclear education and training. Studies on different theoretical and experimental aspects of radiation protection (solid state nuclear track and thermoluminescent detectors) are also being carried out. The last day of the Study Tour was devoted to a visit to the College for Advanced Technology at Zittau, where a training reactor with a power of a few watts has been recently installed. (author)

Reactor costs and maintenance, with reference to the Culham Mark II conceptual tokamak reactor design

International Nuclear Information System (INIS)

Hancox, R.; Mitchell, J.T.D.

1977-01-01

Published designs of tokamak reactors have proposed conceptual solutions for most of the technological problems encountered. Two areas which remain uncertain, however, are the capital cost of the reactor and the practicability of reactor maintenance. A cost estimate for the Culham Conceptual Tokamak Reactor (Mk I) is presented. The capital cost of a power station incorporating this reactor would be significantly higher than that of an equivalent fast breeder fission power station, mainly because of the low power density of the fusion reactor which affects both the reactor and building costs. To reduce the fusion station capital costs a new conceptual design is proposed (Mk II) which incorporates a shaped plasma cross-section to give a higher plasma pressure ratio, βsub(t) approximately 0.1. Since the higher power density implies more severe radiation damage of the blanket structure, the question of reactor maintenance assumes greater importance. With the proposed scheme for regular replacement of the blanket, a fusion power station availability around 0.9 should be achievable. (author)

Reactor costs and maintenance, with reference to the Culham Mark II conceptual Tokamak reactor design

International Nuclear Information System (INIS)

Hancox, R.; Mitchell, J.T.D.

1976-01-01

Published designs of tokamak reactors have proposed conceptual solutions for most of the technological problems encountered. Two areas which remain uncertain, however, are capital cost of the reactor and the practicability of reactor maintenance. A cost estimate for the Culham Conceptual Tokamak Reactor (Mk I) is presented. The capital cost of a power station incorporating this reactor would be significantly higher than that of an equivalent fast breeder fission power station, due mainly to the low power density of the fusion reactor which affects both the reactor and building costs. In order to reduce the fusion station capital costs a new conceptual design is proposed (Mk II) which incorporates a shaped plasma cross-section to give a higher plasma pressure ratio, βsub(t) approximately 0.1. Since the higher power density implies more severe radiation damage of the blanket structure, the question of reactor maintenance assumes greater importance. With the proposed scheme for regular replacement of the blanket, a fusion power station availability around 0.9 should be achievable. (orig.) [de

Station Capacity

DEFF Research Database (Denmark)

Landex, Alex

2011-01-01

the probability of conflicts and the minimum headway times into account. The last method analyzes how optimal platform tracks are used by examining the arrival and departure pattern of the trains. The developed methods can either be used separately to analyze specific characteristics of the capacity of a station......Stations are often limiting the capacity of railway networks. This is due to extra need of tracks when trains stand still, trains turning around, and conflicting train routes. Although stations are often the capacity bottlenecks, most capacity analysis methods focus on open line capacity. Therefore...... for platform tracks and the probability that arriving trains will not get a platform track immediately at arrival. The third method is a scalable method that analyzes the conflicts in the switch zone(s). In its simplest stage, the method just analyzes the track layout while the more advanced stages also take...

Operator training facilities for CEGB advanced gas cooled reactors

International Nuclear Information System (INIS)

Green, J.F.; Birnie, S.

1980-01-01

The facilities provided at the Nuclear Power Training Centre of the CEGB for the training of operators fo the AGR are described. The simulator control desks are replicas of three AGR designs with, in addition, simulation of the Data Processing System for each station. Three modes of operation are envisaged: a.) Demonstration where the simulator is used by the tutor to illustrate lecture on plant behaviour. b.) Interaction where the student carries out normal procedures and experiences plant failure situations. c.) Investigation where engineering staff use the simulator for validation of modified operational procedures, ergonomic studies etc. (orig./HP)

Modern design and safety analysis of the University of Florida Training Reactor

International Nuclear Information System (INIS)

Jordan, K.A.; Springfels, D.; Schubring, D.

2015-01-01

Highlights: • A new safety analysis of the University of Florida Training Reactor is presented. • This analysis uses modern codes and replaces the NRC approved analysis from 1982. • Reduction in engineering margin confirms that the UFTR is a negligible risk reactor. • Safety systems are not required to ensure that safety limits are not breached. • Negligible risk reactors are ideal for testing digital I&C equipment. - Abstract: A comprehensive series of neutronics and thermal hydraulics analyses were conducted to demonstrate the University of Florida Training Reactor (UFTR), an ARGONAUT type research reactor, as a negligible risk reactor that does not require safety-related systems or components to prevent breach of a safety limit. These analyses show that there is no credible UFTR accident that would result in major fuel damage or risk to public health and safety. The analysis was based on two limiting scenarios, whose extremity bound all other accidents of consequence: (1) the large step insertion of positive reactivity and (2) the release of fission products due to mechanical damage to a spent fuel plate. The maximum step insertion of positive reactivity was modeled using PARET/ANL software and shows a maximum peak fuel temperature of 283.2 °C, which is significantly below the failure limit of 530 °C. The exposure to the staff and general public was calculated for the worst-case fission product release scenario using the ORIGEN-S and COMPLY codes and was shown to be 6.5% of the annual limit. Impacts on reactor operations and an Instrumentation & Control System (I&C) upgrade are discussed

Modern design and safety analysis of the University of Florida Training Reactor

Energy Technology Data Exchange (ETDEWEB)

Jordan, K.A., E-mail: kjordan@ufl.edu [University of Florida, 106 UFTR Bldg., PO Box 116400, Gainesville, FL 32611-6400 (United States); Springfels, D., E-mail: dspringfels@ufl.edu [University of Florida, 106 UFTR Bldg., PO Box 116400, Gainesville, FL 32611-6400 (United States); Schubring, D., E-mail: dlschubring@ufl.edu [University of Florida, 202 Nuclear Science Building, PO Box 118300, Gainesville, FL 32611-8300 (United States)

2015-05-15

Highlights: • A new safety analysis of the University of Florida Training Reactor is presented. • This analysis uses modern codes and replaces the NRC approved analysis from 1982. • Reduction in engineering margin confirms that the UFTR is a negligible risk reactor. • Safety systems are not required to ensure that safety limits are not breached. • Negligible risk reactors are ideal for testing digital I&C equipment. - Abstract: A comprehensive series of neutronics and thermal hydraulics analyses were conducted to demonstrate the University of Florida Training Reactor (UFTR), an ARGONAUT type research reactor, as a negligible risk reactor that does not require safety-related systems or components to prevent breach of a safety limit. These analyses show that there is no credible UFTR accident that would result in major fuel damage or risk to public health and safety. The analysis was based on two limiting scenarios, whose extremity bound all other accidents of consequence: (1) the large step insertion of positive reactivity and (2) the release of fission products due to mechanical damage to a spent fuel plate. The maximum step insertion of positive reactivity was modeled using PARET/ANL software and shows a maximum peak fuel temperature of 283.2 °C, which is significantly below the failure limit of 530 °C. The exposure to the staff and general public was calculated for the worst-case fission product release scenario using the ORIGEN-S and COMPLY codes and was shown to be 6.5% of the annual limit. Impacts on reactor operations and an Instrumentation & Control System (I&C) upgrade are discussed.

Team skills training

International Nuclear Information System (INIS)

Coe, R.P.; Carl, D.R.

1991-01-01

Numerous reports and articles have been written recently on the importance of team skills training for nuclear reactor operators, but little has appeared on the practical application of this theoretical guidance. This paper describes the activities of the Training and Education Department at GPU Nuclear (GPUN). In 1987, GPUN undertook a significant initiative in its licensed operator training programs to design and develop initial and requalification team skills training. Prior to that time, human interaction skills training (communication, stress management, supervisory skills, etc.) focused more on the individual rather than a group. Today, GPU Nuclear conducts team training at both its Three Mile Island (YMI), PA and Oyster Creek (OC), NJ generating stations. Videotaped feedback is sued extensively to critique and reinforce targeted behaviors. In fact, the TMI simulator trainer has a built-in, four camera system specifically designed for team training. Evaluations conducted on this training indicated these newly acquired skills are being carried over to the work environment. Team training is now an important and on-going part of GPUN operator training

Tests of a new CCD-camera based neutron radiography detector system at the reactor stations in Munich and Vienna

Energy Technology Data Exchange (ETDEWEB)

Lehmann, E; Pleinert, H [Paul Scherrer Inst. (PSI), Villigen (Switzerland); Schillinger, B [Technische Univ. Muenchen (Germany); Koerner, S [Atominstitut der Oesterreichischen Universitaeten, Vienna (Austria)

1997-09-01

The performance of the new neutron radiography detector designed at PSI with a cooled high sensitive CCD-camera was investigated under real neutronic conditions at three beam ports of two reactor stations. Different converter screens were applied for which the sensitivity and the modulation transfer function (MTF) could be obtained. The results are very encouraging concerning the utilization of this detector system as standard tool at the radiography stations at the spallation source SINQ. (author) 3 figs., 5 refs.

General Electric's training program for BWR chemists

International Nuclear Information System (INIS)

Osborn, R.N.; Lim, W.

1981-01-01

This paper describes the development and implementation of the General Electric boiling water reactor chemistry training program from 1959 to the present. The original intention of this program was to provide practical hands on type training in radiochemistry to BWR chemistry supervisors with fossil station experience. This emphasis on radiochemistry has not changed through the years, but the training has expanded to include the high purity water chemistry of the BWR and has been modified to include new commission requirements, engineering developments and advanced instrumentation. Student and instructor qualifications are discussed and a description of the spin off courses for chemistry technicians and refresher training is presented

Accident Analysis of Chinese CPR1000 in Response to Station Blackout

Energy Technology Data Exchange (ETDEWEB)

Kim, Juyoul [FNC Technology Co., Yongin (Korea, Republic of); Cilliers, Anthonie [North-West University, Potchefstroom (South Africa)

2016-10-15

Stress tests required evaluation of the consequences of loss of safety functions from any initiating event (e.g., earthquake or flooding) causing loss of electrical power, including station blackout (SBO). The SBO scenario involves a loss of offsite power, failure of the redundant emergency diesel generators, failure of alternate current (AC) power restoration and the eventual degradation of the reactor coolant pump (RCP) seals resulting in a long term loss of coolant. Using PCTRAN/CPR1000, this study analyses the station blackout on a Chinese CPR1000 which is the most representative type reactor in terms of number of reactors, operating period, power capacity and geological distance from Korean Peninsula. Both the physical effects of the accidents as well as the releases of radioisotopes are calculated and discussed. Station blackout simulation was conducted in this study. The resulting effects seen are consistent with other stress test station blackout tests used utilizing licensed simulation codes. An exact comparison is however not possible as the plants on which the simulations was done vary greatly and the limitations of availability to Chinese FSAR. PCTRAN/CPR1000 is an extremely useful simulation package that provides engineers and scientists very accurate feedback to how a nuclear power plant would react as a whole under various plant conditions. It is able to do this extremely fast as well. As a training tool PCTRAN/CPR1000 provides hands-on experience with many of the primary plant operations and develops an intuitive understanding of the plant.

The operating organization and the recruitment, training and qualification of personnel for research reactors. Safety guide

International Nuclear Information System (INIS)

2008-01-01

This Safety Guide provides recommendations on meeting the requirements on the operating organization and on personnel for research reactors. It covers the typical operating organization for research reactor facilities; the recruitment process and qualification in terms of education, training and experience; programmes for initial and continuing training; the authorization process for those individuals having an immediate bearing on safety; and the processes for their requalification and reauthorization

Training and qualification of licensed reactor operators at General Public Utilities Nuclear Corporation

International Nuclear Information System (INIS)

Long, R.L.; Coe, R.P.

1992-01-01

Following the Three Mile Island-2 (TMI-2) accident in 1979, the utility responsible for managing the facility has looked closely at the training and qualification of its reactor operators. Performance-based operator training programmes are now in place, as required by the United States National Academy for Nuclear Training. Operators also participate directly in the development of a professional code of behaviour. (UK)

Education and training activities at North Carolina State University's PULSTAR reactor

International Nuclear Information System (INIS)

Mayo, C.W.

1992-01-01

Research reactor utilization has been an integral part of the North Carolina State University's (NCSU's) nuclear engineering program since its inception. The undergraduate curriculum has a strong teaching laboratory component. Graduate classes use the reactor for selected demonstrations, experiments, and projects. The reactor is also used for commercial power reactor operator training programs, neutron radiography, neutron activation analysis (NAA), and sample and tracer activation for industrial short courses and services as part of the university's land grant mission. The PULSTAR reactor is a 1-MW pool-type reactor that uses 4% enriched UO 2 pellet fuel in Zircaloy II cladding. Standard irradiation facilities include wet exposure ports, a graphite thermal column, and a pneumatic transfer system. In the near term, general facility upgrades include the installation of signal isolation and computer data acquisition and display functions to improve the teaching and research interface with the reactor. In the longer term, the authors foresee studies of new core designs and the development of beam experiment design tools. These would be used to study modifications that may be desired at the end of the current core life and to undertake the development of new research instruments

Texas Instruments Technical Seminar: Power Management and Wireless

CERN Multimedia

2006-01-01

Monday 6 November TECHNICAL TRAINING SEMINAR 14:00 to 17:30 - Training Centre Auditorium (bldg. 593) Texas Instruments Technical Seminar: Power Management and Wireless Michael Scholtholt, Field Application Engineer / TEXAS INSTRUMENTS (US, D, CH) The range of power management products available today offers the possibility to find the best solution for each application. To select the right product it is therefore necessary to understand system requirements, how power supply products work, and where they differentiate. This Technical Training Seminar will also present an overview of how to choose the right RF platform based on markets and applications: nowadays almost everbody has at least one wireless product in use, and this tendency seems to increase significantly. Power Management Voltage mode vs. current mode control Differentiating DC/DC converters by analyzing control and compensation schemes: line / load regulation, transient response, BOM, board space, ease-of-use Introduction to evaluati...

Texas Instruments Technical Seminar: Power Management and Wireless

CERN Multimedia

2006-01-01

Monday 6 November TECHNICAL TRAINING SEMINAR 14:00 to 17:30 - Training Centre Auditorium (bldg. 593) Texas Instruments Technical Seminar: Power Management and Wireless Michael Scholtholt, Field Application Engineer / TEXAS INSTRUMENTS (US, D, CH) The range of power management products available today offers the possibility to find the best solution for each application. To select the right product it is therefore necessary to understand system requirements, how power supply products work, and where they differentiate. This Technical Training Seminar will also present an overview of how to choose the right RF platform based on markets and applications: nowadays almost everbody has at least one wireless product in use, and this tendency seems to increase significantly. Power Management Voltage mode vs. current mode control Differentiating DC/DC converters by analyzing control and compensation schemes: line / load regulation, transient response, BOM, board space, ease-of-use Introduction to evalu...

Principles of education and training of plant engineers for nuclear power stations

International Nuclear Information System (INIS)

Ackermann, G.; Meyer, K.; Brune, W.

1978-01-01

Experience in education and advanced training of nuclear engineers in the GDR is reviewed. The basic education of engineers is carried out at universities and colleges. Graduate engineers who have been working in non-nuclear industries for a longer time receive their basic education in nuclear engineering through postgraduate studies. Graduate engineers with a basic knowledge of nuclear engineering are trained at the Nuclear Power Plant School of the Rheinsberg nuclear power plant and at the nuclear power plants of the GDR under operational conditions relating to their future job. In addition to basic theoretical knowledge, training at a nuclear power plant simulator plays an important role. This permits training of the staff under normal operating conditions including transient processes and under unusual conditions. Further particular modes of advanced professional training such as courses in radiation protection and further postgraduate studies are described. This system of education has proved successful. It will be developed further to meet the growing demands. (author)

Formal on-the-job training programs at power generating stations

Energy Technology Data Exchange (ETDEWEB)

Hoch, R.R. [HGS, Inc., Ellicott City, MD (United States)

1996-11-01

On-the-Job Training (OJT) should be utilized for all posts in the stations. OJT for entry level positions should include training in many mundane areas that are often overlooked such as record keeping (log sheets and log books), proper communications and how to conduct himself or herself on the watch, during either emergency or routine situations. A separate OJT Program should be provided to prepare personnel to qualify for promotion to the next level. (Depending on any common agreements or bargaining unit contracts, OJT Programs can also be used to pre-qualify candidates for promotion to the next level.) By allowing the trainee to retain all OJT Program materials, it will also be available to him or her for continued reference or remedial training. (When an OJT Program is first instituted, it may be validated by issuing it to incumbent personnel and, subsequent, incorporating their comments or corrections.) This paper describes a formal OJT program.

The role of a small teaching reactor in education and training

International Nuclear Information System (INIS)

Bobek, L.M.; Mayer, J.A. Jr.

1992-01-01

It cannot be simply concluded that because an undergraduate nuclear engineering program has access to a higher power research reactor that the number of BS graduates will be proportionately larger than a program whose reactor operates at a much lower power level. What can be concluded is that although smaller in size and capability, low-power research reactors and the nuclear engineering programs they serve provide an important role in producing much-needed nuclear engineers and scientists at the undergraduate level. Designed and built by General Electric primarily as a teaching tool for nuclear engineering education, the nuclear reactor at Worcester Polytechnic Institute (WPI) first began operation in 1959. The reactor power level was upgraded from 1 to 10 kW in 1969, and its 20-yr operating license was renewed in 1983. With the support of DOE funds, the reactor was converted to low-enriched fuel in 1988. Under partial funding from the DOE University Reactor Instrumentation Program, the reactor control console will soon be replaced. Since a small research reactor is an ideal tool for providing basic and intermediate nuclear training, the incorporation of nuclear subjects into traditional disciplines will consequently enhance reactor facility usage. With its continued modernization, the WPI nuclear reactor facility will play a key role in meeting nuclear manpower needs while providing excellent and rewarding career opportunities for students in all disciplines for many years to come

Training astronauts using three-dimensional visualisations of the International Space Station.

Science.gov (United States)

Rycroft, M; Houston, A; Barker, A; Dahlstron, E; Lewis, N; Maris, N; Nelles, D; Bagaoutdinov, R; Bodrikov, G; Borodin, Y; Cheburkov, M; Ivanov, D; Karpunin, P; Katargin, R; Kiselyev, A; Kotlayarevsky, Y; Schetinnikov, A; Tylerov, F

1999-03-01

Recent advances in personal computer technology have led to the development of relatively low-cost software to generate high-resolution three-dimensional images. The capability both to rotate and zoom in on these images superposed on appropriate background images enables high-quality movies to be created. These developments have been used to produce realistic simulations of the International Space Station on CD-ROM. This product is described and its potentialities demonstrated. With successive launches, the ISS is gradually built up, and visualised over a rotating Earth against the star background. It is anticipated that this product's capability will be useful when training astronauts to carry out EVAs around the ISS. Simulations inside the ISS are also very realistic. These should prove invaluable when familiarising the ISS crew with their future workplace and home. Operating procedures can be taught and perfected. "What if" scenario models can be explored and this facility should be useful when training the crew to deal with emergency situations which might arise. This CD-ROM product will also be used to make the general public more aware of, and hence enthusiastic about, the International Space Station programme.

Historical Channel Adjustment and Estimates of Selected Hydraulic Values in the Lower Sabine River and Lower Brazos River Basins, Texas and Louisiana

Science.gov (United States)

Heitmuller, Franklin T.; Greene, Lauren E.

2009-01-01

The U.S. Geological Survey, in cooperation with the Texas Water Development Board, evaluated historical channel adjustment and estimated selected hydraulic values at U.S. Geological Survey streamflow-gaging stations in the lower Sabine River Basin in Texas and Louisiana and lower Brazos River Basin in Texas to support geomorphic assessments of the Texas Instream Flow Program. Channel attributes including cross-section geometry, slope, and planform change were evaluated to learn how each river's morphology changed over the years in response to natural and anthropogenic disturbances. Historical and contemporary cross-sectional channel geometries at several gaging stations on each river were compared, planform changes were assessed, and hydraulic values were estimated including mean flow velocity, bed shear stress, Froude numbers, and hydraulic depth. The primary sources of historical channel morphology information were U.S. Geological Survey hard-copy discharge-measurement field notes. Additional analyses were done using computations of selected flow hydraulics, comparisons of historical and contemporary aerial photographs, comparisons of historical and contemporary ground photographs, evaluations of how frequently stage-discharge rating curves were updated, reviews of stage-discharge relations for field measurements, and considerations of bridge and reservoir construction activities. Based on historical cross sections at three gaging stations downstream from Toledo Bend Reservoir, the lower Sabine River is relatively stable, but is subject to substantial temporary scour-and-fill processes during floods. Exceptions to this characterization of relative stability include an episode of channel aggradation at the Sabine River near Bon Wier, Texas, during the 1930s, and about 2 to 3 feet of channel incision at the Sabine River near Burkeville, Texas, since the late 1950s. The Brazos River, at gaging stations downstream from Waco, Texas, has adjusted to a combination of

Ten years of KRB Gundremmingen demonstration power station

International Nuclear Information System (INIS)

Facius, H. von; Ettemeyer, R.

1976-01-01

In August 1976 the first large nuclear power station in the Federal Republic, the KRB Gundremmingen plant with a net power of 237 MWe, has been in operation ten years. The construction of KRB as a demonstration plant was a major step forward on the way to the economic utilization of nuclear power for German utilities. Design and operation of the plant have decisively influenced the further development of the technology of light water reactors in the Federal Republic. Unlike the Kahl Experimental Nuclear Power Station (VAK), which was a test facility designed to generate experience and to train personnel, the decision to build KRB from the outset was conditional upon the fulfillment of economic criteria. Here are some of the aspects in which KRB has greatly influenced the development of nuclear power station technology: first application of internal steam-water separation instead of a steam drum with a water content of the steam of less than 1%; construction of a reactor buildung with all the necessary safety factors; solution of the corrosion and erosion problems linked with the use of a saturated steam turbine; special measures taken to prevent the turbine from speeding up due to post-evaporation effects after shutdown. Detailed comments are devoted to the subjects of availability, causes of failure and repair work. (orig.) [de

Education for Agricultural Improvement: Teacher Certification at the Agricultural and Mechanical College of Texas

Science.gov (United States)

Burlbaw, Lynn M.; Williams, Lauren; Kelly, Larry J.

2017-01-01

Texas A&M University has long been known for its engineering and agricultural programs. Only in the last 50 years has its reputation included the preparation of teachers for general education in the public schools of Texas. However, agricultural education has been an integral part of the institution's mandate since early in the 20th century.…

Study on the present and future training of managers and operators for reactor facilities

International Nuclear Information System (INIS)

Hagemann, G.; Preuss, W.; Tietze, A.; Wuest, S.

1973-09-01

The study gives a survey on the training methods for the operating personnel of reactors in operation or under construction in the FRG and compares them with the training and testing methods of other countries, in particular the USA. (RW/AK) [de

Blogs, Webinars and Significant Learning: A Case Report on a Teacher Training Program for College Teachers

Science.gov (United States)

Polanco-Bueno, Rodrigo

2013-01-01

This case study reports on a teacher training experience for college professors in which participants were trained, taking advantage of technological tools, in two main teaching competences. First, professors were trained to use technology to enrich students' learning outcomes. Second, they applied strategies of significant learning in the design…

Defense Base Realignment and Closure Budget Data for Naval Air Technical Training Center, Naval Air Station Pensacola, Florida

National Research Council Canada - National Science Library

Granetto, Paul

1994-01-01

.... This report provides the results of the audit of 19 projects, valued at $288.9 million, for the realignment of the Naval Air Technical Training Center from Naval Air Station Memphis, Tennessee, to Naval Air Station Pensacola, Florida...

Participation of Ostrava Mining College in training of personnel for nuclear technology

International Nuclear Information System (INIS)

Kuchar, L.

1983-01-01

The mining and geology faculty of the Mining College educates specialists for surveying, extraction and treatment of uranium raw materials. In 1980 the faculty introduced an interdisciplinary study course for the technology of drilling, geological surveying and mine surveying. A contract has been signed between the College and the Czechoslovak Uranium Industry on specialized and scientific cooperation, expertise, postgraduate courses, etc. The metallurgy faculty of the College introduced the nuclear metallurgy specialization in 1964. Students attending the course will acquire knowledge not only on the metallurgy of nuclear fuels, cladding, shielding and structural materials, their production and processing but also on the science of metals, heat treatment, metal testing, etc. A study course is now being prepared relating to materials problems of nuclear power which is oriented to modern methods of material assessment for nuclear power facilities, light water reactors and their components. In 1976 the Mining College also introduced the nuclear power specialization at its mechanical engineering and electrical engineering faculties. In the years 1976-1982 more than fifty students graduated from the faculty whose theses were oriented to the problems of welding, surfacing, machining and upgrading of WWER-440 and WWER-1000 components. In the years 1979-82 the College ran a postgraduate study course on ''Machines and equipment of nuclear power plants''. (E.S.)

Evaluation of an Avatar-Based Training Program to Promote Suicide Prevention Awareness in a College Setting.

Science.gov (United States)

Rein, Benjamin A; McNeil, Daniel W; Hayes, Allison R; Hawkins, T Anne; Ng, H Mei; Yura, Catherine A

2018-02-20

Training programs exist that prepare college students, faculty, and staff to identify and support students potentially at risk for suicide. Kognito is an online program that trains users through simulated interactions with virtual humans. This study evaluated Kognito's effectiveness in preparing users to intervene with at-risk students. Training was completed by 2,727 university students, faculty, and staff from April, 2014 through September, 2015. Voluntary and mandatory participants at a land-grant university completed Kognito modules designed for higher education, along with pre- and post-assessments. All modules produced significant gains in reported Preparedness, Likelihood, and Self-Efficacy in intervening with troubled students. Despite initial disparities in reported abilities, after training participants reported being similarly capable of assisting at-risk students, including LGBTQ and veteran students. Kognito training appears to be effective, on a large scale, in educating users to act in a facilitative role for at-risk college students.

A midsize reactor facility - A regional resource for research and education

International Nuclear Information System (INIS)

Vernetson, W.G.

1991-01-01

The mission of the University of Florida Training Reactor (UFTR) is to serve the regional needs of Florida and the Southeast for access to quality reactor usage. Well-advertised capabilities of the facility support diversified usages that include education, training, research, service, and public information programs to address the needs of a broad spectrum of users ranging from high school students and teachers, to university researchers, and even the occasional service user. Despite the midsize power of the facility, the UFTR's status as the only nonpower reactor within 350 miles in one of our largest states means that it is uniquely situated to contribute in these various areas in ways usually reserved for larger facilities. Nine state universities and a well-developed community college system in addition to private schools and a growing complement of progressive high schools assure a broad-based user community. The key to accomplishing mission objectives is to continue diversification and improvement of both the reactor and associated experimental capabilities to meet the needs of this user community

Majors Matter: Differences in Wages over Time in Texas

Science.gov (United States)

Schneider, Mark

2016-01-01

The Texas Higher Education Coordinating Board (THECB) has developed an extensive data system that captures the wages earned by graduates of public colleges and universities, by major. The board then makes those data available, providing a highly detailed look at the wages of completers at various points between 1 and 10 years after attaining a…

On the occurrence of Stenopus tenui- rostris De Man, 1888 in Natal ...

African Journals Online (AJOL)

Department of Biology, Texas A & M University, College. Station, Texas 77843, USA. S. Koslowski c/o Durban Corporation, Durban. Received 8 JQlluary 1990; accepted 5 March 1990. The stenopodidean shrimp Slenopus lenuiroslris De Man,. 1888 is reported from Natal waters for the first time. This record represents a ...

Shippingport Station decommissioning project overview

International Nuclear Information System (INIS)

Schreiber, J.J.

1985-01-01

The U.S. Department of Energy is in the process of decommissioning the Shippingport Atomic Power Station located on the Ohio River, 30 miles northwest of Pittsburgh, Pennsylvania. The Shippingport Station is the first commercial size nuclear power plant to undergo decommissioning in the United Staes. The plant is located on approximately 7 acres of land owned by the Duquesne Light Company (DLC) and leased to the U.S. Government. DLC operates two nuclear power plants, Beaver Valley 1 and 2, located immediately adjacent to the site and the Bruce Mansfield coal-fired power plant is also within the immediate area. The Station was shutdown in October, 1982. Defueling operations began in 1983 and were completed by September, 1984. The Shippingport Station consists of a 275' x 60' fuel handling building containing the reactor containment chamber, the service building, the turbine building, the radioactive waste processing building, the administration building and other smaller support buildings. The Station has four coolant loops and most of the containment structures are located below grade. Structures owned by the U.S. Government including the fuel handling building, service building, contaminated equipment room, the boiler chambers, the radioactive waste processing building and the decontamination and laydown buildings will be dismantled and removed to 3 feet below grade. The area will then be filled with clean soil and graded. The turbine building, testing and training building and the administration building are owned by DLC and will remain

Combined use of the RPI [Rensselaer Polytechnic Institute] reactor for training and critical experiments

International Nuclear Information System (INIS)

Harris, D.R.; Rohr, R.R.; Rodriguez-Vera, F.

1990-01-01

The Rensselaer Polytechnic Institute (RPI) reactor critical facility (RCF) has provided educational and research opportunities for RPI and other students for >25 yr. The RCF was built by the American Locomotive Company (ALCO) in the 1950s as a critical facility in support of the army package power reactor program, and, when ALCO went out of business in 1964, the RCF was acquired by RPI. Since that time, RPI has operated the RCF primarily in a teaching mode in the nuclear engineering department, although reactor research, activation analyses, and reactivity assays have been carried out as well. Until recently, the RCF was fueled by plates containing highly enriched uranium as a cermet in stainless steel. This highly enriched uranium (HEU) fuel was replaced recently by 4.81 wt% enriched UO 2 high-density pellets clad in stainless steel rods. The use of these SPERT (F1) fuel rods in the RCF provided a cost-effective method for conversion of the core from HEU to low-enriched uranium and for enhancement of the RCF training and research program. The RCF is the only facility in the United States that provides reactor training on a core containing fuel that is similar to that used in power industry light water reactors (LWRs). Moreover, the RCF is the only facility in the United States currently available for supplying critical experimental data in support of the LWR power industry. Thus, the RCF is in a unique position to carry out important training and research services consistent with RPI's nuclear engineering objectives

Social Media in Tertiary Education-Vhembe Further Education Training College Case Study

Directory of Open Access Journals (Sweden)

Manzira Francis Mungofa

2015-08-01

Full Text Available Social media technologies are being widely used by students in institutions of higher education and these are transforming their way of learning, social conduct, communication and networking. The intend of this research was conducted to determine value of social media technologies to students in higher education but with a focus that was directed towards students in a vocational training college. A random sample of 105 students from Vhembe Further Education Training College (FET participated in the study and they were the following departments, Business/Finance, Engineering, Hospitality and Tourism. Analysis of results was executed through application of SPSS statistical package. Findings show that social media technology has infused a new culture of learning among students. In addition, social media applications which are being widely used by students for learning activities that include studying, access of education content, and social communication are: Facebook, WhatsApp, Twitter and YouTube.

Fast neutron activation analysis at Texas A and M University

International Nuclear Information System (INIS)

James, W.D.

1997-01-01

Fast neutron generators are used at Texas A and M University to provide a supply of high energy neutrons for nuclear analytical measurements. A series of neutron activation analysis procedures have been developed for determining various major, minor and trace constituents in a variety of materials. These procedures are primarily developed to compliment our reactor based NAA program, thereby expanding the list of determinable elements to include those difficult or impossible to measure using thermal neutrons. A few typical methods are discussed. The unique implementation of the methodologies at Texas A and M are explained. (author)

Nuclear Power Station Kalkar, 300 MWe Prototype Nuclear Power Plant with Fast Sodium Cooled Reactor (SNR-300), Plant description

International Nuclear Information System (INIS)

1984-06-01

The nuclear power station Kalkar (SNR-300) is a prototype with a sodium cooled fast reactor and a thermal power of 762 MW. The present plant description has been made available in parallel to the licensing procedure for the reactor plant and its core Mark-Ia as supplementary information for the public. The report gives a detailed description of the whole plant including the prevention measures against the impact of external and plant internal events. The radioactive materials within the reactor cooling system and the irradiation protection and surveillance measures are outlined. Finally, the operation of the plant is described with the start-up procedures, power operation, shutdown phases with decay heat removal and handling procedures

Model engineering for piping layout of boiling water reactor nuclear station

International Nuclear Information System (INIS)

Tsukada, Koji; Uchiyama, Masayuki; Wada, Takanao; Jibu, Noboru.

1977-01-01

A nuclear power station is made up of a wide variety of equipment, piping, ventilation ducts, conduits, and cable trays, etc. Even if equipment arrangement and piping layout are carefully planned on drawings, troubles such as interference often occur at field installation. Accordingly, it is thought very useful to make thorough examinations with plastic three-dimensional models in addition to drawings in reducing troubles at field, shortening the construction period, and improving economics. Examination with plastic models offers the following features: (1) It permits visual three-dimensional examination. (2) Group thinking and examination is possible. (3) Troubles due to failure to understand complicated drawings can be reduced drastically. Manufacturing a 1/20 scale model of the reactor building of the Tokai No. 2 Power Station of the Japan Atomic Power Co., Hitachi has performed model engineering-solution of interference troubles related to equipment and piping, securing of work space for in-service inspection (ISI), carry-in/installation of various equipment and piping, and determination of the piping route of which only the starting and terminating points were given under the complicated ambient conditions. Success with this procedure has confirmed that model engineering is an effective technique for future plant engineering. (auth.)

How to handle station black outs

Energy Technology Data Exchange (ETDEWEB)

Reisch, Frigyes [Swedish Nuclear Power Inspectorate, S-10252 Stockholm (Sweden)

1986-02-15

Station black out is defined as the loss of ail high voltage alternating current at a nuclear power site. An international study was made to survey the practices in the different countries. The best way to handle station black out is to avoid it therefore briefly the normal off site and emergency on site power supplies are discussed. The ways in use to enhance nuclear power plants using Boiling Water Reactors or Pressurized Water Reactors to cope with a station black out are discussed in some detail. (author)

How to handle station black outs

International Nuclear Information System (INIS)

Reisch, Frigyes

1986-01-01

Station black out is defined as the loss of ail high voltage alternating current at a nuclear power site. An international study was made to survey the practices in the different countries. The best way to handle station black out is to avoid it therefore briefly the normal off site and emergency on site power supplies are discussed. The ways in use to enhance nuclear power plants using Boiling Water Reactors or Pressurized Water Reactors to cope with a station black out are discussed in some detail. (author)

Team training using full-scale reactor coolant pump seal mock-ups

International Nuclear Information System (INIS)

McDonald, T.J.; Hamill, R.W.

1987-01-01

The use of full-scale reactor coolant pump (RCP) seal mock-ups has greatly enhanced Northeast Utilities' ability to effectively utilize the team training approach to technical training. With the advent of the Institute of Nuclear Power Operations accreditation come a new emphasis and standards for the integrated training of plant engineering personnel, maintenance mechanics, quality control personnel, and health physics personnel. The results of purchasing full-scale RCP mock-ups to pilot the concept of team training have far exceeded expectations and cost-limiting factors. The initial training program analysis identified RCP seal maintenance as a task that required training for maintenance department personnel. Due to radiation exposure considerations and the unavailability of actual plant equipment for training purposes, the decision was made to procure a mock-up of an RCP seal assembly and housing. This mock-up was designed to facilitate seal cartridge removal, disassembly, assembly, and installation, duplicating all internal components of the seal cartridge and housing area in exact detail

An Examination of College Counselors' Work with Student Sex Addiction: Training, Screening, and Referrals

Science.gov (United States)

Giordano, Amanda L.; Cashwell, Craig S.

2018-01-01

Given the prevalence of sex addiction (SA) among collegiate populations, the authors designed this study to examine college counselors' training in SA, use of formal assessments, and referrals to support groups. Results indicated that 84.4% of college counselors (N = 77) had at least one client present with SA-related issues in the past year.…

Austin Community College District's P-16 Initiative Graduates America

Science.gov (United States)

Hensley, Mary; Madsen, Gary

2010-01-01

Austin Community College (ACC) District's P-16 Initiative supports partnerships with 30 school districts--reaching traditionally underserved students and bridging the gap between high school and college--so more Texas students can reach their educational goals. The P-16 Initiative is a constellation of efforts designed to provide broad-based…

Assessing the vulnerability of sorghum converted lines to anthracnose and downy mildew infection

Science.gov (United States)

A total of 59 converted sorghum lines and six checks were evaluated for resistance to two foliar fungal diseases, anthracnose and downy mildew (SDM) in 2008 and 2009 growing seasons at the Texas A&M AgriLife Research Farm, College Station, Texas. In 2008, 23 lines exhibited resistance (35%), 29 sus...

Development and construction of nuclear power and nuclear heating stations in the USSR

International Nuclear Information System (INIS)

Schmidt, G.; Kirmse, B.

1983-01-01

The state-of-the-art of nuclear power technology in the USSR is reviewed by presenting characteristic data on design and construction. The review takes into consideration the following types of facilities: Nuclear power stations with 1000 MWe pressurized water reactors, with 1000 MWe pressure tube boiling water reactors, and with 600 MWe fast breeder reactors; nuclear heating power stations with 1000 MWe reactors and nuclear heating stations with 500 MWth boiling water reactors

State-space model predictive control method for core power control in pressurized water reactor nuclear power stations

Energy Technology Data Exchange (ETDEWEB)

Wang, Guo Xu; Wu, Jie; Zeng, Bifan; Wu, Wangqiang; Ma, Xiao Qian [School of Electric Power, South China University of Technology, Guangzhou (China); Xu, Zhibin [Electric Power Research Institute of Guangdong Power Grid Corporation, Guangzhou (China)

2017-02-15

A well-performed core power control to track load changes is crucial in pressurized water reactor (PWR) nuclear power stations. It is challenging to keep the core power stable at the desired value within acceptable error bands for the safety demands of the PWR due to the sensitivity of nuclear reactors. In this paper, a state-space model predictive control (MPC) method was applied to the control of the core power. The model for core power control was based on mathematical models of the reactor core, the MPC model, and quadratic programming (QP). The mathematical models of the reactor core were based on neutron dynamic models, thermal hydraulic models, and reactivity models. The MPC model was presented in state-space model form, and QP was introduced for optimization solution under system constraints. Simulations of the proposed state-space MPC control system in PWR were designed for control performance analysis, and the simulation results manifest the effectiveness and the good performance of the proposed control method for core power control.

Evaluating Question, Persuade, Refer (QPR) Suicide Prevention Training in a College Setting

Science.gov (United States)

Mitchell, Sharon L.; Kader, Mahrin; Darrow, Sherri A.; Haggerty, Melinda Z.; Keating, Niki L.

2013-01-01

This study assesses short-term and long-term learning outcomes of Question, Persuade, Refer (QPR) suicide prevention training in a college setting. Two hundred seventy-three participants completed pretest, posttest, and follow-up surveys regarding suicide prevention knowledge, attitudes, and skills. Results indicated: (a) increases in suicide…

Predicting Employment Outcomes for Consumers in Community College Short-Term Training Programs

Science.gov (United States)

Flannery, K. Brigid; Benz, Michael R.; Yovanoff, Paul; Kato, Mary McGrath; Lindstrom, Lauren

2011-01-01

Postsecondary education has been linked to improved access to employment opportunities for individuals with and without disabilities. The purpose of this study was to determine factors associated with increased employment outcomes for Vocational Rehabilitation consumers enrolled in community college short term occupational skill training programs.…

A simulator-based nuclear reactor emergency response training exercise.

Science.gov (United States)

Waller, Edward; Bereznai, George; Shaw, John; Chaput, Joseph; Lafortune, Jean-Francois

Training offsite emergency response personnel basic awareness of onsite control room operations during nuclear power plant emergency conditions was the primary objective of a week-long workshop conducted on a CANDU® virtual nuclear reactor simulator available at the University of Ontario Institute of Technology, Oshawa, Canada. The workshop was designed to examine both normal and abnormal reactor operating conditions, and to observe the conditions in the control room that may have impact on the subsequent offsite emergency response. The workshop was attended by participants from a number of countries encompassing diverse job functions related to nuclear emergency response. Objectives of the workshop were to provide opportunities for participants to act in the roles of control room personnel under different reactor operating scenarios, providing a unique experience for participants to interact with the simulator in real-time, and providing increased awareness of control room operations during accident conditions. The ability to "pause" the simulator during exercises allowed the instructors to evaluate and critique the performance of participants, and to provide context with respect to potential offsite emergency actions. Feedback from the participants highlighted (i) advantages of observing and participating "hands-on" with operational exercises, (ii) their general unfamiliarity with control room operational procedures and arrangements prior to the workshop, (iii) awareness of the vast quantity of detailed control room procedures for both normal and transient conditions, and (iv) appreciation of the increased workload for the operators in the control room during a transient from normal operations. Based upon participant feedback, it was determined that the objectives of the training had been met, and that future workshops should be conducted.

Royal College surgical objectives of urologic training: A survey of faculty members from Canadian training programs

Science.gov (United States)

Zakaria, Ahmed S.; Haddad, Richard; Dragomir, Alice; Kassouf, Wassim; Andonian, Sero; Aprikian, Armen G.

2014-01-01

Introduction: According to the Royal College objectives of training in urology, urologic surgical procedures are divided as category A, B and C. We wanted to determine the level of proficiency required and achieved by urology training faculty for Royal College accreditation. Methods: We conducted a survey that was sent electronically to all Canadian urology training faculty. Questions focused on demographics (i.e., years of practice, geographic location, subspecialty, access to robotic surgery), operating room contact with residents, opinion on the level of proficiency required from a list of 54 surgical procedures, and whether their most recent graduates attained category A proficiency in these procedures. Results: The response rate was 43.7% (95/217). Among respondents, 92.6% were full timers, 21.1% practiced urology for less than 5 years and 3.2% for more than 30 years. Responses from Quebec and Ontario formed 69.4% (34.7% each). Of the respondents, 37.9% were uro-oncologists and 75.7% reported having access to robotic surgery. Sixty percent of faculty members operate with R5 residents between 2 to 5 days per month. When respondents were asked which categories should be listed as category A, only 8 procedures received 100% agreement. Also, results varied significantly when analyzed by sub-specialty. For example, almost 50% or more of uro-oncologists believed that radical cystectomy, anterior pelvic exenteration and extended pelvic lymphadenectomy should not be category A. The following procedures had significant disagreement suggesting the need for re-classification: glanular hypospadias repair, boari flap, entero-vesical and vesicovaginal fistulae repair. Overall, more than 80% of faculty reported that their recent graduating residents had achieved category A proficiency, in a subset of procedures. However, more than 50% of all faculty either disagreed or were ambivalent that all of their graduating residents were Category A proficient in several procedures

Texas Hydrogen Highway Fuel Cell Hybrid Bus and Fueling Infrastructure Technology Showcase - Final Scientific/Technical Report

Energy Technology Data Exchange (ETDEWEB)

Hitchcock, David

2012-06-29

The Texas Hydrogen Highway project has showcased a hydrogen fuel cell transit bus and hydrogen fueling infrastructure that was designed and built through previous support from various public and private sector entities. The aim of this project has been to increase awareness among transit agencies and other public entities on these transportation technologies, and to place such technologies into commercial applications, such as a public transit agency. The initial project concept developed in 2004 was to show that a skid-mounted, fully-integrated, factory-built and tested hydrogen fueling station could be used to simplify the design, and lower the cost of fueling infrastructure for fuel cell vehicles. The approach was to design, engineer, build, and test the integrated fueling station at the factory then install it at a site that offered educational and technical resources and provide an opportunity to showcase both the fueling station and advanced hydrogen vehicles. The two primary technology components include: Hydrogen Fueling Station: The hydrogen fueling infrastructure was designed and built by Gas Technology Institute primarily through a funding grant from the Texas Commission on Environmental Quality. It includes hydrogen production, clean-up, compression, storage, and dispensing. The station consists of a steam methane reformer, gas clean-up system, gas compressor and 48 kilograms of hydrogen storage capacity for dispensing at 5000 psig. The station is skid-mounted for easy installation and can be relocated if needed. It includes a dispenser that is designed to provide temperaturecompensated fills using a control algorithm. The total station daily capacity is approximately 50 kilograms. Fuel Cell Bus: The transit passenger bus built by Ebus, a company located in Downey, CA, was commissioned and acquired by GTI prior to this project. It is a fuel cell plug-in hybrid electric vehicle which is ADA compliant, has air conditioning sufficient for Texas operations

Loss of feedwater heater analysis for the South Texas Project

International Nuclear Information System (INIS)

Joyce, K.C.; Johnson, M.R.; Albury, C.R.

1987-01-01

The results of the steady state and transient analyses of the low pressure feedwater heater train for the South Texas Nuclear Project are presented. The South Texas Project consists of two 1250 MW Westinghouse PWR units. This analysis was performed using the Modular Modeling System (MMS) simulation code. The model presented will be incorporated into the secondary side model in support of the plant training simulator and the analysis of secondary side transients. Results of this analysis are considered preliminary until benchmarked against actual plant data. A model description of the feedwater heater train from the condensate pumps to the deaerator is presented. The methodology used to develop the model is also discussed. Results of the steady state run are presented, and a transient, the loss of extraction steam to feedwater heater 15A, is examined

Mentoring SFRM: A New Approach to International Space Station Flight Control Training

Science.gov (United States)

Huning, Therese; Barshi, Immanuel; Schmidt, Lacey

2009-01-01

The Mission Operations Directorate (MOD) of the Johnson Space Center is responsible for providing continuous operations support for the International Space Station (ISS). Operations support requires flight controllers who are skilled in team performance as well as the technical operations of the ISS. Space Flight Resource Management (SFRM), a NASA adapted variant of Crew Resource Management (CRM), is the competency model used in the MOD. ISS flight controller certification has evolved to include a balanced focus on development of SFRM and technical expertise. The latest challenge the MOD faces is how to certify an ISS flight controller (Operator) to a basic level of effectiveness in 1 year. SFRM training uses a twopronged approach to expediting operator certification: 1) imbed SFRM skills training into all Operator technical training and 2) use senior flight controllers as mentors. This paper focuses on how the MOD uses senior flight controllers as mentors to train SFRM skills.

Preliminary accident analysis of Flexblue® underwater reactor

Directory of Open Access Journals (Sweden)

Haratyk Geoffrey

2015-01-01

Full Text Available Flexblue® is a subsea-based, transportable, small modular reactor delivering 160 MWe. Immersion provides the reactor with an infinite heat sink – the ocean – around the metallic hull. The reference design includes a loop-type PWR with two horizontal steam generators. The safety systems are designed to operate passively; safety functions are fulfilled without operator action and external electrical input. Residual heat is removed through four natural circulation loops: two primary heat exchangers immersed in safety tanks cooled by seawater and two emergency condensers immersed in seawater. In case of a primary piping break, a two-train safety injection system is actuated. Each train includes a core makeup tank, an accumulator and a safety tank at low pressure. To assess the capability of these features to remove residual heat, the reactor and its safety systems have been modelled using thermal-hydraulics code ATHLET with conservative assumptions. The results of simulated transients for three typical PWR accidents are presented: a turbine trip with station blackout, a large break loss of coolant accident and a small break loss of coolant accident. The analyses show that the safety criteria are respected and that the reactor quickly reaches a safe shutdown state without operator action and external power.

TEPCO plans to construct Higashidori Nuclear Power Station

International Nuclear Information System (INIS)

Tsuruta, Atsushi

2008-01-01

In 2006, TEPCO submitted to the government plans for the construction of Higashidori Nuclear Power Station. The application was filed 41 years after the project approved by the Higashidori Village Assembly. This nuclear power station will be the first new nuclear power plant constructed by TEPCO since the construction of Units No.6 and 7 at the Kashiwazaki Kariwa Nuclear Power Station 18 years ago. Higashidori Nuclear Power Station is to be constructed at a completely new site, which will become the fourth TEPCO nuclear power station. Higashidori Nuclear Power Station Unit No.1 will be TEPCO's 18th nuclear reactor. Unit No.1 will be an advanced boiling water reactor (ABWR), a reactor-type with a proven track record. It will be TEPCO's third ABWR. Alongside incorporating the latest technology, in Higashidori Nuclear Power Station Unit No.1, the most important requirement is for TEPCO to reflect in the new unit information and experience acquired from the operation of other reactors (information and experience acquired through the experience of operating TEPCO's 17 units at Fukushima Daiichi Nuclear Power Station, Fukushima Daini Nuclear Power Station and Kashiwazaki Kashiwa Nuclear Power Station in addition to information on non-conformities at nuclear power stations in Japan and around the world). Higashidori Nuclear Power Station is located in Higashidori-Village (Aomori Prefecture) and the selected site includes a rich natural environment. From an environmental perspective, we will implement the construction with due consideration for the land and sea environment, aiming to ensure that the plant can co-exist with its natural surroundings. The construction plans are currently being reviewed by the Nuclear and Industrial Safety Agency. We are committed to making progress in the project for the start of construction and subsequent commercial operation. (author)

Operating experience and performance at Narora Atomic Power Station

International Nuclear Information System (INIS)

Mittal, Subhash; Gupta, J.P.

1998-01-01

Narora Atomic Power Station consists of two units of 220 MWe capacity each. These are Pressurized Heavy Water Reactors, fuelled by natural uranium, moderated and cooled by heavy water. The Station is owned by Nuclear Power Corporation of India Ltd., which is responsible for design, construction, commissioning, and operation of all nuclear power stations in the country. NAPS was the first opportunity to apply operating experiences in design, keeping in view the evolving safety and seismicity requirements, ease of maintenance, inservice inspection needs, improved construction ability and standardization. Both the units of NAPS are having improved safety standards of current international levels. All the equipment are indigenous with improved quality and reliability. The first unit of the station went critical in March 1989 and synchronized to the grid in July 1989. The second units followed with its criticality in October 1991 and synchronization in January 1992. Considering the initial stabilizing period, the performance of both units of NAPS has progressively improved over the years. The annual capacity factor for NAPS - 1 was 90.01% and for NAPS - 2 was 89.01% for the financial year 1997-1998. This paper presents an analysis of the performance during the last three years and measures taken to improve it. The stated enhanced performance could be achieved by improvement in human performance by training/re-training, scrupulous monitoring and review of equipment/systems, institution of adequate procedure and ensuring their adherence. (authors)

The University of Texas Cold Neutron Source

International Nuclear Information System (INIS)

Uenlue, Kenan; Rios-Martinez, Carlos; Wehring, B.W.

1994-01-01

A cold neutron source has been designed, constructed, and tested by the Nuclear Engineering Teaching Laboratory (NETL) at The University of Texas at Austin. The Texas Cold Neutron Source (TCNS) is located in one of the beam ports of the NETL 1-MW TRIGA Mark II research reactor. The main components of the TCNS are a cooled moderator, a heat pipe, a cryogenic refrigerator, and a neutron guide. 80 ml of mesitylene moderator are maintained at about 30 K in a chamber within the reactor graphite reflector by the heat pipe and cryogenic refrigerator. The heat pipe is a 3-m long aluminum tube that contains neon as the working fluid. The cold neutrons obtained from the moderator are transported by a curved 6-m long neutron guide. This neutron guide has a radius of curvature of 300 m, a 50x15 mm cross-section, 58 Ni coating, and is separated into three channels. The TCNS will provide a low-background subthermal neutron beam for neutron capture and scattering research. After the installation of the external portion of the neutron guide, a neutron focusing system and a Prompt Gamma Activation Analysis facility will be set up at the TCNS. ((orig.))

Format of Basic Instruction Program Resistance Training Classes: Effect on Fitness Change in College Students

Science.gov (United States)

Barfield, J. P.; Channell, Brian; Pugh, Chip; Tuck, Matt; Pendel, Dustin

2012-01-01

New resistance training programs such as CrossFit are gaining favor among college-aged students. CrossFit and related commercial resistance training programs may provide a valuable elective option within basic instruction program (BIP) curricula, but the fitness benefits of this course have not been compared with those of existing BIP resistance…

Utilization of the Dalat Research Reactor for Radioisotope Production, Neutron Activation Analysis, Research and Training

International Nuclear Information System (INIS)

Nguyen Nhi Dien; Duong Van Dong; Cao Dong Vu; Nguyen Xuan Hai

2013-01-01

The Dalat Nuclear Research Reactor (DNRR) is a 500 kW pool type reactor loaded with a mixed core of HEU (36% enrichment) and LEU (19.75% enrichment) fuel assemblies. The reactor is used as a neutron source for the purposes of radioisotopes production, neutron activation analysis, basic and applied research and training. The reactor is operated mainly in continuous runs of 108 hours for cycles of 3–4 weeks for the above mentioned purposes. The current status of safety, operation and utilization of the reactor is given and some aspects for improvement of commercial products and services of the DNRR are also discussed in this paper. (author)

The Association between Sensation Seeking and E-Cigarette Use in Texas Young Adults: A Cross-Sectional Study

Science.gov (United States)

Case, Kathleen R.; Loukas, Alexandra; Harrell, Melissa B.; Wilkinson, Anna V.; Springer, Andrew E.; Pérez, Adriana; Creamer, MeLisa R.; Perry, Cheryl L.

2017-01-01

Objective: To examine the associations between sensation seeking and ever and current e-cigarette use in Texas young adults (18-29 years old). Current cigarette use was examined as a potential effect modifier of the associations. Participants: Participants included college students enrolled in four-year and two-year colleges in four metropolitan…

The College of Anaesthetists of Ireland Simulation Training programme: a descriptive report and analysis of course participants' feedback.

Science.gov (United States)

Cafferkey, Aine; Coyle, Elizabeth; Greaney, David; Harte, Sinead; Hayes, Niamh; Langdon, Miriam; Straub, Birgitt; Burlacu, Crina

2018-03-20

Simulation-based education is a modern training modality that allows healthcare professionals to develop knowledge and practice skills in a safe learning environment. The College of Anaesthetists of Ireland (CAI) was the first Irish postgraduate medical training body to introduce mandatory simulation training into its curriculum. Extensive quality assurance and improvement data has been collected on all simulation courses to date. Describe The College of Anaesthetists of Ireland Simulation Training (CAST) programme and report the analysis of course participants' feedback. A retrospective review of feedback forms from four simulation courses from March 2010 to August 2016 took place. Qualitative and quantitative data from 1069 participants who attended 112 courses was analysed. Feedback was overall very positive. Course content and delivery were deemed to be appropriate. Participants agreed that course participation would influence their future practice. A statistically significant difference (P simulation training in specialist anaesthesia training in Ireland.

Computer software design description for the Treated Effluent Disposal Facility (TEDF), Project L-045H, Operator Training Station (OTS)

International Nuclear Information System (INIS)

Carter, R.L. Jr.

1994-01-01

The Treated Effluent Disposal Facility (TEDF) Operator Training Station (OTS) is a computer-based training tool designed to aid plant operations and engineering staff in familiarizing themselves with the TEDF Central Control System (CCS)

Personnel training at EDF's nuclear and fossil generation division and its application for the personnel of a nuclear power station abroad

International Nuclear Information System (INIS)

Rabouhams, J.

1991-01-01

Safety in nuclear power stations relies so much upon human competence that the training of the personnel has to respond to the basic need of having personnel who are competent in their job permanently available. EDF has designed, organized and managed a large volume of training in order to provide its personnel involved in the operation of nuclear power station with initial training, training, retraining and improvement within the framework of quality organization. To deal with this training in the most efficient way EDF has developed various training aids ranging from booklets to fullscope simulator or fullscope mockups which are continually updated. All EDF experience has been used to train Daya Bay nuclear power plant personnel who have been monitored throughout the training programmes. Adequate safety conduct and attitudes including the socio-cultural background have been developed during the training. The principle teaching method was shadow training in other words the transfer in situ of knowledge, know how, and conduct from an experienced engineer. (author)

An Investigation of the Teaching Approach Used by Tutors to Prepare Science and Mathematics Teachers during Training at Morogoro Teachers' College

Science.gov (United States)

Mungure, Daudi Mika

2017-01-01

This paper investigated the teaching approach used by tutors to prepare science and mathematics teachers during training at Morogoro teachers' college. For six years consecutive the performance of science and mathematics in secondary school has become very poor even though the training colleges produce science and mathematics teachers every year…

Influence of Conflict Resolution Training on Conflict Handling Styles of College Students

Science.gov (United States)

Waithaka, Abel Gitimu; Moore-Austin, Shante'; Gitimu, Priscilla N.

2015-01-01

The purpose of this study was to investigate the influence of conflict resolution skills training on conflict handling styles, and conflict orientation of college students. Conflict handling styles was measured by the Thomas-Kilmann MODE instrument, while Conflict orientation was measured by conflict orientation survey instrument. A sample of 135…

Major Refurbishment of the University of Florida Training Reactor

International Nuclear Information System (INIS)

Joradn, Kelly; Berglund, Matthew; Shea, Brian

2013-01-01

The research reactor fleet is aging with few replacements being built. At the same time the technology for refurbishment of the older reactors has advanced well beyond that of currently installed equipment. The disparity between new and old technology results in an inability to find simple replacements for the older, highly integrated components. The lack of comprehensive guidance for digital equipment adds to the technical problems of installing individual replacement parts. Up to this point, no U. S. facilities have attempted a complete modernization effort because of the time commitment, financial burden, and licensing required for a total upgrade. The University of Florida Training Reactor is tackling this problem with a replacement of nearly all of the major facility sub-systems, including electrical distribution, reactor controls, nuclear instrumentation, security, building management, and environmental controls. This approach offers increased flexibility over the piece-by-piece replacement method by leveraging modern control systems based on global standards and capable of good data interchange with higher levels of redundancy. The UFTR reviewed numerous technologies to arrive at the final system architecture and this 'clean-slate' installation methodology. It is this concept of total system replacement and strict use of modular, open-standards technology that has allowed for a facility design that will be easy to install, maintain, and build upon over time

Major Refurbishment of the University of Florida Training Reactor

Energy Technology Data Exchange (ETDEWEB)

Joradn, Kelly; Berglund, Matthew; Shea, Brian [Univ., of Florida, Florida (United States)

2013-07-01

The research reactor fleet is aging with few replacements being built. At the same time the technology for refurbishment of the older reactors has advanced well beyond that of currently installed equipment. The disparity between new and old technology results in an inability to find simple replacements for the older, highly integrated components. The lack of comprehensive guidance for digital equipment adds to the technical problems of installing individual replacement parts. Up to this point, no U. S. facilities have attempted a complete modernization effort because of the time commitment, financial burden, and licensing required for a total upgrade. The University of Florida Training Reactor is tackling this problem with a replacement of nearly all of the major facility sub-systems, including electrical distribution, reactor controls, nuclear instrumentation, security, building management, and environmental controls. This approach offers increased flexibility over the piece-by-piece replacement method by leveraging modern control systems based on global standards and capable of good data interchange with higher levels of redundancy. The UFTR reviewed numerous technologies to arrive at the final system architecture and this 'clean-slate' installation methodology. It is this concept of total system replacement and strict use of modular, open-standards technology that has allowed for a facility design that will be easy to install, maintain, and build upon over time.

Application of Nuclear Power Plant Simulator for High School Student Training

Energy Technology Data Exchange (ETDEWEB)

Kong, Chi Dong; Choi, Soo Young; Park, Min Young; Lee, Duck Jung [Ulsan National Institute of Science and Technology, Ulsan (Korea, Republic of)

2014-10-15

In this context, two lectures on nuclear power plant simulator and practical training were provided to high school students in 2014. The education contents were composed of two parts: the micro-physics simulator and the macro-physics simulator. The micro-physics simulator treats only in-core phenomena, whereas the macro-physics simulator describes whole system of a nuclear power plant but it considers a reactor core as a point. The high school students showed strong interests caused by the fact that they operated the simulation by themselves. This abstract reports the training detail and evaluation of the effectiveness of the training. Lectures on nuclear power plant simulator and practical exercises were performed at Ulsan Energy High School and Ulsan Meister High School. Two simulators were used: the macro- and micro-physics simulator. Using the macro-physics simulator, the following five simulations were performed: reactor power increase/decrease, reactor trip, single reactor coolant pump trip, large break loss of coolant accident, and station black-out with D.C. power loss. Using the micro-physics simulator, the following three analyses were performed: the transient analysis, fuel rod performance analysis, and thermal-hydraulics analysis. The students at both high schools showed interest and strong support for the simulator-based training. After the training, the students showed passionate responses that the education was of help for them to get interest in a nuclear power plant.

Application of Nuclear Power Plant Simulator for High School Student Training

International Nuclear Information System (INIS)

Kong, Chi Dong; Choi, Soo Young; Park, Min Young; Lee, Duck Jung

2014-01-01

In this context, two lectures on nuclear power plant simulator and practical training were provided to high school students in 2014. The education contents were composed of two parts: the micro-physics simulator and the macro-physics simulator. The micro-physics simulator treats only in-core phenomena, whereas the macro-physics simulator describes whole system of a nuclear power plant but it considers a reactor core as a point. The high school students showed strong interests caused by the fact that they operated the simulation by themselves. This abstract reports the training detail and evaluation of the effectiveness of the training. Lectures on nuclear power plant simulator and practical exercises were performed at Ulsan Energy High School and Ulsan Meister High School. Two simulators were used: the macro- and micro-physics simulator. Using the macro-physics simulator, the following five simulations were performed: reactor power increase/decrease, reactor trip, single reactor coolant pump trip, large break loss of coolant accident, and station black-out with D.C. power loss. Using the micro-physics simulator, the following three analyses were performed: the transient analysis, fuel rod performance analysis, and thermal-hydraulics analysis. The students at both high schools showed interest and strong support for the simulator-based training. After the training, the students showed passionate responses that the education was of help for them to get interest in a nuclear power plant

Keeping research reactors relevant: a pro-active approach for SLOWPOKE-2 at RMC

International Nuclear Information System (INIS)

Cosby, L.; Nielsen, K.; Bennett, L.G.I.

2011-01-01

In 2001, the Royal Military College of Canada replaced its aging analogue SLOWPOKE-2 reactor control system with a digital control system. The system was successfully commissioned and has provided a renewed platform for student learning and research. An upgrade to the digital control and instrumentation system has been completed and will be installed in October 2010. The upgrade includes new computer hardware, updated software and a simulation and training system that will enhance training, education and research by licensed operators, students and researchers.

The Classroom Performance System (CPS): Effects on student participation, attendance, and achievement in multicultural anatomy and physiology classes at South Texas College

Science.gov (United States)

Termos, Mohamad Hani

2011-12-01

The Classroom Performance System (CPS) is an instructional technology tool that increases student performance and addresses different learning styles. Instructional technologies are used to promote active learning; however, student embarrassment issue in a multicultural setting is not addressed. This study assessed the effect of the CPS on student participation, attendance, and achievement in multicultural college-level anatomy and physiology classes at South Texas College, where the first spoken language is not English. Quantitative method and quasi-experimental design were employed and comparative statistic methods and pre-post tests were used to collect the data. Participants were college students and sections of study were selected by convenient sampling. Participation was 100% during most of the lectures held and participation rate did not strike above 68% in control group. Attendance was significantly higher in CPS sections than the control group as shown by t-tests. Experimental sections had a higher increase in the pre-post test scores and student averages on lecture exams increased at a higher rate as compared to the control group. Therefore, the CPS increased student participation, attendance, and achievement in multicultural anatomy and physiology classes. The CPS can be studied in other settings where the first spoken language is English or in other programs, such as special education programs. Additionally, other variables can be studied and other methodologies can be employed.

Neutron radiography (NRAD) reactor 64-element core upgrade

Energy Technology Data Exchange (ETDEWEB)

Bess, John D. [Idaho National Lab. (INL), Idaho Falls, ID (United States)

2014-03-01

The neutron radiography (NRAD) reactor is a 250 kW TRIGA (registered) (Training, Research, Isotopes, General Atomics) Mark II , tank-type research reactor currently located in the basement, below the main hot cell, of the Hot Fuel Examination Facility (HFEF) at the Idaho National Laboratory (INL). It is equipped with two beam tubes with separate radiography stations for the performance of neutron radiography irradiation on small test components. The interim critical configuration developed during the core upgrade, which contains only 62 fuel elements, has been evaluated as an acceptable benchmark experiment. The final 64-fuel-element operational core configuration of the NRAD LEU TRIGA reactor has also been evaluated as an acceptable benchmark experiment. Calculated eigenvalues differ significantly (approximately ±1%) from the benchmark eigenvalue and have demonstrated sensitivity to the thermal scattering treatment of hydrogen in the U-Er-Zr-H fuel.

Darlington Station outage - a maintenance perspective

International Nuclear Information System (INIS)

Plourde, J.; Marczak, J.; Stone, M.; Myers, R.; Sutton, K.

1997-01-01

Ontario Hydro's Darlington Nuclear Generating Station (4x881MW(e)net) has carried out its first station outage since full commercial operation. The outage presented challenges to the organization in terms of outage planning, support, management, and safe execution within the constraints of schedule, budget and resources. This paper will focus on the success of the outage maintenance program, identifying the major work programs - a vacuum structure and containment outage, an emergency service water system outage, an emergency coolant injection system outage, intake channel inspections, low pressure service water inspections, and significant outage maintenance work on each of the four reactor units. Planning for the outage was initiated early in anticipation of this important milestone in the station's life. Detailed safety reviews - nuclear, radiation, and conventional - were conducted in support of the planned maintenance program. System lineup and work protection were provided by the Station Operator work group. Work protection permitry was initiated well in advance of the outage. Station maintenance staff resources were bolstered in support of the outage to ensure program execution could be maintained within the schedule. Training programs were in place to ensure that expectations were clear and that high standards would be maintained. Materials management issues in support of maintenance activities were given high priority to ensure no delays to the planned work. Station management review and monitoring in preparation for and during the outage ensured that staff priorities remained focused. Lessons learned from the outage execution are being formalized in maintenance procedures and outage management procedures, and shared with the nuclear community. (author)

Economic simplified boiling water reactor (ESBWR) response to an extended station blackout/ loss of all AC power

International Nuclear Information System (INIS)

Barrett, A.J.; Marquino, W.

2013-01-01

U.S. federal regulations require light water cooled nuclear power plants to cope with Station Blackout for a predetermined amount of time based on design factors for the plant. U.S. regulations define Station Blackout (SBO) as a loss of the offsite electric power system concurrent with turbine trip and unavailability of the onsite emergency AC power system. According to U.S. regulations, typically the coping period for an SBO is 4 hours and can be as long as 16 hours for currently operating BWR plants. Being able to cope with an SBO and loss of all AC power is required by international regulators as well. The U.S. licensing basis for the ESBWR is a coping period of 72 hours for an SBO based on U.S. NRC requirements for passive safety plants. In the event of an extended SBO (viz., greater than 72 hours), the ESBWR response shows that the design is able to cope with the event for at least 7 days without AC electrical power or operator action. ESBWR is a Generation III+ reactor design with an array of passive safety systems. The ESBWR primary success path for mitigation of an SBO event is the Isolation Condenser System (ICS). The ICS is a passive, closed loop, safety system that initiates automatically on a loss of power. Upon Station Blackout or loss of all AC power, the ICS begins removing decay heat from the Reactor Pressure Vessel (RPV) by (i) condensing the steam into water in heat exchangers located in pools of water above the containment, and (ii) transferring the decay heat to the atmosphere. The condensed water is then returned by gravity to cool the reactor again. The ICS alone is capable of maintaining the ESBWR in a safe shutdown condition after an SBO for an extended period. The fuel remains covered throughout the SBO event. The ICS is able to remove decay heat from the RPV for at least 7 days and maintains the reactor in a safe shutdown condition. The water level in the RPV remains well above the top of active fuel for the duration of the SBO event

Floating nuclear heat. And power station 'Pevec' with KLT-40S type reactor plant for remote regions of Russia

International Nuclear Information System (INIS)

Veshnyakov, K.B.; Kiryushin, A.I.; Panov, Yu.K.; Polunichev, V.I.

2000-01-01

Floating small nuclear power plants power for local energy systems of littoral regions of Russia, located far from central energy system, open a new line in nuclear power development. Designing a floating power unit of a lead nuclear heat and power generating station for port Pevec at the Chuckchee national district is currently nearing completion. Most labor-intensive components are being manufactured. The co-generation NPP Pevec is to be created on the basis of a floating power unit with KLT-40S type reactor plant. KLT-40S reactor plant is based on similar propulsion plants, verified at operation of Russia's nuclear-powered civil ships, evolutionary improved by elimination of 'weak points' revealed during its prototypes operation or on the basis of safety analysis. KLT-40S reactor plant uses the most wide-spread and developed in the world practice PWR-type reactor. KLT-40S meets contemporary national and international requirements imposed to future reactor plants. The NHPS description, its main technical-economic data, environmental safety indices, basic characteristics of KLT-40S reactor plant are presented. Prospects of small NPPs utilization outside Russia, particularly as an energy source for sea water desalination, are considered. (author)

Comparison of oxide- and metal-core behavior during CRBRP [Clinch River Breeder Reactor Plant] station blackout

International Nuclear Information System (INIS)

Polkinghorne, S.T.; Atkinson, S.A.

1986-01-01

A resurrected concept that could significantly improve the inherently safe response of Liquid-Metal cooled Reactors (LMRs) during severe undercooling transients is the use of metallic fuel. Analytical studies have been reported on for the transient behavior of metal-fuel cores in innovative, inherently safe LMR designs. This paper reports on an analysis done, instead, for the Clinch River Breeder Reactor Plant (CRBRP) design with the only innovative change being the incorporation of a metal-fuel core. The SSC-L code was used to simulate a protected station blackout accident in the CRBRP with a 943 MWt Integral Fast Reactor (IFR) metal-fuel core. The results, compared with those for the oxide-fueled CRBRP, show that the margin to boiling is greater for the IFR core. However, the cooldown transient is more severe due to the faster thermal response time of metallic fuel. Some additional calculations to assess possible LMR design improvements (reduced primary system pressure losses, extended flow coastdown) are also discussed. 8 refs., 13 figs., 2 tabs

Preventing Interpersonal Violence on College Campuses: The Effect of One Act Training on Bystander Intervention.

Science.gov (United States)

Alegría-Flores, Kei; Raker, Kelli; Pleasants, Robert K; Weaver, Mark A; Weinberger, Morris

2015-05-22

Sexual assault, stalking, dating violence, and intimate partner violence, herein collectively termed interpersonal violence (IV), are public health problems affecting 20% to 25% of female college students. Currently, One Act is one of the few IV prevention training programs at universities that teach students bystander skills to intervene in low- and high-risk IV situations. The objectives of this study were 1) to evaluate One Act's effects on date rape attitudes and behaviors, and bystanders' confidence, willingness to help, and behavior, and 2) to compare the effects on bystander skills between One Act and Helping Advocates for Violence Ending Now (HAVEN), an IV response training program with similar participants. Data were collected over 2 years, before and after One Act and HAVEN trainings. We measured outcomes with four scales: College Date Rape Attitudes and Behaviors, Bystander Confidence, Willingness to Help, and Bystander Behavior. The analysis compared within- and between-group mean differences in scale scores pre- and post-trainings using linear mixed models. One Act showed improvements for date rape attitudes and behaviors (p trainings' effects on bystander willingness to help and behavior had similar patterns but were not statistically significant. We found a larger positive impact on bystander confidence among students who participated in the bystander prevention training compared with the response training. Further research is needed to improve the measures for bystander behavior and measure the bystander trainings' larger impact on the community. © The Author(s) 2015.

Sensitivity study of steam explosion characteristics to uncertain input parameters using TEXAS-V code

International Nuclear Information System (INIS)

Grishchenko, Dmitry; Basso, Simone; Kudinov, Pavel; Bechta, Sevostian

2014-01-01

Release of core melt from failed reactor vessel into a pool of water is adopted in several existing designs of light water reactors (LWRs) as an element of severe accident mitigation strategy. Corium melt is expected to fragment, solidify and form a debris bed coolable by natural circulation. However, steam explosion can occur upon melt release threatening containment integrity and potentially leading to large early release of radioactive products to the environment. There are many factors and parameters that could be considered for prediction of the fuel-coolant interaction (FCI) energetics, but it is not clear which of them are the most influential and should be addressed in risk analysis. The goal of this work is to assess importance of different uncertain input parameters used in FCI code TEXAS-V for prediction of the steam explosion energetics. Both aleatory uncertainty in characteristics of melt release scenarios and water pool conditions, and epistemic uncertainty in modeling are considered. Ranges of the uncertain parameters are selected based on the available information about prototypic severe accident conditions in a reference design of a Nordic BWR. Sensitivity analysis with Morris method is implemented using coupled TEXAS-V and DAKOTA codes. In total 12 input parameters were studied and 2 melt release scenarios were considered. Each scenario is based on 60,000 of TEXAS-V runs. Sensitivity study identified the most influential input parameters, and those which have no statistically significant effect on the explosion energetics. Details of approach to robust usage of TEXAS-V input, statistical enveloping of TEXAS-V output and interpretation of the results are discussed in the paper. We also provide probability density function (PDF) of steam explosion impulse estimated using TEXAS-V for reference Nordic BWR. It can be used for assessment of the uncertainty ranges of steam explosion loads for given ranges of input parameters. (author)

Upgrade of VR-1 training reactor I and C

International Nuclear Information System (INIS)

Kropik, M.; Matejka, K.; Chab, V.

2003-01-01

The contribution describes the upgrade of the VR-1 training reactor I and C (Instrumentation and Control). The reactor was put into operation in the 1990, and its I and C seems to be obsolete now. The new I and C utilises the same digital technology as the old one. The upgrade has been done gradually during holidays in order not to disturb the reactor utilisation during teaching and training. The first stage consisted in the human-machine interface and the control room upgrade in 2001. A new operator's desk, displays, indicators and buttons were installed. Completely new software and communication interface to the present I and C were developed. During the second stage in 2002, new control rod drivers and safety circuits were installed. The rod motors were replaced and necessary mechanical changes on the control rod mechanism, induced by the utilisation of the new motor, were done. The new safety circuits utilise high quality relays with forced contacts to guarantee high reliability of their operation. The third stage, the control system upgrade is being carried out now. The new control system is based on an industrial PC mounted in a 19 inch crate. The operating system of the PC is the Microsoft Windows XP with the real time support RTX of the VentureCom Company. A large amount of work has been devoted to the software requirements to specify all dependencies, modes and permitted actions, safety measures, etc. The Department took an active part in the setting of software requirements and later in verification and validation of the software and the whole control system. Finally, a new protection system consisting of power measuring and power protection channels will be installed in 2004 or 2005. (author)

A PC-based high temperature gas reactor simulator for Indonesian conceptual HTR reactor basic training

Science.gov (United States)

Syarip; Po, L. C. C.

2018-05-01

In planning for nuclear power plant construction in Indonesia, helium cooled high temperature reactor (HTR) is favorable for not relying upon water supply that might be interrupted by earthquake. In order to train its personnel, BATAN has cooperated with Micro-Simulation Technology of USA to develop a 200 MWt PC-based simulation model PCTRAN/HTR. It operates in Win10 environment with graphic user interface (GUI). Normal operation of startup, power maneuvering, shutdown and accidents including pipe breaks and complete loss of AC power have been conducted. A sample case of safety analysis simulation to demonstrate the inherent safety features of HTR was done for helium pipe break malfunction scenario. The analysis was done for the variation of primary coolant pipe break i.e. from 0,1% - 0,5 % and 1% - 10 % helium gas leakages, while the reactor was operated at the maximum constant power of 10 MWt. The result shows that the highest temperature of HTR fuel centerline and coolant were 1150 °C and 1296 °C respectively. With 10 kg/s of helium flow in the reactor core, the thermal power will back to the startup position after 1287 s of helium pipe break malfunction.

The Identification of Factors Influencing College Students' Attitudes toward Radioactivity.

Science.gov (United States)

Crater, Harold L., Jr.

The two basic questions considered in this study were: (1) What attitudes do college students hold toward radioactivity? and (2) What are some characteristics associated with the college students who hold the more favorable attitudes toward radioactivity? The sample studied included 1,205 mostly undergraduate students at the University of Texas at…

The role of Columbia Basin College in training technicians for environmental remediation at the DOE Hanford Site

International Nuclear Information System (INIS)

Ferrigno, K.F.

1991-01-01

Community colleges have the ability to play a vital role in the environmental remediation training process for DOE hazardous waste sites. Columbia Basin College in Pasco, Washington is presently involved in such training through numerous workshops offered primarily for employees at the Hanford DOE site, and a two-year associate of applied science degree in Hazardous Materials Management Technology. The workshops are oriented towards specific applied technical training (40 Hour OSHA/80 Hour WISHA, Hazardous/Radioactive Waste Video conference, and others) whereas the degree program provides a broad background in the skills needed for environmental technicians (16 hazmat courses plus support sciences and humanities). The degree program, combined with hazmat work experience, should provide the necessary background for project supervision as well as for skilled field technicians

Why rapidly expanding the number of college-trained workers may not lower income inequality: The curious case of Taiwan, 1978-2011

OpenAIRE

Keng, Shao-Hsun; Lin, Chun-Hung; Orazem, Peter

2014-01-01

Since 1990, Taiwan increased the college share of its labor force from 7% to 28% by converting junior colleges to 4-year colleges. Such a rapid surge in skill supply should suppress college wages and lower income inequality. Instead, inequality rose steadily. The surge of weaker college graduates made them weak substitutes for better trained college graduates, increasing wage inequality within skill groups. The college premium would have been 15% higher had college quality remained unchanged ...

Training for the Self-Catering Industry. An Example of College/Employer Collaboration in Training for Unemployed Adults. FEU/REPLAN.

Science.gov (United States)

Further Education Unit, London (England).

A Local Collaborative Project was developed by an employers' association (Best of British Holidays), Evesham College of Further Education, the Department of Education and Science PICKUP Unit, and Hereford and Worcester Local Education Authority to train workers for the self-catering (travel and tourism) industry in England. During the project,…

Materials Test Station

Data.gov (United States)

Federal Laboratory Consortium — When completed, the Materials Test Station at the Los Alamos Neutron Science Center will meet mission need. MTS will provide the only fast-reactor-like irradiation...

INTEGRATION PECULIARITIES OF COMPUTERIZED MEANS OF EDUCATION INTO THE PROCESS OF TEACHER TRAINING AT PEDAGOGICAL COLLEGES

Directory of Open Access Journals (Sweden)

Olga M. Naumenko

2010-08-01

Full Text Available Important problems of using the computerized means of education in the process of teacher training at pedagogical college are considered. On the basis of the analysis of the organisation of educational process in different pedagogical colleges, the general principles of construction of the educational module “Methodology of computerized means of education in educational process” are considered.

Gipsy Hill Training College Graduates: Once, Always and Everywhere a Modern Woman Teacher in the Interwar Years

Science.gov (United States)