WorldWideScience

Sample records for plant examination program

  1. Individual plant examination program aspirations and achievements

    International Nuclear Information System (INIS)

    Flack, J.H.

    1994-01-01

    An Individual Plant Examination (IPE) is a systematic examination of a nuclear power plant for vulnerabilities, or risk significant contributors. By mid 1994, all licensees of commercial nuclear power plants will have performed an IPE on their units. To date, the NRC staff has received sixty-three (80%) of the seventy-eight expected IPE submittals. Twelve IPE reviews are now complete, with twenty-two in various stages of review. This paper provides a preliminary overview and comparison of licensees IPEs to Commission objectives. Insights and findings stemming from the review program are also presented

  2. The Stored Waste Examination Pilot Plant program at the INEL

    International Nuclear Information System (INIS)

    McKinley, K.B.; Anderson, B.C.; Clements, T.L.; Hinckley, J.P.; Mayberry, J.L.; Smith, T.H.

    1983-01-01

    Since 1970, defense transuranic waste has been placed into 20-year retrievable storage at the Radioactive Waste Management Complex at the Idaho National Engineering Laboratory (INEL). A major objective of the U.S. Department of Energy (DOE) Nuclear Waste Management Program is to remove all retrievably stored transuranic waste from the INEL. The January 1981 DOE Record of Decision on the Waste Isolation Pilot Plant (WIPP) stated, ''The WIPP facility will dispose of defense transuranic waste stored retrievably at the Idaho National Engineering Laboratory.'' After retrieval and before shipment, processing may be necessary to prepare the waste for acceptance, handling, and enhanced long-term isolation in the WIPP. However, some of the waste is certifiable to the WIPP waste acceptance criteria without container opening or waste processing. To minimize costs, the Stored Waste Examination Pilot Plant (SWEPP) is being developed to certify INEL stored transuranic waste without container opening or waste processing. The SWEPP certification concept is based on records assessment, nondestructive examination techniques, assay techniques, health physics examinations, and limited opening of containers at another facility for quality control

  3. Individual plant examination program: Perspectives on reactor safety and plant performance. Part 6, appendices A, B, and C

    International Nuclear Information System (INIS)

    1997-12-01

    This report provides perspectives gained by reviewing 75 Individual Plant Examination (IPE) submittals pertaining to 108 nuclear power plant units. IPEs are probabilistic analyses that estimate the core damage frequency (CDF) and containment performance for accidents initiated by internal events (including internal flooding, but excluding internal fire). The U.S. Nuclear Regulatory Commission (NRC), Office of Nuclear Regulatory Research, reviewed the WE submittals with the objective of gaining perspectives in three major areas: (1) improvements made to individual plants as a result of their IPEs and the collective results of the IPE program, (2) plant-specific design and operational features and modeling assumptions that significantly affect the estimates of CDF and containment performance, and (3) strengths and weaknesses of the models and methods used in the IPEs. These perspectives are gained by assessing the core damage and containment performance results, including overall CDF, accident sequences, dominant contributions to component failure and human error, and containment failure modes. In particular, these results are assessed in relation to the design and operational characteristics of the various reactor and containment types, and by comparing the IPEs to probabilistic risk assessment characteristics. Methods, data, boundary conditions, and assumptions used in the IPEs are considered in understanding the differences and similarities observed among the various types of plants

  4. Individual plant examination program: Perspectives on reactor safety and plant performance. Parts 2--5: Final report; Volume 2

    International Nuclear Information System (INIS)

    1997-12-01

    This report provides perspectives gained by reviewing 75 Individual Plant Examination (IPE) submittals pertaining to 108 nuclear power plant units. IPEs are probabilistic analyses that estimate the core damage frequency (CDF) and containment performance for accidents initiated by internal events. The US Nuclear Regulatory Commission (NRC) reviewed the IPE submittals with the objective of gaining perspectives in three major areas: (1) improvements made to individual plants as a result of their IPEs and the collective results of the IPE program, (2) plant-specific design and operational features and modeling assumptions that significantly affect the estimates of CDF and containment performance, and (3) strengths and weaknesses of the models and methods used in the IPEs. These perspectives are gained by assessing the core damage and containment performance results, including overall CDF, accident sequences, dominant contributions to component failure and human error, and containment failure modes. Methods, data, boundary conditions, and assumptions used in the IPEs are considered in understanding the differences and similarities observed among the various types of plants. This report is divided into three volumes containing six parts. Part 1 is a summary report of the key perspectives gained in each of the areas identified above, with a discussion of the NRC's overall conclusions and observations. Part 2 discusses key perspectives regarding the impact of the IPE Program on reactor safety. Part 3 discusses perspectives gained from the IPE results regarding CDF, containment performance, and human actions. Part 4 discusses perspectives regarding the IPE models and methods. Part 5 discusses additional IPE perspectives. Part 6 contains Appendices A, B and C which provide the references of the information from the IPEs, updated PRA results, and public comments on draft NUREG-1560 respectively

  5. Individual plant examination program: Perspectives on reactor safety and plant performance. Part 1: Final summary report; Volume 1

    International Nuclear Information System (INIS)

    1997-12-01

    This report provides perspectives gained by reviewing 75 Individual Plant Examination (IPE) submittals pertaining to 108 nuclear power plant units. IPEs are probabilistic analyses that estimate the core damage frequency (CDF) and containment performance for accidents initiated by internal events. The US Nuclear Regulatory Commission (NRC) reviewed the IPE submittals with the objective of gaining perspectives in three major areas: (1) improvements made to individual plants as a result of their IPEs and the collective results of the IPE program, (2) plant-specific design and operational features and modeling assumptions that significantly affect the estimates of CDF and containment performance, and (3) strengths and weaknesses of the models and methods used in the IPEs. These perspectives are gained by assessing the core damage and containment performance results, including overall CDF, accident sequences, dominant contributions to component failure and human error, and containment failure modes. Methods, data, boundary conditions, and assumptions used in the IPEs are considered in understanding the differences and similarities observed among the various types of plants. This report is divided into three volumes containing six parts. Part 1 is a summary report of the key perspectives gained in each of the areas identified above, with a discussion of the NRC's overall conclusions and observations. Part 2 discusses key perspectives regarding the impact of the IPE Program on reactor safety. Part 3 discusses perspectives gained from the IPE results regarding CDF, containment performance, and human actions. Part 4 discusses perspectives regarding the IPE models and methods. Part 5 discusses additional IPE perspectives. Part 6 contains Appendices A, B and C which provide the references of the information from the IPEs, updated PRA results, and public comments on draft NUREG-1560 respectively

  6. Individual plant examination program: Perspectives on reactor safety and plant performance. Parts 2--5: Final report; Volume 2

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-12-01

    This report provides perspectives gained by reviewing 75 Individual Plant Examination (IPE) submittals pertaining to 108 nuclear power plant units. IPEs are probabilistic analyses that estimate the core damage frequency (CDF) and containment performance for accidents initiated by internal events. The US Nuclear Regulatory Commission (NRC) reviewed the IPE submittals with the objective of gaining perspectives in three major areas: (1) improvements made to individual plants as a result of their IPEs and the collective results of the IPE program, (2) plant-specific design and operational features and modeling assumptions that significantly affect the estimates of CDF and containment performance, and (3) strengths and weaknesses of the models and methods used in the IPEs. These perspectives are gained by assessing the core damage and containment performance results, including overall CDF, accident sequences, dominant contributions to component failure and human error, and containment failure modes. Methods, data, boundary conditions, and assumptions used in the IPEs are considered in understanding the differences and similarities observed among the various types of plants. This report is divided into three volumes containing six parts. Part 1 is a summary report of the key perspectives gained in each of the areas identified above, with a discussion of the NRC`s overall conclusions and observations. Part 2 discusses key perspectives regarding the impact of the IPE Program on reactor safety. Part 3 discusses perspectives gained from the IPE results regarding CDF, containment performance, and human actions. Part 4 discusses perspectives regarding the IPE models and methods. Part 5 discusses additional IPE perspectives. Part 6 contains Appendices A, B and C which provide the references of the information from the IPEs, updated PRA results, and public comments on draft NUREG-1560 respectively.

  7. Bulk Electrical Cable Non-Destructive Examination Methods for Nuclear Power Plant Cable Aging Management Programs

    Energy Technology Data Exchange (ETDEWEB)

    Glass, Samuel W. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Jones, Anthony M. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Fifield, Leonard S. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Hartman, Trenton S. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

    2016-09-01

    This Pacific Northwest National Laboratory milestone report describes progress to date on the investigation of nondestructive test methods focusing particularly on bulk electrical test methods that provide key indicators of cable aging and damage. The work includes a review of relevant literature as well as hands-on experimental verification of inspection capabilities. As nuclear power plants consider applying for second, or subsequent, license renewal to extend their operating period from 60 years to 80 years, it is important to understand how the materials installed in plant systems and components will age during that time and develop aging management programs to assure continued safe operation under normal and design basis events (DBE). Normal component and system tests typically confirm the cables can perform their normal operational function. The focus of the cable test program, however, is directed toward the more demanding challenge of assuring the cable function under accident or DBE. The industry has adopted 50% elongation at break (EAB) relative to the un-aged cable condition as the acceptability standard. All tests are benchmarked against the cable EAB test. EAB, however, is a destructive test so the test programs must apply an array of other nondestructive examination (NDE) tests to assure or infer the overall set of cable’s system integrity. Assessment of cable integrity is further complicated in many cases by vendor’s use of dissimilar material for jacket and insulation. Frequently the jacket will degrade more rapidly than the underlying insulation. Although this can serve as an early alert to cable damage, direct test of the cable insulation without violating the protective jacket becomes problematic. This report addresses the range of bulk electrical NDE cable tests that are or could be practically implemented in a field-test situation with a particular focus on frequency domain reflectometry (FDR). The FDR test method offers numerous advantages

  8. Individual plant examination: Submittal guidance

    International Nuclear Information System (INIS)

    1989-08-01

    Based on a Policy Statement on Severe Accidents Regarding Future Designs and Existing Plants, the performance of a plant examination is requested from the licensee of each nuclear power plant. The plant examination looks for vulnerabilities to severe accidents and cost-effective safety improvements that reduce or eliminate the important vulnerabilities. This document delineates guidance for reporting the results of that plant examination. 38 refs., 2 tabs

  9. Individual plant examination and future PRA applications

    International Nuclear Information System (INIS)

    Monty, B.S.; Sursock, J.P.; Thierry, R.J.

    1992-01-01

    PRA is being used in many areas of plant operation as has been demonstrated in previous studies. With the U.S. NRC's emphasis on the use of risk to identify plant vulnerabilities and the development of plant specific PRA models for all plants, it is expected that the use of PRA will be expanded. Key areas where this is expected to occur include the development of risk-based Technical Specifications, risk management, and risk-centered maintenance programs. This paper focuses on the Individual Plant Examination requirement and the possible uses of risk-based methods in controlling plant operation to enhance plant safety and availability, and how the IPE requirement will potentially further this area of development. (orig./DG)

  10. Better Plants Program Overview

    Energy Technology Data Exchange (ETDEWEB)

    None

    2015-09-30

    The U.S. Department of Energy’s (DOE’s) Better Buildings, Better Plants Program is a voluntary partnership initiative to drive significant energy efficiency improvement across energy intensive companies and organizations. 157 leading manufacturers and public water and wastewater treatment utilities are partnering with DOE through Better Plants to improve energy efficiency, slash carbon emissions, and cut energy costs.

  11. Examining work structure in nuclear power plants

    International Nuclear Information System (INIS)

    Bauman, M.B.; Boulette, M.D.; Van Cott, H.P.

    1985-01-01

    This paper describes the assessment of the work structure of ten nuclear power plants. Work structure factors are those factors that relate to the way in which work at all levels in a plant is organized, staffed, managed, rewarded, and perceived by plant personnel. Questionnaires given to a cross-section of personnel at the plants were the primary source of data collection. Structured ''critical incident'' interviews were conducted to verify the questionnaire results. The study revealed that a variety of work structure factor problem areas do exist in nuclear power plants. The paper highlights a prioritized set of candidate research themes to be considered in EPRI's Work Structure and Performance Research Program

  12. Plant Modernization Programs

    International Nuclear Information System (INIS)

    O'Hara, John

    2004-01-01

    Most nuclear plants were designed and built from the 1960's through the 1990's. These plants employ predominantly analog instrumentation and control (I and C) technology, and their control rooms are made up of primarily hardwired controls (e.g., switches, knobs and handles) and displays (e.g., gauges, linear scales and indicator lights). Over the past several years, these plants have been modernized with digital I and C and computer-based human-system interfaces (HSIs) such as software-based process controls, touch-screen interfaces and large-screen, overview displays. As these computer based HIS technologies are integrated into control rooms based on conventional technology, hybrid control rooms are created. The paper summarizes lessons learned from the study of plant modernization programs over the past ten years so that they can be used to help improve the modification process. While the research focused on the impact of technology change on human performance, a number of organizational and programmatic issues were observed as well. Eleven lessons learned are presented

  13. From IPE [individual plant examinations] to IPEEE [individual plant examination of external events

    International Nuclear Information System (INIS)

    Newton, I.M.

    1994-01-01

    In addition to doing individual plant examinations (IPEs) which assess risk to nuclear plants from internal factors, all US plants are now also required to analyse external events and submit an IPEEE (Individual Plant Examination of External Events). Specifically, the IPEEEs require an assessment of plant-specific risks from the following types of initiating events: seismic events; fire; wind; tornadoes; flooding; accidents involving transportation or nearby facilities, such as oil refineries. (author)

  14. Pantex Plant meteorological monitoring program

    International Nuclear Information System (INIS)

    Snyder, S.F.

    1993-07-01

    The current meteorological monitoring program of the US Department of Energy's Pantex Plant, Amarillo, Texas, is described in detail. Instrumentation, meteorological data collection and management, and program management are reviewed. In addition, primary contacts are noted for instrumentation, calibration, data processing, and alternative databases. The quality assurance steps implemented during each portion of the meteorological monitoring program are also indicated

  15. Passive Nuclear Plants Program (UPDATE)

    International Nuclear Information System (INIS)

    Chimeno, M. A.

    1998-01-01

    The light water passive plants program (PCNP), today Advanced Nuclear Power Plants Program (PCNA), was constituted in order to reach the goals of the Spanish Electrical Sector in the field of advanced nuclear power plants, optimize the efforts of all Spanish initiatives, and increase joint presence in international projects. The last update of this program, featured in revision 5th of the Program Report, reflects the consolidation of the Spanish sector's presence in International programs of the advanced power plants on the basis of the practically concluded American ALWR program. Since the beginning of the program , the PCNP relies on financing from the Electrical sector, Ocide, SEPI-Endesa, Westinghouse, General Electric, as well as from the industrial cooperators, Initec, UTE (Initec- Empresarios Agrupados), Ciemat, Enusa, Ensa and Tecnatom. The program is made up of the following projects, already concluded: - EPRI's Advanced Light Water Plants Certification Project - Westinghouse's AP600 Project - General Electric's SBWR Project (presently paralyzed) and ABWR project Currently, the following project are under development, at different degrees of advance: - EPP project (European Passive Plant) - EBWR project (European Advanced Boiling Water Reactor)

  16. Recent experience in nuclear plant nondestructive examinations

    International Nuclear Information System (INIS)

    Epps, T.N.

    1986-01-01

    This paper reviews recent experience in nuclear plant inservice inspection activities including ultrasonic examination of piping materials, personnel qualification, results, and the overall significance to the industry. Several areas of concern to the nuclear power industry have recently been addressed by Southern Company Services' (SCS) Inspection, Testing, and Engineering Department during implementation of preservice and in-service inspection activities in the SCS system. The most significant of these activities is the ultrasonic inspection of Type 304 stainless steel piping for the presence of intergranular stress corrosion cracking (IGSCC). This activity has been in the forefront of boiling water reactor (BWR) in-service inspections for the past several years

  17. Human event observations in the individual plant examinations

    Energy Technology Data Exchange (ETDEWEB)

    Forester, J. [Sandia National Labs., Albuquerque, NM (United States)

    1995-04-01

    A major objective of the Individual Plant Examination Insights Program is to identify the important determinants of core damage frequency for the different reactor and containment types and plant designs as indicated in the IPEs. The human reliability analysis is a critical component of the probabilistic risk assessments which were done for the IPEs. The determination and selection of human actions for incorporation into the event and fault tree models and the quantification of their failure probabilities can have an important impact on the resulting estimates of CDF and risk. Two important goals of the NRCs IPE Insights Program are (1) to determine the extent to which human actions and their corresponding failure probabilities influenced the results of the IPEs and (2) to identify which factors played significant roles in determining the differences and similarities in the results of the HRA analyses across the different plants. To obtain the relevant information, the NRC`s IPE database, which contains information on plant design, CDF, and containment performance obtained from the IPEs, was used in conjunction with a systematic examination of the HRA analyses and results from the IPEs. Regarding the extent to which the results of the HRA analyses were significant contributors to the plants` CDFs, examinations of several different measures indicated that while individual human actions could have important influences on CDF for particular initiators, the HRA results did not appear to be the most significant driver of plant risk. Another finding was that while there were relatively wide variations in the calculated human error probabilities for similar events across plants, there was no evidence for any systematic variation as a function of the HRA methods used in the analyses. Much of the variability in HEP values can be explained by differences in plant characteristics and sequence-specific factors. Details of these results and other findings are discussed.

  18. Human event observations in the individual plant examinations

    International Nuclear Information System (INIS)

    Forester, J.

    1995-01-01

    A major objective of the Individual Plant Examination Insights Program is to identify the important determinants of core damage frequency for the different reactor and containment types and plant designs as indicated in the IPEs. The human reliability analysis is a critical component of the probabilistic risk assessments which were done for the IPEs. The determination and selection of human actions for incorporation into the event and fault tree models and the quantification of their failure probabilities can have an important impact on the resulting estimates of CDF and risk. Two important goals of the NRCs IPE Insights Program are (1) to determine the extent to which human actions and their corresponding failure probabilities influenced the results of the IPEs and (2) to identify which factors played significant roles in determining the differences and similarities in the results of the HRA analyses across the different plants. To obtain the relevant information, the NRC's IPE database, which contains information on plant design, CDF, and containment performance obtained from the IPEs, was used in conjunction with a systematic examination of the HRA analyses and results from the IPEs. Regarding the extent to which the results of the HRA analyses were significant contributors to the plants' CDFs, examinations of several different measures indicated that while individual human actions could have important influences on CDF for particular initiators, the HRA results did not appear to be the most significant driver of plant risk. Another finding was that while there were relatively wide variations in the calculated human error probabilities for similar events across plants, there was no evidence for any systematic variation as a function of the HRA methods used in the analyses. Much of the variability in HEP values can be explained by differences in plant characteristics and sequence-specific factors. Details of these results and other findings are discussed

  19. Human event observations in the individual plant examinations

    International Nuclear Information System (INIS)

    Forester, J.

    1995-01-01

    A major objective of the Nuclear Regulatory Commission's (NRC) Individual Plant Examination (IPE) Insights Program is to identify the important determinants of core damage frequency (CDF) for the different reactor and containment types and plant designs as indicated in the IPEs. The human reliability analysis (HRA) is a critical component of the probabilistic risk assessments (PRAS) which were done for the IPES. The determination and selection of human actions for incorporation into the event and fault tree models and the quantification of their failure probabilities can have an important impact on the resulting estimates of CDF and risk. Therefore, two important goals of the NRCs IPE Insights Program are (1) to determine the extent to which human actions and their corresponding failure probabilities influenced the results of the IPEs and (2) to identify which factors played significant roles in determining the differences and similarities in the results of the HRA analyses across the different plants. To obtain the relevant information, the NRC's IPE database, which contains information on plant design, CDF, and containment performance obtained from the IPES, was used in conjunction with a systematic examination of the HRA analyses and results from the IPES. Regarding the extent to which the results of the HRA analyses were significant contributors to the plants' CDFs, examinations of several different measures indicated that while individual human actions could have important influences on CDF for particular initiators, the HRA results did not appear to be the most significant driver of plant risk (CDF). Another finding was that while there were relatively wide variations in the calculated human error probabilities (HEPs) for similar events across plants, there was no evidence for any systematic variation as a function of the HRA methods used in the analyses

  20. Human event observations in the individual plant examinations

    International Nuclear Information System (INIS)

    Lois, E.; Forester, J.

    1994-01-01

    A main objective of the Nuclear Regulatory Commission's (NRC) Individual Plant Examination (IPE) Insights Program is to document significant safety insights relative to core damage frequency (CDF) for the different reactor and containment types and plant designs as indicated in the IPEs. The Human Reliability Analysis (HRA) is a critical component of the Probabilistic Risk Assessments (PRAs) which were done for the IPEs. The determination and selection of human actions for incorporation into the event and fault tree models and the quantification of their failure probabilities can have an important impact on the resulting estimates of CDF and risk. Therefore, two important goals of the NRCs IPE Insights Program are (1) to determine the extent to which human actions and their corresponding failure probabilities influenced the results of the IPEs and (2) to identify which factors played significant roles in determining the differences and similarities in the results of the HRA analyses across the different plants. To obtain the relevant information, the NRCs IPE database, which contains information on plant design, CDF, and containment performance obtained from the IPEs, was used in conjunction with a systematic examination of the HRA results from the IPEs

  1. Programs to improve plant performance

    International Nuclear Information System (INIS)

    Felmus, N.L.

    1987-01-01

    Looking toward the 1990's, we see a period in which our industry will face the challenge of improving the performance of the nuclear plants which are built and operating. The skills and technology are at hand to make good plant performance a reality and we believe the time has come to use them to achieve that end. As reserve margins decline, utilities and their regulators will increasingly seek to tap the unexploited capacity tied up in plants operating below their optimum availability. This paper describes a number of the programs, plant improvements and operations improvements which can yield a significant increase in nuclear plant availability and capacity factor now and into the 1990's. (author)

  2. Nuclear plant aging research program

    International Nuclear Information System (INIS)

    Eissenberg, D.M.

    1987-01-01

    The U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, has established the Nuclear Plant Aging Research (NPAR) program in its Division of Engineering Technology. Principal contractors for this program include Oak Ridge National Laboratory, Brookhaven National Laboratory, Idaho National Engineering Laboratory, and Pacific Northwest Laboratory. The program goals are: to identify and characterize time-dependent degradation (aging) of nuclear plant safety-related electrical and mechanical components which could lead to loss of safety function; to identify and recommend methods for detecting and trending aging effects prior to loss of safety function so that timely maintenance can be implemented; and to recommend maintenance practices for mitigating the effects of aging. Research activities include prioritization of system and component aging in nuclear plants, characterization of aging degradation of specific components including identification of functional indicators useful for trending degradation, and testing of practical methods and devices for measuring the functional indicators. Aging assessments have been completed on electric motors, snubbers, motor-operated valves, and check valves. Testing of trending methods and devices for motor-operated valves and check valves is in progress

  3. Japanese plant life extension program

    International Nuclear Information System (INIS)

    Yoshitsugu, M.

    1988-01-01

    As one of the main items of up-grading light water reactor program in Japan, plant life extension has been recommended by Advisory Committee of Ministry of International trade and Industry and the practical work has begun to be carried out. It is overviewed here. After preliminary works, including investigation on the state of the arts through a entrusted survey work, participation in international meetings and exchange of informations with related organizations, actual work has just started. So-called critical components based on our experience during the past 17 years have been listed up and some experimental works inaugurated as from 1987

  4. An Examination of New Counselor Mentor Programs

    Science.gov (United States)

    Bass, Erin; Gardner, Lauren; Onwukaeme, Chika; Revere, Dawn; Shepherd, Denise; Parrish, Mark S.

    2013-01-01

    An analysis of current new counselor mentor programs reveals the need for such programs, but information regarding established programs is limited. A review of the literature addresses program characteristics and data obtained from existing mentor program participants. An overview of four programs explaining the framework outlined for mentoring…

  5. Tamarisk coalition - native riparian plant materials program

    Science.gov (United States)

    Stacy Kolegas

    2012-01-01

    The Tamarisk Coalition (TC), a nonprofit organization dedicated to riparian restoration in the western United States, has created a Native Plant Materials Program to address the identified need for native riparian plant species for use in revegetation efforts on the Colorado Plateau. The specific components of the Native Plant Materials Program include: 1) provide seed...

  6. Aquatic Plant Control Research Program

    National Research Council Canada - National Science Library

    Cofrancesco, Alfred

    1998-01-01

    .... This search for natural plant enemies (insects and fungal pathogens) has led researchers to the native ranges of noxious aquatic plants, located throughout the continents of Africa, Asia, Europe, and Australia...

  7. Examining Burma's Development: A Research Fellowship Program ...

    International Development Research Centre (IDRC) Digital Library (Canada)

    The Regional Center for Social Science and Sustainable Development (RCSD) at Thailand's Chiang Mai University will manage the four-year program, which targets junior and mid-level academic and non-academic Burmese scholars. The program will ... LVIF announces five more funded projects. Eleven world-class ...

  8. QA programs in nuclear power plants

    International Nuclear Information System (INIS)

    Ellingson, A.C.

    1976-01-01

    As an overview of quality assurance programs in nuclear power plants, the energy picture as it appears today is reviewed. Nuclear power plants and their operations are described and an attempt is made to place in proper perspective the alleged ''threats'' inherent in nuclear power. Finally, the quality assurance programs being used in the nuclear industry are described

  9. Spanish program of advanced Nuclear Power Plants

    International Nuclear Information System (INIS)

    Marco, M.; Redon, R.

    1993-01-01

    The energy Spanish Plan is promoting some actions within the area of advanced reactors. Efforts are focussed onto the European Program of Advanced Reactors, the Program of Passive Plants (EPRI), European Fast Reactor Project and the APWR-1000 Program of INI. Electrical sector utilities and industrial partners supported by the Administration have organized an steering committee. The program of Passive Plants includes activities on Qualification, design and detailed engineering (Qualification project, SBWR project of G.E. and AP600 Project of Westinghouse. The european project on advanced plants has the following Spanish contribution: Analysis of alternative Dossier on European requisites (EUR) and Design of an European Reactor (EPR)

  10. Plant performance monitoring program at Krsko NPP

    International Nuclear Information System (INIS)

    Bach, B.; Kavsek, D.

    2004-01-01

    A high level of nuclear safety and plant reliability results from the complex interaction of a good design, operational safety and human performance. This is the reason for establishing a set of operational plant safety performance indicators, to enable monitoring of both plant performance and progress. Performance indicators are also used for setting challenging targets and goals for improvement, to gain additional perspective on performance relative to other plants and to provide an indication of a potential need to adjust priorities and resources to achieve improved overall plant performance. A specific indicator trend over a certain period can provide an early warning to plant management to evaluate the causes behind the observed changes. In addition to monitoring the changes and trends, it is also necessary to compare the indicators with identified targets and goals to evaluate performance strengths and weaknesses. Plant Performance Monitoring Program at Krsko NPP defines and ensures consistent collection, processing, analysis and use of predefined relevant plant operational data, providing a quantitative indication of nuclear power plant performance. When the program was developed, the conceptual framework described in IAEA TECDOC-1141 Operational Safety Performance Indicators for Nuclear Power Plants was used as its basis in order to secure that a reasonable set of quantitative indications of operational safety performance would be established. Safe, conservative, cautious and reliable operation of the Krsko NPP is a common goal for all plant personnel. It is provided by continuous assurance of both health and safety of the public and employees according to the plant policy stated in program MD-1 Notranje usmeritve in cilji NEK, which is the top plant program. Establishing a program of monitoring and assessing operational plant safety performance indicators represents effective safety culture of plant personnel.(author)

  11. Postirradiation examination of Kori-1 nuclear power plant fuels

    International Nuclear Information System (INIS)

    Ro, S.G.; Kim, E.K.; Lee, K.S.; Min, D.K.

    1994-01-01

    Full size fuels discharged from Kori-1 PWR nuclear power plant have been subjected to postirradiation examination. The fuels under investigation were irradiated for one- to four-reactor cycles. Nondestructive examination and dismantling of the fuel assemblies have been conducted in the pool of the postirradiation examination facility (PIEF) of Korea Atomic Energy Research Institue. Subsequently nondestructive and destructive examinations of fuel rods have been performed in the hot cells of the PIEF. An evaluation of fuel burnup behaviors was based on the postirradiation examination data and the nominal design values. The results did not show any evidence of abnormalities in the fuel integrity. (orig.)

  12. Postirradiation examination of Kori-1 nuclear power plant fuels

    Science.gov (United States)

    Seung-Gy, Ro; Eun-Ka, Kim; Key-Soon, Lee; Duck-Kee, Min

    1994-05-01

    Full size fuels discharged from Kori-1 PWR nuclear power plant have been subjected to postirradiation examination. The fuels under investigation were irradiated for one- to four-reactor cycles. Nondestructive examination and dismantling of the fuel assemblies have been conducted in the pool of the postirradiation examination facility (PIEF) of Korea Atomic Energy Research Institute. Subsequently nondestructive and destructive examinations of fuel rods have been performed in the hot cells of the PIEF. An evaluation of fuel burnup behaviors was based on the postirradiation examination data and the nominal design values. The results did not show any evidence of abnormalities in the fuel integrity.

  13. Angra nuclear plant - environmental control program

    International Nuclear Information System (INIS)

    Kircher, E.; Cruz, E.S. da

    1989-01-01

    The pre-operational studies, that were elaborated before the beginning of Angra I Power Plant operation, are described in particular the environmental radiological safety area till the fuel loading in the core reactor. Several aspects are included, as socio-economic survey, seismological analysis, Meteorological Program, marine biology, water cooling system, exposure measures of natural radiation, marine sediments characterization in the effluent dispersion area and Environmental Radiological Monitoring Program. The main environmental programs developed for the operational phase of the Angra I Plant are also presented, citing some considerations about the Meteorological Program, Marine Biology Control Program, Temperature and Chlorine Control in Piraquara de Fora Bay, Radiological Environmental Monitoring Program, Sanitary Effluent Control Program and Radiological Emergency Program. (C.G.C.). 2 refs

  14. EPRI nuclear power plant decommissioning technology program

    International Nuclear Information System (INIS)

    Kim, Karen S.; Bushart, Sean P.; Naughton, Michael; McGrath, Richard

    2011-01-01

    The Electric Power Research Institute (EPRI) is a non-profit research organization that supports the energy industry. The Nuclear Power Plant Decommissioning Technology Program conducts research and develops technology for the safe and efficient decommissioning of nuclear power plants. (author)

  15. Y-12 Plant Decontamination and Decommissioning Program

    International Nuclear Information System (INIS)

    1992-01-01

    The Decontamination and Decommissioning (D and D) Program at the Oak Ridge Y-12 Plant is part of the Environmental Restoration (ER) and Waste Management (WM) Programs (ERWM). The objective of the ER Program is to provide Y-12 the capability to meet applicable environmental regulations through facility development activities and site remedial actions. The WM Program supports the ER program. The D and D Program provides collective management of sites within the Plant which are in need of decontamination and decommissioning efforts, prioritizes those areas in terms of health, safety, and environmental concerns, and implements the appropriate level of remedial action. The D and D Program provides support to identifiable facilities which formerly served one or more of the many Plant functions. Program activities include (1) surveillance and maintenance of facilities awaiting decommissioning; (2) planning safe and orderly facility decommissioning; and (3) implementing a program to accomplish facility disposition in a safe, cost effective, and timely manner. In order to achieve the first objective, a formal plan which documents the surveillance and maintenance needs for each facility has been prepared. This report provides this documentation for the Y-12 facilities currently included in the D and D Program, as well as those planned for future inclusion in the Program, and includes projected resource requirements for the planning period of FY 1993 through FY 2000

  16. The Susquehanna plant lifetime excellence program

    International Nuclear Information System (INIS)

    McNamara, R.W.

    1988-01-01

    This paper discusses how the Susquehanna plant lifetime excellence program (SPLEX) blends many of the objectives of a new managing for excellence program with plant life extension objectives to achieve excellence in the lifetime operation and availability of the two-unit Susquehanna steam electric station. Investments in lifetime excellence improvements will provide near-term, as well as plant life extension, benefits. A high-quality lifetime experience record, together with extensive, periodic technical assessments and cost-benefit analyses, will provide conclusive justification for future extensions of the unit operating licenses

  17. Preliminary perspectives gaines from individual plant examination of external events (IPEEE) seismic and fire submittal review

    International Nuclear Information System (INIS)

    Chen, J.T.; Connell, E.; Chokshi, N.

    1997-01-01

    As a result of the U.S. Nuclear Regulatory Commission (USNRC) initiated Individual plant Examination of External Events (IPEEE) program, every operating nuclear power reactor in the United States has performed an assessment of severe accident due to external events. This paper provides a summary of the preliminary insights gained through the review of 24 IPEEE submittals

  18. Quality assurance program for nuclear power plants

    International Nuclear Information System (INIS)

    Gamon, T.H.

    1976-02-01

    The Topical Report presented establishes and provides the basis for the Brown and Root Quality Assurance Program for Nuclear Power Plants from which the Brown and Root Quality Assurance Manual is prepared and implemented. The Quality Assurance Program is implemented by the Brown and Root Power Division during the design, procurement, and construction phases of nuclear power plants. The Brown and Root Quality Assurance Program conforms to the requirements of Nuclear Regulatory Commission Regulation 10 CFR 50, Appendix B; to approved industry standards such as ANSI N45.2 and ''Daughter Standards''; or to equivalent alternatives as indicated in the appropriate sections of the report

  19. Quality assurance program for nuclear power plants

    International Nuclear Information System (INIS)

    Gamon, T.H.

    1976-06-01

    This topical report establishes and provides the basis for the Brown and Root Quality Assurance Program for Nuclear Power Plants from which the Brown and Root Quality Assurance Manual is prepared and implemented. The Quality Assurance Program is implemented by the Brown and Root Power Division during the design, procurement, and construction phases of nuclear power plants. The Brown and Root Quality Assurance Program conforms to the requirements of Nuclear Regulatory Commission Regulation 10 CFR 50, Appendix B; to approved industry standards such as ANSI N45.2 and ''Daughter Standards''; or to equivalent alternatives as indicated in the appropriate sections of this report

  20. Mechanized ultrasonic examination of piping systems in nuclear power plants

    International Nuclear Information System (INIS)

    Edelmann, X.; Pfister, O.; Allidi, F.

    1988-01-01

    The success of mechanized ultrasonic examination applied on welds in piping systems in nuclear power plants is highly dependent on its careful preparation. From the development of an adequate examination technique to its implementation on site, many problems are to be solved. This is especially the case when dealing with austenitic welds or dissimilar metal welds. In addition to the specific needs for examination technique based on material properties and requirements for minimum flaw size detection, accessibility and radiation aspects have to be considered. A crew of skilled and highly trained examination personnel is required. Experience in various nuclear power plants, - BWR's and PWR's of different designs - has shown, that even difficult examination problems can be successfully solved, provided that there is a good preparation. The necessary step by step proceeding is illustrated by examples concerning mechanized examination. Preservice inspections and in-service inspections with specific requirements, due to the types of flaws to be found or the type of material concerned, are discussed

  1. Qualification of nuclear power plant inspection, examination, and testing personnel. Revision 1, September 1980

    International Nuclear Information System (INIS)

    Anon.

    1981-01-01

    Appendix B, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants, to 10 CFR Part 50, Domestic Licensing of Production and Utilization Facilities, requires that the quality assurance program provide for indoctrination and training of personnel performing activities affecting quality as necessary to ensure that quality assurance personnel achieve and maintain suitable proficiency. This guide describes a method acceptable to the NRC staff for complying with the Commission's regulations with regard to qualification of inspection, examination, and testing personnel for all types of nuclear power plants

  2. Examining the Perceptions of Brand Images Regarding Competing MBA Programs

    Science.gov (United States)

    Hinds, Timothee; Falgoust, Dexter; Thomas, Kerry, Jr.; Budden, Michael C.

    2010-01-01

    In today's economic environment, it is crucial to create a strong, consistent brand image within a graduate business program. This study examines the perceptions that students at Southeastern Louisiana University hold about its MBA program and the MBA programs of its main competitors. A focus group was conducted to identify competitors and factors…

  3. Examining the Role of Multicultural Competence in Leadership Program Design

    Science.gov (United States)

    Wilson, Amy B.

    2015-01-01

    Research examining the multicultural competence of leadership educators across a variety of institutions demonstrated variance based on leadership program structure, program elements, and the ways in which diversity was addressed in the program. The Multicultural Competence in Student Affairs-Preliminary 2 (MCSA-P2) scale was used to measure…

  4. B Plant cleanout and stabilization program update

    International Nuclear Information System (INIS)

    Gehrke, J.W.

    1994-01-01

    The B Plant Cleanout and Stabilization Program Update FY1993 committed to an annual update document. The Cleanout and Stabilization Program (CSP) plan, Reference 1, remains as the best source of detailed discussion of CSP work and continues to be valid. The CSP presented a five year plan that left a number of plant systems operational to support WESF (Waste Encapsulation and Storage Facility) capsule storage. It is now apparent that the transition of B Plant to a long-term surveillance and maintenance mode (LTS and M) will be necessary to complete B Plant deactivation. To accomplish the LTS and M mode for B Plant, WESF will need to be physically isolated to allow stand alone operation for many years beyond the anticipated B Plant deactivation. B Plant has processed large quantities (> 100 megacuries) of cesium-137 and strontium-90. Residual radioactive contamination from this processing is in many forms and locations in B Plant. The plant design incorporates many features for radiological containment and confinement and systems to prevent the exposure of plant personnel and the public to excessive radiation. To minimize or reduce the radiological hazard wherever possible this program includes activities in four areas: Prevent Migration of Contamination; Stabilize Major Radioactive Source Terms; characterize Radioactive Source Terms; and Reduce Radiation Dose Rates. This document will describe work that is need to meet current goals and objectives and work that has changed, been completed, ore redirected. A systems engineering approach to defining this mission was initiated in FY1994 that will also be addressed in this document

  5. Revised inspection program for nuclear power plants

    International Nuclear Information System (INIS)

    1978-01-01

    The United States Nuclear Regulatory Commission (NRC) regulates nuclear power plants to assure adequate protection of the public and the environment from the dangers associated with nuclear materials. NRC fulfills this responsibility through comprehensive safety reviews of nuclear facilities, licensing of organizations that use nuclear materials, and continuing inspection. The NRC inspection program is currently conducted from the five regional offices in or near Philadelphia, Atlanta, Chicago, Dallas and San Francisco. Inspectors travel from the regional offices to nuclear power plants in various phases of construction, test and operation in order to conduct inspections. However, in June 1977 the Commission approved a revision to the inspection program that will include stationing inspectors at selected plants under construction and at all plants in operation. In addition, the revised program provides for appraising the performance of licensees on a national basis and involves more direct measurement and observation by NRC inspectors of work and tests in progress. The program also includes enhanced career management consisting of improved training and career development for inspectors and other professionals. The report was requested in the Conference Report on the NRC Authorization for Appropriations for Fiscal Year 1978. The report provides a discussion of the basis for both the current and revised inspection programs, describes these programs, and shows how the NRC inspection force will be trained and utilized. In addition, the report includes a discussion of the actions that will be taken to assure the objectivity of inspectors

  6. Optimal installation program for reprocessing plants

    International Nuclear Information System (INIS)

    Kubokawa, Toshihiko; Kiyose, Ryohei

    1976-01-01

    Optimization of the program of installation of reprocessing plants is mathematically formulated as problem of mixed integer programming, which is numerically solved by the branch-and-bound method. A new concept of quasi-penalty is used to obviate the difficulties associated with dual degeneracy. The finiteness of the useful life of the plant is also taken into consideration. It is shown that an analogous formulation is possible for the cases in which the demand forecasts and expected plant lives cannot be predicted with certainty. The scale of the problem is found to have kN binary variables, (k+2)N continuous variables, and (k+3)N constraint conditions, where k is the number of intervals used in the piece-wise linear approximation of a nonlinear objective function, and N the overall duration of the period covered by the installation program. Calculations are made for N=24 yr and k=3, with the assumption that the plant life is 15 yr, the plant scale factor 0.5, and the maximum plant capacity 900 (t/yr). The results are calculated and discussed for four different demand forecasts. The difference of net profit between optimal and non-optimal installation programs is found to be in the range of 50 -- 100 M$. The pay-off matrix is calculated, and the optimal choice of action when the demand cannot be forecast with certainty is determined by applying Bayes' theory. The optimal installation program under such conditions of uncertainty is obtained also with a stochastic mixed integer programming model. (auth.)

  7. Human action perspectives based on individual plant examination results

    International Nuclear Information System (INIS)

    Forester, J.; Thompson, C.; Drouin, M.; Lois, E.

    1996-01-01

    This paper provides perspectives on human actions gained from reviewing 76 individual plant examination (IPE) submittals. Human actions found to be important in boiling water reactors (BWRs) and in pressurized water reactors (PWRs) are presented and the events most frequently found important are discussed. Since there are numerous factors that can influence the quantification of human error probabilities (HEPs) and introduce significant variability in the resulting HEPs (which in turn can influence which events are found to be important), the variability in HEPs for similar events across IPEs is examined to assess the extent to which variability in results is due to real versus artifactual differences. Finally, similarities and differences in human action observations across BWRs and PWRs are examined

  8. Advancements in nuclear plant maintenance programs

    International Nuclear Information System (INIS)

    Meligi, A.E.; Maras, M.C.

    1993-01-01

    The viability of the nuclear option as a technology choice for present and future electricity generation will be decided primarily on the basis of operating cost to achieve plant performance objectives. In a nuclear plant, performance is judged not only on availability and output rate but also on safety risk and radiation exposure. Operating, cost is essentially made up of the fuel cost and operation and maintenance (O and M) cost. Over the past decade, the industry average nuclear plant performance has improved significantly; however, this improvement was accompanied by rising O and M cost. The net result was that the nuclear option lost its long-standing economic advantage over the coal option, based on the industry average comparison, around 1987 - with the gap narrowing slightly in the last 2 years. In recent times, gas-fired plants have also become a basis for comparison. The electric generation cost comparisons of various fuel options has led to even greater scrutiny of nuclear plant performance, with the poorer performing plants facing the risk of shutdown. While effective O and M programs improve plant performance, present industry data show that there is no direct correlation between the cost of a plant O and M program and its associated performance. There is a significant number of existing tools and techniques in the O and M area that have proved to be successful and have resulted in significant benefits and payback. This paper presents an overview of the nuclear industry efforts to improve the conduct of O and M activities, describes the basic elements of an effective O and M program, and addresses some of the state-of-the-art tools and techniques to enhance maintenance work planning, training, and procedures

  9. 75 FR 34941 - Review of the Commission's Program Access Rules and Examination of Programming Tying Arrangements

    Science.gov (United States)

    2010-06-21

    ... Commission's Program Access Rules and Examination of Programming Tying Arrangements AGENCY: Federal... Program Access Rules and Examination of Programming Tying Arrangements, MB Docket No. 07-198, FCC 10-17... information collection is contained in Sections 4(i), 303(r), and 628 of the Communications Act of 1934, as...

  10. Examination of a Museum Program for Children with Autism

    Science.gov (United States)

    Mulligan, Shelley; Rais, Paula; Steele-Driscoll, Jacqueline; Townsend, Samantha

    2013-01-01

    This study examined the effectiveness of a children's museum program designed to support young children with autism spectrum disorders (ASD) and their families. The program offers specialized materials, financial incentives, an exclusive time, and trained volunteers to increase the comfort level, enjoyment, and learning opportunities of attendees.…

  11. An Examination of a Gender-Separate Advisory Program

    Science.gov (United States)

    Weilbacher, Gary; Lanier, Jill

    2012-01-01

    In this qualitative study, the authors examine the advisory program of a Horizon Schools to Watch middle grades school. Horizon Schools to Watch is the Illinois affiliate of the National Forum to Accelerate Middle School Reform national Schools to Watch (STW) program, meaning schools with the STW designation have made significant inroads in…

  12. AP: A Critical Examination of the Advanced Placement Program

    Science.gov (United States)

    Sadler, Philip M.; Sonnert, Gerhard; Tai, Robert; Klopfenstein, Kirstin

    2016-01-01

    The Advanced Placement (AP) program was created to enhance the experience of gifted students as they transition from high school to college. "AP: A Critical Examination of the Advanced Placement Program," edited by Philip M. Sadler, Gerhard Sonnert, Robert Tai, and Kirstin Klopfenstein (2010, Harvard Education Press), questions the…

  13. TMI-2 information and examination program 1981 annual report

    International Nuclear Information System (INIS)

    1982-04-01

    The Department of Energy's Technical Information and Examination Program at Three Mile Island Unit 2 continued the research and development work begun on the Island in 1979. The work concentrated in seven major areas: instrumentation and electrical components; radiation and environment; off-site core examination; radioactive waste technology development; configuration and document control; waste immobilization; and reactor evaluation. Research and development work associated with the program aims toward communicating applicable information to the nuclear community. The program seeks to assist in resolving specific problems at TMI-2 and to stimulate interest in specific work activities, thus ensuring that the entire nuclear industry avails itself of the maximum amount of information possible

  14. Plant lifetime management and research program

    International Nuclear Information System (INIS)

    Sakai, K.; Nagayama, M.

    1993-01-01

    The importance of nuclear power generation has been increasing in Japan. Because the lower generation cost and more stable fuel supply, in comparison with the case of fossil plants, are beneficial to Japan which has scarce natural resources. In addition, nuclear power generation is expected to help reduce carbon dioxide emission which causes global warming. In these circumstances, the safe and stable operations of nuclear power plants are of prime importance, and the frequency of unscheduled shutdown has been kept low in Japan as a result of thorough periodic inspections supported by aging management. This paper covers the development process of the aging management program and related research programs in The Kansai Electric Power Co., Inc. (KEPCO). KEPCO runs 11 nuclear power units (PWR). A Table shows the commencement date of commercial operation and operating hours for each unit. The early plants, such as Mihama-2 Unit, have been operated for more than 100,000 hours and are in the phase of aging management. Accordingly, we have been conducting aging management programs since 1987. in order to identify age-related degradation and work out countermeasures.The aging management programs have ensured safe and stable operation of nuclear power plants. Each result of the lifetime assessment has provided the information which helps establishing maintenance programs. For example, the result of the lifetime assessment has been reflected to the intervals of overhaulings and inspections, and the replacement timing of some components. In the future activities of aging management should be revised and should focus lifetime assessment on components which provoke difficulties in inspections because of high radiation exposure or high inspection cost

  15. Nuclear Plant Aging Research (NPAR) program plan

    International Nuclear Information System (INIS)

    1991-06-01

    A comprehensive Nuclear Plant Aging Research (NPAR) Program was implemented by the US NRC office of Nuclear Regulatory Research in 1985 to identify and resolve technical safety issues related to the aging of systems, structures, and components in operating nuclear power plants. This is Revision 2 to the Nuclear Plant Aging Research Program Plant. This planes defines the goals of the program the current status of research, and summarizes utilization of the research results in the regulatory process. The plan also describes major milestones and schedules for coordinating research within the agency and with organizations and institutions outside the agency, both domestic and foreign. Currently the NPAR Program comprises seven major areas: (1) hardware-oriented engineering research involving components and structures; (2) system-oriented aging interaction studies; (3) development of technical bases for license renewal rulemaking; (4) determining risk significance of aging phenomena; (5) development of technical bases for resolving generic safety issues; (6) recommendations for field inspection and maintenance addressing aging concerns; (7) and residual lifetime evaluations of major LWR components and structures. The NPAR technical database comprises approximately 100 NUREG/CR reports by June 1991, plus numerous published papers and proceedings that offer regulators and industry important insights to aging characteristics and aging management of safety-related equipment. Regulatory applications include revisions to and development of regulatory guides and technical specifications; support to resolve generic safety issues; development of codes and standards; evaluation of diagnostic techniques; (e.g., for cables and valves); and technical support for development of the license renewal rule. 80 refs., 25 figs., 10 tabs

  16. Concrete Technology program for nuclear power plants

    International Nuclear Information System (INIS)

    Hassazadeh, M.; Wrangensten, L.

    2009-01-01

    The nuclear power plants in Sweden and Finland were built during the seventies/eighties and it is planned to extend their service life and increase their production capacity. The challenges are now to assess the condition of the concrete structures; to verify whether or not the structures can withstand the prescribed loads and functions; and verify if the structures can be upgraded in order to fulfil the requirements regarding load bearing and functional capacity. A research program was launched whose priority is condition assessment of the reactor containment. The research includes condition of the pre-stressing reinforcement, reinforcement bars, lining, leakage etc. The conditions are assessed both by destructive and non-destructive test methods. The addressed properties are physical, mechanical, electro-chemical and geometrical. The paper presents the organisation of the program, the co-operating partners, the research program, and the content of the on-going and planned research projects

  17. Neurolinguistic Programming Examined: Imagery, Sensory Mode, and Communication.

    Science.gov (United States)

    Fromme, Donald K.; Daniell, Jennifer

    1984-01-01

    Tested Neurolinguistic Programming (NLP) assumptions by examining intercorrelations among response times of students (N=64) for extracting visual, auditory, and kinesthetic information from alphabetic images. Large positive intercorrelations were obtained, the only outcome not compatible with NLP. Good visualizers were significantly better in…

  18. TMI-2 Technical Information and Examination Program. 1982 annual report

    International Nuclear Information System (INIS)

    1983-04-01

    The Department of Energy's Technical Information and Examination Program at Three Mile Island Unit 2 continued the research and development work begun on the island in 1980. The work concentrated in seven major areas: instrumentation and electrical components, radiation and environment, core activities, information and industry coordination, configuration and document control, waste immobilization, and reactor evaluation. The program assists in resolving specific problems at TMI-2 while developing techniques and broadening understanding of accident consequences to improve the overall safety and reliability of nuclear power. The Technical Information and Examination Program aims to communicate applicable information to the nuclear power industry to ensure that the industry can avail itself of the maximum amount of information possible

  19. TMI-2 Technical Information and Examination Program 1983 annual report

    International Nuclear Information System (INIS)

    Scardena, D.E.

    1984-04-01

    The Department of Energy's Technical Information and Examination Program at Three Mile Island Unit 2 continued the research and development work begun on the Island in 1980. The work concentrated in six major areas: waste immobilization, reactor evaluation, data acquisition, information and industry coordination, core activities, and EPICOR II and waste research and disposition. The program assists in resolving specific problems at TMI-2 while developing techniques and broadening understanding of accident consequences to improve the overall safety and reliability of nuclear power. The Technical Information and Examination Program aims to communicate applicable information to the nuclear power industry to ensure that the industry can avail itself to the maximum amount of information possible

  20. Examination of the program to avoid round-off error

    International Nuclear Information System (INIS)

    Shiota, Y.; Kusunoki, T.; Tabushi, K.; Shimomura, K.; Kitou, S.

    2005-01-01

    The MACRO programs which express a simple shape such as PLANE, SPHERE, CYLINDER and CONE, are used to the formation of the geometry in EGS4. Each MACRO calculates the important value for the main code to recognize the configured geometry. This calculation process may generate the calculation error due to the effect of a round-off error. SPHERE, CYLINDER and CONE MACRO include the function to avoid the effect, but PLANE MACRO dose not include. The effect of the round-off error is small usually in case of PLANE MACRO, however a slant plane may cause the expansion of the effect. Therefore, we have configured the DELPLANE program with the function to avoid the effect of the round-off error. In this study, we examine the DELPLANE program using the simply geometry with slant plane. As a result, the normal PLANE MACRO generates the round-off error, however DELPLANE program dose not generates one. (author)

  1. Cost effective snubber reduction program for nuclear power plants

    International Nuclear Information System (INIS)

    Adams, T.M.; Antaki, G.A.; Chang, K.C.

    1985-01-01

    Due to the stringent seismic requirements imposed on nuclear power plants, piping engineers have resorted to the extensive use of snubbers to support nuclear piping systems. The advantage of snubbers is that they provide dynamic restraint while allowing free thermal growth of the pipe. Unfortunately, as more plants go into operation, utilities have to face the costs of strict in-service inspection requirements and risks of unscheduled or extended plant outages associated with snubber failures. The snubber inspection requirements, defined in plant Technical Specifications, require periodic visual inspections of all snubbers and functional tests of a percentage of the plant snubbers, during refueling outages. For a typical 1000 Mw unit this represents from 50 to several hundred snubbers to be functionally tested at each refueling outage. Should failures occur during testing, the sample size must be further increased. Very quickly the costs and risks of extended shutdowns have led the industry to consider, and in many cases implement, snubber reduction programs. At the same time several changes in seismic design criteria have greatly facilitated the reduction of snubbers, making snubber elimination economically and technically attractive. In this paper we examine the costs and benefits of snubber reduction programs and propose a method for evaluating their cost benefits

  2. 75 FR 9691 - Review of the Commission's Program Access Rules and Examination of Programming Tying Arrangements

    Science.gov (United States)

    2010-03-03

    ... involving programming they own, that impede competition in the video distribution market. See H.R. Rep. No... availability of programming and charging discriminatory prices to non- cable technologies.'' H.R. Rep. No. 102... Access Rules and Examination of Programming Tying Arrangements; Final Rule #0;#0;Federal Register / Vol...

  3. Nuclear Plant Aging Research (NPAR) program plan

    International Nuclear Information System (INIS)

    1985-07-01

    The nuclear plant aging research described in this plan is intended to resolve issues related to the aging and service wear of equipment and systems at commercial reactor facilities and their possible impact on plant safety. Emphasis has been placed on identification and characterization of the mechansims of material and component degradation during service and evaluation of methods of inspection, surveillance, condition monitoring and maintenance as means of mitigating such effects. Specifically the goals of the program are as follows: (1) to identify and characterize aging and service wear effects which, if unchecked, could cause degradation of structures, components, and systems and thereby impair plant safety; (2) to identify methods of inspection, surveillance and monitoring, or of evaluating residual life of structures, components, and systems, which will assure timely detection of significant aging effects prior to loss of safety function; and (3) to evaluate the effectiveness of storage, maintenance, repair and replacement practices in mitigating the rate and extent of degradation caused by aging and service wear

  4. Relationship between internal medicine program board examination pass rates, accreditation standards, and program size.

    Science.gov (United States)

    Falcone, John L; Gonzalo, Jed D

    2014-01-19

    To determine Internal Medicine residency program compliance with the Accreditation Council for Graduate Medical Education 80% pass-rate standard and the correlation between residency program size and performance on the American Board of Internal Medicine Certifying Examination. Using a cross-sectional study design from 2010-2012 American Board of Internal Medicine Certifying Examination data of all Internal Medicine residency pro-grams, comparisons were made between program pass rates to the Accreditation Council for Graduate Medical Education pass-rate standard. To assess the correlation between program size and performance, a Spearman's rho was calculated. To evaluate program size and its relationship to the pass-rate standard, receiver operative characteristic curves were calculated. Of 372 Internal Medicine residency programs, 276 programs (74%) achieved a pass rate of =80%, surpassing the Accreditation Council for Graduate Medical Education minimum standard. A weak correlation was found between residency program size and pass rate for the three-year period (p=0.19, pInternal Medicine residency programs complied with Accreditation Council for Graduate Medical Education pass-rate standards, a quarter of the programs failed to meet this requirement. Program size is positively but weakly associated with American Board of Internal Medicine Certifying Examination performance, suggesting other unidentified variables significantly contribute to program performance.

  5. TMI-2 Technical Information and Examination Program. 1984 annual report

    International Nuclear Information System (INIS)

    Hess, C.J.

    1985-04-01

    In 1984, the US Department of Energy's Technical Information and Examination Program entered its fifth year of research and development work at Three Mile Island Unit 2 (TMI-2) and at the Idaho National Engineering Laboratory and other supporting laboratories. The work concentrated on six major areas: waste immobilization, reactor evaluation, data acquisition, information and industry coordination, core activities, and EPICOR II and waste research and disposition

  6. Design basis programs and improvements in plant operation

    International Nuclear Information System (INIS)

    Metcalf, M.F.

    1991-01-01

    Public Service Electric and Gas (PSE and G) Company operates three commercial nuclear power plants in southern New Jersey. The three plants are of different designs and vintages (two pressurized water reactors licensed in 1976 and 1980 and one boiling water reactor licensed in 1986). As the industry recognized the need to develop design basis programs, PSE and G also realized the need after a voluntary 52-day shutdown of one unit because of electrical design basis problems. In its drive to be a premier electric utility, PSE and G has been aggressively active in developing design basis documents (DBDs) with supporting projects and refined uses to obtain the expected value and see the return on investment. Progress on Salem is nearly 75% complete, while Hope Creek is 20% complete. To data, PSE and G has experienced success in the use of DBDs in areas such as development of plant modifications, development of the reliability-centered maintenance program, procedure upgrades, improved document retrieval, resolution of regulatory issues, and training. The paper examines the design basis development process, supporting projects, and expected improvements in plant operations as a result of these efforts

  7. Quality Assurance Program Plan for the Waste Isolation Pilot Plant Experimental-Waste Characterization Program

    International Nuclear Information System (INIS)

    1991-01-01

    This Quality Assurance Program Plan (QAPP) identifies the quality of data necessary to meet the specific objectives associated with the Department of Energy (DOE) Waste Isolation Pilot Plant (WIPP) Experimental-Waste Characterization Program (the Program). This experimental-waste characterization program is only one part of the WIPP Test Phase, both in the short- and long-term, to quantify and evaluate the characteristics and behavior of transuranic (TRU) wastes in the repository environment. Other parts include the bin-scale and alcove tests, drum-scale tests, and laboratory experiments. In simplified terms, the purpose of the Program is to provide chemical, physical, and radiochemical data describing the characteristics of the wastes that will be emplaced in the WIPP, while the remaining WIPP Test Phase is directed at examining the behavior of these wastes in the repository environment. 50 refs., 35 figs., 33 tabs

  8. Bohunice Nuclear Power Plant Safety Upgrading Program

    International Nuclear Information System (INIS)

    Toth, A.; Fagula, L.

    1996-01-01

    Bohunice nuclear Power Plant generation represents almost 50% of the Slovak republic electric power production. Due to such high level of commitment to nuclear power in the power generation system, a special attention is given to safe and reliable operation of NPPs. Safety upgrading and operational reliability improvement of Bohunice V-1 NPP was carried out by the Bohunice staff continuously since the plant commissioning. In the 1990 - 1993 period extensive projects were realised. As a result of 'Small Reconstruction of the Bohunice V-1 NPP', the standards of both the nuclear safety and operational reliability have been significantly improved. The implementation of another modifications that will take place gradually during extended refuelling outages and overhauls in the course of 1996 through 1999, is referred to as the Gradual Reconstruction of the Bohunice V-1 Plant. The general goal of the V-1 NPP safety upgrading is the achievement of internationally acceptable level of nuclear safety. Extensive and financially demanding modification process of Bohunice V-2 NPP is likely to be implemented after a completion of the Gradual Reconstruction of the Bohunice V-1 NPP, since the year 1999. With this in mind, a first draft of the strategy of the Bohunice V-2 NPP upgrading program based on Probabilistic Safety assessment consideration was developed. A number of actions with a general effect on Bohunice site safety is evident. All these activities are aimed at reaching the essential objective of Bohunice NPP Management - to ensure a safe, reliable and effective electric energy and heat generation at the Bohunice site. (author)

  9. LAND JUDGING AND PLANT NUTRITION, A PROGRAMMED INSTRUCTION UNIT, REPORT NUMBER 13.

    Science.gov (United States)

    LONG, GILBERT A.

    A UNIT OF PROGRAMED LEARNING MATERIALS WAS PRESENTED ON THE PRINCIPLES AND PROCEDURES OF LAND JUDGING AND PLANT NUTRITION. IN HIS PREPARATION, THE AUTHOR FIRST IDENTIFIED PRINCIPLES AND FACTS NECESSARY FOR EFFECTIVE LAND CLASSIFICATION AND PLANT NUTRITION BY EXAMINING RELEVANT SCIENTIFIC REPORTS. USING THIS INFORMATION, HE THEN FORMED A TEAM OF 16…

  10. Examining the Factors of Licensure Examination for Teachers Performance for Program Strategy Enhancement

    Directory of Open Access Journals (Sweden)

    Januard D. Dagdag

    2017-11-01

    Full Text Available Passing the Licensure Examination for Teachers (LET has been the ultimate focus of tertiary education institutions in the Philippines to meet the present demand of local and global parties and communities. Hence, various strategies are conducted to increase the likelihood that the prospect will happen. With this, the current study determines the predictors of LET performance of the 146 Bachelor of Secondary Education graduates that could serve as basis for enhancing program strategies for a better LET rating. A descriptive correlational method through the analysis of registration data on LET, grade weighted average, college admission test (CAT scores, and course audit scores was conducted. Descriptive statistics and correlational tests were employed in the analysis of these data. Results showed that low LET performance is influenced by low performances in academics and admission test, and limited course audit units taken. Admission test performance, however, does not predict LET performance in Major. On the other hand, course audit performance can only forecast licensure exam scores in Major. Hence, to increase LET performance, the program should consider benchmarking from LET performing institutions, choose the right faculty to teach a course, secure the validity and/or reliability of instructional materials and assessment tools with LET competencies, strictly implement the admission and retention policy, and assess regularly the efficacy of the course audit in all areas

  11. Canadian programs on understanding and managing aging degradation of nuclear power plant components

    International Nuclear Information System (INIS)

    Chadha, J.A.; Pachner, J.

    1989-06-01

    Maintaining adequate safety and reliability of nuclear power plants and nuclear power plant life assurance and life extension are growing in importance as nuclear plants get older. Age-related degradation of plant components is complex and not fully understood. This paper provides an overview of the Canadian approach and the main activities and their results towards understanding and managing age-related degradation of nuclear power plant components, structures and systems. A number of pro-active programs have been initiated to anticipate, detect and mitigate potential aging degradation at an early stage before any serious impact on plant safety and reliability. These programs include Operational Safety Management Program, Nuclear Plant Life Assurance Program, systematic plant condition assessment, refurbishment and upgrading, post-service examination and testing, equipment qualification, research and development, and participation in the IAEA programs on safety aspects of nuclear power plant aging and life extension. A regulatory policy on nuclear power plants is under development and will be based on the domestic as well as foreign and international studies and experience

  12. Fuel Gas Demonstration Plant Program. Volume I. Demonstration plant

    Energy Technology Data Exchange (ETDEWEB)

    1979-01-01

    The objective of this project is for Babcock Contractors Inc. (BCI) to provide process designs, and gasifier retort design for a fuel gas demonstration plant for Erie Mining Company at Hoyt Lake, Minnesota. The fuel gas produced will be used to supplement natural gas and fuel oil for iron ore pellet induration. The fuel gas demonstration plant will consist of five stirred, two-stage fixed-bed gasifier retorts capable of handling caking and non-caking coals, and provisions for the installation of a sixth retort. The process and unit design has been based on operation with caking coals; however, the retorts have been designed for easy conversion to handle non-caking coals. The demonstration unit has been designed to provide for expansion to a commercial plant (described in Commercial Plant Package) in an economical manner.

  13. Overall quality assurance program requirements for nuclear power plants

    International Nuclear Information System (INIS)

    1992-09-01

    This standard contains the requirements for the owner's overall quality assurance program for a nuclear power plant. This program encompasses all phases of a nuclear power plant life cycle, including site evaluation, design, procurement, manufacturing, construction and installation, commissioning, operation, and decommissioning. It covers the activities associated with specifying, directing, and administering the work to be done during these phases, and the evaluation and integrated of the activities and programs of participants

  14. Examining Dehydration and Hypoxic Stress in Wheat Plants Using a Porous Tube Plant Nutrient Delivery System Developed for Microgravity

    Science.gov (United States)

    Dreschel, T. W.; Hall, C. R.; Foster, T. E.; Salganic, M.; Warren, L.; Corbett, M.

    2005-01-01

    The Porous Tube Plant Nutrient Delivery System (PTPNDS) was designed for NASA to grow plants in microgravity of space. The system utilizes a controlled fluid loop to supply nutrients and water to plant roots growing on a ceramic surface moistened by capiflary action. A PTPNDS test bed was developed and utilizing remote sensing systems, spectral analyses procedures, gas-exchange, and fluorescence measurements, we examined differences in plant water status for wheat plants (Triticum aestivum, cv. Perigee) grown in a modified growth chamber during the summers of 2003 and 2004. Some differences in plant performance were detectable in the gas-exchange and fluorescence measurements. For instance, in both years the plants grown with the most available water had the lowest rates of photosynthesis and exhibited higher proportions of non-photochemical quenching particularly under low light levels. In addition, small differences in mean leaf water content between treatments were detected using spectral reflectance analyses.

  15. Water Treatment Plant Operation. Volume II. A Field Study Training Program.

    Science.gov (United States)

    California State Univ., Sacramento. School of Engineering.

    The purpose of this water treatment field study training program is to: (1) develop new qualified water treatment plant operators; (2) expand the abilities of existing operators, permitting better service both to employers and public; and (3) prepare operators for civil service and certification examinations (examinations administered by…

  16. Water Treatment Plant Operation. Volume I. A Field Study Training Program.

    Science.gov (United States)

    California State Univ., Sacramento. School of Engineering.

    The purpose of this water treatment field study training program is to: (1) develop new qualified water treatment plant operators; (2) expand the abilities of existing operators, permitting better service both to employers and public; and (3) prepare operators for civil service and certification examinations (examinations administered by…

  17. Operation of Wastewater Treatment Plants. Volume 1. A Field Study Training Program. Third Edition. Revised.

    Science.gov (United States)

    California State Univ., Sacramento. Dept. of Civil Engineering.

    The purpose of this wastewater treatment field study training program is to: (1) develop new qualified wastewater treatment plant operators; (2) expand the abilities of existing operators, permitting better service both to employers and public; and (3) prepare operators for civil service and certification examinations (examinations administered by…

  18. Water Treatment Plant Operation Volume 2. A Field Study Training Program. Revised.

    Science.gov (United States)

    California State Univ., Sacramento. School of Engineering.

    The purpose of this water treatment field study training program is to: (1) develop new qualified water treatment plant operators; (2) expand the abilities of existing operators, permitting better service both to employers and public; and (3) prepare operators for civil service and certification examinations (examinations administered by…

  19. Operations Program Plan for the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    1990-09-01

    This document, Revision 4 of the Operations Program Plan, has been developed as the seven-year master plan for operating of the Waste Isolation Pilot Plant (WIPP). Subjects covered include public and technical communications; regulatory and environmental programs; startup engineering; radiation handling, surface operations, and underground operations; waste certification and waste handling; transportation development; geotechnical engineering; experimental operations; engineering program; general maintenance; security program; safety, radiation, and regulatory assurance; quality assurance program; training program; administration activities; management systems program; and decommissioning. 243 refs., 19 figs., 25 tabs. (SM)

  20. Cost effective water treatment program in Heavy Water Plant (Manuguru)

    International Nuclear Information System (INIS)

    Mohapatra, C.; Prasada Rao, G.

    2002-01-01

    Water treatment technology is in a state of continuous evolution. The increasing urgency to conserve water and reduce pollution has in recent years produced an enormous demand for new chemical treatment programs and technologies. Heavy water plant (Manuguru) uses water as raw material (about 3000 m 3 /hr) and its treatment and management has benefited the plant in a significant way. It is a fact that if the water treatment is not proper, it can result in deposit formation and corrosion of metals, which can finally leads to production losses. Therefore, before selecting treatment program, complying w.r.t. quality requirements, safety and pollution aspects cost effectiveness shall be examined. The areas where significant benefits are derived, are raw water treatment using polyelectrolyte instead of inorganic coagulant (alum), change over of regenerant of cation exchangers from hydrochloric acid to sulfuric acid and in-house development of cooling water treatment formulation. The advantages and cost effectiveness of these treatments are discussed in detail. Further these treatments has helped the plant in achieving zero discharge and indirectly increased cost reduction of final product (heavy water); the dosage of 3 ppm of polyelectrolyte can replace 90 ppm alum at turbidity level of 300 NTU of raw water which has resulted in cost saving of Rs. 15-20 lakhs in a year beside other advantages; the change over of regenerant from HCl to H 2 SO 4 will result in cost saving of at least Rs.1.4 crore a year besides other advantages; the change over to proprietary formulation to in-house formulation in cooling water treatment has resulted in a saving about Rs.11 lakhs a year. To achieve the above objectives in a sustainable way the performance results are being monitored. (author)

  1. Examining quality improvement programs: the case of Minnesota hospitals.

    Science.gov (United States)

    Olson, John R; Belohlav, James A; Cook, Lori S; Hays, Julie M

    2008-10-01

    To determine if there is a hierarchy of improvement program adoption by hospitals and outline that hierarchy. Primary data were collected in the spring of 2007 via e-survey from 210 individuals representing 109 Minnesota hospitals. Secondary data from 2006 were assembled from the Leapfrog database. As part of a larger survey, respondents were given a list of improvement programs and asked to identify those programs that are used in their hospital. DATA COLLECTION/DATA EXTRACTION: Rasch Model Analysis was used to assess whether a unidimensional construct exists that defines a hospital's ability to implement performance improvement programs. Linear regression analysis was used to assess the relationship of the Rasch ability scores with Leapfrog Safe Practices Scores to validate the research findings. Principal Findings. The results of the study show that hospitals have widely varying abilities in implementing improvement programs. In addition, improvement programs present differing levels of difficulty for hospitals trying to implement them. Our findings also indicate that the ability to adopt improvement programs is important to the overall performance of hospitals. There is a hierarchy of improvement programs in the health care context. A hospital's ability to successfully adopt improvement programs is a function of its existing capabilities. As a hospital's capability increases, the ability to successfully implement higher level programs also increases.

  2. Interdisciplinary research and training program in the plant sciences

    Energy Technology Data Exchange (ETDEWEB)

    Wolk, C.P.

    1991-01-01

    This document is the compiled progress reports from the Interdisciplinary Research and Training Program in the Plant Sciences funded through the MSU-DOE Plant Research Laboratory. Fourteen reports are included, covering topics such as the molecular basis of plant/microbe symbiosis, cell wall proteins and assembly, gene expression, stress responses, growth regulator biosynthesis, interaction between nuclear and organelle genomes, sensory transduction and tropisms, intracellular sorting and membrane trafficking, regulation of lipid metabolism, the molecular basis of disease resistance and plant pathogenesis, developmental biology of Cyanobacteria and hormonal involvement in environmental control of plant growth. 132 refs. (MHB)

  3. Idaho Chemical Processing Plant training program

    International Nuclear Information System (INIS)

    1975-01-01

    Objectives, regulations and requirements, training methods, certification and recertification, progression and incentives, and coverage of the ICPP operator training program are discussed in detail. (LK)

  4. Aquatic Plant Control Research Program. Volume A-00-1

    National Research Council Canada - National Science Library

    Kirk, James

    2000-01-01

    ... at the Waterways Experiment Station. It is principally intended to be a forum whereby information pertaining to and resulting from the Corps of Engineers' nationwide Aquatic Plant Control Research Program (APCRP...

  5. Program change management during nuclear power plant decommissioning

    International Nuclear Information System (INIS)

    Bushart, Sean; Kim, Karen; Naughton, Michael

    2011-01-01

    Decommissioning a nuclear power plant is a complex project. The project involves the coordination of several different departments and the management of changing plant conditions, programs, and regulations. As certain project Milestones are met, the evolution of such plant programs and regulations can help optimize project execution and cost. This paper will provide information about these Milestones and the plant departments and programs that change throughout a decommissioning project. The initial challenge in the decommissioning of a nuclear plant is the development of a definitive plan for such a complex project. EPRI has published several reports related to decommissioning planning. These earlier reports provided general guidance in formulating a Decommissioning Plan. This Change Management paper will draw from the experience gained in the last decade in decommissioning of nuclear plants. The paper discusses decommissioning in terms of a sequence of major Milestones. The plant programs, associated plans and actions, and staffing are discussed based upon experiences from the following power reactor facilities: Maine Yankee Atomic Power Plant, Yankee Nuclear Power Station, and the Haddam Neck Plant. Significant lessons learned from other sites are also discussed as appropriate. Planning is a crucial ingredient of successful decommissioning projects. The development of a definitive Decommissioning Plan can result in considerable project savings. The decommissioning plants in the U.S. have planned and executed their projects using different strategies based on their unique plant circumstances. However, experience has shown that similar project milestones and actions applied through all of these projects. This allows each plant to learn from the experiences of the preceding projects. As the plant transitions from an operating plant through decommissioning, the reduction and termination of defunct programs and regulations can help optimize all facets of

  6. Examination of a University-Affiliated Safe Ride Program

    Science.gov (United States)

    Gieck, D. Joseph; Slagle, David M.

    2010-01-01

    A university-affiliated safe ride program was evaluated to determine whether these programs can reduce drunk-driving related costs. Data was collected from 187 safe ride passengers during three nights of operation. Among the passengers, 93% were enrolled at a local University, 31% were younger than 21, and 40% reported a prior alcohol-related…

  7. Programmed system for nuclear power plant protection

    International Nuclear Information System (INIS)

    Jover, Pierre.

    1980-06-01

    The progress in the field of microprocessors and large scale integration circuits, have incited to introduce this new technologies into nuclear power plant protection system. The hardware and software design principles are briefly listed; then, a quad-redundant protection system for 1300 MWe PWR, developed in France is described [fr

  8. Nuclear plant analyzer program for Bulgaria

    International Nuclear Information System (INIS)

    Shier, W.; Kennett, R.

    1993-01-01

    An interactive nuclear plant analyzer(NPA) has been developed for use by the Bulgarian technical community in the training of plant personnel, the development and verification of plant operating procedures, and in the analysis of various anticipated operational occurrences and accident scenarios. The current NPA includes models for a VVER-440 Model 230 and a VVER-1000 Model 320 and is operational on an IBM RISC6000 workstation. The RELAP5/MOD2 computer code has been used for the calculation of the reactor responses to the interactive commands initiated by the NPA operator. The interactive capabilities of the NPA have been developed to provide considerable flexibility in the plant actions that can be initiated by the operator. The current capabilities for both the VVER-440 and VVER-1000 models include: (1) scram initiation; (2) reactor coolant pump trip; (3) high pressure safety injection system initiation; (4) low pressure safety injection system initiation; (5) pressurizer safety valve opening; (6) steam generator relief/safety valve opening; (7) feedwater system initiation and trip; (8) turbine trip; and (9) emergency feedwater initiation. The NPA has the capability to display the results of the simulations in various forms that are determined by the model developer. Results displayed on the reactor mask are shown through the user defined, digital display of various plant parameters and through color changes that reflect changes in primary system fluid temperatures, fuel and clad temperatures, and the temperature of other metal structures. In addition, changes in the status of various components and systems can be initiated and/or displayed both numerically and graphically on the mask. This paper provides a description of the structure of the NPA, a discussion of the simulation models used for the VVER-440 and the VVER-1000, and an overview of the NPA capabilities. Typical results obtained using both simulation models will be discussed

  9. Nuclear plant aging research program activities

    International Nuclear Information System (INIS)

    Eissenberg, D.M.

    1986-01-01

    The objective of this program is to provide recommendations for use by NRC regarding the availability and capability of diagnostic methods for assuring the operational readiness of NPP safety systems and components

  10. Examination history and abnormal thyroid and breast lesions according to residential distance from nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Lim, Young Khi [Dept. of Radiological Science, Gachon University, Incheon (Korea, Republic of)

    2016-12-15

    Ascertainment bias are common in epidemiologic studies to assess the association between thyroid cancer risk and living near nuclear power plants because many thyroid cancers are diagnosed by chance through health examination. We surveyed the ultra sonography (USG) examination history and conducted thyroid and breast USG in residents living near nuclear power plants. The study population comprised 2,421 residents living near nuclear power plants in Korea. Information on demographic characteristics, including diagnostic examination history, was collected by interview using questionnaires. USG examination was conducted to evaluate the presence of thyroid nodules and breast lesion. Study participants were divided into 3 groups according to the distance of their respective villages from a nuclear power plant. The proportions of USG examination history and prevalence of thyroid nodules and breast lesions were compared between groups. Examination histories of thyroid USG were 23.1%, 13.7%, and 10.5% in men and 31.3%, 26.7%, 18.3% in women in the short, intermediate, and long distance groups, respectively. There were significant inverse associations between thyroid USG history and the distance from nuclear power plants (P for trend=0.001 for men and 0.017 for women). However, there was no association between the distance of villages from nuclear power plants and prevalence of thyroid nodules. Our results suggest that there may be an ascertainment bias in population-based studies examining the harmful effects of NPPs examination and researchers should pay attention to ascertainment bias resulted from differential health examination. Correction for ascertainment bias, active follow-up and examination for all study population to remove differential health examination is needed.

  11. Examination history and abnormal thyroid and breast lesions according to residential distance from nuclear power plants

    International Nuclear Information System (INIS)

    Lim, Young Khi

    2016-01-01

    Ascertainment bias are common in epidemiologic studies to assess the association between thyroid cancer risk and living near nuclear power plants because many thyroid cancers are diagnosed by chance through health examination. We surveyed the ultra sonography (USG) examination history and conducted thyroid and breast USG in residents living near nuclear power plants. The study population comprised 2,421 residents living near nuclear power plants in Korea. Information on demographic characteristics, including diagnostic examination history, was collected by interview using questionnaires. USG examination was conducted to evaluate the presence of thyroid nodules and breast lesion. Study participants were divided into 3 groups according to the distance of their respective villages from a nuclear power plant. The proportions of USG examination history and prevalence of thyroid nodules and breast lesions were compared between groups. Examination histories of thyroid USG were 23.1%, 13.7%, and 10.5% in men and 31.3%, 26.7%, 18.3% in women in the short, intermediate, and long distance groups, respectively. There were significant inverse associations between thyroid USG history and the distance from nuclear power plants (P for trend=0.001 for men and 0.017 for women). However, there was no association between the distance of villages from nuclear power plants and prevalence of thyroid nodules. Our results suggest that there may be an ascertainment bias in population-based studies examining the harmful effects of NPPs examination and researchers should pay attention to ascertainment bias resulted from differential health examination. Correction for ascertainment bias, active follow-up and examination for all study population to remove differential health examination is needed

  12. Oral Anatomy Laboratory Examinations in a Physical Therapy Program

    Science.gov (United States)

    Fabrizio, Philip A.

    2013-01-01

    The process of creating and administering traditional tagged anatomy laboratory examinations is time consuming for instructors and limits laboratory access for students. Depending on class size and the number of class, sections, creating, administering, and breaking down a tagged laboratory examination may involve one to two eight-hour days.…

  13. State of Washington Aquatic Plant Management Program

    Science.gov (United States)

    1979-10-01

    endothall (DMA salt); and herbivorous fish, insects , and pathogens. 4. Comments Received from Public Review of the Draft Environmental Impact Statement...SNYIAOWMNWAL MANWULATION UIONOGC SSUCTION DREDGE HAND RUMOVA HOTTON SHADING WATER LEVEL FLUCTUATIONS HERBIVOROUS FIS1H INSECTS , PAT1OGIENS, ETC. set...the control of acuatic plants. 52 4. PROBABLE IMPACTS OF THE PROPOSED ACTION ON~ THE ENVIRON4MENT 4.01 Impacts on Air Quality, Noise and Traffic. 4.01.1

  14. Examining Community-Engaged Scholarship in Public Administration Programs

    Science.gov (United States)

    Norvell, Katrina Herndon

    2010-01-01

    This study sought to broaden the understanding of the role that academic professions play in shaping the values and attitudes of faculty toward CES. This study explored faculty perceptions regarding the factors that encourage or dissuade them in the pursuit of CES within public administration programs. As a framework for research, a conceptual…

  15. Examining the role of shrub expansion and fire in Arctic plant silica cycling

    Science.gov (United States)

    Carey, J.; Fetcher, N.; Parker, T.; Rocha, A. V.; Tang, J.

    2017-12-01

    All terrestrial plants accumulate silica (SiO2) to some degree, although the amount varies by species type, functional group, and environmental conditions. Silica improves overall plant fitness, providing protection from a variety of biotic and abiotic stressors. Plant silica uptake serves to retain silica in terrestrial landscapes, influencing silica export rates from terrestrial to marine systems. These export rates are important because silica is often the limiting nutrient for primary production by phytoplankton in coastal waters. Understanding how terrestrial plant processes influence silica export rates to oceanic systems is of interest on the global scale, but nowhere is this issue more important than in the Arctic, where marine diatoms rely on silica for production in large numbers and terrestrial runoff largely influences marine biogeochemistry. Moreover, the rapid rate of change occurring in the Arctic makes understanding plant silica dynamics timely, although knowledge of plant silica cycling in the region is in its infancy. This work specifically examines how shrub expansion, permafrost thaw, and fire regimes influence plant silica behavior in the Alaskan Arctic. We quantified silica accumulation in above and belowground portions of three main tundra types found in the Arctic (wet sedge, moist acidic, moist non-acidic tundra) and scaled these values to estimate how shrub expansion alters plant silica accumulation rates. Results indicate that shrub expansion via warming will increase silica storage in Arctic land plants due to the higher biomass associated with shrub tundra, whereas conversion of tussock to wet sedge tundra via permafrost thaw would produce the opposite effect in the terrestrial plant BSi pool. We also examined silica behavior in plants exposed to fire, finding that post-fire growth results in elevated plant silica uptake. Such changes in the size of the terrestrial vegetation silica reservoir could have direct consequences for the rates

  16. Nuclear Power Plant Fire Protection Research Program

    International Nuclear Information System (INIS)

    Datta, A.

    1985-07-01

    The goal is to develop test data and analytical capabilities to support the evaluation of: (1) the contribution of fires to the risk from nuclear power plants; (2) the effects of fires on control room equipment and operations; and (3) the effects of actuation of fire suppression systems on safety equipment. A range of fire sources will be characterized with respect to their energy and mass evolution, including smoke, corrosion products, and electrically conductive products of combustion. An analytical method for determining the environment resulting from fire will be developed. This method will account for the source characteristics, the suppression action following detection of the fire, and certain parameters specific to the plant enclosure in which the fire originates, such as the geometry of the enclosure and the ventilation rate. The developing local environment in the vicinity of safety-related equipment will be expressed in terms of temperatures, temperature rise rates, heat fluxes, and moisture and certain species content. The response of certain safe shutdown equipment and components to the environmental conditions will be studied. The objective will be to determine the limits of environmental conditions that a component may be exposed to without impairment of its ability to function

  17. TMI-2 core-examination program: INEL facilities readiness study

    International Nuclear Information System (INIS)

    McLaughlin, T.B.

    1983-02-01

    This report reviews the capability and readiness of remote handling facilities at the Idaho National Engineering Laboratory (INEL) to receive, and store the TMI-2 core, and to examine and analyze TMI-2 core samples. To accomplish these objectives, the facilities must be able to receive commercial casks, unload canisters from the casks, store the canisters, open the canisters, handle the fuel debris and assemblies, and perform various examinations. The report identifies documentation, including core information, necessary to INEL before receiving the entire TMI-2 core. Also identified are prerequisites to INEL's receipt of the first canister: costs, schedules, and a preliminary project plan for the tasks

  18. Examining Understandings of Parent Involvement in Early Childhood Programs

    Science.gov (United States)

    Hilado, Aimee V.; Kallemeyn, Leanne; Phillips, Lauren

    2013-01-01

    The importance of parent involvement in children's development and learning is increasingly recognized in the research literature and in federal and state policies; however, no unified definition of parent involvement exists. This study examined different understandings and definitions of parent involvement in a sample of administrators of…

  19. The Nevada Proficiency Examination Program: Evaluating the Writing Samples.

    Science.gov (United States)

    Howard, Edward H.

    Writing tests are part of the mandated statewide proficiency examination in Nevada. The ninth-grade screening test and the eleventh-grade diploma-certifying test require that a student write a paragraph and a business letter, each on an assigned topic and each at an acceptable level of proficiency. Pilot tests, extended discussion, and statistical…

  20. Bibliography of the Maryland Power Plant Research Program, fourteenth edition

    International Nuclear Information System (INIS)

    McLean, R.I.

    1993-02-01

    The Power Plant Siting Act of 1971 (Sec. 3-303) established the Power Plant Research Program to ensure that demands for electric power would be met in a timely manner at a reasonable cost while assuring that the associated environmental impact would be acceptable. The scope of the Program extends to estimating the impact of proposed new generating facilities, evaluating the acceptability of proposed transmission line routes, assessing the impact of existing generation facilities, and investigating generic issues related to power plant site evaluation and associated environmental and land use considerations. The bibliography is a compilation of all the studies performed for and/or by the Power Plant and Environmental Review Division since its inception

  1. Bibliography of the Maryland Power Plant Research Program, Thirteenth Edition

    International Nuclear Information System (INIS)

    McLean, R.I.

    1992-02-01

    The Power Plant Siting Act of 1971 (Sec. 3-303) established the Power Plant Research Program to insure that demands for electric power would be met in a timely manner at a reasonable cost while assuring that the associated environmental impact would be acceptable. The scope of the Program extends to estimating the impact of proposed new generating facilities, evaluating the acceptability of proposed transmission line routes, assessing the impact of existing generation facilities, and investigating generic issues related to power plant site evaluation and associated environmental and land use considerations. The bibliography is a compilation of all the studies performed for and or by the Power Plant and Environmental Review Division since its inception. Reports published by the Division considered to be of general interest are routinely made available through the National Technical Information Service. Those reports so registered may be identified by the NTIS accession number immediately following the citation in the bibliography

  2. Global warming mitigation strategies and programs for power plant developers

    International Nuclear Information System (INIS)

    Holmes, N.R.

    1992-01-01

    Power plant developers are increasingly being surprised by regulatory agencies requiring them to mitigate the carbon dioxide(CO 2 ) emissions from their proposed power plants, as part of the plant's operating permit conditions. Since carbon dioxide is not a criteria pollutant with a National Ambient Air Quality Standard, power plant developers are often troubled by this additional regulatory requirement. This presentation will describe the contribution that CO 2 makes to global warming, the role of trees and forests as carbon sequesters or sinks, some non-forestry related and forestry related mitigation programs, including the advantages, disadvantages, and some cost estimates for the forestry related CO 2 mitigation programs. As public concern about global warming continues to escalate, it is almost certain that regulatory agencies will increase their focus on CO 2 mitigation

  3. Early Site Permit Demonstration Program: Plant parameters envelope report

    International Nuclear Information System (INIS)

    1993-03-01

    The Early Site Permit (ESP) Demonstration Program is the nuclear industry's initiative for piloting the early resolution of siting-related issues before the detailed design proceedings of the combined operating license review. The ESP Demonstration Program consists of three phases. The plant parameters envelopes task is part of Phase 1, which addresses the generic review of applicable federal regulations and develops criteria for safety and environmental assessment of potential sites. The plant parameters envelopes identify parameters that characterize the interface between an ALWR design and a potential site, and quantify the interface through values selected from the Utility Requirements Documents, vendor design information, or engineering assessments. When augmented with site-specific information, the plant parameters envelopes provide sufficient information to allow ESPs to be granted based on individual ALWR design information or enveloping design information for the evolutionary, passive, or generic ALWR plants. This document is expected to become a living document when used by future applicants

  4. Examining the Small Renewable Energy Power (SREP) Program in Malaysia

    Energy Technology Data Exchange (ETDEWEB)

    Sovacool, Benjamin K., E-mail: bsovacool@nus.edu.sg [Lee Kuan Yew School of Public Policy, National University of Singapore, 469C Bukit Timah Road, Singapore 259772 (Singapore); Drupady, Ira Martina [Lee Kuan Yew School of Public Policy, National University of Singapore, 469C Bukit Timah Road, Singapore 259772 (Singapore)

    2011-11-15

    The Small Renewable Energy Power (SREP) Program was the premier policy mechanism implemented by the national government to promote small-scale renewable electricity in Malaysia from 2001 to 2010. However, it managed meet less than 3 percent of its original goal by 2005. This study investigates what happened. More specifically, using a qualitative semi-structured interview approach with data presented in a narrative format, it answers the following five questions: (1) What are the primary energy policy and security challenges facing Malaysia? (2) What were the drivers behind the SREP in Malaysia? (3) What were the major benefits arising from the SREP? (4) What were the significant challenges to implementation? (5) What lessons or insights does the SREP offer for the study of energy policy design and implementation more generally? We find that the SREP failed to achieve its targets due to capacity caps, a lengthy approval process, lack of monitoring, exclusion of stakeholders, and few (if any) pre-feasibility studies. Other factors explaining its poor performance include opposition from the national utility Tenaga Nasional Berhad and electricity tariffs unmatched with true production costs. - Highlights: > The Small Renewable Energy Power Program aimed to install 500 MW by 2005. > It installed only 12 MW by December 2005. > This study investigates why the SREP failed to achieve its targets.

  5. Examining the Small Renewable Energy Power (SREP) Program in Malaysia

    International Nuclear Information System (INIS)

    Sovacool, Benjamin K.; Drupady, Ira Martina

    2011-01-01

    The Small Renewable Energy Power (SREP) Program was the premier policy mechanism implemented by the national government to promote small-scale renewable electricity in Malaysia from 2001 to 2010. However, it managed meet less than 3 percent of its original goal by 2005. This study investigates what happened. More specifically, using a qualitative semi-structured interview approach with data presented in a narrative format, it answers the following five questions: (1) What are the primary energy policy and security challenges facing Malaysia? (2) What were the drivers behind the SREP in Malaysia? (3) What were the major benefits arising from the SREP? (4) What were the significant challenges to implementation? (5) What lessons or insights does the SREP offer for the study of energy policy design and implementation more generally? We find that the SREP failed to achieve its targets due to capacity caps, a lengthy approval process, lack of monitoring, exclusion of stakeholders, and few (if any) pre-feasibility studies. Other factors explaining its poor performance include opposition from the national utility Tenaga Nasional Berhad and electricity tariffs unmatched with true production costs. - Highlights: → The Small Renewable Energy Power Program aimed to install 500 MW by 2005. → It installed only 12 MW by December 2005. → This study investigates why the SREP failed to achieve its targets.

  6. Human factors engineering plan for reviewing nuclear plant modernization programs

    International Nuclear Information System (INIS)

    O'Hara, John; Higgins, James

    2004-12-01

    The Swedish Nuclear Power Inspectorate reviews the human factors engineering (HFE) aspects of nuclear power plants (NPPs) involved in the modernization of the plant systems and control rooms. The purpose of a HFE review is to help ensure personnel and public safety by verifying that accepted HFE practices and guidelines are incorporated into the program and nuclear power plant design. Such a review helps to ensure the HFE aspects of an NPP are developed, designed, and evaluated on the basis of a structured top-down system analysis using accepted HFE principles. The review addresses eleven HFE elements: HFE Program Management, Operating Experience Review, Functional Requirements Analysis and Allocation, Task Analysis, Staffing, Human Reliability Analysis, Human-System Interface Design, Procedure Development, Training Program Development, Human Factors Verification and Validation, and Design Implementation

  7. Status of the decommissioning program of the Eurochemic reprocessing plant

    International Nuclear Information System (INIS)

    Detilleux, E.J.

    1976-01-01

    Reprocessing operations at the Eurochemic demonstration plant stopped in December 1974, after 8 years of operation. Immediately thereafter, cleaning and decontamination were begun as the first phase of the decommissioning program. The facility and reprocessing program are described to indicate the magnitude of the problem, and the requirements of the local authorities are reviewed. The technical decommissioning program consists of several phases: (1) plant cleaning and rinsing, (2) establishment of the final fissile-material balance, (3) plant decontamination for access to process equipment, (4) equipment dismantling, and (5) conditioning and storage of newly generated wastes. The two first phases have been completed, and the third one is nearing completion. Some dismantling has been performed, including the plutonium dioxide production unit. Waste-conditioning and surface-storage facilities have been built to meet the dismantling requirements. Since reprocessing may be resumed in the future, decontamination has been performed with ''smooth'' reagents to limit corrosion and dismantling has been limited to subfacilities

  8. Human factors engineering plan for reviewing nuclear plant modernization programs

    Energy Technology Data Exchange (ETDEWEB)

    O' Hara, John; Higgins, James [Brookhaven National Laboratory, Upton, NY (United States)

    2004-12-01

    The Swedish Nuclear Power Inspectorate reviews the human factors engineering (HFE) aspects of nuclear power plants (NPPs) involved in the modernization of the plant systems and control rooms. The purpose of a HFE review is to help ensure personnel and public safety by verifying that accepted HFE practices and guidelines are incorporated into the program and nuclear power plant design. Such a review helps to ensure the HFE aspects of an NPP are developed, designed, and evaluated on the basis of a structured top-down system analysis using accepted HFE principles. The review addresses eleven HFE elements: HFE Program Management, Operating Experience Review, Functional Requirements Analysis and Allocation, Task Analysis, Staffing, Human Reliability Analysis, Human-System Interface Design, Procedure Development, Training Program Development, Human Factors Verification and Validation, and Design Implementation.

  9. Genetic Programming for Medicinal Plant Family Identification System

    Directory of Open Access Journals (Sweden)

    Indra Laksmana

    2014-11-01

    Full Text Available Information about medicinal plants that is available in text documents is generally quite easy to access, however, one needs some efforts to use it. This research was aimed at utilizing crucial information taken from a text document to identify the family of several species of medicinal plants using a heuristic approach, i.e. genetic programming. Each of the species has its unique features. The genetic program puts the characteristics or special features of each family into a tree form. There are a number of processes involved in the investigated method, i.e. data acquisition, booleanization, grouping of training and test data, evaluation, and analysis. The genetic program uses a training process to select the best individual, initializes a generate-rule process to create several individuals and then executes a fitness evaluation. The next procedure is a genetic operation process, which consists of tournament selection to choose the best individual based on a fitness value, the crossover operation and the mutation operation. These operations have the purpose of complementing the individual. The best individual acquired is the expected solution, which is a rule for classifying medicinal plants. This process produced three rules, one for each plant family, displaying a feature structure that distinguishes each of the families from each other. The genetic program then used these rules to identify the medicinal plants, achieving an average accuracy of 86.47%.

  10. Practical standard for nuclear power plant life management programs: 2007

    International Nuclear Information System (INIS)

    2006-03-01

    The standard specifies the method of implementing nuclear power plant life management programs. The plant life management programs evaluate the integrity of the plant structures, systems and components, assessing if appropriate measures are taken against existing aging phenomena, if there are possibilities of occurrence and development of aging phenomena and if a sufficient level of margin is maintained to assure the integrity throughout the future operating period. The programs also assess the validity of the current maintenance activities, such as trend monitoring, walkdowns, periodic tests and inspections, repair and replacement work for the purpose of preventive maintenance, and utilization of lessons learned from past trouble experience, in order to newly identify maintenance measures. The technical evaluation on aging phenomena is conducted to establish the 10 year maintenance program for nuclear power plants until the plant reaches 30 years of service. The standard was established and issued by the Atomic Energy Society of Japan (AESJ) through the discussion of experts in the associated fields. (T. Tanaka)

  11. NOTE - Program R: applications in plant breeding

    Directory of Open Access Journals (Sweden)

    Luiz Alexandre Peternelli

    2011-01-01

    Full Text Available Nowadays the demand for so-called free, or open source software for data analysis as well as the appeal to use it isgreat. An public domain software that has become extremely well-known, with ever-increasing numbers of fans and even coworkers, is Environment R, or simply R. R is extremely useful for data analysis and manipulation in view of a range of tools alreadyimplemented. Also, R is not simply a statistical program, because, by its easy on using internal functions and also creating new ones,statistical procedures applied to data can also be created, manipulated, evaluated and interpreted. R contains numerous libraries(or packages, some already included in the default setting. This course will focus on the application of R in statistical analyses inplant breeding. Explanations on the use of various commands and functions will be illustrated with examples, to facilitate theinterpretation and adaptation to other similar problems.

  12. Research program plan. Non-destructive examination. Volume 4

    International Nuclear Information System (INIS)

    Muscara, J.

    1985-07-01

    Nondestructive examination/evaluation (NDE) of nuclear reactor components is required during fabrication, before service, and at regularly scheduled shutdowns for periodic inservice inspection (ISI). Any flaws produced during fabrication should be detected by the fabrication and preservice baseline examinations and components containing rejectable flaws should be repaired before the reactor enters service. The purpose of ISI is to ensure that any flaws which develop during service can be detected and evaluated and that unacceptable components are repaired or replaced to maintain safety, as well as to identify possible generic-type defects that may be present or developing in the remainder of the system or other similar systems so that timely corrective actions can be taken. The major thrusts of the research in ultrasonic testing for ISI are (1) to define the influence of inspection variables and procedures on inspection reliability and to determine the impact of inspection unreliability on system safety and (2) to study and evaluate improved techniques for reliable and accurate flaw detection and characterization. This research, therefore, has direct impact on evaluations of and improvements in reactor safety

  13. Development of Intelligent Database Program for PSI/ISI Data Management of Nuclear Power Plant

    International Nuclear Information System (INIS)

    Park, Un Su; Park, Ik Keun; Um, Byong Guk; Park, Yun Won; Kang, Suk Chul

    1998-01-01

    For an effective and efficient management of large amounts of preservice/inservice inspection(PSI/ISI) data in nuclear power plants, an intelligent Windows 95-based data management program was developed. This program enables the prompt extraction of previously conducted PSI/ISI conditions and results so that the time-consuming data management, painstaking data processing and analysis in the past are avoided. The program extracts, and the associated remedies. Furthermore, additional inspection data and comments can be easily added or deleted for subsequent PSI/ISI operation. Although the initial version of the program was applied to Kori nuclear power plant, this program can be equally applied to other nuclear power plant. And also this program can be used to offer the fundamental data for application of evaluation data related to fracture mechanics analysis(FMA), probabilistic reliability assessment(PRA) of PSI/ISI results, performance demonstration initiative(PDI) and risk-informed ISI based on probability of detection(POD) information of ultrasonic examination. Besides, the program can be further developed as a unique PSI/ISI data management expert system that can be apart of PSI/ISI data management expert system that can be a part of PSI/ISI Total Support System(TSS) for Korean nuclear power plants

  14. 46 CFR 176.630 - The Alternative Hull Examination (AHE) Program application.

    Science.gov (United States)

    2010-10-01

    ... 46 Shipping 7 2010-10-01 2010-10-01 false The Alternative Hull Examination (AHE) Program... PASSENGER VESSELS (UNDER 100 GROSS TONS) INSPECTION AND CERTIFICATION Hull and Tailshaft Examinations § 176.630 The Alternative Hull Examination (AHE) Program application. If your vessel meets the eligibility...

  15. 46 CFR 176.650 - Alternative Hull Examination Program options: Divers or underwater ROV.

    Science.gov (United States)

    2010-10-01

    ... 46 Shipping 7 2010-10-01 2010-10-01 false Alternative Hull Examination Program options: Divers or...) SMALL PASSENGER VESSELS (UNDER 100 GROSS TONS) INSPECTION AND CERTIFICATION Hull and Tailshaft Examinations § 176.650 Alternative Hull Examination Program options: Divers or underwater ROV. To complete the...

  16. 46 CFR 115.650 - Alternative Hull Examination (AHE) Program options: Divers or underwater ROV.

    Science.gov (United States)

    2010-10-01

    ... 46 Shipping 4 2010-10-01 2010-10-01 false Alternative Hull Examination (AHE) Program options... MORE THAN 49 PASSENGERS INSPECTION AND CERTIFICATION Hull and Tailshaft Examinations § 115.650 Alternative Hull Examination (AHE) Program options: Divers or underwater ROV. To complete your underwater...

  17. Integrated inspection programs at Bruce Heavy Water Plant

    International Nuclear Information System (INIS)

    Brown, K.C.

    1992-01-01

    Quality pressure boundary maintenance and an excellent loss prevention record at Bruce Heavy Water Plant are the results of the Material and Inspection Unit's five inspection programs. Experienced inspectors are responsible for the integrity of the pressure boundary in their own operating area. Inspectors are part of the Technical Section, and along with unit engineering staff, they provide technical input before, during, and after the job. How these programs are completed, and the results achieved, are discussed. 5 figs., 1 appendix

  18. The program of reactors and nuclear power plants

    International Nuclear Information System (INIS)

    Calabrese, Carlos R.

    2001-01-01

    Into de framework of the program of research reactors and nuclear power plants, the operating Argentine reactors are described. The uses of the research reactors in Argentina are summarized. The reactors installed by Argentina in other countries (Peru, Algeria, Egypt) are briefly described. The CAREM project for the design and construction of an innovator small power reactor (27 MWe) is also described in some detail. The next biennial research and development program for reactor is briefly outlined

  19. Integrated inspection programs at Bruce Heavy Water Plant

    Energy Technology Data Exchange (ETDEWEB)

    Brown, K C [Ontario Hydro, Tiverton, ON (Canada)

    1993-12-31

    Quality pressure boundary maintenance and an excellent loss prevention record at Bruce Heavy Water Plant are the results of the Material and Inspection Unit`s five inspection programs. Experienced inspectors are responsible for the integrity of the pressure boundary in their own operating area. Inspectors are part of the Technical Section, and along with unit engineering staff, they provide technical input before, during, and after the job. How these programs are completed, and the results achieved, are discussed. 5 figs., 1 appendix.

  20. Slurry steam generator program and baseline eddy current examination

    International Nuclear Information System (INIS)

    Clark, R.A.; Doctor, P.G.

    1985-01-01

    The Steam Generator Group Project was initiated in January 1982 with formation of consortium including NRC, EPRI, Japanese, French, and Italian participants. The project utilizes a retired-from-service nuclear steam generator established in a specially designed facility which houses the unit in its normal vertical operating position. The most important objectives deal with validation of nondestructive examination (NDE) techniques used to characterize steam generators during service. This research generator offers the first opportunity to characterize a statistically significant number of service-induced defects nondestructively followed by destructive metallographic confirmation. The project seeks to establish the reliability of defect detection and the accuracy of sizing defects via current state-of-the-art NDE. Other service degraded tubes will be burst tested to establish remaining service integrity. The integrity information and NDE reliability results will serve as inputs to establish a model for steam generator in-service inspections, and provide a data base for evaluation of tube plugging criteria. In addition to NDE validation goals, the project will use the service degraded generator as a specimen for demonstration/proof testing of repair and maintenance techniques, including chemical cleaning/decontamination technologies. In addition to the efforts associated with NDE, a multitude of other project tasks have continued through 1984, and results are presented

  1. Surry steam generator program and baseline eddy current examination

    International Nuclear Information System (INIS)

    Clark, R.A.; Doctor, P.G.

    1985-01-01

    The Steam Generator Group Project was initiated in January 1982 with formation of consortium including NRC, EPRI, Japanese, French, and Italian participants. The project utilizes a retired-from-service nuclear steam generator established in a specially designed facility which houses the unit in its normal vertical operating position. The most important objectives deal with validation of nondestructive examination (NDE) techniques used to characterize steam generators during service. This research generator offers the first opportunity to characterize a statistically significant number of service-induced defects nondestructively followed by destructive metallographic confirmation. The project seeks to establish the reliability of defect detection and the accuracy of sizing defects via current state-of-the-art NDE. Other service degraded tubes will be burst tested to establish remaining service integrity. The integrity information and NDE reliability results will serve as inputs to establish a model for steam generator in-service inspections, and provide a data base for evaluation of tube plugging criteria. In addition to NDE validation goals, the project will use the service degraded generator as a specimen for demonstration/proof testing of repair and maintenance techniques, including chemical cleaning/decontamination technologies. In addition to the efforts associated with NDE, a multitude of other project tasks have continued through 1984, and results are presented

  2. Aquatic Plant Control Research Program. Allelopathic Aquatic Plants for Aquatic Plant Management: A Feasibility Study

    Science.gov (United States)

    1989-10-01

    1978. " Ecotoxicology of aquatic plant communi- ties," Principles of Ecotoxicology , SCOPE Report 12, Chapter 11, pp 239-255. [Heavy metals, Pollutants...Phragmites communis and Equisetum limosum were cultivated . They found plant-plant influences depend on soil type. Typha latifolia, S. A2 lacustris, and

  3. Quality assurance program preparation - review of requirements and plant systems - selection of program levels

    International Nuclear Information System (INIS)

    Asmuss, G.

    1980-01-01

    The establishment and implementation for a practicable quality assurance program for a nuclear power plant demands a detailed background in the field of engineering, manufacturing, organization and quality assurance. It will be demonstrated with examples to define and control the achievement of quality related activities during the phases of design, procurement, manufactoring, commissioning and operation. In general the quality assurance program applies to all items, processes and services important to safety of nuclear power plant. The classification for safety related and non-safety related items and services demonstrate the levels of quality assurance requirements. The lecture gives an introduction of QA Program preparation under the following topics: -Basic criteria and international requirements - Interaction of QA activities - Modular and product oriented QA programs - Structuring of organization for the QA program - Identification of the main quality assurance functions and required actions - Quality Assurance Program documentation - Documentation of planning of activities - Control of program documents - Definitions. (orig./RW)

  4. Quality assurance program description: Hanford Waste Vitrification Plant, Part 1

    International Nuclear Information System (INIS)

    1992-01-01

    This document describes the Department of Energy's Richland Field Office (DOE-RL) quality assurance (QA) program for the processing of high-level waste as well as the Vitrification Project Quality Assurance Program for the design and construction of the Hanford Waste Vitrification Plant (HWVP). It also identifies and describes the planned activities that constitute the required quality assurance program for the HWVP. This program applies to the broad scope of quality-affecting activities associated with the overall HWVP Facility. Quality-affecting activities include designing, purchasing, fabricating, handling, shipping, storing, cleaning, erecting, installing, inspecting, testing, maintaining, repairing, and modifying. Also included are the development, qualification, and production of waste forms which may be safely used to dispose of high-level radioactive waste resulting from national defense activities. The HWVP QA program is made up of many constituent programs that are being implemented by the participating organizations. This Quality Assurance program description is intended to outline and define the scope and application of the major programs that make up the HWVP QA program. It provides a means by which the overall program can be managed and directed to achieve its objectives. Subsequent parts of this description will identify the program's objectives, its scope, application, and structure

  5. Plant programmed cell death, ethylene and flower senescence

    NARCIS (Netherlands)

    Woltering, E.J.; Jong, de A.; Hoeberichts, F.A.; Iakimova, E.T.; Kapchina, V.

    2005-01-01

    Programmed cell death (PCD) applies to cell death that is part of the normal life of multicellular organisms. PCD is found throughout the animal and plant kingdoms; it is an active process in which a cell suicide pathway is activated resulting in controlled disassembly of the cell. Most cases of PCD

  6. Near-term benefits of the plant life extension program

    International Nuclear Information System (INIS)

    Kaushansky, M.M.

    1987-01-01

    The aging process can be expected to reduce the availability and increase the production costs of nuclear power plants over time. To mitigate this process and recover or enhance plant availability, capacity, thermal efficiency, and maintenance expenditures, the utility must dedicate increased attention and commitment to a comprehensive plant life extension (PLEX) program. Improvements must be justified by balancing the cost of the recommended modifications with the economic value of benefits obtained from its implementation. It is often extremely difficult for utility management to make an optimal selection from among hundreds of proposed projects, most of which are cost-effective. A properly structured PLEX program with an emphasis on near-term benefits should provide the utility with a means of evaluating proposed projects, thus determining the optimum combination for authorization and implementation

  7. The Meteorological Monitoring program at a former nuclear weapons plant

    International Nuclear Information System (INIS)

    Maxwell, D.R.; Bowen, B.M.

    1994-01-01

    The purpose of the Meteorological Monitoring program at Rocky Flats Plant (RFP) is to provide meteorological information for use in assessing the transport, and diffusion, and deposition of effluent actually or potentially released into the atmosphere by plant operations. Achievement of this objective aids in protecting health and safety of the public, employees, and environment, and directly supports Emergency Response programs at RFP. Meteorological information supports the design of environmental monitoring networks for impact assessments, environmental surveillance activities, remediation activities, and emergency responses. As the mission of the plant changes from production of nuclear weapons parts to environmental cleanup and economic development, smaller releases resulting from remediation activities become more likely. These possible releases could result from airborne fugitive dust, evaporation from collection ponds, or grass fires

  8. An augmented audit program for assuring radiation safety during radiographic examination operations

    International Nuclear Information System (INIS)

    Jervey, R.A. Jr.; Papin, P.J.

    1993-01-01

    Auditing a gamma radiography program is required as part of the authorizing license. Checklists and cursory reviews are the typical approach to addressing program requirements. A more proactive approach is recommended. The audit program described was prepared for a specific set of operating conditions but can be applied to any given program. Improvements in the effectiveness of the radiography safety program can be made with additional examination and emphasis on direct observation of licensed activities

  9. 15. international conference on plant growth substances: Program -- Abstracts

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-12-31

    Since the 14th Conference in Amsterdam in 1991, progress in plant hormone research and developmental plant biology has been truly astonishing. The five ``classical`` plant hormones, auxin, gibberellin, cytokinin, ethylene, and abscisic acid, have been joined by a number of new signal molecules, e.g., systemin, jasmonic acid, salicylic acid, whose biosynthesis and functions are being understood in ever greater detail. Molecular genetics has opened new vistas in an understanding of transduction pathways that regulate developmental processes in response to hormonal and environmental signals. The program of the 15th Conference includes accounts of this progress and brings together scientists whose work focuses on physiological, biochemical, and chemical aspects of plant growth regulation. This volume contains the abstracts of papers presented at this conference.

  10. Detection of programmed cell death in plant embryos.

    Science.gov (United States)

    Filonova, Lada H; Suárez, María F; Bozhkov, Peter V

    2008-01-01

    Programmed cell death (PCD) is an integral part of embryogenesis. In plant embryos, PCD functions during terminal differentiation and elimination of the temporary organ, suspensor, as well as during establishment of provascular system. Embryo abortion is another example of embryonic PCD activated at pathological situations and in polyembryonic seeds. Recent studies identified the sequence of cytological events leading to cellular self-destruction in plant embryos. As in most if not all the developmental cell deaths in plants, embryonic PCD is hallmarked by autophagic degradation of the cytoplasm and nuclear disassembly that includes breakdown of the nuclear envelope and DNA fragmentation. The optimized setup of terminal deoxynucleotidyl transferase-mediated dUTP nick end labeling (TUNEL) allows the routine in situ analysis of nuclear DNA fragmentation in plant embryos. This chapter provides step-by-step procedure of how to process embryos for TUNEL and how to combine TUNEL with immunolocalization of the protein of interest.

  11. Oak Ridge Y-12 Plant groundwater protection program management plan

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-06-01

    The Oak Ridge Y- 1 2 Plant (Y-12 Plant) is owned by the United States Department of Energy (DOE) and managed by Lockheed Martin Energy Systems, Inc. (Energy Systems) under contract No. DE-AC05-84OR21400. The Y-12 Plant Groundwater Protection Program (GWPP), which was initiated in 1975, provides for the protection of groundwater resources consistent with Federal, State, and local regulations, and in accordance with DOE orders and Energy Systems policies and procedures. The Y-12 Plant is located in Anderson County, Tennessee, and is within the corporate limits of the City of Oak Ridge. The Y-12 Plant is one of three major DOE complexes that comprise the 37,000-acre Oak Ridge Reservation (ORR) located in Anderson and Roane counties. The Y-12 Plant is located in Bear Creek Valley at an elevation of about 950 feet (ft) above sea level. Bear Creek Valley is bounded on the northwest and southeast, and is isolated from populated areas of Oak Ridge, by parallel ridges that rise about 300 ft above the valley floor. The Y-12 Plant and its fenced buffer area are about 0.6 mile wide by 3.2 miles long and cover approximately 4,900 acres. The main industrialized section encompasses approximately 800 acres.

  12. Oak Ridge Y-12 Plant groundwater protection program management plan

    International Nuclear Information System (INIS)

    1996-06-01

    The Oak Ridge Y- 1 2 Plant (Y-12 Plant) is owned by the United States Department of Energy (DOE) and managed by Lockheed Martin Energy Systems, Inc. (Energy Systems) under contract No. DE-AC05-84OR21400. The Y-12 Plant Groundwater Protection Program (GWPP), which was initiated in 1975, provides for the protection of groundwater resources consistent with Federal, State, and local regulations, and in accordance with DOE orders and Energy Systems policies and procedures. The Y-12 Plant is located in Anderson County, Tennessee, and is within the corporate limits of the City of Oak Ridge. The Y-12 Plant is one of three major DOE complexes that comprise the 37,000-acre Oak Ridge Reservation (ORR) located in Anderson and Roane counties. The Y-12 Plant is located in Bear Creek Valley at an elevation of about 950 feet (ft) above sea level. Bear Creek Valley is bounded on the northwest and southeast, and is isolated from populated areas of Oak Ridge, by parallel ridges that rise about 300 ft above the valley floor. The Y-12 Plant and its fenced buffer area are about 0.6 mile wide by 3.2 miles long and cover approximately 4,900 acres. The main industrialized section encompasses approximately 800 acres

  13. Procedural and submittal guidance for the individual plant examination of external events (IPEEE) for severe accident vulnerabilities

    International Nuclear Information System (INIS)

    Chen, J.T.; Chokshi, N.C.; Kenneally, R.M.; Kelly, G.B.; Beckner, W.D.; McCracken, C.; Murphy, A.J.; Reiter, L.; Jeng, D.

    1991-06-01

    Based on a Policy statement on Severe Accidents, the licensee of each nuclear power plant is requested to perform an individual plant examination. The plant examination systematically looks for vulnerabilities to severe accidents and cost-effective safety improvements that reduce or eliminate the important vulnerabilities. This document presents guidance for performing and reporting the results of the individual plant examination of external events (IPEEE). The guidance for reporting the results of the individual plant examination of internal events (IPE) is presented in NUREG-1335. 53 refs., 1 figs., 2 tabs

  14. Examination of Energy Efficiency Increasing Measures in an Automobile Assembly Plant

    Directory of Open Access Journals (Sweden)

    Fatma ÇANKA KILIÇ

    2018-03-01

    Full Text Available In this study, energy consumption analysis was performed in a car assembly plant (Body-inWhite (BiW productions, painting processes, chassis and accessory assembly processes. Examined automobile assembly plant has a production capacity of 200,000 vehicles per year by working six days a week and three shifts a day. Highly energy consuming processes are determined. Energy efficiency increasing opportunities in energy consuming systems (paint shop, drying ovens, compressed air, heating and cooling systems and effects of current automotive assembly techniques on energy efficiency are examined. Most of the total energy in the studied plant is consumed in the paint shop. Considering annual energy consumption; paint shop is responsible for the %50 of total electrical energy and %70 of total natural gas consumption. Specific energy consumption of plant is calculated as 853 kWh (SET; 275 kWh for electricity consumption (SETe , and 578 kWh for natural gas (SETdg . By performing determined energy efficiency measures; SET of plant will reduce %1 for the SETe , and %5,7 for SETdg

  15. A Study of Automation for Examination Analysis of Inservice Inspection for Nuclear Power Plant (I)

    International Nuclear Information System (INIS)

    Kim, W.

    1985-01-01

    The developing country, KOREA where does not possess the natural resources for traditional energy such as oil and gas, so. The nuclear energy is the most single reliable source available for closing the energy gap. For these reason, It is inavoidable to construct the nuclear power plant and to develop technology related nuclear energy. The rate of operation in large nuclear power facilities depends upon the performance of work system through design and construction, and also the applied technology. Especially, it is the most important element that safety and reliability in operation of nuclear power plant. In view of this aspects, Nuclear power plant is performed severe examinations during perceives and inservice inspection. This study provide an automation of analysis for volumetric examination which is required to nuclear power plant components. It is composed as follows: I. Introduction II. Inservice Inspection of Nuclear Power Plant * General Requirement. * Principle and Methods of Ultrasonic Test. * Study of Flaw Evaluation and Design of Classifying Formula for Flaws. III. Design of Automation for Flaw Evaluation. IV. An Example V. Conclusion In this theory, It is classifying the flaws, the formula of classifying flaws and the design of automation that is the main important point. As motioned the above, Owing to such as automatic design, more time could be allocated to practical test than that of evaluation of defects, Protecting against subjective bias tester by himself and miscalculation by dint of various process of computation. For the more, adopting this method would be used to more retaining for many test data and comparative evaluating during successive inspection intervals. Inspire of limitation for testing method and required application to test components, it provide useful application to flow evaluation for volumetric examination. Owing to the characteristics of nuclear power plant that is highly skill intensive industry and has huge system, the

  16. 46 CFR 71.50-19 - The Alternative Hull Examination (AHE) Program application.

    Science.gov (United States)

    2010-10-01

    ... 46 Shipping 3 2010-10-01 2010-10-01 false The Alternative Hull Examination (AHE) Program...) PASSENGER VESSELS INSPECTION AND CERTIFICATION Drydocking § 71.50-19 The Alternative Hull Examination (AHE... apply to the AHE Program. You must submit an application at least 90 days before the requested hull...

  17. At What Cost? Examining the Cost Effectiveness of a Universal Social-Emotional Learning Program

    Science.gov (United States)

    Hunter, Leah J.; DiPerna, James C.; Hart, Susan Crandall; Crowley, Max

    2018-01-01

    Although implementation of universal social-emotional learning programs is becoming more common in schools, few studies have examined the cost-effectiveness of such programs. As such, the purpose of this article is two fold. First, we provide an overview of cost-effectiveness methods for school-based programs, and second, we share results of a…

  18. An Examination of Program Selection Criteria for Part-Time MBA Students

    Science.gov (United States)

    Colburn, Michael; Fox, Daniel E.; Westerfelt, Debra Kay

    2011-01-01

    Prospective graduate students select a graduate program as a result of a multifaceted decision-making process. This study examines the selection criteria that part-time MBA students used in selecting a program at a private university. Further, it analyzes the methods by which the students first learned of the MBA program. The authors posed the…

  19. Tecnomatix Plant Simulation modeling and programming by means of examples

    CERN Document Server

    Bangsow, Steffen

    2015-01-01

    This book systematically introduces the development of simulation models as well as the implementation and evaluation of simulation experiments with Tecnomatix Plant Simulation. It deals with all users of Plant Simulation, who have more complex tasks to handle. It also looks for an easy entry into the program. Particular attention has been paid to introduce the simulation flow language SimTalk and its use in various areas of the simulation. The author demonstrates with over 200 examples how to combine the blocks for simulation models and how to deal with SimTalk for complex control and analys

  20. Research and examinations at the Tono Mines. Fiscal year's programs (Heisei 12 fiscal year). Technical report

    International Nuclear Information System (INIS)

    2000-04-01

    This program showed details on the research and examination program of the Japan Nuclear Cycle Development Institute to be carried out at the Tono Mines in the Heisei 12 fiscal year, according to the 'Fundamental program on research and examinations at the Tono Mines' established on October, 1998. And, this program is carried out under an aim at understanding of transfer and delay performance of materials in deposit rocks with uranium and geological features such as fault, and at development of technology and apparatus for general investigation and evaluation of geological environment, as a stratum science research. Here were described on research and examination of mechanical stability on the rock board, research and examination of geological environment around a tunnel, research and examination of material transfer in the rock board, and research and examination of the Tsukiyoshi stratum abstractly before 1999 and in details at 2000 fiscal years. (G.K.)

  1. Genesis of the Brazilian nuclear power plants program

    International Nuclear Information System (INIS)

    Syllus, G.; Lepecki, W.

    1996-01-01

    The genesis of the Brazilian Nuclear Power Program is described by the authors - who participated in the events - from the beginning of the sixties, until the definition and the start of the implementation in 1975 of the Reference Nuclear Power Program. A description is made of the main events, studies and decisions that contributed to the evolution of the Program: the GTRP (Nuclear Power Plant Working Group); the Thorium Group; the Lane Group; the decision about Angra 1; CNEN's analyses about the reactor line and, finally, the creation of CBTN (Nuclear Technology Brazilian Company), which elaborated the studies that resulted in the final definition of the Program and led to the Brazilian German Agreement and the establishment of NUCLEBRAS. (author)

  2. IAEA team to report on Kashiwazaki Kariwa Nuclear Power Plant examination

    International Nuclear Information System (INIS)

    2007-01-01

    Full text: The Kashiwazaki Kariwa Nuclear Power Plant in Japan, affected by a strong earthquake on 16 July, shut down safely and damage appears less than expected, a fact finding mission of international nuclear safety experts has concluded. The six member expert team of the International Atomic Energy Agency was dispatched upon the request of the Japanese authorities. The mission report will be issued within a few days. The Director General of the IAEA, Mohamed ElBaradei, said today that he welcomed the cooperation and transparency the team had received from the Japanese authorities. The mission's findings and the Japanese analyses of the event include important lessons learned - both positive and negative - that will be relevant to other nuclear plants worldwide, he said. The team conducted a three day physical examination covering the complex of seven units, as well as analysis of instrument logs and other records from the time of the event. It has concluded that plant safety features performed as required during the earthquake. The team's review of plant operator records and analyses support the Japanese authorities' conclusion that the very small amount of radioactivity released was well below the authorized limits for public health and environmental safety. Damage from the earthquake appears to be limited to those sections of the plant that would not affect the reactor or systems related to reactor safety. Detailed checks and inspections by the operator and Japanese authorities are ongoing. According to the IAEA team, significant work, such as detailed examination of the reactor vessels, cores and fuel elements, has still to be performed. Physical stresses resulting from the earthquake could affect the long term safe operation of some plant components, the team said. Additional engineering analysis of such components would be an important consideration for future examination, to determine whether they should be replaced earlier than otherwise anticipated. The

  3. Status of the Monticello nuclear generating plant lead plant license renewal program

    International Nuclear Information System (INIS)

    Pickens, T.A.

    1992-01-01

    In 1988, the Monticello nuclear generating plant was chosen by the US Department of Energy through Sandia National Laboratories and the Electric Power Research Institute to serve as the lead boiling water reactor in the lead plant license renewal program. The purpose of the lead plant license renewal program is to provide insights during the development of and to demonstrate the license renewal regulatory process with the US Nuclear Regulatory Commission (NRC). The work being performed in three phases: (1) preparation of the technical basis for license renewal; (2) development of the technical basis into a formal license renewal application; and (3) review of the application by the NRC. This paper discusses the systems and structures identified as important to license renewal in accordance with 10CFR54 as well as the plant documents and programs that were used in going through the identification process. The systems and structures important to license renewal will then provide insights into how structures and components were identified that are required to be evaluated for aging, the elements of the aging evaluations, and the effective programs used to manage potentially significant aging

  4. Hanford Waste Vitrification Plant Project Waste Form Qualification Program Plan

    International Nuclear Information System (INIS)

    Randklev, E.H.

    1993-06-01

    The US Department of Energy has created a waste acceptance process to help guide the overall program for the disposal of high-level nuclear waste in a federal repository. This Waste Form Qualification Program Plan describes the hierarchy of strategies used by the Hanford Waste Vitrification Plant Project to satisfy the waste form qualification obligations of that waste acceptance process. A description of the functional relationship of the participants contributing to completing this objective is provided. The major activities, products, providers, and associated scheduling for implementing the strategies also are presented

  5. Perry Nuclear Power Plant Area/Equipment Temperature Monitoring Program

    International Nuclear Information System (INIS)

    McGuire, L.L.

    1991-01-01

    The Perry Nuclear Power Plant Area/Equipment Temperature Monitoring Program serves two purposes. The first is to track temperature trends during normal plant operation in areas where suspected deviations from established environmental profiles exist. This includes the use of Resistance Temperature Detectors, Recorders, and Temperature Dots for evaluation of equipment qualified life for comparison with tested parameters and the established Environmental Design Profile. It also may be used to determine the location and duration of steam leaks for effect on equipment qualified life. The second purpose of this program is to aid HVAC design engineers in determining the source of heat outside anticipated design parameters. Resistance Temperature Detectors, Recorders, and Temperature Dots are also used for this application but the results may include design changes to eliminate the excess heat or provide qualified equipment (cable) to withstand the elevated temperature, splitting of environmental zones to capture accurate temperature parameters, or continued environmental monitoring for evaluation of equipment located in hot spots

  6. Analysis of integrated plant upgrading/life extension programs

    International Nuclear Information System (INIS)

    McCutchan, D.A.; Massie, H.W. Jr.; McFetridge, R.H.

    1988-01-01

    A present-worth generating cost model has been developed and used to evaluate the economic value of integrated plant upgrading life extension project in nuclear power plants. This paper shows that integrated plant upgrading programs can be developed in which a mix of near-term availability, power rating, and heat rate improvements can be obtained in combination with life extension. All significant benefits and costs are evaluated from the viewpoint of the utility, as measured in discounted revenue requirement differentials between alternative plans which are equivalent in system generating capacity. The near-term upgrading benefits are shown to enhance the benefit picture substantially. In some cases the net benefit is positive, even if the actual life extension proves to be less than expected

  7. Development of a SPV management program for nuclear power plants

    International Nuclear Information System (INIS)

    Lee, Eun-Chan; Na, Jang-Hwan; Lee, Doo-Young; Oh, Seong-Jong; Jerng, Dong-Wook

    2009-01-01

    The Single Point Vulnerability (SPV) is a characteristic of a component whose failure results in plant transients. KHNP (Korea Hydro and Nuclear Power Co.) has evaluated major systems with critical components and developed a SPV management program to reduce the trip frequency and to raise plant's availability. This study includes a comprehensive methodology for SPV evaluation and its results. This methodology consists of the qualitative evaluation focused on the SPV component list preparation and the quantitative evaluation through FMEA (Failure Mode Effect Analyses) and FTA (Fault Tree Analyses) of critical systems. The qualitative evaluation reduced differences of the SPV lists between the identically designed plants and established strategies for the improvement of the SPV component reliability. The quantitative evaluation identified additional SPV components and developed the fault tree model for a Trip Monitor which showed logic relationships of channel components in the trip-related systems. (author)

  8. "PERLE bedside-examination-course for candidates in state examination" - Developing a training program for the third part of medical state examination (oral examination with practical skills).

    Science.gov (United States)

    Karthaus, Anne; Schmidt, Anita

    2016-01-01

    In preparation for the state examination, many students have open questions and a need for advice. Tutors of the Skills Lab PERLE-"Praxis ERfahren und Lernen" (experiencing and learning practical skills) have developed a new course concept to provide support and practical assistance for the examinees. The course aims to familiarize the students with the exam situation in order to gain more confidence. This enables the students to experience a confrontation with the specific situation of the exam in a protected environment. Furthermore, soft skills are utilized and trained. Concept of the course: The course was inspired by the OSCE-model (Objective Structured Clinical Examination), an example for case-based learning and controlling. Acquired knowledge can be revised and extended through the case studies. Experienced tutors provide assistance in discipline-specific competencies, and help in organizational issues such as dress code and behaviour. Evaluation of the course: An evaluation was conducted by the attending participants after every course. Based on this assessment, the course is constantly being developed. In March, April and October 2015 six courses, with a total of 84 participants, took place. Overall 76 completed questionnaires (91%) were analysed. Strengths of the course are a good tutor-participants-ratio with 1:4 (1 Tutor provides guidance for 4 participants), the interactivity of the course, and the high flexibility in responding to the group's needs. Weaknesses are the tight schedule, and the currently not yet performed evaluation before and after the course. In terms of "best practise", this article shows an example of how to offer low-cost and low-threshold preparation for the state examination.

  9. An analysis of the impacts of economic incentive programs on commercial nuclear power plant operations and maintenance costs

    International Nuclear Information System (INIS)

    Kavanaugh, D.C.; Monroe, W.H.; Wood, R.S.

    1996-02-01

    Operations and Maintenance (O and M) expenditures by nuclear power plant owner/operators possess a very logical and vital link in considerations relating to plant safety and reliability. Since the determinants of O and M outlays are considerable and varied, the potential linkages to plant safety, both directly and indirectly, can likewise be substantial. One significant issue before the US Nuclear Regulatory Commission is the impact, if any, on O and M spending from state programs that attempt to improve plant operating performance, and how and to what extent these programs may affect plant safety and pose public health risks. The purpose of this study is to examine the role and degree of impacts from state promulgated economic incentive programs (EIPs) on plant O and M spending. A multivariate regression framework is specified, and the model is estimated on industry data over a five-year period, 1986--1990. Explanatory variables for the O and M spending model include plant characteristics, regulatory effects, financial strength factors, replacement power costs, and the performance incentive programs. EIPs are found to have statistically significant effects on plant O and M outlays, albeit small in relation to other factors. Moreover, the results indicate that the relatively financially weaker firms are more sensitive in their O and M spending to the presence of such programs. Formulations for linking spending behavior and EIPs with plant safety performance remains for future analysis

  10. Post-irradiation examination and R and D programs using irradiated fuels at KAERI

    International Nuclear Information System (INIS)

    Chun, Yong Bum; Min, Duck Kee; Kim, Eun Ka and others

    2000-12-01

    This report describes the Post-Irradiation Examination(PIE) and R and D programs using irradiated fuels at KAERI. The objectives of post-irradiation examination (PIE) for the PWR irradiated fuels, CANDU fuels, HANARO fuels and test fuel materials are to verify the irradiation performance and their integrity as well as to construct a fuel performance data base. The comprehensive utilization program of the KAERI's post-irradiation examination related nuclear facilities such as Post-Irradiation Examination Facility (PIEF), Irradiated Materials Examination Facility (IMEF) and HANARO is described

  11. Post-irradiation examination and R and D programs using irradiated fuels at KAERI

    International Nuclear Information System (INIS)

    Chun, Yong Bum; So, Dong Sup; Lee, Byung Doo; Lee, Song Ho; Min, Duck Kee

    2001-09-01

    This report describes the Post-Irradiation Examination(PIE) and R and D programs using irradiated fuels at KAERI. The objectives of post-irradiation examination (PIE) for the PWR irradiated fuels, CANDU fuels, HANARO fuels and test fuel materials are to verify the irradiation performance and their integrity as well as to construct a fuel performance data base. The comprehensive utilization program of the KAERI's post-irradiation examination related nuclear facilities such as Post-Irradiation Examination Facility (PIEF), Irradiated Materials Examination Facility (IMEF) and HANARO is described

  12. Application of the comet assay in studies of programmed cell death (PCD in plants

    Directory of Open Access Journals (Sweden)

    Maria Charzyńska

    2014-01-01

    Full Text Available Programmed cell death (PCD in plants is an intensively investigated process. One of the main characteristics of PCD in both animal and plant organisms is the non-random, internucleosomal fragmentation of nuclear DNA, usually analysed using total DNA gel electrophoresis or TUNEL method. In this paper we present application of the "comet assay" (Single Cell Gel Electrophoresis for detection of nDNA degradation in studies of PCD during plant life cycle. We analyzed three types of tissue: anther tapetum, endosperm and mesophyll which were prepared in different ways to obtain a suspension of viable cells (without cell walls. The comet assay gives a possibility of examination of the nDNA degradation in individual cell. This method is significant for studies of the plant tissue differentiation and senescence especially in the cases when it is not possible to isolate large number of cells at the same developmental stage.

  13. 46 CFR 115.630 - The Alternative Hull Examination (AHE) Program application.

    Science.gov (United States)

    2010-10-01

    ... 46 Shipping 4 2010-10-01 2010-10-01 false The Alternative Hull Examination (AHE) Program... PASSENGERS INSPECTION AND CERTIFICATION Hull and Tailshaft Examinations § 115.630 The Alternative Hull... hull examination date to the Officer in Charge, Marine Inspection (OCMI) who will oversee the survey...

  14. Round Robin Test for Performance Demonstration System of Ultrasound Examination Personnel in Nuclear Power Plants

    International Nuclear Information System (INIS)

    Kim, Young Ho; Yang, Seung Han; Kim, Yong Sik; Yoon, Byung Sik; Lee, Hee Jong

    2005-01-01

    Ultrasound testing performance during in-service inspection for the main components of NPPs is strongly affected by each examination person. Therefore, ASME established a more strict qualification requirement in Sec. XI Appendix VIII for the ultrasound testing personnel in nuclear power plants. The Korean Performance Demonstration (KPD) System according to the ASME code for the ultrasonic testing personnel, equipments, and procedures to apply to the Class 1 and 2 piping ultrasound examination of nuclear power plants in Korea was established. And a round robin test was conducted in order to verify the effectiveness of PD method by comparing the examination results from the method of Performance Demonstration (PD) and a traditional ASME code dB-drop method. The round robin test shows that the reliability of the PD method is better than that of the dB-drop method. As a result, application of the PD method to the in-service inspection of the nuclear power plants will improve the performance of ultrasound testing

  15. Exploratory study of the radiation-protection training programs in nuclear power plants

    International Nuclear Information System (INIS)

    Fields, C.D.

    1982-06-01

    The objective of the study was to examine current radiation training programs at a sample of utilities operating nuclear reactors and to evaluate employee information on radiation health. The study addressed three elements: (1) employee perceptions and understanding of ionizing radiation; (2) utility trainers-their background, training, and problems; (3) the content, materials, and conduct of training programs; (4) program uniformity and completeness. These areas were examined through visits to utilities, surveys, and employee interviews. The programs reviewed were developed by utility personnel who have backgrounds, for the most part, in health physics but who may have little formal training in adult education. This orientation, coupled with the inherent nature of the subject, has produced training programs that appear to be too technical to achieve the educational job intended. The average nuclear power plant worker does not have the level of sophistication needed to understand some of the information. It became apparent that nuclear power plant workers have concerns that do not necessarily reflect those of the scientific community. Many of these result from misunderstandings about radiation. Unfortunately, the training programs do not always address these unfounded but very real fears

  16. The integrated in situ testing program for the Waste Isolation Pilot Plant (WIPP)

    International Nuclear Information System (INIS)

    Matalucci, R.V.

    1987-03-01

    The US Department of Energy (DOE) is developing the Waste Isolation Pilot Plant (WIPP) Project in southeastern New Mexico as a research and development (R and D) facility for examining the response of bedded (layered) salt to the emplacement of radioactive wastes generated from defense programs. The WIPP Experimental Program consists of a technology development program, including laboratory testing and theoretical analysis activities, and an in situ testing program that is being done 659 m underground at the project site. This experimental program addresses three major technical areas that concern (1) thermal/structural interactions, (2) plugging and sealing, and (3) waste package performance. To ensure that the technical issues involved in these areas are investigated with appropriate emphasis and timing, an in situ testing plan was developed to integrate the many activities and tasks associated with the technical issues of waste disposal. 5 refs., 4 figs

  17. Relationship Between Physician Assistant Program Length and Physician Assistant National Certifying Examination Pass Rates.

    Science.gov (United States)

    Colletti, Thomas P; Salisbury, Helen; Hertelendy, Attila J; Tseng, Tina

    2016-03-01

    This study was conducted to examine the relationship between physician assistant (PA) educational program length and PA programs' 5-year average Physician Assistant National Certifying Examination (PANCE) first-time pass rates. This was a retrospective correlational study that analyzed previously collected data from a nonprobability purposive sample of accredited PA program Web sites. Master's level PA programs (n = 108) in the United States with published average PANCE scores for 5 consecutive classes were included. Provisional and probationary programs were excluded (n = 4). Study data were not normally distributed per the Kolmogorov-Smirnov test, P = .00. There was no relationship between program length and PANCE pass rates, ρ (108) = -0.04, P = .68. Further analyses examining a possible relationship between program phase length (didactic and clinical) and PANCE pass rates also demonstrated no differences (ρ [107] = -0.05, P = .60 and ρ [107] = 0.02, P = .80, respectively). The results of this study suggest that shorter length PA programs perform similarly to longer programs in preparing students to pass the PANCE. In light of rapid expansion of PA educational programs, educators may want to consider these findings when planning the length of study for new and established programs.

  18. Optimizing Violence Prevention Programs: An Examination of Program Effectiveness among Urban High School Students

    Science.gov (United States)

    Thompkins, Amanda C.; Chauveron, Lisa M.; Harel, Ofer; Perkins, Daniel F.

    2014-01-01

    Background: While demand for youth violence prevention programs increases, the ability of the school-day schedule to accommodate their time requirements has diminished. Viable school-based prevention programs must strike a balance between brevity and effectiveness. This article reports results from an effectiveness trial of a 12-session…

  19. Evaluation of Haddam Neck (Connecticut Yankee) Nuclear Power Plant, environmental impact prediction, based on monitoring programs

    International Nuclear Information System (INIS)

    Gore, K.L.; Thomas, J.M.; Kannberg, L.D.; Mahaffey, J.A.; Waton, D.G.

    1976-12-01

    A study was undertaken by the U.S. Nuclear Regulatory Commission (NRC) to evaluate the nonradiological environmental data obtained from three nuclear power plants operating for a period of one year or longer. The document presented reports the second of three nuclear power plants to be evaluated in detail by Battelle, Pacific Northwest Laboratories. Haddam Neck (Connecticut Yankee) Nuclear Power Plant nonradiological monitoring data were assessed to determine their effectiveness in the measurement of environmental impacts. Efforts were made to determine if: (1) monitoring programs, as designed, can detect environmental impacts, (2) appropriate statistical analyses were performed and if they were sensitive enough to detect impacts, (3) predicted impacts could be verified by monitoring programs, and (4) monitoring programs satisfied the requirements of the Environmental Technical Specifications. Both preoperational and operational monitoring data were examined to test the usefulness of baseline information in evaluating impacts. This included an examination of the methods used to measure ecological, chemical, and physical parameters, and an assessment of sampling periodicity and sensitivity where appropriate data sets were available. From this type of analysis, deficiencies in both preoperational and operational monitoring programs may be identified and provide a basis for suggested improvement

  20. Savannah River Plant Separations Department mixed waste program

    International Nuclear Information System (INIS)

    Wierzbicki, W.M.

    1988-01-01

    The Department of Energy's (DOE) Savannah River Plant (SRP) generates radioactive and mixed waste as a result of the manufacture of nuclear material for the national defense program. The radioactive portion of the mixed waste and all nonhazardous radioactive wastes would continue to be regulated by DOE under the Atomic Energy Act. The Separations Department is the largest generator of solid radioactive waste at the Savannah River Plant. Over the last three years, the Separations Department has developed and implemented a program to characterize candidate mixed-waste streams. The program consisted of facility personnel interviews, a waste-generation characterization program and waste testing to determine whether a particular waste form was hazardous. The Separations Department changed waste-handling practices and procedures to meet the requirements of the generator standards. For each Separation Department Facility, staging areas were established, inventory and reporting requirements were developed, operating procedures were revised to ensure proper waste handling, and personnel were provided hazardous waste training. To emphasize the importance of the new requirements, a newsletter was developed and issued to all Separations supervisory personnel

  1. Examining strategies to facilitate vitamin B1 biofortification of plants by genetic engineering

    Directory of Open Access Journals (Sweden)

    Lucille ePourcel

    2013-05-01

    Full Text Available Thiamin (vitamin B1 is made by plants and microorganisms but is an essential micronutrient in the human diet. All organisms require it as a cofactor in its form as thiamin pyrophosphate (TPP for the activity of key enzymes of central metabolism. In humans, deficiency is widespread particularly in populations where polished rice is a major component of the diet. Considerable progress has been made on the elucidation of the biosynthesis pathway within the last few years enabling concrete strategies for biofortification purposes to be devised, with a particular focus here on genetic engineering. Furthermore, the vitamin has been shown to play a role in both abiotic and biotic stress responses. The precursors for de novo biosynthesis of thiamin differ between microorganisms and plants. Bacteria use intermediates derived from purine and isoprenoid biosynthesis, whereas the pathway in yeast involves the use of compounds from the vitamin B3 and B6 groups. Plants on the other hand use a combination of the bacterial and yeast pathways and there is subcellular partitioning of the biosynthesis steps. Specifically, thiamin biosynthesis occurs in the chloroplast of plants through the separate formation of the pyrimidine and thiazole moieties, which are then coupled to form thiamin monophosphate (TMP. Phosphorylation of thiamin to form TPP occurs in the cytosol. Therefore, thiamin (or TMP must be exported from the chloroplast to the cytosol for the latter step to be executed. The regulation of biosynthesis is mediated through riboswitches, where binding of the product TPP to the pre-mRNA of a biosynthetic gene modulates expression. Here we examine and hypothesize on genetic engineering approaches attempting to increase the thiamin content employing knowledge gained with the model plant Arabidopsis thaliana. We will discuss the regulatory steps that need to be taken into consideration and can be used a prerequisite for devising such strategies in crop plants.

  2. CHIT: a cost accounting program for postirradiation examinations of fast breeder reactor materials

    International Nuclear Information System (INIS)

    Phillips, J.R.; Dowler, K.E.

    1975-09-01

    CHIT is the Los Alamos Scientific Laboratory's cost accounting computer program for nondestructive and destructive examinations of irradiated fuel pins. The program allows immediate retrieval of fuel pin examination information and provides itemized listings for completed and projected fuel pin examinations, detailed cost accounting summaries for each investigator, fuel pin examinations during a specified time interval, and various subsets of the information. CHIT has been in successful operation for the past two years, providing precise information on cost accounting more efficiently than possible with a manual technique

  3. ERDA LWR plant technology program: role of government/industry in improving LWR performance

    International Nuclear Information System (INIS)

    1975-01-01

    Information is presented under the following chapter headings: executive summary; LWR plant outages; LWR plant construction delays and cancellations; programs addressing plant outages, construction delays, and cancellations; need for additional programs to remedy continuing problems; criteria for government role in LWR commercialization; and the proposed government program

  4. Application of plant life management program and experience at NRU

    International Nuclear Information System (INIS)

    Nickerson, J.; Dam, R.; Arnold, J.; See Hoye, D.

    2004-01-01

    The National Research Universal (NRU) reactor has seen extensive and excellent service since going into operation in 1957. During that time, significant investments in upgrading and improving the facility have been implemented. Recently, as part of the NRU Licenseability Extension (LE) program, AECL has developed a Plant Life Management (PLiM) program to support planned operation to at least 2012. The objective of the PLiM program is to systematically assess the various aging related degradation mechanisms in order to evaluate both current condition and the potential for further extending service life. Another objective is to identify the associated maintenance, surveillance and inspection strategy for service life extension of important Structures, Systems, and Components (SSCs). The strategy uses approaches that build on AECL's PLiM/PLEx experience at CANDU plants, but also utilizes previous Age Management and refurbishment work performed at NRU. The program is multi-faceted, systematic and integrated, and involves the facility operations organization in the assessment process. The PLiM program has used a number of pilot studies in the initial stages to test out PLiM procedures, gain experience with the various aging assessment techniques and enhance effectiveness of interfaces between the aging assessment team and the facility staff. The aging assessment process begins with the screening and prioritization of the facility SSCs. Selection of the appropriate assessment technique is based on priority and component type. Life and condition assessment techniques used at other plants have been adapted to NRU and performed on important components and structures. For important systems, a combination of condition assessment and systematic maintenance assessment techniques are being used. Detailed PLiM procedures have been developed and are in trial use in pilot studies. These procedures are currently being updated with the experience gained during the pilot studies. In

  5. A Qualitative Approach to Examining Knowledge Sharing in Iran Tax Administration Reform Program

    Directory of Open Access Journals (Sweden)

    Mehdi Shami Zanjanie

    2012-02-01

    Full Text Available The paper aims to examine knowledge sharing infrastructure of "Iran Tax Administration Reform Program". The qualitative approach by using case study method was applied in this research. In order to meet the research goal, four infrastructural dimensions of knowledge sharing were studied: leadership & strategy, culture, structure, and information technology. To the authors’ knowledge, this was maybe the first paper which examined knowledge sharing infrastructure in programs environment

  6. 46 CFR 71.50-31 - Continued participation in the Alternative Hull Examination (AHE) program.

    Science.gov (United States)

    2010-10-01

    ... 46 Shipping 3 2010-10-01 2010-10-01 false Continued participation in the Alternative Hull... the Alternative Hull Examination (AHE) program. (a) To continue to participate in the AHE Program, vessel operators must conduct an annual hull condition assessment. At a minimum, vessel operators must...

  7. Teaming up for Literacy: Examining Participants' Contributions to a Collaborative Family-Based Program

    Science.gov (United States)

    Kumar, Tracey

    2016-01-01

    This study of participants' contributions to a university-based family literacy program was informed by both "funds of knowledge" (Moll, 1992) and "multiple literacies" (Auerbach, 1995). The study examined participants' contributions to the design, implementation, and evaluation of a university-based family literacy program. In…

  8. Next Generation Nuclear Plant Materials Research and Development Program Plan

    International Nuclear Information System (INIS)

    G.O. Hayner; R.L. Bratton; R.N. Wright

    2005-01-01

    The U.S Department of Energy (DOE) has selected the Very High Temperature Reactor (VHTR) design for the Next Generation Nuclear Plant (NGNP) Project. The NGNP will demonstrate the use of nuclear power for electricity and hydrogen production without greenhouse gas emissions. The reactor design will be a graphite moderated, helium-cooled, prismatic or pebble-bed, thermal neutron spectrum reactor that will produce electricity and hydrogen in a state-of-the-art thermodynamically efficient manner. The NGNP will use very high burn-up, low-enriched uranium, TRISO-coated fuel and have a projected plant design service life of 60 years. The VHTR concept is considered to be the nearest-term reactor design that has the capability to efficiently produce hydrogen. The plant size, reactor thermal power, and core configuration will ensure passive decay heat removal without fuel damage or radioactive material releases during accidents. The NGNP Project is envisioned to demonstrate the following: (1) A full-scale prototype VHTR by about 2021; (2) High-temperature Brayton Cycle electric power production at full scale with a focus on economic performance; (3) Nuclear-assisted production of hydrogen (with about 10% of the heat) with a focus on economic performance; and (4) By test, the exceptional safety capabilities of the advanced gas-cooled reactors. Further, the NGNP program will: (1) Obtain a Nuclear Regulatory Commission (NRC) License to construct and operate the NGNP, this process will provide a basis for future performance based, risk-informed licensing; and (2) Support the development, testing, and prototyping of hydrogen infrastructures. The NGNP Materials Research and Development (R and D) Program is responsible for performing R and D on likely NGNP materials in support of the NGNP design, licensing, and construction activities. The NGNP Materials R and D Program includes the following elements: (1) Developing a specific approach, program plan and other project management

  9. Next Generation Nuclear Plant Materials Research and Development Program Plan

    Energy Technology Data Exchange (ETDEWEB)

    G.O. Hayner; R.L. Bratton; R.N. Wright

    2005-09-01

    The U.S Department of Energy (DOE) has selected the Very High Temperature Reactor (VHTR) design for the Next Generation Nuclear Plant (NGNP) Project. The NGNP will demonstrate the use of nuclear power for electricity and hydrogen production without greenhouse gas emissions. The reactor design will be a graphite moderated, helium-cooled, prismatic or pebble-bed, thermal neutron spectrum reactor that will produce electricity and hydrogen in a state-of-the-art thermodynamically efficient manner. The NGNP will use very high burn-up, low-enriched uranium, TRISO-coated fuel and have a projected plant design service life of 60 years. The VHTR concept is considered to be the nearest-term reactor design that has the capability to efficiently produce hydrogen. The plant size, reactor thermal power, and core configuration will ensure passive decay heat removal without fuel damage or radioactive material releases during accidents. The NGNP Project is envisioned to demonstrate the following: (1) A full-scale prototype VHTR by about 2021; (2) High-temperature Brayton Cycle electric power production at full scale with a focus on economic performance; (3) Nuclear-assisted production of hydrogen (with about 10% of the heat) with a focus on economic performance; and (4) By test, the exceptional safety capabilities of the advanced gas-cooled reactors. Further, the NGNP program will: (1) Obtain a Nuclear Regulatory Commission (NRC) License to construct and operate the NGNP, this process will provide a basis for future performance based, risk-informed licensing; and (2) Support the development, testing, and prototyping of hydrogen infrastructures. The NGNP Materials Research and Development (R&D) Program is responsible for performing R&D on likely NGNP materials in support of the NGNP design, licensing, and construction activities. The NGNP Materials R&D Program includes the following elements: (1) Developing a specific approach, program plan and other project management tools for

  10. Audit program for physical security systems at nuclear power plants

    International Nuclear Information System (INIS)

    Minichino, C.

    1982-01-01

    Licensees of nuclear power plants conduct audits of their physical security systems to meet the requirements of 10 CFR 73, Physical Protection of Plants and Materials. Section 73.55, Requirements for physical Protection of Licensed Activities in Nuclear Power Reactors Against Radiological Sabotage, requires that the security programs be reviewed at least every 12 months, that the audit be conducted by individuals independent of both security management and security supervision, and that the audit program review all aspects of the physical security system: hardware, personnel, and operational and maintenance procedures. This report contains information for the Nuclear Regulatory Commission (NRC) and for the licensees of nuclear power reactors who carry out these comprehensive audits. Guidance on the overall management of the audit function includes organizational structure and issues concerning the auditors who perform the review: qualifications, independence, due professional care, and standards. Guidance in the audit program includes purpose and scope of the audit, planning, techniques, post-audit procedures, reporting, and follow-up

  11. Air sampling program at the Portsmouth Gaseous Diffusion Plant

    International Nuclear Information System (INIS)

    Hulett, S.H.

    1975-01-01

    An extensive air sampling program has been developed at the Portsmouth Gaseous Diffusion Plant for monitoring the concentrations of radioactive aerosols present in the atmosphere on plantsite as well as in the environs. The program is designed to minimize exposures of employees and the environment to airborne radioactive particulates. Five different air sampling systems, utilizing either filtration or impaction, are employed for measuring airborne alpha and beta-gamma activity produced from 235 U and 234 Th, respectively. Two of the systems have particle selection capabilities: a personal sampler with a 10-mm nylon cyclone eliminates most particles larger than about 10 microns in diameter; and an Annular Kinetic Impactor collects particulates greater than 0.4 microns in diameter which have a density greater than 12-15 gm/cm 3 . A Hi-Volume Air Sampler and an Eberline Model AIM-3 Scintillation Air Monitor are used in collecting short-term samples for assessing compliance with ''ceiling'' standards or peak concentration limits. A film-sort aperture IBM card system is utilized for continuous 8-hour samples. This sampling program has proven to be both practical and effective for assuring accurate monitoring of the airborne activity associated with plant operations

  12. Utilization of aging program results in plant inspections

    International Nuclear Information System (INIS)

    Gunther, W.; Fullwood, R.

    1989-01-01

    Research conducted under the auspices of the US Nuclear Regulatory Commission Nuclear Plant Aging Research (NPAR) Program has resulted in a large data base of component and system operating experience. This data base has been used to determine equipment aging susceptibility and the potential for equipment aging to impact plant safety and reliability. Methods of detecting and mitigating component and system aging have also been identified. This paper discusses how the NPAR results could be used to focus inspection activities on age-sensitive components and systems and on the specific modes and mechanisms of age degradation. These activities range from the regular inspections conducted by resident inspectors to extensive special inspections such as the Safety System Functional Inspection typically conducted by a team of inspectors. 5 refs., 3 figs., 1 tab

  13. Only in dying, life: programmed cell death during plant development.

    Science.gov (United States)

    Van Hautegem, Tom; Waters, Andrew J; Goodrich, Justin; Nowack, Moritz K

    2015-02-01

    Programmed cell death (PCD) is a fundamental process of life. During the evolution of multicellular organisms, the actively controlled demise of cells has been recruited to fulfil a multitude of functions in development, differentiation, tissue homeostasis, and immune systems. In this review we discuss some of the multiple cases of PCD that occur as integral parts of plant development in a remarkable variety of cell types, tissues, and organs. Although research in the last decade has discovered a number of PCD regulators, mediators, and executers, we are still only beginning to understand the mechanistic complexity that tightly controls preparation, initiation, and execution of PCD as a process that is indispensable for successful vegetative and reproductive development of plants. Copyright © 2014 Elsevier Ltd. All rights reserved.

  14. Utilization of aging program results in plant inspections

    International Nuclear Information System (INIS)

    Gunther, W.; Fullwood, R.

    1988-01-01

    Research conducted under the auspices of the US Nuclear Regulatory Commission Nuclear Plant Aging Research (NPAR) Program has resulted in a large data base of component and system operating experience. This data base has been used to determine equipment aging susceptibility and the potential for equipment aging to impact plant safety and reliability. Methods of detecting and mitigating component and system aging have also been identified. This paper discusses how the NPAR results could be used to focus inspection activities on age-sensitive components and systems and on the specific modes and mechanisms of age degradation. These activities range from the regular inspections conducted by resident inspectors to extensive special inspections such as the Safety System Functional Inspection typically conducted by a team of inspectors. 5 refs., 3 figs., 1 tab

  15. A lifecycle management program for NPP turbine balance of plant

    International Nuclear Information System (INIS)

    Manabe, Jun; Yamakami, Katsuhiko; Hiraoka, Satoshi; Kawai, Toshinari

    2009-01-01

    A lifecycle management program, for turbine balance of plant of light water reactor units which had been operated for more than 20 years but still having a long intended residual life time, was proposed and implemented from the view point of system and equipment supplier. Here would be introduced the program executed for several utilities. The program consists of unit surveillance analyzing both operation and inspection data, degradation assessment for the equipment and prospecting for the future by planning the proper measures for the issues based on both technology and economy. The program is introduced exampling the generating power affected by main steam pressure reduction derived from the scale adhesion and degradation of equipment. Multidisciplinary optimum design for the replacement of the feedwater heaters, one of the items of the planning, is introduced. Additionally would be introduced the new concept maintenance support program, mainly applied to the units already replaced their principal machines and auxiliaries, configured with both the condition based maintenance system monitoring the trend of parameters of a component and the diagnosis of malfunctions ascertaining the equipment by analyzing and synthesizing operation parameters. (author)

  16. TMI-2 accident evaluation program sample acquisition and examination plan. Executive summary

    International Nuclear Information System (INIS)

    Russell, M.L.; McCardell, R.K.; Broughton, J.M.

    1985-12-01

    The purpose of the TMI-2 Accident Evaluation Program Sample Acquisition and Examination (TMI-2 AEP SA and E) program is to develop and implement a test and inspection plan that completes the current-condition characterization of (a) the TMI-2 equipment that may have been damaged by the core damage events and (b) the TMI-2 core fission product inventory. The characterization program includes both sample acquisitions and examinations and in-situ measurements. Fission product characterization involves locating the fission products as well as determining their chemical form and determining material association

  17. Determination of commercially valuable characteristics of plant varieties for energetic use during the state examination

    Directory of Open Access Journals (Sweden)

    В. В. Баликіна

    2014-12-01

    Full Text Available The analysis of commercially valuable indices of plant varieties for energetic use was carried out and the necessity to determine energetic indices during the state scientific-and-technical examination is substantiated. In order to explain the requirements for registration of new varieties of energy crops concerning the defi nition of indices of ability for distribution, the collection of species and hybrid forms of willow was used. Factors that prove the economic and environmental advantages of energy willow cultivation for biofuel are specifi ed.

  18. 46 CFR 115.660 - Continued participation in the Alternative Hull Examination (AHE) Program.

    Science.gov (United States)

    2010-10-01

    ... 46 Shipping 4 2010-10-01 2010-10-01 false Continued participation in the Alternative Hull... MORE THAN 49 PASSENGERS INSPECTION AND CERTIFICATION Hull and Tailshaft Examinations § 115.660 Continued participation in the Alternative Hull Examination (AHE) Program. (a) To continue to participate in...

  19. 46 CFR 176.660 - Continued participation in the Alternative Hull Examination (AHE) Program.

    Science.gov (United States)

    2010-10-01

    ... 46 Shipping 7 2010-10-01 2010-10-01 false Continued participation in the Alternative Hull... (CONTINUED) SMALL PASSENGER VESSELS (UNDER 100 GROSS TONS) INSPECTION AND CERTIFICATION Hull and Tailshaft Examinations § 176.660 Continued participation in the Alternative Hull Examination (AHE) Program. (a) To...

  20. Examining the Influence of Campus Leadership Programs at a Catholic University

    Science.gov (United States)

    Whitney, Rich; Meents-DeCaigny, Ellen

    2014-01-01

    This study uses the socially responsible leadership and leadership efficacy scales in the Multi-Institutional Study of Leadership (MSL) to examine leadership programs at one Catholic campus, and their influence on socially responsible leadership and leadership efficacy. Examining students that identified as involved in 14 campus leadership…

  1. Unique programming: an examination of the benefits of a free choice program

    Science.gov (United States)

    Dorothy L. Schmalz; Deborah L. Kerstetter; Harry C. Zinn

    2002-01-01

    This study was an investigation of a free choice program and the benefits free choice yields on the developing characteristics of self-esteem and intrinsic motivation among adolescent girls. Both quantitative and qualitative data were collected at Brown Ledge Camp, an all girls summer camp outside of Burlington, Vermont, during the summer of 2000. Quantitative results...

  2. Severe accident management program at Cofrentes Nuclear Power Plant

    International Nuclear Information System (INIS)

    Borondo, L.; Serrano, C.; Fiol, M.J.; Sanchez, A.

    2000-01-01

    Cofrentes Nuclear Power Plant (GE BWR/6) has implemented its specific Severe Accident Management Program within this year 2000. New organization and guides have been developed to successfully undertake the management of a severe accident. In particular, the Technical Support Center will count on a new ''Severe Accident Management Team'' (SAMT) which will be in charge of the Severe Accident Guides (SAG) when Control Room Crew reaches the Emergency Operation Procedures (EOP) step that requires containment flooding. Specific tools and training have also been developed to help the SAMT to mitigate the accident. (author)

  3. The Savannah River Plant low-level waste segregation program

    International Nuclear Information System (INIS)

    Wheeler, V.B.

    1987-01-01

    To extend the life of the Savannah River Plant (SRP) Radioactive Waste Burial Ground, a sitewide program has been implemented to segregate waste that is essentially free of contamination from routine radioactive waste. Much of the low-level waste disposed of as radioactive has no detectable contamination and can be buried in a sanitary landfill. A Landfill Monitoring Facility (LMF) will be constructed at SRP to house the state-of-the-art technology required to provide a final survey on the candidate waste streams that had previously been classified as radioactive. 3 figs

  4. The waste isolation pilot plant regulatory compliance program

    International Nuclear Information System (INIS)

    Mewhinney, J.A.; Kehrman, R.F.

    1996-01-01

    The passage of the WIPP Land Withdrawal Act of 1992 (LWA) marked a turning point for the Waste Isolation Pilot Plant (WIPP) program. It established a Congressional mandate to open the WIPP in as short a time as possible, thereby initiating the process of addressing this nation's transuranic (TRU) waste problem. The DOE responded to the LWA by shifting the priority at the WIPP from scientific investigations to regulatory compliance and the completion of prerequisites for the initiation of operations. Regulatory compliance activities have taken four main focuses: (1) preparing regulatory submittals; (2) aggressive schedules; (3) regulator interface; and (4) public interactions

  5. Final examination of trainees for nuclear power plant operators at an education and training centre

    International Nuclear Information System (INIS)

    Gieci, A.

    1986-01-01

    General and specialized theoretical training, on-the-job training in the training power plant and simulator training is followed by a final examination. The examination which is obligatory for all trainees is conceived according to Hick's law which requires linear dependence between the time which the operator needs for taking a decision on how to cope with a certain situation and the measure of entropy of the situation. Research in the field of man-machine relations has helped clarify the thinking of the operator who on the basis of received signals forms what is termed the conceptual model of the situation. The final examination should assess the trainee's ability to form conceptual models - the examination must therefore be something more than just a test of knowledge. The given questions and required answers must create a stress situation for the examinee such that the measure to which he is able to cope is conditioned by his ability to form conceptual models. The statutes of the final examinations were drawn up with the aim of achieving standardization and reproducibility. Questions are put through a special form (a model form is also given). (A.K.)

  6. Waste Isolation Pilot Plant Groundwater Protection Management Program Plan

    Energy Technology Data Exchange (ETDEWEB)

    Washington TRU Solutions

    2002-09-24

    U.S. Department of Energy (DOE) Order 5400.1, General Environmental Protection Program, requires each DOE site to prepare a Groundwater Protection Management Program Plan. This document fulfills the requirement for the Waste Isolation Pilot Plant (WIPP). This document was prepared by the Hydrology Section of the Westinghouse TRU Solutions LLC (WTS) Environmental Compliance Department, and it is the responsibility of this group to review the plan annually and update it every three years. This document is not, nor is it intended to be, an implementing document that sets forth specific details on carrying out field projects or operational policy. Rather, it is intended to give the reader insight to the groundwater protection philosophy at WIPP.

  7. Interdisciplinary Research and Training Program in the Plant Sciences

    Energy Technology Data Exchange (ETDEWEB)

    Wolk, C.P.

    1992-01-01

    Research on plants continued. Topics include: Molecular basis of symbiotic plant-microbe interations; enzymatic mechanisms and regulation of plant cell wall biosynthesis; molecular mechanisms that regulate the expression of genes in plants; resistance of plants to environmental stress; studies on hormone biosynthesis and action; plant cell wall proteins; interaction of nuclear and organelle genomes; sensor transduction in plants; molecular mechanisms of trafficking in the plant cell; regulation of lipid metabolism; molecular bases of plant disease resistance mechanisms; biochemical and molecular aspects of plant pathogenesis; developmental biology of nitrogen-fixing cyanobacteria; environmental control of plant development and its relation to plant hormones.

  8. Integrated plant safety assessment: systematic evaluation program. Haddam Neck Plant, Connecticut Yankee Atomic Power Company. Docket No. 50-213

    International Nuclear Information System (INIS)

    1983-03-01

    The Systematic Evaluation Program was initiated in February 1977 by the US Nuclear Regulatory Commission to review the designs of older operating nuclear reactor plants to confirm and document their safety. The review provides: (1) an assessment of how these plants compare with current licensing safety requirements relating to selected issues, (2) a basis for deciding on how these differences should be resolved in an integrated plant review, and (3) a documented evaluation of plant safety. This report documents the review of Haddam Neck Plant, operated by Connecticut Yankee Atomic Power Company. The Haddam Neck Plant is one of 10 plants reviewed under Phase II of this program. This report indicates how 137 topics selected for review under Phase I of the program were addressed. Equipment and procedural changes have been identified as a result of the review

  9. Next Generation Nuclear Plant Methods Technical Program Plan

    Energy Technology Data Exchange (ETDEWEB)

    Richard R. Schultz; Abderrafi M. Ougouag; David W. Nigg; Hans D. Gougar; Richard W. Johnson; William K. Terry; Chang H. Oh; Donald W. McEligot; Gary W. Johnsen; Glenn E. McCreery; Woo Y. Yoon; James W. Sterbentz; J. Steve Herring; Temitope A. Taiwo; Thomas Y. C. Wei; William D. Pointer; Won S. Yang; Michael T. Farmer; Hussein S. Khalil; Madeline A. Feltus

    2010-12-01

    One of the great challenges of designing and licensing the Very High Temperature Reactor (VHTR) is to confirm that the intended VHTR analysis tools can be used confidently to make decisions and to assure all that the reactor systems are safe and meet the performance objectives of the Generation IV Program. The research and development (R&D) projects defined in the Next Generation Nuclear Plant (NGNP) Design Methods Development and Validation Program will ensure that the tools used to perform the required calculations and analyses can be trusted. The Methods R&D tasks are designed to ensure that the calculational envelope of the tools used to analyze the VHTR reactor systems encompasses, or is larger than, the operational and transient envelope of the VHTR itself. The Methods R&D focuses on the development of tools to assess the neutronic and thermal fluid behavior of the plant. The fuel behavior and fission product transport models are discussed in the Advanced Gas Reactor (AGR) program plan. Various stress analysis and mechanical design tools will also need to be developed and validated and will ultimately also be included in the Methods R&D Program Plan. The calculational envelope of the neutronics and thermal-fluids software tools intended to be used on the NGNP is defined by the scenarios and phenomena that these tools can calculate with confidence. The software tools can only be used confidently when the results they produce have been shown to be in reasonable agreement with first-principle results, thought-problems, and data that describe the “highly ranked” phenomena inherent in all operational conditions and important accident scenarios for the VHTR.

  10. Next Generation Nuclear Plant Methods Technical Program Plan -- PLN-2498

    Energy Technology Data Exchange (ETDEWEB)

    Richard R. Schultz; Abderrafi M. Ougouag; David W. Nigg; Hans D. Gougar; Richard W. Johnson; William K. Terry; Chang H. Oh; Donald W. McEligot; Gary W. Johnsen; Glenn E. McCreery; Woo Y. Yoon; James W. Sterbentz; J. Steve Herring; Temitope A. Taiwo; Thomas Y. C. Wei; William D. Pointer; Won S. Yang; Michael T. Farmer; Hussein S. Khalil; Madeline A. Feltus

    2010-09-01

    One of the great challenges of designing and licensing the Very High Temperature Reactor (VHTR) is to confirm that the intended VHTR analysis tools can be used confidently to make decisions and to assure all that the reactor systems are safe and meet the performance objectives of the Generation IV Program. The research and development (R&D) projects defined in the Next Generation Nuclear Plant (NGNP) Design Methods Development and Validation Program will ensure that the tools used to perform the required calculations and analyses can be trusted. The Methods R&D tasks are designed to ensure that the calculational envelope of the tools used to analyze the VHTR reactor systems encompasses, or is larger than, the operational and transient envelope of the VHTR itself. The Methods R&D focuses on the development of tools to assess the neutronic and thermal fluid behavior of the plant. The fuel behavior and fission product transport models are discussed in the Advanced Gas Reactor (AGR) program plan. Various stress analysis and mechanical design tools will also need to be developed and validated and will ultimately also be included in the Methods R&D Program Plan. The calculational envelope of the neutronics and thermal-fluids software tools intended to be used on the NGNP is defined by the scenarios and phenomena that these tools can calculate with confidence. The software tools can only be used confidently when the results they produce have been shown to be in reasonable agreement with first-principle results, thought-problems, and data that describe the “highly ranked” phenomena inherent in all operational conditions and important accident scenarios for the VHTR.

  11. Evaluation of nuclear power plant environmental impact prediction, based on monitoring programs. Summary and recommendations

    International Nuclear Information System (INIS)

    Gore, K.L.; Thomas, J.M.; Kannberg, L.D.; Watson, D.G.

    1977-02-01

    An evaluation of the effectivenss of non-radiological environmental monitoring programs is presented. The monitoring programs for Monticello, Haddam Neck, and Millstone Nuclear Generating Plants are discussed. Recommendations for improvements in monitoring programs are presented

  12. An international comparison of nuclear plant training programs

    International Nuclear Information System (INIS)

    Mason, J.H.

    1993-01-01

    In 1990, I visited four utility companies that own and operate pressurized water reactor (PWR) plants in different countries. The purpose of my visits and associated research was to compare nuclear power plant operator and technician training programs. The companies were: Duke Power Company (DUKE) in the United States, Electricite de France (EDF) in France, Kansai Electric Power Company (KEPCO) in Japan, and RWE Energie AG (RWE) in Germany. The purpose of this paper is to highlight selected aspects of the comparison. First, comparisons of the four subject utilities and four typical nuclear power stations operated by each company, McGuire, Paluel, Ohi, and Biblis, are provided. Then comparisons of new employee demographics and training program specific content are provided. Finally, some general observations are drawn from the comparisons. The comparisons are based on information obtained from documents, interviews, and visits to stations and training centers. However, some interpretation of the information was necessary in order to enable a comparison. For example, categorization of training modules requires judgement, interpretation, and translation. In all cases, the information is intended to be representative or typical, rather than statistically precise

  13. Vacuolar processing enzyme in plant programmed cell death

    Directory of Open Access Journals (Sweden)

    Noriyuki eHatsugai

    2015-04-01

    Full Text Available Vacuolar processing enzyme (VPE is a cysteine proteinase originally identified as the proteinase responsible for the maturation and activation of vacuolar proteins in plants, and it is known to be an orthologue of animal asparaginyl endopeptidase (AEP/VPE/legumain. VPE has been shown to exhibit enzymatic properties similar to that of caspase 1, which is a cysteine protease that mediates the programmed cell death (PCD pathway in animals. Although there is limited sequence identity between VPE and caspase 1, their predicted three-dimensional structures revealed that the essential amino-acid residues for these enzymes form similar pockets for the substrate peptide YVAD. In contrast to the cytosolic localization of caspases, VPE is localized in vacuoles. VPE provokes vacuolar rupture, initiating the proteolytic cascade leading to PCD in the plant immune response. It has become apparent that the VPE-dependent PCD pathway is involved not only in the immune response, but also in the responses to a variety of stress inducers and in the development of various tissues. This review summarizes the current knowledge on the contribution of VPE to plant PCD and its role in vacuole-mediated cell death, and it also compares VPE with the animal cell death executor caspase 1.

  14. Basis for snubber aging research: Nuclear Plant Aging Research Program

    International Nuclear Information System (INIS)

    Brown, D.P.; Palmer, G.R.; Werry, E.V.; Blahnik, D.E.

    1990-01-01

    This report describes a research plan to address the safety concerns of aging in snubbers used on piping and equipment in commercial nuclear power plants. The work is to be performed under Phase 2 of the Snubber Aging Study of the Nuclear Plant Aging Research Program of the US Nuclear Regulatory Commission with the Pacific Northwest Laboratory (PNL) as the prime contractor. Research conducted by PNL under Phase 1 provided an initial assessment of snubber operating experience and was primarily based on a review of licensee event reports. The work proposed is an extension of Phase 1 and includes research at nuclear power plants and in test laboratories. Included is technical background on the design and use of snubbers in commercial nuclear power applications; the primary failure modes of both hydraulic and mechanical snubbers are discussed. The anticipated safety, technical, and regulatory benefits of the work, along with concerns of the NRC and the utilities, are also described. 21 refs., 7 figs., 1 tab

  15. Examining the effectiveness of a restorative justice program for various types of juvenile offenders.

    Science.gov (United States)

    Bergseth, Kathleen J; Bouffard, Jeffrey A

    2013-09-01

    Restorative justice (RJ) programs have become widespread in the United States and in other countries. These programs are often seen as a viable alternative to traditional retributive processing, especially for minor, and sometimes more serious, forms of delinquency and adult criminality. The programs hold promise for achieving several goals, including increased community and victim involvement, greater satisfaction with the case outcomes, improved offender compliance, increased perceptions of fairness, and even recidivism reduction. Meta-analyses have demonstrated varying degrees of program success in recidivism reduction, which may in part reflect differential effectiveness of the RJ approach for various kinds of offenders. This study examined whether an RJ program for juvenile offenders had differential impacts on recidivism across various offender characteristics (including age, gender, racial group, offending history, and current offense). Results generally support the effectiveness of the program for many types of offenders. Implications for future research and potential improvements to the RJ model are discussed.

  16. Results of technical and economical examinations for substantiation of special plant design for reprocessing and radioactive wastes disposal

    International Nuclear Information System (INIS)

    Galkin, A.V.; Baldov, A.N.

    2001-01-01

    In the paper the results of technical and economical examinations for substantiation of special plant design for reprocessing and radioactive wastes disposal are presented. Ground for the examination conducting was Health of Nation Programme ratified by the President and a number of Governmental decisions. The special plant is planned in the Mangystau Region. In the framework of feasibility study the data base by the worldwide known technologies was implemented, on reprocessing and experience of radioactive waste disposal. The technical requirements for the special plant construction are determined. The alternative options by structure content and site location of the special plant and radioactive waste disposal are cited

  17. Technical Proposal Salton Sea Geothermal Power Pilot Plant Program

    Energy Technology Data Exchange (ETDEWEB)

    None

    1975-03-28

    The proposed Salton Sea Geothermal Power Pilot Plant Program comprises two phases. The objective of Phase 1 is to develop the technology for power generation from high-temperature, high-salinity geothermal brines existing in the Salton Sea known geothermal resources area. Phase 1 work will result in the following: (a) Completion of a preliminary design and cost estimate for a pilot geothermal brine utilization facility. (b) Design and construction of an Area Resource Test Facility (ARTF) in which developmental geothermal utilization concepts can be tested and evaluated. Program efforts will be divided into four sub-programs; Power Generation, Mineral Extraction, Reservoir Production, and the Area Resources Test Facility. The Power Generation Subprogram will include testing of scale and corrosion control methods, and critical power cycle components; power cycle selection based on an optimization of technical, environmental and economic analyses of candidate cycles; preliminary design of a pilot geothermal-electric generating station to be constructed in Phase 2 of this program. The Mineral Extraction Subprogram will involve the following: selection of an optimum mineral recovery process; recommendation of a brine clean-up process for well injection enhancement; engineering, construction and operation of mineral recovery and brine clean-up facilities; analysis of facility operating results from environmental, economical and technical point-of-view; preliminary design of mineral recovery and brine clean-up facilities of sufficient size to match the planned pilot power plant. The Reservoir Production Subprogram will include monitoring the operation and maintenance of brine production, handling and injection systems which were built with private funding in phase 0, and monitoring of the brine characteristics and potential subsidence effects during well production and injection. Based on the above, recommendations and specifications will be prepared for production and

  18. Next Generation Nuclear Plant Research and Development Program Plan

    Energy Technology Data Exchange (ETDEWEB)

    P. E. MacDonald

    2005-01-01

    The U.S Department of Energy (DOE) is conducting research and development (R&D) on the Very High Temperature Reactor (VHTR) design concept for the Next Generation Nuclear Plant (NGNP) Project. The reactor design will be a graphite moderated, thermal neutron spectrum reactor that will produce electricity and hydrogen in a highly efficient manner. The NGNP reactor core could be either a prismatic graphite block type core or a pebble bed core. Use of a liquid salt coolant is also being evaluated. The NGNP will use very high-burnup, low-enriched uranium, TRISO-coated fuel, and have a projected plant design service life of 60 years. The VHTR concept is considered to be the nearest-term reactor design that has the capability to efficiently produce hydrogen. The plant size, reactor thermal power, and core configuration will ensure passive decay heat removal without fuel damage or radioactive material releases during accidents. The objectives of the NGNP Project are to: Demonstrate a full-scale prototype VHTR that is commercially licensed by the U.S. Nuclear Regulatory Commission Demonstrate safe and economical nuclearassisted production of hydrogen and electricity. The DOE laboratories, led by the INL, will perform R&D that will be critical to the success of the NGNP, primarily in the areas of: High temperature gas reactor fuels behavior High temperature materials qualification Design methods development and validation Hydrogen production technologies Energy conversion. The current R&D work is addressing fundamental issues that are relevant to a variety of possible NGNP designs. This document describes the NGNP R&D planned and currently underway in the first three topic areas listed above. The NGNP Advanced Gas Reactor (AGR) Fuel Development and Qualification Program is presented in Section 2, the NGNP Materials R&D Program Plan is presented in Section 3, and the NGNP Design Methods Development and Validation R&D Program is presented in Section 4. The DOE-funded hydrogen

  19. Next Generation Nuclear Plant Research and Development Program Plan

    Energy Technology Data Exchange (ETDEWEB)

    None

    2005-01-01

    The U.S Department of Energy (DOE) is conducting research and development (R&D) on the Very High Temperature Reactor (VHTR) design concept for the Next Generation Nuclear Plant (NGNP) Project. The reactor design will be a graphite moderated, thermal neutron spectrum reactor that will produce electricity and hydrogen in a highly efficient manner. The NGNP reactor core could be either a prismatic graphite block type core or a pebble bed core. Use of a liquid salt coolant is also being evaluated. The NGNP will use very high-burnup, low-enriched uranium, TRISO-coated fuel, and have a projected plant design service life of 60 years. The VHTR concept is considered to be the nearest-term reactor design that has the capability to efficiently produce hydrogen. The plant size, reactor thermal power, and core configuration will ensure passive decay heat removal without fuel damage or radioactive material releases during accidents. The objectives of the NGNP Project are to: (1) Demonstrate a full-scale prototype VHTR that is commercially licensed by the U.S. Nuclear Regulatory Commission (2) Demonstrate safe and economical nuclear-assisted production of hydrogen and electricity. The DOE laboratories, led by the INL, will perform R&D that will be critical to the success of the NGNP, primarily in the areas of: (1) High temperature gas reactor fuels behavior; (2) High temperature materials qualification; (3) Design methods development and validation; (4) Hydrogen production technologies; and (5) Energy conversion. The current R&D work is addressing fundamental issues that are relevant to a variety of possible NGNP designs. This document describes the NGNP R&D planned and currently underway in the first three topic areas listed above. The NGNP Advanced Gas Reactor (AGR) Fuel Development and Qualification Program is presented in Section 2, the NGNP Materials R&D Program Plan is presented in Section 3, and the NGNP Design Methods Development and Validation R&D Program is presented

  20. Anhydrobiosis and programmed cell death in plants: Commonalities and Differences

    Directory of Open Access Journals (Sweden)

    Samer Singh

    2015-05-01

    Full Text Available Anhydrobiosis is an adaptive strategy of certain organisms or specialised propagules to survive in the absence of water while programmed cell death (PCD is a finely tuned cellular process of the selective elimination of targeted cell during developmental programme and perturbed biotic and abiotic conditions. Particularly during water stress both the strategies serve single purpose i.e., survival indicating PCD may also function as an adaptive process under certain conditions. During stress conditions PCD cause targeted cells death in order to keep the homeostatic balance required for the organism survival, whereas anhydrobiosis suspends cellular metabolic functions mimicking a state similar to death until reestablishment of the favourable conditions. Anhydrobiosis is commonly observed among organisms that have ability to revive their metabolism on rehydration after removal of all or almost all cellular water without damage. This feature is widely represented in terrestrial cyanobacteria and bryophytes where it is very common in both vegetative and reproductive stages of life-cycle. In the course of evolution, with the development of advanced vascular system in higher plants, anhydrobiosis was gradually lost from the vegetative phase of life-cycle. Though it is retained in resurrection plants that primarily belong to thallophytes and a small group of vascular angiosperm, it can be mostly found restricted in orthodox seeds of higher plants. On the contrary, PCD is a common process in all eukaryotes from unicellular to multicellular organisms including higher plants and mammals. In this review we discuss physiological and biochemical commonalities and differences between anhydrobiosis and PCD.

  1. Examining Variations in Fourth-Grade Children's Participation in School Breakfast and Lunch Programs by Student and Program Demographics

    Science.gov (United States)

    Guinn, Caroline H.; Baxter, Suzanne Domel; Finney, Christopher J.; Hitchcock, David B.

    2013-01-01

    Purpose/Objectives: Analyses were conducted to examine variations in fourth-grade children's participation in school-breakfast and school-lunch programs by weekday, month, socioeconomic status, absenteeism, gender, and school-breakfast location. Methods: Fourth-grade children were participants in a dietary-reporting validation study during either…

  2. 50 CFR 23.79 - How may I participate in the Plant Rescue Center Program?

    Science.gov (United States)

    2010-10-01

    ... 50 Wildlife and Fisheries 6 2010-10-01 2010-10-01 false How may I participate in the Plant Rescue Center Program? 23.79 Section 23.79 Wildlife and Fisheries UNITED STATES FISH AND WILDLIFE SERVICE... may I participate in the Plant Rescue Center Program? (a) Purpose. We have established the Plant...

  3. The Waste Isolation Pilot Plant Performance Assessment Program

    International Nuclear Information System (INIS)

    Myers, J.; Coons, W.E.; Eastmond, R.; Morse, J.; Chakrabarti, S.; Zurkoff, J.; Colton, I.D.; Banz, I.

    1986-01-01

    The Waste Isolation Pilot Plant (WIPP) Performance Assessment Program involves a comprehensive analysis of the WIPP project with respect to the recently finalized Environmental Protection Agency regulations regarding the long-term geologic isolation of radioactive wastes. The performance assessment brings together the results of site characterization, underground experimental, and environmental studies into a rigorous determination of the performance of WIPP as a disposal system for transuranic radioactive waste. The Program consists of scenario development, geochemical, hydrologic, and thermomechanical support analyses and will address the specific containment and individual protection requirements specified in 40 CFR 191 sub-part B. Calculated releases from these interrelated analyses will be reported as an overall probability distribution of cumulative release resulting from all processes and events occurring over the 10,000 year post-closure period. In addition, results will include any doses to the public resulting from natural processes occurring over the 1,000 year post-closure period. The overall plan for the WIPP Performance Assessment Program is presented along with approaches to issues specific to the WIPP project

  4. Experimental program plan for the Waste Isolation Pilot Plant

    Energy Technology Data Exchange (ETDEWEB)

    1994-01-01

    The US Department of Energy has prepared this Experimental Program Plan for the Waste Isolation Pilot Plant (EPP) to provide a summary of the DOE experimental efforts needed for the performance assessment process for the WIPP, and of the linkages of this process to the appropriate regulations. The Plan encompasses a program of analyses of the performance of the planned repository based on scientific studies, including tests with transuranic waste at laboratory sites, directed at evaluating compliance with the principal regulations governing the WIPP. The Plan begins with background information on the WIPP project, the requirements of the LWA (Land Withdrawal Act), and its objective and scope. It then presents an overview of the regulatory requirements and the compliance approach. Next are comprehensive discussions of plans for compliance with disposal regulations, followed by the SWDA (Solid Waste Disposal Act) and descriptions of activity programs designed to provide information needed for determining compliance. Descriptions and justifications of all currently planned studies designed to support regulatory compliance activities are also included.

  5. Experimental program plan for the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    1994-01-01

    The US Department of Energy has prepared this Experimental Program Plan for the Waste Isolation Pilot Plant (EPP) to provide a summary of the DOE experimental efforts needed for the performance assessment process for the WIPP, and of the linkages of this process to the appropriate regulations. The Plan encompasses a program of analyses of the performance of the planned repository based on scientific studies, including tests with transuranic waste at laboratory sites, directed at evaluating compliance with the principal regulations governing the WIPP. The Plan begins with background information on the WIPP project, the requirements of the LWA (Land Withdrawal Act), and its objective and scope. It then presents an overview of the regulatory requirements and the compliance approach. Next are comprehensive discussions of plans for compliance with disposal regulations, followed by the SWDA (Solid Waste Disposal Act) and descriptions of activity programs designed to provide information needed for determining compliance. Descriptions and justifications of all currently planned studies designed to support regulatory compliance activities are also included

  6. Introduction to an open source internet-based testing program for medical student examinations.

    Science.gov (United States)

    Lee, Yoon-Hwan

    2009-12-20

    The author developed a freely available open source internet-based testing program for medical examination. PHP and Java script were used as the programming language and postgreSQL as the database management system on an Apache web server and Linux operating system. The system approach was that a super user inputs the items, each school administrator inputs the examinees' information, and examinees access the system. The examinee's score is displayed immediately after examination with item analysis. The set-up of the system beginning with installation is described. This may help medical professors to easily adopt an internet-based testing system for medical education.

  7. Introduction to an Open Source Internet-Based Testing Program for Medical Student Examinations

    Directory of Open Access Journals (Sweden)

    Yoon-Hwan Lee

    2009-12-01

    Full Text Available The author developed a freely available open source internet-based testing program for medical examination. PHP and Java script were used as the programming language and postgreSQL as the database management system on an Apache web server and Linux operating system. The system approach was that a super user inputs the items, each school administrator inputs the examinees’ information, and examinees access the system. The examinee’s score is displayed immediately after examination with item analysis. The set-up of the system beginning with installation is described. This may help medical professors to easily adopt an internet-based testing system for medical education.

  8. Integrated plant-safety assessment, Systematic Evaluation Program: Big Rock Point Plant (Docket No. 50-155)

    International Nuclear Information System (INIS)

    1983-09-01

    The Systematic Evaluation Program was initiated in February 1977 by the US Nuclear Regulatory Commission to review the designs of older operating nuclear reactor plants to reconfirm and document their safety. This report documents the review of the Big Rock Point Plant, which is one of ten plants reviewed under Phase II of this program. This report indicates how 137 topics selected for review under Phase I of the program were addressed. It also addresses a majority of the pending licensing actions for Big Rock Point, which include TMI Action Plan requirements and implementation criteria for resolved generic issues. Equipment and procedural changes have been identified as a result of the review

  9. Waste Isolation Pilot Plant Groundwater Protection Management Program Plan

    International Nuclear Information System (INIS)

    1993-01-01

    The DOE has mandated in DOE Order 5400.1 that its operations will be conducted in an environmentally safe manner. The Waste Isolation Pilot Plant (WIPP) will comply with DOE Order 5400.1 and will conduct its operations in a manner that ensures the safety of the environment and the public. This document outlines how the WIPP will protect and preserve groundwater within and surrounding the WIPP facility. Groundwater protection is just one aspect of the WIPP environmental protection effort. The WIPP groundwater surveillance program is designed to determine statistically if any changes are occurring in groundwater characteristics within and surrounding the WIPP facility. If a change is noted, the cause will be determined and appropriate corrective action initiated

  10. Aquatic Plant Management Program current status and seasonal workplan

    Energy Technology Data Exchange (ETDEWEB)

    Burns, E.R.; Bates, A.L.; Webb, D.H.

    1993-07-01

    The objective of the TVA Aquatic Plant Management Program is to support in an environmentally and economically responsible manner, the balanced multiple uses of the water resource of the Tennessee Valley. This is accomplished by following an integrated approach to prevent introduction and spread of noxious species, documenting occurrence and spread of existing species, and suppressing or eliminating problems in designated high use areas. It is not the TVA objective, nor is it biologically feasible and prudent to eliminate all aquatic vegetation. Aerial photography, helicopter reconnaissance, and field surveys are used to assess distributions and abundance of various aquatic macrophytes. Water level fluctuations are supplemented by herbicide applications to control undesirable vegetation. Investigations are conducted to evaluate water level fluctuation schemes, as well as biological, mechanical, and alternative chemical control techniques which offer potential for more environmentally compatible and cost-effective management operations.

  11. Power plant system assessment. Final report. SP-100 Program

    International Nuclear Information System (INIS)

    Anderson, R.V.; Atkins, D.F.; Bost, D.S.

    1983-01-01

    The purpose of this assessment was to provide system-level insights into 100-kWe-class space reactor electric systems. Using these insights, Rockwell was to select and perform conceptual design studies on a ''most attractive'' system that met the preliminary design goals and requirements of the SP-100 Program. About 4 of the 6 months were used in the selection process. The remaining 2 months were used for the system conceptual design studies. Rockwell completed these studies at the end of FY 1983. This report summarizes the results of the power plant system assessment and describes our choice for the most attractive system - the Rockwell SR-100G System (Space Reactor, 100 kWe, Growth) - a lithium-cooled UN-fueled fast reactor/Brayton turboelectric converter system

  12. Nuclear power plant thermal-hydraulic performance research program plan

    International Nuclear Information System (INIS)

    1988-07-01

    The purpose of this program plan is to present a more detailed description of the thermal-hydraulic research program than that provided in the NRC Five-Year Plan so that the research plan and objectives can be better understood and evaluated by the offices concerned. The plan is prepared by the Office of Nuclear Regulatory Research (RES) with input from the Office of Nuclear Reactor Regulation (NRR) and updated periodically. The plan covers the research sponsored by the Reactor and Plant Systems Branch and defines the major issues (related to thermal-hydraulic behavior in nuclear power plants) the NRC is seeking to resolve and provides plans for their resolution; relates the proposed research to these issues; defines the products needed to resolve these issues; provides a context that shows both the historical perspective and the relationship of individual projects to the overall objectives; and defines major interfaces with other disciplines (e.g., structural, risk, human factors, accident management, severe accident) needed for total resolution of some issues. This plan addresses the types of thermal-hydraulic transients that are normally considered in the regulatory process of licensing the current generation of light water reactors. This process is influenced by the regulatory requirements imposed by NRC and the consequent need for technical information that is supplied by RES through its contractors. Thus, most contractor programmatic work is administered by RES. Regulatory requirements involve the normal review of industry analyses of design basis accidents, as well as the understanding of abnormal occurrences in operating reactors. Since such transients often involve complex thermal-hydraulic interactions, a well-planned thermal-hydraulic research plan is needed

  13. The examination of Hevea brasiliensis plants produced by in vitro culture and mutagenesis by DNA fingerprinting techniques

    International Nuclear Information System (INIS)

    Low, F.C.; Atan, S.; Jaafar, H.

    1998-01-01

    Rubber (Hevea brasiliensis) plants derived from anther and ovule culture as well as gamma-irradiated plants were examined by several DNA marker techniques. These include restriction fragment length polymorphisms (RFLPs), random amplified polymorphic DNA (RAPD), sequence tagged microsatellite sites (STMS), DNA amplification fingerprinting (DAF) and amplified fragment length polymorphisms (AFLPs). Compared to control plants produced by vegetative propagation (cutting and budding), plants produced by in vitro culture appeared to have a reduction in the number of rDNA loci. Two RAPD protocols were compared and found to be similar in amplification of the major DNA bands. After confirmation that the RAPD method adopted was reproducible, the technique was applied to the present studies. Eight out of the 60 primers screened were able to elicit polymorphisms between pooled DNA from in vitro culture plants. Variations in DNA patterns were observed between pooled DNA samples of anther-derived plants as well as between anther-derived and ovule-derived plants. Comparisons of RAPD patterns obtained between anther-derived plants exposed to increasing dosages of gamma-irradiation with non irradiated anther-derived plants revealed distinct DNA polymorphisms. The changes in DNA profiles did not appear to be correlated to the dosage of irradiation. Since somaclonal variation was detected, it was difficult to identify changes which were specifically caused by irradiation. Application of the STMS technique to tag micro satellite sequences (GA) n , (TA) n and (TTA) n in the hydroxymethylglutaryl coenzyme A reductase-1 (hmgr-1) gene failed to detect differences between plants derived from anther and ovule culture. Although restriction endonuclease digestions with methylation sensitive enzymes suggested that four in vitro culture plants examined exhibited similar digestion patterns as the controls, a change in cytosine methylation in one anther-derived plant was detected. Examination of

  14. Quality Assurance Program Plan for the Waste Isolation Pilot Plant Experimental-Waste Characterization Program

    International Nuclear Information System (INIS)

    1991-01-01

    This Quality Assurance Program Plan (QAPP) identifies the quality of data necessary to meet the specific objectives associated with the Department of Energy (DOE) Waste Isolation Pilot Plant (WIPP) Experimental-Waste Characterization Program (the Program). DOE plans to conduct experiments in the WIPP during a Test Phase of approximately 5 years. These experiments will be conducted to reduce the uncertainties associated with the prediction of several processes (e.g., gas generation) that may influence repository performance. The results of the experiments will be used to assess the ability of the WIPP to meet regulatory requirements for the long-term protection of human health and the environment from the disposal of TRU wastes. 37 refs., 25 figs., 18 tabs

  15. Examining the Feasibility and Effectiveness of a Community-Based Obesity Prevention Program

    Science.gov (United States)

    Cotter, Elizabeth W.; Bera, Victoria; Elsemore, Johanna; Snelling, Anastasia

    2018-01-01

    Background: Latinos in the United States are at heightened risk for obesity and health disparities, yet community-based interventions to promote health are limited. Purpose: This research examined the feasibility and efficacy of a culturally relevant obesity prevention program (Vivir Sano), which included stress reduction and behavioral lifestyle…

  16. A Critical Examination of the Process of Modifying the Curriculum of Alternative Secondary Educational Programs

    Science.gov (United States)

    Ross, Michael

    2014-01-01

    This study, "A Critical Examination of the Process of Modifying the Curriculum of Alternative Secondary Educational Programs," was done with the use of action research to study (a) whether students currently participating in a continuation school believe their educational and career needs are presently being met; (b) the types of career…

  17. Assessment of Primary Representational Systems with Neurolinguistic Programming: Examination of Preliminary Literature.

    Science.gov (United States)

    Dorn, Fred J.; And Others

    1983-01-01

    Reviews the inconsistent findings of studies on neurolinguistic programing and recommends some areas that should be examined to verify various claims. Discusses methods of assessing client's primary representational systems, including predicate usage and eye movements, and suggests that more reliable methods of assessing PRS must be found. (JAC)

  18. 46 CFR 176.620 - Description of the Alternative Hull Examination (AHE) Program for certain passenger vessels.

    Science.gov (United States)

    2010-10-01

    ... 46 Shipping 7 2010-10-01 2010-10-01 false Description of the Alternative Hull Examination (AHE... Hull and Tailshaft Examinations § 176.620 Description of the Alternative Hull Examination (AHE) Program for certain passenger vessels. The Alternative Hull Examination (AHE) Program provides you with an...

  19. 46 CFR 71.50-15 - Description of the Alternative Hull Examination (AHE) Program for certain passenger vessels.

    Science.gov (United States)

    2010-10-01

    ... 46 Shipping 3 2010-10-01 2010-10-01 false Description of the Alternative Hull Examination (AHE... Description of the Alternative Hull Examination (AHE) Program for certain passenger vessels. The Alternative Hull Examination (AHE) Program provides you with an alternative to a drydock examination by allowing...

  20. Examination of radioactive contamination in the soil-plant system and their transfer to selected animal tissues

    International Nuclear Information System (INIS)

    Chibowski, S.; Gladysz, A.

    1999-01-01

    This paper investigates gamma emitter radioactivity in a system consisting of soil and plants. Some selected sample of tissues of animals fed with the plants from these sites were also measured. In soil and plant samples artificial ( 137 Cs and 134 Cs) and natural (thorium and uranium series) isotopes were detected. Despite the relatively high content of the natural isotopes in plants and their seeds, their accumulation in animal tissues was not detected.The 40 K isotope was transferred in the chain soil-plant-animal in the highest degree. From the group of the natural isotopes, only 212 Pb was detected in examined animal tissue samples. Other natural isotopes were below detection level. In the samples heavy metal content was also examined. In any sample no element concentration was noticed above trade acceptable limit. (author)

  1. Examination of program exposure across intervention delivery modes: face-to-face versus internet

    Directory of Open Access Journals (Sweden)

    Mummery W Kerry

    2007-03-01

    Full Text Available Abstract Background There has been increasing interest in the ability of the internet to produce behaviour change. The focus of this study was to describe program exposure across three intervention groups from a randomised trial (RT comparing traditional face-to-face, internet-mediated (combined internet plus face-to-face, and internet-only program delivery. Methods Baseline and immediately post-intervention survey data, and exposure rates from participants that commenced the RT were included (n = 192. Exposure was defined as either face-to-face attendance, website usage, or a combination of both for the internet-mediated group. Characteristics of participants who were exposed to at least 75% of the program material were explored. Descriptive analysis and logistical regression were used to examine differences between groups for program exposure. Results All groups showed decrease in program exposure over time. Differences were also observed (χ2 = 10.37, p Conclusion These results suggest that the internet groups were as effective as the face-to-face delivery mode in engaging participants in the program material. However, different delivery methods may be more useful to different sub-populations. It is important to explore which target groups that internet-based programs are best suited, in order to increase their impact.

  2. Attributes of Candidates Passing the ABS Certifying Examination on the First Attempt-Program Directors׳ Perspective.

    Science.gov (United States)

    Sheikh, Mohd Raashid; Hulme, Michael

    2016-01-01

    The American Board of Surgery Certifying Examination (CE) is a pivotal event in a surgeon's career development, as it is the last challenge before achieving Board certification. First-time pass rate on the CE is one of the key metrics of surgery residency programs. The overall pass rate on the CE has declined significantly in recent years. The goal of this study was the identification of attributes of general surgery residents that are associated with passing the CE at the first attempt. The modified Delphi process was used to survey general surgery program directors. The study was conducted in 2 rounds in the interest of time available for surgical education research fellowship project. All 259 program directors were contacted in each round of surveys. In all, 49 (19%) responded to the first round and 54 (21%) responded to the second round of survey. The characteristics of a successful resident on CE include confidence, self-motivation, sound knowledge base, strong performance on the Board's training examination (American Board of Surgery In-Training Examination), and mock orals, and good communication skills. Postgraduate years 4 and 5 are the most likely resident levels at which failure could be predicted. Copyright © 2015 Association of Program Directors in Surgery. Published by Elsevier Inc. All rights reserved.

  3. Implementing the objective structured clinical examination in a geriatrics fellowship program-a 3-year experience.

    Science.gov (United States)

    Avelino-Silva, Thiago J; Gil, Luiz A; Suemoto, Claudia K; Kikuchi, Elina L; Lin, Sumika M; Farias, Luciana L; Jacob-Filho, Wilson

    2012-07-01

    The Objective Structured Clinical Examination (OSCE) appears to be an effective alternative for assessing not only medical knowledge, but also clinical skills, including effective communication and physical examination skills. The purpose of the current study was to implement an OSCE model in a geriatrics fellowship program and to compare the instrument with traditional essay examination. Seventy first- and second-year geriatric fellows were initially submitted to a traditional essay examination and scored from 0 to 10 by a faculty member. The same fellows subsequently underwent an OSCE with eight 10-minute stations covering a wide range of essential aspects of geriatric knowledge. Each OSCE station had an examiner responsible for its evaluation according to a predefined checklist. Checklist items were classified for analysis purposes as clinical knowledge items (CKI) and communication skills items (CSI); fellow responses were scored from 0 to 10.Although essay examinations took from 30 to 45 minutes to complete, 180-200 minutes were required to evaluate fellows using the proposed OSCE method. Fellows scored an average of 6.2 ± 1.2 on the traditional essay examination and 6.6 ± 1.0 on the OSCE (P examination was similar to their performance on CKI (P = .13). Second-year fellows performed better than first-year fellows on the essay examination (P geriatrics fellowship program. Combining different testing modalities may provide the best assessment of competence for various domains of knowledge, skills, and behavior. © 2012, Copyright the Authors Journal compilation © 2012, The American Geriatrics Society.

  4. Computer program for afterheat temperature distribution for mobile nuclear power plant

    Science.gov (United States)

    Parker, W. G.; Vanbibber, L. E.

    1972-01-01

    ESATA computer program was developed to analyze thermal safety aspects of post-impacted mobile nuclear power plants. Program is written in FORTRAN 4 and designed for IBM 7094/7044 direct coupled system.

  5. A review of electric cable aging effects and monitoring programs for plant license renewal

    International Nuclear Information System (INIS)

    Lofaro, R.J.

    1999-01-01

    As commercial nuclear power plants approach the end of their original license period, some utilities are considering the possibility of license renewal. The requirements for applying for license renewal are specified in the License Renewal Rule, which is in Title 10 of the Code of Federal Regulations, Part 54 (10 CFR54). Among the requirements specified in the rule is the performance of an Integrated Plant Assessment (IPA) which identifies and lists structures and components subject to an aging management review. The intent of this requirement is to ensure that aging degradation will not adversely affect plant safety during the license renewal period. The aging management review includes an identification of the aging effects and monitoring programs for components within the scope of the rule. Among the components within the scope are electric cables since they are passive, long-lived components that are not replaced on a periodic basis. This paper examines the aging causes and effects of electric cables, along with the programs that are typically used to ensure that proper aging management practices are in place to monitor and mitigate the effects of aging on electric cables

  6. Evaluation of Monticello Nuclear Power Plant, Environmental Impact Prediction, based on monitoring programs

    International Nuclear Information System (INIS)

    Gore, K.L.; Thomas, J.M.; Kannberg, L.D.; Watson, D.G.

    1976-11-01

    This report evaluates quantitatively the nonradiological environmental monitoring programs at Monticello Nuclear Generating Plant. The general objective of the study is to assess the effectiveness of monitoring programs in the measurement of environmental impacts. Specific objectives include the following: (1) Assess the validity of environmental impact predictions made in the Environmental Statement by analysis of nonradiological monitoring data; (2) evaluate the general adequacy of environmental monitoring programs for detecting impacts and their responsiveness to Technical Specifications objectives; (3) assess the adequacy of preoperational monitoring programs in providing a sufficient data base for evaluating operational impacts; (4) identify possible impacts that were not predicted in the environmental statement and identify monitoring activities that need to be added, modified or deleted; and (5) assist in identifying environmental impacts, monitoring methods, and measurement problems that need additional research before quantitative predictions can be attempted. Preoperational as well as operational monitoring data were examined to test the usefulness of baseline information in evaluating impacts. This included an examination of the analytical methods used to measure ecological and physical parameters, and an assessment of sampling periodicity and sensitivity where appropriate data were available

  7. Survey of radionuclide emissions from coal-fired power plants and examination of impacts from a proposed circulating fluidized bed boiler power plant

    International Nuclear Information System (INIS)

    Steiner, C.P.; Militana, L.M.; Harvey, K.A.; Kinsey, G.D.

    1995-01-01

    This paper presents the results of a literature survey that examined radionuclide emissions from coal-fired power plants. Literature references from both the US and foreign countries are presented. Emphasis is placed on references from the US because the radionuclide emissions from coal-fired power plants are related to radionuclide concentrations in the coal, which vary widely throughout the world. The radionuclides were identified and quantified for various existing power plants reported in the literature. Applicable radionuclide emissions criteria discovered in the literature search were then applied to a proposed circulating fluidized bed boiler power plant. Based upon the derived radionuclide emission rates applied to the proposed power plant, an air quality modeling analysis was performed. The estimated ambient concentrations were compared to the most relevant existing regulatory ambient levels for radionuclides

  8. Waste Isolation Pilot Plant Groundwater Protection Management Program Plan

    Energy Technology Data Exchange (ETDEWEB)

    Washington Regulatory and Environmental Services

    2005-07-01

    The DOE established the Groundwater Monitoring Program (GMP) (WP 02-1) to monitor groundwater resources at WIPP. In the past, the GMP was conducted to establish background data of existing conditions of groundwater quality and quantity in the WIPP vicinity, and to develop and maintain a water quality database as required by regulation. Today the GMP is conducted consistent with 204.1.500 NMAC (New MexicoAdministrative Code), "Adoption of 40 CFR [Code of Federal Regulations] Part 264,"specifically 40 CFR §264.90 through §264.101. These sections of 20.4.1 NMAC provide guidance for detection monitoring of groundwater that is, or could be, affected by waste management activities at WIPP. Detection monitoring at WIPP is designed to detect contaminants in the groundwater long before the general population is exposed. Early detection will allow cleanup efforts to be accomplished before any exposure to the general population can occur. Title 40 CFR Part 264, Subpart F, stipulates minimum requirements of Resource Conservation and Recovery Act of 1976 (42 United States Code [U.S.C.] §6901 et seq.) (RCRA) groundwater monitoring programs including the number and location of monitoring wells; sampling and reporting schedules; analytical methods and accuracy requirements; monitoring parameters; and statistical treatment of monitoring data. This document outlines how WIPP intends to protect and preserve groundwater within the WIPP Land Withdrawal Area (WLWA). Groundwater protection is just one aspect of the WIPP environmental protection effort. An overview of the entire environmental protection effort can be found in DOE/WIPP 99-2194, Waste Isolation Pilot Plant Environmental Monitoring Plan. The WIPP GMP is designed to statistically determine if any changes are occurring in groundwater characteristics within and surrounding the WIPP facility. If a change is noted, the cause will then be determined and the appropriate corrective action(s) initiated.

  9. Waste Isolation Pilot Plant Groundwater Protection Management Program Plan

    International Nuclear Information System (INIS)

    2005-01-01

    The DOE established the Groundwater Monitoring Program (GMP) (WP 02-1) to monitor groundwater resources at WIPP. In the past, the GMP was conducted to establish background data of existing conditions of groundwater quality and quantity in the WIPP vicinity, and to develop and maintain a water quality database as required by regulation. Today the GMP is conducted consistent with 204.1.500 NMAC (New Mexico Administrative Code), 'Adoption of 40 CFR [Code of Federal Regulations] Part 264,'specifically 40 CFR 264.90 through 264.101. These sections of 20.4.1 NMAC provide guidance for detection monitoring of groundwater that is, or could be, affected by waste management activities at WIPP. Detection monitoring at WIPP is designed to detect contaminants in the groundwater long before the general population is exposed. Early detection will allow cleanup efforts to be accomplished before any exposure to the general population can occur. Title 40 CFR Part 264, Subpart F, stipulates minimum requirements of Resource Conservation and Recovery Act of 1976 (42 United States Code [U.S.C.] 6901 et seq.) (RCRA) groundwater monitoring programs including the number and location of monitoring wells; sampling and reporting schedules; analytical methods and accuracy requirements; monitoring parameters; and statistical treatment of monitoring data. This document outlines how WIPP intends to protect and preserve groundwater within the WIPP Land Withdrawal Area (WLWA). Groundwater protection is just one aspect of the WIPP environmental protection effort. An overview of the entire environmental protection effort can be found in DOE/WIPP 99-2194, Waste Isolation Pilot Plant Environmental Monitoring Plan. The WIPP GMP is designed to statistically determine if any changes are occurring in groundwater characteristics within and surrounding the WIPP facility. If a change is noted, the cause will then be determined and the appropriate corrective action(s) initiated.

  10. Undergraduate grade point average and graduate record examination scores: the experience of one graduate nursing program.

    Science.gov (United States)

    Newton, Sarah E; Moore, Gary

    2007-01-01

    Graduate nursing programs frequently use undergraduate grade point average (UGPA) and Graduate Record Examination (GRE) scores for admission decisions. The literature indicates that both UGPA and GRE scores are predictive of graduate school success, but that UGPA may be the better predictor. If that is so, one must ask if both are necessary for graduate nursing admission decisions. This article presents research on one graduate nursing program's experience with UGPA and GRE scores and offers a perspective regarding their continued usefulness for graduate admission decisions. Data from 120 graduate students were examined, and regression analysis indicated that UGPA significantly predicted GRE verbal and quantitative scores (p < .05). Regression analysis also determined a UGPA score above which the GRE provided little additional useful data for graduate nursing admission decisions.

  11. Development of a measure of training program effectiveness for nuclear power plants

    International Nuclear Information System (INIS)

    Connelly, E.M.; Haas, P.; VanHemel, S.B.; Wreathall, J.

    1991-01-01

    The approach taken to develop measures of training program effectiveness recognizes that many subject matter experts (SMEs) with varying viewpoints on training effectiveness are working to insure nuclear power plant (NPP) safety. This paper discusses a model as the effectiveness rating strategies of various SMEs whose ratings are important to training; i.e., build a measure of effectiveness (MOE) representing the rating strategy of a sample of those SMEs. A quantitative model of these assessment strategies permits a broad review of them by ll interested parties and provides the basis for building a broadly accepted training program MOE. Major differences in assessment strategies can be examined to determine whether they are appropriate to the different points of view or are in conflict. This paper describes the basic concepts of building effectiveness measures, the methodology used to build the measures, a summary of the measures developed form NRC and industry sources, and an analysis of the differences among SMEs' measures

  12. CHAP: a composite nuclear plant simulation program applied to the 3000 MW(t) HTGR

    International Nuclear Information System (INIS)

    Secker, P.A.; Bailey, P.G.; Gilbert, J.S.; Willcutt, G.J.E. Jr.; Vigil, J.C.

    1977-01-01

    The Composite HTGR Analysis Program (CHAP) is a general systems analysis program which has been developed at LASL. The program is being used for simulating large HTGR nuclear power plant operation and accident transients. The general features and analytical methods of the CHAP program are discussed. Features of the large HTGR model and results of model transients are also presented

  13. Increase plant safety and reduce cost by implementing risk-informed in-service inspection programs

    International Nuclear Information System (INIS)

    Billington, A.; Monette, P.

    2001-01-01

    The idea behind the program is that it is possible to 'inspect less, but inspect better'. In other words, the risk-informed In-Service Inspection (ISI) process is used to improve the effectiveness of examination of piping components, i.e. concentrate inspection resources and enhance inspection strategies on high safety significant locations, and reduce inspection requirements on others. The Westinghouse Owners Group (WOG) risk-informed ISI process has already been applied for full scope (Millstone 3, Surry 1) and limited scope (Beznau, Ringhals 4, Asco, Turkey Point 3). By examining the high safety significant piping segments for the different fluid piping systems, the total piping core damage frequency is reduced. In addition, more than 80% of the risk associated with potential pressure boundary failures is addressed with the WOG risk-informed ISI process, while typically less that 50% of this same risk is addressed by the current inspection programs. The risk-informed ISI processes are used to improve the effectiveness of inspecting safety-significant piping components, to reduce inspection requirements on other piping components, to evaluate improvements to plant availability and enhanced safety measures, including reduction of personnel radiation exposure, and to reduce overall Operation and Maintenance (O and M) costs while maintaining regulatory compliance. A description of the process as well as benefits from past projects is presented, since the methodology is applicable for WWER plant design. (author)

  14. Increase plant safety and reduce cost by implementing risk-informed In-Service Inspection programs

    International Nuclear Information System (INIS)

    Billington, A.; Monette, P.; Doumont, C.

    2000-01-01

    The idea behind the program is that it is possible to 'inspect less, but inspect better'. In other words, the risk-informed In-Service Inspection (ISI) process is used to improve the effectiveness of examination of piping components, i.e. concentrate inspection resources and enhance inspection strategies on high safety significant locations, and reduce inspection requirements on others. The Westinghouse Owners Group (WOG) risk-informed ISI process has already been applied for full scope (Millstone 3, Surry 1) and limited scope (Beznau, Ringhals 4, Asco, Turkey Point 3). By examining the high safety significant piping segments for the different fluid piping systems, the total piping core damage frequency is reduced. In addition, more than 80% of the risk associated with potential pressure boundary failures is addressed with the WOG risk-informed ISI process, while typically less than 50% of this same risk is addressed by the current inspection programs. The risk-informed ISI processes are used: to improve the effectiveness of inspecting safety-significant piping components; to reduce inspection requirements on other piping components; to evaluate improvements to plant availability and enhanced safety measures, including reduction of personnel radiation exposure; and to reduce overall Operation and Maintenance (O and M) costs while maintaining regulatory compliance. A description of the process as well as benefits of past projects is presented, since the methodology is applicable for VVER plant design. (author)

  15. An Approach to Examining the Proximal and Intermediate Outcomes of an Intensive Family Preservation Program

    Science.gov (United States)

    Hurley, Kristin Duppong; Griffith, Annette; Ingram, Stephanie; Bolivar, Claudine; Mason, W. Alex; Trout, Alexandra

    2012-01-01

    This study examined the effects of the Boys Town In-Home Family Program (BT-IHFP) on parenting skills, family functioning, and child behavior for at-risk families involved with child protective services. The BT-IHFP is designed as a home-based, family-centered alternative to out-of-home placement with the goal of improving family functioning,…

  16. United States Medical Licensing Examination and American Board of Pediatrics Certification Examination Results: Does the Residency Program Contribute to Trainee Achievement.

    Science.gov (United States)

    Welch, Thomas R; Olson, Brad G; Nelsen, Elizabeth; Beck Dallaghan, Gary L; Kennedy, Gloria A; Botash, Ann

    2017-09-01

    To determine whether training site or prior examinee performance on the US Medical Licensing Examination (USMLE) step 1 and step 2 might predict pass rates on the American Board of Pediatrics (ABP) certifying examination. Data from graduates of pediatric residency programs completing the ABP certifying examination between 2009 and 2013 were obtained. For each, results of the initial ABP certifying examination were obtained, as well as results on National Board of Medical Examiners (NBME) step 1 and step 2 examinations. Hierarchical linear modeling was used to nest first-time ABP results within training programs to isolate program contribution to ABP results while controlling for USMLE step 1 and step 2 scores. Stepwise linear regression was then used to determine which of these examinations was a better predictor of ABP results. A total of 1110 graduates of 15 programs had complete testing results and were subject to analysis. Mean ABP scores for these programs ranged from 186.13 to 214.32. The hierarchical linear model suggested that the interaction of step 1 and 2 scores predicted ABP performance (F[1,1007.70] = 6.44, P = .011). By conducting a multilevel model by training program, both USMLE step examinations predicted first-time ABP results (b = .002, t = 2.54, P = .011). Linear regression analyses indicated that step 2 results were a better predictor of ABP performance than step 1 or a combination of the two USMLE scores. Performance on the USMLE examinations, especially step 2, predicts performance on the ABP certifying examination. The contribution of training site to ABP performance was statistically significant, though contributed modestly to the effect compared with prior USMLE scores. Copyright © 2017 Elsevier Inc. All rights reserved.

  17. Examining Sense of Community among Medical Professionals in an Online Graduate Program

    Directory of Open Access Journals (Sweden)

    Kadriye O. Lewis

    2015-01-01

    Full Text Available As the number of online degree programs continues to grow, one of the greatest challenges is developing a sense of community among learners who do not convene at the same time and place. This study examined the sense of community among medical professionals in an online graduate program for healthcare professionals. We took the sample from a fully online program delivered jointly by a state university and a local children's hospital in the Midwest. We administered Rovai's Classroom Community Survey with 11 additional demographic questions. We also utilized online interviews to further explore students’ understanding of sense of community. A bi-factor model was fitted to the online sense of community survey data. Using multivariate analysis of variance (MANOVA and univariate analysis of variance (ANOVA we identified potential group differences. The qualitative data were analyzed thematically in a recursive and iterative process. Study results suggested that a dominant factor existed: sense of community with two sub-domain factors including sense of learning and sense of connectedness. No significant differences in sense of community with regard to gender, native language, or area of medical practice were detected. However, results showed a difference in sense of community between the three courses examined. This study is the first to examine the sense of community among online medical professionals. Since our findings are in contrast to those of previous studies, this opens the door to additional studies around the possible differences between the community characteristics and needs of medical professionals as online students.

  18. 78 FR 35330 - Initial Test Programs for Water-Cooled Nuclear Power Plants

    Science.gov (United States)

    2013-06-12

    ... Plants AGENCY: Nuclear Regulatory Commission. ACTION: Regulatory guide; issuance. SUMMARY: The U.S... Programs for Water-Cooled Nuclear Power Plants.'' This guide describes the general scope and depth that the... power plants. ADDRESSES: Please refer to Docket ID NRC-2012-0293 about the availability of information...

  19. 77 FR 73056 - Initial Test Programs for Water-Cooled Nuclear Power Plants

    Science.gov (United States)

    2012-12-07

    ... Plants AGENCY: Nuclear Regulatory Commission. ACTION: Draft regulatory guide; request for comment... (DG), DG-1259, ``Initial Test Programs for Water-Cooled Nuclear Power Plants.'' This guide describes... (ITPs) for light water cooled nuclear power plants. DATES: Submit comments by January 31, 2013. Comments...

  20. An Examination of Peer-Delivered Parenting Skills Programs Across New York State.

    Science.gov (United States)

    Acri, Mary C; Craig, Nancy; Adler, Josh

    2018-03-24

    Peers are an important adjunct to the public mental health service system, and are being increasingly utilized across the country as a cost-effective solution to workforce shortages. Despite the tremendous growth of peer-delivered support over the past two decades, it has only been within the past few years that peer programs have been the subject of empirical inquiry. The purpose of this study was to examine the prevalence and characteristics of peer-delivered parenting programs across the New York State public mental health service system. We surveyed 46 family peer organizations across New York State regarding their delivery of structured peer-delivered parenting programs. Thirty-four (76%) completed the questionnaire, and of them, 18 (53%) delivered a parenting program. Subsequent interviews with seven of the 18 organizations revealed peer organizations had been delivering eight unique parenting programs for upwards of two decades. Additionally, organizations offered multiple supports to families to participate. Training, supervision, and issues around fidelity are discussed, as well as the implications of this study for states utilizing a peer workforce.

  1. A STUDY OF THE REQUIRED PUBLIC ACCOUNTING PROGRAM IN PUBLIC COMPETITIVE EXAMINATIONS HELD BY CESPE

    Directory of Open Access Journals (Sweden)

    Fátima de Souza Freire

    2012-11-01

    Full Text Available With a view to standardizing the contents offered to future Accounting professionals, the Federal Accounting Council (CFC elaborated the National Proposal for Undergraduate Accountancy Program Contents. Thus, the curriculum that Higher Education Institutions (HEI adopt serves as an ally for students’ professional conquests. Stability and favorable job conditions attract many people to the dispute for a public function, with a growing Braz ilian public competitive examination market. According to the National Association for Protection and Support to Public Competitive Examinations (Anpac, between 2003 and 2009, the number of public servants in the executive power with a higher education degree in Brazil increased by 26%. The aim of this study was to confront the CFC’s suggested knowledge with the contents required during tests applied in public competitive examinations for Accountancy professionals. The intent is to identify what Public Accounting knowledge is demanded from candidates for the public career. Through a documentary research, 561 calls from public competitive examinations exclusively for Accountancy professionals were selected for the study sample. They were classified according to the proposed program contents, the test questions by the Center for Selection and Event Promotion (Cespe, between 2000 and 2009. In conclusion, the most frequent required Public Accounting areas are contents related to Public Equity and Budget. The results demonstrate that the CFC’s suggested content is in line with the knowledge required from candidates for public functions.

  2. A simple program to reduce the stress associated with NRC nuclear operator examinations

    International Nuclear Information System (INIS)

    Sajwau, T.; Chardos, S.

    1988-01-01

    The NRC license for nuclear reactor operators requires periodic written examinations to demonstrate ongoing technical competency. Poor performance raises a competency question and can affect the individuals' careers. Accordingly, the exams can be highly stressful events. Stress has been demonstrated to affect memory, perception, other cognitive attitudes, and test performance. The phenomenon of test anxiety is well known. Instead of a generic, broadly focused stress management approach, a sharply focused, two-part program was developed for TVA operators scheduled to take the NRC examination. The first part was presented early in preparatory training, and the second part was given just prior to the examination. The first part consisted of a simple model of stress found in exams, early warning signs of test stress, and tactics of stress management that were practical to use during the NRC exam itself

  3. A review of nondestructive examination technology for polyethylene pipe in nuclear power plant

    Science.gov (United States)

    Zheng, Jinyang; Zhang, Yue; Hou, Dongsheng; Qin, Yinkang; Guo, Weican; Zhang, Chuck; Shi, Jianfeng

    2018-05-01

    Polyethylene (PE) pipe, particularly high-density polyethylene (HDPE) pipe, has been successfully utilized to transport cooling water for both non-safety- and safety-related applications in nuclear power plant (NPP). Though ASME Code Case N755, which is the first code case related to NPP HDPE pipe, requires a thorough nondestructive examination (NDE) of HDPE joints. However, no executable regulations presently exist because of the lack of a feasible NDE technique for HDPE pipe in NPP. This work presents a review of current developments in NDE technology for both HDPE pipe in NPP with a diameter of less than 400 mm and that of a larger size. For the former category, phased array ultrasonic technique is proven effective for inspecting typical defects in HDPE pipe, and is thus used in Chinese national standards GB/T 29460 and GB/T 29461. A defect-recognition technique is developed based on pattern recognition, and a safety assessment principle is summarized from the database of destructive testing. On the other hand, recent research and practical studies reveal that in current ultrasonic-inspection technology, the absence of effective ultrasonic inspection for large size was lack of consideration of the viscoelasticity effect of PE on acoustic wave propagation in current ultrasonic inspection technology. Furthermore, main technical problems were analyzed in the paper to achieve an effective ultrasonic test method in accordance to the safety and efficiency requirements of related regulations and standards. Finally, the development trend and challenges of NDE test technology for HDPE in NPP are discussed.

  4. The refinement of a cultural standardized patient examination for a general surgery residency program.

    Science.gov (United States)

    Chun, Maria B J; Deptula, Peter; Morihara, Sarah; Jackson, David S

    2014-01-01

    Recent articles have documented the importance of cultural competency in surgery. Surgical residency programs have used the Objective Structured Clinical Examinations or cultural standardized patient examinations as a training tool. Past studies evaluating cultural competency have noted the importance of including an observational (control) arm, which would allow for a more objective assessment of a resident's competency in this area. The purpose of our article is to present the results of a follow-up study to a pilot cultural standardized patient examination for surgery residents. All first-year surgery residents were required to participate in the videotaped cultural SP examination as part of the general surgery residency curriculum. Two measures were used to assess resident performance. On the day of the examination, the Cross-Cultural Care Survey was administered. The examination was assessed by the residents themselves, faculty observers, and standardized patients, using a written checklist that was developed to evaluate residents on all 6 Accreditation Council for Graduate Medical Education competencies. The current study includes 20 first-year surgery residents from academic years 2011 to 2012 and 2012 to 2013. The examination of pretest differences in groups found that students born outside of the United States had significantly higher scores on attitude (t = -2.68, df = 18, p = 0.02), but no statistically significant differences were found in skillfulness or knowledge or in the overall rating scale. For the overall rating scale, change from pretest to posttest was statistically significant (t = -2.25, df = 18, p = 0.04). Further analysis revealed that students who were born in the United States demonstrated a significant increase in ratings (t = -3.08, df = 10, p = 0.01) whereas students who were not born in the United States showed little change (t = -0.35, df = 7, p = 0.74). These results show that the means in attitude scales changed little for all

  5. Integrated plant safety assessment. Systematic evaluation program, Big Rock Point Plant (Docket No. 50-155). Final report

    International Nuclear Information System (INIS)

    1984-05-01

    The Systematic Evaluation Program was initiated in February 1977 by the U.S. Nuclear Regulatory Commission to review the designs of older operating nuclear reactor plants to reconfirm and document their safety. The review provides (1) an assessment of how these plants compare with current licensing safety requirements relating to selected issues, (2) a basis for deciding how these differences should be resolved in an integrated plant review, and (3) a documented evaluation of plant safety when the supplement to the Final Integrated Plant Safety Assessment Report has been issued. This report documents the review of the Big Rock Point Plant, which is one of ten plants reviewed under Phase II of this program. This report indicates how 137 topics selected for review under Phase I of the program were addressed. It also addresses a majority of the pending licensing actions for Big Rock Point, which include TMI Action Plan requirements and implementation criteria for resolved generic issues. Equipment and procedural changes have been identified as a result of the review

  6. ‘I used to be ashamed’. The influence of an educational program on tribal and non-tribal children's knowledge and valuation of wild food plants

    NARCIS (Netherlands)

    Cruz Garcia, G.S.; Howard, P.L.

    2013-01-01

    This study examines the influence of an extra-curricular educational program on children's knowledge and cultural valuation of wild food plants, which are an important component of their diets. This program aims to reinforce children's traditional knowledge and values around biological resources in

  7. Plant life extension program for Indian PHWR power plants - Actual experience and future plans

    International Nuclear Information System (INIS)

    Sharma, M.B.; Ghoshal, B.; Shirolkar, K.M.; Ahmad, S.N.

    2002-01-01

    Full text: The Nuclear Power Corporation of India Limited (NPCIL) is responsible for design, construction and operation for all nuclear power plants in India. Currently, it has fourteen (14) reactor units under operation and another eight units are under various stages of planning and construction. India has adopted Pressurised Heavy Water Reactors (PHWRs) for the initial phase of its nuclear power program. In the earlier PHWRs zircaloy-2 has been used as coolant tube material. Subsequent studies and experience have shown their life to be considerably lower (about 10 full power years) than originally estimated. This meant that reactors at Rajasthan - 1 and 2 Madras - 1 and 2 Narora - 1 and 2 and Kakrapara-1 would require en-masse coolant channel replacement at least once in their lifetime. Subsequent reactors from Kakrapara-2 onwards would not need this en-masse coolant channel replacement as the coolant tube material has been upgraded to Zr 2.5% Nb. En-masse coolant channel replacement and other life extension work have been carried out successfully in Rajasthan Unit-2 (RAPS-2). Madras unit-2 (MAPS-2) has been shutdown since January 2002 and preparatory work for en-masse coolant channel replacement and plant life extension is in progress. This paper discusses in brief the experience of RAPS-2 in carrying out the above jobs as well as the strategies being adopted for MAPS-2. Since the coolant channel replacement work requires a plant outage of about 18 months, this opportunity is used to extend life of existing systems as well as upgradation work. This life extension and upgradation program is based on the results of detailed in service inspection, evaluation of performance of critical equipment, obsolescence and other strategic reasons. This paper discusses in detail some of the major areas of work done, for example introduction of supplementary control room, process control, computer based plant information and event analysis systems, provision of enhanced

  8. A Comprehensive Examination of the Influence of State Tobacco Control Programs and Policies on Youth Smoking

    Science.gov (United States)

    Loomis, Brett R.; Han, Beth; Gfroerer, Joe; Kuiper, Nicole; Couzens, G. Lance; Dube, Shanta; Caraballo, Ralph S.

    2013-01-01

    Objectives. We examined the influence of tobacco control policies (tobacco control program expenditures, smoke-free air laws, youth access law compliance, and cigarette prices) on youth smoking outcomes (smoking susceptibility, past-year initiation, current smoking, and established smoking). Methods. We combined data from the 2002 to 2008 National Surveys on Drug Use and Health with state and municipality population data from the US Census Bureau to assess the associations between state tobacco control policy variables and youth smoking outcomes, focusing on youths aged 12 to 17 years. We also examined the influence of policy variables on youth access when these variables were held at 2002 levels. Results. Per capita funding for state tobacco control programs was negatively associated with all 4 smoking outcomes. Smoke-free air laws were negatively associated with all outcomes except past-year initiation, and cigarette prices were associated only with current smoking. We found no association between these outcomes and retailer compliance with youth access laws. Conclusions. Smoke-free air laws and state tobacco control programs are effective strategies for curbing youth smoking. PMID:23327252

  9. A preliminary examination of the economics of cogeneration with fusion plants

    International Nuclear Information System (INIS)

    Hazelrigg, G.A.; Coleman, D.E.

    1983-01-01

    Cogeneration, the process of using reject heat from electric energy generation plants, offers substantial savings in energy consumption and thus is likely to see increased implementation, especially in the form of district heating, over the next few decades. The use of fusion plants for cogeneration offers added advantages of potentially low marginal costs and reduced siting restrictions compared to nuclear and coal plants, and freedom from use of limited fossil fuels. Fusion can thus provide increased economic incentive to the implementation of cogeneration systems. Conversely, cogeneration improves the economics of fusion and thus provides both added incentive for its development and reduced economic requirements on commercial fusion technologies

  10. Simulators in the training program for nuclear power plants

    International Nuclear Information System (INIS)

    Grimm, E.

    1988-01-01

    The principle simulator of the reactor school of the Paul Scherrer Institute is described. A compact simulator at the nuclear power plant Beznau is used for beginners as well as for refresher courses. Full simulator training cannot be taken in Switzerland. The Swiss nuclear power plants take advantage of the services of foreign nuclear power plants or training centers. The role of the instructor is discussed

  11. Examining the Factors Associated with Paid Employment of Clients Enrolled in First Episode of Psychosis Programs

    Directory of Open Access Journals (Sweden)

    Carolyn S. Dewa

    2012-01-01

    Full Text Available Schizophrenia is one of the most debilitating mental disorders. For a significant portion of individuals who suffer from this disorder, onset occurs in young adulthood, arresting important social and educational development that is necessary for future successful labor force participation. The purpose of this paper is to contribute to the literature about clients enrolled in first episode psychosis programs and psychosocial outcomes by examining the factors associated with paid employment among young adults who have experienced their first psychotic episodes. In this paper, we consider the association of socioeconomic factors to employment. Our results suggest that in addition to treatment, socioeconomic factors such as receipt of public disability benefits and educational attainment are associated with employment status. These results can help to inform future directions for the enhancement of psychosocial programs in FEP models to promote paid employment.

  12. Technical methods for a risk-informed, performance-based fire protection program at nuclear power plants

    International Nuclear Information System (INIS)

    Dey, M.K.

    1998-01-01

    This paper presents a technical review and examination of technical methods that are available for developing a risk-informed, performance-based fire protection program at a nuclear plant. The technical methods include ''engineering tools'' for examining the fire dynamics of fire protection problems, reliability techniques for establishing an optimal fire protection surveillance program, fire computer codes for analyzing important fire protection safety parameters, and risk-informed approaches that can range from drawing qualitative insights from risk information to quantifying the risk impact of alternative fire protection approaches. Based on this technical review and examination, it is concluded that methods for modeling fires, and reliability and fire PRA analyses are currently available to support the initial implementation of simple risk-informed, performance-based approaches in fire protection programs. (author)

  13. Technical methods for a risk-informed, performance-based fire protection program at nuclear power plants

    International Nuclear Information System (INIS)

    Dey, M.K.

    2000-01-01

    This paper presents a technical review and examination of technical methods that are available for developing a risk-informed, performance-based fire protection program at a nuclear plant. The technical methods include 'engineering tools' for examining the fire dynamics of fire protection problems, reliability techniques for establishing an optimal fire protection surveillance program, fire computer codes for analyzing important fire protection safety parameters, and risk-informed approaches that can range from drawing qualitative insights from risk information to quantifying the risk impact of alternative fire protection approaches. Based on this technical review and examination, it is concluded that methods for modeling fires, and reliability and fire probabilistic risk analyses (PRA) are currently available to support the initial implementation of simple risk-informed, performance-based approaches in fire protection programs. (orig.) [de

  14. An Examination of the Plastid DNA of Hypohaploid Nicotiana plumbaginifolia Plants

    Science.gov (United States)

    Cannon, Gordon C.; Van, K. Tran Thanh; Heinhorst, Sabine; Trinh, T. H.; Weissbach, Arthur

    1989-01-01

    DNA was extracted from different morphological types of hypohaploid Nicotiana plumbaginifolia plants. The cellular levels of chloroplast DNA (expressed as percent of total DNA) were found to be approximately two- to threefold higher in two albino hypohaploids than in a green hypohaploid. The level of chloroplast DNA in the green hypohaploid was not significantly different from either in vitro or in vivo grown haploid N. plumbaginifolia plants. Molecular hybridization with DNA probes for the large subunit of ribulose bisphosphate carboxylase from spinach and with Pvull fragments representing the entire Nicotiana tabacum chloroplast genome revealed no gross qualitative differences in the chloroplast DNAs of hypohaploid plants. Based on these observations we have concluded that the lack of chloroplast function observed in the albino forms of hypohaploid N. plumbaginifolia plants is not due to changes in the chloroplast genome. Images Figure 1 Figure 2 PMID:16666781

  15. Using Mass Spectroscopy to Examine Wetland Carbon Flow from Plants to Methane

    Science.gov (United States)

    Waldo, N.; Tfaily, M. M.; Moran, J.; Hu, D.; Cliff, J. B.; Gough, H. L.; Chistoserdova, L.; Beck, D.; Neumann, R. B.

    2017-12-01

    In the anoxic soil of wetlands, microbes produce methane (CH4), a greenhouse gas. Prior studies have documented an increase in CH4 emissions as plant productivity increases, likely due to plants releasing more labile organic carbon from roots. But in the field, it is difficult to separate changes in plant productivity and root carbon exudation from other seasonal changes that can affect methane emissions, e.g. temperature. Clarifying the role that root exudation plays in fueling methane production is important because increasing atmospheric temperatures and CO2 levels are projected to increase plant productivity and exudation. To advance understanding of climate-methane feedbacks, this study tracked the flow of carbon from plants into the wetland rhizosphere as plant productivity increased in controlled laboratory conditions. We grew Carex aquatilis, a wetland sedge, in peat-filled rootboxes. Both early and late during the plant growth cycle, we exposed plants to headspace 13CO2, which the plants fixed. Some of this labeled carbon was exuded by the roots and used by rhizosphere microbes. We tracked the isotope ratio of emitted CH4 to establish the time required for plant-released carbon to fuel methanogenesis, and to determine the relative contribution of plant-derived carbon to total CH4 emission. We destructively harvested root and rhizosphere samples from various locations that we characterized by isotope ratio mass spectrometry (MS) to determine isotopic enrichment and therefore relative abundance of root exudates. We analyzed additional aliquots of rhizosphere soil by Fourier transform ion cyclotron resonance MS to track chemical changes in soil carbon as root exudates were converted into methane. To advance mechanistic understanding of the synergistic and competitive microbial interactions that affect methane dynamics in the wetland rhizosphere, we used fluorescence in-situ hybridization to visualize microbial community composition and spatial associations

  16. Role of Measurement of the Maximum Intimal-Medial Thickness in the Brain Health Examination Program

    OpenAIRE

    上山, 憲司; 中川原, 譲二; 武田, 利兵衛; 中村, 博彦

    2005-01-01

    The maximum intimal-medial thickness (Max-IMT) of the carotid artery wall (Max-IMT) was measured by ultrasonography in 1,932 people checked in the brain health examination program in our hospital. We studied relationship Max-IMT and age, systolic blood pressure, presence of asymptomatic cerebral infarction. Five hundreds seventy-two people (29.9%) had atherosclerotic thickness of Max-IMT that was more than 1.1 mm. Normal Max-IMT that less than 1.0 mm was observed in 1,360 people (70.1%). More...

  17. Cost-Effectiveness of Elderly Health Examination Program: The Example of Hypertension Screening

    Directory of Open Access Journals (Sweden)

    Bing-Hwa Deng

    2007-01-01

    Full Text Available The National Health Insurance (NHI and social welfare agencies have implemented the Elderly Health Examination Program (EHEP for years. No study has ever attempted to evaluate whether this program is cost-effective. The purposes of this study were, firstly, to understand the prevalence and incidence rates of hypertension and, secondly, to estimate the cost and effectiveness of the EHEP, focusing on hypertension screening. The data sources were: (1 hypertension and clinical information derived from the 1996 and 1997 EHEP, which was used to generate prevalence and incidence rates of hypertension; and (2 claim data of the NHI that included treatment costs of stroke patients (in-and outpatients. Hypothetical models were used to evaluate the cost-effectiveness of the hypertension screening program in various conditions. Sensitivity analysis was also employed to evaluate the effect of each estimation indicator on the cost and effectiveness of the hypertension screening program. A total of 28.3% of the elderly population in Kaohsiung (25,174 of 88,812 participated in the 1996 EHEP; 14,915 of them participated in the following 1997 EHEP, with a retention rate of 59.3%. Criteria from the Sixth Report of the Joint National Committee on Detection, Evaluation, and Treatment of High Blood Pressure (JNC VI (systolic blood pressure/diastolic blood pressure ≥ 160/95mmHg or taking antihypertensive drugs were used; we found that prevalence and incidence rates of hypertension were 24.6% and 6.6%, respectively. Hypertension rates are increasing in the aging process as shown in both prevalence and incidence models. In comparison with non-participants, the prevalence model indicates that each hypertension patient who had attended the EHEP not only saved NT$34,570–34,890 in medical and associated costs, but also increased their lifespan by 128 days. The present findings suggest that the EHEP is a cost-effective program with health and social welfare policy

  18. An examination of stress, coping, and adaptation in nurses in a recovery and monitoring program.

    Science.gov (United States)

    Bowen, Marie Katherine; Taylor, Kathleen P; Marcus-Aiyeku, Ulanda; Krause-Parello, Cheryl A

    2012-10-01

    Addiction rates in nurses are higher than in the general population. The relationship between stress, coping, and adaptation in nurses (N = 82) enrolled in a recovery and monitoring program in the state of New Jersey was examined. Social support, a variable tested as a mediator of this relationship, was also examined. Participants completed the Perceived Stress Scale, Multidimensional Scale of Perceived Social Support, and Psychological General Well-Being Index. Negative relationships were found between stress and social support and stress and well-being, and a positive relationship was found between social support and well-being (all ps prevent potential untoward consequences. Ultimately, methods to strengthen social support and social networks will enhance the probability of sustained recovery, relapse prevention, and safe reentry into nursing practice. Implications for behavioral health providers and health care practitioners are discussed.

  19. The IEAGHG Power Plant Assessment Program (PPAP). Development and testing June 2002-October 2005

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-12-15

    The Power Plant Assessment Program (PPAP) is an Excel based program which allows alternative CO{sub 2} capture technologies for centralised power generation to be compared using multi-criteria analysis. This report outlines recent development work on the program and the results obtained from evaluating a range of novel capture processes with it.

  20. Handbook for nuclear power plant self-assessment programs. Final report, July 1991

    International Nuclear Information System (INIS)

    1991-07-01

    EPRI has prepared this handbook to help utilities with their Self-Assessment Programs at nuclear power plants. Self-assessments are independent reviews performed by nuclear plant utilities to identify trends in operational activities that are important to safety, and to assess the impact of these trends on plant safety. Activities performed as self-assessments include reviews and evaluations of plant performance and abnormal events, technical evaluations of plant activities to identify potential problem areas, and reviews of other sources of plant design and operating experience for applicability to safety. This handbook is based on information obtained from utilities and includes examples of activities and methods that have proven effective. The handbook includes a summary of NRC requirements, guidelines for self-assessment program planning, descriptions and examples of investigative techniques, and key references that can be consulted for additional information. It can serve as a training guide for plant staff members who are assigned to self-assessment activities. (author)

  1. Status of IGA in Japanese plants and results of S/G pulled tube examinations

    International Nuclear Information System (INIS)

    Takamatsu, H.

    1986-01-01

    Currently there are 14 operating PWRs in Japan. Five of the plants have been affected by the intergranular stress corrosion cracking (IGSCC). The experience of the 14 plants with regard to tube plugging is summarized. The five affected plants are: Mihama 2, Takahama 1, Takahama 2, Ohi 1 and Genkai 1. The first two plants experienced IGSCC in the tube sheet crevice region (55 and 124 tubes plugged) and a slight problem with IGSCC in tube support plate crevices (13 and 8 tubes plugged). The other three plants have experienced extensive IGSCC in their tube support plate crevices (1330, 773 and 667 tubes plugged, respectively). The Japanese consider that their IGSCC (IGA) problem is caused by a combination material and environmental factors. All three factors must be present for attack to take place. If the two environmental factors can be controlled, then the attack will stop. The preventive measures being employed by the Japanese are given. These include: prevention of free caustic (i.e., sludge lancing, crevice cleaning, boron injection and improvement in water treatment) and maintenance of deoxidation environment (i.e., hydrazine soaking before operation and enriching the concentration of hydrazine in the secondary water)

  2. Qualification of quality assurance program audit personnel for nuclear power plants - August 1980

    International Nuclear Information System (INIS)

    Anon.

    1981-01-01

    Appendix B, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants, to 10 CFR Part 50, Domestic Licensing of Production and Utilization Facilities, establishes overall quality assurance requirements for the design, construction, and operation of safety-related structures, and components of nuclear power plants. Criterion XVIII, Audits, of Appendix B establishes requirements for conducting audits of the quality assurance program. This guide describes a method acceptable to the NRC staff for complying with the Commission's regulations with regard to qualification of quality assurance program audit personnel for nuclear power plants

  3. 46 CFR 71.50-27 - Alternative Hull Examination (AHE) program options: Divers or underwater remotely operated...

    Science.gov (United States)

    2010-10-01

    ... 46 Shipping 3 2010-10-01 2010-10-01 false Alternative Hull Examination (AHE) program options...-27 Alternative Hull Examination (AHE) program options: Divers or underwater remotely operated vehicle... operations; (2) Provide permanent hull markings, a temporary grid system of wires or cables spaced not more...

  4. Xylella fastidiosa: an examination of a re-emerging plant pathogen.

    Science.gov (United States)

    Rapicavoli, Jeannette; Ingel, Brian; Blanco-Ulate, Barbara; Cantu, Dario; Roper, Caroline

    2018-04-01

    Xylella fastidiosa is a Gram-negative bacterial plant pathogen with an extremely wide host range. This species has recently been resolved into subspecies that correlate with host specificity. This review focuses on the status of X. fastidiosa pathogenic associations in plant hosts in which the bacterium is either endemic or has been recently introduced. Plant diseases associated with X. fastidiosa have been documented for over a century, and much about what is known in the context of host-pathogen interactions is based on these hosts, such as grape and citrus, in which this pathogen has been well described. Recent attention has focused on newly emerging X. fastidiosa diseases, such as in olives. Bacteria; Gammaproteobacteria; family Xanthomonadaceae; genus Xylella; species fastidiosa. Gram-negative rod (0.25-0.35 × 0.9-3.5 μm), non-flagellate, motile via Type IV pili-mediated twitching, fastidious. Xylella fastidiosa has a broad host range that includes ornamental, ecological and agricultural plants belonging to over 300 different species in 63 different families. To date, X. fastidiosa has been found to be pathogenic in over 100 plant species. In addition, it can establish non-symptomatic associations with many plants as a commensal endophyte. Here, we list the four distinct subspecies of X. fastidiosa and some of the agriculturally relevant diseases caused by them: X. fastidiosa ssp. fastidiosa causes Pierce's disease (PD) of grapevine (Vitis vinifera); X. fastidiosa ssp. multiplex causes almond leaf scorch (ALS) and diseases on other nut and shade tree crops; X. fastidiosa ssp. pauca causes citrus variegated chlorosis (CVC) (Citrus spp.), coffee leaf scorch and olive quick decline syndrome (OQDS) (Olea europaea); X. fastidiosa ssp. sandyi causes oleander leaf scorch (OLS) (Nerium oleander). Significant host specificity seemingly exists for some of the subspecies, although this could be a result of technical biases based on the limited number of

  5. Barriers and enabling factors for work-site physical activity programs: a qualitative examination.

    Science.gov (United States)

    Fletcher, Gena M; Behrens, Timothyh K; Domina, Lorie

    2008-05-01

    Work sites offer a productive setting for physical activity (PA) promoting interventions. Still, PA participation remains low. Thus, the purpose of this study was to examine the reasoning behind commonly reported barriers and enabling factors to participation in PA programs in a work-site setting. Employees from a large city government were recruited to participate in focus groups, stratified by white- and blue-collar occupations. Responses from open-ended questions about factors influencing participation in PA programs were audio recorded and transcribed verbatim. Resulting data were analyzed with open and axial coding. The sample consisted of 60 employees composing 9 focus groups. Although time was the most common barrier between both groups, white-collars workers responded that scheduling and work conflicts were the most common barrier concerning time. Blue-collar workers indicated shift work as their most common barrier. In addition, health was a significant enabling factor for both occupational categories. White-collar workers were much more concerned with appearances and were more highly motivated by weight loss and the hopefulness of quick results than were blue-collar workers. These findings are important in the understanding of PA as it relates to the reasoning behind participation in work-site programs in regard to occupational status.

  6. An Examination of an Iconic Trap-Neuter-Return Program: The Newburyport, Massachusetts Case Study

    Directory of Open Access Journals (Sweden)

    Daniel D. Spehar

    2017-10-01

    Full Text Available The use of trap-neuter-return (TNR as a humane alternative to the lethal management of free-roaming cats has been on the rise for several decades in the United States; however a relative paucity of data from TNR programs exists. An iconic community-wide TNR effort; initiated in 1992 and renowned for having eliminated hundreds of free-roaming cats from the Newburyport; Massachusetts waterfront; is cited repeatedly; yet few details appear in the literature. Although the presence of feline population data was quite limited; a detailed narrative emerged from an examination of contemporaneous reports; extant TNR program documents; and stakeholder testimony. Available evidence indicates that an estimated 300 free-roaming cats were essentially unmanaged prior to the commencement of the TNR program; a quick reduction of up to one-third of the cats on the waterfront was attributed to the adoption of sociable cats and kittens; the elimination of the remaining population; over a 17-year period; was ascribed to attrition. These findings illuminate the potential effectiveness of TNR as a management practice; as well as call attention to the need for broad adoption of systematic data collection and assessment protocols.

  7. Examining the Effect of Social Values Education Program Being Applied to Nursery School Students upon Acquiring Social Skills

    Science.gov (United States)

    Sapsaglam, Özkan; Ömeroglu, Esra

    2016-01-01

    This study was conducted in an attempt to develop Social Values Education Program aimed at nursery school students and examine the effect of Social Values Education Program upon the social skill acquisition of nursery school students. The effect of the education program that was developed within the scope of the study upon the social skill…

  8. The Devil Is in the Details: Examining the Evidence for "Proven" School-Based Drug Abuse Prevention Programs

    Science.gov (United States)

    Gandhi, Allison Gruner; Murphy-Graham, Erin; Petrosino, Anthony; Chrismer, Sara Schwartz; Weiss, Carol H.

    2007-01-01

    In an effort to promote evidence-based practice, government officials, researchers, and program developers have developed lists of model programs in the prevention field. This article reviews the evidence used by seven best-practice lists to select five model prevention programs. The authors' examination of this research raises questions about the…

  9. Los Alamos Nuclear Plant Analyzer: an interactive power-plant simulation program

    International Nuclear Information System (INIS)

    Steinke, R.; Booker, C.; Giguere, P.; Liles, D.R.; Mahaffy, J.H.; Turner, M.R.

    1984-01-01

    The Nuclear Plant Analyzer (NPA) is a computer-software interface for executing the TRAC or RELAP5 power-plant systems codes. The NPA is designed to use advanced supercomputers, long-distance data communications, and a remote workstation terminal with interactive computer graphics to analyze power-plant thermal-hydraulic behavior. The NPA interface simplifies the running of these codes through automated procedures and dialog interaction. User understanding of simulated-plant behavior is enhanced through graphics displays of calculational results. These results are displayed concurrently with the calculation. The user has the capability to override the plant's modeled control system with hardware-adjustment commands. This gives the NPA the utility of a simulator, and at the same time, the accuracy of an advanced, best-estimate, power-plant systems code for plant operation and safety analysis

  10. Nuclear Plant Analyzer: an interactive TRAC/RELAP Power-Plant Simulation Program

    International Nuclear Information System (INIS)

    Steinke, R.; Booker, C.; Giguere, P.; Liles, D.; Mahaffy, J.; Turner, M.; Wiley, R.

    1984-01-01

    The Nuclear Plant Analyzer (NPA) is a computer-software interface for executing the TRAC or RELAP5 power-plant systems codes. The NPA is designed to use advanced supercomputers, long-distance data communications, and a remote workstation terminal with interactive computer graphics to analyze power-plant thermal-hydraulic behavior. The NPA interface simplifies the running of these codes through automated procedures and dialog interaction. User understanding of simulated-plant behavior is enhanced through graphics displays of calculational results. These results are displayed concurrently with the calculation. The user has the capability to override the plant's modeled control system with hardware adjustment commands. This gives the NPA the utility of a simulator, and at the same time, the accuracy of an advanced, best-estimate, power-plant systems code for plant operation and safety analysis

  11. Hanford Waste Vitrification Plant quality assurance program description: Overview and applications

    International Nuclear Information System (INIS)

    Caplinger, W.H.

    1990-12-01

    This document describes the Hanford Waste Vitrification Plant Project Quality Assurance Program. This program is being implemented to ensure the acceptability of high-level radioactive canistered waste forms produced by the Hanford Waste Vitrification Plant for disposal in a licensed federal repository. The Hanford Waste Vitrification Plant Quality Assurance Program is comprised of this Quality Assurance Program Description as well as the associated contractors' quality assurance programs. The objective of this Quality Assurance Program Description is to provide the Hanford Waste Vitrification Plant Project participants with guidance and direction for program implementation while satisfying the US Department of Energy Office of Civilian Radioactive Waste Management needs in repository licensing activities with regard to canistered waste forms. To accomplish this objective, this description will be prepared in three parts: Part 1 - Overview and applications document; Part 2 - Development and qualification of the canistered waste form; Part 3 - Production of canistered waste forms. Part 1 describes the background, strategy, application, and content of the Hanford Waste Vitrification Plant Quality Assurance Program. This Quality Assurance Program Description, when complete, is designed to provide a level of confidence in the integrity of the canistered waste forms. 8 refs

  12. Development priorities for non-destructive examination of concrete structures in nuclear plant

    International Nuclear Information System (INIS)

    1998-01-01

    The objective of this report is to provide a basis for assessing development priorities for NDE of safety related concrete structures in nuclear plants, taking account of both the benefit and the cost of potential developments in NDE techniques. An OECD/NEA Workshop which considered the requirements for NDE of safety related concrete structures was held in the UK on 12 November 97. NDE techniques have the potential to satisfy at least some of the needs of the nuclear industry. NDE techniques have been used successfully on a variety of reinforced and post-tensioned concrete structures, notably highway and reservoir structures. However, there is limited experience of their use to evaluate typical nuclear safety related structures having thick sections, steel liners or access to one side only. There is a general lack of confidence in the techniques because there is very little independent advice on their applicability, capability, accuracy and reliability. The information obtained by techniques such as RADAR, ultrasonics, stress wave and radiography appears qualitative rather than quantitative and there is concern that NDE procedures lack the necessary qualification to permit their use on safety critical structures. There is no authoritative international guidance or standard for NDE of concrete structures. NDE of concrete structures is often based upon equipment developed for other materials and technologies, eg. examination of steel, evaluation of ground conditions. Other industries are developing equipment specifically for civil engineering applications and at the recent OECD workshop a number of relevant national and European programmes were identified. The nuclear industry maintain its awareness of developments and should seek to influence the development of equipment. The quantification of the capabilities of NDE techniques is seen as a priority area for development. The provision of authoritative documentation in the form of reports and Standards is desirable

  13. Examining the effectiveness of micro-enterprise development programs in Malaysia

    Directory of Open Access Journals (Sweden)

    Noor Raihani Zainol

    2017-06-01

    Full Text Available Previous studies on socioeconomic development have examined the effect of development initiatives (i.e., access to finance and training on several socioeconomic indicators (i.e., income, empowerment, asset, quality of life, employment. These studies have focused mostly on the outcomes of specific types of programs offered by specific development organizations. This study however focuses on informal women micro-entrepreneurs’ participation in various development programs available to them and their influence on entrepreneurial competencies, human capital development, competitive advantages, economic vulnerability, supportive environment, and performance of micro-enterprises. This cross-sectional study adopted the purposive random sampling method and collected data from 384 informal women entrepreneurs from the local markets in different districts of Kelantan, Malaysia. The findings show that the development program participants have relatively higher levels of entrepreneurial competencies, human capital development, and higher levels of enterprise performance compared to non-participants. It is also noted that the level of economic vulnerability is relatively low among participants compared to non-participants. However, these findings contradict most of the earlier studies that show a significant positive impact of micro-credit on socio-economic wellbeing, as the difference in entrepreneurial competencies, human capital development, economic vulnerability, and performance of micro-enterprises among participants and non-participants in this study is not statistically significant. However, findings reported significantly higher levels of competitive advantages, and better supportive environment among the participants compared to the non-participants. Development organizations should therefore focus on expanding their outreach to spread the positive effects of their development programs towards uplifting the economic condition of low and middle

  14. Initial examination of the effects of overtime and shift scheduling on nuclear power plant safety performance

    International Nuclear Information System (INIS)

    Baker, K.; Olson, J.; Montgomery, J.

    1990-01-01

    The research reported here uses currently available data to begin to document overtime and shift scheduling practices in the nuclear industry and assess their safety consequences. Overtime and the 12-hour shift schedule have been found to affect employee fatigue and human error in other industries but neither of these practices have been systematically researched within the nuclear industry. Overtime has long been a standard practice in the nuclear industry and, recently, several licensees have adopted a 12-hour shift schedule for control room operations crews. Although 12-hour shifts have certain benefits for the employer and employee alike (e.g., can require fewer total employees and provide longer periods of time-off) there is some concern that the 12-hour shift may produce greater employee fatigue. Moreover, the 12-hour shift may exacerbate the negative effect of overtime. The potential effect of human error in the nuclear industry for the health and safety of both nuclear power plant workers and the general public requires that these practices be assessed. Data on overtime practices was obtained from the International Brotherhood of Electrical Workers (IBEW) for plants covered by the bargaining unit - approximately 63% of the total number of operating plants. Information on operator shift schedule was collected from all operating plants in 1987 by the NRC. The research produced fairly strong evidence that greater amounts of overtime worked by operators is associated with a greater number of operational problems

  15. Spent fuel characterization program in Jose Cabrera nuclear power plant

    International Nuclear Information System (INIS)

    Lloret, M.; Canencia, R.; Blanco, J.; POMAR, C.

    2010-01-01

    Jose Cabrera Nuclear Power Plant (NPP) is a 14x14 PWR reactor built in 1964 in Spain (160 MWe). The commercial operation started in 1969 and finished in 2006. During year 2009, 377 fuel assemblies from cycles 11 to 29 have been stored in 12 containers HI-STORM 100, and positioned in an Interim Spent Fuel Storage Installation built near the NPP. The spent fuel characterization and classification is a critical and complex activity that could impact all the storage process. As every container has a number of positions for damaged fuel, the loading plans and the quantity of containers depends on the total fuels classified as damaged. The classification of the spent fuel in Jose Cabrera has been performed on the basis of the Interim Staff Guidance ISG-1 from USNRC, 'Damaged Fuel'. As the storage system should assure thermal limitations, criticality control, retrievability, confinement and shielding for radioactive protection, the criteria analyzed for every spent fuel have been the existence/non existence of fuel leaks; damage that could affect the criticality analysis (as missing fuel pins) and any situation that could affect the future retrievability, as defects on the top nozzle. The first classification was performed based upon existing core records. If there were no indication of operating leakers during the concerned cycles and the structural integrity was adequate, the fuel was classified as intact or undamaged. When operating records indicated a fuel leaker, an additional inspection by ultrasonic testing of all the fuel in the concerned cycle was performed to determine the fuel leakers. If the examination results indicated that the fuel has cladding cracks, it was classified as damaged fuel without considering if it was a gross breach or a hairline crack. Additionally, it was confirmed that the water chemistry specifications for spent fuel pool has been fulfilled. Finally, a visual inspection before dry cask storage was performed and foreign particles were

  16. Spent fuel characterization program in Jose Cabrera nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Lloret, M.; Canencia, R. [Product Engineering, Enusa Industrias Avanzadas S.A., Santiago Rusinol 12, 28040 Madrid (Spain); Blanco, J.; POMAR, C. [Direction of Nuclear Generation, Gas Natural SDG, Avda. San Luis 77, 28033 Madrid (Spain)

    2010-07-01

    Jose Cabrera Nuclear Power Plant (NPP) is a 14x14 PWR reactor built in 1964 in Spain (160 MWe). The commercial operation started in 1969 and finished in 2006. During year 2009, 377 fuel assemblies from cycles 11 to 29 have been stored in 12 containers HI-STORM 100, and positioned in an Interim Spent Fuel Storage Installation built near the NPP. The spent fuel characterization and classification is a critical and complex activity that could impact all the storage process. As every container has a number of positions for damaged fuel, the loading plans and the quantity of containers depends on the total fuels classified as damaged. The classification of the spent fuel in Jose Cabrera has been performed on the basis of the Interim Staff Guidance ISG-1 from USNRC, 'Damaged Fuel'. As the storage system should assure thermal limitations, criticality control, retrievability, confinement and shielding for radioactive protection, the criteria analyzed for every spent fuel have been the existence/non existence of fuel leaks; damage that could affect the criticality analysis (as missing fuel pins) and any situation that could affect the future retrievability, as defects on the top nozzle. The first classification was performed based upon existing core records. If there were no indication of operating leakers during the concerned cycles and the structural integrity was adequate, the fuel was classified as intact or undamaged. When operating records indicated a fuel leaker, an additional inspection by ultrasonic testing of all the fuel in the concerned cycle was performed to determine the fuel leakers. If the examination results indicated that the fuel has cladding cracks, it was classified as damaged fuel without considering if it was a gross breach or a hairline crack. Additionally, it was confirmed that the water chemistry specifications for spent fuel pool has been fulfilled. Finally, a visual inspection before dry cask storage was performed and foreign particles

  17. Angra nuclear plant - environmental control program; Usina Nuclear de Angra: programa de controle ambiental

    Energy Technology Data Exchange (ETDEWEB)

    Kircher, E; Cruz, E.S. da [FURNAS, Rio de Janeiro, RJ (Brazil)

    1990-12-31

    The pre-operational studies, that were elaborated before the beginning of Angra I Power Plant operation, are described in particular the environmental radiological safety area till the fuel loading in the core reactor. Several aspects are included, as socio-economic survey, seismological analysis, Meteorological Program, marine biology, water cooling system, exposure measures of natural radiation, marine sediments characterization in the effluent dispersion area and Environmental Radiological Monitoring Program. The main environmental programs developed for the operational phase of the Angra I Plant are also presented, citing some considerations about the Meteorological Program, Marine Biology Control Program, Temperature and Chlorine Control in Piraquara de Fora Bay, Radiological Environmental Monitoring Program, Sanitary Effluent Control Program and Radiological Emergency Program. (C.G.C.). 2 refs.

  18. Examining relational empowerment for elementary school students in a yPAR program.

    Science.gov (United States)

    Langhout, Regina Day; Collins, Charles; Ellison, Erin Rose

    2014-06-01

    This paper joins relational empowerment, youth empowerment, and Bridging Multiple Worlds frameworks to examine forms of relational empowerment for children in two intermediary institutions-school and a youth participatory action research after-school program (yPAR ASP). Participants were twelve children, most of whom were Latina/o and from im/migrant families, enrolled in a yPAR ASP for 2 years. A mixed-method approach was utilized; we analyzed children's interviews, self-defined goals, and their social networks to examine their experiences of relational empowerment. We conclude that children experienced each of the five relational empowerment factors-collaborative competence, bridging social divisions, facilitating others' empowerment, mobilizing networks, and passing on a legacy-in the yPAR ASP setting, and some factors in school. These experiences, however, were more pronounced in the yPAR ASP setting. Additionally, social network analyses revealed that a small but meaningful percentage of actors bridged worlds, especially home and family, but by year 2, also school and the yPAR ASP. Finally, most helpers for school-based goals came from school, but a sizable number came from family, friends, and home worlds, and by year 2, also came from the yPAR ASP. Implications range from theoretical to methodological development, including the use of social network analysis as a tool to descriptively examine relational power in context.

  19. Growing Plants and Scientists: Fostering Positive Attitudes toward Science among All Participants in an Afterschool Hydroponics Program

    Science.gov (United States)

    Patchen, Amie K.; Zhang, Lin; Barnett, Michael

    2017-06-01

    This study examines an out-of-school time program targeting elementary-aged youth from populations that are typically underrepresented in science fields (primarily African-American, Hispanic, and/or English Language Learner participants). The program aimed to foster positive attitudes toward science among youth by engaging them in growing plants hydroponically (in water without soil). Participants' attitudes toward science, including anxiety, desire, and self-concept, were examined through pre-post survey data ( n = 234) over the course of an afterschool program at three separate sites. Data showed that participants' anxiety decreased and desire increased for both male and female participants over the program. Self-concept increased for female participants at all three sites but did not change significantly for male participants. Participants' first language (English or Spanish) was not a factor in attitude outcomes. The primarily positive outcomes suggest that hydroponics can be a useful educational platform for engaging participants in garden-based programming year round, particularly for settings that do not have the physical space or climate to conduct outdoor gardening. Similarities in positive attitude outcomes at the three sites despite differences in format, implementation, and instructor background experience suggest that the program is resilient to variation in context. Understanding which aspects of the program facilitated positive outcomes in the varied contexts could be useful for the design of future programs.

  20. ESP and NOAH: computer programs for flood-risk analysis of nuclear power plants

    International Nuclear Information System (INIS)

    Wagner, D.P.; Montague, D.F.; Rooney, J.J.; Fussell, J.B.; Baker, L.S.

    1982-06-01

    This report describes a computer program package that aids in assessing the impact of floods on risk from nuclear power plants. The package consists of two distinct computer programs: ESP and NOAH. The ESP program improves the efficiency of a flood analysis by screening accident sequences and identifying accident sequences that are potentially significant contributors to risk in the event of a flood. Input to ESP includes accident sequences from an existing risk assessment and flood screening criteria. The NOAH program provides detailed qualitative analysis of the plant systems identified by ESP. NOAH performs a qualitative flood simulation of the fault tree

  1. Some contributions to the examination of composites from power plant wastes

    Directory of Open Access Journals (Sweden)

    Trifunović Prvoslav

    2015-01-01

    Full Text Available This paper describes an investigation into the possibilities of the use of all three types of solid power plant wastes: fly ash (FA, flue gas desulphurization gypsum (FGD gypsum and bottom ash (BA as components of composites for road construction. Two mixtures were made: 1. power plant wastes - Portland cement (PC and 2. power plant wastes - sand (S - Portland cement (PC. The mass ratio of components in these mixtures was: 1. FA - FGD gypsum - BA - PC = 2 : 1.5 : 5 : 1.5 and 2. FA- FGD gypsum-BA - S - PC= 2 : 1.5 : 4 : 1 : 1.5. For both mixtures, the compressive strength, the mineralogical composition, the water absorption and the resistance to freeze-thaw treatment were determined 7 and 28 days after preparation of samples (mixing with water. The obtained results showed that both mixtures could have potential to be used for sub-base layers in road construction and the second mixture (with natural aggregate-sand has advantage over the first mixture in terms of compressive strength, mineralogical composition, and resistance to freeze-thaw treatment.

  2. 46 CFR 115.620 - Description of the Alternative Hull Examination (AHE) Program for certain passenger vessels.

    Science.gov (United States)

    2010-10-01

    ... 46 Shipping 4 2010-10-01 2010-10-01 false Description of the Alternative Hull Examination (AHE... ACCOMMODATIONS FOR MORE THAN 49 PASSENGERS INSPECTION AND CERTIFICATION Hull and Tailshaft Examinations § 115.620 Description of the Alternative Hull Examination (AHE) Program for certain passenger vessels. The Alternative...

  3. Three Mile Island Startup program and its contributions to plant performance

    International Nuclear Information System (INIS)

    Brill, R.A.; Barton, J.J.

    1976-01-01

    The General Public Utilities Service Corporation Startup Organization provided a specialized group for startup testing, coordination, and management of the Three Mile Island Unit No. 1 nuclear power plant. This organization conducted an extensive test program which contributed to Three Mile Island's high first year plant availability

  4. Plant and Industry Experience. MAS-122. Waste Isolation Division (WID). Management and Supervisor Training (MAST) Program.

    Science.gov (United States)

    Westinghouse Electric Corp., Carlsbad, NM.

    This learning module, which is part of a management and supervisor training program for managers and supervisors employed at the Department of Energy's Waste Isolation Division, is designed to prepare trainees to use plant and industry experience to improve plant safety and reliability. The following topics are covered in the module's individual…

  5. Meteorological monitoring Program in the location to the Juragua Nuclear Power Plant

    International Nuclear Information System (INIS)

    Linares Gonzalez, M.E.; Ramos Biltres, E.O.; Prendes Alonso, M.

    1998-01-01

    The objective gives the work it is to present the meteorological Monitoring program in the Juragua nuclear power plant, which you makes according to the standards settled down by the OIEA, the standards give the World meteorological organization and the demands to the content and elaboration gives the Nuclear Power Plant security documents DTN-1.03.91

  6. Plant materials program. Progress report, June 1980-May 1981

    International Nuclear Information System (INIS)

    Childs, W.; Cubicciotti, D.; Fox, M.; Giannuzzi, A.; Gilman, J.; Jones, R.; McIlree, A.

    1981-11-01

    This is the first annual progress report of the Plant Materials Subprogram, which was organized in May 1980 to address corrosion-related materials problems in light water reactors. The first section of the report provides an overview of plant materials problems which have a high impact on plant availability. These include pipe and pressure vessel cracking, condenser leakage, turbine disc cracking, and steam generator tube denting and cracking. The status and goals of research and development work related to each of these problems are reviewed briefly. Subsequent report sections provide more detailed reviews of significant progress in the relevant technical topic areas: intergranular stress corrosion cracking of austenitic stainless steels; environmentally-assisted cracking of carbon and low alloy steels; intergranular stress corrosion cracking of nickel-base alloys; and improved fabrication technology

  7. Plant Materials Program: progress June 1981 to May 1982

    International Nuclear Information System (INIS)

    Childs, W.; Cubicciotti, D.; Fox, M.; Giannuzzi, A.; Gilman, J.; Jones, R.

    1983-02-01

    This is the second annual progress report of the Plant Materials Subprogram, which was organized in May 1980 to address corrosion-related materials problems in light water reactors. The first section of the report provides an overview of plant materials problems which have a high impact on plant availability. These include pipe and pressure vessel cracking, condenser leakage, turbine disc cracking, steam geerator tube attack and cracking, and cracking of nickel alloy springs, beams and pins. The status and goals of research and development work related to each of these problems are reviewed briefly. Subsequent report sections provide more detailed reviews of significant progress in the relevant technical topic areas: intergranular stress corrosion cracking of austenitic stainless steels; environmentally-assisted cracking of carbon and low alloy steels; intergranular stress corrosion cracking of nickel-base alloys; and improved fabrication technology

  8. Plant Materials Program: progress June 1981-May 1982

    International Nuclear Information System (INIS)

    Childs, W.; Cubicciotti, D.; Fox, M.; Giannuzzi, A.; Gilman, J.; Jones, R.

    1983-02-01

    This is the second annual progress report of the Plant Materials Subprogram, which was organized in May 1980 to address corrosion-related materials problems in light water reactors. The first section of the report provides an overview of plant materials problems which have impact on plant availability. These include pipe and pressure vessel cracking, condenser leakage, turbine disc cracking, steam generator tube attack and cracking, and cracking of nickel alloy springs, beams and pins. The status and goals of research and development work related to each of these problems are reviewed briefly. Subsequent report sections provide more detailed reviews of significant progress in the relevant technical topic area: integranular stress corrosion cracking of austenitic stainless steels; environmentally-assisted cracking of carbon and low alloy steels; intergranular stress corrosion cracking of nickel-base alloys; and improved fabrication technology

  9. Evaluation of breast self-examination program using Health Belief Model in female students

    Directory of Open Access Journals (Sweden)

    Mitra Moodi

    2011-01-01

    Full Text Available Background: Breast cancer has been considered as a major health problem in females, because of its high incidence in recent years. Due to the role of breast self-examination (BSE in early diagnosis and prevention of morbidity and mortality rate of breast cancer, promoting student knowledge, capabilities and attitude are required in this regard. This study was conducted to evaluation BSE education in female University students using Health Belief Model. Methods: In this semi-experimental study, 243 female students were selected using multi-stage randomized sampling in 2008. The data were collected by validated and reliable questionnaire (43 questions before intervention and one week after intervention. The intervention program was consisted of one educational session lasting 120 minutes by lecturing and showing a film based on HBM constructs. The obtained data were analyzed by SPSS (version11.5 using statistical paired t-test and ANOVA at the significant level of α = 0.05. Results: 243 female students aged 20.6 ± 2.8 years old were studied. Implementing the educational program resulted in increased knowledge and HBM (perceived susceptibility, severity, benefit and barrier scores in the students (p ≤ 0.01. Significant increases were also observed in knowledge and perceived benefit after the educational program (p ≤ 0.05. ANOVA statistical test showed significant difference in perceived benefit score in students of different universities (p = 0.05. Conclusions: Due to the positive effects of education on increasing knowledge and attitude of university students about BSE, the efficacy of the HBM in BSE education for female students was confirmed.

  10. A prospective examination of disease management program use by complex cardiac outpatients.

    Science.gov (United States)

    Gravely, Shannon; Reid, Robert D; Oh, Paul; Ross, Heather; Stewart, Donna E; Grace, Sherry L

    2012-01-01

    The use of disease management programs (DMPs) by patients with cardiovascular disease (CVD) is associated with improved outcomes. Although rates of cardiac rehabilitation (CR) use are well established, less is known about other DMPs. The objectives of this study were to describe the degree of DMP utilization by CVD outpatients, and examine factors related to use. This study represents a secondary analysis of a larger prospective cohort study. In hospital, 2635 CVD inpatients from 11 hospitals in Ontario Canada completed a survey that assessed factors affecting DMP utilization. One year later, 1803 participants completed a mailed survey that assessed DMP utilization. One thousand seventy-three (59.5%) participants reported using at least 1 DMP. Overall, 951 (52.7%) reported participating in cardiac rehabilitation, and among participants with a comorbid indication, 212 (41.2%) reported attending a diabetes education centre, 28 (25.9%) attended stroke rehabilitation, 35 (12.9%) used a heart failure clinic, and 13 (11.7%) attended a smoking cessation program. A multinomial logistic regression analysis showed that compared with no DMP use, participants that attended 1 or multiple programs were younger, married, diagnosed with a myocardial infarction, less likely to have had a percutaneous coronary intervention and had higher perceptions of personal control over their heart condition. There were few differences between participants that used 1 vs multiple DMPs, however, having diabetes or comorbid stroke significantly increased the likelihood of multiple DMP use. Approximately 40% of CVD outpatients do not access DMPs. An integrated approach to vascular disease management appears warranted. Copyright © 2012 Canadian Cardiovascular Society. Published by Elsevier Inc. All rights reserved.

  11. Factors influencing moisture analysis in the 3013 destructive examination surveillance program

    Energy Technology Data Exchange (ETDEWEB)

    Scogin, J. H. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

    2017-10-24

    Thermogravimetric analysis of a solid sample with mass spectrometry (TGA-MS) of the evolved gas is used in the destructive examination (DE) portion of the Integrated Surveillance Program to quantify the moisture content of the material stored in a 3013 container. As with any measurement determined from a small sample, the collection, storage, transportation, and handling of the sample can affect its ability to represent the properties of the bulk material. During the course of the DE program, questions have periodically arisen concerning the ability of the moisture sample to reflect reliably the actual moisture content of the entire material stored in the 3013 container. Most concerns are related to the ability to collect a representative sample and to preserve the moisture content of the sample between collection and analysis. Recent delays in analysis caused by maintenance issues with the TGA-MS instrument presented a unique opportunity to document and quantify the effects various factors have on the TGA-MS moisture measurement. This report will use recent data to document the effects that current sample collection and handling practices have on the TGA-MS moisture measurement. Some suggestions will be made which could improve the current sample collection and handling practices for the TGA-MS moisture measurement so that the analytical results more accurately reflect the moisture content of the material stored in the 3013 container.

  12. Factors influencing moisture analysis in the 3013 destructive examination surveillance program

    International Nuclear Information System (INIS)

    Scogin, J. H.

    2017-01-01

    Thermogravimetric analysis of a solid sample with mass spectrometry (TGA-MS) of the evolved gas is used in the destructive examination (DE) portion of the Integrated Surveillance Program to quantify the moisture content of the material stored in a 3013 container. As with any measurement determined from a small sample, the collection, storage, transportation, and handling of the sample can affect its ability to represent the properties of the bulk material. During the course of the DE program, questions have periodically arisen concerning the ability of the moisture sample to reflect reliably the actual moisture content of the entire material stored in the 3013 container. Most concerns are related to the ability to collect a representative sample and to preserve the moisture content of the sample between collection and analysis. Recent delays in analysis caused by maintenance issues with the TGA-MS instrument presented a unique opportunity to document and quantify the effects various factors have on the TGA-MS moisture measurement. This report will use recent data to document the effects that current sample collection and handling practices have on the TGA-MS moisture measurement. Some suggestions will be made which could improve the current sample collection and handling practices for the TGA-MS moisture measurement so that the analytical results more accurately reflect the moisture content of the material stored in the 3013 container.

  13. Program for photon shielding calculations. Examination of approximations on irradiation geometries

    International Nuclear Information System (INIS)

    Isozumi, Yasuhito; Ishizuka, Fumihiko; Miyatake, Hideo; Kato, Takahisa; Tosaki, Mitsuo

    2004-01-01

    Penetration factors and related numerical data in 'Manual of Practical Shield Calculation of Radiation Facilities (2000)', which correspond to the irradiation geometries of point isotropic source in infinite thick material (PI), point isotropic source in finite thick material (PF) and vertical incident to finite thick material (VF), have been carefully examined. The shield calculation based on the PI geometry is usually performed with effective dose penetration factors of radioisotopes given in the 'manual'. The present work cleary shows that such a calculation may lead to an overestimate more than twice larger, especially for thick shield of concrete and water. Employing the numerical data in the 'manual', we have fabricated a simple computer program for the estimation of penetration factors and effective doses of radioisotopes in the different irradiation geometries, i.e., PI, PF and VF. The program is also available to calculate the effective dose from a set of radioisotopes in the different positions, which is necessary for the γ-ray shielding of radioisotope facilities. (author)

  14. Next Generation Nuclear Plant Materials Research and Development Program Plan

    Energy Technology Data Exchange (ETDEWEB)

    G. O. Hayner; E.L. Shaber

    2004-09-01

    The U.S Department of Energy (DOE) has selected the Very High Temperature Reactor (VHTR) design for the Next Generation Nuclear Plant (NGNP) Project. The NGNP will demonstrate the use of nuclear power for electricity and hydrogen production without greenhouse gas emissions. The reactor design will be a graphite moderated, helium-cooled, prismatic or pebble-bed, thermal neutron spectrum reactor that will produce electricity and hydrogen in a state-of-the-art thermodynamically efficient manner. The NGNP will use very high burn-up, low-enriched uranium, TRISO-coated fuel and have a projected plant design service life of 60 years.

  15. Candu Energy's Aging and Obsolescence Program and its Application to Operating Facilities and New Plant Design

    International Nuclear Information System (INIS)

    Dam, R.; Gold, R.; McCrea, L.

    2012-01-01

    While plant aging is inevitable, predictable and 'graceful 'aging' behavior can be achieved through the implementation of a comprehensive and integrated Plant Life Management (PLiM) program. Despite organizations like the IAEA and INPO placing more emphasis on equipment reliability, there is still a lack of completely integrated programs in the industry as evidenced by: - Piece-meal, often crisis-driven, implementation comprising many different, partial solutions; - Duplication of effort often seen when different groups work in 'silos'. A strategy which fits with existing plant processes and programs, and which coordinates a broad range of equipment reliability activities is key to achieving the desired results. An example of such a program is the Aging and Obsolescence Program (AOP). AOP follows application of INPO AP-913 guidance for equipment reliability. The program is augmented to include single point vulnerability identification, unified approach to short and long lived components, risk management, spare parts management, and the identification and resolution of obsolescence issues. The systematic nature of the program provides the needed foundation to old and new stations alike. For existing operating stations some of the key uses include outage interval extension, reduced forced outages, and/or outage time reduction, any of which can translate into improving plant performance, competitiveness, and significant dollars saved. Program elements applied to new plant design are commensurate with the industry direction to 'design for reliability', and has allowed Candu Energy to learn and to improve upon what it can offer to operating stations. This paper intends to describe the basic elements of Candu Energy's Aging and Obsolescence Program and will share some of the experience having applied it to existing operating stations, consider applications to support expanding regulatory requirements, and describe the integration into the design of new plants, promoting

  16. Japan's international cooperation programs on seismic safety of nuclear power plants

    International Nuclear Information System (INIS)

    Sanada, Akira

    1997-01-01

    MITI is promoting many international cooperation programs on nuclear safety area. The seismic safety of nuclear power plants (NPPs) is a one of most important cooperation areas. Experts from MITI and related organization join the multilateral cooperation programs carried out by international organization such as IAEA, OECD/NEA etc. MITI is also promoting bilateral cooperation programs such as information exchange meetings, training programs and seminars on nuclear safety with several countries. Concerning to the cooperation programs on seismic safety of NPPs such as information exchange and training, MITI shall continue and expand these programs. (J.P.N.)

  17. Japan`s international cooperation programs on seismic safety of nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Sanada, Akira [Agency of Natural Resources and Energy, Tokyo (Japan)

    1997-03-01

    MITI is promoting many international cooperation programs on nuclear safety area. The seismic safety of nuclear power plants (NPPs) is a one of most important cooperation areas. Experts from MITI and related organization join the multilateral cooperation programs carried out by international organization such as IAEA, OECD/NEA etc. MITI is also promoting bilateral cooperation programs such as information exchange meetings, training programs and seminars on nuclear safety with several countries. Concerning to the cooperation programs on seismic safety of NPPs such as information exchange and training, MITI shall continue and expand these programs. (J.P.N.)

  18. Industrial Fuel Gas Demonstration Plant Program. Demonstration plant operation plan (Deliverable No. 38)

    Energy Technology Data Exchange (ETDEWEB)

    None

    1979-01-01

    The Demo Plant Operating Plan is composed of the following sequence of events starting with the training or personnel, familiarizing of the personnel with the plant and completing the long-term run in the following sequences: inspection during construction, plant completion, shakedown of equipment, process unit startup, shakedown of process units, variable run operation and a turnaround. During the construction period, technical personnel from DRC, MLGW and IGT will be at the plant site becoming familiar with the equipment, its installation and all of the auxiliaries so that on completion of construction they will be well grounded on the plant detail and its configuration. At the same time the supervisory operating personnel will have hands on training the gasifier operation at the IGT pilot plant to develop a field for gasifier operation. As a plant sections are completed, they will be checked out in accordance with the contractor and operator (client) procedure as outlined. Subsequent to this, various vendor designs and furnished equipment will be checked out operating-wise and a performance test run if feasible. The actual startup of the plant will be subsequential with the support areas as utilities, coal handling and waste treatment being placed in operation first. Subsequent to this the process units will be placed in operation starting from the rear of the process train and working forward. Thus the downstream units will be operating before the reactor is run on coal. The reactor will be checked out on coke operation.

  19. Intergrated plant safety assessment. Systematic evaluation program. Palisades plant, Consumers Power Company, Docket No. 50-255. Final report

    International Nuclear Information System (INIS)

    1982-10-01

    The Nuclear Regulatory Commission (NRC) has published its Final Integrated Plant Safety Assessment Report (IPSAR) (NUREG-0820), under the scope of the Systematic Evaluation Program (SEP), for Consumers Power Company's Palisades Plant located in Covert, Van Buren County, Michigan. The SEP was initiated by the NRC to review the design of older operating nuclear reactor plants to reconfirm and document their safety. This report documents the review completed under the SEP for the Palisades Plant. The review has provided for (1) as assessment of the significance of differences between current technical positions on selected safety issues and those that existed when the Palisades Plant was licensed, (2) a basis for deciding on how these differences should be resolved in an integrated plant review, and (3) a documented evaluation of plant safety when all supplements to the Final IPSAR and the Safety Evaluation Report for converting the license from a provisional to a full-term license have been issued. The report also addresses the comments and recommendations made by the Advisory Committee on Reactor Safeguards in connection with its review of the Draft Report, issued in April 1982

  20. Studies and research concerning BNFP: evaluation of spent-fuel-examination techniques for the Barnwell Nuclear Fuel Plant

    International Nuclear Information System (INIS)

    Anderson, R.T.; Gray, J.H.; Rogell, M.L.

    1982-09-01

    A study was made of various examinations which could be remotely performed on a production basis with spent fuel at the Barnwell Nuclear Fuel Plant (BNFP). These techniques could form an integral portion of fuel disassembly and canning operations. Their benefits accrue to either improved fuel storage, reprocessing, or both. In conjunctoin with these studies, evaluations have been made of the operational impact of receiving failed or canned fuel at the BNFP

  1. Corrosion and thermal plant section: 1983 review and 1984 programs

    International Nuclear Information System (INIS)

    Brown, J.

    1984-01-01

    The projects and achievements of the Corrosion and Thermal Plant Section in 1983 are reviewed. Proposed projects and objectives for 1984 are described in outline and an overview of the changes in direction of the work of the section is presented

  2. Operation of Wastewater Treatment Plants: A Home Study Training Program.

    Science.gov (United States)

    California State Univ., Sacramento. Dept. of Civil Engineering.

    This manual was prepared by experienced wastewater treatment plant operators to provide a home study course to develop new qualified workers and expand the abilities of existing workers. The objective of this manual is to provide the knowledge and skills necessary for certification. Participants learn the basic operational aspects of treatment…

  3. Examination of some assumed severe reactor accidents at the Olkiluoto nuclear power plant

    International Nuclear Information System (INIS)

    Pekkarinen, E.; Rossi, J.

    1989-02-01

    Knowledge and analysis methods of severe accidents at nuclear power plants and of subsequent response of primary system and containment have been developed in last few years to the extent that realistic source tems of the specified accident sequences can be calculated for the Finnish nuclear power plants. The objective of this investigation was to calculate the source terms of off-site consequences brought about by some selected severe accident sequences initiated by the total loss of on-site and off-site AC power at the Olkiluoto nuclear power plant. The results describing the estimated off-site health risks are expressed as conditional assuming that the accident has taken place, because the probabilities of the occurence of the accident sequences considered have not been analysed in this study. The range and probabilities of occurence of health detriments are considered by calculating consequences in different weeather conditions and taking into account the annual frequency of each weather condition and statistical population distribution. The calculational results indicate that the reactor building provides and additional holdup and deposition of radioactive substance (except coble gases) released from the containment. Furthermore, the release fractions of the core inventory to the environment of volatile fission products such as iodine, cesium and tellurium remain under 0.03. No early health effects are predicted for the surrounding population in case the assumed short-tem countermeasures are performed effectively. Acute health effects are extremely improbable even without any active countermeasure. By reducing the long-term exposure from contaminated agricultural products, the collective dose from natural long-term background radiation, for instance in the sector of 30 degrees towards the southern Finland up to the distance of 300 kilometers, would be expected to increase with 2-20 percent depending on the release considered

  4. Inpo programs for improvement of nuclear power plant operations

    International Nuclear Information System (INIS)

    Edward Moore, C.

    1989-01-01

    The talk shows how key INPO programs help foster improved nuclear power operations. The talk focuses on the results being seen from six key efforts: evaluations, training and accreditation, assistance, events analysis and information exchange, human performance and maintenance. The talk stresses that all INPO programs are geared toward enhanced performance and that progress in key performance areas since 1980 shows that INPO and U.S. industry efforts are achieving desired results

  5. Reduced program of inspection by induced currents for condenser of Embalse nuclear power plant

    International Nuclear Information System (INIS)

    Obrutsky, L.; Mendonca, H.

    1986-01-01

    In this work it's presented a reduced inspection in service program by the technique of induced currents to the turbine condenser of Embalse's Power Plant (Cordoba). The authors based its elaboration on the results obtained in the exam of a small number of tubes and on experience obtained through four inspections in the condensers of Atucha I Power Plant, through mathematical models of oxygen and ammoniac distribution in both Power Plants, and its experimental verification in the case of Atucha I. This program improves the quality of inspection thereby reducing time, equipment and personnel employed. (C.M.) [pt

  6. Aging research program at the LaCrosse nuclear power plant

    International Nuclear Information System (INIS)

    DiBenedetto, P.A.; Goller, K.R.; Sideris, T.

    1988-01-01

    A research program on the time-dependent, environmentally and operationally induced degradation of components, systems and structures---that is aging---is being conducted at the LaCrosse Boiling Water Reactor (LACBWR) nuclear power plant. In the spring of 1987, Dairyland Power Cooperative, the owner/licensee of the LACBWR plant announced that it was permanently shutting down this plant and intended to decommission it. Shortly thereafter, Dairyland entered into an agreement with DiBenedetto Associates (DBA) to be the exclusive agent and manager of the Aging Research Program (ARP). Wyle Laboratories is the primary supporting contractor to DBA in this effort

  7. DCD – a novel plant specific domain in proteins involved in development and programmed cell death

    Directory of Open Access Journals (Sweden)

    Doerks Tobias

    2005-07-01

    Full Text Available Abstract Background Recognition of microbial pathogens by plants triggers the hypersensitive reaction, a common form of programmed cell death in plants. These dying cells generate signals that activate the plant immune system and alarm the neighboring cells as well as the whole plant to activate defense responses to limit the spread of the pathogen. The molecular mechanisms behind the hypersensitive reaction are largely unknown except for the recognition process of pathogens. We delineate the NRP-gene in soybean, which is specifically induced during this programmed cell death and contains a novel protein domain, which is commonly found in different plant proteins. Results The sequence analysis of the protein, encoded by the NRP-gene from soybean, led to the identification of a novel domain, which we named DCD, because it is found in plant proteins involved in development and cell death. The domain is shared by several proteins in the Arabidopsis and the rice genomes, which otherwise show a different protein architecture. Biological studies indicate a role of these proteins in phytohormone response, embryo development and programmed cell by pathogens or ozone. Conclusion It is tempting to speculate, that the DCD domain mediates signaling in plant development and programmed cell death and could thus be used to identify interacting proteins to gain further molecular insights into these processes.

  8. Design of a PLC control program for a batch plant : VHS case study 1

    NARCIS (Netherlands)

    Mader, A.H.; Brinksma, E.; Wupper, H.; Bauer, N.

    2001-01-01

    This article reports on the systematic design and validation of a PLC control program for the batch plant that has been selected as a case study for the EC project on Verification of Hybrid Systems (VHS). We show how a correct design of the control program can be obtained in an incremental manner

  9. Design of a PLC Control Program for a Batch Plant - VHS Case Study 1

    NARCIS (Netherlands)

    Mader, Angelika H.; Brinksma, Hendrik; Wupper, H.; Bauer, N.

    2001-01-01

    This article reports on the systematic design and validation of a PLC control program for the batch plant that has been selected as a case study for the EC project on Verification of Hybrid Systems (VHS). We show how a correct design of the control program can be obtained in an incremental manner

  10. Portsmouth Gaseous Diffusion Plant Decontamination and Decommissioning Program surveillance and maintenance plan, FY 1993--2002

    International Nuclear Information System (INIS)

    Schloesslin, W.

    1992-11-01

    The Decontamination and Decommissioning (D ampersand D) Program at the Portsmouth Gaseous Diffusion Plant (PORTS) is part of the Environmental Restoration (ER) and Waste Management (WM) Programs (ERWM). The objective of the ER Program is to provide PORTS the capability to meet applicable environmental regulations through facility development activities and site remedial actions. The WM Program supports the ER Program. The D ampersand D Program provides collective management of the sites within the plant which require decontamination and decommissioning, prioritizes those areas in terms of health, safety and environmental concerns, and implements the appropriate level of remedial action. The D ampersand D Program provides support to facilities which formerly served one or more of the many Plant functions. Program activities include (1) surveillance and maintenance of facilities awaiting decommissioning; (2) planning safe and orderly facility decommissioning; and (3) implementing a program to accomplish facility disposition in a safe, cost effective, and timely manner. In order to achieve the first objective, a formal plan which documents the surveillance and maintenance needs for each inactive facility has been prepared. This report provides this documentation for the PORTS facilities currently included in the D ampersand D Program and includes projected resource requirements for the planning period of FY 1993 through FY 2002

  11. Using systematic aging assessments to improve effectiveness of plant maintenance programs

    International Nuclear Information System (INIS)

    Watson, P.; Yang, J.X.; Dam, R.F.; Nickerson, J.H.

    2003-01-01

    Nuclear plant equipment aging assessment studies provided by AECL include life assessments, condition assessments or systematic assessments of maintenance. AECL has developed several tools to apply the results of aging assessment studies to improve the effectiveness of actual plant maintenance programs. The Systematic Assessment of Maintenance and the SYSTMS tool generate maintenance tasks for a system. The System Maintenance Datastore tool assesses the maintenance resources on a system basis, and can thus quantify the savings realized by optimizing the maintenance program. Long term trends in condition-based maintenance due to component aging can be predicted, and resource savings due to optimum timing of component replacement or general plant refurbishment can be quantified. The System based Adaptive Maintenance Process ensures the maintenance program is continually updated to reflect the latest plant equipment condition and maintenance strategy information. (author)

  12. Evaluation of bioassay program at uranium fuel fabrication plants

    International Nuclear Information System (INIS)

    Biggs, D.

    1981-03-01

    Results of a comprehensive study of urinalysis, lung burden and personal air sample measurements for workers at a uranium fuel fabrication plant are presented. Correlations between measurements were found and regression models used to explain the relationship between lung burden, daily intakes and urinary excretions of uranium. Assuming the ICRP lung model, the lung burden histories of ten workers were used to estimate the amounts in each of the long-term compartments of the lung. Estimates of the half lives of each compartment and of the maximum relative contributions to the urine from each compartment are given. These values were then used to predict urinary excretions from the long-term compartments for workers at another fuel fabrication plant. The standard error of estimate compared well with the daily variation in urinary excretion. (author)

  13. Integrated Plant Safety Assessment, Systematic Evaluation Program, Palisades Plant (Docket No. 50-255)

    International Nuclear Information System (INIS)

    1983-11-01

    This report documents the review completed under the SEP for those issues that required refined engineering evaluations or the continuation of ongoing evaluations after the Final IPSAR for the Palisades Plant was issued. The review has provided for (1) an assessment of the significance of differences between current technical positions on selected safety issues and those that existed when the Palisades Plant was licensed, (2) a basis for deciding on how these differences should be resolved in an integrated plant review, and (3) a documented evaluation of plant safety when the supplement to the Final IPSAR and the Safety Evaluation Report for converting the license from a provisional to a full-term license have been issued. The Final IPSAR and its supplement will form part of the bases for considering the conversion of the provisional operating license to a full-term operating license

  14. Examination and testing requirements for concrete containment structures for CANDU nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1993-07-01

    This Standard provides the examination and testing requirements that will apply to the work of any organization participating in the construction, installation, and fabrication of parts or components of concrete containment structures, or both, that are defined as class containment. 2 tabs.

  15. Examination and testing requirements for concrete containment structures for CANDU nuclear power plants

    International Nuclear Information System (INIS)

    1993-07-01

    This Standard provides the examination and testing requirements that will apply to the work of any organization participating in the construction, installation, and fabrication of parts or components of concrete containment structures, or both, that are defined as class containment. 2 tabs

  16. Summer Treatment Program for Preschoolers with Externalizing Behavior Problems: a Preliminary Examination of Parenting Outcomes.

    Science.gov (United States)

    Graziano, Paulo A; Ros, Rosmary; Hart, Katie C; Slavec, Janine

    2017-11-07

    Within an at-risk sample of preschoolers with externalizing behavior problems (EBP), the current study examined the initial promise of a multimodal intervention, the Summer Treatment Program for Pre-Kindergarteners (STP-PreK), in improving parenting outcomes. Using an open trial design, 154 parents and their preschool children (73% male; M age  = 5.06 years; 82% Hispanic/Latino background) with at-risk or clinically elevated levels of EBP (57% of which were referred by schools or mental health/medical professionals) completed a baseline and post-treatment assessment. A subsample of 90 families completed a follow-up assessment approximately 6 to 9 months after treatment completion. Parental measures of parenting stress and discipline strategies were collected across all three assessments. Observational data were also collected across all assessments during a 5-min standardized child-led play situation and a 5-min parent-led clean up task. The parenting component of the STP-PreK included a School Readiness Parenting Program (SRPP) of which the behavioral management component was implemented via a Parent-Child Interaction Therapy (PCIT) adaptation (8 weekly group sessions with 15-20 parents in each group, lack of requirement of "mastery" criteria). All parenting outcomes (both ratings and observed) significantly improved after the intervention (Cohen's d mean effect size across measures 0.89) with all effects being maintained at the 6-9 month follow-up. These findings highlight the initial promise of our SRPP's PCIT adaptation in targeting multiple aspects of parenting while yielding comparable parenting skills acquisition compared to traditional individual PCIT.

  17. Development of computer program for safety of nuclear power plant against tsunami

    International Nuclear Information System (INIS)

    Jin, S. B.; Choi, K. R.; Lee, S. K.; Cho, Y. S.

    2001-01-01

    The main objective of this study is the development of a computer program to check the safety of nuclear power plants along the coastline of the Korean Peninsula. The computer program describes the propagation and associated run-up process of tsunamis by solving linear and nonlinear shallow-water equations with finite difference methods. The computer program has been applied to several ideal and simplified problems. Obtained numerical solutions are compared to existing and available solutions and measurements. A very good agreement between numerical solutions and existing measurement is observed. The computer program developed in this study can be to check the safety analysis of nuclear power plants against tsunamis. The program can also be used to study the propagation of tsunamis for a long distance, and associated run-up and run-down process along a shoreline. Furthermore, the computer program can be used to provide the proper design criteria of coastal facilities and structures

  18. College and university programs for meeting the needs of educating nuclear power plant personnel

    International Nuclear Information System (INIS)

    Hajek, B.K.; Miller, D.W.; De Vuono, A.C.

    1981-01-01

    ANS, INPO, and NRC are considering various recommendations for university courses to be required for all nuclear power plant licensed personnel. This paper discusses these recommendations and compares them with the content and constraints of traditional university academic programs. One solution being pursued by utilities in Ohio is discussed. In this program, courses are being obtained from several different educational institutions for presentation at the power plant site. The program provides sufficient flexibility so that decisions on specific degree options do not have to be made at this time

  19. Results from the Nuclear Plant Aging Research Program: Their use in inspection activities

    International Nuclear Information System (INIS)

    Gunther, W.; Taylor, J.

    1990-09-01

    The US NCR's Nuclear Plant Aging Research (NPAR) Program has determined the susceptibility to aging of components and systems, and the potential for aging to impact plant safety and availability. The NPAR Program also identified methods for detecting and mitigating aging in components. This report describes the NPAR results which can enhance NRC inspection activities. Recommendations are provided for communicating pertinent information to NRC inspectors. These recommendations are based on a detailed assessment of the NRC's Inspection Program, and feedback from resident and regional inspectors as described within. Examples of NPAR report summaries and aging inspection guides for components and systems are included. 13 refs., 3 figs., 4 tabs

  20. A Comparative Cross-Cultural Examination of Community Art Education Programs in South Korea and the United States

    Science.gov (United States)

    Shin, Ryan; Kim, Junghee

    2014-01-01

    The authors conducted comparative cross-cultural research to examine a select group of the available and more noteworthy art education organizations and their programs after observing significant differences in the community art education programs offered in Tucson, Arizona, and Anyang, South Korea. The study reports several major differences…

  1. Evaluation of Millstone Nuclear Power Plant, Environmental Impact prediction, based on monitoring programs

    International Nuclear Information System (INIS)

    Gore, K.L.; Thomas, J.M.; Kannberg, L.D.; Watson, D.G.

    1977-02-01

    This report evaluates the nonradiological monitoring program at Millstone Nuclear Power Plant. Both operational as well as preoperational monitoring programs were analyzed to produce long-term (5 yr or longer) data sets, where possible. In order to determine the effectiveness of these monitoring programs, the appropriate data sets have to be analyzed by the appropriate statistical analysis. Thus, both open literature and current statistical analysis being developed at Pacific Northwest Laboratories (PNL) were employed in data analysis

  2. Evaluation of Millstone Nuclear Power Plant, Environmental Impact prediction, based on monitoring programs

    Energy Technology Data Exchange (ETDEWEB)

    Gore, K.L.; Thomas, J.M.; Kannberg, L.D.; Watson, D.G.

    1977-02-01

    This report evaluates the nonradiological monitoring program at Millstone Nuclear Power Plant. Both operational as well as preoperational monitoring programs were analyzed to produce long-term (5 yr or longer) data sets, where possible. In order to determine the effectiveness of these monitoring programs, the appropriate data sets have to be analyzed by the appropriate statistical analysis. Thus, both open literature and current statistical analysis being developed at Pacific Northwest Laboratories (PNL) were employed in data analysis.

  3. Operation of Wastewater Treatment Plants: A Field Study Training Program. Volume I. Second Edition.

    Science.gov (United States)

    California State Univ., Sacramento. Dept. of Civil Engineering.

    This manual was prepared by experienced wastewater collection system workers to provide a home study course to develop new qualified workers and expand the abilities of existing workers. This volume is directed primarily towards entry-level operators and the operators of ponds, package plants, or small treatment plants. Ten chapters examine the…

  4. Methodology to classify accident sequences of an Individual Plant Examination according to the severe releases for BWR type reactors

    International Nuclear Information System (INIS)

    Sandoval V, S.

    2001-01-01

    The Light Water Reactor (LWR) operation regulations require to every operating plant to perform of an Individual Plant Examination study (Ipe). One of the main purposes of an Ipe is t o gain a more quantitative understanding of the overall probabilities of core damage and fission product releases . Probabilistic Safety Analysis (PSA) methodologies and Severe Accident Analysis are used to perform Ipe studies. PSA methodologies are used to identify and analyse the set of event sequences that might originate the fission product release from a nuclear power plant; these methodologies are combinatorial in nature and generate thousands of sequences. Among other uses within an Ipe, severe accident simulations are used to determine the characteristics of the fission product release for the identified sequences and in this way, the releases can be understood and characterized. A vast amount of resources is required to simulate and analyse every Ipe sequence. This effort is unnecessary if similar sequences are grouped. The grouping scheme must achieve an efficient trade off between problem reduction and accuracy. The methodology presented in this work enables an accurate characterization and analysis of the Ipe fission product releases by using a reduced problem. The methodology encourages the use of specific plant simulations. (Author)

  5. Patterns of medicinal plant use: an examination of the Ecuadorian Shuar medicinal flora using contingency table and binomial analyses.

    Science.gov (United States)

    Bennett, Bradley C; Husby, Chad E

    2008-03-28

    Botanical pharmacopoeias are non-random subsets of floras, with some taxonomic groups over- or under-represented. Moerman [Moerman, D.E., 1979. Symbols and selectivity: a statistical analysis of Native American medical ethnobotany, Journal of Ethnopharmacology 1, 111-119] introduced linear regression/residual analysis to examine these patterns. However, regression, the commonly-employed analysis, suffers from several statistical flaws. We use contingency table and binomial analyses to examine patterns of Shuar medicinal plant use (from Amazonian Ecuador). We first analyzed the Shuar data using Moerman's approach, modified to better meet requirements of linear regression analysis. Second, we assessed the exact randomization contingency table test for goodness of fit. Third, we developed a binomial model to test for non-random selection of plants in individual families. Modified regression models (which accommodated assumptions of linear regression) reduced R(2) to from 0.59 to 0.38, but did not eliminate all problems associated with regression analyses. Contingency table analyses revealed that the entire flora departs from the null model of equal proportions of medicinal plants in all families. In the binomial analysis, only 10 angiosperm families (of 115) differed significantly from the null model. These 10 families are largely responsible for patterns seen at higher taxonomic levels. Contingency table and binomial analyses offer an easy and statistically valid alternative to the regression approach.

  6. Next Generation Nuclear Plant Materials Selection and Qualification Program Plan

    Energy Technology Data Exchange (ETDEWEB)

    R. Doug Hamelin; G. O. Hayner

    2004-11-01

    The U.S. Department of Energy (DOE) has selected the Very High Temperature Reactor (VHTR) design for the Next Generation Nuclear Plant (NGNP) Project. The NGNP will demonstrate the use of nuclear power for electricity and hydrogen production without greenhouse gas emissions. The reactor design is a graphite-moderated, helium-cooled, prismatic or pebble bed thermal neutron spectrum reactor with an average reactor outlet temperature of at least 1000 C. The NGNP will use very high burn up, lowenriched uranium, TRISO-Coated fuel in a once-through fuel cycle. The design service life of the NGNP is 60 years.

  7. Examination of vegetation around a nuclear plant emitting gaseous fluorides in order to detect fluorine pollution

    International Nuclear Information System (INIS)

    Teulon, Francoise; Bonnaventure, J. P.

    1971-08-01

    Fluorine pollution (chronic or occasional) around a plant rejecting gaseous fluoride effluents can be detected from vegetation samples by chemical analysis. Systematic monitoring allows the effects and gravity of the pollution to be estimated. The analytical method used consists of a double distillation (in phosphoric acid and perchloric acid) followed by a spectro-colorimetric analysis (alizarine-complexon-lanthane). This method of control allows both the efficiency of the trapping installations and also the appearance of effluents at unexpected places to be checked, In the event of an accident it is possible to determine the advisability of prohibiting the consumption of locally grown produce by humans or fodder by cattle. Research conducted in order to determine the relation between visible, damage to certain vegetables (tomatoes, haricot beans and sorghum) and their fluorine contents demonstrated that such a relation appears above all at the level of the leaves; chemical analysis may thus be used to confirm or reject information obtained on the basis of visual evidence [fr

  8. Assessment of cooling tower (ultimate heat sink) performance in the Byron individual plant examination

    International Nuclear Information System (INIS)

    Campbell, H.D.; Hawley, J.T.; Klopp, G.T.; Thelen, W.A.

    2004-01-01

    A time-dependent model of the Byron Nuclear Generation Station safety-related cooling towers has been developed for use with the Byron PRA (IPE). The model can either be run in a stand-alone program with externally supplied heat loads, or can be directly coupled into MAAP (Modular Accident Analysis Program). The primary feature of the model is a careful tracking of the basin temperature through the progression of different severe accidents. Heat removal rates from containment, both from containment fan-coolers and the residual heat removal system, are determined by the feed-back of this time-varying return temperature. Also, the inventory of the basin is tracked in time, and this is controlled by make-up, evaporative losses due to the heat load supplied to the towers, and the possibility of unsecured blowdown. The model has been used to determine the overall capabilities and vulnerabilities of the Byron Ultimate Heat Sink (UHS). It was determined that the UHS is very reliable with respect to maintaining acceptably low basin temperatures, requiring only at most two of eight operating cooling tower fans. Further, when the two units have their Essential Service Water (ESW) systems cross-tied, one of four ESW operating pumps is sufficient to handle the loads from the accident unit with the other unit proceeding to an orderly shutdown. The major vulnerability of the Byron UHS is shown to be the ability to maintain inventory, although the time-scales for basin dry-out are relatively long, being eight to twenty-one hours, depending upon when blowdown is secured. (author)

  9. Industrial Fuel Gas Demonstration Plant Program: environmental permit compliance plan

    Energy Technology Data Exchange (ETDEWEB)

    Bodamer, Jr., James W.; Bocchino, Robert M.

    1979-11-01

    This Environmental Permit Compliance Plan is intended to assist the Memphis Light, Gas and Water Division in acquiring the necessary environmental permits for their proposed Industrial Fuel Gas Demonstration Plant in a time frame consistent with the construction schedule. Permits included are those required for installation and/or operation of gaseous, liquid and solid waste sources and disposal areas. Only those permits presently established by final regulations are described. The compliance plan describes procedures for obtaining each permit from identified federal, state and local agencies. The information needed for the permit application is presented, and the stepwise procedure to follow when filing the permit application is described. Information given in this plan was obtained by reviewing applicable laws and regulations and from telephone conversations with agency personnel on the federal, state and local levels. This Plan also presents a recommended schedule for beginning the work necessary to obtain the required environmental permits in order to begin dredging operations in October, 1980 and construction of the plant in September, 1981. Activity for several key permits should begin as soon as possible.

  10. Synthesis gas demonstration plant program, Phase I. Site confirmation report

    Energy Technology Data Exchange (ETDEWEB)

    1978-12-01

    With few reservations, the Baskett, Kentucky site exhibits the necessary characteristics to suggest compatibility with the proposed Synthesis Gas Demonstration Plant Project. An evaluation of a broad range of technical disciplinary criteria in consideration of presently available information indicated generally favorable conditions or, at least, conditions which could be feasibly accommodated in project design. The proximity of the Baskett site to market areas and sources of raw materials as well as a variety of transportation facilities suggests an overall favorable impact on Project economic feasibility. Two aspects of environmental engineering, however, have been identified as areas where the completion or continuation of current studies are required before removing all conditions on site suitability. The first aspect involves the current contradictory status of existing land use and planning ordinances in the site area. Additional investigation of the legality of, and local attitudes toward, these present plans is warranted. Secondly, terrestrial and aquatic surveys of plant and animal life species in the site area must be completed on a seasonal basis to confirm the preliminary conclusion that no exclusionary conditions exist.

  11. 46 CFR 115.625 - Eligibility requirements for the Alternative Hull Examination (AHE) Program for certain passenger...

    Science.gov (United States)

    2010-10-01

    ... 46 Shipping 4 2010-10-01 2010-10-01 false Eligibility requirements for the Alternative Hull... OVERNIGHT ACCOMMODATIONS FOR MORE THAN 49 PASSENGERS INSPECTION AND CERTIFICATION Hull and Tailshaft Examinations § 115.625 Eligibility requirements for the Alternative Hull Examination (AHE) Program for certain...

  12. Electronic Engineering Technology Program Exit Examination as an ABET and Self-Assessment Tool

    Science.gov (United States)

    Thomas, Gary; Darayan, Shahryar

    2018-01-01

    Every engineering, computing, and engineering technology program accredited by the Accreditation Board for Engineering and Technology (ABET) has formulated many and varied self-assessment methods. Methods used to assess a program for ABET accreditation and continuous improvement are for keeping programs current with academic and industrial…

  13. A Qualitative Examination of Challenges Influencing Doctoral Students in an Online Doctoral Program

    Science.gov (United States)

    Deshpande, Anant

    2016-01-01

    The main purpose of the study was to investigate the challenges faced by students in completion of an online doctoral program at the University of Liverpool, Online Doctoral Business Administration program. We analyse the responses of 91 doctoral students in an online DBA program. Based on the exploratory qualitative study themes were developed…

  14. Enhancing materials management programs in nuclear power plants

    International Nuclear Information System (INIS)

    Hassaballa, M.M.; Malak, S.M.

    1992-01-01

    Materials management programs for the nuclear utilities in the United States are continually being affected, concurrent with the gradual disappearance of qualified component and replacement parts vendors by regulatory concerns about procurement and materials management. In addition, current economic and competitive pressures are forcing utilities to seek avenues for reducing procurement costs for safety-related items. In response to these concerns, initiatives have been undertaken and engineering guidelines have been developed by the nuclear power industry-sponsored organizations, such as the Electric Power Research Institute and the Nuclear Management Resources Council. It is our experience that successful materials management programs require a multitude of engineering disciplines and experience and are composed of three major elements: strategic procurement plan, parts classification and procurement data base, and enhancement tools. This paper provides a brief description of each of the three elements

  15. EPRI's nuclear power plant instrumentation and control program and its applicability to advanced reactors

    International Nuclear Information System (INIS)

    Naser, J.; Torok, R.; Wilkinson, D.

    1997-01-01

    I ampersand C systems in nuclear power plants need to be upgraded over the lifetime of the plant in a reliable and cost-effective manner to replace obsolete equipment, to reduce O ampersand M costs, to improve plant performance, and to maintain safety. This applies to operating plants now and will apply to advanced reactors in the future. The major drivers for the replacement of the safety, control, and information systems in nuclear power plants are the obsolescence of the existing hardware and the need for more cost-effective power production. Competition between power producers is dictating more cost-effective power production. The increasing O ampersand M costs to maintain systems experiencing obsolescence problems is counter to the needs for more cost-effective power production and improved competitiveness. This need for increased productivity applies to government facilities as well as commercial plants. Increasing competition will continue to be a major factor in the operation of both operating plants and advanced reactors. It will continue to dictate the need for improved productivity and cost-effectiveness. EPRI and its member nuclear utilities are working together on an industry wide I ampersand C Program to address I ampersand C issues and to develop cost-effective solutions. A majority of the I ampersand C products and demonstrations being developed under this program will benefit advanced reactors in both the design and operational phases of their life cycle as well as it will benefit existing plants. 20 refs

  16. Health examination of residents and its task after the Chernobyl Nuclear power plant accident

    International Nuclear Information System (INIS)

    Takamura, Noboru

    2012-01-01

    Described is the outline of health effects after the Chernobyl Accident (CA, Apr. 26, 1986) and of health examination/its future task, for learning to make use of means for the recent Fukushima Accident (FA). Total released radioactivity of the Level 7 CA is estimated to amount to 5.20 million TBq, 6-10 times as high as the same level of FA. Different from the Fukushima, no rapid means were taken by old Soviet Union to restrict the distribution and ingestion of contaminated foods, which was the major cause of internal radioiodine exposure. Afterward, in 1990s, WHO, European and other countries began to investigate CA, and markedly increased incidence of thyroid cancer was shown by health examination of 160 thousands children by a project of Sasakawa Memorial Health Foundation. In 2006, WHO and IAEA evaluated published literatures to summarize health effects related directly or possibly unrelated to CA: as for thyroid cancer, its prevalence tended to move in adolescence or older, and surgery and therapy for metastasis with radioiodine were significantly effective to improve their prognosis; however, their long term follow-up and treatment are continuously needed. Not observed was the increased incidence of leukemia, which is different from A-bomb survivors, and other cancers as well as benign diseases, but resident's concern about their health and effects on the next generation is increasing. Currently, systems of self-monitoring of foods are being established by residents around Chernobyl. Instructions and means learned from CA and A-bomb experiences are applied to this FA, but assurance of health of all these concerned people should be a future task against its fading with time. (T.T.)

  17. Greater confinement disposal program at the Savannah River Plant

    International Nuclear Information System (INIS)

    Cook, J.R.; Towler, O.A.; Peterson, D.L.; Johnson, G.M.; Helton, B.D.

    1984-01-01

    The first facility to demonstrate Greater Confinement Disposal (GCD) in a humid environment in the United States has been built and is operating at the Savannah River Plant. GCD practices of waste segregation, packaging, emplacement below the root zone, and waste stabilization are being used in the demonstration. Activity concentrations to select wastes for GCD are based on a study of SRP burial records, and are equal to or less than those for Class B waste in 10CFR61. The first disposal units to be constructed are 9-foot diameter, thirty-foot deep boreholes which will be used to dispose of wastes from production reactors, tritiated wastes, and selected wastes from off-site. In 1984 an engineered GCD trench will be constructed for disposal of boxed wastes and large bulky items. 2 figures, 1 table

  18. Greater Confinement Disposal Program at the Savannah River Plant

    International Nuclear Information System (INIS)

    Towler, O.A.; Cook, J.R.; Peterson, D.L.

    1983-01-01

    Plans for improved LLW disposal at the Savannah River Plant include Greater Confinement Disposal (GCD) for the higher activity fractions of this waste. GCD practices will include waste segregation, packaging, emplacement below the root zone, and stabilizing the emplacement with cement. Statistical review of SRP burial records showed that about 95% of the radioactivity is associated with only 5% of the waste volume. Trigger values determined in this study were compared with actual burials in 1982 to determine what GCD facilities would be needed for a demonstration to begin in Fall 1983. Facilities selected include 8-feet-diameter x 30-feet-deep boreholes to contain reactor scrap, tritiated waste, and selected wastes from offsite

  19. Waste Isolation Pilot Plant in situ experimental program for HLW

    International Nuclear Information System (INIS)

    Molecke, M.A.

    1977-01-01

    The Waste Isolation Pilot Plant (WIPP) will be a facility to demonstrate the environmental and operational safety of storing radioactive wastes in a deep geologic bedded salt facility. The WIPP will be located in southeastern New Mexico, approximately 30 miles east of the city of Carlsbad. The major focus of the pilot plant operation involves ERDA defense related low and intermediate-level transuranic wastes. The scope of the project also specifically includes experimentation utilizing commercially generated high-level wastes, or alternatively, spent unreprocessed fuel elements. WIPP HLW experiments are being conducted in an inter-related laboratory, bench-scale, and in situ mode. This presentation focuses on the planned in situ experiments which, depending on the availability of commercially reprocessed waste plus delays in the construction schedule of the WIPP, will begin in approximately 1985. Such experiments are necessary to validate preceding laboratory results and to provide actual, total conditions of geologic storage which cannot be adequately simulated. One set of planned experiments involves emplacing bare HLW fragments into direct contact with the bedded salt environment. A second set utilizes full-size canisters of waste emplaced in the salt in the same manner as planned for a future HLW repository. The bare waste experiments will study in an accelerated manner waste-salt bed-brine interactions including matrix integrity/degradation, brine leaching, system chemistry, and potential radionuclide migration through the salt bed. Utilization of full-size canisters of HLW in situ permits us to demonstrate operational effectiveness and safety. Experiments will evaluate corrosion and compatibility interactions between the waste matrix, canister and overpack materials, getter materials, stored energy, waste buoyancy, etc. Using full size canisters also allows us to demonstrate engineered retrievability of wastes, if necessary, at the end of experimentation

  20. Light Water Reactor Sustainability Program, U.S. Efforts in Support of Examinations at Fukushima Daiichi-2017 Evaluations

    Energy Technology Data Exchange (ETDEWEB)

    Farmer, Mitchell T. [Argonne National Lab. (ANL), Argonne, IL (United States)

    2017-08-01

    Although the accident signatures from each unit at the Fukushima Daiichi Nuclear Power Station (NPS) [Daiichi] differ, much is not known about the end-state of core materials within these units. Some of this uncertainty can be attributed to a lack of information related to cooling system operation and cooling water injection. There is also uncertainty in our understanding of phenomena affecting: a) in-vessel core damage progression during severe accidents in boiling water reactors (BWRs), and b) accident progression after vessel failure (ex-vessel progression) for BWRs and Pressurized Water Reactors (PWRs). These uncertainties arise due to limited full scale prototypic data. Similar to what occurred after the accident at Three Mile Island Unit 2, these Daiichi units offer the international community a means to reduce such uncertainties by obtaining prototypic data from multiple full-scale BWR severe accidents. Information obtained from Daiichi is required to inform Decontamination and Decommissioning activities, improving the ability of the Tokyo Electric Power Company Holdings, Incorporated (TEPCO Holdings) to characterize potential hazards and to ensure the safety of workers involved with cleanup activities. This document, which has been updated to include FY2017 information, summarizes results from U.S. efforts to use information obtained by TEPCO Holdings to enhance the safety of existing and future nuclear power plant designs. This effort, which was initiated in 2014 by the Reactor Safety Technologies Pathway of the Department of Energy Office of Nuclear Energy Light Water Reactor (LWR) Sustainability Program, consists of a group of U.S. experts in LWR safety and plant operations that have identified examination needs and are evaluating TEPCO Holdings information from Daiichi that address these needs. Each year, annual reports include examples demonstrating that significant safety insights are being obtained in the areas of component performance, fission

  1. Auditing of quality assurance programs for nuclear power plants - September 1980 - (Rev.1)

    International Nuclear Information System (INIS)

    Anon.

    1981-01-01

    Appendix B, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants, to 10 CFR Part 50, Domestic Licensing of Production and Utilization Facilities, establishes overall quality assurance requirements for the design, construction, and operation of structures, systems, and components of nuclear power plants important to safety. Criterion XVIII, Audits, of Appendix B to 10 CFR Part 50 establishes requirements for conducting audits of the quality assurance program. This guide describes a method acceptable to the NRC staff for complying with the Commission's regulations with regard to auditing of quality assurance programs for nuclear power plants. The Advisory Committee on Reactor Safeguards has been consulted concerning this guide and has concurred in the regulatory position

  2. Early Site Permit Demonstration Program: Plant parameters envelope report. Volume 1

    Energy Technology Data Exchange (ETDEWEB)

    1993-03-01

    The Early Site Permit (ESP) Demonstration Program is the nuclear industry`s initiative for piloting the early resolution of siting-related issues before the detailed design proceedings of the combined operating license review. The ESP Demonstration Program consists of three phases. The plant parameters envelopes task is part of Phase 1, which addresses the generic review of applicable federal regulations and develops criteria for safety and environmental assessment of potential sites. The plant parameters envelopes identify parameters that characterize the interface between an ALWR design and a potential site, and quantify the interface through values selected from the Utility Requirements Documents, vendor design information, or engineering assessments. When augmented with site-specific information, the plant parameters envelopes provide sufficient information to allow ESPs to be granted based on individual ALWR design information or enveloping design information for the evolutionary, passive, or generic ALWR plants. This document is expected to become a living document when used by future applicants.

  3. National emergency medical assistance program for commercial nuclear power plants

    International Nuclear Information System (INIS)

    Linnemann, R.E.; Berger, M.E.

    1987-01-01

    Radiation Management Consultant's Emergency Medical Assistance Program (EMAP) for nuclear facilities provides a twenty-four hour emergency medical and health physics response capability, training of site and off-site personnel, and three levels of care for radiation accident victims: first air and rescue at an accident site, hospital emergency assessment and treatment, and definitive evaluation and treatment at a specialized medical center. These aspects of emergency preparedness and fifteen years of experience in dealing with medical personnel and patients with real or suspected radiation injury will be reviewed

  4. Lessons Learned on University Education Programs of Chemical Engineering Principles for Nuclear Plant Operations - 13588

    International Nuclear Information System (INIS)

    Ryu, Jun-hyung

    2013-01-01

    University education aims to supply qualified human resources for industries. In complex large scale engineering systems such as nuclear power plants, the importance of qualified human resources cannot be underestimated. The corresponding education program should involve many topics systematically. Recently a nuclear engineering program has been initiated in Dongguk University, South Korea. The current education program focuses on undergraduate level nuclear engineering students. Our main objective is to provide industries fresh engineers with the understanding on the interconnection of local parts and the entire systems of nuclear power plants and the associated systems. From the experience there is a huge opportunity for chemical engineering disciple in the context of giving macroscopic overview on nuclear power plant and waste treatment management by strengthening the analyzing capability of fundamental situations. (authors)

  5. A Plant Health Care Program for Brambles in the Pacific Northwest

    OpenAIRE

    McElroy, F. D.

    1992-01-01

    Pratylenchus and Xiphinema species have been associated with decline and mortality of brambles (Rubus species) in the Pacific Northwest of the United States. These nematodes cause direct feeding damage and (or) transmit viruses that result in poor fruit quality and plant decline. A nematode management program has been developed by the author to minimize chemical use and nematode-induced damage while optimizing fruit production. Nematode management is an integral part of a total plant health c...

  6. Fiscal Year 1993 Well Plugging and Abandonment Program Summary Report Y-12 Plant, Oak Ridge, Tennessee

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-09-01

    This report is a synopsis of the progress of the well plugging and abandonment program at the Y-12 Plant, Oak Ridge, Tennessee, from October 1993 through August 1994. A total of 57 wells and borings were plugged and abandoned during the period of time covered in this report. All wells and borings were plugged and abandoned in accordance with the Monitoring Well Plugging and Abandonment Plan for the U.S. Department of Energy, Y-12 Plant, Oak Ridge, Tennessee.

  7. Fiscal year 1993 well plugging and abandonment program, Y-12 Plant, Oak Ridge, Tennessee

    Energy Technology Data Exchange (ETDEWEB)

    1993-09-01

    This report is a synopsis of the progress of the well plugging and abandonment program at the Y-12 Plant, Oak Ridge, Tennessee, from December 1992 through August 20, 1993. A total of 70 wells and borings were plugged and abandoned during the period of time covered in this report. All wells and borings were plugged and abandoned in accordance with the Monitoring Well Plugging and Abandonment Plan for the US Department of Energy, Y-12 Plant, Oak Ridge, Tennessee (HSW, Inc. 1991).

  8. The microcomputer scientific software series 7: data recorder program for storing plant lists and calculating synecological coordinates.

    Science.gov (United States)

    Kevin Nimerfro; Gary Brand

    1993-01-01

    Describes a computer program designed for data recorders that stores plant lists and computes synecological coordinates from the stored list. The method of synecological coordinates uses plant species present on a site to quantify the site`s environmental factors.

  9. Uncertain and multi-objective programming models for crop planting structure optimization

    Directory of Open Access Journals (Sweden)

    Mo LI,Ping GUO,Liudong ZHANG,Chenglong ZHANG

    2016-03-01

    Full Text Available Crop planting structure optimization is a significant way to increase agricultural economic benefits and improve agricultural water management. The complexities of fluctuating stream conditions, varying economic profits, and uncertainties and errors in estimated modeling parameters, as well as the complexities among economic, social, natural resources and environmental aspects, have led to the necessity of developing optimization models for crop planting structure which consider uncertainty and multi-objectives elements. In this study, three single-objective programming models under uncertainty for crop planting structure optimization were developed, including an interval linear programming model, an inexact fuzzy chance-constrained programming (IFCCP model and an inexact fuzzy linear programming (IFLP model. Each of the three models takes grayness into account. Moreover, the IFCCP model considers fuzzy uncertainty of parameters/variables and stochastic characteristics of constraints, while the IFLP model takes into account the fuzzy uncertainty of both constraints and objective functions. To satisfy the sustainable development of crop planting structure planning, a fuzzy-optimization-theory-based fuzzy linear multi-objective programming model was developed, which is capable of reflecting both uncertainties and multi-objective. In addition, a multi-objective fractional programming model for crop structure optimization was also developed to quantitatively express the multi-objective in one optimization model with the numerator representing maximum economic benefits and the denominator representing minimum crop planting area allocation. These models better reflect actual situations, considering the uncertainties and multi-objectives of crop planting structure optimization systems. The five models developed were then applied to a real case study in Minqin County, north-west China. The advantages, the applicable conditions and the solution methods

  10. Greater confinement disposal program at the Savannah River Plant

    International Nuclear Information System (INIS)

    Towler, O.A.; Cook, J.R.; Peterson, D.L.; Reddick, J.A.

    1984-01-01

    A facility to demonstrate Greater Confinement Disposal (GCD) of low-level solid radioactive waste in a humid environment has been built and is operating at the Savannah River Plant (SRP). GCD practices of waste segregation into high and low activity concentrations, emplacement of waste below the root zone, waste stabilization, and capping are being used in the demonstration. Activity concentrations to select wastes for GCD are based on the volume/activity distribution of low-level solid wastes as obtained from SRP burial records, and are equal to or less than those for Class B waste in 10 CFR 61. The first disposal units constructed are twenty 9-ft-diam, 30-ft-deep boreholes. These holes will be used to dispose of wastes from the production reactors, tritiated wastes, and selected wastes from offsite. In 1984, construction will begin on an engineered GCD trench for disposal of boxed waste and large bulky items that meet the activity concentration criteria. 4 references, 5 figures, 2 tables

  11. Quality assurance program manual for nuclear power plants. Volume I. Policies

    International Nuclear Information System (INIS)

    1976-01-01

    The Consumers Power Company Quality Assurance Program Manual for Nuclear Power Plants consists of policies and procedures which comply with current NRC regulatory requirements and industry codes and standards in effect during the design, procurement, construction, testing, operation, refueling, maintenance, repair and modification activities associated with nuclear power plants. Specific NRC and industry documents that contain the requirements, including the issue dates in effect, are identified in each nuclear power plant's Safety Analysis Report. The requirements established by these documents form the basis for the Consumer Power Quality Assurance Program, which is implemented to control those structures, systems, components and operational safety actions listed in each nuclear power plant's Quality List (Q-List). As additional and revised requirements are issued by the NRC and professional organizations involved in nuclear activities, they will be reviewed for their impact on this manual, and changes will be made where considered necessary. CP Co 1--Consumers Power Company QA Program Topical Report is Volume I of this manual and contains Quality Assurance Program Policies applicable during all phases of nuclear power plant design, construction and operation

  12. Aquatic Plant Control Research Program. Use of the White Amur for Aquatic Plant Management.

    Science.gov (United States)

    1984-08-01

    the body cavities. Curvature of the spine can Black Bass Act (16 U.S.C. 856-856). This result from imbalanced diets in some areas. law, which supports... Malaysian Aquwculture Joural frequently publish papers on the white Proceeding. of te Indo-PaW Fisheries Council amur (Table Al). Publications which...prepared diets . Data on plant consumption are found in The following popular articles present Woynarovich (1968), Vietmeyer (1976) and positive and

  13. Optimization of planting pattern plan in Logung irrigation area using linear program

    Science.gov (United States)

    Wardoyo, Wasis; Setyono

    2018-03-01

    Logung irrigation area is located in Kudus Regency, Central Java Province, Indonesia. Irrigation area with 2810 Ha of extent is getting water supply from Logung dam. Yet, the utilization of water at Logung dam is not optimal and the distribution of water is still not evenly distributed. Therefore, this study will discuss about the optimization of irrigation water utilization based on the beginning of plant season. This optimization begins with the analysis of hydrology, climatology and river discharge in order to determine the irrigation water needs. After determining irrigation water needs, six alternatives of planting patterns with the different early planting periods, i.e. 1st November, 2nd November, 3rd November, 1st December, 2nd December, and 3rd December with the planting pattern of rice-secondary crop-sugarcane is introduced. It is continued by the analysis of water distribution conducted using linear program assisted by POM-Quantity method for Windows 3 with the reliable discharge limit and the available land area. Output of this calculation are to determine the land area that can be planted based on the type of plant and growing season, and to obtaine the profits of harvest yields. Based on the optimum area of each plant species with 6 alternatives, the most optimum area was obtained at the early planting periods on 3rd December with the production profit of Rp 113.397.338.854,- with the planting pattern of rice / beans / sugarcane-rice / beans / sugarcane-beans / sugarcane.

  14. European passive plant program A design for the 21st century

    International Nuclear Information System (INIS)

    Adomaitis, D.; Oyarzabal, M.

    1998-01-01

    In 1994, a group of European utilities initiated, together with Westinghouse and its industrial partner GENESI (an Italian consortium including ANSALDO and FIAT), a program designated EPP (European Passive Plant) to evaluate Westinghouse passive nuclear plant technology for application in Europe. The following major tasks were accomplished: (1) the impacts of the European utility requirements (EUR) on the Westinghouse nuclear island design were evaluated; and (2) a 1000 MWe passive plant reference design (EP1000) was established which conforms to the EUR and is expected to be licensable in Europe. With respect to safety systems and containment, the reference plant design closely follows that of the Westinghouse simplified pressurized water reactor (SPWR) design, while the AP600 plant design has been taken as the basis for the EP1000 reference design in the auxiliary system design areas. However, the EP1000 design also includes features required to meet the EUR, as well as key European licensing requirements. (orig.)

  15. Integrated Plant Safety Assessment, Systematic Evaluation Program: Yankee Nuclear Power Station (Docket No. 50-29)

    International Nuclear Information System (INIS)

    1987-10-01

    The US Nuclear Regulatory Commission (NRC) has prepared Supplement 1 to the final Integrated Plant Safety Assessment Report (IPSAR) (NUREG-0825), under the scope of the Systematic Evaluation Program (SEP), for Yankee Atomic Electric Company's Yankee Nuclear Power Station located in Rowe, Massachusetts. The SEP was initiated by the NRC to review the design of older operating nuclear power plants to reconfirm and document their safety. This report documents the review completed under the SEP for those issues that required refined engineering evaluations or the continuation of ongoing evaluations after the Final IPSAR for the Yankee plant was issued. The review has provided for (1) an assessment of the significance of differences between current technical positions on selected safety issues and those that existed when Yankee was licensed, (2) a basis for deciding how these differences should be resolved in an integrated plant review, and (3) a documented evaluation of plant safety. 2 tabs

  16. Programs of plant life management at NPP Dukovany

    International Nuclear Information System (INIS)

    Pochman, K.; Ruscak, M.; Brumovsky, M.

    2000-01-01

    The program of lifetime management at NPP Dukovany is oriented towards an effective usage of facilities while keeping their safety parameters, mainly concerning nuclear safety. The goal is to achieve maximum usage of the design lifetime under the condition of fulfilling above mentioned requirements. Evaluation procedures have been prepared for selected components. These are subsequently discussed and approved by the State Office of Nuclear Safety. The databases of original data are built up regarding the evaluated components. The input data are completed as well according to the approved procedures. Generally valid approaches based on the evaluation of all possible degradation mechanisms are modified regarding the original status of particular component. The procedures are oriented towards a quantification of residual lifetime. They employ knowledge of initiation and kinetics of degradation mechanisms. They also define mechanisms, which should be quantified. For irreplaceable components or components whose replacement is difficult, the program is focused to the control of operation conditions and inspection of facilities. However, they are again based on the knowledge of degradation kinetics. If at least some parts of the facility could be replaced, better material selection regarding the operation conditions is an option. Systems included into the ageing management system will be specified in the paper. Also, the measures will be identified which serve as a check of implementation of all possible stressors and degradation mechanisms into the first screening. The examples of lifetime evaluation of some systems and components will be given in the paper: reactor pressure vessel, reactor internals, steam generator tubes and feedwater piping. Specific approaches will be shown fro different original status of components and different operation conditions. (author)

  17. Rockwell International's Critical Mass Laboratory Program at the Rocky Flats Plant

    International Nuclear Information System (INIS)

    McCarthy, J.D.

    1984-01-01

    The primary mission of the laboratory is to provide data in support of plant operations. To fulfill this task, the facility has unique capabilities for perfoming general purpose critical mass experiment. The critical mass laboratory performed over 1000 critical measurements, primarily with plutonium metal and uranium metal, oxide and solution; it worked also on the NRC program (high-enriched uranium measurements). Presently the laboratory staff prepares for a series of critical measurements on a poisoned tube tank; the laboratory intends to continue to pursue basic plant support programs in the future

  18. Mark II containment lead plant program load evaluation and acceptance criteria

    International Nuclear Information System (INIS)

    1978-10-01

    The report, prepared by the Office of Nuclear Reactor Regulation, addresses the portion of the Mark II owner's program that provides a generic methodology for establishing design basis LOCA and safety relief valve loads for the lead Mark II facilities (Zimmer, Shoreham, and LaSalle), i.e., the lead plant program. The report includes an evaluation of the Mark II owner's load methodology, a description of load methodologies that we find acceptable for use in the individual plant unique assessments, and the basis for the stated conclusions

  19. Availability Improvement Program for Louisiana Power and Light's Waterford 3 Nuclear Power Plant

    International Nuclear Information System (INIS)

    Simoneaux, G.E.

    1985-01-01

    The Middle South Utilities System (MSUS) began an Availability Improvement Program (AIP) in the late nineteen-seventies for the benefit of all the operating units making up the System. This paper describes the methodology that is being employed in implementing a formal Avalability Improvement Program for a new nuclear unit known as Waterford 3. The tasks needed to install and maintain the AIP at Waterford 3 are discussed in terms of Analytical Methodology, Avalability Data System, and Plant Imvolvement. In particular, the AIP will provide: Management reporting; External reporting; A self-sufficient core of trained avalability personnel; Procedures and methodologies to monitor plant availability and to analyze availability problems

  20. The computer program system for structural design of nuclear power plants

    International Nuclear Information System (INIS)

    Aihara, S.; Atsumi, K.; Sasagawa, K.; Satoh, S.

    1979-01-01

    In recent days, the design method of the Nuclear Power Plant has become more complex than in the past. The Finite Element Method (FEM) applied for analysis of Nuclear Power Plants, especially requires more computer use. The recent computers have made remarkable progress, so that in design work manpower and time necessary for analysis have been reduced considerably. However, instead the arrangement of outputs have increased tremendously. Therefore, a computer program system was developed for performing all of the processes, from data making to output arrangement, and rebar evaluations. This report introduces the computer program system pertaining to the design flow of the Reactor Building. (orig.)

  1. Fundamental attributes of a practical configuration management program for nuclear plant design control

    International Nuclear Information System (INIS)

    Klein, S.M.

    1988-06-01

    This summarizes the results of an evaluation of findings identifies during a number of Safety-System Functional Inspections and Safety System Outage Modification Inspections which are related to configuration management for nuclear plant design control. A computerized database of these findings was generated from a review of the design inspection reports. Based on the results of the evaluation, attributes of a configuration management program were developed which are responsive to minimizing these types of inspection findings. Incorporation of these key attributes is considered good practice in the development of a configuration management program for design control at operating nuclear plants

  2. Operating experience review for nuclear power plants in the Systematic Evaluation Program

    International Nuclear Information System (INIS)

    Mays, G.T.; Harrington, K.H.

    1982-01-01

    The Systematic Evaluation Program Branch (SEPB) of the Nuclear Regulatory Commission (NRC) is conducting the Systematic Evaluation Program (SEP) whose purpose is to determine the safety margins of the design and operation of the eleven oldest operating commercial nuclear power plants in the United States. This paper describes the methodology and results of the operational experience review portion of the SEP evaluation. SEPB will combine the results from these operational reviews with other safety topic evaluations to perform an integrated assessment of the SEP plants

  3. Waste Isolation Pilot Plant transuranic wastes experimental characterization program: executive summary

    International Nuclear Information System (INIS)

    Molecke, M.A.

    1978-11-01

    A general overview of the Waste Isolation Pilot Plant transuranic wastes experimental characterization program is presented. Objectives and outstanding concerns of this program are discussed. Characteristics of transuranic wastes are also described. Concerns for the terminal isolation of such wastes in a deep bedded salt facility are divided into two phases, those during the short-term operational phase of the facility, and those potentially occurring in the long-term, after decommissioning of the repository. An inclusive summary covering individual studies, their importance to the Waste Isolation Pilot Plant, investigators, general milestones, and comments are presented

  4. N Reactor Production Assurance Program blance of plant evaluation: report of findings and conclusions

    International Nuclear Information System (INIS)

    Hurd, E.N.; Bitten, E.J.

    1985-03-01

    Fourteen tasks were identified by UNC Nuclear Industries for evaluating the life expectancy of N Reactor structures, systems and components in the Balance of Plant portion of the Production Assurance Program. A Westinghouse Hanford Company (WHC) evaluation team was assigned to each of these fourteen tasks. A uniform set of criteria was used by all teams in evaluating the problems that may be encountered during the extended plant operating lifetime. The overall conclusion is that extended life to those Balance of Plant components and systems studied can be achieved. Problems with the potential for compromising that conclusion are identified, and feasible solutions are provided

  5. An overview of the United States Department of Energy Plant Lifetime Improvement Program

    International Nuclear Information System (INIS)

    Rosinski, S.T.; Clauss, J.M.; Harrison, D.L.

    2004-01-01

    Since 1985, the U.S. Department of Energy (DOE) has been working with the nuclear industry and the U.S. Nuclear Regulatory Commission (NRC) to establish and demonstrate the option to extend the life of nuclear power plants through the renewal of operating licenses. This paper focuses primarily on DOE'S Plant Lifetime Improvement (PLIM) Program efforts to develop the technical criteria and bases for effective aging management and lifetime improvement for continued operation of nuclear power plants. This paper describes current projects to resolve generic technical issues, including degradation of long-lived components, reactor pressure vessel (RPV) embrittlement management approaches, and analytical methodologies to characterize RPV integrity. (author)

  6. Monitoring programmed cell death of living plant tissues in microfluidics using electrochemical and optical techniques

    DEFF Research Database (Denmark)

    Mark, Christina; Heiskanen, Arto; Svensson, Birte

    Programmed cell death (PCD) in plants can influence the outcome of yield and quality of crops through its important role in seed germination and the defence process against pathogens. The main scope of the project is to apply microfluidic cell culture for the measurement of electrochemically......, since it is known that reactive oxygen species, which are affected by changes in the redox activity of the cells3, are involved in PCD in plants, but the relationship between and mechanisms behind ROS and PCD is only poorly understood in plant cells4. Recently, it has been shown, using optical detection...

  7. The Development of a Cultural-Based Educational Program to Enhance Breast Self-Examination (BSE Self-Efficacy

    Directory of Open Access Journals (Sweden)

    Juanita Juanita

    2012-08-01

    Full Text Available Purpose: To develop the educational program which is appropriate with Islamic culture in order to enhance BSE self-efficacy of nursing students and thus promote BSE practice. Method: This study is a development research study which is consisting of three phases including: 1 reviewing several existing BSE educational programs; 2 program design based on SCT and Islamic culture; and 3 program validation by three experts. Result: Based on previous studies, the most appropriate theory to enhance self-efficacy was Social Cognitive Theory (SCT because this theory provides several strategies to increase the self-efficacy. Further, the program that used Islamic culture was more appropriate to increase BSE practice among Muslim women. As a result, the newly developed program was developed used SCT and Islamic culture. This program was comprised of four sessions including: 1 exploring Islamic mandate on prevention and individual responsibility in health promotion, and culture-related beliefs toward BSE, 2 health education by conducting lecturing session and watching a video about BSE procedures, 3 BSE training activities including BSE demonstration and return demonstration, 4 follow-up by conducting a meeting. Conclusion: The cultural-based educational program for enhancing BSE self-efficacy and promoting BSE is a program using multifaceted methods. It designed based on a review of the literature from previous studies and were supported by research findings on experimental studies in other population. Keywords: Cultural, Educational program development, Breast self-examination, Self-efficacy.

  8. Systems theory as a framework for examining a college campus-based support program for the former foster youth.

    Science.gov (United States)

    Schelbe, Lisa; Randolph, Karen A; Yelick, Anna; Cheatham, Leah P; Groton, Danielle B

    2018-01-01

    Increased attention to former foster youth pursuing post-secondary education has resulted in the creation of college campus based support programs to address their need. However, limited empirical evidence and theoretical knowledge exist about these programs. This study seeks to describe the application of systems theory as a framework for examining a college campus based support program for former foster youth. In-depth semi-structured interviews were conducted with 32 program stakeholders including students, mentors, collaborative members, and independent living program staff. Using qualitative data analysis software, holistic coding techniques were employed to analyze interview transcripts. Then applying principles of extended case method using systems theory, data were analyzed. Findings suggest systems theory serves as a framework for understanding the functioning of a college campus based support program. The theory's concepts help delineate program components and roles of stakeholders; outline boundaries between and interactions among stakeholders; and identify program strengths and weakness. Systems theory plays an important role in identifying intervention components and providing a structure through which to identify and understand program elements as a part of the planning process. This study highlights the utility of systems theory as a framework for program planning and evaluation.

  9. GESIT: a thermodynamic program for single cycle gas turbine plants with and without intercoolers

    Energy Technology Data Exchange (ETDEWEB)

    Heil, J

    1973-08-01

    A computer program for the thermodynamic modeling of singlecycle gas turbine plants is described. A high-temperature reactor is assumed as a heat source in the program, but the HTR can be replaced with another heat source without difficulty. Starting from a set of independent data, the program calculates efficiencies and mass flows. It indicates all values for a heat and power balance and prints out the temperatures and pressures for the different parts of the cycle. Besides this, the program is able to optimize the compression ratios for minimal power input. It also takes into account turbine rotor cooling (at the roots of the blades). Furthermore, the program is able to use either total pressure loss or specified losses in different parts of the cycle. The program GESlT can also handle systems with one or two intercoolers, or with no intercooler. GESIT gives all input and output values for the heat exchangers and turbo-machines. First the single-cycle gas turbine plant is described. After that the computational basis for the program and the program structure is explained. Instructions for data input are given so that the program can be immediately utilized. An example of input data together with the associated output is presented. (auth)

  10. The Influence of Using TI-84 Calculators with Programs on Algebra I High Stakes Examinations

    Science.gov (United States)

    Spencer, Misty

    2013-01-01

    The purpose of this study was to determine if there was a significant difference in scores on the Mississippi Algebra I SATP2 when one group was allowed to use programs and the other group was not allowed to use programs on TI-84 calculators. An additional purpose of the study was also to determine if there was a significant difference in the…

  11. Does Teaching Experience Matter? Examining Biology Teachers' Prior Knowledge for Teaching in an Alternative Certification Program

    Science.gov (United States)

    Friedrichsen, Patricia J.; Abell, Sandra K.; Pareja, Enrique M.; Brown, Patrick L.; Lankford, Deanna M.; Volkmann, Mark J.

    2009-01-01

    Alternative certification programs (ACPs) have been proposed as a viable way to address teacher shortages, yet we know little about how teacher knowledge develops within such programs. The purpose of this study was to investigate prior knowledge for teaching among students entering an ACP, comparing individuals with teaching experience to those…

  12. Recruitment Strategies Aiming to Attract Females into Undergraduate Engineering Programs: Examining Their Role and Use

    Science.gov (United States)

    Howenstine, Julie Anne

    2013-01-01

    By 2009, the percentage of women who graduated with general undergraduate degrees had increased to almost 58% of all students who completed 4-year degree programs (National Center for Education Statistics, 2009a). These percentages, however, have not been reflected in the enrollment rates of females into undergraduate engineering programs. In…

  13. An Examination of the Feasibility of Integrating Motivational Interviewing Techniques into FCS Cooperative Extension Programming

    Science.gov (United States)

    Radunovich, Heidi Liss; Ellis, Sarah; Spangler, Taylor

    2017-01-01

    Demonstrating program impact through behavior change is critical for the continued success of Family and Consumer Sciences (FCS) Cooperative Extension programming. However, the literature suggests that simply providing information to participants does not necessarily lead to behavior change. This study pilot tested the integration of Motivational…

  14. A Study Examining the Dimensionality of Core Competencies Measure in Teacher Preparation Programs: Challenges and Lessons

    Science.gov (United States)

    Kizil, Ruhan Circi; Briggs, Derek; Seidel, Kent; Green, Kathy

    2014-01-01

    The evidence that teacher preparation programs have an impact on teacher quality is often limited. Progress in research on this topic will remain rather limited in its influence on practice until more proximal measures of teacher education outcomes can be established. The dearth of variables to measure the impact of teacher preparation programs on…

  15. Regulatory oversight strategy for chemistry program at Canadian nuclear power plants

    International Nuclear Information System (INIS)

    Kameswaran; Ram

    2012-09-01

    Chemistry program is one of the essential programs for the safe operation of a nuclear power plant. It helps to ensure the necessary integrity, reliability and availability of plant structures, systems and components important to safety. Additionally, the program plays an important role in asset preservation, limiting radiation exposure and environmental protection. A good chemistry program will minimize corrosion of materials, reduce activation products, minimize of the buildup of radioactive material leading to occupational radiation exposure and it helps limit the release of chemicals and radioactive materials to the environment. The legal basis for the chemistry oversight at Canadian NPPs is established by the Nuclear Safety and Control Act and its associated regulations. It draws on the Canadian Nuclear Safety Commission's regulatory framework and NPP operating license conditions that include applicable standards such as CAN/CSA N286-05 Management System Requirements for Nuclear Power Plants. This paper focuses on the regulatory oversight strategy used in Canada to assess the performance of chemistry program at the nuclear power plants (NPPs) licensed by CNSC. The strategy consists of a combination of inspection and performance monitoring activities. The activities are further supported from information gathered through staff inspections of cross-cutting areas such as maintenance, corrective-action follow-ups, event reviews and safety related performance indicators. (authors)

  16. Oak Ridge Y-12 Plant biological monitoring and abatement program (BMAP) plan

    Energy Technology Data Exchange (ETDEWEB)

    Adams, S.M.; Brandt, C.C.; Cicerone, D.S. [and others

    1998-02-01

    The proposed Biological Monitoring and Abatement Program (BMAP) for East Fork Poplar Creek (EFPC) at the Oak Ridge Y-12 Plant, as described, will be conducted for the duration of the National Pollutant Discharge Elimination System permit issued for the Y-12 Plant on April 28, 1995, and which became effective July 1, 1995. The basic approach to biological monitoring used in this program was developed by the staff in the Environmental Sciences Division at the Oak Ridge National Laboratory at the request of Y-12 Plant personnel. The proposed BMAP plan is based on results of biological monitoring conducted since 1985. Details of the specific procedures used in the current routine monitoring program are provided, but experimental designs for future studies are described in less detail. The overall strategy used in developing this plan was, and continues to be, to use the results obtained from each task to define the scope of future monitoring efforts. Such efforts may require more intensive sampling than initially proposed in some areas or a reduction in sampling intensity in others. By using the results of previous monitoring efforts to define the current program and to guide them in the development of future studies, an effective integrated monitoring program has been developed to assess the impacts of the Y-12 Plant operation on the biota of EFPC and to document the ecological effects of remedial actions.

  17. Oak Ridge Y-12 Plant biological monitoring and abatement program (BMAP) plan

    International Nuclear Information System (INIS)

    Adams, S.M.; Brandt, C.C.; Cicerone, D.S.

    1998-02-01

    The proposed Biological Monitoring and Abatement Program (BMAP) for East Fork Poplar Creek (EFPC) at the Oak Ridge Y-12 Plant, as described, will be conducted for the duration of the National Pollutant Discharge Elimination System permit issued for the Y-12 Plant on April 28, 1995, and which became effective July 1, 1995. The basic approach to biological monitoring used in this program was developed by the staff in the Environmental Sciences Division at the Oak Ridge National Laboratory at the request of Y-12 Plant personnel. The proposed BMAP plan is based on results of biological monitoring conducted since 1985. Details of the specific procedures used in the current routine monitoring program are provided, but experimental designs for future studies are described in less detail. The overall strategy used in developing this plan was, and continues to be, to use the results obtained from each task to define the scope of future monitoring efforts. Such efforts may require more intensive sampling than initially proposed in some areas or a reduction in sampling intensity in others. By using the results of previous monitoring efforts to define the current program and to guide them in the development of future studies, an effective integrated monitoring program has been developed to assess the impacts of the Y-12 Plant operation on the biota of EFPC and to document the ecological effects of remedial actions

  18. Relevant aspects of a quality assurance program applied to a nuclear power plant operation

    International Nuclear Information System (INIS)

    Fernandez, J.C.

    1987-01-01

    The purpose of this work was to enumerate the most relevant subjects to be taken into account for the elaboration of a Quality Assurance Program aimed to regulate a nuclear power plant operation. At first, it was necessary to point out the relevance that implies the presence of a group of personnel, experienced in quality assurance with enough knowledge on the technical and organizing aspects of the plant. Other aspect to be taken into account was the contemplation of the international requirements, through the International Atomic Energy Agency and of the national requirements that each country had set up by the corresponding regulating agencies. These organizations pointed out the minimum rules that must be followed for the adequate and efficient execution of a program. The Quality Assurance Manual and the program and work procedures constituted the Quality Assurance Program which must be checked as regards its fulfillment by auditors and quality assurance supervisions. (Author)

  19. NRC research program on plant aging: Listing and summaries of reports issued through July 1992

    International Nuclear Information System (INIS)

    Kondic, N.N.

    1992-09-01

    The US Nuclear Regulatory Commission is conducting the Nuclear Plant Aging Research (NPAR) Program. This is a comprehensive hardware-oriented engineering research program focused on understanding the aging mechanisms of components and systems in nuclear power plants. The NPAR program also focuses on methods for simulating and monitoring the aging-related degradation of these components and systems. In addition, it provides recommendations for effective maintenance to manage aging and for implementation of the research results in the regulatory process. This document contains a listing and index of reports generated in the NPAR Program that were issued through July 1992 and summaries of those reports. Each summary describes the elements of the research covered in the report and outlines the significant results. For the convenience of the user, the reports are indexed by personal author, corporate author, and subject

  20. NRC Research Program on Plant Aging: Listing and summaries of reports issued through June 1991

    International Nuclear Information System (INIS)

    Kondic, N.N.; Hill, E.L.

    1991-07-01

    The US Nuclear Regulatory Commission is conducting the Nuclear Plant Aging Research (NPAR) Program. This is a comprehensive hardware-oriented engineering research program focused on understanding the aging mechanisms of components and systems in nuclear power plants. The NPAR program also focuses on methods for simulating and monitoring the aging-related degradation of these components and systems. In addition, it provides recommendations for effective maintenance to manage aging and for the implementation of the research results in the regulatory process. This document contains a listing and index of reports generated in the NPAR Program that were issued through June 1991 and summaries of those reports. Each summary describes the elements of the research covered in the report and outlines the significant results. For the convenience of the user, the reports are indexed by personal author, corporate author, and subject. 102 refs

  1. NRC research program on plant aging: Listing and abstracts of reports issued through February 1, 1989

    International Nuclear Information System (INIS)

    Kondic, N.N.

    1989-08-01

    The US Nuclear Regulatory Commission is conducting the Nuclear Plant Aging Research (NPAR) Program. This is a comprehensive hardware-oriented program focused on understanding the aging mechanisms of components and systems in nuclear plants. The NPAR Program also focuses on methods for simulating and monitoring the aging-related degradation of these components and systems. This document contains a listing and index of reports generated in the NPAR Program that were issued through February 1, 1989, and abstracts of those reports. Each abstract describes the elements of the research covered in the report and outlines the significant results. For the convenience of the user, the reports are indexed by personal author, corporate author, and subject

  2. NRC research program on plant aging: Listing and summaries of reports issued through May 1990

    International Nuclear Information System (INIS)

    Kondic, N.N.; Hill, E.L.

    1990-07-01

    The US Nuclear Regulatory Commission is conducting the Nuclear Plant Aging Research (NPAR) Program. This is a comprehensive hardware-oriented engineering research program focused on understanding the aging mechanisms of components and systems in nuclear plants. The NPAR program also focuses on methods for simulating and monitoring the aging-related degradation of these components and systems. In addition, it provides recommendations for effective maintenance to manage aging and for the implementation of the research results in the regulatory process. This document contains a listing and index of reports generated in the NPAR Program that were issued through May 1990 and summaries of those reports. Each summary describes the elements of the research covered in the report and outlines the significant results. For the convenience of the user, the reports are indexed by personal author, corporate author, and subject

  3. Senescence and programmed cell death in plants: polyamine action mediated by transglutaminase

    Directory of Open Access Journals (Sweden)

    Stefano eDel Duca

    2014-04-01

    Full Text Available Research on polyamines in plants laps a long way of about 50 years and many roles have been discovered for these aliphatic cations. Polyamines regulate cell division, differentiation, organogenesis, reproduction, dormancy-break and senescence, homeostatic adjustments in response to external stimuli and stresses. Nevertheless, the molecular mechanisms of their multiple activities are still matter of research. Polyamines are present in free and bound forms and interact with several important cell molecules; some of these interactions may occur by covalent linkages catalyzed by transglutaminase, giving rise to ‘cationisation’ or cross-links among specific proteins. Senescence and PCD can be delayed by polyamines; in order to re-interpret some of these effects and to obtain new insights into their molecular mechanisms, their conjugation has been revised here. The transglutaminase-mediated interactions between proteins and polyamines are the main target of this review. After an introduction on the characteristics of this enzyme, on its catalysis and role in PCD in animals, the plant senescence and PCD models in which TGase has been studied, are presented: the corolla of naturally senescing or excised flowers, the leaves senescing, either excised or not, the pollen during self-incompatible pollination, the hypersensitive response and the tuber storage parenchyma during dormancy release. In all the models examined, transglutaminase appears to be involved by a similar molecular mechanism as described during apoptosis in animal cells, even though several substrates are different. Its effect is probably related to the type of PCD, but mostly to the substrate to be modified in order to achieve the specific PCD program. As a cross-linker of polyamines and proteins, transglutaminase is an important factor involved in multiple, sometimes controversial, roles of polyamines during senescence and PCD.

  4. Examining quality of contraceptive services for adolescents in Oregon's family planning program.

    Science.gov (United States)

    Rodriguez, Maria Isabel; Darney, Blair G; Elman, Emily; Linz, Rachel; Caughey, Aaron B; McConnell, K John

    2015-04-01

    To assess the quality of care provided to adolescents (10-19 years old) compared to women (aged 20-25 years) who accessed services in Oregon's Contraceptive Care (CCare) program. We analyzed data routinely collected using the Clinic Visit Record form from women aged 25 years and younger who visited CCare clinics between January 1, 2004, and October 31, 2010. Modern methods were characterized into three tiers: Tier 1 is the intrauterine device, implant and sterilization; Tier 2, hormonal methods; and Tier 3, all barrier methods. Nonmodern methods included no method, withdrawal and natural family planning. We used multivariable logistic regression models to examine the effect of age on three indicators of quality of contraceptive care: transitioning from a nonmodern to a modern method, transitioning from Tier 3 methods to Tier 1 or Tier 2 methods, and initiation of long-acting reversible contraception (LARC). We then produced predicted probabilities to facilitate data interpretation. Adolescents accounted for 344,856 (41%) of the 848,221 clinic visits occurring in CCare among women under age 25. Compared with women (ages 20-25 years), young and older adolescents had decreased odds of LARC initiation [odds ratio (OR) 0.24 (95% confidence interval [CI] 0.16-0.35) and OR 0.44 (95% CI 0.38-0.52), respectively]. However, compared with women, both young and older adolescents had increased odds of leaving with any contraceptive method [OR 1.8 95% (CI 1.26-2.59) and OR 1.42 (95% CI 1.21-1.66)]. Among clients presenting with no method of contraception at the beginning of the visit, 78.7% of young adolescents (95% CI 73.84-83.03) compared with 81.44% (95% CI 77.02-85.52) of older adolescents, and 76.63% (95% CI 69.90-80.75) of young women left with a modern method, controlling for other covariates. Although adolescents served by CCare are more likely to initiate contraception, they are less likely to receive LARC than women aged 20-25 years. Efforts are needed to ensure that

  5. Insights from the U.S. department of Energy plant safety evaluation program of VVER and RBMK reactors

    International Nuclear Information System (INIS)

    Petri, M.C.; Binder, J.L.; Pasedag, W.F.

    2001-01-01

    Throughout the years 1990 the U.S. Department of Energy has worked build capability in countries of the former Soviet Union to assess the safety of their VVER and RBMK reactors. Through this Plant Safety Evaluation Program, deterministic and probabilistic analyses have been used to provide a documented plant risk profile to support safe plant operation and to set priorities for safety upgrades. Work has been sponsored at thirteen nuclear power plant sites in eight countries. The Plant Safety Evaluation Program has resulted in immediate and long-term safety benefits for the Soviet-designed nuclear plants. (author)

  6. The program of reactors and nuclear power plants; Programa de reactores y centrales nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Calabrese, Carlos R [Comision Nacional de Energia Atomica, General San Martin (Argentina). Centro Atomico Constituyentes

    2001-07-01

    Into de framework of the program of research reactors and nuclear power plants, the operating Argentine reactors are described. The uses of the research reactors in Argentina are summarized. The reactors installed by Argentina in other countries (Peru, Algeria, Egypt) are briefly described. The CAREM project for the design and construction of an innovator small power reactor (27 MWe) is also described in some detail. The next biennial research and development program for reactor is briefly outlined.

  7. Using the baseline environmental management report (BEMR) to examine alternate program scenarios

    International Nuclear Information System (INIS)

    Kristofferson, K.

    1995-01-01

    The US Department of Energy's (DOE) Office of Environmental Management (EM) released the first Baseline Environmental Management Report (BEMR) in March, 1995. The Congressionally-mandated report provides life-cycle cost estimates, tentative schedules, and projected activities necessary to complete DOE's Environmental Management Program. This ''base case'' estimate is based on current program assumptions and the most likely set of activities. However, since the future course of the Environmental Management Program depends upon a number of fundamental technical and policy choices, alternate program scenarios were developed. These alternate cases show the potential cost impacts of changing assumptions in four key areas: future land use, program funding and scheduling, technology development, and waste management configurations. Several cost and program evaluation tools were developed to support the analysis of these alternate cases. The objective of this paper is to describe the analytical tool kit developed to support the development of the 1995 Baseline Report and to discuss the application of these tools to evaluate alternate program scenarios

  8. An Examination of Georgia Young Farmer Program Participants’ Learning Style Preferences

    Directory of Open Access Journals (Sweden)

    Barry S. Bailey

    2017-10-01

    Full Text Available This study was designed to describe Georgia Young Farmer Program participants’ learning style preferences. Using survey research methods, a questionnaire was designed to collect data related to the purpose of the study. The population for this study included active members in the program. Study findings showed that participants had a preference for kinesthetic learning over visual and auditory learning. While participants indicated a preference for kinesthetic learning, all three learning styles were deemed effective. Preferences for learning styles and perception of effectiveness did not differ by personal characteristics. Recommendations include taking learning style preferences into account when designing and delivering programming, training for teachers, and continuing to assess learners’ preferences.

  9. Examining the Effectiveness of the Smoking Prevention Program "I Do Not Smoke, I Exercise" in Elementary and Secondary School Settings.

    Science.gov (United States)

    Kolovelonis, Athanasios; Goudas, Marios; Theodorakis, Yannis

    2016-11-01

    The aim of the study was to examine the effectiveness of the smoking prevention program "I do not smoke, I exercise" implemented with elementary and secondary school students. "I do not smoke, I exercise" is a theory-based smoking prevention program that promotes exercise as an alternative of smoking. The program consists of eight sessions implemented weekly. Participants were 338 Greek students (135 elementary and 203 secondary students) who were pre- and posttested in smoking, program, and exercise-related measures. The results showed that the program had significant effects on elementary students' attitudes toward smoking, intention to smoke, subjective norms, attitudes toward the application of the program, and knowledge about the health consequences of smoking. For secondary students, significant effects were found on students' perceived behavioral control and knowledge about the health consequences of smoking, while very few students reported a smoking experience before and after the intervention. Therefore the program "I do not smoke, I exercise" may have positive effects on variables related with smoking behavior. Differences in the program's impact on elementary and secondary students were identified. All these are discussed with reference to the need of implementing smoking prevention programs in schools contexts. © 2016 Society for Public Health Education.

  10. An examination of factors that hinder and programs that stimulate Papuan entrepreneurs

    NARCIS (Netherlands)

    Burg, van J.C.

    2007-01-01

    This report describes the results of a study on entrepreneurship in the Indonesian province Papua. The study was performed for Oikonomos Foundation to help evaluating the current entrepreneurship support programs and to identify future challenges. Seven important difficulties for Papuan

  11. Examining the Leisure Constraints Affecting International Collegiate Students’ Participation in Intramural Sport Programs

    OpenAIRE

    Dongwook Cho; Taryn Price

    2016-01-01

    A primary objective of United States’ higher education institutions is the production of well-balanced citizens. Aside from awarded degrees, other primary offerings include leisure opportunities, from campus recreation programs. Campus recreation through intramural sport programs offers students an opportunity to participate in sport and physical fitness activities on campus with and against other collegiate students. Recognizing the continuous increase in collegiate enrollment of internation...

  12. Integrated Plant Safety Assessment: Systematic Evaluation Program. Haddam Neck Plant, Connecticut Yankee Atomic Power Company, Docket No. 50-213. Final report

    International Nuclear Information System (INIS)

    1983-01-01

    The Systematic Evaluation Progam was initiated in February 1977 by the US Nuclear Regulatory Commission review the designs of older operating nuclear reactor plants to confirm and document their safety. The review provides: (1) an assessment of how these plants compare with curent licensing safety requirements relating to selected issues, (2) a basis for deciding on how these differences should be resolved in an integrated plant review, and (3) a documented evaluation of plant safety. This report documents the review of Haddam Neck Plant, operated by Connecticut Yankee Atomic Power Company. The Haddam Neck Plant is one of 10 plants reviewed under Phase II of this program. This report indicates how 137 topics selected for review under Phase I of the program were addressed. Equipment and procedural changes have been identified as a result of the review

  13. A reliability program for emergency diesel generators at nuclear power plants: Program structure

    International Nuclear Information System (INIS)

    Lofgren, E.V.; DeMoss, G.M.; Fragola, J.R.; Appignani, P.L.; Delarche, G.; Boccio, J.

    1988-04-01

    The purpose of this report is to provide technical guidelines for NRC staff use in the development of positions for evaluating emergency diesel generator (EDG) reliability programs. Such reviews will likely result following resolution of USI A-44 and GSI B-56. The diesel generator reliability program is a management system for achieving and maintaining a selected (or target) level of reliability. This can be achieved by: (1) understanding the factors that control the EDG reliability and (2) then applying reliability and maintenance techniques in the proper proportion to achieve selected performance goals. The concepts and guidelines discussed in this report are concepts and approaches that have been successful in applications where high levels of reliability must be maintained. Both an EDG reliability program process and a set of review items for NRC use are provided. The review items represent a checklist for reviewing EDG reliability programs. They do not, in themselves, constitute a reliability program. Rather, the review items are those distinctive features of a reliability program that must be present for the program to be effective

  14. Design and Assessment of an Associate Degree-Level Plant Operations Technical Education Program

    Science.gov (United States)

    Selwitz, Jason Lawrence

    2017-01-01

    Research was undertaken to develop and evaluate an associate degree-level technical education program in Plant Operations oriented towards training students in applied science, technology, engineering, and mathematics (STEM) skills and knowledge relevant to a spectrum of processing industries. This work focuses on four aspects of the curriculum…

  15. Native plant development and restoration program for the Great Basin, USA

    Science.gov (United States)

    N. L. Shaw; M. Pellant; P. Olweli; S. L. Jensen; E. D. McArthur

    2008-01-01

    The Great Basin Native Plant Selection and Increase Project, organized by the USDA Bureau of Land Management, Great Basin Restoration Initiative and the USDA Forest Service, Rocky Mountain Research Station in 2000 as a multi-agency collaborative program (http://www.fs.fed.us/rm/boise/research/shrub/greatbasin.shtml), has the objective of improving the availability of...

  16. Requirements for auditing of quality assurance programs for nuclear power plants

    International Nuclear Information System (INIS)

    Anon.

    1979-01-01

    Requirements and guidance are provided for establishing and implementing a system of internal and external audits of quality assurance programs for nuclear power plants, including the preparation, performance, reporting and follow-up of audits by both the auditing and the audited organizations. This standard is to be used in conjunction with ANSI N45.2

  17. Risk maps for targeting exotic plant pest detection programs in the United States

    Science.gov (United States)

    R.D. Magarey; D.M. Borchert; J.S. Engle; M Garcia-Colunga; Frank H. Koch; et al

    2011-01-01

    In the United States, pest risk maps are used by the Cooperative Agricultural Pest Survey for spatial and temporal targeting of exotic plant pest detection programs. Methods are described to create standardized host distribution, climate and pathway risk maps for the top nationally ranked exotic pest targets. Two examples are provided to illustrate the risk mapping...

  18. Quality assurance of analytical, scientific, and design computer programs for nuclear power plants

    International Nuclear Information System (INIS)

    1994-06-01

    This Standard applies to the design and development, modification, documentation, execution, and configuration management of computer programs used to perform analytical, scientific, and design computations during the design and analysis of safety-related nuclear power plant equipment, systems, structures, and components as identified by the owner. 2 figs

  19. Quality assurance of analytical, scientific, and design computer programs for nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-06-01

    This Standard applies to the design and development, modification, documentation, execution, and configuration management of computer programs used to perform analytical, scientific, and design computations during the design and analysis of safety-related nuclear power plant equipment, systems, structures, and components as identified by the owner. 2 figs.

  20. An overview of the US Department of Energy Plant Lifetime Improvement Program

    International Nuclear Information System (INIS)

    Moonka, A.K.; Harrison, D.L.

    1995-01-01

    This paper provides a brief summary of the U.S. Department of Energy's (USDOE's) cooperative effort with the nuclear industry to develop technology to manage the effects of material degradation in systems, structures and components (SSCs) that impact plant safety or can significantly improve plant performance/economics and to establish and demonstrate the license renewal process. Also included are efforts to reduce decontamination/decommission costs, and reduce the uncertainty in long-term service-life decision making. During 1995, the Plant Lifetime Improvement (PLIM) Program was renamed the Commercial Operating Light Water Reactor (COLWR) Program activities are focused on sustaining the LWR option for domestic electricity generation by supporting operation of existing LWRs as long as they are safe, efficient, and economical. The status of the key projects is discussed in this paper

  1. Reliability programs for nuclear power plants. Regulatory standard S-98 revision 1

    International Nuclear Information System (INIS)

    2005-07-01

    The purpose of this regulatory standard is to help assure, in accordance with the purpose of the Nuclear Safety and Control Act (NSCA), that a licensee who constructs or operates a nuclear power plant (NPP) develops and implements a reliability program that assures that the systems important to safety at the plant can and will meet their defined design and performance specifications at acceptable levels of reliability throughout the lifetime of the facility. This regulatory standard describes the requirements of a reliability program for a nuclear power plant. The licensee shall implement the requirements described in this regulatory standard when a condition of a licence or other legally enforceable instrument so requires.(author)

  2. Development of Web-Based Examination System Using Open Source Programming Model

    Science.gov (United States)

    Abass, Olalere A.; Olajide, Samuel A.; Samuel, Babafemi O.

    2017-01-01

    The traditional method of assessment (examination) is often characterized by examination questions leakages, human errors during marking of scripts and recording of scores. The technological advancement in the field of computer science has necessitated the need for computer usage in majorly all areas of human life and endeavors, education sector…

  3. A measurement control program for plutonium isotopic gamma-ray systems at the Rocky Flats Plant

    International Nuclear Information System (INIS)

    Fleissner, J.G.

    1986-01-01

    A sound measurement control (MC) program should be an integral part of every nondestructive assay measurement system used for the assay of special nuclear materials. This paper describes a measurement control program for plutonium isotopic composition measurements, using high-resolution gamma-ray spectroscopy, that has been implemented in the Analytical Laboratories and the Chemistry Standards Laboratory at the Rocky Flats Plant. This MC program emphasizes the standardization of data collection procedures along with the implementation of internal and external measurement control checks to provide the requisite measurement quality assurance

  4. Status of Pantex Plant Waste Management Project/program control system

    International Nuclear Information System (INIS)

    Price, Wesley J.; Matthews, William L.

    1992-01-01

    During a December 1990 Waste Management Program Review held in Albuquerque, New Mexico, the Waste Management and Operational Surety Division (WMOSD) introduced the project control system to be used for the Waste Management (WM) Operations Program. The system was entitled 'TRAC-WM' (Tracking and Control for Waste Management). The stated objective for this system was to establish a frame work for planning, managing, and controlling work within the WM program. As a result Mason and Hanger (the operating contractor at the Pantex Plant) initiated the development of a computerized waste management project tracking system. (author)

  5. Examining an underappreciated control on lignin decomposition in soils? Effects of reactive manganese species on intact plant cell walls

    Science.gov (United States)

    Keiluweit, M.; Bougoure, J.; Pett-Ridge, J.; Kleber, M.; Nico, P. S.

    2011-12-01

    Lignin comprises a dominant proportion of carbon fluxes into the soil (representing up to 50% of plant litter and roots). Two lines of evidence suggest that manganese (Mn) acts as a strong controlling factor on the residence time of lignin in soil ecosystems. First, Mn content is highly correlated with litter decomposition in temperate and boreal forest soil ecosystems and, second, microbial agents of lignin degradation have been reported to rely on reactive Mn(III)-complexes to specifically oxidize lignin. However, few attempts have been made to isolate the mechanisms responsible for the apparent Mn-dependence of lignin decomposition in soils. Here we tested the hypothesis that Mn(III)-oxalate complexes may act as a perforating 'pretreatment' for structurally intact plant cell walls. We propose that these diffusible oxidizers are small enough to penetrate and react with non-porous ligno-cellulose in cell walls. This process was investigated by reacting single Zinnia elegans tracheary elements with Mn(III)-oxalate complexes in a continuous flow-through microreactor. The uniformity of cultured tracheary elements allowed us to examine Mn(III)-induced changes in cell wall chemistry and ultrastructure on the micro-scale using fluorescence and electron microscopy as well as synchrotron-based infrared and X-ray spectromicroscopy. Our results show that Mn(III)-complexes substantially oxidize specific lignin components of the cell wall, solubilize decomposition products, severely undermine the cell wall integrity, and cause cell lysis. We conclude that Mn(III)-complexes induce oxidative damage in plant cell walls that renders ligno-cellulose substrates more accessible for microbial lignin- and cellulose-decomposing enzymes. Implications of our results for the rate limiting impact of soil Mn speciation and availability on litter decomposition in forest soils will be discussed.

  6. Preventing child maltreatment: Examination of an established statewide home-visiting program.

    Science.gov (United States)

    Chaiyachati, Barbara H; Gaither, Julie R; Hughes, Marcia; Foley-Schain, Karen; Leventhal, John M

    2018-05-01

    Although home visiting has been used in many populations in prevention efforts, the impact of scaled-up home-visiting programs on abuse and neglect remains unclear. The objective of this study was to assess the impact of voluntary participation in an established statewide home-visiting program for socially high-risk families on child maltreatment as identified by Child Protective Services (CPS). Propensity score matching was used to compare socially high-risk families with a child born between January 1, 2008 and December 31, 2011 who participated in Connecticut's home-visiting program for first-time mothers and a comparison cohort of families who were eligible for the home-visiting program but did not participate. The main outcomes were child maltreatment investigations, substantiations, and out-of-home placements by CPS between January 1, 2008 and December 31, 2013. In the unmatched sample, families who participated in home-visiting had significantly higher median risk scores (P home visiting. First substantiations also occurred later in the child's life among home-visited families. There was a trend toward decreased out-of-home placement (HR 0.73, 95% CI 0.53-1.02, P = .06). These results from a scaled-up statewide program highlight the potential of home visiting as an important approach to preventing child abuse and neglect. Copyright © 2018 Elsevier Ltd. All rights reserved.

  7. Computer Program Application Study for Newly Constructed Fossil Power Plant Performance Analysis

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Hyun; Park, Jong Jeng [Korea Electric Power Research Institute, Taejon (Korea, Republic of)

    1996-12-31

    The power plant is affected in its availability and economy significantly by the equipment degraded gradually as operation continues, which makes it quite important to evaluate the plant performance more accurately and analyze its effects to the plant economy quantitatively. The methodology thereof includes many calculation steps and requires huge man hours and efforts but would produce relatively less precise results than desired. The object of the project first aims to figure out a methodology which can analyze numerically the inherent effects of each equipment on the cycle performance as well as its performance evaluation and which further helps to determine more reasonable investment for the effective plant economy. Another aspect of the project results in the implementation of the methodology which is embodied in the sophisticated computer programs based on the conventional personal computer with the interactive graphic user interface facilities. (author). 44 refs., figs.

  8. A novel approach for studying programmed cell death in living plant tissues

    DEFF Research Database (Denmark)

    Mark, Christina

    to traditional approaches. Future applications of this type of setup could be used for other types of plant tissues such as leaves or germinating embryos for studying the effects of e.g. biotic and abiotic stresses or for screening of compounds for biological effects. Due to the ease of use and many......Programmed cell death (PCD) is a highly regulated process in which cells are killed as part of developmental programmes or as defence mechanisms against pathogens, but the process is less well understood in plant cells compared to animal cells. Reactive oxygen species (ROS) are involved in PCD...... in plants, but the relationship between and mechanisms behind ROS and PCDhas not yet been fully elucidated due to the involvement of complex signalling networks. Elucidation of these mechanisms and signalling pathways will allow manipulation of cell death in plants, which could help to improve yield...

  9. Computer Program Application Study for Newly Constructed Fossil Power Plant Performance Analysis

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Hyun; Park, Jong Jeng [Korea Electric Power Research Institute, Taejon (Korea, Republic of)

    1997-12-31

    The power plant is affected in its availability and economy significantly by the equipment degraded gradually as operation continues, which makes it quite important to evaluate the plant performance more accurately and analyze its effects to the plant economy quantitatively. The methodology thereof includes many calculation steps and requires huge man hours and efforts but would produce relatively less precise results than desired. The object of the project first aims to figure out a methodology which can analyze numerically the inherent effects of each equipment on the cycle performance as well as its performance evaluation and which further helps to determine more reasonable investment for the effective plant economy. Another aspect of the project results in the implementation of the methodology which is embodied in the sophisticated computer programs based on the conventional personal computer with the interactive graphic user interface facilities. (author). 44 refs., figs.

  10. DEVELOPMENT OF WEB-BASED EXAMINATION SYSTEM USING OPEN SOURCE PROGRAMMING MODEL

    Directory of Open Access Journals (Sweden)

    Olalere A. ABASS

    2017-04-01

    Full Text Available The traditional method of assessment (examination is often characterized by examination questions leakages, human errors during marking of scripts and recording of scores. The technological advancement in the field of computer science has necessitated the need for computer usage in majorly all areas of human life and endeavors, education sector not excluded. This work, Web-based Examination System (WES was, therefore, born out of the will to stymie the problems plaguing the conventional (paper-based examination system by providing a campus-wide service for e-assessment devoid of irregularities and generally fair to examinees and equally enhances instant feedback. This system developed using combination of CSS, HTML, PHP SQL MySQL and Dreamweaver is capable of reducing proportion of workload on examination, grading and reviewing on the part of examiners. Thus, the system enables the release of examination results in record time and without error. WES can serve as an effective solution for mass education evaluation and offers many novel features that cannot be implemented in paper-based systems, such as real time data collection, management and analysis, distributed and interactive assessment towards promoting distance education.

  11. Examinations on Applications of Manual Calculation Programs on Lung Cancer Radiation Therapy Using Analytical Anisotropic Algorithm

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Jung Min; Kim, Dae Sup; Hong, Dong Ki; Back, Geum Mun; Kwak, Jung Won [Dept. of Radiation Oncology, , Seoul (Korea, Republic of)

    2012-03-15

    There was a problem with using MU verification programs for the reasons that there were errors of MU when using MU verification programs based on Pencil Beam Convolution (PBC) Algorithm with radiation treatment plans around lung using Analytical Anisotropic Algorithm (AAA). On this study, we studied the methods that can verify the calculated treatment plans using AAA. Using Eclipse treatment planning system (Version 8.9, Varian, USA), for each 57 fields of 7 cases of Lung Stereotactic Body Radiation Therapy (SBRT), we have calculated using PBC and AAA with dose calculation algorithm. By developing MU of established plans, we compared and analyzed with MU of manual calculation programs. We have analyzed relationship between errors and 4 variables such as field size, lung path distance of radiation, Tumor path distance of radiation, effective depth that can affect on errors created from PBC algorithm and AAA using commonly used programs. Errors of PBC algorithm have showned 0.2{+-}1.0% and errors of AAA have showned 3.5{+-}2.8%. Moreover, as a result of analyzing 4 variables that can affect on errors, relationship in errors between lung path distance and MU, connection coefficient 0.648 (P=0.000) has been increased and we could calculate MU correction factor that is A.E=L.P 0.00903+0.02048 and as a result of replying for manual calculation program, errors of 3.5{+-}2.8% before the application has been decreased within 0.4{+-}2.0%. On this study, we have learned that errors from manual calculation program have been increased as lung path distance of radiation increases and we could verified MU of AAA with a simple method that is called MU correction factor.

  12. Examinations on Applications of Manual Calculation Programs on Lung Cancer Radiation Therapy Using Analytical Anisotropic Algorithm

    International Nuclear Information System (INIS)

    Kim, Jung Min; Kim, Dae Sup; Hong, Dong Ki; Back, Geum Mun; Kwak, Jung Won

    2012-01-01

    There was a problem with using MU verification programs for the reasons that there were errors of MU when using MU verification programs based on Pencil Beam Convolution (PBC) Algorithm with radiation treatment plans around lung using Analytical Anisotropic Algorithm (AAA). On this study, we studied the methods that can verify the calculated treatment plans using AAA. Using Eclipse treatment planning system (Version 8.9, Varian, USA), for each 57 fields of 7 cases of Lung Stereotactic Body Radiation Therapy (SBRT), we have calculated using PBC and AAA with dose calculation algorithm. By developing MU of established plans, we compared and analyzed with MU of manual calculation programs. We have analyzed relationship between errors and 4 variables such as field size, lung path distance of radiation, Tumor path distance of radiation, effective depth that can affect on errors created from PBC algorithm and AAA using commonly used programs. Errors of PBC algorithm have showned 0.2±1.0% and errors of AAA have showned 3.5±2.8%. Moreover, as a result of analyzing 4 variables that can affect on errors, relationship in errors between lung path distance and MU, connection coefficient 0.648 (P=0.000) has been increased and we could calculate MU correction factor that is A.E=L.P 0.00903+0.02048 and as a result of replying for manual calculation program, errors of 3.5±2.8% before the application has been decreased within 0.4±2.0%. On this study, we have learned that errors from manual calculation program have been increased as lung path distance of radiation increases and we could verified MU of AAA with a simple method that is called MU correction factor.

  13. Head Start Program Quality: Examination of Classroom Quality and Parent Involvement in Predicting Children's Vocabulary, Literacy, and Mathematics Achievement Trajectories

    Science.gov (United States)

    Wen, Xiaoli; Bulotsky-Shearer, Rebecca J.; Hahs-Vaughn, Debbie L.; Korfmacher, Jon

    2012-01-01

    Guided by a developmental-ecological framework and Head Start's two-generational approach, this study examined two dimensions of Head Start program quality, classroom quality and parent involvement and their unique and interactive contribution to children's vocabulary, literacy, and mathematics skills growth from the beginning of Head Start…

  14. Examination of Sign Language Education According to the Opinions of Members from a Basic Sign Language Certification Program

    Science.gov (United States)

    Akmese, Pelin Pistav

    2016-01-01

    Being hearing impaired limits one's ability to communicate in that it affects all areas of development, particularly speech. One of the methods the hearing impaired use to communicate is sign language. This study, a descriptive study, intends to examine the opinions of individuals who had enrolled in a sign language certification program by using…

  15. 46 CFR 71.50-17 - Eligibility requirements for the Alternative Hull Examination (AHE) Program for certain passenger...

    Science.gov (United States)

    2010-10-01

    ... 46 Shipping 3 2010-10-01 2010-10-01 false Eligibility requirements for the Alternative Hull...-17 Eligibility requirements for the Alternative Hull Examination (AHE) Program for certain passenger... aluminum; (2) It has an effective hull protection system; (3) It has operated exclusively in fresh water...

  16. Examining the Permanence of the Effect of an Empathy Program for the Acquisition of Empathy Skills on Gifted Adolescents

    Science.gov (United States)

    Nedim Bal, Pervin

    2015-01-01

    This study aimed to examine the permanence of the effect of an Empathy Training Program, administered 8 months ago on gifted adolescents studying in 6th and 7th grades. The sample of this study consisted of 60 students with IQ scores of above 130 and studied in Enderun Gifted Children Center. Bryant's Empathy Scale for Children was administered to…

  17. An Examination of Mental Health Content in Course Work and Field Experiences in Connecticut Educational Leadership Preparation Programs

    Science.gov (United States)

    Papa, Dorothy P.

    2017-01-01

    This exploratory mixed method convergent parallel study examined Connecticut Educational leadership preparation programs for the existence of mental health content to learn the extent to which pre-service school leaders are prepared for addressing student mental health. Interviews were conducted with school mental health experts and Connecticut…

  18. Examining Intercultural Growth for Business Students in Short-Term Study Abroad Programs: Too Good to Be True?

    Science.gov (United States)

    Gullekson, Nicole L.; Tucker, Mary L.; Coombs, Garth, Jr.; Wright, Scott B.

    2011-01-01

    Changes in ethnocentrism, intercultural communication apprehension, international awareness and activities were examined in business students participating in a 16-day consulting program abroad and compared to a control group of students at the home university. Anticipated changes in the study abroad students were found; however, when compared to…

  19. Set up for Success: An Examination of the Ronald E. McNair Postbaccalaureate Achievement Program's Mentoring Component

    Science.gov (United States)

    Wyre, Dwuena Cene

    2011-01-01

    Often, individuals are set up to fail. However, effective mentoring can set individuals up to succeed. This nonexperimental cross-sectional, predictive study examines the Ronald E. McNair Postbaccalaureate Achievement Program's mentoring component. Specific focus is placed on faculty mentor competency and its impact on McNair student intent to…

  20. Examination of Student, Program, and Institutional Support Characteristics That Relate to PGA Golf Management Students' Intent to Persist

    Science.gov (United States)

    Cain, Christopher

    2013-01-01

    The examination of student (entry characteristics, academic performance, career goals, and interaction with peers and faculty), program (programmatic interventions, academic major, and learning communities), and institutional support characteristics (financial aid and residence) that relate to cohort intent to persist are studied among 490 PGA…

  1. Effects of Two Testicular Cancer Education Programs on Self-Examination Knowledge and Attitudes among College-Aged Men.

    Science.gov (United States)

    Marty, Phillip J.; McDermott, Robert J.

    1985-01-01

    This study compared instructional outcomes of two education programs about testicular cancer and testicular self-examination. Instruction facilitated by a former testicular cancer patient was compared to information provided by printed materials. There was no difference in information dissemination, but possible differences in attitude resulted.…

  2. Utilization of logistic computer programs in the power plant piping industry

    International Nuclear Information System (INIS)

    Motzel, E.

    1982-01-01

    Starting from the general situation of the power plant piping industry, the utilization of computer programs as well as the specific magnitude of complexity connected with the project realisation, the necessity for using logistic computer programs especially in case of nuclear power plants is explained. The logistic term as well as the logistic data are described. At the example of the nuclear power plant KRB II, Gundremmingen, Block B/C the practical use of such programs is shown. The planning, scheduling and supervision is carried out computer-aided by means of network-technique. The material management, prefabrication, installation including management of certificates for welding and testing activities is planned and controlled by computer programs as well. With the piping systems installed a complete erection work documentation is available which also serves as base for the billing versus the client. The budgeted costs are continuously controlled by means of a cost control program. Summing-up the further development in controlling piping contracts computer-supported is described with regard to software, hardware and the organisation structure. Furthermore the concept of a self-supporting field computer is introduced for the first time. (orig.) [de

  3. Station blackout transient at the Browns Ferry Unit 1 Plant: a severe accident sequence analysis (SASA) program study

    International Nuclear Information System (INIS)

    Schultz, R.R.

    1982-01-01

    Operating plant transients are of great interest for many reasons, not the least of which is the potential for a mild transient to degenerate to a severe transient yielding core damage. Using the Browns Ferry (BF) Unit-1 plant as a basis of study, the station blackout sequence was investigated by the Severe Accident Sequence Analysis (SASA) Program in support of the Nuclear Regulatory Commission's Unresolved Safety Issue A-44: Station Blackout. A station blackout transient occurs when the plant's AC power from a comemrcial power grid is lost and cannot be restored by the diesel generators. Under normal operating conditions, f a loss of offsite power (LOSP) occurs [i.e., a complete severance of the BF plants from the Tennessee Valley Authority (TVA) power grid], the eight diesel generators at the three BF units would quickly start and power the emergency AC buses. Of the eight diesel generators, only six are needed to safely shut down all three units. Examination of BF-specific data show that LOSP frequency is low at Unit 1. The station blackout frequency is even lower (5.7 x 10 - 4 events per year) and hinges on whether the diesel generators start. The frequency of diesel generator failure is dictated in large measure by the emergency equipment cooling water (EECW) system that cools the diesel generators

  4. The development of the Waste Isolation Pilot Plant (WIPP) project's public affairs program

    International Nuclear Information System (INIS)

    Walter, L.H.

    1988-01-01

    The Waste Isolation Pilot Plant (WIPP) offers a perspective on the value of designing flexibility into a public affairs program to enable it to grow with and complement a project's evolution from construction through to operations. This paper discusses how the WIPP public affairs program progressed through several stages to its present scope. During the WIPP construction phase, the public affairs program laid a foundation for Project acceptance in the community. A speaker's bureau, a visitors program, and various community outreach and support programs emphasized the educational and socioeconomic benefits of having this controversial project in Carlsbad. Then, in this past year as the project entered a preoperational status, the public affairs program emphasis shifted to broaden the positive image that had been created locally. In this stage, the program promoted the project's positive elements with the various state agencies, government officials, and federal organizations involved in our country's radioactive waste management and transportation program. Currently, an even broader, more aggressive public affairs program is planned. During this stage public affairs will be engaged in a comprehensive institutional and outreach program, explaining and supporting WIPP's mission in each of the communities and agencies affected by the operation of the country's first geologic repository

  5. Department of Energy's safety and health program for enrichment plant workers is not adequately implemented

    International Nuclear Information System (INIS)

    Staats, E.B.

    1980-01-01

    The Department of Energy's (DOE's) program to protect the safety and health of employees at its contractor-operated uranium enrichment plants has not been fully implemented by DOE's Oak Ridge Operations Office. Appraisals and inspections of plant conditions are not as frequent and/or as thorough as required. Instead of independently investigating employee complaints, DOE has delegated this responsibility to the contractor. It is recommended that the Secretary of Energy make sure that Oak Ridge properly conducts inspections and appraisals and investigates and follows up on all employee complaints. He should also take steps to provide increased independence and objectivity in the Oak Ridge Operations Office's safety and health program. Furthermore, the Congress should authorize the Secretary of Energy to institute a program of non-reimbursable penalties and fines for violations of safety and health standards and procedures

  6. Handbook of nuclear power plant seismic fragilities, Seismic Safety Margins Research Program

    International Nuclear Information System (INIS)

    Cover, L.E.; Bohn, M.P.; Campbell, R.D.; Wesley, D.A.

    1983-12-01

    The Seismic Safety Margins Research Program (SSMRP) has a gola to develop a complete fully coupled analysis procedure (including methods and computer codes) for estimating the risk of an earthquake-induced radioactive release from a commercial nuclear power plant. As part of this program, calculations of the seismic risk from a typical commercial nuclear reactor were made. These calculations required a knowledge of the probability of failure (fragility) of safety-related components in the reactor system which actively participate in the hypothesized accident scenarios. This report describes the development of the required fragility relations and the data sources and data reduction techniques upon which they are based. Both building and component fragilities are covered. The building fragilities are for the Zion Unit 1 reactor which was the specific plant used for development of methodology in the program. Some of the component fragilities are site-specific also, but most would be usable for other sites as well

  7. Development of reliability program for emergency diesel generators in domestic nuclear power plants

    International Nuclear Information System (INIS)

    Kim, Young Ho; Jung, Hyun Jong; Choi, Kwang Hee; Hong, Seoung Yeul

    2001-01-01

    Surveillance tests of Emergency Diesel Generators (EDGs) in Nuclear Power Plants (NPPs) have been conducted periodically to verify the reliability and integrity of the EDGs, however, it was found that these surveillance methods were so conservative and severe as to accelerate the degradation of the EDGs. Hence, new regulatory guideline, Reg. Guide 1.9 Rev. 3, was established by the U.S. NRC to resolve these problems. But it requires the additional implementation of reliability program of the EDGs to improve the actual reliability of them. In Korea, the EDGs of Yonggwang nuclear units 3 and 4 were the first plant applying new Reg. guide 1.9 rev.3 and implementing EDG reliability program. Furthermore it is expected that new guideline for the EDGs will be applied to other EDGs of Korean NPPs. In this paper, this reliability program is described, and it can be used as a reference for other EDGs in Korean NPPs

  8. Results from the Nuclear Plant Aging Research Program: Their use in inspection activities

    Energy Technology Data Exchange (ETDEWEB)

    Gunther, W.; Taylor, J. (Brookhaven National Lab., Upton, NY (USA))

    1990-09-01

    The US NCR's Nuclear Plant Aging Research (NPAR) Program has determined the susceptibility to aging of components and systems, and the potential for aging to impact plant safety and availability. The NPAR Program also identified methods for detecting and mitigating aging in components. This report describes the NPAR results which can enhance NRC inspection activities. Recommendations are provided for communicating pertinent information to NRC inspectors. These recommendations are based on a detailed assessment of the NRC's Inspection Program, and feedback from resident and regional inspectors as described within. Examples of NPAR report summaries and aging inspection guides for components and systems are included. 13 refs., 3 figs., 4 tabs.

  9. Examining the Relevance of Emotional Intelligence within Educational Programs for the Gifted and Talented

    Science.gov (United States)

    Bellamy, Al; Gore, David; Sturgis, Judy

    2005-01-01

    This study explored the relationships between emotional intelligence, locus of control, and self-efficacy among gifted and talented students participating in a two week long summer educational program. Results revealed statistically significant correlations between these variables. Gender was found to moderate the relationships. The study also…

  10. A Dynamical Systems Theory Examination of Social Connections in Outdoor Recreation Programs

    Science.gov (United States)

    Jostad, Jeremy

    2015-01-01

    Adolescence is a developmental time period in which social connections are an important aspect to fostering positive growth and identity. Outdoor Adventure Education (OAE) programs are strategically positioned to help in this developmental process because of the novel social environment, however, little is known about how these types of social…

  11. Examining science teachers' pedagogical content knowledge in the context of a professional development program

    NARCIS (Netherlands)

    Wongsopawiro, Dirk Soenario

    2012-01-01

    This dissertation reports on the pedagogical content knowledge (PCK) of science teachers during a professional development program. This research intended to help us understand why and how teachers make their classroom decisions as they teach science. The main questions in this study were: What is

  12. Competency-Based Education in Three Pilot Programs: Examining Implementation and Outcomes

    Science.gov (United States)

    Steele, Jennifer L.; Lewis, Matthew W.; Santibanez, Lucrecia; Faxon-Mills, Susannah; Rudnick, Mollie; Stecher, Brian M.; Hamilton, Laura S.

    2014-01-01

    In 2011, the Bill & Melinda Gates Foundation created the Project Mastery grant program to support competency-based education initiatives in large school systems that serve a high proportion of disadvantaged youth. Competency-based education meets students where they are academically, provides students with opportunities for choice, and awards…

  13. Body Talk: Examining a Collaborative Multiple-Visit Program for Visitors with Eating Disorders

    Science.gov (United States)

    Baddeley, Gwen; Evans, Laura; Lajeunesse, Marilyn; Legari, Stephen

    2017-01-01

    "Sharing the Douglas/Sharing the Museum," a collaboration program of the Montreal Museum of Fine Arts (MMFA), the Douglas Mental Health Institute and the Department of Creative Arts Therapies at Concordia University, serves patients from the Eating Disorder Unit of the Douglas. Participants eat lunch at the museum and look at, talk…

  14. Curricular Abstinence: Examining Human Sexuality Training in School Counselor Preparation Programs

    Science.gov (United States)

    Behun, Richard Joseph; Cerrito, Julie A.; Delmonico, David L.; Campenni, Estelle

    2017-01-01

    Professional school counselors (PSCs; N = 486) rated their level of perceived preparedness acquired in their school counselor preparation program with respect to knowledge, skills, and self-awareness of five human sexuality domains (behavior, health, morality, identity, violence) across grade level (elementary vs. secondary) and three human…

  15. Examining the Preliminary Efficacy of a Dating Violence Prevention Program for Hispanic Adolescents

    Science.gov (United States)

    Gonzalez-Guarda, Rosa Maria; Guerra, Jessica E.; Cummings, Amanda A.; Pino, Karen; Becerra, Maria M.

    2015-01-01

    The purpose of this study is to evaluate the preliminary efficacy of a dating violence (DV) prevention program for Cuban American adolescents ("JOVEN"/YOUTH: "Juntos Opuestos a la Violence Entre Novios"/Together Against Dating Violence). A randomized-controlled experimental design with a delayed condition was used to evaluate…

  16. A Review of Research Methods Used to Examine Employee Assistance Program Delivery Options.

    Science.gov (United States)

    Csiernik, Rick

    1995-01-01

    This review of literature on Employee Assistance Programs (EAPs) focuses on EAP delivery options. More than half of the 48 studies reviewed used a case study approach. EAPs provided by on-staff professionals were the most frequently discussed delivery option, although this is not the most dominant form of EAP provision. (SLD)

  17. An Examination of Job Skills Posted on Internet Databases: Implications for Information Systems Degree Programs.

    Science.gov (United States)

    Liu, Xia; Liu, Lai C.; Koong, Kai S.; Lu, June

    2003-01-01

    Analysis of 300 information technology job postings in two Internet databases identified the following skill categories: programming languages (Java, C/C++, and Visual Basic were most frequent); website development (57% sought SQL and HTML skills); databases (nearly 50% required Oracle); networks (only Windows NT or wide-area/local-area networks);…

  18. Oak Ridge Y-12 Plant Biological Monitoring and Abatement Program Plan

    Energy Technology Data Exchange (ETDEWEB)

    Adams, S.M.; Brandt, C.C.; Christensen, S.W.; Greeley, M.S.JR.; Hill, W.R.; Peterson, M.J.; Ryon, M.G.; Smith, J.G.; Southworth, G.R.; Stewart, A.J.

    2000-09-01

    The revised Biological Monitoring and Abatement Program (BMAP) for East Fork Poplar Creek (EFPC) at the Oak Ridge Y-12 Plant, as described, will be conducted as required by the National Pollutant Discharge Elimination System permit issued for the Y-12 Plant on April 28, 1995 and became effective July 1, 1995. The basic approach to biological monitoring used in this program was developed by the staff in the Environmental Science Division (ESD) at the Oak Ridge National Laboratory (ORNL) at the request of the Y-12 Plant. The revision to the BMAP plan is based on results of biological monitoring conducted during the period of 1985 to present. Details of the specific procedures used in the current routine monitoring program are provided; experimental designs for future studies are described in less detail. The overall strategy used in developing this plan was, and continues to be, to use the results obtained from each task to define the scope of future monitoring efforts. Such efforts may require more intensive sampling than initially proposed in some areas (e.g., additional bioaccumulation monitoring if results indicate unexpectedly high PCBs or Hg) or a reduction in sampling intensity in others (e.g., reduction in the number of sampling sites when no impact is still observed). The program scope will be re-evaluated annually. By using the results of previous monitoring efforts to define the current program and to guide us in the development of future studies, an effective integrated monitoring program has been developed to assess the impacts of Y-12 Plant operations (past and present) on the biota of EFPC and to document the ecological effects of remedial actions.

  19. Industrial Fuel Gas Demonstration Plant Program. Monthly, quarterly and annual progress report, December 1978 and Calender Year 1978

    Energy Technology Data Exchange (ETDEWEB)

    None

    1978-01-01

    A new pilot plant program developed by DOE and the team members, was started on September 20, 1978. Pilot plant success was achieved in obtaining an ash balanced condition for several days with ash agglomeration with a pure coal feed. This was the objective of the first three months of the approved program.

  20. Environmental justice and factors that influence participation in tree planting programs in Portland, Oregon, U.S

    Science.gov (United States)

    Geoffrey H. Donovan; John Mills

    2014-01-01

    Many cities have policies encouraging homeowners to plant trees. For these policies to be effective, it is important to understand what motivates a homeowner’s tree-planting decision. Researchers address this question by identifying variables that influence participation in a tree-planting program in Portland, Oregon, U.S. According to the study, homeowners with street...

  1. Detection and plant monitoring programs: lessons from an intensive survey of Asclepias meadii with five observers.

    Directory of Open Access Journals (Sweden)

    Helen M Alexander

    Full Text Available Monitoring programs, where numbers of individuals are followed through time, are central to conservation. Although incomplete detection is expected with wildlife surveys, this topic is rarely considered with plants. However, if plants are missed in surveys, raw count data can lead to biased estimates of population abundance and vital rates. To illustrate, we had five independent observers survey patches of the rare plant Asclepias meadii at two prairie sites. We analyzed data with two mark-recapture approaches. Using the program CAPTURE, the estimated number of patches equaled the detected number for a burned site, but exceeded detected numbers by 28% for an unburned site. Analyses of detected patches using Huggins models revealed important effects of observer, patch state (flowering/nonflowering, and patch size (number of stems on probabilities of detection. Although some results were expected (i.e. greater detection of flowering than nonflowering patches, the importance of our approach is the ability to quantify the magnitude of detection problems. We also evaluated the degree to which increased observer numbers improved detection: smaller groups (3-4 observers generally found 90 - 99% of the patches found by all five people, but pairs of observers or single observers had high error and detection depended on which individuals were involved. We conclude that an intensive study at the start of a long-term monitoring study provides essential information about probabilities of detection and what factors cause plants to be missed. This information can guide development of monitoring programs.

  2. Detection and plant monitoring programs: lessons from an intensive survey of Asclepias meadii with five observers.

    Science.gov (United States)

    Alexander, Helen M; Reed, Aaron W; Kettle, W Dean; Slade, Norman A; Bodbyl Roels, Sarah A; Collins, Cathy D; Salisbury, Vaughn

    2012-01-01

    Monitoring programs, where numbers of individuals are followed through time, are central to conservation. Although incomplete detection is expected with wildlife surveys, this topic is rarely considered with plants. However, if plants are missed in surveys, raw count data can lead to biased estimates of population abundance and vital rates. To illustrate, we had five independent observers survey patches of the rare plant Asclepias meadii at two prairie sites. We analyzed data with two mark-recapture approaches. Using the program CAPTURE, the estimated number of patches equaled the detected number for a burned site, but exceeded detected numbers by 28% for an unburned site. Analyses of detected patches using Huggins models revealed important effects of observer, patch state (flowering/nonflowering), and patch size (number of stems) on probabilities of detection. Although some results were expected (i.e. greater detection of flowering than nonflowering patches), the importance of our approach is the ability to quantify the magnitude of detection problems. We also evaluated the degree to which increased observer numbers improved detection: smaller groups (3-4 observers) generally found 90 - 99% of the patches found by all five people, but pairs of observers or single observers had high error and detection depended on which individuals were involved. We conclude that an intensive study at the start of a long-term monitoring study provides essential information about probabilities of detection and what factors cause plants to be missed. This information can guide development of monitoring programs.

  3. Regulatory approach of the monitoring the effectiveness of maintenance at nuclear power plants program

    International Nuclear Information System (INIS)

    Vajgel, Stefan

    2009-03-01

    The electrical power generation using nuclear power plants requires this installation being safety, reliable and available for the working periods. For this purpose, an adequate, effective and well conducted maintenance program makes an essential and useful tool to the owner of the plant. However, it is necessary to follow the regulatory requirements for this program implementation which monitories this maintenance effectiveness. There are Brazilian norms requirements which must be followed. The international regulatory guides establish these requirements in good details but it is necessary to verify if this methodology for implementing can be totally applied here in Brazil. Then, the american guide NUMARC 93-01 which details how can be implemented a program for this monitoring, shows some methods for using. In this thesis, the Delphi and Probabilistic Safety Analysis were briefly included because they were preferred for implementing this monitoring.in a Brazilian plant. The results which are being obtained show that, looking the regulatory aspects, the NUMARC 93-01 follows our regulations and gives good results for the plant management. (author)

  4. TMI-2 core-examination program: INEL facilities-readiness study

    International Nuclear Information System (INIS)

    McLaughlin, T.B.

    1982-09-01

    This document is a review of the Idaho National Engineering Laboratory's (INEL) remote handling facilities. Their availability and readiness to conduct examination and analyses of TMI-2 core samples was determined. Examination of these samples require that the facilities be capable of receiving commercial casks, unloading canisters from the casks, opening the canisters, handling the fuel debris and assemblies, and performing various examinations. The documentation that was necessary for the INEL to have before the receipt of the core material was identified. The core information was also required for input to these documents. The costs, schedules, and a preliminary-project plan are presented for the tasks which are identified as prerequisites to the receipt of the first core sample

  5. CANADA’S MOTHER-CHILD PROGRAM: EXAMINING ITS EMERGENCE, USAGE, AND CURRENT STATE

    Directory of Open Access Journals (Sweden)

    Sarah Brennan

    2014-04-01

    Full Text Available One of many issues a mother must face while incarcerated is separation from her child(ren for an extended period of time. Empirical findings have consistently highlighted various negative effects for both mothers and their children as a result of this separation. To curb some of the negative effects, Correctional Service Canada’s Mother-Child Program offers full- and part-time visitation between children and their incarcerated mothers at various women’s federal correctional facilities in Canada. The current study involves an in-depth critical analysis of Canada’s MCP by asking three related questions. First, to what extent has the MCP been used since its full implementation in 2001? Second, to what extent is the MCP used today? Third, do any barriers exist currently that are inhibiting the success of the MCP and, if so, how can these be addressed? The results of the study reveal that, since the full implementation of the program in 2001, the participation rate declined from an already low starting point and has remained relatively low since. Further, three main factors were suggested as potential barriers impeding the success of the MCP: correctional overcrowding, a more punitive institutional culture, and a series of changes to the program’s eligibility criteria. Recommendations on ways to increase the usage of the program are offered and suggestions for future research are made.

  6. Quality assurance program application during the decommissioning phase of the Shoreham Nuclear Plant

    International Nuclear Information System (INIS)

    Patch, R.L.

    1993-01-01

    The application of Quality Assurance (QA) requirements for operating nuclear power plants has evolved over the last 30 years. QA programs started as good management practices and evolved to a process that is implemented integral to very detailed Probabilistic Risk Assessments (PRAs). QA programs for controlling activities during decommissioning of nuclear power plants are still in their infancy. Regulatory guidance is currently being developed, and much of what exists is in the form of draft guidance documents. In determining where to apply QA controls during decommissioning, a series of questions must be asked: Is there an existing regulatory commitment? (Safety related or safety significant activity); Are there any postulated accidents which need to be prevented or mitigated; What are the unacceptable risks; Are there other key factors, such as human performance issues and Industrial Safety Programs, to be considered? Which QA controls are needed and to what extent they should be applied must be evaluated on a case by case basis. How much QA to apply is usually a risk evaluation in itself. Can you afford not to apply a specific control? Can you afford to apply costly and rigorous quality control programs? These questions had to be answered at the Shoreham Nuclear Power Station (SNPS) in order to develop and implement an acceptable and effective Quality Assurance program. Exploring the SNPS open-quotes lessons learnedclose quotes on how to apply a quality assurance program during decommissioning is what the following discussion is about

  7. Test program for closure activities at a mixed waste disposal site at the Savannah River Plant

    International Nuclear Information System (INIS)

    Cook, J.R.; Harley, J.P. Jr.

    1988-01-01

    A 58-acre site at the Savannah River Plant which was used for disposal of low-level radioactive waste and quantities of the hazardous materials lead, cadmium, scintillation fluid, and oil will be the first large waste site at the Savannah River Plant to be permanently closed. The actions leading to closure of the facility will include surface stabilization and capping of the site. Test programs have been conducted to evaluate the effectiveness of dynamic compaction as a stabilization technique and the feasibility of using locally derived clay as a capping material

  8. Fiscal year 1996 well plugging and abandonment program Y-12 Plant, Oak Ridge, Tennessee

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-04-01

    This report is a synopsis of the progress of the well plugging and abandonment program at the Oak Ridge Y-12 Plant, Oak Ridge, Tennessee, from August 1995 through August 1996. A total of 27 wells, piezometers, and borings were plugged and abandoned during the period of time covered in this report. All wells and borings were plugged and abandoned in accordance with the Monitoring Well Plugging and Abandonment Plan for the U.S. Department of Energy, Y-12 Plant, Oak Ridge, Tennessee (HSW, Inc. 1991).

  9. Examining the psychological pathways to behavior change in a group-based lifestyle program to prevent type 2 diabetes.

    Science.gov (United States)

    Critchley, Christine R; Hardie, Elizabeth A; Moore, Susan M

    2012-04-01

    To examine the psychological process of lifestyle change among adults at risk for type 2 diabetes. A randomized control trial in which 307 volunteers (intervention, n = 208; wait control, n = 99) diagnosed with prediabetes completed a six-session group-based intervention to promote healthier living. Participants' motivation to change, diet and exercise self-efficacy, mood, knowledge about diabetes, activity levels, healthy eating, waist circumference, and weight were assessed before and after the program. Participation in the program was associated with significant increases in healthy eating and physical activity, reductions in waist and weight, and improvements in motivation, positive mood, self-efficacy, and knowledge. Examination of the pathways to lifestyle change showed that the educational aspect of the program increased activity levels because it increased diabetes knowledge and improved mood. Eating behavior was not mediated by any of the psychological variables. Improvements in diet and physical activity were, in turn, directly associated with changes in weight and waist circumference. Although the program significantly improved motivation, self-efficacy, and mood, its impact on knowledge uniquely explained the increase in physical activity. Group-based programs that are tailored to lifestyle behaviors may provide a cost-effective method of diabetes prevention, but more research is needed to explain why they improve healthy eating.

  10. Ageing management program of wires for Atucha II Nuclear Power Plant

    International Nuclear Information System (INIS)

    Zorrilla, J.; Antonaccio, E.; Luraschi, C.; Simionato, E.; Nieto, H.

    2012-01-01

    Electrical cables constitute one of the most important components of NPP in terms o maintenance, safety and availability of the plant. Due to their large extension (thousands of kilometers) it is impossible to fully replace them and aging management becomes essential for long term operation of NPP. Since Atucha II is under construction there was a good opportunity to establish and implement a holistic cable aging management program from the beginning according to the state of the art in this field. The scope of this program involves safety related cables, including EQ cables and non EQ cables as well. Due to the diversity of the installed cables is impossible to address an aging management program of every single specimen. However it is possible to establish 'cables families' of similar aging behavior based on insulation and jacket material, manufacture, etc Several aging management strategies were set for the different 'cables families'. These strategies include cables deposit in plant, elaboration of procedures of visual and tactile inspection, NDE techniques, etc Currently the aging management program is being implemented covering topic such as: Cable screening and grouping. Review of EQ documentation and conventional qualification information referring to the installed cables. Establishment of base line of condition monitoring techniques. Calibration and set up of test parameters for NDE techniques. Aging mechanism characterization and determination of. Design construction and installation of cable deposit in plant (author)

  11. End-of-life destructive examination of light water breeder reactor fuel rods (LWBR Development Program)

    International Nuclear Information System (INIS)

    Richardson, K.D.

    1987-10-01

    Destructive examination of 12 representative Light Water Breeder Reactor fuel rods was performed following successful operation in the Shippingport Atomic Power Station for 29,047 effective full power hours, about five years. Light Water Breeder Reactor fuel rods were unique in that the thorium oxide and uranium-233 oxide fuel was contained within Zircaloy-4 cladding. Destructive examinations included analysis of released fission gas; chemical analysis of the fuel to determine depletion, iodine, and cesium levels; chemical analysis of the cladding to determine hydrogen, iodine, and cesium levels; metallographic examination of the cladding, fuel, and other rod components to determine microstructural features and cladding corrosion features; and tensile testing of the irradiated cladding to determine mechanical strength. The examinations confirmed that Light Water Breeder Reactor fuel rod performance was excellent. No evidence of fuel rod failure was observed, and the fuel operating temperature was low (below 2580 0 F at which an increased percentage of fission gas is released). 21 refs., 80 figs., 20 tabs

  12. OAK RIDGE Y-12 PLANT BIOLOGICAL MONITORING AND ABATEMENT PROGRAM (BMAP) PLAN

    Energy Technology Data Exchange (ETDEWEB)

    ADAMS, S.M.; BRANDT, C.C.; CHRISTENSEN, S.W.; CICERONE, D.S.; GREELEY, M.S.JR; HILL, W.R.; HUSTON, M.S.; KSZOS, L.A.; MCCARTHY, J.F.; PETERSON, M.J.; RYON, M.G.; SMITH, J.G.; SOUTHWORTH, G.R.; STEWART, A.J.

    1998-10-01

    The proposed Biological Monitoring and Abatement Program (BMAP) for East Fork Poplar Creek (EFPC) at the Oak Ridge Y-12 Plant, as described, will be conducted for the duration of the National Pollutant Discharge Elimination System permit issued for the Y-12 Plant on April 28, 1995, and which became effective July 1, 1995. The basic approach to biological monitoring used in this program was developed by the staff in the Environmental Sciences Division at the Oak Ridge National Laboratory at the request of Y- 12 Plant personnel. The proposed BMAP plan is based on results of biological monitoring conducted since 1985. Details of the specific procedures used in the current routine monitoring program are provided but experimental designs for future studies are described in less detail. The overall strategy used in developing this plan was, and continues to be, to use the results obtained from each task to define the scope of future monitoring efforts. Such efforts may require more intensive sampling than initially proposed in some areas (e.g., additional toxicity testing if initial results indicate low survival or reproduction) or a reduction in sampling intensity in others (e.g., reduction in the number of sampling sites when no impact is observed). By using the results of previous monitoring efforts to define the current program and to guide us in the development of future studies, an effective integrated monitoring program has been developed to assess the impacts of the Y-12 Plant operation on the biota of EFPC and to document the ecological effects of remedial actions.

  13. Development of graphic display program of reactor operating parameters for emergency exercise at nuclear power plants

    International Nuclear Information System (INIS)

    Okuda, Yasunori; Yoshida, Yoshitaka; Gotou, Kazuko

    2001-01-01

    A scenario of nuclear emergency exercise based on the result of accident progress analysis is expected to ensure effective training. Thereupon a new graphic display program for reactor operating parameters has been developed to present real-time of plant process values (parameters), released radioactivities from the plant, and dose rate data around the site calculated by using the accident analysis code MAAP4 and other codes. This system has a trend graph screen displaying reactor operating parameters, an environmental dose rate summary screen indicating dose rate distribution around the site on the map, and a plant parameters summary screen showing important plant parameters on a simplified plant system diagram. One screen can be switched to another any time. It also has a jump-function easily accessing any stage during the exercise scenario in accordance with progress of the exercise. As a result of the application of this system to a real nuclear emergency exercise, it has been verified that this system is quite useful for confirming the parameters when the nuclear emergency exercise starts and the licensee reports the plant conditions to related bodied. (author)

  14. Development of graphic display program of reactor operating parameters for emergency exercise at nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Okuda, Yasunori; Yoshida, Yoshitaka [Institute of Nuclear Safety System Inc., Mihama, Fukui (Japan); Gotou, Kazuko [Kansai Electric Power Co., Inc., Osaka (Japan)

    2001-09-01

    A scenario of nuclear emergency exercise based on the result of accident progress analysis is expected to ensure effective training. Thereupon a new graphic display program for reactor operating parameters has been developed to present real-time of plant process values (parameters), released radioactivities from the plant, and dose rate data around the site calculated by using the accident analysis code MAAP4 and other codes. This system has a trend graph screen displaying reactor operating parameters, an environmental dose rate summary screen indicating dose rate distribution around the site on the map, and a plant parameters summary screen showing important plant parameters on a simplified plant system diagram. One screen can be switched to another any time. It also has a jump-function easily accessing any stage during the exercise scenario in accordance with progress of the exercise. As a result of the application of this system to a real nuclear emergency exercise, it has been verified that this system is quite useful for confirming the parameters when the nuclear emergency exercise starts and the licensee reports the plant conditions to related bodied. (author)

  15. Examining neural correlates of skill acquisition in a complex videogame training program

    OpenAIRE

    Prakash, Ruchika S.; De Leon, Angeline A.; Mourany, Lyla; Lee, Hyunkyu; Voss, Michelle W.; Boot, Walter R.; Basak, Chandramallika; Fabiani, Monica; Gratton, Gabriele; Kramer, Arthur F.

    2012-01-01

    Acquisition of complex skills is a universal feature of human behavior that has been conceptualized as a process that starts with intense resource dependency, requires effortful cognitive control, and ends in relative automaticity on the multi-faceted task. The present study examined the effects of different theoretically based training strategies on cortical recruitment during acquisition of complex video game skills. Seventy-five participants were recruited and assigned to one of three trai...

  16. Volatile Organic Compound (VOC) Air Monitoring Program design for the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    Frank, L.

    1991-01-01

    The Waste Isolation Pilot Plant (WIPP) Volatile Organic Compound (VOC) Monitoring Program has been developed as part of the Department of Energy's (DOE's) No-Migration Variance petition submitted to the Environmental Protection Agency (EPA). The program is designed to demonstrate that there will be no migration of hazardous chemicals past the unit boundary in concentrations which exceed any health-based standards. The monitoring program will use EPA compendium Method TO-14. Both air and carbon sorption media samples will be collected as part of the program. Eleven separate monitoring sites have been selected where both 24-hour integrated and 1-hour grab samples will be collected and analyzed for five target compounds. The bin-scale experimental test rooms will be configured with a gas collection manifold and an activated carbon sorption bed to remove VOCs before they can be emitted into the WIPP underground atmosphere. 10 refs., 4 figs., 7 tabs

  17. The evolution of the Waste Isolation Pilot Plant (WIPP) project's public affairs program

    International Nuclear Information System (INIS)

    Walter, L.H.

    1988-01-01

    As a first-of-a-kind facility, the Waste Isolation Pilot Plant (WIPP) presents a unique perspective on the value of designing a public affairs program that grown with and complements a project's evolution from construction to operations. Like the project itself, the public affairs programs progressed through several stages to its present scope. During the construction phase, foundations were laid in the community. Then, in this past year as the project entered a preoperational status, emphasis shifted to broaden the positive image that had been created locally. In this stage, public affairs presented the project's positive elements to the various state agencies, government officials, and federal organizations involved in our country's radioactive waste management program. Most recently, and continuing until receipt of the first shipment of waste in October 1988, an even broader, more aggressive public affairs program is planned

  18. An overview of the United States Department of Energy plant lifetime improvement program

    International Nuclear Information System (INIS)

    Rosinski, S.T.; Clauss, J.M.; Harrison, D.L.

    1993-01-01

    Today, 109 nuclear power plants provide over 20 percent of the electrical energy generated in the US. The operating license of the first of these plants will expire in the year 2000; one third of the operating licenses will expire by 2010 and the remaining plant licenses are scheduled to expire by 2033. The National Energy Strategy assumes that 70 percent of these plants will continue to operate beyond their current license expiration to assist in ensuring an adequate, diverse, and environmentally acceptable energy supply for economic growth. In order to preserve this energy resource in the US three major tasks must be successfully completed: (1) establishment of the regulations, technical standards, and procedures for the preparation and review of a license renewal application; (2) development, verification, and validation of the various technical criteria and bases for needed monitoring, refurbishment, or replacement of plant equipment; and (3) demonstration of the regulatory process. Since 1985, the US Department of Energy (DOE) has been working with the nuclear industry and the US Nuclear Regulatory Commission (NRC) to establish and demonstrate the option to extend the life of nuclear power plants through the renewal of operating licenses. This paper focuses primarily on DOE's Plant Lifetime Improvement (PLIM) Program efforts to develop the technical criteria and bases for effective aging management and lifetime improvement for continued operation of nuclear power plants. This paper describes current projects to resolve generic technical issues, including degradation of long-lived components, reactor pressure vessel (RPV) embrittlement management approaches, and analytical methodologies to characterize RPV integrity

  19. Fiscal year 1996 well installation program summary, Y-12 Plant Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    1997-04-01

    This report summarizes the well installation activities conducted during the federal fiscal year (FY) 1996 drilling program at the Oak Ridge Y-12 Plant, Oak Ridge Tennessee. Synopses of monitoring well construction/well development data, well location rationale, geological/hydrological observations, quality assurance/quality control methods, and health and safety monitoring are included. Two groundwater monitoring wells were installed during the FY 1996 drilling program. One of the groundwater monitoring wells was installed in the Lake Reality area and was of polyvinyl chloride screened construction. The other well, installed near the Ash Disposal Basin, was of stainless steel construction

  20. Implementation of the utilization program for the fuel elements of the Atucha I nuclear power plant

    International Nuclear Information System (INIS)

    Martin, H.R.; Serra, O.H.; Parker, Alejandro

    1981-01-01

    The programming operation for the use of the fuel elements in the Atucha-1 nuclear power plant was initially under the responsibility of the KWU Company, as part of the services rendered due for the manufacturing of said elements. This job was done with the help of the TRISIC program, developed in the early seventies by CNEA and SIEMENS staff. From april 21, 1979 on, CNEA took over the responsibility and strategy of the interchange of fuel elements. The several stages carried out for the implementation of this service are detailed. (M.E.L.) [es

  1. A reliability program for emergency diesel generators at nuclear power plants: Maintenance, surveillance, and condition monitoring

    International Nuclear Information System (INIS)

    Lofgren, E.V.; Henderson, W.; Burghardt, D.; Kripps, L.; Rothleder, B.

    1988-12-01

    This report is a companion report on NUREG/CR-5078, Volume 1, ''A Reliability Program for Emergency Diesel Generators at Nuclear Power Plants: Program Structure.'' The purpose of this report is to provide technical findings and insights related to: failure evaluation, troubleshooting, maintenance, surveillance, and condition monitoring. Examples and recommendations are provided for each of these areas based on actual emergency diesel generator (EDG) operating experience and the opinions of diesel generator experts. This report expands the more general guidance provided in Volume 1. In addition, a discussion of EDG interactions with other plant systems (e.g., instrument, air, service water, dc power) is provided since experience has shown that these support systems and their operation can adversely affect EDG reliability. Portions of this report have been designed for use by onsite personnel for evaluating operational characteristics of EDGs. 5 refs., 8 figs., 7 tabs

  2. Summary of inspection findings of licensee inservice testing programs at United States commercial nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Dunlop, A.; Colaccino, J.

    1996-12-01

    Periodic inspections of pump and valve inservice testing (IST) programs in United States commercial nuclear power plants are performed by Nuclear Regulatory Commission (NRC) Regional Inspectors to verify licensee regulatory compliance and licensee commitments. IST inspections are conducted using NRC Inspection Procedure 73756, {open_quotes}Inservice Testing of Pumps and Valves{close_quotes} (IP 73756), which was updated on July 27, 1995. A large number of IST inspections have also been conducted using Temporary Instruction 2515/114, {open_quotes}Inspection Requirements for Generic Letter 89-04, Acceptable Inservice Testing Programs{close_quotes} (TI-2515/114), which was issued January 15, 1992. A majority of U.S. commercial nuclear power plants have had an IST inspection to either IP 73756 or TI 2515/114. This paper is intended to summarize the significant and recurring findings from a number of these inspections since January of 1990.

  3. Development of intelligent database program for PSI/ISI data management of nuclear power plant

    International Nuclear Information System (INIS)

    Um, Byong Guk; Park, Un Su; Park, Ik Keun; Park, Yun Won; Kang, Suk Chul

    1998-01-01

    An intelligent database program has been developed under fully compatible with windows 95 for the construction of total support system and the effective management of Pre-/In-Service Inspection data. Using the database program, it can be executed the analysis and multi-dimensional evaluation of the defects detected during PSI/ISI in the pipe and the pressure vessel of the nuclear power plants. And also it can be used to investigate the NDE data inspected repetitively and the contents of treatment, and to offer the fundamental data for application of evaluation data related to Fracture Mechanics Analysis(FMA). Furthermore, the PSI/ISI database loads and material properties can be utilized to secure the higher degree of safety, integrity, reliability, and life-prediction of components and systems in nuclear power plant.

  4. Oregon state university's advanced plant experiment (APEX) AP1000 integral facility test program

    International Nuclear Information System (INIS)

    Reyes, J.N.; Groome, J.T.; Woods, B.G.; Young, E.; Abel, K.; Wu, Q.

    2005-01-01

    Oregon State University (OSU) has recently completed a three year study of the thermal hydraulic behavior of the Westinghouse AP1000 passive safety systems. Eleven Design Basis Accident (DBA) scenarios, sponsored by the U.S. Department of Energy (DOE) with technical support from Westinghouse Electric, were simulated in OSU's Advanced Plant Experiment (APEX)-1000. The OSU test program was conducted within the purview of the requirements of 10CFR50 Appendix B, NQA-1 and 10 CFR 21 and the test data was used to provide benchmarks for computer codes used in the final design approval of the AP1000. In addition to the DOE certification testing, OSU conducted eleven confirmatory tests for the U.S. Nuclear Regulatory Commission. This paper presents the test program objectives, a description of the APEX-1000 test facility and an overview of the test matrix that was conducted in support of plant certification. (authors)

  5. Results of calendar year 1995 Well Inspection and Maintenance Program Y-12 Plant, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    McMaster, B.W.

    1996-07-01

    This document is a compendium of results of the 1995 Monitor Well Inspection and Maintenance Program at the US Department of Energy's Oak Ridge Y-12 Plant. This report documents the work relating to well inspections and maintenance requests. Inspections are implemented in order to better assess the condition and maintenance needs of wells that are actively being monitored. Currently this approach calls for inspecting all wells on a routine (annual or triennial) basis which are: (1) in an active sampling program; (2) included in a hydrologic study; or (3) not in service, but not scheduled for plugging and abandonment. Routine inspections help to ensure that representative groundwater samples and hydrologic data are being collected, and contribute to the effective longevity of each well. This report formally presents well inspection and maintenance activities that were conducted at the Y-12 Plant from August through December 1995

  6. Material protection control and accounting program activities at the Urals electrochemical integrated plant

    International Nuclear Information System (INIS)

    McAllister, S.

    1997-01-01

    The Urals Electrochemical Integrated Plant (UEIP) is the Russian Federation's largest uranium enrichment plant and one of three sites in Russia blending high enriched uranium (HEU) into commercial grade low enriched uranium. UEIP is located approximately 70 km north of Yekaterinburg in the closed city of Novouralsk (formerly Sverdlovsk- 44). DOE's MPC ampersand A program first met with UEIP in June of 1996, however because of some contractual issues the work did not start until September of 1997. The six national laboratories participating in DOE's Material Protection Control and Accounting program are cooperating with UEIP to enhance the capabilities of the physical protection, access control, and nuclear material control and accounting systems. The MPC ampersand A work at UEIP is expected to be completed during fiscal year 2001

  7. Program of social protection for Chornobyl nuclear power plant staff and Slavutich town residents in the aftermath of the plant shutdown

    International Nuclear Information System (INIS)

    Komarov, V.A.

    2001-01-01

    In order to solve social issues related to ChNPP shutdown, the Ukrainian Government approved 'Program of Social Protection for Chornobyl Nuclear Power Plant Staff and Slavutich Town Residents in Aftermath of Plant Shutdown' on 29 November 2000. The Program Objective is to ensure social protection and support of well being of ChNPP staff and Slavutich town residents after the plant shutdown. Preserve and develop town infrastructure. Create compensatory jobs; efficiently manage human resources; provide social allowances and guarantees to the ChNPP staff that is being released, and Slavutich town residents

  8. Improving human reliability through better nuclear power plant system design: Program for advanced nuclear power studies

    International Nuclear Information System (INIS)

    Golay, M.W.

    1993-01-01

    The project on ''Development of a Theory of the Dependence of Human Reliability upon System Designs as a Means of Improving Nuclear Power Plant Performance'' was been undertaken in order to address the problem of human error in advanced nuclear power plant designs. Lack of a mature theory has retarded progress in reducing likely frequencies of human errors. Work being pursued in this project is to perform a set of experiments involving human subjects who are required to operate, diagnose and respond to changes in computer-simulated systems, relevant to those encountered in nuclear power plants, which are made to differ in complexity in a systematic manner. The computer program used to present the problems to be solved also records the response of the operator as it unfolds

  9. Comparative Study on Electric Generation Cost of HTR with Another Electric Plant Using LEGECOST Program

    International Nuclear Information System (INIS)

    Mochamad-Nasrullah; Soetrisnanto, Arnold Y.; Tosi-Prastiadi; Adiwardojo

    2000-01-01

    Monetary and economic crisis in Indonesia resulted in impact of electricity and demand and supply planning that it has to be reevaluated. One of the reasons is budget limitation of the government as well as private companies. Considering this reason, the economic calculation for all of aspect could be performed, especially the calculation of electric generation cost. This paper will discuss the economic aspect of several power plants using fossil and nuclear fuel including High Temperature Reactor (HTR). Using Levelized Generation Cost (LEGECOST) program developed by IAEA (International Atomic Energy Agency), the electric generation cost of each power plant could be calculated. And then, the sensitivity analysis has to be done using several economic parameters and scenarios, in order to be known the factors that influence the electric generation cost. It could be concluded, that the electric generation cost of HTR is cheapest comparing the other power plants including nuclear conventional. (author)

  10. Quality assurance program manual for nuclear power plants. Volume I. Policies

    International Nuclear Information System (INIS)

    1975-01-01

    Policies and procedures are presented which comply with current NRC regulatory requirements and industry codes and standards in effect during the design, procurement, construction, testing, operation, refueling, maintenance, repair and modification activities associated with nuclear power plants. Specific NRC and industry documents that contain the requirements, including the issue dates in effect, are identified in each nuclear power plant's Safety Analysis Report. The requirements established by these documents form the basis for the Consumers Power Quality Assurance Program, which is implemented to control those structures, systems, components and operational safety actions listed in each nuclear power plant's Quality List (Q-List). As additional and revised requirements are issued by the NRC and professional organizations involved in nuclear activities, they will be reviewed for their impact on this manual, and changes will be made where considered necessary

  11. A comparative examination of tuberculosis immigration medical screening programs from selected countries with high immigration and low tuberculosis incidence rates

    Science.gov (United States)

    2011-01-01

    Background Tuberculosis (TB) in migrants is an ongoing challenge in several low TB incidence countries since a large proportion of TB in these countries occurs in migrants from high incidence countries. To meet these challenges, several countries utilize TB screening programs. The programs attempt to identify and treat those with active and/or infectious stages of the disease. In addition, screening is used to identify and manage those with latent or inactive disease after arrival. Between nations, considerable variation exists in the methods used in migration-associated TB screening. The present study aimed to compare the TB immigration medical examination requirements in selected countries of high immigration and low TB incidence rates. Methods Descriptive study of immigration TB screening programs Results 16 out of 18 eligible countries responded to the written standardized survey and phone interview. Comparisons in specific areas of TB immigration screening programs included authorities responsible for TB screening, the primary objectives of the TB screening program, the yield of detection of active TB disease, screening details and aspects of follow up for inactive pulmonary TB. No two countries had the same approach to TB screening among migrants. Important differences, common practices, common problems, evidence or lack of evidence for program specifics were noted. Conclusions In spite of common goals, there is great diversity in the processes and practices designed to mitigate the impact of migration-associated TB among nations that screen migrants for the disease. The long-term goal in decreasing migration-related introduction of TB from high to low incidence countries remains diminishing the prevalence of the disease in those high incidence locations. In the meantime, existing or planned migration screening programs for TB can be made more efficient and evidenced based. Cooperation among countries doing research in the areas outlined in this study should

  12. A National Survey Examining Manuscript Dissertation Formats Among Nursing PhD Programs in the United States.

    Science.gov (United States)

    Graves, Janessa M; Postma, Julie; Katz, Janet R; Kehoe, Leanne; Swalling, Eileen; Barbosa-Leiker, Celestina

    2018-03-08

    Among research-focused nursing doctoral (PhD) programs in the United States, the traditional dissertation format has recently given way to a series of publication-ready manuscripts, often bookended by introduction and conclusion chapters. To help programs make decisions about the use of these formats, this study undertook a national survey of programs offering PhDs in nursing. The purpose of this study was to explore the advantages and disadvantages of the traditional format versus manuscript option for dissertations among nursing PhD programs in the United States. Cross-sectional census survey of U.S. nursing PhD programs. A web-based survey was administered to all U.S. nursing PhD programs. Respondents indicated formats offered, factors contributing to decisions of which formats to offer, and lessons learned. Descriptive statistics and inductive content analyses were used for analysis. Of 121 eligible institutions, 79 provided eligible responses (66.7%). The majority (59%) offered both formats; 11% offered the manuscript option only, and 24% offered the traditional format only. Faculty support (or lack thereof) contributed to adoption (or not) of the manuscript option. Respondents' approaches to the manuscript option (e.g., number of papers) and advice are summarized. Manuscript option dissertations are commonly offered and provide benefits to students and faculty; however, thoughtful implementation is critical. Programs need to agree upon clear expectations and have graduate school support (e.g., formatting). Faculty need mentorship in advising manuscript option students who choose to use this format, and the time and support. Finally, students need additional writing skills that could be provided through coursework or via individual work with mentors. As nursing education continues to expand further into doctoral research, programs must examine dissertation formats in order to both prepare future nurse scholars and disseminate nursing research that is critical

  13. Context Matters for Social-Emotional Learning: Examining Variation in Program Impact by Dimensions of School Climate.

    Science.gov (United States)

    McCormick, Meghan P; Cappella, Elise; O'Connor, Erin E; McClowry, Sandee G

    2015-09-01

    This paper examines whether three dimensions of school climate-leadership, accountability, and safety/respect-moderated the impacts of the INSIGHTS program on students' social-emotional, behavioral, and academic outcomes. Twenty-two urban schools and N = 435 low-income racial/ethnic minority students were enrolled in the study and received intervention services across the course of 2 years, in both kindergarten and first grade. Intervention effects on math and reading achievement were larger for students enrolled in schools with lower overall levels of leadership, accountability, and safety/respect at baseline. Program impacts on disruptive behaviors were greater in schools with lower levels of accountability at baseline; impacts on sustained attention were greater in schools with lower levels of safety/respect at baseline. Implications for Social-Emotional Learning program implementation, replication, and scale-up are discussed.

  14. Examining the Sensory Profiles of At-Risk Youth Participating in a Pre-employment Program

    Directory of Open Access Journals (Sweden)

    Chi-Kwan Shea Ph.D., OTR/L

    2012-11-01

    Full Text Available The purpose of this study is to use Dunn’s model of sensory processing to investigate the sensory profiles of youth participating in a community-based occupational therapy pre-employment program. The youth participants had been involved in the juvenile justice system and were placed on probation. The studyanalyzed data from the Adolescent/Adult Sensory Profile (AASP questionnaires (Brown & Dunn, 2002 completed by 79 youth participants. Analysis of the participants’ scores on the AASP showed statistically significant differences from the norm in two quadrants; the delinquent youth scored lower in Sensation Seeking and higher in Sensation Avoiding. The delinquent youth participants demonstrated a high prevalence of atypical sensory processing patterns. Implications for further investigation and practice are discussed.

  15. Examining the response programming function of the Quiet Eye: Do tougher shots need a quieter eye?

    Science.gov (United States)

    Walters-Symons, Rosanna; Wilson, Mark; Klostermann, Andre; Vine, Samuel

    2018-02-01

    Support for the proposition that the Quiet Eye (QE) duration reflects a period of response programming (including task parameterisation) has come from research showing that an increase in task difficulty is associated with increases in QE duration. Here, we build on previous research by manipulating three elements of task difficulty that correspond with different parameters of golf-putting performance; force production, impact quality and target line. Longer QE durations were found for more complex iterations of the task and furthermore, more sensitive analyses of the QE duration suggest that the early QE proportion (prior to movement initiation) is closely related to force production and impact quality. However, these increases in QE do not seem functional in terms of supporting improved performance. Further research is needed to explore QE's relationship with performance under conditions of increased difficulty.

  16. PCXMC. A PC-based Monte Carlo program for calculating patient doses in medical x-ray examinations

    International Nuclear Information System (INIS)

    Tapiovaara, M.; Lakkisto, M.; Servomaa, A.

    1997-02-01

    The report describes PCXMC, a Monte Carlo program for calculating patients' organ doses and the effective dose in medical x-ray examinations. The organs considered are: the active bone marrow, adrenals, brain, breasts, colon (upper and lower large intestine), gall bladder, heats, kidneys, liver, lungs, muscle, oesophagus, ovaries, pancreas, skeleton, skin, small intestine, spleen, stomach, testes, thymes, thyroid, urinary bladder, and uterus. (42 refs.)

  17. Examining mixing methods in an evaluation of a smoking cessation program.

    Science.gov (United States)

    Betzner, Anne; Lawrenz, Frances P; Thao, Mao

    2016-02-01

    Three different methods were used in an evaluation of a smoking cessation study: surveys, focus groups, and phenomenological interviews. The results of each method were analyzed separately and then combined using both a pragmatic and dialectic stance to examine the effects of different approaches to mixing methods. Results show that the further apart the methods are philosophically, the more diverse the findings. Comparisons of decision maker opinions and costs of the different methods are provided along with recommendations for evaluators' uses of different methods. Copyright © 2015. Published by Elsevier Ltd.

  18. Recommended research program for improving seismic safety of light-water nuclear power plants

    International Nuclear Information System (INIS)

    1979-04-01

    Recommendations are presented for research areas concerned with seismic safety. These recommendations are based on an analysis of the answers to a questionnaire which was sent to over 80 persons working in the area of seismic safety of nuclear power plants. In addition to the answers of the 55 questionnaires which were received, the recommendations are based on ideas expressed at a meeting of an ad hoc group of professionals formed by Sandia, review of literature, current research programs, and engineering judgement

  19. Prototype vibration measurement program for reactor internals (177-fuel assembly plant). Supplement 1

    International Nuclear Information System (INIS)

    Simonis, J.C.; Post, R.C.; Thoren, D.E.

    1976-08-01

    The surveillance specimen holder tubes installed in the Babcock and Wilcox 177-fuel assembly plants have been redesigned. The structural adequacy of this design has been verified through extensive analysis. The design adequacy will be further confirmed by measuring the vibrational response of the surveillance specimen holder tube during normal and transient flow operation. This report describes the vibration measurement program that will be conducted at Toledo Edison's Davis Besse 1 site

  20. European passive plant program preliminary safety analyses to support system design

    International Nuclear Information System (INIS)

    Saiu, Gianfranco; Barucca, Luciana; King, K.J.

    1999-01-01

    In 1994, a group of European Utilities, together with Westinghouse and its Industrial Partner GENESI (an Italian consortium including ANSALDO and FIAT), initiated a program designated EPP (European Passive Plant) to evaluate Westinghouse Passive Nuclear Plant Technology for application in Europe. In the Phase 1 of the European Passive Plant Program which was completed in 1996, a 1000 MWe passive plant reference design (EP1000) was established which conforms to the European Utility Requirements (EUR) and is expected to meet the European Safety Authorities requirements. Phase 2 of the program was initiated in 1997 with the objective of developing the Nuclear Island design details and performing supporting analyses to start development of Safety Case Report (SCR) for submittal to European Licensing Authorities. The first part of Phase 2, 'Design Definition' phase (Phase 2A) was completed at the end of 1998, the main efforts being design definition of key systems and structures, development of the Nuclear Island layout, and performing preliminary safety analyses to support design efforts. Incorporation of the EUR has been a key design requirement for the EP1000 form the beginning of the program. Detailed design solutions to meet the EUR have been defined and the safety approach has also been developed based on the EUR guidelines. The present paper describes the EP1000 approach to safety analysis and, in particular, to the Design Extension Conditions that, according to the EUR, represent the preferred method for giving consideration to the Complex Sequences and Severe Accidents at the design stage without including them in the design bases conditions. Preliminary results of some DEC analyses and an overview of the probabilistic safety assessment (PSA) are also presented. (author)

  1. A study of the international trend and comprehensive enhancement program on the Nuclear Power Plant safety

    Energy Technology Data Exchange (ETDEWEB)

    Jang, Soon Hong; Cho, Nam Jin; Paek, Won Phil [Korea Advanced Institute of Science and Technology, Taejon (Korea, Republic of)

    1990-12-15

    The objectives of this study are as follows : overview of the international trend related to the safety of Nuclear Power Plant(NPPs), study of the present status of NPP safety in Korea in aspects of design, construction and operation, suggestion of the comprehensive program to improve NPP safety in Korea. The results of this study can contribute to improve the safety of existing and future NPPs, and to establish the severe accident policy in Korea.

  2. A study of the international trend and comprehensive enhancement program on the Nuclear Power Plant safety

    International Nuclear Information System (INIS)

    Jang, Soon Hong; Cho, Nam Jin; Paek, Won Phil

    1990-12-01

    The objectives of this study are as follows : overview of the international trend related to the safety of Nuclear Power Plant(NPPs), study of the present status of NPP safety in Korea in aspects of design, construction and operation, suggestion of the comprehensive program to improve NPP safety in Korea. The results of this study can contribute to improve the safety of existing and future NPPs, and to establish the severe accident policy in Korea

  3. V-Model based Configuration Management Program for New-Build Nuclear Power Plant

    Energy Technology Data Exchange (ETDEWEB)

    An, Kyungik [PartDB Co. Ltd., Daejeon (Korea, Republic of); Cho, Yoon Sang [KHNP Co. Ltd., Daejeon (Korea, Republic of); Freeland, Kent R. [Industrial Analysts Incorporated, New Hampshire (United States)

    2014-05-15

    As NPP operators undertook design basis reconstitution efforts, they began to realize that the design basis is a foundation for Configuration Management (CM). This realization was made evident in the magnitude of the problems that were being observed. This experience also raised serious questions about how the information being developed to produce the design basis documents would be kept up to date in the future. A process to reconstitute the design basis is likely to be ineffective if CM controls are not in place. The right IT solution for CM depends upon a number of factors, including the nuclear power plant culture, budget, target technology, and the nuclear power plant owner/operator's standards, requirements and limitations for its generating fleet. Comprehensive CM Program for NPP is the single greatest strategy to meet the commitment to nuclear excellence. The safety and viability of nuclear power, particularly at the fleet level, depends upon the development of positive design control and design basis to better understanding plant operating dynamics and margin management, along with technology to control the realization of such design in the physical plant. However the most of plant facilities are modified many times, often without suitable support needed to confirm with their design base and to update their engineering data, maintenance rules and operating procedures. This lack of equilibrium between the requirements, design information and physical plant still remains a important issue. This study focuses on how to manage the configuration information of NPP using systems engineering V-model approach, and proposes data model to manage the configuration information in relation to manage their life cycle. Comprehensive CM Program and IMS for NPP life cycle support is the greatest strategy to meet the commitment to nuclear safety.

  4. ROS-mediated abiotic stress-induced programmed cell death in plants

    Directory of Open Access Journals (Sweden)

    Veselin ePetrov

    2015-02-01

    Full Text Available During the course of their ontogenesis, plants are continuously exposed to a large variety of abiotic stress factors which can damage tissues and jeopardize the survival of the organism unless properly countered. While animals can simply escape and thus evade stressors, plants as sessile organisms have developed complex strategies to withstand them. When the intensity of a detrimental factor is high, one of the defense programs employed by plants is the induction of programmed cell death (PCD. This is an active, genetically controlled process which is initiated to isolate and remove damaged tissues thereby ensuring the survival of the organism. The mechanism of PCD induction usually includes an increase in the levels of reactive oxygen species (ROS which are utilized as mediators of the stress signal. Abiotic stress-induced PCD is not only a process of fundamental biological importance, but also of considerable interest to agricultural practice as it has the potential to significantly influence crop yield. Therefore, numerous scientific enterprises have focused on elucidating the mechanisms leading to and controlling PCD in response to adverse conditions in plants. This knowledge may help to develop novel strategies to obtain more resilient crop varieties with improved tolerance and enhanced productivity. The aim of the present review is to summarize the recent advances in research on ROS-induced PCD related to abiotic stress and the role of the organelles in the process.

  5. Final Report on the Operation and Maintenance Improvement Program for Concentrating Solar Power Plants

    International Nuclear Information System (INIS)

    Cohen, Gilbert E.; Kearney, David W.; Kolb, Gregory J.

    1999-01-01

    This report describes the results of a six-year, $6.3 million project to reduce operation and maintenance (O ampersand M) costs at power plants employing concentrating solar power (CSP) technology. Sandia National Laboratories teamed with KJC Operating Company to implement the O ampersand M Improvement Program. O ampersand M technologies developed during the course of the program were demonstrated at the 150-MW Kramer Junction solar power park located in Boron, California. Improvements were made in the following areas: (a) efficiency of solar energy collection, (b) O ampersand M information management, (c) reliability of solar field flow loop hardware, (d) plant operating strategy, and (e) cost reduction associated with environmental issues. A 37% reduction in annual O ampersand M costs was achieved. Based on the lessons learned, an optimum solar- field O ampersand M plan for future CSP plants is presented. Parabolic trough solar technology is employed at Kramer Junction. However, many of the O ampersand M improvements described in the report are also applicable to CSP plants based on solar power tower or dish/engine concepts

  6. Final Report on the Operation and Maintenance Improvement Program for Concentrating Solar Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Cohen Gilbert E.; Kearney, David W.; Kolb, Gregory J.

    1999-06-01

    This report describes the results of a six-year, $6.3 million project to reduce operation and maintenance (O&M) costs at power plants employing concentrating solar power (CSP) technology. Sandia National Laboratories teamed with KJC Operating Company to implement the O&M Improvement Program. O&M technologies developed during the course of the program were demonstrated at the 150-MW Kramer Junction solar power park located in Boron, California. Improvements were made in the following areas: (a) efficiency of solar energy collection, (b) O&M information management, (c) reliability of solar field flow loop hardware, (d) plant operating strategy, and (e) cost reduction associated with environmental issues. A 37% reduction in annual O&M costs was achieved. Based on the lessons learned, an optimum solar- field O&M plan for future CSP plants is presented. Parabolic trough solar technology is employed at Kramer Junction. However, many of the O&M improvements described in the report are also applicable to CSP plants based on solar power tower or dish/engine concepts.

  7. Viral recombination blurs taxonomic lines: examination of single-stranded DNA viruses in a wastewater treatment plant

    Directory of Open Access Journals (Sweden)

    Victoria M. Pearson

    2016-10-01

    Full Text Available Understanding the structure and dynamics of microbial communities, especially those of economic concern, is of paramount importance to maintaining healthy and efficient microbial communities at agricultural sites and large industrial cultures, including bioprocessors. Wastewater treatment plants are large bioprocessors which receive water from multiple sources, becoming reservoirs for the collection of many viral families that infect a broad range of hosts. To examine this complex collection of viruses, full-length genomes of circular ssDNA viruses were isolated from a wastewater treatment facility using a combination of sucrose-gradient size selection and rolling-circle amplification and sequenced on an Illumina MiSeq. Single-stranded DNA viruses are among the least understood groups of microbial pathogens due to genomic biases and culturing difficulties, particularly compared to the larger, more often studied dsDNA viruses. However, the group contains several notable well-studied examples, including agricultural pathogens which infect both livestock and crops (Circoviridae and Geminiviridae, and model organisms for genetics and evolution studies (Microviridae. Examination of the collected viral DNA provided evidence for 83 unique genotypic groupings, which were genetically dissimilar to known viral types and exhibited broad diversity within the community. Furthermore, although these genomes express similarities to known viral families, such as Circoviridae, Geminiviridae, and Microviridae, many are so divergent that they may represent new taxonomic groups. This study demonstrated the efficacy of the protocol for separating bacteria and large viruses from the sought after ssDNA viruses and the ability to use this protocol to obtain an in-depth analysis of the diversity within this group.

  8. Fiscal year 1995 well plugging and abandonment program Y-12 Plant, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    1995-09-01

    This report is a synopsis of the progress of the well plugging and abandonment program at the Y-12 Plant, Oak Ridge, Tennessee, from September 1994 through August 1995. A total of 67 wells, piezometers, and borings were plugged and abandoned during the period of time covered in this report. All wells and borings were plugged and abandoned if (1) its construction did not meet current standards (substandard construction); (2) it was irreparably damaged or had deteriorated beyond practical repair; (3) its location interfered with or otherwise impeded site operations, construction, or closure activities; or (4) special circumstances existed as defined on a case-by-case basis and approved by the Y-12 Plant Groundwater Protection Program (GWPP) Manager. This summary report contains: general geologic setting of the Y-12 Plant and vicinity; discussion of well plugging and abandonment methods, grouting procedures, and waste management practices (a Waste Management Plan for Drilling Activities is included in Appendix C); summaries of plugging and abandonment activities at each site; and quality assurance/quality control (QA/QC) and health and safety protocols used during the FY 1995 Plugging and Abandonment Program

  9. Fiscal year 1995 well plugging and abandonment program Y-12 Plant, Oak Ridge, Tennessee

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-09-01

    This report is a synopsis of the progress of the well plugging and abandonment program at the Y-12 Plant, Oak Ridge, Tennessee, from September 1994 through August 1995. A total of 67 wells, piezometers, and borings were plugged and abandoned during the period of time covered in this report. All wells and borings were plugged and abandoned if (1) its construction did not meet current standards (substandard construction); (2) it was irreparably damaged or had deteriorated beyond practical repair; (3) its location interfered with or otherwise impeded site operations, construction, or closure activities; or (4) special circumstances existed as defined on a case-by-case basis and approved by the Y-12 Plant Groundwater Protection Program (GWPP) Manager. This summary report contains: general geologic setting of the Y-12 Plant and vicinity; discussion of well plugging and abandonment methods, grouting procedures, and waste management practices (a Waste Management Plan for Drilling Activities is included in Appendix C); summaries of plugging and abandonment activities at each site; and quality assurance/quality control (QA/QC) and health and safety protocols used during the FY 1995 Plugging and Abandonment Program.

  10. Development and Evaluation of a Student-Initiated Test Preparation Program for the USMLE Step 1 Examination.

    Science.gov (United States)

    Schwartz, Lindsay F; Lineberry, Matthew; Park, Yoon Soo; Kamin, Carol S; Hyderi, Abbas A

    2018-01-01

    Studies have documented performance on the United States Medical Licensing Examination® (USMLE) Step 1 exam as an important factor that residency program directors consider when deciding which applicants to interview and rank. Therefore, success on this exam, though only one aspect of applicant evaluation, is important in determining future career prospects for medical students. Unfortunately, mean test scores at the University of Illinois College of Medicine at Chicago (UIC) have historically been below the national average. This retrospective and quasi-experimental mixed-methods study describes the development, evaluation, and effects of a student-initiated USMLE Step 1 preparatory program at UIC. The program provided second year students with First Aid for the USMLE Step 1 at the beginning of the academic year, as well as a six month subscription to the USMLE World question bank midyear. In addition, optional peer review sessions covering basic sciences and organ systems were taught by high-performing upperclassmen. The goals of the program were to raise mean USMLE Step 1 exam scores and increase the percentage of students passing the exam on their first time. The program premiered during the 2012-13 academic year. Data from this cohort as well as four others (N = 830; 2010-2014 examinees) were gathered. Performances between preintervention (2010-12 examinees) and postintervention (2013-14 examinees) cohorts of students were compared. Focus groups and interviews with staff and students were conducted, recorded, and analyzed to investigate the impact that the program had on student interactions and perceptions of the learning environment. There was a significant difference in exam performance pre- versus postintervention, with average USMLE Step 1 scores improving by 8.82 points following the implementation of the student-initiated program, t(5.61) = 828, p Step 1 (odds ratio = 3.08, SE = 1.07, p < .01). Students and staff commented on the sense of community and

  11. Project Management Plan for the Idaho National Engineering Laboratory Waste Isolation Pilot Plant Experimental Test Program

    International Nuclear Information System (INIS)

    Connolly, M.J.; Sayer, D.L.

    1993-11-01

    EG ampersand G Idaho, Inc. and Argonne National Laboratory-West (ANL-W) are participating in the Idaho National Engineering Laboratory's (INEL's) Waste Isolation Pilot Plant (WIPP) Experimental Test Program (WETP). The purpose of the INEL WET is to provide chemical, physical, and radiochemical data on transuranic (TRU) waste to be stored at WIPP. The waste characterization data collected will be used to support the WIPP Performance Assessment (PA), development of the disposal No-Migration Variance Petition (NMVP), and to support the WIPP disposal decision. The PA is an analysis required by the Code of Federal Regulations (CFR), Title 40, Part 191 (40 CFR 191), which identifies the processes and events that may affect the disposal system (WIPP) and examines the effects of those processes and events on the performance of WIPP. A NMVP is required for the WIPP by 40 CFR 268 in order to dispose of land disposal restriction (LDR) mixed TRU waste in WIPP. It is anticipated that the detailed Resource Conservation and Recovery Act (RCRA) waste characterization data of all INEL retrievably-stored TRU waste to be stored in WIPP will be required for the NMVP. Waste characterization requirements for PA and RCRA may not necessarily be identical. Waste characterization requirements for the PA will be defined by Sandia National Laboratories. The requirements for RCRA are defined in 40 CFR 268, WIPP RCRA Part B Application Waste Analysis Plan (WAP), and WIPP Waste Characterization Program Plan (WWCP). This Project Management Plan (PMP) addresses only the characterization of the contact handled (CH) TRU waste at the INEL. This document will address all work in which EG ampersand G Idaho is responsible concerning the INEL WETP. Even though EG ampersand G Idaho has no responsibility for the work that ANL-W is performing, EG ampersand G Idaho will keep a current status and provide a project coordination effort with ANL-W to ensure that the INEL, as a whole, is effectively and

  12. DSNP, Program and Data Library System for Dynamic Simulation of Nuclear Power Plant

    International Nuclear Information System (INIS)

    Saphier, D.; Madell, J.; Dean, E.

    1988-01-01

    1 - Description of problem or function: DSNP (Dynamic Simulator for Nuclear Power-Plants) is a system of programs and data files by which a nuclear power plant, or part thereof, can be simulated. The acronym DSNP is used interchangeably for the DSNP language, the DSNP libraries, the DSNP pre-compiler, and the DSNP document generator. The DSNP language is a special-purpose, block-oriented digital- simulation language developed to facilitate the preparation of dynamic simulations of a large variety of nuclear power plants. It is a user-oriented language that permits the user to prepare simulation programs directly from power plant block diagrams and flow charts by recognizing the symbolic DSNP statements for the appropriate physical components and listing these statements in a logical sequence according to the flow of physical properties in the simulated power plant. Physical components of nuclear power plants are represented by functional blocks, or modules. Many of the more complex components are represented by several modules. The nuclear reactor, for example, has a kinetic module, a power distribution module, a feedback module, a thermodynamic module, a hydraulic module, and a radioactive heat decay module. These modules are stored in DSNP libraries in the form of a DSNP subroutine or function, a block of statements, a macro, or a combination of the above. Basic functional blocks such as integrators, pipes, function generators, connectors, and many auxiliary functions representing properties of materials used in nuclear power plants are also available. The DSNP pre-compiler analyzes the DSNP simulation program, performs the appropriate translations, inserts the requested modules from the library, links these modules together, searches necessary data files, and produces a simulation program in FORTRAN. FORTRAN is considered to be a subset of DSNP and can be inserted anywhere in the simulation program without restriction. I/O statements can be located anywhere in

  13. A nuclear power plant operator's view on the effects of ICRP recommendation 26 upon his radiation protection program

    International Nuclear Information System (INIS)

    Selleslagh, E.

    1981-01-01

    The effects of ICRP recommendation 26 on rules to be implemented by nuclear power plant operators in their radiation protection program, are examined from various points of view: legal and para-legal aspects such as implementation by local authorities and interference with the regulatory process, external and internal irradiation control and limitation, ALARA and cost-benefit aspects, and the record keeping and monitoring requirements. It appears that certain parts of ICRP 26 were not retained by Euratom and thus have little chance of appearing in modified European law. Nonetheless, they are applied through licensing practices. ICRP 26 itself either confirms existing practice, which was often more conservative than law, or relaxes limits, and provides a more logical context for non-whole body exposures. ALARA-rules and practices cause an additional administrative burden, but this already existed and provides useful data for the plant management. The problem of ''zero dose'' and of converting in vivo measurements to dose in case the intakes are unknown, are addressed briefly. It is concluded that ICRP 26 brings no real changes for radiation protection in nuclear power plants, except maybe some increased flexibility, and that the operators are pretty happy with it, but less so with the way it is being imposed on them. (author)

  14. Examining the Sustainability of an Evidence-Based Preschool Curriculum: The REDI Program

    Science.gov (United States)

    Sanford DeRousie, Rebecca M.; Bierman, Karen L.

    2011-01-01

    This study examined the extent to which an evidence-based preschool curriculum (Head Start REDI) was sustained by 20 teachers during the year following a randomized controlled efficacy trial, when teachers were no longer required by the research project to implement the curriculum. Two quantitative measures of sustainability (teacher ratings, REDI coach ratings) and a qualitative measure (teacher interview) were collected and compared. Sustainability varied by the specific curriculum component, with higher rates of sustainability for the social-emotional component (Preschool PATHS) than for the language and literacy components. Estimates of sustainability were affected by the method of measurement, with REDI coach ratings and qualitative teacher interviews more closely aligned than teacher ratings. Responses from qualitative interviews identified the main factors that teachers thought affected sustainability. Teacher responses suggest that efforts to promote sustainability are best targeted at reducing barriers, such as competing demands, rather than simply highlighting the benefits of the new curriculum. PMID:22408287

  15. Examining DNA fingerprinting as an epidemiology tool in the tuberculosis program in the Northwest Territories, Canada.

    Science.gov (United States)

    Case, Cheryl; Kandola, Kami; Chui, Linda; Li, Vincent; Nix, Nancy; Johnson, Rhonda

    2013-01-01

    Tuberculosis (TB) is an important public health problem in the Northwest Territories (NWT), particularly among Canadian Aboriginal people. To analyse the transmission patterns of tuberculosis among the population living in the NWT, a territorial jurisdiction located within Northern Canada. This population-based retrospective study examined the DNA fingerprints of all laboratory confirmed cases of TB in the NWT, Canada, between 1990 and 2009. An isolate of each lab-confirmed case had genotyping done using IS6110 Restriction Fragment Length Polymorphism. DNA patterns were assigned to each DNA fingerprint, and indistinguishable fingerprints patterns were assigned a cluster. Social network analysis (SNA) was used to examine direct linkages among cases determined through conventional contact tracing (CCT), their DNA fingerprint and home community. Of the 225 lab-confirmed cases identified, the study was limited to 195 subjects due to DNA fingerprinting data availability. The mean age of the cases was 43.8 years (±22.6) and 120 (61.5%) males. The Dene (First Nations) encompassed 120 of the cases (87.7%), 8 cases (4.1%) were Inuit, 2 cases (1.0%) were Metis, 7 cases (3.6%) were Immigrants and 1 case had unknown ethnicity. One hundred and eighty six (95.4%) subjects were clustered, resulting in 8 clusters. Trend analysis showed significant relationships between with risk factors for unemployment (p=0.020), geographic location (p≤0.001) and homelessness (p≤0.001). Other significant risk factors included excessive alcohol consumption, prior infection with Mycobacterium tuberculosis and prior contact with a case of TB. This study demonstrates how DNA fingerprinting and SNA can be additional epidemiological tools, along with CCT method, to determine transmission patterns of TB.

  16. A longitudinal examination of alcohol pharmacotherapy adoption in substance use disorder treatment programs: patterns of sustainability and discontinuation.

    Science.gov (United States)

    Abraham, Amanda J; Knudsen, Hannah K; Roman, Paul M

    2011-07-01

    The objectives of this study were to (a) identify the patterns of disulfiram (Antabuse) and tablet naltrexone (Revia) adoption over a 48-month period in a nationally representative sample of privately funded programs that deliver substance use disorder treatment; (b) examine predictors of sustainability, later adoption, discontinuation, and nonadoption of disulfiram and tablet naltrexone; and (c) measure reasons for medication discontinuation. Two waves of data were collected via face-to-face structured interviews with 223 program administrators. These data demonstrated that adoption of medications for alcohol use disorders (AUDs) was a dynamic process. Although nonadoption was the most common pattern, approximately 20% of programs sustained use of the AUD medications and 30% experienced organizational change in adoption over the study period. Bivariate multinomial logistic regression models revealed that organizational characteristics were associated with sustainability including location in a hospital setting, program size, accreditation, revenues from private insurance, referrals from the criminal justice system, number of medical staff, and use of selective serotonin reuptake inhibitors at baseline. Two patterns of discontinuation were found: Programs either discontinued use of all substance use disorder medications or replaced disulfiram/tablet naltrexone with a newer AUD medication. These findings suggest that adoption of AUD medications may be positively affected by pressure from accreditation bodies, partnering with primary care physicians, medication-specific training for medical staff, greater availability of resources to cover the costs associated with prescribing AUD medications, and amending criminal justice contracts to include support for AUD medication use.

  17. Design and analysis of aquatic monitoring programs at nuclear power plants

    International Nuclear Information System (INIS)

    McKenzie, D.H.; Kannberg, L.D.; Gore, K.L.; Arnold, E.M.; Watson, D.G.

    1977-11-01

    This report addresses some of the problems of designing, conducting, and analyzing aquatic environmental monitoring programs for impact assessment of nuclear power plants. The concepts discussed are applicable to monitoring the effects of chemical, radioactive, or thermal effluents. The concept of control and treatment station pairs is the fundamental basis for the experimental method proposed. This concept is based on the hypothesis that the relationship between the two stations forming the pair can be estimated from the preoperational period and that this relationship holds during the operational period. Any changes observed in this relationship during the operational period are assumed to be the result of the power plant impacts. Thus, it is important that station pairs are selected so it can be assumed that they respond to natural environmental changes in a manner that maintains that relationship. The major problem in establishing the station pairs will be the location of the control station. The universal heterogeneity in the environment will prevent the establishment of identical station pairs. The requirement that the control station remain unaffected by the operation of the power plant dictates a spacial separation with its associated differences in habitat. Thus, selection of the control station will be based upon balancing the following two criteria: (1) far enough away from the plant site to be beyond the plant influence, and (2) close enough to the treatment station that the biological communities will respond to natural environmental changes consistently in the same manner

  18. Training Program for Cardiology Residents to Perform Focused Cardiac Ultrasound Examination with Portable Device.

    Science.gov (United States)

    Siqueira, Vicente N; Mancuso, Frederico J N; Campos, Orlando; De Paola, Angelo A; Carvalho, Antonio C; Moises, Valdir A

    2015-10-01

    Training requirements for general cardiologists without echocardiographic expertise to perform focused cardiac ultrasound (FCU) with portable devices have not yet been defined. The objective of this study was to evaluate a training program to instruct cardiology residents to perform FCU with a hand-carried device (HCD) in different clinical settings. Twelve cardiology residents were subjected to a 50-question test, 4 lectures on basic echocardiography and imaging interpretation, the supervised interpretation of 50 echocardiograms and performance of 30 exams using HCD. After this period, they repeated the written test and were administered a practical test comprising 30 exams each (360 patients) in different clinical settings. They reported on 15 parameters and a final diagnosis; their findings were compared to the HCD exam of a specialist in echocardiography. The proportion of correct answers on the theoretical test was higher after training (86%) than before (51%; P = 0.001). The agreement was substantial among the 15 parameters analyzed (kappa ranging from 0.615 to 0.891; P < 0.001). The percentage of correct interpretation was lower for abnormal (75%) than normal (95%) items, for valve abnormalities (85%) compared to other items (92%) and for graded scale (87%) than for dichotomous (95%) items (P < 0.0001, for all). For the final diagnoses, the kappa value was higher than 0.941 (P < 0.001; 95% CI [0.914, 0.955]). The training proposed enabled residents to perform FCU with HCD, and their findings were in good agreement with those of a cardiologist specialized in echocardiography. © 2015, Wiley Periodicals, Inc.

  19. Residency program trainee-satisfaction correlate with results of the European board examination in neurosurgery.

    Science.gov (United States)

    Stienen, Martin N; Netuka, David; Demetriades, Andreas K; Ringel, Florian; Gautschi, Oliver P; Gempt, Jens; Kuhlen, Dominique; Schaller, Karl

    2016-10-01

    Substantial country differences in neurosurgical training throughout Europe have recently been described, ranging from subjective rating of training quality to objective working hours per week. The aim of this study was to analyse whether these differences translate into the results of the written and oral part of the European Board Examination in Neurological Surgery (EBE-NS). Country-specific composite scores for satisfaction with quality of theoretical and practical training, as well as working hours per week, were obtained from an electronic survey distributed among European neurosurgical residents between June 2014 and March 2015. These were related to anonymous country-specific results of the EBE-NS between 2009 and 2016, using uni- and multivariate linear regression analysis. A total of n = 1025 written and n = 63 oral examination results were included. There was a significant linear relationship between the country-specific EBE-NS result in the written part and the country-specific composite score for satisfaction with quality of theoretical training [adjusted regression coefficient (RC) -3.80, 95 % confidence interval (CI) -5.43-7 -2.17, p working time. For the oral part, there was a linear relationship between the country-specific EBE-NS result and the country-specific composite score for satisfaction with quality of practical training (RC 9.47, 95 % CI 1.47-17.47, p = 0.021), however neither with satisfaction with quality of theoretical training nor with working time. With every one-step improvement on the country-specific satisfaction score for theoretical training, the score in the EBE-NS Part 1 increased by 3.8 %. With every one-step improvement on the country-specific satisfaction score for practical training, the score in the EBE-NS Part 2 increased by 9.47 %. Improving training conditions is likely to have a direct positive influence on the knowledge level of trainees, as measured by the EBE-NS. The effect of the actual working

  20. Motivations and reasons for women attending a Breast Self-Examination training program: A qualitative study

    Directory of Open Access Journals (Sweden)

    Huang Chiun-Sheng

    2010-07-01

    Full Text Available Abstract Background Breast cancer is a major threat to Taiwanese women's health. Despite the controversy surrounding the effectiveness of breast self-examination (BSE in reducing mortality, BSE is still advocated by some health departments. The aim of the study is to provide information about how women decide to practice BSE and their experiences through the training process. Sixty-six women aged 27-50 were recruited. Methods A descriptive study was conducted using small group and individual in-depth interviews to collect data, and using thematic analysis and constant comparison techniques for data analysis. Results It was found that a sense of self-security became an important motivator for entering BSE training. The satisfaction in obtaining a sense of self-security emerged as the central theme. Furthermore, a ladder motivation model was developed to explain the participants' motivations for entering BSE training. The patterns of motivation include opportunity taking, clarifying confusion, maintaining health, and illness monitoring, which were connected with the risk perception for breast cancer. Conclusions We recognize that the way women decide to attend BSE training is influenced by personal and social factors. Understanding the different risk assessments women rely on in making their health decisions is essential. This study will assist researchers and health professionals to gain a better understanding of alternative ways to deal with breast health, and not to be limited by the recommendations of the health authorities.