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Sample records for texas college station training reactor

  1. The training and research reactor of the Zittau Technical College

    International Nuclear Information System (INIS)

    Ackermann, G.; Hampel, R.; Konschak, K.

    1979-01-01

    The light-water moderated training and research reactor of the Zittau Technical College, which has been put into operation 1 July 1979, is described. Having a power of 10 MW, it is provided for education of students and advanced training of nuclear power plant staff members. High inherent nuclear safety and economy of operation are achieved by appropriate design of the reactor core and the use of fresh fuel elements provided for the 10-MW research reactor at the Rossendorf Central Institute for Nucleear Research for one year on a loan basis. Further characteristics of the reactor are easy accessibility of the core interior for in-core studies, sufficient external experimental channels, and a control and protection system meeting the requirements of teaching operation. The installed technological and dosimetric devices not only ensure reliable operation of the reactor, but also extend the potentialities of experimental work and education that is reported in detail. The principles on which the training programs are based are explained in the light of some examples. The training reactor is assumed to serve for providing basic knowledge about processes in nuclear power stations with pressurized water reactors. Where the behaviour of a nuclear power station cannot sufficiently be demonstrated by the training reactor, a reasonable completion of practical training at special simulation models and experimental facilities of the Technical College and at the nuclear power plant simulator of the Rheinsberg nuclear power plant school has been conceived. (author)

  2. Reactor operator: Training for the job while earning college credit

    International Nuclear Information System (INIS)

    Murdick, S.A.

    1988-01-01

    The nuclear industry is looking for ways to maximize the dollars spent to train licensed reactor operators and other personnel and, at the same time, upgrade their educational level. The prospects of college credit and/or degree requirements imposed by the US Nuclear Regulatory Commission have provided a significant driving force behind this search. The task is complicated, however, because shift schedules do not permit reactor operators to pursue higher education through the traditional classroom route, and the need for plant-specific training and requalification programs dictate against uniformly adapting college-based courses for training use. The National Program on Noncollegiate Sponsored Instruction (National PONSI) has been of considerable help to the nuclear industry in meeting these challenges. Through its college credit recommendation service, National PONSI has assessed the comparability of certain industry training activities to college-level instruction and has been instrumental in gaining academic recognition of these activities. The program has become a vital means for the industry to achieve its dual mission of preparing employees to successfully perform their jobs and providing them with ways to obtain college degrees in the shortest possible time

  3. Reactor operator: Training for the job while earning college credit

    Energy Technology Data Exchange (ETDEWEB)

    Murdick, S.A.

    1988-01-01

    The nuclear industry is looking for ways to maximize the dollars spent to train licensed reactor operators and other personnel and, at the same time, upgrade their educational level. The prospects of college credit and/or degree requirements imposed by the US Nuclear Regulatory Commission have provided a significant driving force behind this search. The task is complicated, however, because shift schedules do not permit reactor operators to pursue higher education through the traditional classroom route, and the need for plant-specific training and requalification programs dictate against uniformly adapting college-based courses for training use. The National Program on Noncollegiate Sponsored Instruction (National PONSI) has been of considerable help to the nuclear industry in meeting these challenges. Through its college credit recommendation service, National PONSI has assessed the comparability of certain industry training activities to college-level instruction and has been instrumental in gaining academic recognition of these activities. The program has become a vital means for the industry to achieve its dual mission of preparing employees to successfully perform their jobs and providing them with ways to obtain college degrees in the shortest possible time.

  4. Predictive models of energy consumption in multi-family housing in College Station, Texas

    Science.gov (United States)

    Ali, Hikmat Hummad

    Patterns of energy consumption in apartment buildings are different than those in single-family houses. Apartment buildings have different physical characteristics, and their inhabitants have different demographic attributes. This study develops models that predict energy usage in apartment buildings in College Station. This is accomplished by analyzing and identifying the predictive variables that affect energy usage, studying the consumption patterns, and creating formulas based on combinations of these variables. According to the hypotheses and the specific research context, a cross-sectional design strategy is adopted. This choice implies analyses across variations within a sample of fourplex apartments in College Station. The data available for analysis include the monthly billing data along with the physical characteristics of the building, climate data for College Station, and occupant demographic characteristics. A simple random sampling procedure is adopted. The sample size of 176 apartments is drawn from the population in such a way that every possible sample has the same chance of being selected. Statistical methods used to interpret the data include univariate analysis (mean, standard deviation, range, and distribution of data), correlation analysis, regression analysis, and ANOVA (analyses of variance). The results show there are significant differences in cooling efficiency and actual energy consumption among different building types, but there are no significant differences in heating consumption. There are no significant differences in actual energy consumption between student and non-student groups or among ethnic groups. The findings indicate that there are significant differences in actual energy consumption among marital status groups and educational level groups. The multiple regression procedures show there is a significant relationship between normalized annual consumption and the combined variables of floor area, marital status, dead band

  5. Safety-evaluation report related to renewal of the operating license for the Texas A and M University Research Reactor. Docket No. 50-128, License R-83

    International Nuclear Information System (INIS)

    1983-03-01

    This Safety Evaluation Report for the application filed by the Texas A and M University (Texas A and M) for a renewal of operating license number R-83 to continue to operate a 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 Texas Engineering and Experiment Station of the Texas A and M University and is located on the campus in College Station, Brazos County, Texas. The staff concludes that the TRIGA reactor facility can continue to be operated by Texas A and M University without endangering the health and safety of the public

  6. Training courses for the staff of the nuclear power station KRSKO conducted at the TRIGA reactor center in Ljubljana

    International Nuclear Information System (INIS)

    Pregl, G.; Najzer, M.

    1976-01-01

    The training program for the Nuclear Power Station Krsko was divided into two modules: fundamentals of nuclear engineering and specialized training according to duties that candidates are supposed to take at the power station. Basic training was organized at the TRIGA Reactor Center in Ljubljana in two different versions. The first version intended for plant operators and all engineers lasted for six months and included about 500 hours of classroom lessons and seminars and 31 laboratory experiments. The educational program was conventional. The following topics were covered: nuclear and atomic physics, reactor theory, reactor dynamics, reactor instrumentation and control, heat transfer in nuclear power plants, nuclear power plant systems, reactor materials, reactor safety, and radiation protection. Until now, two groups, consisting of 37 candidates altogether, have attended this basic course. Plans have been made to conduct two additional courses of about 20 students each for technicians other than operators. The program of this second version will be reduced, with the emphasis on reactor core physics and radiation protection. Classroom lessons will be strongly supported by laboratory experiments. (author)

  7. Overview: Texas College and Career Readiness Standards

    Science.gov (United States)

    Texas Higher Education Coordinating Board, 2009

    2009-01-01

    The Texas College and Career Readiness Standards define what students should know and be able to accomplish in order to succeed in entry-level college courses or skilled workforce opportunities upon graduation from high school. This paper answers the following questions: (1) Who developed the Texas College and Career Readiness Standards?; (2) What…

  8. Use of multiple on-campus reactors in education and training programs

    International Nuclear Information System (INIS)

    Schlapper, G.A.

    1989-01-01

    In its undergraduate and graduate programs in nuclear engineering and health physics, Texas A ampersand M University utilizes two reactors for the training and education of students. The 5-W AGN-201 nuclear training reactor has been in use since the late 1950s, while the 1-MW TRIGA Nuclear Science Center Reactor (NSCR) was first utilized in late 1961. Both facilities have been upgraded since initial criticality, the AGN power level being increased from the original 200-mW limit to its 5-W current level and the NSCR undergoing conversion from a 100-kW materials test reactor fueled deign to a 1-MW TRIGA-fueled facility. The AGN reactor is operated by the Department of Nuclear Engineering of the College of Engineering and is almost solely utilized in training and education programs. The NSCR facility is administered by the Texas Engineering Experiment Station and support research efforts of faculty and students of departments within and outside the university in addition to contributing to the education and training programs of the nuclear engineering department

  9. Technical Training seminar: Texas Instruments

    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 Michael Scholtholt, Field Application Engineer / TEXAS INSTRUMENTS (US, D, CH) POWER - A short approach to Texas Instruments power products 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 the SWIFT software FPGA + CPLD power solutions WIRELESS / CHIPCON Decision criteria when choosing a RF platform Introduction to Texas Instruments wireless products: standardized platforms proprietary platforms ( 2.4 GHz / sub 1 GHz) development tools Antenna design: example for 2.4 GHz questions, discussion Industrial partners: Robert Medioni, François Caloz / Spoerle Electronic, CH-1440 Montagny (VD), Switzerland Phone: +41 24 447 0137, email: RMedioni@spoerle.com, http://www.spoerle.com Language: English. Free s...

  10. Training of power station staff

    International Nuclear Information System (INIS)

    Dusserre, J.

    1993-01-01

    ELECTRICITE DE FRANCE currently operates 51 generating stations with 900 and 1300 MW Pressurized Water Reactors while, only 15 years ago, France possessed only a very small number of such stations. It was therefore vital to set up a major training organization to produce staff capable of starting, controlling and maintaining these facilities with a constant eye to improving quality and safety. Operator and maintenance staff training is based on highly-structured training plans designed to match both the post to be filled and the qualifications possessed by the person who is to fill it. It was essential to set up suitable high-performance training resources to handle this fast growth in staff. These resources are constantly being developed and allow EDF to make steady progress in a large number of areas, varying from the effects of human factors to the procedures to be followed during an accident

  11. 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

  12. Texas Affordable Baccalaureate Program: A Collaboration between the Texas Higher Education Coordinating Board, South Texas College, and Texas A&M University-Commerce. CBE Case Study

    Science.gov (United States)

    Klein-Collins, Rebecca; Glancey, Kathleen

    2015-01-01

    This case study is part of a series on newer competency-based degree programs that have been emerging in recent years. In January 2014, the Texas Higher Education Coordinating Board (THECB), South Texas College (STC), and Texas A&M University-Commerce (A&M Commerce) launched the Texas Affordable Baccalaureate Program, the state's first…

  13. 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

  14. Reactor safety training for decision making

    International Nuclear Information System (INIS)

    Scott, C.K.

    2003-01-01

    The purpose of this paper is to describe an approach to reactor safety training for technical staff working at an operating station. The concept being developed is that, when the engineer becomes a registered professional engineer, they have sufficient reactor safety knowledge to perform independent technical work without compromising the safety of the plant. This goal would be achieved with a focused training program while working as an engineer-in-training (four years in NB). (author)

  15. 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…

  16. Training of engineers for nuclear power station operation

    International Nuclear Information System (INIS)

    Myerscough, P.B.

    1980-01-01

    The requirements for staffing and training of a nuclear electric utility are described. Current training facilities at the Central Electricity Generating Board are applicable to gas-cooled technology with the possibility of the introduction of a thermal water system and fast reactors in the future. The CEGB training centres provide for the initial training of operational staff, revision training of experienced operational staff, and training of non-operational staff from the stations and supporting departments. Details are given of the content of the training courses which also provide simulation facilities of the basic dynamics of the CEGB stations. Further developments in simulation will include dynamics of the boiler and turbine plants in Magnox stations. The flexibility of the AGR simulations will enable the training exercises to be adjusted to meet changing operating patterns for each AGR station. (U.K.)

  17. Decommissioning of multiple-reactor stations: facilitation by sequential decommissioning

    International Nuclear Information System (INIS)

    Moore, E.B.; Smith, R.I.; Wittenbrock, N.G.

    1982-01-01

    Reductions in cost and radiation dose can be achieved for decommissionings at multiple reactor stations because of factors not necessarily present at a single reactor station: reactors of similar design, the opportunity for sequential decommissioning, a site dedicated to nuclear power generation, and the option of either interim or permanent low-level radioactive waste storage facilities onsite. The cost and radiation dose reductions occur because comprehensive decommissioning planning need only be done once, because the labor force is stable and need only be trained once, because there is less handling of radioactive wastes, and because central stores, equipment, and facilities may be used. The cost and radiation dose reductions are sensitive to the number and types of reactors on the site, and to the alternatives selected for decommissioning. 3 tables

  18. 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...

  19. 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

  20. 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)

  1. 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.

  2. 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…

  3. 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

  4. 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

  5. Texas Student Success Council: Finding Common Ground to Increase Community College Completion

    Science.gov (United States)

    Collins, Michael Lawrence

    2014-01-01

    In 2011, a prominent Texas business group erected provocative billboards condemning low completion rates at the state's community colleges and questioning the value of tax dollars spent there. The Texas Association of Business put up the signs to prod community colleges to do more to increase student success and help create a better educated…

  6. 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)

  7. 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…

  8. The training and assessment of operations engineers at Hinkley Point 'B' nuclear power station

    International Nuclear Information System (INIS)

    Walsey, B.A.; Howard, J.D.

    1986-01-01

    The Nuclear Power Training Centre at Oldbury-on-Severn was established to provide a common training of staff at all nuclear power stations operated by the Central Electricity Generating Board, following the ''Standard Specification for the Nuclear Training of Staff at CEGB Nuclear Power Stations''. The paper deals with the following aspects of AGR Stations: The Legislation applicable to these stations. The current training requirements for Operations Staff. The development of training for operations staff at Hinkley Point 'B' including training for career progression within the Operations Department. A detailed explanation of the training package developed for Reactor Desk Drivers at Hinkley 'B'. Revision training of Operations staff to ensure that they continue to run the plant in a safe and commercially viable manner. The training of Shift Operations Engineers for their duties under the Station Emergency Plan. (author)

  9. 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

  10. 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)

  11. 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…

  12. 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…

  13. An assessment of the SSC impact on the training and employment needs of North Central Texas

    International Nuclear Information System (INIS)

    Orsak, C.G.; McGlohen, P.; Jenkens, L.

    1992-01-01

    The Texas Higher Education Coordinating Board has funded the Navarro College/Dallas County Community College Districe SSC Technical Training Project to determine the direct and inderect manpower needs in the eighteen-county North Cenbtral Texas area surrounding the Superconducting Super Collider Laboratory (SSCL) and to identify training programs to be developed by local community colleges. The tasks of this project were specifically designed to maximize the use of existing informatiion resources of various organizations and agencies concerned with lobor force development issues to provide custom databases focusied upon the SSCL. The labor market informataion (LMI) resources developed in this project provide a strong foundation for examining the impacts of the SSCL on the training and employment needs of the North Central Texas region. The direct and indirect effects of the SSCL are analyzed to the smallest level of occupational detail feasible. Regional labor demand estimates and forecasts were updated and expanded, county level demand data was developed, statewide vocational education programs were inventoried and lists of affected regional employers were extracted. All of the data developed in this project is available in standard Dbase disk files, formatted to be compatible with other LMI resources such as INTERLINK's LMIS. Further, a custom version of INTERLINK's PC-based LMIS software was developed for the SSC Technical Training Project to provide the greatest access to and linkage between the labor demand and supply data developed in this study. Future efforts to develop additional information resources relevant to the event of the SSCL must focus upon comparative analyses of similar projects, such as Fermilab and others, to provide more detail to the products developed in this project

  14. The JASON reactor at the Royal Naval College: Silver Jubilee 6th November 1987

    International Nuclear Information System (INIS)

    Lakey, J.R.A.; Roust, C.B.

    1988-01-01

    The 10 kW Research and Training Reactor Jason has been used at the Royal Naval College for 25 years in support of the Naval Nuclear Submarine Propulsion Programme. The principal features of Jason, relevant to its training role are given, along with the specifications of Jason, instrumentation, maintenance and operational experience. The educational role of the reactor is described with respect to the Nuclear Reactor Course, Nuclear Advanced Course, and the Nuclear Radiation Protection Course. Future developments in operator training, advantages of the low power reactor, quality control of education and training, and research and development, are also discussed. (U.K.)

  15. 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

  16. Physical trajectory profile data from glider Stommel deployed by Texas A&M University; Texas A&M University - College Station; Geochemical and Environmental Research Group in the Gulf of Mexico from 2017-06-27 to 2017-07-05 (NCEI Accession 0164085)

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — Monitoring the baseline water quality across the Texas shelf. The National Centers for Environmental Information (NCEI) received the data in this archival package...

  17. Physical trajectory profile data from glider Stommel deployed by Texas A&M University; Texas A&M University - College Station; Geochemical and Environmental Research Group in the Gulf of Mexico from 2017-01-20 to 2017-05-07 (NCEI Accession 0162538)

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — Monitoring the baseline water quality across the Texas shelf. The National Centers for Environmental Information (NCEI) received the data in this archival package...

  18. 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...

  19. 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.)

  20. 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…

  1. 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…

  2. Community College Faculty Who Conduct Industry Training Activities: A Job Satisfaction Study.

    Science.gov (United States)

    Konicek, Dale George

    1992-01-01

    Discusses the relationship between industry-related training assignments and faculty job satisfaction, presenting findings from a study of faculty in 37 Texas community colleges. Highlights demographic and work environment variables. Reports general faculty satisfaction with the work but dissatisfaction with working conditions. Presents teachers'…

  3. 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

  4. 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

  5. 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

  6. 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.

  7. 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

  8. 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)

  9. 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

  10. 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

  11. 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…

  12. 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…

  13. 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…

  14. 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…

  15. 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)

  16. 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

  17. 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

  18. 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)

  19. 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

  20. 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.

  1. 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)

  2. 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 ...

  3. 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

  4. Mouse Plantar Flexor Muscle Size and Strength After Inactivity and Training

    Science.gov (United States)

    2010-07-01

    atrophy and weakness as a function of the intensity of the train- ing ( 15 ). Although the hind limb suspension resulted in loss of muscle mass in...Muscle Biology Laboratory, Department of Health and Kinesiology , Texas A&M University, College Station, TX, and Gordon L. Warren, Ph.D., Division of

  5. 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)

  6. 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.

  7. 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)

  8. 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

  9. 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.

  10. 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.)

  11. 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.

  12. 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

  13. 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.)

  14. 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)

  15. 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)

  16. Imperial College Reactor Centre annual report 1983

    International Nuclear Information System (INIS)

    1983-01-01

    The report covers the following matters: research topics (reactor engineering; neutron and gamma dosimetry; nuclear physics; stable and radiotracer studies; neutron activation analysis (medicine; the environment; archaeology; geology)); personnel; publications; overseas visits; research contracts; teaching; reactor operations. (U.K.)

  17. 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

  18. 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.

  19. 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

  20. 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…

  1. 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...

  2. 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

  3. 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.)

  4. 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)

  5. 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)

  6. 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

  7. 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)

  8. 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)

  9. 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

  10. Training gilts to use a feeder station

    NARCIS (Netherlands)

    Vermeer, H.M.; Kiezebrink, M.C.; Werf, van der J.T.N.; Spoolder, H.A.M.

    2009-01-01

    Group housing of dry sows is compulsory in Europe from 2013 onwards. Many pig farmers who still have to convert to group housing fear the resulting demand on their ability to interact with individual animals. An example of such interaction is the training of gilts to use economically attractive but

  11. 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

  12. 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.)

  13. 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)

  14. 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

  15. 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)

  16. Imperial College Reactor Centre annual report. 1983

    International Nuclear Information System (INIS)

    1984-01-01

    It is reported that the reactor operated reliably during the year with less than half a day of operating time lost by faults or failures. Brief accounts of the 34 research projects at the Centre are given, and a list of teaching experiments or visits is included. These include undergraduate and post-graduate teaching. Commercial requests for irradiations and neutron activation analysis are reported as increasing. (U.K.)

  17. 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…

  18. 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…

  19. 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…

  20. 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…

  1. 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.

  2. 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)

  3. 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

  4. 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.

  5. Extended Station Blackout Analysis for VVER-1000 MWe Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Gaikwad, A. J.; Rao, R. S.; Lakshmanan, S. P.; Gupta, A., E-mail: avinashg@aerb.gov.in [Atomic Energy Regulatory Board, Mumbai (India)

    2014-10-15

    Post Fukushima, the plant behaviour for an extended station black-out (ESBO) scenario with only passive system availability for about 7 days has become imperative. Thermal hydraulic analysis of ESBO with the availability of passive heat removal system (PHRS), passive first stage and second stage hydro accumulators were carried out to demonstrate the design capabilities. Two different cases having primary leak rates of 2.2 tons/hr and 6.6 tons/hr were analyzed to study sustenance of natural circulation. For the study, out of 4 PHRS trains, one PHRS train was assumed to be in failure mode. The objective here is to predict the core cooling capability for a period of 7 days under ESBO conditions with the available water inventories from first and second stage hydroaccumulators only. Over simplified energy balance studies cannot ascertain sustenance of natural circulation in the primary system, steam generators (SGs) and PHRS. The analysis was carried out by using system thermal hydraulic safety code RELAP5/SCDAP/MOD 3.4. It is inferred that the inventory in the first stage accumulators and second stage accumulators compensate the leak and decay heat is removed effectively with the help of passive heat removal systems. It is also observed that even after 7 days of ESBO a large inventory is still available in the second stage accumulators and the primary system remains subcooled. (author)

  6. 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)

  7. 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

  8. 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.

  9. 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.

  10. 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.

  11. 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…

  12. 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

  13. 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.

  14. 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…

  15. 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

  16. Community Colleges Mobilize to Train Cybersecurity Workers

    Science.gov (United States)

    Parry, Marc

    2009-01-01

    If you work at a community college that teaches cybersecurity, it pays to be located in the backyard of a spy agency. Just don't ask Kelly A. Koermer, administrator of the Anne Arundel Community College, what's inside those dark towers at Fort Meade. She points out other highlights of the restricted region: an employees-only exit off the highway,…

  17. 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…

  18. 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

  19. 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 ...

  20. 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

  1. 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

  2. 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)

  3. 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.

  4. 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

  5. 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

  6. 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.

  7. 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

  8. 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

  9. 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

  10. 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.…

  11. Inverness College: Innovations in Aquaculture Training.

    Science.gov (United States)

    Regional Technology Strategies, Inc., Carrboro, NC.

    This paper describes the aquaculture program developed at Inverness College in Scotland. Inverness is located in the Scottish Highlands and serves an area roughly the size of Belgium, but with a population of only 300,000. The regional infrastructure and human capital resources in the Highlands are relatively weak due to inadequate transportation,…

  12. Aerospace Training. Washington's Community and Technical Colleges

    Science.gov (United States)

    Washington State Board for Community and Technical Colleges, 2014

    2014-01-01

    Aerospace is an economic powerhouse that generates jobs and fuels our economy. Washington's community and technical colleges produce the world-class employees needed to keep it that way. With about 1,250 aerospace-related firms employing more than 94,000 workers, Washington has the largest concentration of aerospace expertise in the nation. To…

  13. UK experience of safety requirements for thermal reactor stations

    International Nuclear Information System (INIS)

    Matthews, R.R.; Dale, G.C.; Tweedy, J.N.

    1977-01-01

    The paper summarises the development of safety requirements since the first of the Generating Boards' Magnox reactors commenced operation in 1962 and includes A.G.R. safety together with the preparation of S.G.H.W.R. design safety criteria. It outlines the basic principles originally adopted and shows how safety assessment is a continuing process throughout the life of a reactor. Some description is given of the continuous effort over the years to obtain increased safety margins for existing and new reactors, taking into account the construction and operating experience, experimental information, and more sophisticated computer-aided design techniques which have become available. The main safeguards against risks arising from the Generating Boards' reactors are the achievement of high standards of design, construction and operation, in conjunction with comprehensive fault analyses to ensure that adequate protective equipment is provided. The most important analyses refer to faults which can lead to excessive fuel element temperatures arising from an increase in power or a reduction in cooling capacity. They include the possibility of unintended control rod withdrawal at power or at start-up, coolant flow failure, pressure circuit failure, loss of boiler feed water, and failure of electric power. The paper reviews the protective equipment, and the policy for reactor safety assessments which include application of maximum credible accident philosophy and later the limited use of reliability and probability methods. Some of the Generating Boards' reactors are now more than half way through their planned working lives and during this time safety protective equipment has occasionally been brought into operation, often for spurious reasons. The general performance, of safety equipment is reviewed particularly for incidents such as main turbo-alternator trip, circulator failure, fuel element failures and other similar events, and some problems which have given rise to

  14. 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)

  15. 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)

  16. 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)

  17. 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.

  18. 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)

  19. 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

  20. 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

  1. 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

  2. Training experience at Experimental Breeder Reactor II

    International Nuclear Information System (INIS)

    Driscoll, J.W.; McCormick, R.P.; McCreery, H.I.

    1978-01-01

    The EBR-II Training Group develops, maintains,and oversees training programs and activities associated with the EBR-II Project. The group originally spent all its time on EBR-II plant-operations training, but has gradually spread its work into other areas. These other areas of training now include mechanical maintenance, fuel manufacturing facility, instrumentation and control, fissile fuel handling, and emergency activities. This report describes each of the programs and gives a statistical breakdown of the time spent by the Training Group for each program. The major training programs for the EBR-II Project are presented by multimedia methods at a pace controlled by the student. The Training Group has much experience in the use of audio-visual techniques and equipment, including video-tapes, 35 mm slides, Super 8 and 16 mm film, models, and filmstrips. The effectiveness of these techniques is evaluated in this report

  3. 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)

  4. 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.

  5. 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.…

  6. 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…

  7. 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…

  8. 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.)

  9. 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...

  10. Loviisa Power Station - final disposal of reactor waste

    International Nuclear Information System (INIS)

    Vaajasaari, Marja

    1987-01-01

    This report is based on the earlier published results of research into the properties and function of the candidate backfill materials. The results of the backfill material research, and the sealing concepts presented in the literature have been evaluatedand applied to sealing the Loviisa Reactor Waste Repository taking into consideration the local rock and groundwater conditions. It is emphasised that the applicability of the presented backfill materials and plugs to repository sealing must still be carefully evaluated on the basis of detailed studies and the local environment. 24 refs

  11. 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)

  12. 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

  13. 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

  14. 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

  15. 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.)

  16. 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.)

  17. 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

  18. 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.)

  19. 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

  20. 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

  1. 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…

  2. 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.

  3. 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 ...

  4. 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...

  5. 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…

  6. Training reactor operators and shift supervisors

    International Nuclear Information System (INIS)

    Schwarz, O.

    1980-01-01

    To establish a central institution run by power plant operators to harmonize the training of power plant operating personnel was raised, and put into practice, quite early in the Federal Republic of Germany. A committee devoted to training plant crews, which had been set up by the organizations of German electricity utilities responsible for operating power plants, was changed into a Kraftwerksschule e.V. (Power Plant School) in 1963. This school runs training courses, along standard lines, for operating personnel of thermal power plants, especially for operators and power plant supervisors, in close cooperation with power plant operators. As the peaceful utilization of nuclear energy expanded, also the training of nuclear power plant operators was included in 1969. Since September 1977, the center has had a simulator of a PWR nuclear power plant, since January 1978 also that of a BWR plant available for training purposes. Besides routine operation the trainees also learn to control those incidents which occur only very rarely in real nuclear power plants. (orig./UA) [de

  7. Loviisa power station - final disposal of reactor waste

    International Nuclear Information System (INIS)

    Kankainen, Tuovi

    1986-10-01

    This study forms a part of the research done to assess the suitability of the rapakivi granitic bedrock of the island of Haestholmen, southern Finland, for the management of reactor waste. The aim is to assess the residence time and the origin of the groundwater. In addition, microfossil analyses and conservative ion data were used in deciphering the origin of the groundwater. Fracture mineral studies were limeted to 13 C determinations on two fracture calcites. Groundwater was sampled at several levels of four drill holes, reaching to a depth of some 200 m. The isotopic results were compared with those of water from a percussion drill hole, shallow dug wells, and the Gulf of Finland. The main conclusions are based on 3 H bundances in groundwater, mean residence time of groundwater deduced from 14 C analyses, and stabile isotope content of groundwater, combined with conservative ion data. Additional information was gained from activity ratios of uranium, and sulphur isotope ratios of sulphate. The groundwater of Haestholmen consists of a surface layer of fresh water, and deeper down, of saline water. The fresh water flows and changes rapidly; most of it has precipitated and infiltrated less than 30 years ago. It intermixes with saline water only at the fresh-saline groundwater interface. The saline water underneath the intermediate zone is relatively stagnant. It mainly consists of sea water from the Litorina Sea stage, intermixed with less than 20% glacial melt water. The evolution of the Haestholmen groundwater towards its present stage began during the melting phase of the Weichselian glaciation. Then the groundwater conditions chanced, and infiltration of melt water along open fractures in the bedrock occured. During the Litorian Sea stage heavy saline Litorina sea water slowly infiltrated in the bedrock and displaced the fresh water almost totally. The Haestholmen island rose above the sea level more than 4000 years ago. Then formation of the surficial layer

  8. Demographic Changes of Hispanic Populations and Hispanic Student Enrollment in Texas Community Colleges: A Literature Review

    Science.gov (United States)

    Hernandez, Jack; Slate, John R.; Joyner, Sheila A.

    2015-01-01

    In this literature review, Hispanic demographic changes in the United States and in Texas are examined. Hispanics have accounted for large changes in population, population change, and proportion of population. Accordingly, the literature was reviewed regarding Hispanic immigrants, both authorized and non-authorized immigrants. The issue of…

  9. 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.

  10. 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

  11. 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)

  12. 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)

  13. 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.)

  14. 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

  15. 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)

  16. 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

  17. 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

  18. 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.

  19. 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)

  20. 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.

  1. 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…

  2. 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

  3. 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)

  4. 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

  5. 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

  6. 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

  7. Health physics training at V.C. Summer Nuclear Station

    International Nuclear Information System (INIS)

    Blue, L.A.; Bellmore, J.R.; Shultz, P.A.

    1981-01-01

    Health Physics training for radiation workers and Health Physics Specialists continues to receive full attention by regulatory agencies such as the NRC and ANI. Guidance for such training continues to develop in a direction which forces utilities to continuously increase the quality and quantity of their Health Physics Training Program. This occurs at a time when our rapidly growing industry is placing greatly increased demands on the available work force of highly trained nuclear workers

  8. 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

  9. 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)

  10. 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.

  11. 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)

  12. 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)

  13. 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

  14. 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.

  15. 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

  16. 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.

  17. 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.)

  18. 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

  19. 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

  20. Intercultural Communication Competence: Advising International Students in a Texas Community College

    Science.gov (United States)

    Zhang, Yi

    2015-01-01

    Academic advising has long been considered a critical factor to student success. With a qualitative, phenomenological research design, this study was undertaken to better understand the lived experiences of academic advisors in communicating with international students in a community college context. Intercultural communication competence was used…

  1. Achieving the Dream: A Look at Hispanic Student Success at Community Colleges in Texas

    Science.gov (United States)

    Williams, Audrey R.

    2013-01-01

    In the last decade, higher education institutions have come under attack for their inability to enhance graduation rates. Although community colleges are known for their open-door enrollment policy, they are currently challenged to improve student success. This study was designed to determine which strategies have been most effective in…

  2. (Re)Defining Masculinity through Peer Interactions: Latino Men in Texas Community Colleges

    Science.gov (United States)

    Sáenz, Victor B.; Mayo, Jeff R.; Miller, Ryan A.; Rodriguez, Sarah L.

    2015-01-01

    This study uses a phenomenological approach to examine how Latino male students at community colleges engage with their male peers. The analysis utilizes a male gender role conflict (MGRC) framework and employs cultural conceptions of masculinity, specifically machismo and caballerismo. Practitioners and researchers might leverage positive aspects…

  3. 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

  4. 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

  5. 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.

  6. 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

  7. 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.

  8. Light Water Reactor Sustainability Program: Analysis of Pressurized Water Reactor Station Blackout Caused by External Flooding Using the RISMC Toolkit

    Energy Technology Data Exchange (ETDEWEB)

    Smith, Curtis [Idaho National Lab. (INL), Idaho Falls, ID (United States); Mandelli, Diego [Idaho National Lab. (INL), Idaho Falls, ID (United States); Prescott, Steven [Idaho National Lab. (INL), Idaho Falls, ID (United States); Alfonsi, Andrea [Idaho National Lab. (INL), Idaho Falls, ID (United States); Rabiti, Cristian [Idaho National Lab. (INL), Idaho Falls, ID (United States); Cogliati, Joshua [Idaho National Lab. (INL), Idaho Falls, ID (United States); Kinoshita, Robert [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2014-08-01

    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 impact of these factors on the safety of the plant, the Risk Informed Safety Margin Characterization (RISMC) project aims to provide insight to decision makers through a series of simulations of the plant dynamics for different initial conditions (e.g., probabilistic analysis and uncertainty quantification). This report focuses, in particular, on the application of a RISMC detailed demonstration case study for an emergent issue using the RAVEN and RELAP-7 tools. This case study looks at the impact of a couple of challenges to a hypothetical pressurized water reactor, including: (1) a power uprate, (2) a potential loss of off-site power followed by the possible loss of all diesel generators (i.e., a station black-out event), (3) and earthquake induces station-blackout, and (4) a potential earthquake induced tsunami flood. The analysis is performed by using a set of codes: a thermal-hydraulic code (RELAP-7), a flooding simulation tool (NEUTRINO) and a stochastic analysis tool (RAVEN) – these are currently under development at the Idaho National Laboratory.

  9. 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…

  10. 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...

  11. 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.

  12. 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

  13. 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,…

  14. 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…

  15. 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…

  16. 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…

  17. 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

  18. Equipment for neutron measurements at VR-1 Sparrow training reactor

    International Nuclear Information System (INIS)

    Kolros, Antonin; Huml, Ondrej; Kos, Josef

    2008-01-01

    Full text: The VR-1 Sparrow training reactor is the experimental nuclear facility especially employed for education and teaching of students from different technical universities in the Czech Republic and other countries. Since 2005 the uniform all-purpose devices EMK310 have been used for measurement at reactor laboratory with different type of gas filled neutron detectors. The neutron detection system are employed for reactivity measurement, control rod calibration, critical experiment, study of delayed neutrons, study of nuclear reactor dynamics and study of detection systems dead time. The small dimension isotropic detectors are especially used for measurement of thermal neutron flux distribution inside the reactor core. The EMK-310 is a high performance, portable, three-channel fast amplitude analyzer designed for counting applications. It was developed for nuclear applications and made in close co-operation with firm TEMA Ltd. The precise rack eliminates electromagnetic disturbance and contains the control unit and four modules. The modules of high voltage supply and amplifier for gas filled detectors or scintillation probes are used in basic configuration. Software is tailored specifically to the reactor measurement and allows full online control. For applications involving the study of signals that may vary with the time, example study of delayed neutrons or nuclear reactor dynamics, the EMK-310 provides a Multichannel Scaling (MCS) acquisition mode. MCS dwell time can be set from 2 ms. Now, the new generation of digital multichannel analyzers DA310 is introduced. They have similarly attributes as EMK310 but the output information of unipolar signals from detector is more complete. The pipeline A/D converter with field programmable gate array (FPGA) is the hearth of the DA310 device. The resolution is 12 bits (4096 channels); the sample frequency is 80 MHz. The application for the neutron noise analysis is supposed. The correction method for non linearity

  19. 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

  20. 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

  1. Technology, safety, and costs of decommissioning a reference pressurized water reactor power station

    International Nuclear Information System (INIS)

    Smith, R.I.; Konzek, G.J.; Kennedy, W.E. Jr.

    1978-05-01

    Safety and cost information was developed for the conceptual decommissioning of a large [1175 MW(e)] pressurized water reactor (PWR) power station. Two approaches to decommissioning, Immediate Dismantlement and Safe Storage with Deferred Dismantlement, were studied to obtain comparisons between costs, occupational radiation doses, potential radiation dose to the public, and other safety impacts. Immediate Dismantlement was estimated to require about six years to complete, including two years of planning and preparation prior to final reactor shutdown, at a cost of $42 million, and accumulated occupational radiation dose, excluding transport operations, of about 1200 man-rem. Preparations for Safe Storage were estimated to require about three years to complete, including 1 1 / 2 years for planning and preparation prior to final reactor shutdown, at a cost of $13 million and an accumulated occupational radiation dose of about 420 man-rem. The cost of continuing care during the Safe Storage period was estimated to be about $80 thousand annually. Accumulated occupational radiation dose during the Safe Storage period was estimated to range from about 10 man-rem for the first 10 years to about 14 man-rem after 30 years or more. The cost of decommissioning by Safe Storage with Deferred Dismantlement was estimated to be slightly higher than Immediate Dismantlement. Cost reductions resulting from reduced volumes of radioactive material for disposal, due to the decay of the radioactive containments during the deferment period, are offset by the accumulated costs of surveillance and maintenance during the Safe Storage period

  2. 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)

  3. Annual progress report of the University of Florida Training Reactor September 1, 1979-August 31, 1980

    International Nuclear Information System (INIS)

    Diaz, N.J.

    1980-11-01

    Reported are: reactor operation, modifications, maintenance and tests, changes to technical specifications and standard operating procedures, radioactive releases and environmental surveillance, and training utilization

  4. 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)

  5. Environmental Assessment Addressing the 301st Fighter Wing Managed Airspace, Naval Air Station Joint Reserve Base, Fort Worth, Texas

    Science.gov (United States)

    2009-05-01

    Salle County McMullen County Terrell County Blanco County Comal County Texas Oklahoma Dallas- Ft. Worth San Antonio Austin Tulsa Oklahoma City Abilene...County Young County Crockett County Glasscock County Irion County Midland County Brown County Reagan County Sterling County Terrell County Upton...7909 Karl May Drive Waco, TX 76708 Margaret Wood Brown County Clerk 200 South Broadway Brownwood, TX 76801 Jo Ann Hale Coleman County

  6. Integrating Space Flight Resource Management Skills into Technical Lessons for International Space Station Flight Controller Training

    Science.gov (United States)

    Baldwin, Evelyn

    2008-01-01

    The Johnson Space Center s (JSC) International Space Station (ISS) Space Flight Resource Management (SFRM) training program is designed to teach the team skills required to be an effective flight controller. It was adapted from the SFRM training given to Shuttle flight controllers to fit the needs of a "24 hours a day/365 days a year" flight controller. More recently, the length reduction of technical training flows for ISS flight controllers impacted the number of opportunities for fully integrated team scenario based training, where most SFRM training occurred. Thus, the ISS SFRM training program is evolving yet again, using a new approach of teaching and evaluating SFRM alongside of technical materials. Because there are very few models in other industries that have successfully tied team and technical skills together, challenges are arising. Despite this, the Mission Operations Directorate of NASA s JSC is committed to implementing this integrated training approach because of the anticipated benefits.

  7. 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)

  8. 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.

  9. 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)

  10. 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)

  11. Final Report: Northern Virginia Community College Training for Biotechnology Workers

    Energy Technology Data Exchange (ETDEWEB)

    Weiss, Johanna V

    2010-05-31

    The intent of this project was to expand Northern Virginia Community College's capability to offer training to support the Biotechnology Industry in the northern Virginia region. The general goal of this project was to create a College Biotechnology Program; specific goals of the project were to a) design curricula/courses to prepare students to become entry-level lab technicians, b) redesign and equip lab space to better suit the needs of the program, c) develop partnerships with the local industry through outreach and the formation on an advisory board, d) recruit students into the program, and e) provide instructional support for local high school teachers. At the end of the grant period, NOVA has successfully created two new curricula in biotechnology: an Associate of Applied Science (A.A.S.) in Biotechnology (initiated in Fall 2008) and a Career Studies Certificate for Biotechnology Lab Technicians (to be initiated in Fall 2010). These curricula were designed with advice from an external advisory committee which is comprised of representatives from industry, transfer institutions and high school administrators. To date, almost all courses have been designed and piloted; the equipment needed for the courses and the initial supplies were paid for by the grant as was the re-modeling of some lab space to be used for the biotech courses. In order to market the program, the NOVA Biotech Program has also established relationships with the local high schools. Presentations were given at several local high schools and on-site workshops were held for high school students and teachers. As a result, close to 1000 students have attended program open houses, presentations within the high schools, or workshops held in the summer. Over 100 teachers have received information and/or training in biotechnology. These outreach efforts as well as high quality curricula have started to attract a number of students to the program – for example, there are currently 70 students

  12. 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),...

  13. 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

  14. 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

  15. 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

  16. 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.

  17. 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.

  18. 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.)

  19. 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)

  20. Experience with reactor power cutback system at Palo Verde nuclear generating station

    International Nuclear Information System (INIS)

    Chari, D.R.; Rec, J.R.; Simoni, L.P.; Eimar, R.L.; Sowers, G.W.

    1987-01-01

    Palo Verde Nuclear Generating Station (PVNGS) is a three unit site which illustrates System 80 nuclear steam supply system (NSSS) design. The System 80 NSSS is the Combustion Engineering (C-E) standard design rated at 3817 Mwth. PVNGS Units 1 and 2 achieved commercial operation on February 13, 1986 and September 22, 1986, respectively, while Unit 3 has a forecast date for commercial operation in the third quarter of 1987. The System 80 design incorporates a reactor power cutback system (RPCS) feature which reduces plant trips caused by two common initiating events: loss of load/turbine trip (LOL) and loss of one main feedwater pump (LOMFWP). The key design objective of the RPCS is to improve overall plant availability and performance, while minimizing challenges to the plant safety system

  1. Experience in surveillance of the prestress of concrete reactor vessels in Wylfa nuclear power station

    International Nuclear Information System (INIS)

    Dawson, P.; Paton, A.A.; Walsh, S.R.

    1989-01-01

    This paper describes experience gained in the in-service surveillance of the prestressing system for the prestressed concrete reactor vessels (PCRVs) at Wylfa nuclear power station. The paper gives details of results for the prestressing system obtained from the statutory in-service inspection program of the PCRVs. The program includes a detailed examination of a selection of prestressing tendon anchorages, anchorage load checks using a lift-off technique on a one percent sample of tendons and corrosion inspection of samples of prestressing strand and determination of their mechanical properties. The results obtained from the above in-service inspections have shown that the prestressing system continues to function within its design limits

  2. Forced vibration tests on the reactor building of a nuclear power station, 1

    International Nuclear Information System (INIS)

    Takeda, Toshikazu; Tsunoda, Tomohiko; Wakamatsu, Kunio; Kaneko, Masataka; Nakamura, Mitsuru; Kunoh, Toshio; Murahashi, Hisahiro

    1988-01-01

    Tsuruga Unit No.2 Nuclear Power Station of the Japan Atomic Power Company is the first PWR-type 4-loop plant constructed in Japan with a prestressed concrete containment vessel (PCCV). This report describes forced vibration tests carried out on the reactor building of this plant. The following were obtained as results: (1) The results of the forced vibration tests corresponded well on the whole with design values. (2) The vibration characteristics of the PCCV observed in the tests after prestressing are no different from the ones before prestressing. This shows that the vibration properties of the PCCV are practically independent of prestressing loads. (3) A seismic response analysis of the design basis earthquake was made on the design model reflecting the test results. The seismic safety of the plant was confirmed by this analysis. (author)

  3. 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.

  4. 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)

  5. 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

  6. 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.)

  7. 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.

  8. 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.

  9. A STRONGLY COUPLED REACTOR CORE ISOLATION COOLING SYSTEM MODEL FOR EXTENDED STATION BLACK-OUT ANALYSES

    Energy Technology Data Exchange (ETDEWEB)

    Zhao, Haihua [Idaho National Laboratory; Zhang, Hongbin [Idaho National Laboratory; Zou, Ling [Idaho National Laboratory; Martineau, Richard Charles [Idaho National Laboratory

    2015-03-01

    The reactor core isolation cooling (RCIC) system in a boiling water reactor (BWR) provides makeup cooling water to the reactor pressure vessel (RPV) when the main steam lines are isolated and the normal supply of water to the reactor vessel is lost. The RCIC system operates independently of AC power, service air, or external cooling water systems. The only required external energy source is from the battery to maintain the logic circuits to control the opening and/or closure of valves in the RCIC systems in order to control the RPV water level by shutting down the RCIC pump to avoid overfilling the RPV and flooding the steam line to the RCIC turbine. It is generally considered in almost all the existing station black-out accidents (SBO) analyses that loss of the DC power would result in overfilling the steam line and allowing liquid water to flow into the RCIC turbine, where it is assumed that the turbine would then be disabled. This behavior, however, was not observed in the Fukushima Daiichi accidents, where the Unit 2 RCIC functioned without DC power for nearly three days. Therefore, more detailed mechanistic models for RCIC system components are needed to understand the extended SBO for BWRs. As part of the effort to develop the next generation reactor system safety analysis code RELAP-7, we have developed a strongly coupled RCIC system model, which consists of a turbine model, a pump model, a check valve model, a wet well model, and their coupling models. Unlike the traditional SBO simulations where mass flow rates are typically given in the input file through time dependent functions, the real mass flow rates through the turbine and the pump loops in our model are dynamically calculated according to conservation laws and turbine/pump operation curves. A simplified SBO demonstration RELAP-7 model with this RCIC model has been successfully developed. The demonstration model includes the major components for the primary system of a BWR, as well as the safety

  10. 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.)

  11. 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.)

  12. 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)

  13. 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

  14. 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…

  15. Results from Accelerator Driven TRIGA Reactor Experiments at The University of Texas at Austin

    International Nuclear Information System (INIS)

    O'Kelly, S.; Braisted, J.; Krause, M.; Welch, L.

    2008-01-01

    Accelerator Driven Transmutation of High-Level Waste (ATW) is one possible solution to the fuel reprocessing back-end problem for the disposal of high level waste such as minor actinides (Am, Np or Cm) and long-lived fission products. International programs continue to support research towards the eventual construction and operation of a proton accelerator driven spallation neutron source coupled to a subcritical 'neutron amplifier' for more efficient HLW transmutation. This project was performed under DOE AFCI Reactor-Accelerator Coupling Experiments (RACE). A 20 MeV Electron Linac was installed in the BP no 5 cave placing neutron source adjacent to an offset reactor core to maximize neutron coupling with available systems. Asymmetric neutron injection 'wasted' neutrons due to high leakage but sufficient neutrons were available to raise reactor power to ∼100 watts. The Linac provided approximately 100 mA but only 50% reached target. The Linac cooling system could not prevent overheating at frequencies over 200 Hz. The Linac electron beam had harmonics of primary frequency and periodic low frequency pulse intensity changes. Neutron detection using fission chambers in current mode eliminated saturation dead time and produced better sensitivity. The Operation of 'dual shielded' fission chambers reduced electron noise from linac. Benchmark criticality calculation using start-up data showed that the MCNPX model overestimates reactivity. TRIGA core was loaded to just slightly supercritical by adding graphite elements and measuring reactivity of $0.037. MCNPX modeled TRIGA core with and without graphite to arrive at 'true' measured subcritical multiplication of 0.998733± 0.00069. Thus, Alpha for the UT-RACE TRIGA core was approximately 155.99 s -1 . The Stochastic Feynman-Alpha Method (SFM) accuracy was evaluated during transients and reactivity changes. SFM was shown to be a potential real-time method of reactivity determination in future ADSS but requires stable

  16. 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)

  17. 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)

  18. 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...

  19. Chernobyl reactor accident. A documentation submitted by the Deutsche Welle radio station. Der Fall Tschernobyl. Eine Dokumentation der Deutschen Welle

    Energy Technology Data Exchange (ETDEWEB)

    1986-01-01

    The documentation abstracted contains a complete survey of the broadcasts transmitted by the Russian wire service of the Deutsche Welle radio station between April 28 and May 15, 1986 on the occasion of the Chernobyl reactor accident. Access is given to extracts of the remarkable eastern and western echoes on the broadcasts of the Deutsche Welle.

  20. 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

  1. 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.

  2. 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.)

  3. 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.

  4. 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…

  5. 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)

  6. 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.…

  7. 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.

  8. 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.

  9. 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.

  10. 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

  11. 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

  12. 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)

  13. Work Ethics Training: Reflections of Technical College Students

    Science.gov (United States)

    Wilson, Sandy

    2017-01-01

    Ample research exists on ethics in the workplace and skills college graduates should have to seek and attain long-term gainful employment. The literature has provided some insight into the understanding of ethical behavior as reported by students and employers; however a gap exists in research which documents college student experiences during…

  14. Achievement Motivation and Stress Inoculation Training: Coping through College

    Science.gov (United States)

    Ayers, Sharonda C.

    2010-01-01

    The benefits of college education are extensive. In addition to the obvious cognitive advantages, those who obtain a college education experience economic, health, family and neighborhood benefits. These benefits are felt not only within the generation of the individual who completed their degree; but inter-generationally as well. The ability to…

  15. 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.

  16. 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

  17. Station black out concurrent with PORV failure using a Generic Pressurized Water Reactor simulator

    International Nuclear Information System (INIS)

    Zubair, Muhammad; Ababneh, Ahmad; Ishag, Ahmed

    2017-01-01

    Highlights: •SBO accident simulation by using a GPWR simulator. •Normal SBO, and SBO with additional failure of Pilot Operated Relief Valve. •The research results will provide help in future for better understanding of accidents in APR 1400 reactors. -- Abstract: Station Black Out (SBO) is an accident situation that refers to the total loss of offsite power, along with the unavailability of onsite power, which results from the failure of all Diesel Generators (DG). Probabilistic Safety Assessment (PSA) spans a number of methods that include modeling of event-trees and simulation of accidents scenarios, aimed to quantify risk and ensure safety in nuclear power plants. PSA also deals with prediction of future accidents and calculation of failure probabilities that has been done in this study. A SBO accident was simulated using a Generic Pressurized Water Reactor (GPWR) simulator from KEYMASTER™. The accident scenario consists of two stages; the first stage belongs to normal SBO, in second stage SBO accident with additional failure of Pilot Operated Relief Valve (PORV) opens and it stuck open has been considered for the pressurizer. A comparison of the two stages was made by plotting variables on the same graph. The research has been carried out to analyze the hot and cold leg temperatures, Steam Generator (SG) pressure, SG Narrow Range (NR) level, SG water-level-percentage (PCT), Pressurizer pressure, Fuel Temperature, and containment pressure. Simulation results suggest that failure in closing PORV has negligible impact on hot and cold leg temperatures, results in an overall less pressure in SGs, but higher pressure in the pressurizer. Additionally, containment pressure did not exceed the maximum approved pressure of 8.7 kg/cm 2 , but was approaching the Advanced Pressurized Water Reactor’s (APR-1400) design pressure of 4.218 kg/cm 2 . Finally, nuclear fuel temperature exceeded Probabilistic Risk Assessment (PRA) limit of 726.7 °C for both scenarios. The

  18. Measurement station for interim inspections of Lightbridge metallic fuel rods at the Halden Boiling Water Reactor

    Science.gov (United States)

    Hartmann, C.; Totemeier, A.; Holcombe, S.; Liverud, J.; Limi, M.; Hansen, J. E.; Navestad, E. AB(; )

    2018-01-01

    Lightbridge Corporation has developed a new Uranium-Zirconium based metallic fuel. The fuel rods aremanufactured via a co-extrusion process, and are characterized by their multi-lobed (cruciform-shaped) cross section. The fuel rods are also helically-twisted in the axial direction. Two experimental fuel assemblies, each containing four Lightbridge fuel rods, are scheduled to be irradiated in the Halden Boiling Water Reactor (HBWR) starting in 2018. In addition to on-line monitoring of fuel rod elongation and critical assembly conditions (e.g. power, flow rates, coolant temperatures, etc.) during the irradiation, several key parameters of the fuel will be measured out-of-core during interim inspections. An inspection measurement station for use in the irradiated fuel handling compartment at the HBWR has therefore been developed for this purpose. The multi-lobed cladding cross section combined with the spiral shape of the Lightbridge metallic fuel rods requires a high-precision guiding system to ensure good position repeatability combined with low-friction guiding. The measurement station is equipped with a combination of instruments and equipment supplied from third-party vendors and instruments and equipment developed at Institute for Energy Technology (IFE). Two sets of floating linear voltage differential transformer (LVDT) pairs are used to measure swelling and diameter changes between the lobes and the valleys over the length of the fuel rods. Eddy current probes are used to measure the thickness of oxide layers in the valleys and on the lobe tips and also to detect possible surface cracks/pores. The measurement station also accommodates gamma scans. Additionally, an eddy-current probe has been developed at IFE specifically to detect potential gaps or discontinuities in the bonding layer between the metallic fuel and the Zirconium alloy cladding. Potential gaps in the bonding layer will be hidden behind a 0.5-1.0 mm thick cladding wall. It has therefore been

  19. Subway platform air quality: Assessing the influences of tunnel ventilation, train piston effect and station design

    Science.gov (United States)

    Moreno, T.; Pérez, N.; Reche, C.; Martins, V.; de Miguel, E.; Capdevila, M.; Centelles, S.; Minguillón, M. C.; Amato, F.; Alastuey, A.; Querol, X.; Gibbons, W.

    2014-08-01

    A high resolution air quality monitoring campaign (PM, CO2 and CO) was conducted on differently designed station platforms in the Barcelona subway system under: (a) normal forced tunnel ventilation, and (b) with daytime tunnel ventilation systems shut down. PM concentrations are highly variable (6-128 μgPM1 m-3, 16-314 μgPM3 m-3, and 33-332 μgPM10 m-3, 15-min averages) depending on ventilation conditions and station design. Narrow platforms served by single-track tunnels are heavily dependent on forced tunnel ventilation and cannot rely on the train piston effect alone to reduce platform PM concentrations. In contrast PM levels in stations with spacious double-track tunnels are not greatly affected when tunnel ventilation is switched off, offering the possibility of significant energy savings without damaging air quality. Sampling at different positions along the platform reveals considerable lateral variation, with the greatest accumulation of particulates occurring at one end of the platform. Passenger accesses can dilute PM concentrations by introducing cleaner outside air, although lateral down-platform accesses are less effective than those positioned at the train entry point. CO concentrations on the platform are very low (≤1 ppm) and probably controlled by ingress of traffic-contaminated street-level air. CO2 averages range from 371 to 569 ppm, changing during the build-up and exchange of passengers with each passing train.

  20. 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)

  1. 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)

  2. 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…

  3. 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,…

  4. 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…

  5. 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.

  6. 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.

  7. 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)

  8. 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

  9. 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

  10. 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.

  11. Technology, safety and costs of decommissioning a reference pressurized water reactor power station. Classification of decommissioning wastes. Addendum 3

    International Nuclear Information System (INIS)

    Murphy, E.S.

    1984-09-01

    The radioactive wastes expected to result from decommissioning of the reference pressurized water reactor power station are reviewed and classified in accordance with 10 CFR 61. The 17,885 cubic meters of waste from DECON are classified as follows: Class A, 98.0%; Class B, 1.2%; Class C, 0.1%. About 0.7% (133 cubic meters) of the waste would be generally unacceptable for disposal using near-surface disposal methods

  12. Technology, safety and costs of decommissioning a Reference Boiling Water Reactor Power Station. Main report. Volume 1

    Energy Technology Data Exchange (ETDEWEB)

    Oak, H.D.; Holter, G.M.; Kennedy, W.E. Jr.; Konzek, G.J.

    1980-06-01

    Technology, safety and cost information is given for the conceptual decommissioning of a large (1100MWe) boiling water reactor (BWR) power station. Three approaches to decommissioning, immediate dismantlement, safe storage with deferred dismantlement and entombment, were studied to obtain comparisons between costs, occupational radiation doses, potential dose to the public and other safety impacts. It also shows the sensitivity of decommissioning safety and costs to the power rating of a BWR in the range of 200 to 1100 MWe.

  13. Confirmatory Survey Results for the Reactor Building Dome Upper Structural Surfaces, Rancho Saco Nuclear Generating Station, Herald, California

    International Nuclear Information System (INIS)

    Wade C. Adams

    2006-01-01

    Results from a confirmatory survey of the upper structural surfaces of the Reactor Building Dome at the Rancho Seco Nuclear Generating Station (RSNGS) performed by the Oak Ridge Institute for Science and Education for the NRC. Also includes results of interlaboratory comparison analyses on several archived soil samples that would be provided by RSNGS personnel. The confirmatory surveys were performed on June 7 and 8, 2006

  14. Enhancements to the SLOWPOKE-2 nuclear research reactor at the Royal Military College of Canada

    Energy Technology Data Exchange (ETDEWEB)

    Hungler, P.C.; Andrews, M.T.; Weir, R.D.; Nielson, K.S.; Chan, P.K.; Bennett, L.G.I., E-mail: paul.hungler@rmc.ca [Royal Military College of Canada, Kingston, Ontario (Canada)

    2014-07-01

    In 1985 a Safe Low Power C(K)ritical Experiment (SLOWPOKE) nuclear research reactor was installed at the Royal Military College of Canada (RMCC). The reactor at nominally 20 kW thermal was named SLOWPOKE-2 and the core was designed to have a total of 198 fuel pins with Low Enriched Uranium (LEU) fuel (19.89% U-235). Installation of the reactor was intended to provide an education tool for members of the Canadian Armed Forces (CAF) and an affordable neutron source for the application of neutron activation analysis (NAA) and radioisotope production. Today, the SLOWPOKE-2 at RMCC continues to be a key education tool for undergraduate and post-graduate students and successfully conducts NAA and isotope production as per its original design intent. RMCC has significantly upgraded the facility and instruments to develop capabilities such as delayed neutron and gamma counting (DNGC) and neutron imaging, including 2D thermal neutron radiography and 3D thermal neutron tomography. These unique nuclear capabilities have been applied to relevant issues in the CAF. The analog control system originally installed in 1985 has been removed and replaced in 2001 by the SLOWPOKE Integrated Reactor Control and Instrumentation System (SIRCIS) which is a digital controller. This control system continues to evolve with SIRCIS V2 currently in operation. The continual enhancement of the facility, instruments and systems at the SLOWPOKE-2 at RMCC will be discussed, including an update on RMCC's refueling plan. (author)

  15. Enhancements to the SLOWPOKE-2 nuclear research reactor at the Royal Military College of Canada

    International Nuclear Information System (INIS)

    Hungler, P.C.; Andrews, M.T.; Weir, R.D.; Nielson, K.S.; Chan, P.K.; Bennett, L.G.I.

    2014-01-01

    In 1985 a Safe Low Power C(K)ritical Experiment (SLOWPOKE) nuclear research reactor was installed at the Royal Military College of Canada (RMCC). The reactor at nominally 20 kW thermal was named SLOWPOKE-2 and the core was designed to have a total of 198 fuel pins with Low Enriched Uranium (LEU) fuel (19.89% U-235). Installation of the reactor was intended to provide an education tool for members of the Canadian Armed Forces (CAF) and an affordable neutron source for the application of neutron activation analysis (NAA) and radioisotope production. Today, the SLOWPOKE-2 at RMCC continues to be a key education tool for undergraduate and post-graduate students and successfully conducts NAA and isotope production as per its original design intent. RMCC has significantly upgraded the facility and instruments to develop capabilities such as delayed neutron and gamma counting (DNGC) and neutron imaging, including 2D thermal neutron radiography and 3D thermal neutron tomography. These unique nuclear capabilities have been applied to relevant issues in the CAF. The analog control system originally installed in 1985 has been removed and replaced in 2001 by the SLOWPOKE Integrated Reactor Control and Instrumentation System (SIRCIS) which is a digital controller. This control system continues to evolve with SIRCIS V2 currently in operation. The continual enhancement of the facility, instruments and systems at the SLOWPOKE-2 at RMCC will be discussed, including an update on RMCC's refueling plan. (author)

  16. Aerial radiological survey of the Comanche Peak Steam Electric Station and surrounding area, Glen Rose, Texas. Date of Survey: March 1982

    International Nuclear Information System (INIS)

    1982-12-01

    An aerial radiological survey was performed from 1 to 9 March 1982 over a 260-square-kilometer area centered on the Comanche Peak Steam Electric Station located in Somervell County, Texas. The survey was conducted by the Energy Measurements Group of EG and G for the US Nuclear Regulatory Commission. All gamma ray data were collected by flying parallel lines spaced 152 meters (500 feet) apart at an altitude of 91 meters (300 feet) above ground level. Count rates obtained from the aerial platform were converted to total exposure rates at 1 meter above the ground and are presented in the form of an isoradiation contour map. The observed exposure rates ranged from 6 to 12 microroentgens per hour (μR/h), with the average background ranging from 6 to 8 μR/h. These values include an estimated cosmic ray contribution of 3.8 μR/h. The exposure rates obtained from ground-based measurements taken in typical background locations within the survey area displayed positive agreement with the aerial data

  17. Investigation of ground-water contamination at a drainage ditch, Installation Restoration Site 4, Naval Air Station Corpus Christi, Corpus Christi, Texas, 2005–06

    Science.gov (United States)

    Vroblesky, Don A.; Casey, Clifton C.

    2007-01-01

    The U.S. Geological Survey, in cooperation with the Naval Facilities Engineering Command Southeast, used newly developed sampling methods to investigate ground-water contamination by chlorobenzenes beneath a drainage ditch on the southwestern side of Installation Restoration Site 4, Naval Air Station Corpus Christi, Corpus Christi, Texas, during 2005-06. The drainage ditch, which is a potential receptor for ground-water contaminants from Installation Restoration Site 4, intermittently discharges water to Corpus Christi Bay. This report uses data from a new type of pore-water sampler developed for this investigation and other methods to examine the subsurface contamination beneath the drainage ditch. Analysis of ground water from the samplers indicated that chlorobenzenes (maximum detected concentration of 160 micrograms per liter) are present in the ground water beneath the ditch. The concentrations of dissolved oxygen in the samples (less than 0.05-0.4 milligram per liter) showed that the ground water beneath and near the ditch is anaerobic, indicating that substantial chlorobenzene biodegradation in the aquifer beneath the ditch is unlikely. Probable alternative mechanisms of chlorobenzene removal in the ground water beneath the drainage ditch include sorption onto the organic-rich sediment and contaminant depletion by cattails through uptake, sorption, and localized soil aeration.

  18. 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

  19. 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

  20. 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)

  1. 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

  2. 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)

  3. 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

  4. 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.

  5. 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.

  6. Aspects Fostering the Programming of Today's College Radio Station: The Advisor's Perspective.

    Science.gov (United States)

    Sauls, Samuel J.

    To help ascertain leadership, guidance, and capabilities of the station advisor (those who foster the efforts of their student staffs), this paper provides an overview of programming elements discussing such topics as programming philosophy, general formats, and legal and ethical issues. It states that those advising the campus radio station can…

  7. Mentoring SFRM: A New Approach to International Space Station Flight Controller Training

    Science.gov (United States)

    Huning, Therese; Barshi, Immanuel; Schmidt, Lacey

    2008-01-01

    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 two-pronged 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. Methods: A mentor works with an operator throughout the training flow. Inserted into the training flow are guided-discussion sessions and on-the-job observation opportunities focusing on specific SFRM skills, including: situational leadership, conflict management, stress management, cross-cultural awareness, self care and team care while on-console, communication, workload management, and situation awareness. The mentor and operator discuss the science and art behind the skills, cultural effects on skills applications, recognition of good and bad skills applications, recognition of how skills application changes subtly in different situations, and individual goals and techniques for improving skills. Discussion: This mentoring program provides an additional means of transferring SFRM knowledge compared to traditional CRM training programs. Our future endeavors in training SFRM skills (as well as other organization s) may benefit from adding team performance skills mentoring. This paper

  8. New Dimensions in Language Training: The Dartmouth College Experiment.

    Science.gov (United States)

    Rassias, John A.

    The expanded foreign study and foreign language programs offered at Dartmouth are examined with emphasis on the influence of Peace Corps language programs during the last half-dozen years on American college campuses. The impact of the programs at Dartmouth since 1964 is discussed in terms of: (1) a brief history of language instruction at…

  9. Between college and work in the Further Education and Training ...

    African Journals Online (AJOL)

    Hennie

    South African Journal of Education, Volume 35, Number 1, February 2015. 1. Art. # 953, 8 ... perspectives of lecturers and supervisors about student learning in their college programmes and their work experience are translated ..... survey data revealed that very little industry ... projects, so I see this as one of my 'big' roles.”.

  10. "Taking Training to the Next Level": The American College of Surgeons Committee on Residency Training Survey.

    Science.gov (United States)

    Damewood, Richard B; Blair, Patrice Gabler; Park, Yoon Soo; Lupi, Linda K; Newman, Rachel Williams; Sachdeva, Ajit K

    The American College of Surgeons (ACS) appointed a committee of leaders from the ACS, Association of Program Directors in Surgery, Accreditation Council for Graduate Medical Education, and American Board of Surgery to define key challenges facing surgery resident training programs and to explore solutions. The committee wanted to solicit the perspectives of surgery resident program directors (PDs) given their pivotal role in residency training. Two surveys were developed, pilot tested, and administered to PDs following Institutional Review Board approval. PDs from 247 Accreditation Council for Graduate Medical Education-accredited general surgery programs were randomized to receive 1 of the 2 surveys. Bias analyses were conducted, and adjusted Pearson χ 2 tests were used to test for differences in response patterns by program type and size. All accredited general surgery programs in the United States were included in the sampling frame of the survey; 10 programs with initial or withdrawn accreditation were excluded from the sampling frame. A total of 135 PDs responded, resulting in a 54.7% response rate (Survey A: n = 67 and Survey B: n = 68). The respondent sample was determined to be representative of program type and size. Nearly 52% of PD responses were from university-based programs, and 41% had over 6 residents per graduating cohort. More than 61% of PDs reported that, compared to 10 years ago, both entering and graduating residents are less prepared in technical skills. PDs expressed significant concerns regarding the effect of duty-hour restrictions on the overall preparation of graduating residents (61%) and quality of patient care (57%). The current 5-year training structure was viewed as needing a significant or extensive increase in opportunities for resident autonomy (63%), and the greatest barriers to resident autonomy were viewed to be patient preferences not to be cared for by residents (68%), liability concerns (68%), and Centers for Medicare and

  11. Becoming a teacher at teacher training colleges in Kenya

    DEFF Research Database (Denmark)

    Dahl, Kari

    Paper presented at International Conference "Health Education and Teacher Training in Kenya" at Sarova Stanley Hotel 8. December 2010, Nairobi, Kenya.......Paper presented at International Conference "Health Education and Teacher Training in Kenya" at Sarova Stanley Hotel 8. December 2010, Nairobi, Kenya....

  12. VPI-NECM, Nuclear Engineering Program Collection for College Training

    International Nuclear Information System (INIS)

    Honomichl, Jiri; Kulikowska, Teresa; Szczesna, Barbara

    1991-01-01

    1 - Description of problem or function: The VPI Modules consist of 6 independent programs designed to calculate: module FARCON - neutron slowing down and epithermal group constants, module SLOCON - thermal neutron spectrum and group constants, module DISFAC - slow neutron disadvantage factors, module ODOG - solution of a one group neutron diffusion equation, module ODMUG - three group critically problem, module FUELBURN - fuel burnup in slow neutron fission reactors. 2 - Method of solution: Module FARCON solves the diffusion equation for a homogeneous medium composed of N isotopes, in 33 groups in fast and resonance energy region. The solution in the thermal energy region carried out by module SLOCON is based on the Wigner-Wilkins approximation and applies the Runge-Kutta method. The burnup calculations are carried out in 3 energy groups. Only Xe-135 and Sm-149 are treated directly. All the other fission products are represented by 2 pseudo isotopes. Module ODOG solves the finite difference diffusion equation by a direct method. Module ODMUG uses the Chebyshev acceleration of outer iterations. It gives a possibility to calculate a critical boron concentration. 3 - Restrictions on the complexity of the problem: It is assumed that the elementary reactor cell consists of the fuel rod surrounded by water. The library data are limited to isotopes typical for water power reactors. The reactor can be treated in one dimension only, i.e. as a slab, sphere or cylinder with one-dimensional symmetry

  13. Proceedings of a workshop on environmental oceanography of the Gulf of Mexico, College Station, Texas, 15--16 March 1976

    International Nuclear Information System (INIS)

    1976-01-01

    A workshop was convened under the sponsorship of the Energy Research and Development Administration to define the most critical energy-related environmental problems in the Gulf of Mexico and develop the framework for a program of research to solve these problems. A major and immediate concern is activity related to the oil and gas industry: production, transportation (including potential superport construction), processing, and use of petroleum-derived fuels. The problems which might be posed by the development of other potential sources of energy, such as coastal and offshore nuclear power plants, were also given consideration. Several keynote speakers presented their thoughts on Gulf environmental problems from different points of view, and their remarks are recorded in Appendix I

  14. Accountability Strain, College Readiness Drain: Sociopolitical Tensions Involved in Maintaining a College-Going Culture in a High "Minority", High Poverty, Texas High School

    Science.gov (United States)

    Welton, Anjale; Williams, Montrischa

    2015-01-01

    Currently school reform discourse encourages states to adopt college readiness standards. Meanwhile, federal and state accountability and related mandated reforms remain a policy concern. As such, it is important to examine the interplay between accountability and the establishment of a college-going culture in high "minority", high…

  15. 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

  16. 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:…

  17. 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…

  18. The Evolution of On-Board Emergency Training for the International Space Station Crew

    Science.gov (United States)

    LaBuff, Skyler

    2015-01-01

    The crew of the International Space Station (ISS) receives extensive ground-training in order to safely and effectively respond to any potential emergency event while on-orbit, but few people realize that their training is not concluded when they launch into space. The evolution of the emergency On- Board Training events (OBTs) has recently moved from paper "scripts" to an intranet-based software simulation that allows for the crew, as well as the flight control teams in Mission Control Centers across the world, to share in an improved and more realistic training event. This emergency OBT simulator ensures that the participants experience the training event as it unfolds, completely unaware of the type, location, or severity of the simulated emergency until the scenario begins. The crew interfaces with the simulation software via iPads that they keep with them as they translate through the ISS modules, receiving prompts and information as they proceed through the response. Personnel in the control centers bring up the simulation via an intranet browser at their console workstations, and can view additional telemetry signatures in simulated ground displays in order to assist the crew and communicate vital information to them as applicable. The Chief Training Officers and emergency instructors set the simulation in motion, choosing the type of emergency (rapid depressurization, fire, or toxic atmosphere) and specific initial conditions to emphasize the desired training objectives. Project development, testing, and implementation was a collaborative effort between ISS emergency instructors, Chief Training Officers, Flight Directors, and the Crew Office using commercial off the shelf (COTS) hardware along with simulation software created in-house. Due to the success of the Emergency OBT simulator, the already-developed software has been leveraged and repurposed to develop a new emulator used during fire response ground-training to deliver data that the crew receives

  19. 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

  20. 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)

  1. 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...

  2. 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...

  3. 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)

  4. Branch-and-Bound algorithm applied to uncertainty quantification of a Boiling Water Reactor Station Blackout

    Energy Technology Data Exchange (ETDEWEB)

    Nielsen, Joseph, E-mail: joseph.nielsen@inl.gov [Idaho National Laboratory, 1955 N. Fremont Avenue, P.O. Box 1625, Idaho Falls, ID 83402 (United States); University of Idaho, Department of Mechanical Engineering and Nuclear Engineering Program, 1776 Science Center Drive, Idaho Falls, ID 83402-1575 (United States); Tokuhiro, Akira [University of Idaho, Department of Mechanical Engineering and Nuclear Engineering Program, 1776 Science Center Drive, Idaho Falls, ID 83402-1575 (United States); Hiromoto, Robert [University of Idaho, Department of Computer Science, 1776 Science Center Drive, Idaho Falls, ID 83402-1575 (United States); Tu, Lei [University of Idaho, Department of Mechanical Engineering and Nuclear Engineering Program, 1776 Science Center Drive, Idaho Falls, ID 83402-1575 (United States)

    2015-12-15

    state. Dynamic PRA (DPRA) methods provide a more rigorous analysis of complex dynamic systems. Unfortunately DPRA methods introduce issues associated with combinatorial explosion of states. This paper presents a methodology to address combinatorial explosion using a Branch-and-Bound algorithm applied to Dynamic Event Trees (DET), which utilize LENDIT (L – Length, E – Energy, N – Number, D – Distribution, I – Information, and T – Time) as well as a set theory to describe system, state, resource, and response (S2R2) sets to create bounding functions for the DET. The optimization of the DET in identifying high probability failure branches is extended to create a Phenomenological Identification and Ranking Table (PIRT) methodology to evaluate modeling parameters important to safety of those failure branches that have a high probability of failure. The PIRT can then be used as a tool to identify and evaluate the need for experimental validation of models that have the potential to reduce risk. In order to demonstrate this methodology, a Boiling Water Reactor (BWR) Station Blackout (SBO) case study is presented.

  5. Branch-and-Bound algorithm applied to uncertainty quantification of a Boiling Water Reactor Station Blackout

    International Nuclear Information System (INIS)

    Nielsen, Joseph; Tokuhiro, Akira; Hiromoto, Robert; Tu, Lei

    2015-01-01

    state. Dynamic PRA (DPRA) methods provide a more rigorous analysis of complex dynamic systems. Unfortunately DPRA methods introduce issues associated with combinatorial explosion of states. This paper presents a methodology to address combinatorial explosion using a Branch-and-Bound algorithm applied to Dynamic Event Trees (DET), which utilize LENDIT (L – Length, E – Energy, N – Number, D – Distribution, I – Information, and T – Time) as well as a set theory to describe system, state, resource, and response (S2R2) sets to create bounding functions for the DET. The optimization of the DET in identifying high probability failure branches is extended to create a Phenomenological Identification and Ranking Table (PIRT) methodology to evaluate modeling parameters important to safety of those failure branches that have a high probability of failure. The PIRT can then be used as a tool to identify and evaluate the need for experimental validation of models that have the potential to reduce risk. In order to demonstrate this methodology, a Boiling Water Reactor (BWR) Station Blackout (SBO) case study is presented.

  6. Full scale reactor safety experiments performed in the Marviken Power Station Sweden

    International Nuclear Information System (INIS)

    Thoren, H.G.; Ericson, L.

    1977-01-01

    Since 1972 experiments oriented towards increasing the understanding of reactor safety processes have been performed at the Marviken Power Station. This was originally built as a direct cycle BHWR but was never taken into nuclear operation. In addition to Sweden, the countries represented in these experiments are Denmark, the Federal Republic of Germany, Finland, Norway, the United States, the Netherlands, France and Japan. The first series of sixteen experiments included studies of the response of the PS-containment to simulated ruptures in the pipe systems that are connected to the pressure vessel. These tests were completed in 1973 and also included experimental studies of iodine transport, containment leakage, the behaviour of auxiliary components under accident conditions and pressure fluctuations in the wetwell water pool. One of the more essential findings of the tests was that the containment performance was in accordance with the pre-test calculations. A second series of eight blowdown tests was begun in February 1976. The main purpose of these tests is to provide additional information as to the characteristics of the pressure oscillations inside the containment and primarily in the wetwell water pool under different conditions. These oscillations were observed in the first series of blowdowns but only low frequencies could then be detected due to limitations in the measurement system. The measurement system was therefore substantially extended for this second series of experiments. A summary of the results from these two sets of blowdown tests are given in the paper. In 1976 preparations for a new test program were initiated. The objective of these tests is to improve the understanding of critical flow in the low quality and subcooled flow regions through short length, large diameter pipes. Extensive modifications of the test facility will be necessary in order to allow a discharge flow through openings which are up to 500 mm in diameter. Advanced plans

  7. Ebola 2014: Setting up a port health screening programme at an international train station.

    Science.gov (United States)

    Cleary, Vivien; Wynne-Evans, Edward; Freed, James; Fleet, Katie; Thorn, Simone; Turbitt, Deborah

    2017-12-01

    An outbreak of Ebola virus disease (EVD) began in Guinea in December 2013 and was declared a Public Health Emergency of International Concern by the World Health Organization in August 2014. In October, the UK government tasked Public Health England (PHE) to set up EVD screening at key ports. The key aim of port-of-entry screening was to identify passengers coming from areas with high risk of EVD, and give them advice to raise their awareness of symptoms and what actions to take. Direct flights from Sierra Leone, Guinea or Liberia had all been cancelled, so intelligence on passenger numbers and routes was used to identify the most commonly used routes from the affected countries into the UK. One of these was St Pancras International train station. Screening had never previously been implemented at a UK train station so had to be set up from scratch. Key to the success of this was excellent multi-agency working between PHE, the UK Border Force, Eurostar, Network Rail and the Cabinet Office. This paper gives an overview of the activation of EVD screening at St Pancras International and the subsequent decommissioning.

  8. 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.

  9. 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)

  10. 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 ...

  11. 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.

  12. 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.

  13. 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

  14. 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.

  15. 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.

  16. Determination of neutron energy spectrum at a pneumatic rabbit station of a typical swimming pool type material test research reactor

    International Nuclear Information System (INIS)

    Malkawi, S.R.; Ahmad, N.

    2002-01-01

    The method of multiple foil activation was used to measure the neutron energy spectrum, experimentally, at a rabbit station of Pakistan Research Reactor-1 (PARR-1), which is a typical swimming pool type material test research reactor. The computer codes MSITER and SANDBP were used to adjust the spectrum. The pre-information required by the adjustment codes was obtained by modelling the core and its surroundings in three-dimensions by using the one dimensional transport theory code WIMS-D/4 and the multidimensional finite difference diffusion theory code CITATION. The input spectrum covariance information required by MSITER code was also calculated from the CITATION output. A comparison between calculated and adjusted spectra shows a good agreement

  17. Exposing College Students to Exercise: The Training Interventions and Genetics of Exercise Response (TIGER) Study

    Science.gov (United States)

    Sailors, Mary H.; Jackson, Andrew S.; McFarlin, Brian K.; Turpin, Ian; Ellis, Kenneth J.; Foreyt, John P.; Hoelscher, Deanna M.; Bray, Molly S.

    2010-01-01

    Objective: The Training Interventions and Genetics of Exercise Response (TIGER) study is an exercise program designed to introduce sedentary college students to regular physical activity and to identify genetic factors that influence response to exercise. Participants: A multiracial/ethnic cohort (N = 1,567; 39% male), age 18 to 35 years,…

  18. 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…

  19. 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…

  20. 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.…

  1. Assessment of Resources for Training Prospective Teachers in Business Education at the Colleges of Education

    Science.gov (United States)

    Okoro, James

    2014-01-01

    This study assessed Resources for Training Prospective Teachers in Business Education at the colleges of Education at South South Nigeria. Business Teacher Education programmes are set up to produce competent teachers for the secondary schools and skilled labour force for the private sector. These products of Business Education programme at the…

  2. Should Your College Start a Center for the Delivery of Contract Training Programs? ERIC Digest.

    Science.gov (United States)

    Deegan, William L.

    Community colleges have been at the forefront in providing contract training programs for clients such as businesses, health care organizations, and government agencies. Many state governments are beginning to provide resources for these programs as an incentive to attract or retain business and industry. One of the consequences of the demand for…

  3. Artificial intelligence and training of nuclear reactor personnel

    International Nuclear Information System (INIS)

    Uhrig, R.E.; Buenaflor, M.T.

    1987-01-01

    Expert computer systems offer an excellent and effective means to reduce the potential for operator error, and improve plant safety and reliability. For the training field the benefits are twofold. First, the inclusion of advisory expert systems in the control environments (the physical control room and its simulator) offer a continuous source of on-the-job diagnostic training. Second, expert systems specifically designed for training are feasible for specialized license/requalification training in higher order analytical skills. This paper consists of two parts. In the first section, the improvements for on-the-job training are examined. In the second section, the benefits for the overall training program are explored in terms of technical and educational rationales

  4. 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.

  5. Design and verification of computer-based reactor control system modification at Bruce-A candu nuclear generating station

    International Nuclear Information System (INIS)

    Basu, S.; Webb, N.

    1995-01-01

    The Reactor Control System at Bruce-A Nuclear Generating Station is going through some design modifications, which involve a rigorous design process including independent verification and validation. The design modification includes changes to the control logic, alarms and annunciation, hardware and software. The design (and verification) process includes design plan, design requirements, hardware and software specifications, hardware and software design, testing, technical review, safety evaluation, reliability analysis, failure mode and effect analysis, environmental qualification, seismic qualification, software quality assurance, system validation, documentation update, configuration management, and final acceptance. (7 figs.)

  6. Characterisation of imperial college reactor centre legacy waste using gamma-ray spectrometry

    International Nuclear Information System (INIS)

    Shuhaimi, Alif Imran Mohd

    2016-01-01

    Waste characterisation is a principal component in waste management strategy. The characterisation includes identification of chemical, physical and radiochemical parameters of radioactive waste. Failure to determine specific waste properties may result in sentencing waste packages which are not compliant with the regulation of long term storage or disposal. This project involved measurement of intensity and energy of gamma photons which may be emitted by radioactive waste generated during decommissioning of Imperial College Reactor Centre (ICRC). The measurement will use High Purity Germanium (HPGe) as Gamma-ray detector and ISOTOPIC-32 V4.1 as analyser. In order to ensure the measurements provide reliable results, two quality control (QC) measurements using difference matrices have been conducted. The results from QC measurements were used to determine the accuracy of the ISOTOPIC software

  7. Characterisation of imperial college reactor centre legacy waste using gamma-ray spectrometry

    Energy Technology Data Exchange (ETDEWEB)

    Shuhaimi, Alif Imran Mohd [Nuclear Energy Department, Regulatory Economics & Planning Division, Tenaga Nasional Berhad (Malaysia)

    2016-01-22

    Waste characterisation is a principal component in waste management strategy. The characterisation includes identification of chemical, physical and radiochemical parameters of radioactive waste. Failure to determine specific waste properties may result in sentencing waste packages which are not compliant with the regulation of long term storage or disposal. This project involved measurement of intensity and energy of gamma photons which may be emitted by radioactive waste generated during decommissioning of Imperial College Reactor Centre (ICRC). The measurement will use High Purity Germanium (HPGe) as Gamma-ray detector and ISOTOPIC-32 V4.1 as analyser. In order to ensure the measurements provide reliable results, two quality control (QC) measurements using difference matrices have been conducted. The results from QC measurements were used to determine the accuracy of the ISOTOPIC software.

  8. 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.

  9. An underground nuclear power station using self-regulating heat-pipe controlled reactors

    Science.gov (United States)

    Hampel, V.E.

    1988-05-17

    A nuclear reactor for generating electricity is disposed underground at the bottom of a vertical hole that can be drilled using conventional drilling technology. The primary coolant of the reactor core is the working fluid in a plurality of thermodynamically coupled heat pipes emplaced in the hole between the heat source at the bottom of the hole and heat exchange means near the surface of the earth. Additionally, the primary coolant (consisting of the working fluid in the heat pipes in the reactor core) moderates neutrons and regulates their reactivity, thus keeping the power of the reactor substantially constant. At the end of its useful life, the reactor core may be abandoned in place. Isolation from the atmosphere in case of accident or for abandonment is provided by the operation of explosive closures and mechanical valves emplaced along the hole. This invention combines technology developed and tested for small, highly efficient, space-based nuclear electric power plants with the technology of fast- acting closure mechanisms developed and used for underground testing of nuclear weapons. This invention provides a nuclear power installation which is safe from the worst conceivable reactor accident, namely, the explosion of a nuclear weapon near the ground surface of a nuclear power reactor. 5 figs.

  10. Underground nuclear power station using self-regulating heat-pipe controlled reactors

    Science.gov (United States)

    Hampel, Viktor E.

    1989-01-01

    A nuclear reactor for generating electricity is disposed underground at the bottom of a vertical hole that can be drilled using conventional drilling technology. The primary coolant of the reactor core is the working fluid in a plurality of thermodynamically coupled heat pipes emplaced in the hole between the heat source at the bottom of the hole and heat exchange means near the surface of the earth. Additionally, the primary coolant (consisting of the working flud in the heat pipes in the reactor core) moderates neutrons and regulates their reactivity, thus keeping the power of the reactor substantially constant. At the end of its useful life, the reactor core may be abandoned in place. Isolation from the atmosphere in case of accident or for abandonment is provided by the operation of explosive closures and mechanical valves emplaced along the hole. This invention combines technology developed and tested for small, highly efficient, space-based nuclear electric power plants with the technology of fast-acting closure mechanisms developed and used for underground testing of nuclear weapons. This invention provides a nuclear power installation which is safe from the worst conceivable reactor accident, namely, the explosion of a nuclear weapon near the ground surface of a nuclear power reactor.

  11. Underground nuclear power station using self-regulating heat-pipe controlled reactors

    International Nuclear Information System (INIS)

    Hampel, V.E.

    1989-01-01

    The author presents a nuclear reactor for generating electricity disposed underground at the bottom of a vertical hole that can be drilled using conventional drilling technology. The primary coolant of the reactor core is the working fluid in a plurality of thermodynamically coupled heat pipes emplaced in the hole between the heat source at the bottom of the hole and heat exchange means near the surface of the earth. Additionally, the primary coolant (consisting of the working fluid in the heat pipes in the reactor core) moderates neutrons and regulates their reactivity, thus keeping the power of the reactor substantially constant. At the end of its useful life, the reactor core may be abandoned in place. Isolation from the atmosphere in case of accident or for abandonment is provided by the operation of explosive closures and mechanical valves emplaced along the hole. This invention combines technology developed and tested for small, highly efficient, space-based nuclear electric power plants with the technology of fast-acting closure mechanisms developed and used for underground testing of nuclear weapons. This invention provides a nuclear power installation which is safe from the worst conceivable reactor accident, namely, the explosion of a nuclear weapon near the ground surface of a nuclear power reactor

  12. 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

  13. Multimedia Course on Nuclear Reactors Physics, Application to a Tailored On the Job Training Course

    International Nuclear Information System (INIS)

    Dies, Javier

    2014-01-01

    In order to improve education and training quality, a Multimedia on Nuclear Reactor Physics has been developed. In some institutions, this course is called Fundamentals of Nuclear Reactor Operation. Nowadays, this multimedia has about 800 slides and the text is in Spanish, English, French and Russian. Until now about 126 institutions from 53 countries have applied for the multimedia. The teacher uses the multimedia during his lectures. Students use it at home to study this course

  14. IAEA Workshop (Training Course) on Codes and Standards for Sodium Cooled Fast Reactors. Working Material

    International Nuclear Information System (INIS)

    2010-01-01

    The training course consisted of lectures and Q&A sessions. The lectures dealt with the history of the development of Design Codes and Standards for Sodium Cooled Fast Reactors (SFRs) in the respective country, the detailed description of the current design Codes and Standards for SFRs and their application to ongoing Fast Reactor design projects, as well as the ongoing development work and plans for the future in this area. Annex 1 contains the detailed Workshop program

  15. 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.

  16. Reference ZrH reactor power system for NASA space station post-operational reentry analysis

    International Nuclear Information System (INIS)

    Elliott, R.D.

    1970-01-01

    The flight dynamic and heating of a spent ZrH reactor power system returning from orbit at the end of its useful life are analyzed. The results of this analysis indicate that the reactor with a large portion of the lithium shield still surrounding it will impact the earth at a velocity of from 660 to 820 ft/sec, depending upon whether it tumbles or becomes stabilized during the latter part of its trajectory. (U.S.)

  17. 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

  18. 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

  19. An Experimental Analysis on Dispatching Rules for the Train Platforming Problem in Busy Complex Passenger Stations

    Directory of Open Access Journals (Sweden)

    Qiongfang Zeng

    2017-09-01

    platforming problem (TPP by using mixed integer linear programming and job shop scheduling theory. First, the operation procedures and scheduled time adjustment costs of different train types specific to busy complex passenger stations are explicitly represented. Second, a multi-criteria scheduling model (MCS for TPP without earliness and tardiness time window (ETTW and a time window scheduling model (TWS with ETTW for TPP are proposed. Third, various dispatching rules were designed by incorporating the dispatcher experiences with modern scheduling theory and a rule-based metaheuristic to solve the above model is presented. With solution improvement strategies analogous to those used in practice by dispatchers, the realistic size problems in acceptable time can be solved.

  20. 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

  1. 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.

  2. 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.)

  3. Geologic framework and hydrogeologic features of the Glen Rose Limestone, Camp Bullis Training Site, Bexar County, Texas

    Science.gov (United States)

    Clark, Allan K.

    2003-01-01

    The Glen Rose Limestone crops out over most of the Camp Bullis Training Site in northern Bexar County, Texas, where it consists of upper and lower members and composes the upper zone and the upper part of the middle zone of the Trinity aquifer. Uncharacteristically permeable in northern Bexar County, the Glen Rose Limestone can provide avenues for recharge to and potential contamination of the downgradient Edwards aquifer, which occupies the southeastern corner of Camp Bullis.The upper member of the Glen Rose Limestone characteristically is thin-bedded and composed mostly of soft limestone and marl, and the lower Glen Rose typically is composed mostly of relatively massive, fossiliferous limestone. The upper member, about 410 to 450 feet thick at Camp Bullis, was divided in this study into five hydrogeologic subdivisions, A through E (youngest to oldest).The approximately 120-foot-thick Interval A has an abundance of caves, which is indicative of its generally well developed fracture, channel, and cavern porosity that in places provides appreciable permeability. The 120- to 150-foot-thick Interval B is similar to Interval A but with less cave development and considerably less permeability. The 10- to 20-foot-thick Interval C, a layer of partly to mostly dissolved soluble carbonate minerals, is characterized by breccia porosity, boxwork permeability, and collapse structures that typically divert ground water laterally to discharge at land surface. The 135- to 180-foot-thick Interval D generally has low porosity and little permeability with some local exceptions, most notably the caprinid biostrome just below the top of the interval, which appears to be permeable by virtue of excellent moldic, vug, fracture, and cavern porosity. The 10- to 20-foot-thick Interval E, a layer of partly to mostly dissolved evaporites similar to Interval C, has similar hydrogeologic properties and a tendency to divert ground water laterally.

  4. A Comparative Analysis of Personal Skills Profiles among Administrators, Department Chairs and Faculty at a College in South Texas

    Science.gov (United States)

    Mejia, Juan Eduardo

    2012-01-01

    To remain competitive in a global economy, institutions of higher learning must commit to excellence and establish as a priority organizational and human resource development (McCabe, 2001). While mission statements from community colleges throughout the country may include similar foci, it is of paramount importance that these institutions of…

  5. 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

  6. 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…

  7. 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.

  8. 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

  9. Future plans for the design and construction of fast reactor power stations in Italy

    International Nuclear Information System (INIS)

    Castelli, G.; Ghilardotti, G.

    1978-01-01

    Studies related to fast reactor technology have been pursued in Italy for a long time and this country is now deeply engaged in the demonstration and marketing phases, in accordance with the outlines of the Italian national energy plan. In the paper the following topics are examined: current possibilities for introducing fast reactors in Italy; the main social and political constraints concerning their introduction; the necessary industrial and organizational structures (in the broadest meaning) existing or foreseen; the national programme pertaining to activities towards achieving this goal. (author)

  10. The application of MVC design pattern in Daya bay reactor neutrino experiments online safety training system

    International Nuclear Information System (INIS)

    Liu Guanchuan; Chu Yuanping

    2011-01-01

    The article made an introduction to MVC, which is an architectural pattern used in software engineering. It specified the advantages and disadvantages of MVC and also the application of MVC in Daya Bay nuclear reactor neutrino experiment online safety training system. (authors)

  11. Investigations of the reactivity temperature coefficient of the Dresden Technical University training and research reactor

    International Nuclear Information System (INIS)

    Adam, E.; Knorr, J.

    1982-01-01

    Approximate formulas are derived for determining the temperature coefficient of reactivity of the training and research reactor (AKR) of the Dresden Technical University. Values calculated on the basis of these approximations show good agreement with experimentally obtained results, thus confirming the applicability of the formulas to simple systems

  12. [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.

  13. 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.

  14. 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

  15. Computer modeling of the dynamic processes in the Maryland University Training Reactor - (MUTR)

    International Nuclear Information System (INIS)

    White, Bernard H. IV; Ebert, David

    1988-01-01

    The simulator described in this paper models the behaviour of the Maryland University Training Reactor (MUTR). The reactor is a 250 kW, TRIGA reactor. The computer model is based on a system of five primary equations and eight auxiliary equations. The primary equations consist of the prompt jump approximation, a heat balance equation for the fuel and the moderator, and iodine and xenon buildup equations. For the comparison with the computer program, data from the reactor was acquired by using a personal computer (pc) which contained a Strawberry Tree data acquisition Card, connected to the reactor. The systems monitored by the pc were: two neutron detectors, fuel temperature, water temperature, three control rod positions and the period meter. The time differenced equations were programmed in the basic language. It has been shown by this paper, that the MUTR power rise from low power critical to high power, can be modelled by a relatively simple computer program. The program yields accurate agreement considering the simplicity of the program. The steady state error between the reactor and computer power is 4.4%. The difference in steady state temperatures, 112 deg. C and 117 deg. C, of the reactor and computer program, respectively, also yields a 4.5% error. Further fine tuning of the coefficients will yield higher accuracies

  16. Use of social media platforms for improving academic performance at Further Education and Training colleges

    OpenAIRE

    Godwin P. Dzvapatsva; Zoran Mitrovic; Anthony D. Dietrich

    2014-01-01

    Background: The National Certificate Vocational (NC[V]) curriculum offered by Further Education and Training (FET) colleges was introduced in 2007 to address the skills shortage in South Africa. Information Technology (IT) lecturers encountered a number of challenges in delivering lessons throughout the course, which affected the academic performance of learners. The biggest challenges identified were the lack of adequate contact hours for the course and inconsistency in the way in which fina...

  17. Interactive Virtual Reactor and Control Room for Education and Training at Universities and Nuclear Power Plants

    International Nuclear Information System (INIS)

    Satoh, Yoshinori; Li, Ye; Zhu, Xuefeng; Rizwan, Uddin

    2014-01-01

    Efficient and effective education and training of nuclear engineering students and nuclear workers are critical for the safe operation and maintenance of nuclear power plants. With an eye toward this need, we have focused on the development of 3D models of virtual labs for education, training as well as to conduct virtual experiments. These virtual labs, that are expected to supplement currently available resources, and have the potential to reduce the cost of education and training, are most easily developed on game-engine platforms. We report some recent extensions to the virtual model of the University of Illinois TRIGA reactor

  18. Interactive Virtual Reactor and Control Room for Education and Training at Universities and Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Satoh, Yoshinori; Li, Ye; Zhu, Xuefeng; Rizwan, Uddin [University of Illinois, Urbana (United States)

    2014-08-15

    Efficient and effective education and training of nuclear engineering students and nuclear workers are critical for the safe operation and maintenance of nuclear power plants. With an eye toward this need, we have focused on the development of 3D models of virtual labs for education, training as well as to conduct virtual experiments. These virtual labs, that are expected to supplement currently available resources, and have the potential to reduce the cost of education and training, are most easily developed on game-engine platforms. We report some recent extensions to the virtual model of the University of Illinois TRIGA reactor.

  19. Power raise through improved reactor inlet header temperature measurement at Bruce A Nuclear Generation Station

    International Nuclear Information System (INIS)

    Basu, S.; Bruggemn, D.

    1997-01-01

    Reactor Inlet Header (RIH) temperature has become a factor limiting the performance of the Ontario Hydro Bruce A units. Specifically, the RIH temperature is one of several parameters that is preventing the Bruce A units from returning to 94% power operation. RIH temperature is one of several parameters which affect the critical heat flux in the reactor channel, and hence the integrity of the fuel. Ideally, RIH temperature should be lowered, but this cannot be done without improving the heat transfer performance of the boilers and feedwater pre-heaters. Unfortunately, the physical performance of the boilers and pre-heaters has decayed and continues to decay over time and as a result the RIH temperature has been rising and approaching its defined limit. With an understanding of the current RIH temperature measurement loop and methods available to improve it, a solution to reduce the measurement uncertainty is presented

  20. A flooding induced station blackout analysis for a pressurized water reactor using the RISMC toolkit

    International Nuclear Information System (INIS)

    Mandelli, Diego; Prescott, Steven; Smith, Curtis; Alfonsi, Andrea; Rabiti, Cristian; Cogliati, Joshua; Kinoshita, Robert

    2015-01-01

    In this paper we evaluate the impact of a power uprate on a pressurized water reactor (PWR) for a tsunami-induced flooding test case. This analysis is performed using the RISMC toolkit: the RELAP-7 and RAVEN codes. RELAP-7 is the new generation of system analysis codes that is responsible for simulating the thermal-hydraulic dynamics of PWR and boiling water reactor systems. RAVEN has two capabilities: to act as a controller of the RELAP-7 simulation (e.g., component/system activation) and to perform statistical analyses. In our case, the simulation of the flooding is performed by using an advanced smooth particle hydrodynamics code called NEUTRINO. The obtained results allow the user to investigate and quantify the impact of timing and sequencing of events on system safety. The impact of power uprate is determined in terms of both core damage probability and safety margins

  1. UK regulatory aspects of prestressed concrete pressure vessels for gas-cooled reactor nuclear power stations

    International Nuclear Information System (INIS)

    Watson, P.S.

    1990-01-01

    Safety assessment principles for nuclear power plants and for nuclear chemical plants demand application of best proven techniques, recognised standards, adequacy margins, inspection and maintenance of all the components including prestressed concrete pressure vessels. In service inspection of prestressed concrete pressure vessels includes: concrete surface examination; anchorage inspection; tendon load check; tendon material examination; foundation settlement and tilt; log-term deformation; vessel temperature excursions; coolant loss; top cap deflection. Hartlepool and Heysham 1 power plants prestress shortfall problem is discussed. Main recommendations can be summarised as follows: at all pressure vessel stations prestress systems should be calibrated in a manner which results in all load bearing components being loaded in a representative manner; at all pressure vessel stations load measurements during calibration should be verified by a redundant and diverse system

  2. A simple health sign increases stair use in a shopping mall and two train stations in Flanders, Belgium.

    Science.gov (United States)

    Boen, Filip; Maurissen, Katrien; Opdenacker, Joke

    2010-06-01

    The aim of this study was to test the impact of a simple health-promotion sign on stair use in three community settings in Flanders, Belgium. A health sign was placed at the junction between the stairs and an escalator in a shopping mall and two train stations. Observations took place on four days: baseline, first intervention, post-intervention and second intervention. In the second station, a second post-intervention phase was added. In total, 1437 choices of shoppers were registered in the mall, while 2869 and 2025 choices of commuters were recorded in the two stations, respectively. Despite the different baselines of stair use, the introduction of the health sign in the first intervention phase resulted in a significant increase in all three settings: 10.0% increase in the mall, 8.6% in the first station and 18.0% in the second station. In the second station, the increase during the second intervention exceeded that of the first intervention. Moreover, in this station stair use in the second post-intervention phase was significantly higher than at baseline. An inexpensive health-promoting sign has a substantial effect on the proportion of stair users among shoppers and commuters. Preliminary evidence was found that repeated exposure to a health sign might have a longer term effect on stair use.

  3. Nuclear power station with a water-cooled reactor pressure vessel

    International Nuclear Information System (INIS)

    Hoffmann, R.; Brunner, G.; Jost, N.

    1987-01-01

    Nuclear radiation produces radiolysis gases, which are undesirable for corrosion and oxyhydrogen gas reasons. To limit the proportion of this radiolysis gas, the invention provides that catalytic surfaces should be introduced into the primary circuit, to produce recombination of hydrogen and oxygen. These surfaces can be accommodated in the upper part of the reactor pressure vessel. The live steam screen can also have a catalytic surface. (orig./HP) [de

  4. 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.

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

    Science.gov (United States)

    Whitehead, Kay

    2012-01-01

    This article examines the ways in which Gipsy Hill Training College's (GHTC) graduates represented their lives and work in the college magazine, the "Gipsy Trail". The so-called "Wraggle Taggle News" featured snippets from married and single women teachers at every stage of their lives and work in Britain and overseas by the…

  6. 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....

  7. 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

  8. Pressurized water reactor simulation in the training environment

    International Nuclear Information System (INIS)

    Wills, A.G.

    1990-01-01

    The paper gives a brief history of PWR Simulation within the DNST and an outline of the training courses leading to the requirement for the Display Array Simulation System. Focus is then placed upon the flexible use of real time simulation in the teaching of plant dynamics by the use of model generated data. The use of interactive consoles and a large scale colour graphic display has led to the success of the Display Array Simulation System within the DNST. Realisation of the potential of the system has led to many other proposed uses for the installed system and the paper concludes by discussing some of these. (orig./DG)

  9. CAI and training system for the emergency operation procedure in the advanced thermal reactor, FUGEN

    International Nuclear Information System (INIS)

    Kozaki, T.; Imanaga, K.; Nakamura, S.; Maeda, K.; Sakurai, N.; Miyamoto, M.

    2003-01-01

    In the Advanced Thermal Reactor (ATR ) of the JNC, 'FUGEN', a symptom based Emergency Operating Procedure (EOF) was introduced in order to operate Fugen more safely and it became necessary for the plant operators to master the EOF. However it took a lot of time for the instructor to teach the EOP to operators and to train them. Thus, we have developed a Computer Aided Instruction (CAI) and Training System for the EOP, by which the operators can learn the EOP and can be trained. This system has two major functions, i.e., CAI and training. In the CAI function, there are three learning courses, namely, the EOP procedure, the simulation with guidance and Q and A, and the free simulation. In the training function, all of necessary control instruments (indicators, switches, annunciators and so forth) and physics models for the EOP training are simulated so that the trainees can be trained for all of the EOPs. In addition, 50 kinds of malfunction models are installed in order to perform appropriate accident scenarios for the EOP. The training of the EOP covers the range from AOO (Anticipated Operational Occurrence) to Over-DBAs (Design Based Accidents). This system is built in three personal computers that are connected by the computer network. One of the computers is expected to be used for the instructor and the other two are for the trainees. The EOP is composed of eight guidelines, such as 'Reactor Control' and 'Depression and Cooling', and the operation screens which are corresponded to the guidelines are respectively provided. According to the trial, we have estimated that the efficiency of the learning and the training would be improved about 30% for the trainee and about 75% for the instructor in the actual learning and training. (author)

  10. Nudging healthy food choices: a field experiment at the train station.

    Science.gov (United States)

    Kroese, Floor M; Marchiori, David R; de Ridder, Denise T D

    2016-06-01

    Recognizing the mindless nature of many food decisions, it has been suggested that attempts to increase healthy eating should not focus on convincing people what is 'right' but rather aim to adjust the environment such that people are automatically directed toward healthy choices. This study investigated a nudge aiming to promote healthy food choices in train station snack shops. The nudge involved a repositioning of food products: healthy foods were placed at the cash register desk, while keeping unhealthy products available elsewhere in the shop. Three snack shops were included: a control condition; a nudge condition repositioning healthy products and a nudge + disclosure condition employing the same nudge together with an explanatory sign. Next to examining its effectiveness during 1 week, the study assessed customers' acceptance of the nudge. Controlling for a baseline week, more healthy (but not fewer unhealthy) products were sold in both nudge conditions, with no difference between the nudge and the nudge + disclosure condition. A majority of customers reported positive attitudes toward the nudge. Repositioning healthy foods is a simple, effective and well-accepted nudge to increase healthy purchases. Moreover, disclosing its purpose does not impact on effectiveness. © The Author 2015. Published by Oxford University Press on behalf of Faculty of Public Health. All rights reserved. For permissions, please e-mail: journals.permissions@oup.com.

  11. MRP-227 Reactor vessel internals inspection planning and initial results at the Oconee nuclear station unit 2

    International Nuclear Information System (INIS)

    Davidsaver, S.B.; Fyfitch, S.; Whitaker, D.E.; Doss, R.L.

    2015-01-01

    The U.S. PWR industry has pro-actively developed generic inspection requirements and standards for reactor vessel (RV) internals. The Electric Power Research Institute (EPRI) Pressurized Water Reactor (PWR) Materials Reliability Program (MRP) has issued MRP-227-A and MRP-228 with mandatory and needed requirements based on the Nuclear Energy Institute (NEI) document NEI 03-08. The inspection and evaluation guidelines contained in MRP-227-A consider eight age-related degradation mechanisms: stress corrosion cracking (SCC), irradiation-assisted stress corrosion cracking (IASCC), wear, fatigue, thermal aging embrittlement, irradiation embrittlement, void swelling and irradiation growth, and thermal and irradiation-enhanced stress relaxation or irradiation-enhanced creep. This paper will discuss the decision planning efforts required for implementing the MRP-227-A and MRP-228 requirements and the results of these initial inspections at the Oconee Nuclear power station (ONS) units. Duke Energy and AREVA overcame a significant technology and NDE challenge by successfully completing the first-of-a-kind MRP-227-A scope requirements at ONS-1 in one outage below the estimated dose and with zero safety issues or events. This performance was repeated at ONS-2 a year later. The remote NDE tooling and processes developed to examine the MRP-227-A scope for ONS-1 and ONS-2 are transferable to other PWRs

  12. 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

  13. 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.

  14. Theoretical model for investigating the dynamic behaviour of the AST-500 type nuclear heating station reactor

    International Nuclear Information System (INIS)

    Grundmann, U.; Rohde, U.; Naumann, B.

    1985-01-01

    Studies on theoretical simulation of the dynamic behaviour of the AST-500 type reactor primary coolant system are summarized. The first version of a dynamic model in the form of the DYNAST code is described. The DYNAST code is based on a one-dimensional description of the primary coolant circuit including core, draught stack, and intermediate heat exchanger, a vapour dome model, and the point model of neutron kinetics. With the aid of the steady-state computational part of the DYNAST code, studies have been performed on different steady-state operating conditions. Furthermore, some methodological investigations on generalization and improvement of the dynamic model are considered and results presented. (author)

  15. 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

  16. 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.

  17. Modeling of a Flooding Induced Station Blackout for a Pressurized Water Reactor Using the RISMC Toolkit

    Energy Technology Data Exchange (ETDEWEB)

    Mandelli, Diego; Prescott, Steven R; Smith, Curtis L; Alfonsi, Andrea; Rabiti, Cristian; Cogliati, Joshua J; Kinoshita, Robert A

    2011-07-01

    In the Risk Informed Safety Margin Characterization (RISMC) approach we want to understand not just the frequency of an event like core damage, but how close we are (or are not) to key safety-related events and how might we increase our safety margins. The RISMC Pathway uses the probabilistic margin approach to quantify impacts to reliability and safety by coupling both probabilistic (via stochastic simulation) and mechanistic (via physics models) approaches. This coupling takes place through the interchange of physical parameters and operational or accident scenarios. In this paper we apply the RISMC approach to evaluate the impact of a power uprate on a pressurized water reactor (PWR) for a tsunami-induced flooding test case. This analysis is performed using the RISMC toolkit: RELAP-7 and RAVEN codes. RELAP-7 is the new generation of system analysis codes that is responsible for simulating the thermal-hydraulic dynamics of PWR and boiling water reactor systems. RAVEN has two capabilities: to act as a controller of the RELAP-7 simulation (e.g., system activation) and to perform statistical analyses (e.g., run multiple RELAP-7 simulations where sequencing/timing of events have been changed according to a set of stochastic distributions). By using the RISMC toolkit, we can evaluate how power uprate affects the system recovery measures needed to avoid core damage after the PWR lost all available AC power by a tsunami induced flooding. The simulation of the actual flooding is performed by using a smooth particle hydrodynamics code: NEUTRINO.

  18. Nuclear safety analyses and core design calculations to convert the Texas A & M University Nuclear Science Center reactor to low enrichment uranium fuel. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Parish, T.A.

    1995-03-02

    This project involved performing the nuclear design and safety analyses needed to modify the license issued by the Nuclear Regulatory Commission to allow operation of the Texas A& M University Nuclear Science Center Reactor (NSCR) with a core containing low enrichment uranium (LEU) fuel. The specific type of LEU fuel to be considered was the TRIGA 20-20 fuel produced by General Atomic. Computer codes for the neutronic analyses were provided by Argonne National Laboratory (ANL) and the assistance of William Woodruff of ANL in helping the NSCR staff to learn the proper use of the codes is gratefully acknowledged. The codes applied in the LEU analyses were WIMSd4/m, DIF3D, NCTRIGA and PARET. These codes allowed full three dimensional, temperature and burnup dependent calculations modelling the NSCR core to be performed for the first time. In addition, temperature coefficients of reactivity and pulsing calculations were carried out in-house, whereas in the past this modelling had been performed at General Atomic. In order to benchmark the newly acquired codes, modelling of the current NSCR core with highly enriched uranium fuel was also carried out. Calculated results were compared to both earlier licensing calculations and experimental data and the new methods were found to achieve excellent agreement with both. Therefore, even if an LEU core is never loaded at the NSCR, this project has resulted in a significant improvement in the nuclear safety analysis capabilities established and maintained at the NSCR.

  19. Blogs, webinars and significant learning: A case report on a teacher training program for college teachers

    Directory of Open Access Journals (Sweden)

    Rodrigo Polanco-Bueno

    2013-02-01

    Full Text Available 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 of students’ learning experiences. The learning experience consisted in an International Certificate on Significant Learning integrated by six modules, 20 hours each. Every module of the program consisted of two consecutive webinars with online activities in between. The results showed the positive impact of the program on participants’ perceptions about the quality of the contents, evidence of learning and products (E-portfolios that served as content mastery evidences, as well as learning products produced by their students. DOI: 10.18870/hlrc.v3i1.72

  20. 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.

  1. American College of Radiology In-Training Examination for Residents in Radiation Oncology (2004-2007)

    International Nuclear Information System (INIS)

    Paulino, Arnold C.; Kurtz, Elizabeth

    2008-01-01

    Purpose: To review the results of the recent American College of Radiology (ACR) in-training examinations in radiation oncology and to provide information regarding the examination changes in recent years. Methods and Materials: A retrospective review of the 2004 to 2007 ACR in-training examination was undertaken. Results: The number of residents taking the in-training examination increased from 2004 to 2007, compatible with the increase in the number of radiation oncology residents in the United States and Canada. The number of questions decreased from approximately 510 in 2004 and 2005, to 405 in 2006 and 360 in 2007, most of these changes were in the clinical oncology section. Although the in-training examination showed construct validity with resident performance improving with each year of additional clinical oncology training, it did so only until Level 3 for biology and physics. Several changes have been made to the examination process, including allowing residents to keep the examination booklet for self-study, posting of the answer key and rationales to questions on the ACR Website, and providing hard copies to residency training directors. In addition, all questions are now A type or multiple choice questions with one best answer, similar to the American Board of Radiology written examination for radiation oncology. Conclusion: Several efforts by the ACR have been made in recent years to make the examination an educational tool for radiation oncology residents and residency directors

  2. Light Water Reactor Sustainability Program Support and Modeling for the Boiling Water Reactor Station Black Out Case Study Using RELAP and RAVEN

    Energy Technology Data Exchange (ETDEWEB)

    Mandelli, Diego [Idaho National Lab. (INL), Idaho Falls, ID (United States); Smith, Curtis [Idaho National Lab. (INL), Idaho Falls, ID (United States); Riley, Thomas [Idaho National Lab. (INL), Idaho Falls, ID (United States); Schroeder, John [Idaho National Lab. (INL), Idaho Falls, ID (United States); Rabiti, Cristian [Idaho National Lab. (INL), Idaho Falls, ID (United States); Alfonsi, Aldrea [Idaho National Lab. (INL), Idaho Falls, ID (United States); Nielsen, Joe [Idaho National Lab. (INL), Idaho Falls, ID (United States); Maljovec, Dan [Idaho National Lab. (INL), Idaho Falls, ID (United States); Wang, Bie [Idaho National Lab. (INL), Idaho Falls, ID (United States); Pascucci, Valerio [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2013-09-01

    The existing fleet of nuclear power plants is in the process of extending its lifetime and increasing the power generated. In order to evaluate the impact of these two factors on the safety of the plant, the Risk Informed Safety Margin Characterization (RISMC) project aims to provide insight to decision makers through a series of simulations of the plant dynamics for different initial conditions (e.g., probabilistic analysis and uncertainty quantification). This report focuses, in particular, on the impact of power uprate on the safety of a boiled water reactor system. The case study considered is a loss of off-site power followed by the loss of diesel generators, i.e., a station black out (SBO) event. Analysis is performed by using a thermo-hydraulic code, i.e. RELAP-5, and a stochastic analysis tool currently under development at INL, i.e. RAVEN. Starting from the event tree models contained in SAPHIRE, we built the input file for RELAP-5 that models in great detail system dynamics under SBO conditions. We also interfaced RAVEN with RELAP-5 so that it would be possible to run multiple RELAP-5 simulation runs by changing specific keywords of the input file. We both employed 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. We also employed advanced data analysis and visualization tools that helped us to correlate simulation outcome such as maximum core temperature with a set of input uncertain parameters. Results obtained gave a detailed overview of the issues associated to power uprate for a SBO accident scenario. We were able to quantify how timing of safety related events were impacted by a higher reactor core power. Such insights can provide useful material to the decision makers to perform risk-infomed safety margins management.

  3. Analysis of station blackout accidents for the Bellefonte pressurized water reactor

    International Nuclear Information System (INIS)

    Gasser, R.D.; Bieniarz, P.P.; Tills, J.L.

    1986-09-01

    An analysis has been performed for the Bellefonte PWR Unit 1 to determine the containment loading and the radiological releases into the environment from a station blackout accident. A number of issues have been addressed in this analysis which include the effects of direct heating on containment loading, and the effects of fission product heating and natural convection on releases from the primary system. The results indicate that direct heating which involves more than about 50% of the core can fail the Bellefonte containment, but natural convection in the RCS may lead to overheating and failure of the primary system piping before core slump, thus, eliminating or mitigating direct heating. Releases from the primary system are significantly increased before vessel breach due to natural circulation and after vessel breach due to reevolution of retained fission products by fission product heating of RCS structures

  4. Applicability of AWJ technique for dismantling reactor of the Fukushima Daiichi Nuclear Power Station. Cutting test of imitation of fuel debris and optimization of the cutting condition

    International Nuclear Information System (INIS)

    Maruyama, Shin-ichiro; Watatani, Satoshi

    2016-01-01

    Based on findings during recovery works that followed the accident at Three Mile Island Station 2, it is assumed that the reactor internals at the Fukushima Daiichi Nuclear Power Station (1F) have complex geometries intermixed with melted fuel and confined in limited spaces. Accordingly, abrasive water jet (AWJ) cutting method is considered to be a promising technique that can be safely and reasonably used for cutting and removing reactor internals. The authors conducted tests to examine the possibility of application and to solve the problems of this technique. In the tests imitation of fuel debris and optimization of the cutting condition is used. The test result made the measures for some of the associated issues clear, and demonstrated that AWJ cutting method is assumed as one of the promising techniques for removing reactor internals. (author)

  5. 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

  6. Annual progress report of the University of Florida Training Reactor, September 1, 1981-August 31, 1982

    International Nuclear Information System (INIS)

    Diaz, N.J.; Vernetson, W.G.

    1982-11-01

    The University of Florida Training Reactor's overall utilization for the past reporting year has decreased by about 50% compared to the previous year, approaching the low levels of utilization characteristic of the previous two reporting years ending in August 1979 and August 1980 respectively. The energy generation also continues to be far below average historical levels and represents a drop of nearly 50% from the improved level of the previous year. The UFTR continues to operate with an outstanding safety record and in full compliance with regulatory requirements. The reactor and associated facilities continue to maintain a high in-state visibility and strong industry relationship. It is hoped that more indirect industry training will be accomplished in the upcoming year

  7. 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

  8. 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...

  9. Simulators and their use in the training of CEGB reactor operations engineers

    International Nuclear Information System (INIS)

    Madden, V.J.; Tompsett, P.A.

    1988-01-01

    The development of simulators in the Central Electricity Generating Board's nuclear power training are traced, and, in describing the overall training programme of an advanced gas-cooled reactor operations engineer, the contribution made by a range of simulation devices from concept through to full-scope replica simulators is indicated. The capabilities of today's simulators are such that they are also making other contributions to the commissioning and safe operation of nuclear power plants. They are being successfully used for ergonomic and procedure validation work and the testing and commissioning of software for automatic control systems, and data and alarm processing systems. (author)

  10. Christian Universities and Colleges: The Need to Train Instructors to Teach the Bible as Literature in Public Schools

    Science.gov (United States)

    Jeynes, William H.

    2012-01-01

    The author examines the national growth of Bible literacy courses in America's public schools and examines what steps Christian universities and colleges can take to help meet the demand for teachers for these courses. The author asserts that several sources of training are currently available, but declares that they will be unable to train a…

  11. 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)

  12. The next 20 years operation of the 36 years old Hungarian training reactor

    International Nuclear Information System (INIS)

    Aszodi, A.

    2007-01-01

    Hungary prepares for extending the design lifetime of the four VVER-440/213 type units; in that case they will finish operation between 2032 and 2037. Discussion on possible new nuclear units in Hungary was recently commenced. The paper describes actions in human resource management and knowledge management, and also the new safety analysis methods which were applied during the recent Periodic Safety Review of the Hungarian Training Reactor

  13. 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.

  14. 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

  15. Nutrition Education and Training Needs in Texas. Nutrition Education and Training Needs Assessment for Federal Fiscal Year 1995. Final Annual Report.

    Science.gov (United States)

    Martin, Ruth E.; Ahmad, Mahassen

    A 3-year needs assessment study examined nutrition knowledge, attitudes, and food practices. Subjects were 135 preschool children ages 3-5 years, 610 parents, 118 day care teachers and providers, 35 food service personnel, and 76 administrators throughout Texas. Registered family day care homes, group day care homes, and day care centers from 11…

  16. Training courses on the use of neutron detection systems carried out on the ISIS research reactor

    International Nuclear Information System (INIS)

    Lescop, Bernard; Foulon, Francois

    2013-06-01

    Training courses on the use of the neutron detection systems for the control of the nuclear reactors are carried out by the National Institute for Nuclear Science using the ISIS research reactor. The study and the comprehension of the operation of these systems are facilitated by the use a research reactor in order to observe the electronic signals in real conditions. Thus, ISIS reactor offers a wide range of neutron fluxes and the level of power can be easily set to any value from zero to nominal power (700 kW). Different kinds of detectors (counters, ionization chambers), which operate in the different modes of detection (pulse, current and Campbelling) can be placed in the periphery of the core for the courses. The electronic signal can be analyzed at each step of the detection process. One goal of the courses is to understand the role of each component of the detection system: detector, cable and each electronic module. A comparison with the nuclear instrumentation used by the instrumentation and control of ISIS reactor is also made. This comparison is very useful to understand the role of the neutron instrumentation in terms of safety, availability, reliability and maintainability. (authors)

  17. Development of a training simulator to operators of the IEA-R1 research reactor

    International Nuclear Information System (INIS)

    Carvalho, Ricardo Pinto de

    2006-01-01

    This work reports the development of a Simulator for the IEA-R1 Research Reactor. The Simulator was developed with Visual C++ in two stages: construction of the mathematics models and development and configuration of graphics interfaces in a Windows XP executable. A simplified modeling was used for main physics phenomena, using a point kinetics model for the nuclear process and the energy and mass conservation laws in the average channel of the reactor for the thermal hydraulic process. The dynamics differential equations were solved by using finite differences through the 4th order Runge- Kutta method. The reactivity control, reactor cooling, and reactor protection systems were also modeled. The process variables are stored in ASCII files. The Simulator allows navigating by screens of the systems and monitoring tendencies of the operational transients, being an interactive tool for teaching and training of IEA-R1 operators. It also can be used by students, professors, and researchers in teaching activities in reactor and thermal hydraulics theory. The Simulator allows simulations of operations of start up, power maneuver, and shut down. (author)

  18. Systems for controlling the electric power of a boiling water reactor power station

    International Nuclear Information System (INIS)

    Fukunishi, Koyu; Kiyokawa, Kazuhiro.

    1975-01-01

    Object: To achieve automatic increase and decrease of electric output in accordance with a predetermined rate of increase or decrease in output when the power output is raised or lowered. Structure: An electric output signal from an atomic power plant is led to a differentiating circuit through a smoothing circuit to produce a signal for rate of change of time, and an error signal between this signal and a preset signal produced from a circuit for a preset rate of change of output with time is supplied to an analog adjuster through a limiter. In this way, the flow rate in the reactor core is adjusted by a speed controller to obtain an output of a predetermined rate of increase. The difference signal between the electric output signal and a desired value signal is passed through an absolute circuit to a comparator circuit for comparison with a predetermined threshold value setting signal. The output signal of the comparator is used to operate a relay to open the contact so as to prevent an increase or decrease in the output beyond the required level. (Kamimura, M.)

  19. Review of reactor pressure vessel evaluation report for Yankee Rowe Nuclear Power Station (YAEC No. 1735)

    International Nuclear Information System (INIS)

    Cheverton, R.D.; Dickson, T.L.; Merkle, J.G.; Nanstad, R.K.

    1992-03-01

    The Yankee Atomic Electric Company has performed an Integrated Pressurized Thermal Shock (IPTS)-type evaluation of the Yankee Rowe reactor pressure vessel in accordance with the PTS Rule (10 CFR 50. 61) and a US Regulatory Guide 1.154. The Oak Ridge National Laboratory (ORNL) reviewed the YAEC document and performed an independent probabilistic fracture-mechnics analysis. The review included a comparison of the Pacific Northwest Laboratory (PNL) and the ORNL probabilistic fracture-mechanics codes (VISA-II and OCA-P, respectively). The review identified minor errors and one significant difference in philosophy. Also, the two codes have a few dissimilar peripheral features. Aside from these differences, VISA-II and OCA-P are very similar and with errors corrected and when adjusted for the difference in the treatment of fracture toughness distribution through the wall, yield essentially the same value of the conditional probability of failure. The ORNL independent evaluation indicated RT NDT values considerably greater than those corresponding to the PTS-Rule screening criteria and a frequency of failure substantially greater than that corresponding to the ''primary acceptance criterion'' in US Regulatory Guide 1.154. Time constraints, however, prevented as rigorous a treatment as the situation deserves. Thus, these results are very preliminary

  20. Development of Abnormal Operating Strategies for Station Blackout in Shutdown Operating Mode in Pressurized Water Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Yoon, Duk-Joo; Lee, Seung-Chan; Sung, Je-Joong; Ha, Sang-Jun [KHNP CRI, Daejeon (Korea, Republic of); Hwang, Su-Hyun [FNC Tech. Co., Yongin (Korea, Republic of)

    2016-10-15

    Loss of all AC power is classified as one of multiple failure accident by regulatory guide of Korean accident management program. Therefore we need develop strategies for the abnormal operating procedure both of power operating and shutdown mode. This paper developed abnormal operating guideline for loss of all AC power by analysis of accident scenario in pressurized water reactor. This paper analyzed the loss of ultimate heat sink (LOUHS) in shutdown operating mode and developed the operating strategy of the abnormal procedure. Also we performed the analysis of limiting scenarios that operator actions are not taken in shutdown LOUHS. Therefore, we verified the plant behavior and decided operator action to taken in time in order to protect the fuel of core with safety. From the analysis results of LOUHS, the fuel of core maintained without core uncovery for 73 minutes respectively for opened RCS states after the SBO occurred. Therefore, operator action for the emergency are required to take in 73 minutes for opened RCS state. Strategy is to cooldown by using spent fuel pool cooling system. This method required to change the plant design in some plant. In RCS boundary closed state, first abnormal operating strategy in shutdown LOUHS is first abnormal operating strategy in shutdown LOUHS is to remove the residual heat of core by steam dump flow and auxiliary feedwater of SG.

  1. 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.

  2. Evaluation of management information systems: A study at a further education and training college

    Directory of Open Access Journals (Sweden)

    Marlien Herselman

    2013-03-01

    Full Text Available Background:Management information systems (MIS are pivotal in the efficient and effective running of Further Education and Training (FET colleges. Therefore, the evaluation of MIS success is an essential spoke in the wheel of FET college success. Based on an extensive literature review it was concluded that no MIS success evaluation model for FET colleges in South Africa exists. Objectives:The main objective was to propose a MIS evaluation model and evaluation tool (questionnaire, and verify the model empirically by evaluating the MIS at a selected FET college. The supporting objectives were firstly, to identify the most appropriate MIS evaluation models from literature. Secondly, to propose a MIS evaluation model for FET colleges based on the literature. Thirdly, to develop the evaluation tool (questionnaire based on these models. Fourthly, to capture and analyse data from one FET college, in order to evaluate the performance of the MIS at the college. The final supporting objective was to evaluate the proposed model by triangulating the findings from the survey with the findings from the interviews.Method:The proposed MIS evaluation model is based on the integration of three existing MIS evaluation models. The evaluation tool was developed by combining four empirically tested questionnaires that capture the constructs in the underlying models. A survey and semi-structured interviews were used as data collection methods. The statistical tests for consistency, scale reliability (Cronbach’s alpha and unidimensionality (Principal Component Analysis were applied to explore the constructs in the model.Results:Results from the empirical testing of the newly designed evaluation tool were used to refine the initial model. The qualitative data capturing and analysis added value in explaining and contextualising the quantitative findings.Conclusion: The main contribution is the SA-FETMIS success model and evaluation tool which managers can use to

  3. 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

  4. 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.)

  5. Electrical Power System Design and Station Blackout (SBO) Management in Indian Fast Breeder Reactors

    International Nuclear Information System (INIS)

    Vijaya, N. M.; Theivarajan, N.; Madhusoodanan, K.

    2015-01-01

    In the nuclear new builds and projects in design stage SBO management measures have significant role. Depending on the onsite and offsite power supply configurations, deterministic SBO duration is established. Design of systems with adequately sized battery capacities for SBO duration, special SBO Diesel Generator Sets, structured load shedding strategy to conserve battery availability to cope with SBO and to monitor the plant safety beyond SBO duration are considered as part of electrical system design now. In the design of PFBR, SBO is given due importance right from conceptual design stage. Both deterministic SBO duration and probabilistic SBO duration versus frequency were established by detailed analysis. Dedicated DC power supply systems and additional SBO DG back-up systems are in place to cope with normal and extended SBO. After the Fukushima event, there is greater requirement to demonstrate plant safety during SBO for a long duration extended over several days. In light of this accident, thermal hydraulic synthesis of PFBR has been carried out to ascertain the capability of the plant to manage a prolonged station blackout event. This has brought out the robustness of the design. Safety design features of PFBR ensure comfortable management of extended SBO. In the design of future FBR projects, current trends in the new nuclear builds and recommendations of international bodies considering Fukushima are duly considered. SBO measures by means of alternate AC power sources, redundant emergency power supply sources with less dependence on other auxiliary systems and dedicated DC power systems are considered to cope with normal and extended SBO beyond design basis. Right from the conceptual design, the system robustness to manage normal and extended SBO will be taken care with the related thermal hydraulic and associated analysis. The paper highlights these SBO management strategies in PFBR and future FBRs. (author)

  6. Management of waste associated with the decommissioning of the JASON research reactor and the nuclear laboratories at the Royal Naval College Greenwich

    International Nuclear Information System (INIS)

    Beeley, P.A.; Lockwood, R.J.S.; Hoult, D.; Major, R.

    2001-01-01

    In 1996 the UK Government announced that the Royal Naval College, Greenwich would pass to non-defence use by the millennium. As a consequence of this decision, the decommissioning of the JASON 10 kW Argonaut research reactor and the relocation of the Department of Nuclear Science and Technology (DNST) were approved by the Ministry of Defence. The decommissioning of the reactor commenced in November 1997 while DNST remained operational until October 1998. The DNST was responsible for education and training in support of the UK Naval Nuclear Propulsion Programme and operated academic laboratories for atomic and nuclear physics, health physics, instrument calibration and radiochemistry. Therefore, besides the nuclear reactor, open and sealed sources (alpha, beta and gamma), intense x-ray (sealed tube) and gamma-ray ( 60 CO and 137 Cs) sources and small 241 Am/Be neutron sources had been used in the Department for over 35 years. Decommissioning of all facilities was therefore a relatively complex task and the management of waste streams was challenging. All facilities were successfully decommissioned for unrestricted site release by December 1999 and this paper will describe the methodology used for preparation, storage, characterisation and disposal of all waste streams. The most significant waste management task during this decommissioning programme was that associated with the JASON reactor. It should be noted that the JASON reactor fuel was not designated as nuclear waste, the fuel removal and storage were covered under separate contracts and therefore no high level waste was generated. With respect to other waste streams, a combination of Monte Carlo modelling and selective sampling and analysis of the reactor materials was used to estimate the quantities of waste as follows: LLW - 76 tonnes packed in 4 half height ISO containers; LLW - 6 Tonnes packed in 200litre drums in 1 full height ISO container; ILW - 60 kg packed in approved shielded containers; FRW -121

  7. Whole Body Vibration Training is Osteogenic at the Spine in College-Age Men and Women.

    Science.gov (United States)

    Ligouri, Gianna C; Shoepe, Todd C; Almstedt, Hawley C

    2012-03-01

    Osteoporosis is a chronic skeletal disease characterized by low bone mass which is currently challenging the American health care system. Maximizing peak bone mass early in life is a cost-effective method for preventing osteoporosis. Whole body vibration (WBV) is a novel exercise method with the potential to increase bone mass, therefore optimizing peak bone and decreasing the risk for osteoporotic fracture. The aim of this investigation was to evaluate changes in bone mineral density at the hip, spine, and whole body in college-age men and women who underwent a WBV training protocol. Active men (n=6) and women (n=4), ages 18-22 participated in the WBV training; while an additional 14 volunteers (1 male, 13 female) served as controls. All participants completed baseline and follow-up questionnaires to assess health history, physical activity, dietary intake, and menstrual history. The WBV training program, using a Vibraflex 550, incorporated squats, stiff-leg dead lifts, stationary lunges, push-up holds, bent-over rows, and jumps performed on the platform, and occurred 3 times a week, for 12 weeks. Dual energy x-ray absorptiometry (Hologic Explorer, Waltham, MA, USA) was used to assess bone mineral density (BMD, g/cm(2)). A two-tailed, t-test identified significantly different changes in BMD between the WBV and control groups at the lateral spine (average change of 0.022 vs. -0.015 g/cm(2)). The WBV group experienced a 2.7% and 1.0% increase in BMD in the lateral spine and posterior-anterior spine while the control group decreased 1.9% and 0.9%, respectively. Results indicate that 12 weeks of WBV training was osteogenic at the spine in college-age men and women.

  8. BERN railway station: security assessment under a speed increase of trains from 30 to 40 km h-1

    International Nuclear Information System (INIS)

    Ribaux, C.; Capron, M.

    1994-01-01

    In the frame of the ''Rail 2000'' project, the CFF (Swiss Railways) would like to increase the speed of trains arriving in Bern station. On the eastern head, this speed would be raised from 30 to 40kmh -1 . The superstructure is formed by a three-storey building which rests on 450mm diameter steel columns.The aim of the present study was: - to determine the security loss of the station superstructure under a train impact on the columns at 40kmh -1 rather than at 30kmh -1 - to propose measures in order to get at 40kmh -1 the same security as at 30kmh -1 Four approaches are dealt with: (1)on the base of accidents statistics and of their cost; (2)review of possible dynamical approaches; (3)equivalent static load (from European railways codes); (4)energy in which, starting from its initial speed, the train loses energy on different obstacles (ballast, platform, protection devices, walls, train's own deformation) and the remaining energy is compared with the maximum energy that the column can dissipate by deformation.The conclusions are presented as a 'security plan' and the proposed protection costs are evaluated. ((orig.))

  9. The final report of ''on-the-job training'' on the CANDU reactor

    International Nuclear Information System (INIS)

    Kim, D.H.; Koh, B.J.

    1983-01-01

    This is the final Report for the technical ''on-the-job traning'' for the Wolsung CANDU nuclear power plant which is the first Pressurized Heavy Water Reactor setting up in Korea. The technical ''on-the-job traning'' was established to increase the capability for the nuclear safety evaluation in order to contribute the future safe operation of the CANDU nuclear power plant. The training has been excuted through three level courses as elementary, intermediate and ''on-the-job training'' at Wolsung power plant. The elementary course was introduction to the CANDU basics and fundamentals. The intermediate course was the more advanced course, and the detailed concepts and engineering explanations of the CANDU system had been instructed. The third course was the ''on-the-job training'' at the Wolsung plant site, which was the most emphasized course during the project. (Author)

  10. An examination of training on the VertiMax resisted jumping device for improvements in lower body power in highly trained college athletes .

    Science.gov (United States)

    Rhea, Matthew R; Peterson, Mark D; Oliverson, Jeff R; Ayllón, Fernando Naclerio; Potenziano, Ben J

    2008-05-01

    Training to develop superior muscular power has become a key component to most progressive sport conditioning programs. Conventional resistance training, plyometrics, and speed/agility modalities have all been employed in an effort to realize superlative combinations of training stimuli. New training devices such as the VertiMax resisted jump trainer are marketed as a means of improving lower body reactive power. The purpose of this study was to evaluate the effectiveness of the VertiMax, in combination with traditional training modalities, for improvements in lower body power among highly trained athletes. Forty men and women Division I collegiate athletes representing the sports of baseball, basketball, soccer, gymnastics, and track completed a 12-week mixed-methods training program. Two groups were constructed with both groups performing the same conventional resistance training and strength training exercises. The training control group performed traditional plyometric exercises while the experimental group performed similar loaded jump training on the VertiMax. Lower body power was measured before and after the training program by the TENDO FiTROdyne Powerlizer and statistically compared for differences between groups. Data analyses identified a significant (p training alone (effect size = 0.09). These data convincingly demonstrate that the VertiMax represents an effective strategy for developing lower body power among trained college athletes, when combined with traditional strength and conditioning approaches.

  11. Women Benefit More Than Men in Response to College-based Meditation Training

    Directory of Open Access Journals (Sweden)

    Rahil Rojiani

    2017-04-01

    Full Text Available Objectives: While recent literature has shown that mindfulness training has positive effects on treating anxiety and depression, there has been virtually no research investigating whether effects differ across genders—despite the fact that men and women differ in clinically significant ways. The current study investigated whether college-based meditation training had different effects on negative affect for men and women.Methods: Seventy-seven university students (36 women, age = 20.7 ± 3.0 years participated in 12-week courses with meditation training components. They completed self-report questionnaires of affect, mindfulness, and self-compassion before and after the course.Results: Compared to men, women showed greater decreases in negative affect and greater increases on scales measuring mindfulness and self-compassion. Women’s improvements in negative affect were correlated to improvements in measures of both mindfulness skills and self-compassion. In contrast, men showed non-significant increases in negative affect, and changes in affect were only correlated with ability to describe emotions, not any measures of experiential or self-acceptance.Conclusion: These findings suggest that women may have more favorable responses than men to school-based mindfulness training, and that the effectiveness of mindfulness-based interventions may be maximized by gender-specific modifications.

  12. The Effects of Balance Training on Stability and Proprioception Scores of the Ankle in College Students

    Directory of Open Access Journals (Sweden)

    Andrew L. Shim

    2015-10-01

    Full Text Available Objective: The purpose of this study was to determine if stability and proprioception scores improved on college-aged students using a slack line device. Methods: One group of 20 participants aged 18-23 from a Midwestern university performed a pre-test/post-test on a computerized posturography plate to determine Center of Pressure (CoP and Limit of Stability (LoS scores.  Participants performed three 20-30 minute sessions per week of balance and proprioceptive training using a Balance Bow for a period of four weeks. Data were analyzed (SPSS 21.0 using a dependent t-test to determine if any changes occurred between pre- and post-test scores after four weeks.  Results: The analyses found no significance difference in Center of Pressure (CoP, normal stability eyes open (NSEO, normal stability eyes closed (NSEC, perturbed stability eyes open (PSEO, perturbed stability eyes closed (PSEC, or LoS forward (F, backward (B, or right (R scores in college-aged participants. A significant difference was found in LoS left (L and a notable trend towards significance was found in LoS R results. Conclusion: With the exception of LoS L stability scores, it was concluded that 12 sessions of 20-30 minutes, utilizing a slack line device, over a four week training period did not significantly improve stability and proprioceptive scores of the ankle in college-aged participants. Keywords: Proprioception, Limit of Stability (LoS, Center of Pressure (CoP, slack line device

  13. Physical Training Program Guidelines for U.S. Navy Recruits: Preparing Recruits for Battle Stations

    National Research Council Canada - National Science Library

    Trone, D

    1999-01-01

    ...) a directive instructing RDCs to ensure that the physical conditioning program for women is sufficient to prepare them for successful completion of the final physical readiness test and Battle Stations...

  14. 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.

  15. New digital control and power protection system of VR 1 training reactor

    International Nuclear Information System (INIS)

    Kropik, M.; Matejka, K.; Juoeickova, M.

    2005-01-01

    The contribution describes the new VR-1 training reactor control and power protection system at the Czech Technical University in Prague. The control system provides safety and control functions, calculates average values of the important variables and sends data and system status to the human-machine interface. The upgraded control system is based on a high quality industrial PC. The operating system of the PC is the Microsoft Windows XP with the real time support RTX of the VentureCom Company. The software was developed according to requirements in MS Visual C. The independent power protection system is a component of the reactor safety (protection) system with high quality and reliability requirements. The digital system is redundant; each channel evaluates the reactor power and the velocity of power changes and provides safety functions. The digital part of the channel is multiprocessor-based. The software was developed with respect to nuclear standards. The software design was coded in the C language regarding the NRC restrictions. Configuration management, verification and validation accompanied the software development. Both systems were thoroughly tested. Firstly, the non active tests were carried out. During these tests, the active core of the reactor was subcritical; the input signals were generated from HPIB and VXI controlled instruments to simulate different operational and safety events. The software for instruments control and tests evaluation utilized Agilent VEE development system. After the successful non active checking, the active tests followed. (author)

  16. Reduced enrichment fuel and its reactivity effects in the University Training Reactor Moata

    International Nuclear Information System (INIS)

    Wilson, D.J.

    1983-08-01

    Concern for nuclear proliferation is likely to preclude future supply of highly enriched uranium fuel for research reactors such as the University Training Reactor Moata. This study calculates the fuel densities necessary to maintain the reactivity per plate of the present high enrichment (90 per cent 235 U) fuel for a range of lower enrichments assuming that no geometry changes are allowed. The maximum uranium density for commercially available aluminium-type research reactor fuels is generally considered to be about 1.7 g cm -3 . With this density limitation, the minimum enrichment to maintain present reactivity per plate is about 35 per cent 235 U. For low enrichment (max. 20 per cent 235 U) fuel, the required U density is about 2.9 g cm -3 , which is beyond the expected range for UAl/sub x/-Al but within that projected for the longer term development and full qualification for U 3 O 8 -Al. Medium enrichment (nominally 45 per cent 235 U) Al/sub x/-Al would be entirely satisfactory as an immediate replacement fuel, requiring no modifications to the reactor and operating procedures, and minimal reappraisal of safety issues. Included in this study are calculations of the fuel coefficients at various enrichments, the effect of replacing standard fuel plates or complete elements with 45 per cent enriched fuel, and the reactivity to be gained by replacing 12-plate with 13-plate elements

  17. 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.

  18. Impact of Train Schedule on Pedestrian Movement on Stairway at Suburban Rail Transit Station in Mumbai, India

    Directory of Open Access Journals (Sweden)

    Shah Jiten

    2015-01-01

    Full Text Available Pedestrian flow takes place in confined environment on stairways under the influence of composition, direction of movement, and schedule of trains. During peak-period, alighting and boarding rate is quite high resulting in very high pedestrian movement from one platform to the other to catch the next train at interchange stations. The transfer of passengers from railway platforms through common undivided stairways becomes difficult, uncomfortable, and unsafe at times when pedestrian flow reaches the capacity level. Understanding of criteria defining quality of flow that affect the effectiveness of facilities like stairways in handling the pedestrian traffic is vital for planning and designing of such facilities to ensure the desired level of service as well as safety in case of emergency. The present paper is based on the study of pedestrian movement on stairways at busy suburban rail transit interchange station at Dadar in Mumbai, India. Pedestrian movements are captured through videography at two stairways and the effect of bidirectional movement on average walking speed is analyzed. The ascending flow in small proportion is found to be more influential in causing speed reduction on undivided stairways. The outcome of the study is useful for capacity and level of service analysis while planning and designing the transit station stairways.

  19. Texas Yehaa !!!

    DEFF Research Database (Denmark)

    Kjellberg, Kurt

    2001-01-01

    Indtryk fra et besøg på SLA, Special Libraries Associations årlige konference, San Antonio, Texas, USA, 9.-13. juni 2001. "An Information Odyssey: Seizing the Competitive Advantage"......Indtryk fra et besøg på SLA, Special Libraries Associations årlige konference, San Antonio, Texas, USA, 9.-13. juni 2001. "An Information Odyssey: Seizing the Competitive Advantage"...

  20. Texas situation

    International Nuclear Information System (INIS)

    Avant, R.V. Jr.; Bowmer, W.J.

    1986-01-01

    The Texas Low-Level Radioactive Waste Disposal Authority was formed in 1981 to address the Texas low-level radioactive waste problem consistent with the direction of P.L. 96-573. The Authority has completed technical tasks, including source term evaluations, preliminary conceptual designs, economic assessments, and long-range planning, and has work in progress on facility design, site selection, operating procedures, and licensing. Site selection has been the major technical activity and will be completed in 1987 after on-site evaluations of potential sites. The Authority expects to have its site licensed and operating in 1992. Texas has been the leader in site selection. Political concerns and the uncertainty of the national agenda led Texas policy makers to slow down the state's progress. The lessons learned through the Texas situation should be instructive to other states and compacts and may well be a prediction of events for these other groups. This paper discusses the background and status of Texas development activities, future plans, and lessons learned

  1. An independent safety assessment of Department of Energy nuclear reactor facilities: Training of operating personnel and personnel selection

    International Nuclear Information System (INIS)

    Drain, J.F.

    1981-02-01

    This study has been prepared for the Department of Energy's Nuclear Facilities Personnel Qualification and Training (NFPQT) Committee. Its purpose is to provide the Committee with background information on, and assessment of, the selection, training, and qualification of nuclear reactor operating personnel at DOE-owned facilities

  2. "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…

  3. A central European training course on reactor physics and kinetics - the 'Eugene Wigner Course' - Organisers view

    International Nuclear Information System (INIS)

    Boeck, H.; Villa, M.; Matejka, K.; Sklenka, L.; Miglierini, M.; Sukods, C.

    2004-01-01

    Initiated by the 5th Framework Program of the European Commission, the European Nuclear Engineering Network (ENEN) is preparing the future European Nuclear Education schemes, degrees and requirements. To fully utilize the benefits of international cooperation and to promote the knowledge of students in nuclear engineering a 2.5 weeks course has been held, both in spring 2003 and 2004. The main emphasis of the course is to perform reactor physics and kinetics experiments on three different research- and training reactors in three different locations (Vienna, Prague, Budapest). The experimental work is preceded by theoretical lectures aiming to prepare the students for the experiments (Bratislava). The students' work will be evaluated, and upon success the students will get a certificate. The finally accepted credit (ECTS) value will be determined by the students' home university. The ENEN-recommended value is between 6 and 8 ECTS. The more detailed description of the course will be given in the full paper. (author)

  4. Pilot program: NRC severe reactor accident incident response training manual: US Nuclear Regulatory Commission response

    International Nuclear Information System (INIS)

    Sakenas, C.A.; McKenna, T.J.; Perkins, K.; 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. US Nuclear Regulatory Commission Response is the fifth 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 NRC response modes, organizations, and official positions; roles of other federal agencies are also described briefly. Each volume serves, respectively, as the text for a course of instruction in a series of courses for NRC response personnel. These materials do not provide guidance or license requirements for NRC licensees. 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

  5. Radiation field studies at the training and research reactor AKR of the Dresden Technical University

    International Nuclear Information System (INIS)

    Leuschner, A.; Reiss, U.; Pretzsch, G.

    1983-01-01

    Results of radiation field studies in the experimental channels of the training and research reactor of the Technical University of Dresden are presented. The flux densities of thermal, intermediate and fast neutrons were determined by means of activation detectors., Gamma dose rates have been measured by thermoluminescent dosimeters. The measured results show symmetry with respect to the vertical axis of the reactor and allow to draw conclusions with regard to the efficiency of the individual layers of the shield. They are an essential basis of performing irradiation experiments in the experimental channels. The results of measurements were compared with those of shielding and design calculations. Taking into account the measuring errors and the approximations used in the computational models, no unexpected deviations have been observed. Hence, the measured and calculated results can be assessed to be in good agreement. (author)

  6. Training simulator for nuclear power plant reactor control model and method

    International Nuclear Information System (INIS)

    Czerbuejewski, F.R.

    1975-01-01

    A description is given of a method and system for the real-time dynamic simulation of a nuclear power plant for training purposes, wherein a control console has a plurality of manual and automatic remote control devices for operating simulated control rods and has indicating devices for monitoring the physical operation of a simulated reactor. Digital computer means are connected to the control console to calculate data values for operating the monitoring devices in accordance with the control devices. The simulation of the reactor control rod mechanism is disclosed whereby the digital computer means operates the rod position monitoring devices in a real-time that is a fraction of the computer time steps and simulates the quick response of a control rod remote control lever together with the delayed response upon a change of direction

  7. Pilot program: NRC severe reactor accident incident response training manual. Overview and summary of major points

    International Nuclear Information System (INIS)

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

    1987-02-01

    Overview and Summary of Major Points is the first in a series of volumes that collectively summarize the U.S. 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 assessment. Other volumes in the series are: Volume 2-Severe Reactor Accident Overview; Volume 3- Response of Licensee and State and Local Officials; Volume 4-Public Protective Actions-Predetermined Criteria and Initial Actions; Volume 5 - U.S. Nuclear Regulatory Commission. Each volume serves, respectively, as the text for a course of instruction in a series of courses for NRC response personnel. These materials do not provide guidance or license requirements for NRC licensees. The volumes have been organized into these training modules to accommodate the scheduling and duty needs of participating NRC staff. Each volume is accompanied by an appendix of slides that can be used to present this material

  8. International Project on Innovative Nuclear Reactors and Fuel Cycles: Introduction and Education and Training Activity

    International Nuclear Information System (INIS)

    Fesenko, G.; Kuznetsov, V.; Phillips, J.R.; Rho, K.; Grigoriev, A.; Korinny, A.; Ponomarev, A.

    2015-01-01

    The IAEA’s International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO) was established in 2000 through IAEA General Conference resolution with aim to ensure that sustainable nuclear energy is available to help meet the energy needs of the 21st century. INPRO seeks to bring together technology holders, users and newcomers to consider jointly the international and national actions required for achieving desired innovations in nuclear reactors and fuel cycles, with a particular focus on sustainability and needs of developing countries. It is a mechanism for INPRO Members to collaborate on topics of joint interest. INPRO activities are undertaken in close cooperation with Member States in the following main areas: Global Scenarios, Innovations, Sustainability Assessment and Strategies, Policy and Dialogue. The paper presents short introduction in INPRO and specifically the distant Education and Training INPRO activity on important topics of nuclear energy sustainability to audiences in different Member States. These activities can support capacity building and national human resource development in the nuclear energy sector. The main benefit of such training courses and workshops is that it is not only targeted to students, but also to lecturers of technical and nuclear universities. Moreover, young professionals working at nuclear energy departments, electric utilities, energy ministries and R&D institutions can participate in such training and benefit from it. (authors)

  9. Technical evaluation report on the monitoring of electric power to the reactor-protection system for the Pilgrim Nuclear Power Station

    International Nuclear Information System (INIS)

    Selan, J.C.

    1982-01-01

    This report documents the technical evaluation of the monitoring of electric power to the reactor protection system (RPS) at the Pilgrim Nuclear Power Station. The evaluation is to determine if the proposed design modification will protect the RPS from abnormal voltage and frequency conditions which could be supplied from the power supplies and will meet certain requirements set forth by the Nuclear Regulatory Commission. The proposed design modifications will protect the RPS from sustained abnormal voltage and frequency conditions from the supplying sources

  10. Technology, safety and costs of decommissioning a reference boiling water reactor power station. Volume 1. Main report. Technical report, September 1977-October 1979

    International Nuclear Information System (INIS)

    Oak, H.D.; Holter, G.M.; Kennedy, W.E. Jr.; Konzek, G.J.

    1980-06-01

    Technology, safety and cost information is given for the conceptual decommissioning of a large (1100MWe) boiling water reactor (BWR) power station. Three approaches to decommissioning, immediate dismantlement, safe storage with deferred dismantlement and entombment, were studied to obtain comparisons between costs, occupational radiation doses, potential dose to the public and other safety impacts. It also shows the sensitivity of decommissioning safety and costs to the power rating of a BWR in the range of 200 to 1100 MWE

  11. Technology, safety and costs of decommissioning a reference boiling water reactor power station. Volume 1. Main report. Technical report, September 1977-October 1979

    Energy Technology Data Exchange (ETDEWEB)

    Oak, H.D.; Holter, G.M.; Kennedy, W.E. Jr.; Konzek, G.J.

    1980-06-01

    Technology, safety and cost information is given for the conceptual decommissioning of a large (1100MWe) boiling water reactor (BWR) power station. Three approaches to decommissioning, immediate dismantlement, safe storage with deferred dismantlement and entombment, were studied to obtain comparisons between costs, occupational radiation doses, potential dose to the public and other safety impacts. It also shows the sensitivity of decommissioning safety and costs to the power rating of a BWR in the range of 200 to 1100 MWE.

  12. Radiological survey of the area surrounding the National Reactor Testing Station, Idaho Falls, Idaho. Date of survey: 1 and 2 February 1972

    International Nuclear Information System (INIS)

    1974-01-01

    The Aerial Radiological Measuring System (ARMS) was used to survey the National Reactor Testing Station (NRTS) during February 1972. The purpose of the survey was primarily to identify the presence of Ru-106 and Rh-106 in a release from the Chemical Processing Plant at NRTS. Additionally, the gamma-ray terrestrial exposure rate levels were mapped and the distribution of any man-made isotopes was located and defined

  13. 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…

  14. Transmit Power Minimization and Base Station Planning for High-Speed Trains with Multiple Moving Relays in OFDMA Systems

    KAUST Repository

    Ghazzai, Hakim

    2016-03-15

    High-speed railway system equipped with moving relay stations placed on the middle of the ceiling of each train wagon is investigated. The users inside the train are served in two hops via the orthogonal frequency-division multiple access (OFDMA) technology. In this work, we first focus on minimizing the total downlink power consumption of the base station (BS) and the moving relays while respecting specific quality of service (QoS) constraints. We first derive the optimal resource allocation solution in terms of OFDMA subcarriers and power allocation using the dual decomposition method. Then, we propose an efficient algorithm based on the Hungarian method in order to find a suboptimal but low complexity solution. Moreover, we propose an OFDMA planning solution for high-speed train by finding the maximal inter-BS distance given the required user data rates in order to perform seamless handover. Our simulation results illustrate the performance of the proposed resource allocation schemes in the case of the 3GPP Long Term Evolution-Advanced (LTE-A) and compare them with previously developed algorithms as well as with the direct transmission scenario. Our results also highlight the significant planning gain obtained thanks to the use of multiple relays instead of the conventional single relay scenario.

  15. Space Flight Resource Management Training for International Space Station Flight Controllers

    Science.gov (United States)

    O'Keefe, William S.

    2011-01-01

    Training includes both SFRM-dedicated lessons and SFRM training embedded into technical lessons. Goal is to reduce certification times by 50% and integrated simulations by 75-90%. SFRM is practiced, evaluated and debriefed in part task trainers and full-task simulation lessons. SFRM model and training are constantly being evaluated against student/management feedback, best practices from industry/ military, and latest research.

  16. 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...

  17. 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)

  18. Trusses Of Tensegrity Type In A Concept Of Train Station Renovation In Żary

    Directory of Open Access Journals (Sweden)

    Lechocka Paulina

    2015-09-01

    Full Text Available The first railway station in Żary was built in 1843 in Germany. After the Second World War and years of socialism in Poland the meaning of railway decreased and its technical condition deteriorated. Now the building needs renovation and change of function. Tensegrity structures may be useful in renovation of platforms shelter. They are strut and tie construction, in which there is self-stabilization between compressed and tensioned elements. Conception of new platform shelter is based on exemplary tensegrity module consist of three struts and nine cables (called „Simplex”. Tensegrity would make railway station more modern, but not cover its original elevation.

  19. In-tank examination and experience with MTR fuel integrity at the Imperial College reactor

    Energy Technology Data Exchange (ETDEWEB)

    Franklin, S.; Chapman, N.; Robertson, B.; Shields, A.; Velez-Moss, S. [Imperial College of Science Technology and Medicine, Silwood Park, Ascot (United Kingdom); Boeck, H.; Schachner, H.; Klapfer, E. [Atominstitut of the Austrian Universities, Vienna (Austria)

    2000-07-01

    Many changes have occurred in the UK nuclear industry over the past 10 years: nuclear power/radiation research groups have closed, the fast reactor program ceased, and the United Kingdom Atomic Energy Authority (UKAEA) changed emphasis to decommissioning. Many UK research reactors and associated facilities have closed. In 1997, the 100 kW CONSORT pool-type reactor became the last civil nuclear research reactor surviving in the UK. Although VIPER, NEPTUNE and VULCAN remain in the defense field, they have lower steady state neutron fluxes. With so many reactors closing, CONSORT has a strong future. In fact, it underpins many research projects, monitoring schemes and power plants - but each provides a relatively small amount of business. The future strategy of the reactor is being reviewed this year. First criticality took place April 1965, and so in parallel, it is important to understand what the residual technical life of the reactor might be. This paper presents the results of an in-service inspection, which took place in August 1999. (author)

  20. In-tank examination and experience with MTR fuel integrity at the Imperial College reactor

    International Nuclear Information System (INIS)

    Franklin, S.; Chapman, N.; Robertson, B.; Shields, A.; Velez-Moss, S.; Boeck, H.; Schachner, H.; Klapfer, E.

    2000-01-01

    Many changes have occurred in the UK nuclear industry over the past 10 years: nuclear power/radiation research groups have closed, the fast reactor program ceased, and the United Kingdom Atomic Energy Authority (UKAEA) changed emphasis to decommissioning. Many UK research reactors and associated facilities have closed. In 1997, the 100 kW CONSORT pool-type reactor became the last civil nuclear research reactor surviving in the UK. Although VIPER, NEPTUNE and VULCAN remain in the defense field, they have lower steady state neutron fluxes. With so many reactors closing, CONSORT has a strong future. In fact, it underpins many research projects, monitoring schemes and power plants - but each provides a relatively small amount of business. The future strategy of the reactor is being reviewed this year. First criticality took place April 1965, and so in parallel, it is important to understand what the residual technical life of the reactor might be. This paper presents the results of an in-service inspection, which took place in August 1999. (author)

  1. 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,…

  2. Assessment of the Professional Training Course under Watershed Project at Fatehjang Field Station, Punjab, Pakistan

    International Nuclear Information System (INIS)

    Khan, M. N.; Hassan, T.; Shah, H.; Abid, S.; Raza, I.; Abbasi, S. S.

    2015-01-01

    Watershed Project organizing different professional trainings to create awareness about water saving technologies as solar powered irrigation system, drip irrigation, sprinkler irrigation, micro catchment, rooftop rainwater harvesting and irrigation scheduling. Therefore, the project activities also include the training of the professionals from the line departments for the demonstrated technologies to foster the process of adoption. For this purpose Climate and Alternate Energy Water Resources Institute, NARC, organized a professional training on Water Rehabilitation and Irrigation Technology Improvements in April, 2014 in collaboration with ICARDA and USDA. Twenty seven professionals from different organizations and departments namely; Al-Mustafa Development Network (ADN), Taleem Foundation, Islamic International University (IIUI) Islamabad, National Agricultural Research Centre (NARC), National Centre for Rural Development (NCRD), National Rural Support Programme (NRSP), On-Farm Water Management (OFWM), Water Management (WM), Potohar Organization for Development Advocacy (PODA), Quaid-i-Azam University (QAU) and Environmental Sciences actively participated in the professional training. The post-training assessment showed that it had positive impact on the awareness of professionals. Majority of the participants were strongly and merely agreed upon the training practicality, technologies adoption probability and its advantages at farmer's field. Overall, most of the training participants were satisfied with the knowledge sharing presentations about the specific technologies discussed during the training. (author)

  3. Business operations and decommissioning strategy for imperial college London research reactor 'Consort' - A financial risk management approach

    International Nuclear Information System (INIS)

    Franklin, S.J.; Gardner, D.; Mumford, J.; Lea, R.; Knight, J.

    2005-01-01

    Imperial College London (IC) operates commercially a 100 kW research reactor, and as site licensee is responsible for funding both operations and eventual decommissioning. With long lead times ahead urgent decisions on the future business options have had to be made in 2004/5 including choices on whether to move to early decommissioning, recognising the high costs entailed, or to pursue continuing operations involving life extension measures such as refuelling. To develop a coherent overall approach strategy a financial risk driven programme was initiated to help define a robust transparent business and termination case for the reactor. This study was carried out in collaboration with a UK firm of financial risk experts, PURE Risk Management Ltd (PURE), working within a dedicated IC London reactor project team. This work evaluated immediate closure options due to financial constraints or life limiting failures, and options for continuing operation extending to 2028. Decommissioning and clean up were reviewed. Bespoke financial models created single value cost outputs and ranges of probabilistic net present values (NPV) for decommissioning costs and financial provisions to meet those costs at various levels of risk acceptance and regulatory compliance. (author)

  4. The Use of Facebook in Blended Course in Teacher Training College

    Directory of Open Access Journals (Sweden)

    Milya Sari

    2014-07-01

    Full Text Available Future educational challenges are related to technology, especially information and communications technology (ICT. The ICT has a very big influence to the learners. Many students have already used social media ‘facebook’ and ‘twitter’, but not so with their teachers. The rapid globalization and ICT development requires a change in attitude and mindset of teachers and students, including in Teacher Training College (LPTK. A good approach is to integrate technology with education through blended learning models (BLM, that is learning that combines face-to-face learning activities and learning online through social media facebook. One of the advantages of BLM is to improve the interaction between learners, between learners and educators, and learners with different learning resources anytime and anywhere without being limited by space and time.

  5. 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…

  6. Assertiveness Skills Training Efficiency on College Students’ Persuasive Subjective Norms against Substance Abuse

    Directory of Open Access Journals (Sweden)

    M. Barati

    2011-10-01

    Full Text Available Introduction & Objective: The prevalence of substance abuse among college students is increasing drastically and requires immediate skill-based substance abuse intervention such as assertive skills. The purpose of this study was to develope the healthy behavior to change the subjective norms of students in order to decrease their tendency towards substance abuse. Materials & Methods: A pre and post nonequivalent control group design study carried out on college students. A total number of 140 students were selected through randomized cluster sampling and randomly assigned to the intervention (n=70 and the control (n=70 groups. The data-gathering tool consisted of a self-report questionnaire assessing the variables of moral , descriptive , and injunctive norms. After the diagnostic evaluation, assertive skills promoting program was applied to persuade the participants against substances abuse. Respondents in the control and experimental groups completed questionnaires at baseline and 2 months after the intervention. Results: The result showed that educational manipulation had significant effect on intervention group’s average response for moral norms (t= -3.36, P<0.001, descriptive norms (t= -3.07, P<0.003, and injunctive norms for persuading substance abuse (t=-3.79, P<0.000.Conclusion: These findings suggest that assertive skills training would be an efficient tool in drug abuse prevention programs among adolescents that should also be included in the comprehensive school health programs. (Sci J Hamadan Univ Med Sci 2011;18(3:40-49

  7. Reactor

    International Nuclear Information System (INIS)

    Toyama, Masahiro; Kasai, Shigeo.

    1978-01-01

    Purpose: To provide a lmfbr type reactor wherein effusion of coolants through a loop contact portion is reduced even when fuel assemblies float up, and misloading of reactor core constituting elements is prevented thereby improving the reactor safety. Constitution: The reactor core constituents are secured in the reactor by utilizing the differential pressure between the high-pressure cooling chamber and low-pressure cooling chamber. A resistance port is formed at the upper part of a connecting pipe, and which is connect the low-pressure cooling chamber and the lower surface of the reactor core constituent. This resistance part is formed such that the internal sectional area of the connecting pipe is made larger stepwise toward the upper part, and the cylinder is formed larger so that it profiles the inner surface of the connecting pipe. (Aizawa, K.)

  8. University of Florida Training Reactor: Annual progress report, September 1, 1986-August 31, 1987

    International Nuclear Information System (INIS)

    Vernetson, W.G.

    1987-11-01

    The University of Florida Training Reactor's overall utilization for the past reporting year (September 1986 through August 1987) has returned to the increased levels of quality usage characteristic of the two years prior to the last reporting year when the maintenance outage to repair sticking control blades reduced availability for the year to near 50%. Indeed, the 91.5% availability factor for this reporting year is the highest in the last five years and probably in the 27 year history of the facility. As a final statement on the effectiveness of the corrective maintenance last year, the overall availability factor has been over 94% since returning to normal operations. The UFTR continues to experience a high rate of utilization in a broad spectrum of areas with total utilization continuing near the highest levels recorded in the early 1970's. This increase has been supported by a variety of usages ranging from research and educational utilization by users within the University of Florida as well as other researchers and educators around the state of Florida through the support of the DOE Reactor Sharing Program and several externally supported usages. Significant usage has also been devoted to facility enhancement where a key ingredient for this usage has been a stable management staff. Uses, reactor operation, maintenance, technical specifications, radioactive releases, and research programs are described in this report

  9. Reactivity worth measurement of the control blades of the University of Florida training reactor

    International Nuclear Information System (INIS)

    Quintero-Leyva, Barbaro

    1997-01-01

    A series of experiments were carried out in order to measure the reactivity worth of the safety and regulating blades of the University of Florida Training Reactor (UFTR) using the Inverse Kinetics, the Inverse Kinetics-Rod Drop method and the Power Ratio. The reactor's own instrumentation (compensated ion chamber) and an independent counting system (fission chamber) were used. A very smooth exponential decay of the flux was observed after 6s of the beginning of the transients using the reading of the reactor detector. The results of the measurements of the reactivity using both detectors were consistent and in good agreement. The compensated ion chamber showed a very smooth exponential behavior; this suggests that if we could record the power for a small sample time, say 0.1 s from the beginning of the transient, several additional research projects could be accomplished. First, precise intercomparison of the methods could be achieved if the statistics level is acceptable. Second, a precise description of the bouncing of the blades and its effects on the reactivity could be achieved. Finally, the design of a reactivity-meter could be based on such study. (author)

  10. Research Reactor Utilization at the University of Utah for Nuclear Education, Training and Services

    International Nuclear Information System (INIS)

    Jevremovic, T.; Choe, D.O.

    2013-01-01

    In the years of nuclear renaissance we all recognize a need for modernizing the approaches in fostering nuclear engineering and science knowledge, in strengthening disciplinary depth in students’ education for their preparation for workforce, and in helping them learn how to extend range of skills, develop habits of mind and subject matter knowledge. The education infrastructure at the University of Utah has been recently revised to incorporate the experiential learning using our research reactor as integral part of curriculum, helping therefore that all of our students build sufficient level of nuclear engineering literacy in order to be able to contribute productively to nuclear engineering work force or continue their education toward doctoral degrees. The University of Utah TRIGA Reactor built 35 years ago represents a university wide facility to promote research, education and training, as well as is used for various applications of nuclear engineering, radiation science and health physics. Our curriculum includes two consecutive classes for preparation of our students for research reactor operating license. Every year the US Nuclear Regulatory Commission’s representatives hold the final exam for our students. Our activities serve the academic community of the University of Utah, commercial and government entities, other universities and national laboratories as well. (author)

  11. Reactor

    International Nuclear Information System (INIS)

    Ikeda, Masaomi; Kashimura, Kazuo; Inoue, Kazuyuki; Nishioka, Kazuya.

    1979-01-01

    Purpose: To facilitate the construction of a reactor containment building, whereby the inspections of the outer wall of a reactor container after the completion of the construction of the reactor building can be easily carried out. Constitution: In a reactor accommodated in a container encircled by a building wall, a space is provided between the container and the building wall encircling the container, and a metal wall is provided in the space so that it is fitted in the building wall in an attachable or detatchable manner. (Aizawa, K.)

  12. Training at the masters degree level in physics and technology of nuclear reactors in the uk

    International Nuclear Information System (INIS)

    Weaver, D.R.

    2000-01-01

    This paper discusses the current situation of university-based training for the nuclear power industry in the UK, drawing on information gathered as part of the survey for a review currently being undertaken by the Committee for Technical and Economic Studies on Nuclear Energy Development and Fuel Cycle (NDC) of the Nuclear Energy Agency (NEA) of the OECD. A particular focus will be the Physics and Technology of Nuclear Reactors MSc course at the University of Birmingham. In the past there were other similar MSc courses in the UK, but through the evolution of time the Birmingham course is now unique in its role of providing masters level training so specifically aimed at the commercial nuclear programme. Mention will, however, be made of other training at the postgraduate level elsewhere in the UK. A description is given of the need to consider a new form of relationship between industry and university in order to provide optimise the provision of masters level training. (author)

  13. Experience in the recruitment, organization and training of operations and maintenance personnel for the Malaysian research reactor

    International Nuclear Information System (INIS)

    Jamal Khair Ibrahim.

    1983-01-01

    The TRIGA Reactor located at the Tun Ismail Atomic Research Centre (PUSPATI) Complex is owned and operated by the Nuclear Energy Unit of the Prime Minster's Department. The operations and maintenance personnel are part and parcel of the national civil service organization. As such, the requirement and remuneration of these personnel are handled by a central federal government personnel management agency in common with personnel from other federal government agencies. In addition, the reactor is the first and only one in Malaysia, a developing country, which is the process of committing herself towards a nuclear power programme. These factors coupled with the absence of an independent reactor operator licensing agency posed unique problems in the recruitment, organization, training and licensing of operations personnel for the facility. The paper discusses these factors and their bearing on the recruitment, training, licensing and career development prospects of the PUSPATI TRIGA Reactor operators. (author)

  14. The Short-Term Effectiveness of a Suicide Prevention Gatekeeper Training Program in a College Setting with Residence Life Advisers

    Science.gov (United States)

    Tompkins, Tanya L.; Witt, Jody

    2009-01-01

    Although the college years prove to be a vulnerable time for students and a critical period for suicide prevention, few school-based prevention strategies have been empirically evaluated. The current study examined the short-term effects of Question, Persuade, and Refer (QPR), a gatekeeper training program that teaches how to recognize warning…

  15. An Evaluation of a Unique Gatekeeper Training for Suicide Prevention of College Students: Demonstrating Effective Partnering within Student Affairs

    Science.gov (United States)

    House, Lisa A.; Lynch, Joseph F.; Bane, Mary

    2013-01-01

    For college students, suicide is the second leading cause of death. In this study, we evaluated a gatekeeper training suicide prevention program that emphasizes emotional connectivity with students in crisis and incorporates the collaborative efforts between Housing/Residential Programs and the Counseling Center. Participants consisted of graduate…

  16. An Evaluation of the Employee Training and Development Process for Nicolet Area Technical College's Basic Education Program.

    Science.gov (United States)

    Karl, Luis C.

    The adult basic education (ABE) program at Nicolet Area Technical College (NATC) evaluated its training and development (T&D) process for new basic education instructors. The study gathered monitoring and screening criteria that addressed valuable components for use in an instrument for validating effectiveness of the ABE program (T&D)…

  17. 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)

  18. 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)

  19. Calibration of new I and C at VR-1 training reactor

    International Nuclear Information System (INIS)

    Kropik, Martin; Jurickova, Monika

    2011-01-01

    The paper describes a calibration of the new instrumentation and control (I and C) at the VR-1 training reactor in Prague. The I and C uses uncompensated fission chambers for the power measurement that operate in a pulse or a DC current and a Campbell regime, according to the reactor power. The pulse regime uses discrimination for the avoidance of gamma and noise influence of the measurement. The DC current regime employs a logarithmic amplifier to cover the whole reactor DC current power range with only one electronic circuit. The system computer calculates the real power from the logarithmic data. The Campbell regime is based on evaluation of the root mean square (RMS) value of the neutron noise. The calculated power from Campbell range is based on the square value of the RMS neutron noise data. All data for the power calculation are stored in computer flash memories. To set proper data there, it was necessary to carry out the calibration of the I and C. At first, the proper discrimination value was found while examining the spectrum of the neutron signal from the chamber. The constants for the DC current and Campbell calculations were determined from an independent reactor power measurement. The independent power measuring system that was used for the calibration was accomplished by a compensated current chamber with an electrometer. The calculated calibration constants were stored in the computer flash memories, and the calibrated system was again successfully compared with the independent power measuring system. Finally, proper gamma discrimination of the Campbell system was carefully checked.

  20. Recruiting, Training, Retaining, and Promoting the Workforce of the Future at Comanche Peak Steam Electric Station

    International Nuclear Information System (INIS)

    Sunseri, M.

    1999-01-01

    TXU Electric expects to encounter a relatively high turnover in the workforce in the coming years. To prepare for this challenge and to maintain a high level of performance, a number of approaches are being implemented. These approaches involve recruiting experienced personnel, recruiting and developing local nonexperienced personnel, and developing current employees. Through these approaches, TXU Electric expects to maintain a high-quality workforce for the continued support of Comanche Peak Steam Electric Station

  1. [To the issue on the optimization and regulation of microclimate in the subway trains and stations].

    Science.gov (United States)

    Leksin, A G; Beresneva, T G; Kaptsov, V A; Korotich, L P; Evlampieva, M N; Timoshenkova, E V

    2014-01-01

    There is presented an overview of currently existing regulatory framework governing the parameters of the microclimate in the salons of subway passenger cars and stations. Analysis of the normative documents indicated that they contain very incomplete, contradictory, often unfounded information about the parameters of microclimate parameters in salons of subway rolling stock. Also, there are no clear cut hygienically-sound requirements for the work of imposed on the rolling stock subway systems provide microclimate, including new systems for air conditioning and disinfection.

  2. Smoke flow temperature beneath tunnel ceiling for train fire at subway station: Reduced-scale experiments and correlations

    International Nuclear Information System (INIS)

    Meng, Na; Wang, Qiang; Liu, Zhaoxia; Li, Xiao; Yang, He

    2017-01-01

    Highlights: • Reduced-scale experiments on train fire at subway station. • Smoke flow temperature beneath tunnel ceiling measured and correlated. • Effect of platform-tunnel conjunction door type on smoke temperature is clarified. - Abstract: This paper is to investigate the smoke flow temperature beneath tunnel ceiling for a train on fire stopping besides a subway station. Experiments were carried out in a reduced-scale (1:10) subway station model to study the maximum smoke temperature and the longitudinal temperature distribution beneath the tunnel ceiling by considering platform-tunnel conjunction doors of two types: the full-seal platform screen door (PSD) and the full-height safety door. For the maximum temperature beneath the tunnel ceiling, it is found to be well correlated non-dimensionally with heat release rate by a 3.65 and a 2.92 power law function for the full-seal platform screen door and the full-height safety door, respectively. For the longitudinal temperature distribution along the tunnel ceiling, it can be well correlated by an exponential function for both types of platform-tunnel conjunction doors. Concerning the effect of the door type, the maximum temperature is lower and the longitudinal temperature decays faster for full-height safety door than that for full-seal PSD. This is due to that with the full-height safety door, the effective width of the tunnel ceiling is widened, which results in more heat losses from the smoke flow to the ceiling.

  3. Performance of small reactors at universities for teaching, research, training and service (TRTS): thirty five years' experience with the Dalhousie University SLOWPOKE-2 reactor

    Energy Technology Data Exchange (ETDEWEB)

    Chatt, A., E-mail: a.chatt@dal.ca [Dalhousie Univ., Trace Analysis Research Centre, Dept. of Chemistry, Halifax, Nova Scotia (Canada)

    2013-07-01

    The Dalhousie University SLOWPOKE-2 Reactor (DUSR) facility, operated during 1976-2011, was the only research reactor in Atlantic Canada as well as the only one associated with a chemistry department in a Canadian university. The most outstanding features of the facility included: a rapid (100 ms) cyclic pneumatic sample transfer system, a permanently installed Cd-site, and a Compton-suppression gamma-ray spectrometer. The usage encompassed fundamental as well as applied studies in various fields using neutron activation analysis (NAA). The facility was used for training undergraduate/graduate students, postdoctoral fellows, technicians, and visiting scientists, and for cooperative projects with other universities, research organizations and industries. (author)

  4. Effect of health-promoting posters placed on the platforms of two train stations in Copenhagen, Denmark, on the choice between taking the stairs or the escalators

    DEFF Research Database (Denmark)

    Iversen, Mette Kathrine; Händel, M N; Nydal Jensen, Eva

    2007-01-01

    OBJECTIVE: The purpose of this study was to determine whether posters placed on the platforms of two train stations in Copenhagen, promoting use of the stairs, would encourage people to use the stairs rather than the adjacent escalator. An additional purpose was to see if the effect of the interv......OBJECTIVE: The purpose of this study was to determine whether posters placed on the platforms of two train stations in Copenhagen, promoting use of the stairs, would encourage people to use the stairs rather than the adjacent escalator. An additional purpose was to see if the effect...... of the intervention was maintained for a week after the poster was removed. MEASUREMENTS: The number of people using stairs and escalators at Copenhagen Central Station and Østerport Train Station in Copenhagen was recorded before and during posters promoting stair use were placed on the platforms, and a week after...... the posters were removed. Two years after the posters were removed, data were collected for 1 week at Østerport Train Station (long-term post-intervention). RESULTS: At Copenhagen Central Station, the overall stair use increased from 12% before the intervention to 16% (P

  5. 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

  6. American College of Surgeons NSQIP: quality in-training initiative pilot study.

    Science.gov (United States)

    Sellers, Morgan M; Reinke, Caroline E; Kreider, Susan; Meise, Chelsey; Nelis, Kara; Volpe, Anita; Anzlovar, Nancy; Ko, Clifford; Kelz, Rachel R

    2013-11-01

    Clinical outcomes data are playing an increasingly important role in medical decision-making, reimbursement, and provider evaluation, but there are no documented programs that provide outcomes data to surgical residents as part of a structured curriculum. Our objectives were to develop a national collaborative of training programs to unify the efforts between quality and education personnel and demonstrate the feasibility of generating customized reports of patient outcomes for use in surgical education. The pool of potential hospitals was evaluated by comparing ACS NSQIP participants with the roster of clinical sites for general surgery residency programs maintained by FREIDA Online. A program and user guide was developed to generate custom reports based on institutional data, and a voluntary pilot was conducted, consisting of initial development, implementation, and feedback stages. Programs that successfully completed installation and report generation were queried for feedback on time and resources used. Of 245 general surgery residency programs, 47% had a NSQIP-affiliated sponsor institution, and an additional 31% had at least 1 NSQIP-affiliated participant institution. Sixty general surgery residency programs have expressed interest in collaboration. Seventeen pilot sites completed training and installation, and were able to independently generate custom reports. The response rate for the post-report survey was 50%. Participants reported that training and installation typically required one 2-hour phone call, and that total time devoted to the project was less than 8 hours. Collaboration between educators and quality improvement personnel from a diverse group of organizations to integrate outcomes data into surgical education is feasible. Obtaining resident and team reports from ACS NSQIP can be done with minimal effort. Future efforts will be aimed at developing a national data-centered curriculum for general surgery programs. Copyright © 2013 American

  7. 77 FR 26321 - Reed College, Reed Research Nuclear Reactor, Renewed Facility Operating License No. R-112

    Science.gov (United States)

    2012-05-03

    ... Nuclear Reactor, Renewed Facility Operating License No. R-112 AGENCY: Nuclear Regulatory Commission... Commission (NRC or the Commission) has issued renewed Facility Operating License No. R- 112, held by Reed... License No. R-112 will expire 20 years from its date of issuance. The renewed facility operating license...

  8. 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

  9. Analyses and estimates of hydraulic conductivity from slug tests in alluvial aquifer underlying Air Force Plant 4 and Naval Air Station-Joint Reserve Base Carswell Field, Fort Worth, Texas

    Science.gov (United States)

    Houston, Natalie A.; Braun, Christopher L.

    2004-01-01

    This report describes the collection, analyses, and distribution of hydraulic-conductivity data obtained from slug tests completed in the alluvial aquifer underlying Air Force Plant 4 and Naval Air Station-Joint Reserve Base Carswell Field, Fort Worth, Texas, during October 2002 and August 2003 and summarizes previously available hydraulic-conductivity data. The U.S. Geological Survey, in cooperation with the U.S. Air Force, completed 30 slug tests in October 2002 and August 2003 to obtain estimates of horizontal hydraulic conductivity to use as initial values in a ground-water-flow model for the site. The tests were done by placing a polyvinyl-chloride slug of known volume beneath the water level in selected wells, removing the slug, and measuring the resulting water-level recovery over time. The water levels were measured with a pressure transducer and recorded with a data logger. Hydraulic-conductivity values were estimated from an analytical relation between the instantaneous displacement of water in a well bore and the resulting rate of head change. Although nearly two-thirds of the tested wells recovered 90 percent of their slug-induced head change in less than 2 minutes, 90-percent recovery times ranged from 3 seconds to 35 minutes. The estimates of hydraulic conductivity range from 0.2 to 200 feet per day. Eighty-three percent of the estimates are between 1 and 100 feet per day.

  10. Design of subjects training on reactor simulator and feasibility study - toward the empirical evaluation of interface design concept

    International Nuclear Information System (INIS)

    Yamaguchi, Y.; Furukawa, H.; Tanabe, F.

    1998-01-01

    On-going JAERI's project for empirical evaluation of the ecological interface design concept was first described. The empirical evaluation is planned to be proceeded through three consecutive steps; designing and actual implementation of the interface on reactor simulator, verification of the interface created, and the validation by the simulator experiment. For conducting the project, three different experimental resources are prerequisite, that are, data analysis method for identifying the operator's strategies, experimental facility including reactor simulator, and experimental subjects or subjects training method. Among the three experimental resources, subjects training method was recently designed and a simulator experiment was earned out in order to examine the feasibility of the designed training method. From the experiment and analysis of the experimental records, we could conclude that it is feasible that the experimental subjects having an appropriate technical basis can gain the sufficient competence for evaluation work of the interface design concept by using the training method designed. (author)

  11. The business and technical case for Continuous Commissioning(reg Trade Mark) for enhanced building operations. A case study: Alamo Community College District San Antonio, Texas, U.S.A

    Energy Technology Data Exchange (ETDEWEB)

    Verdict, Malcolm; Wei, Guanghua [Texas A and M Univ. System, College Station, TX (United States). Energy Systems Laboratory

    2005-07-01

    This paper provides both the business and technical cases for the 'Continuous Commissioning' of large [>25,000 square feet], buildings through a whole building diagnostic and HVAC optimization approach known as 'Continuous Commissioning'. 'Continuous Commissioning' is defined as the ongoing engineering process to resolve operating problems, improve comfort, optimize energy use and identify retrofits in existing buildings and central plant facilities. It is also known as 'building retro-commissioning' or 'building tune-up'. It involves a rigorous, whole-building, engineering evaluation of the heating and cooling systems to identify mechanical problems, inadequate or ineffective control strategies. Some of the most common problems are: 1) Improper calibration of sensors and metering, 2) inadequate control strategies for optimum operation and comfort, 3) incorrect scheduling of heating and cooling equipment, 4) lack of air and water-side economizer equipment, 5) inadequate building automation systems, and 6) inadequate operations and maintenance. The CC process, described in this paper, was successfully applied at Alamo Community College District (ACCD) in San Antonio, Texas, USA by the Energy Systems Laboratory (ESL), a part of the Texas A and M Univ. System. ACCD has multiple buildings on 4 campuses with total conditioned area of 2.35 Million square feet. ACCD's business approach was unique because the cost of conducting the CC process was financed as an Energy Cost Reduction Measure (ECRM) along with several energy efficiency retrofits.

  12. 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

  13. 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

  14. Comparison of wastewater plant of Nova Pampulha, with an UASB reactor, with another ten brazilian stations; Comparacion de la EDAR de Nova Pampulha, dotada de reactor UASB, con otras diez plantas brasilenas

    Energy Technology Data Exchange (ETDEWEB)

    Barrosa Correa, S. M. B.; Ruiz, E.; Romero, F.

    2004-07-01

    This work is based on data of the wastewater plant of Nova Pampulha with an UASB reactor. The objective of this research was focussed in the comparison of this plant with another ten brazilian stations provided with different depuration techniques. Firstly the graphical comparison of average operational data suggest analogies between influents (less suspended solids in the Nova Pampulha), effluent (more suspended solids and bacteria in the same station) and alimentation's (smaller for suspended solids and bacteria in Nova Pampulha, where there is also an increase in alkalinity). Cluster analysis, made with percentages of elimination of constituents in the eleven stations and shown as dendrograms, was chosen as the second comparative method. A third comparison was affected by multiple linear regression for obtaiming mathematical models from the eliminations of constituents, with statistical significance at level of the 95% confidence, using as possible independent variables the flows and the concentrations of influents. The explanations of the variances of data by the calculated equations is in the range 46 to 91%. As a general conclusion, it can be said that a well operated UASB reactor may be a satisfactory technique for wastewater treatment and well adapted to climatological Brazilian conditions. (Author) 14 refs.

  15. Technology, safety and costs of decommissioning a reference boiling water reactor power station. Volume 2. Appendices. Technical report, September 1977-October 1979

    International Nuclear Information System (INIS)

    Oak, H.D.; Holter, G.M.; Kennedy, W.E. Jr.; Konzek, G.J.

    1980-06-01

    Technology, safety and cost information is given for the conceptual decommissioning of a large (1100MWe) boiling water reactor (BWR) power station. Three approaches to decommissioning, immediate dismantlement, safe storage with deferred dismantlement and entombment, were studied to obtain comparisons between costs, occupational radiation doses, potential dose to the public and other safety impacts. It also shows the sensitivity of decommissioning safety and costs to the power rating of a BWR in the range of 200 to 1100 MWE. This volume contains the appendices

  16. Development of an automated system of nuclear materials accounting for nuclear power stations with water-cooled, water-moderated reactors

    International Nuclear Information System (INIS)

    Babaev, N.S.

    1981-06-01

    The results of work carried out under IAEA Contract No. 2336/RB are described (subject: an automated system of nuclear materials accounting for nuclear power stations with water-cooled, water-moderated (VVER) reactors). The basic principles of an accounting system for this type of nuclear power plant are outlined. The general structure and individual units of the information computer program used to achieve automated accounting are described and instructions are given on the use of the program. A detailed example of its application (on a simulated nuclear power plant) is examined

  17. Technical evaluation report on the monitoring of electric power to the reactor protection system for the Nine Mile Point Nuclear Station, Unit 1 (Docket No. 50-220)

    International Nuclear Information System (INIS)

    Selan, J.C.

    1984-01-01

    This report documents the technical evaluation of the monitoring of electric power to the reactor protection system (RPS) at the Nine Mile Point Nuclear Station, Unit 1. The evaluation is to determine if the proposed design modification will protect the RPS from abnormal voltage and frequency conditions which could be supplied from the power supplies and will meet certain requirements set forth by the Nuclear Regulatory Commission. The proposed design modifications will protect the RPS from sustained abnormal voltage and frequency conditions from the supplying sources

  18. Radioactivity monitoring by the official monitoring stations in North-Rhine Westphalia and the Juelich Nuclear Research Centre after the Chernobyl reactor accident

    International Nuclear Information System (INIS)

    1986-01-01

    This official report presents a governmental declaration of the prime minister of NRW, Mr. Rau, concerning the reactor accident at Chernobyl, and a joint declaration of ministers of NRW, concerning the impact of the accident on the Land NRW. These statements are completed by six official reports on radioactivity measurements carried out by the official monitoring stations of the Land and by the KFA Juelich. These reports inform about methods, scope, and results of the measuring campaigns accomplished by the Zentralstelle fuer Sicherheitstechnik (ZFS), the public materials testing office (MPA), the Chemisches Untersuchungsamt, the Landesamt fuer Wasser und Abfall, and the KFA Juelich. (DG) [de

  19. Technology, safety and costs of decommissioning a reference boiling water reactor power station. Volume 2. Appendices. Technical report, September 1977-October 1979

    Energy Technology Data Exchange (ETDEWEB)

    Oak, H.D.; Holter, G.M.; Kennedy, W.E. Jr.; Konzek, G.J.

    1980-06-01

    Technology, safety and cost information is given for the conceptual decommissioning of a large (1100MWe) boiling water reactor (BWR) power station. Three approaches to decommissioning, immediate dismantlement, safe storage with deferred dismantlement and entombment, were studied to obtain comparisons between costs, occupational radiation doses, potential dose to the public and other safety impacts. It also shows the sensitivity of decommissioning safety and costs to the power rating of a BWR in the range of 200 to 1100 MWE. This volume contains the appendices.

  20. Design of a Control Room for Jordan Research and Training Reactor (JRTR)

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Yong Jun; Suh, Sang Moon; Lee, Hyun Chul; Park, Je Yun [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2012-05-15

    Since the main role of JRTR(Jordan Research and Training Reactor) operating personnel is safe and reliable operation of the reactor, MCR(Main Control Room) and SCR(Supplementary Control Room) must provide them with sufficient information and controls needed to optimize their performance. Before the TMI accident, control room were generally designed just with intuitive common sense, without using any proper HFE(human factors engineering) practices. Many results derived from the analysis of TMI accident showed that a more comprehensive and systematic approaches to develop MCR design requirements were needed. Moreover changes of operators' role as a decision maker from a physical controller in rapid improvement of control system which resulted in higher automation clearly needed more featured regulatory requirements and guidelines. So many regulatory and industrial guidance for control room design have been developed by relevant institution and regulatory bodies. In this paper, a conceptual design of the JRTR control room in the effort of satisfying current regulatory requirements and guidelines are presented. And some information display design is also presented