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Sample records for brigham young university laboratory reactor

  1. God and Mammon: At Brigham Young University, at Wheaton College

    Science.gov (United States)

    Webb, LaVarr G.; Marema, Lenore

    1977-01-01

    Convinced that what the state touches it secularizes, a growing number of religious institutions are challenging the federal government and risking a reduction in federal funding. The cases of Wheaton College and Brigham Young University are described. (Editor/LBH)

  2. An Historical Study of Adult Education Programs of the Brigham Young University from 1921-1966.

    Science.gov (United States)

    Smith, Keith L.

    The history of the development of adult education and extension at Brigham Young University began in 1921 with President Harris's proposal for an extension division and for a Department of Social Leadership, Education, and Religion. The Extension Division's aim was to carry to Mormons the philosophy of the University as well as to offer formal and…

  3. Bringing Online Learning to Campus: The Hybridization of Teaching and Learning at Brigham Young University

    Directory of Open Access Journals (Sweden)

    Gregory L. Waddoups

    2002-01-01

    Full Text Available The primary purpose of Brigham Young University (BYU is to provide students with a combination of sacred and secular education often described as the "BYU experience". Achieving this purpose is challenged by the rapid growth in Church membership and an enrollment cap of 30,000 students. To address these challenges, BYU sponsors the use of technology to bridge the gap between the increased Church membership and the number of students allowed under the enrollment caps. This institutional case study shows how these challenges have influenced the hybridization of teaching and learning for on campus (resident and off campus (distance students. It also describes how BYU has brought distance education to campus, and is beginning to bring campus-based educational practices to distance education.

  4. Strengthening the Physics Program at Brigham Young University - What Have We Learned?

    Science.gov (United States)

    Sommerfeldt, Scott

    2015-03-01

    During the decade of the 1990s, the Department of Physics and Astronomy at Brigham Young University (BYU) experienced remarkable growth, growing from approximately 200 majors in the first half of the decade to over 300 majors by the end of the decade. Since that time, the number of majors has held fairly steady, fluctuating between 300-350 majors. One can naturally ask, what led to this significant growth? This is a difficult question to answer, as a number of variables are potentially involved, all of which may have had some impact on the outcome. This paper will explore a number of items that have been implemented in the program over this time that may have contributed to establishing a strong physics program that provides an excellent education for our undergraduate majors. Many of these possible contributors can be viewed as an outgrowth of perhaps one major characteristic of the department - a strong and unified commitment to providing excellent undergraduate training in physics. This commitment to undergraduate education has informed many of the decisions that have been made over the past several decades. Several examples that will be discussed include the implementation of the requirement that each student complete a mentored learning experience before graduation, the introduction of several different degrees to better accommodate the range of student interests, and moving the experimental and computational lab courses to earlier in the student's program to allow later courses and research to build upon these skills. As a result of the greatly enhanced process of program assessment that has been put in place at BYU, these various elements are reviewed regularly, which provides feedback and allows us to make modifications as warranted to try and further strengthen the program.

  5. Innovation and Global elearning: A Case Study at Brigham Young University--Idaho

    Science.gov (United States)

    Young, Alan L.

    2016-01-01

    This chapter provides a case study of innovation using eLearning in higher education. The case study shows how one university made system-wide organizational and procedural changes to create low-cost, open-access distance learning opportunities on a global level in response to student needs and opportunities.

  6. "Worlds Without End": The Cosmological Theodicy of Brigham Young

    OpenAIRE

    Kirkham, James Chase

    2012-01-01

    A striking characteristic of Brigham Young's theology was his inclusion of a cosmology in his teachings. In his speeches as President of the Church of Jesus Christ of Latter-day Saints, Young juxtaposed cosmological pronouncements with practical advice. Young regularly opined on such topics as the eternal nature of matter and light and the interaction of gods and humans with these substances. Dovetailed to his cosmic musings was down-to-earth advice on raising children, avoiding the evils of ...

  7. Education among the Mormons: Brigham Young and the Schools of Utah.

    Science.gov (United States)

    Buchanan, Frederick S.

    1982-01-01

    Examined are 20th century claims made about the Mormon commitment to education, the historic development of public schooling in Utah and its relationship to the thinking of Brigham Young, and the implications of the Mormon past on the claims made about its educational perspectives. (RM)

  8. 大学开放教育资源项目能否实现资金的自给自足*--来自美国杨百翰大学自主学习项目的案例报告%The Open Education Resources Projects Can Achieve Financial Self-Sufficiency--A Case Report from the Brigham Young University Independent Study Project

    Institute of Scientific and Technical Information of China (English)

    李莹; 丁唯佳; 赵莹

    2014-01-01

    自2001年美国麻省理工学院(MIT)对国际社会宣布推行开放课件(OCW:Open Courseware)以来,越来越多的大学创建了开放教育资源(OER)项目,很多OER项目创立之初是受外来资金的支持,当项目周期临近或者结束的时候,大学OER是否具有长期的可持续性是很多项目也是开放教育资源运动本身发展面临的重要挑战。聚焦OER项目可持续性,主要是关注大学开放教育资源项目能否实现资金的自给自足和成本的自我补偿。美国杨百翰大学实证研究回答了三个问题:自主学习项目的课程转化为开放教育资源的成本如何?开放教育资源对付费学习项目产生怎样的影响?如果这种影响是积极的,是否足够支持在自主学习项目中维持一个开放教育资源项目?研究结果有力地说明,杨百翰大学自主学习项目转向开放共享模式后在财政上是可以实现自给的。杨百翰大学自主学习项目的OER试点课程提供了一个积极的结论,那就是开放教育资源提供机构可以实现自我的可持续发展,同时满足了向全社会免费开放课程、提供公共产品的目标。%Since the Massachusetts Institute of Technology (MIT) announced the launch of OpenCourseWare (OCW) in the international communities in 2001, more and more universities have stepped into the process of OER construction, financed by external supports in the early days. The sustainability has become serious and significant challenges when the OER program circle wound up. Focusing on the OER program sustainability is mainly concerned with whether the OER can realize self-compensation. The empirical results of Brigham Young University answer three questions, consisting of the conversion costs from independent study program to the OER, the impacts of the OER on paying learning, and if the impacts are positive whether it can maintain the OER within independent study. The

  9. Research reactor usage at the Idaho National Engineering Laboratory in support of university research and education

    International Nuclear Information System (INIS)

    The Idaho National Engineering Laboratory is a US Department of Energy laboratory which has a substantial history of research and development in nuclear reactor technologies. There are a number of available nuclear reactor facilities which have been incorporated into the research and training needs of university nuclear engineering programs. This paper addresses the utilization of the Advanced Reactivity Measurement Facility (ARMF) and the Coupled Fast Reactivity Measurement Facility (CFRMF) for thesis and dissertation research in the PhD program in Nuclear Science and Engineering by the University of Idaho and Idaho State University. Other reactors at the INEL are also being used by various members of the academic community for thesis and dissertation research, as well as for research to advance the state of knowledge in innovative nuclear technologies, with the EBR-II facility playing an essential role in liquid metal breeder reactor research. 3 refs

  10. Broad scope educational role of a midsize university reactor NAA laboratory

    International Nuclear Information System (INIS)

    Broad scope educational activities at the Neutron Activation Analysis Laboratory (NAAL) associated with the 100 kW University of Florida Training Reactor (UFTR) have been implemented to serve a deserve and multidisciplinary academic clientele to meet a wide spectrum of educational needs for students at all academic levels. Educational usage of the complementary laboratory facilities is described and the importance of such academic experimental experience is emphasized for developing and maintaining a cadre of professionals in the analytical applications of nuclear energy. The synergistic operation of the NAAL and the reactor at the University of Florida to serve as a model worthy of emulation for other similar facilities is emphasized. (author)

  11. Independent Confirmatory Survey Report for the University of Arizona Nuclear Reactor Laboratory, Tucson, Arizona DCN:2051-SR-01-0

    International Nuclear Information System (INIS)

    The University of Arizona (University) research reactor is a TRIGA swimming pool type reactor designed by General Atomics and constructed at the University in 1958. The reactor first went into operation in December of 1958 under U.S. Nuclear Regulatory Commission (NRC) license R-52 until final shut down on May 18, 2010. Initial site characterization activities were conducted in February 2009 during ongoing reactor operations to assess the radiological status of the Nuclear Reactor Laboratory (NRL) excluding the reactor tank, associated components, and operating systems. Additional post-shutdown characterization activities were performed to complete characterization activities as well as verify assumptions made in the Decommissioning Plan (DP) that were based on a separate activation analysis (ESI 2009 and WMG 2009). Final status survey (FSS) activities began shortly after the issuance of the FSS plan in May 2011. The contractor completed measurement and sampling activities during the week of August 29, 2011.

  12. University of Wisconsin Nuclear Reactor Laboratory annual report, fiscal year 1983-1984

    International Nuclear Information System (INIS)

    Operational activities for the reactor are described concerning nuclear engineering classes from the University of Wisconsin; reactor sharing program; utility personnel training; sample irradiations and neutron activation analysis services; and changes in personnel, facility, and procedures. Results of surveillance tests are presented for operating statistics and fuel exposure; emergency shutdowns and inadvertent scrams; maintenance; radioactive waste disposal; radiation exposures; environmental surveys; and publications and presentations on work based on reactor use

  13. Reducing Check-in Errors at Brigham Young University through Statistical Process Control

    Science.gov (United States)

    Spackman, N. Andrew

    2005-01-01

    The relationship between the library and its patrons is damaged and the library's reputation suffers when returned items are not checked in. An informal survey reveals librarians' concern for this problem and their efforts to combat it, although few libraries collect objective measurements of errors or the effects of improvement efforts. Brigham…

  14. University Reactor Conversion Lessons Learned Workshop for Purdue University Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Eric C. Woolstenhulme; Dana M. Hewit

    2008-09-01

    The Department of Energy’s Idaho National Laboratory, under its programmatic responsibility for managing the University Research Reactor Conversions, has completed the conversion of the reactor at Purdue University Reactor. With this work completed and in anticipation of other impending conversion projects, the INL convened and engaged the project participants in a structured discussion to capture the lessons learned. The lessons learned process has allowed us to capture gaps, opportunities, and good practices, drawing from the project team’s experiences. These lessons will be used to raise the standard of excellence, effectiveness, and efficiency in all future conversion projects.

  15. University of Wisconsin Nuclear Reactor Laboratory annual report, 1981-1982

    International Nuclear Information System (INIS)

    Information is presented concerning operations at the UWNR reactor; operating statistics and fuel exposure; emergency shutdowns and inadvertent scrams; maintenance operations; radioactive waste disposal; summary of radiation exposures; results of environmental studies; and publications and presentations on work based on reactor use

  16. Brigham City Hydro Generation Project

    Energy Technology Data Exchange (ETDEWEB)

    Ammons, Tom B. [Energy Conservation Specialist, Port Ewen, NY (United States)

    2015-10-31

    Brigham City owns and operates its own municipal power system which currently includes several hydroelectric facilities. This project was to update the efficiency and capacity of current hydro production due to increased water flow demands that could pass through existing generation facilities. During 2006-2012, this project completed efficiency evaluation as it related to its main objective by completing a feasibility study, undergoing necessary City Council approvals and required federal environmental reviews. As a result of Phase 1 of the project, a feasibility study was conducted to determine feasibility of hydro and solar portions of the original proposal. The results indicated that the existing Hydro plant which was constructed in the 1960’s was running at approximately 77% efficiency or less. Brigham City proposes that the efficiency calculations be refined to determine the economic feasibility of improving or replacing the existing equipment with new high efficiency equipment design specifically for the site. Brigham City completed the Feasibility Assessment of this project, and determined that the Upper Hydro that supplies the main culinary water to the city was feasible to continue with. Brigham City Council provided their approval of feasibility assessment’s results. The Upper Hydro Project include removal of the existing powerhouse equipment and controls and demolition of a section of concrete encased penstock, replacement of penstock just upstream of the turbine inlet, turbine bypass, turbine shut-off and bypass valves, turbine and generator package, control equipment, assembly, start-up, commissioning, Supervisory Control And Data Acquisition (SCADA), and the replacement of a section of conductors to the step-up transformer. Brigham City increased the existing 575 KW turbine and generator with an 825 KW turbine and generator. Following the results of the feasibility assessment Brigham City pursued required environmental reviews with the DOE and

  17. The Implementation of an Integrated Management System for TRIGA Research Reactor at LENA (Laboratory of Applied Nuclear Energy) - University of Pavia (Italy) -

    International Nuclear Information System (INIS)

    The Laboratory of Applied Nuclear Energy ('LENA') is an Interdepartmental Research Centre of the University of Pavia which operate, among other facilities, a 250 kW TRIGA Mark II Research Nuclear Reactor. The reactor is at the disposal of researchers from Pavia University and of other users, both public and private, for research activities, training and education and other services. The Centre itself carries out research and training activities and provides services for private enterprises, encouraging the transfer of the results of nuclear technology research to the production system, including the education and training of specialists in nuclear technology. The prerequisite for the management of the reactor is the satisfaction of all stakeholders requirements, among which safety constraints, efficiency and effectiveness in the delivery of the services. In order to continuously improve the safety and quality of reactor management and the accomplishment of the stakeholder requirements, LENA decided to implement an Integrated Management System in accordance with International Standard ISO 9001:2008. This choice allowed to satisfy both national and international compulsory requirements (i.e. safe reactor operation and maintenance) and typical ISO 9001 requirements (as e.g. continuous improvement, users/stakeholders care and satisfaction). In addition, through this systematic and graded approach, that led to the standardization of all processes involved in reactor operation and maintenance, all the aspects of the reactor management mentioned in the IAEA publication The Management System for Facilities and Activities (IAEA Safety Standards Series No. GS-R-3) were also satisfied. This publication, in facts, provides a guidance for establishing, implementing, assessing and continually improving a management system for facilities and activities that integrates safety, health, environmental, security, quality and economic elements. (author)

  18. The Implementation of an Integrated Management System for TRIGA Research Reactor at LENA (Laboratory of Applied Nuclear Energy) - University of Pavia (Italy) -

    Energy Technology Data Exchange (ETDEWEB)

    Cagnazzo, M.; Tigliole, A. Borio Di; Magrotti, G.; Manera, S.; Marchetti, F.; Prata, M.; Salvini, A. [Laboratory of Applied Nuclear Energy (LENA), University of Pavia (Italy); Giordano, M. [Innovation and Management Systems Division, University of Pavia (Italy); Boogaard, J.P.; Bradley, E.; Vincze, P. [International Atomic Energy Agency (IAEA), Vienna (Austria)

    2011-07-01

    The Laboratory of Applied Nuclear Energy ('LENA') is an Interdepartmental Research Centre of the University of Pavia which operate, among other facilities, a 250 kW TRIGA Mark II Research Nuclear Reactor. The reactor is at the disposal of researchers from Pavia University and of other users, both public and private, for research activities, training and education and other services. The Centre itself carries out research and training activities and provides services for private enterprises, encouraging the transfer of the results of nuclear technology research to the production system, including the education and training of specialists in nuclear technology. The prerequisite for the management of the reactor is the satisfaction of all stakeholders requirements, among which safety constraints, efficiency and effectiveness in the delivery of the services. In order to continuously improve the safety and quality of reactor management and the accomplishment of the stakeholder requirements, LENA decided to implement an Integrated Management System in accordance with International Standard ISO 9001:2008. This choice allowed to satisfy both national and international compulsory requirements (i.e. safe reactor operation and maintenance) and typical ISO 9001 requirements (as e.g. continuous improvement, users/stakeholders care and satisfaction). In addition, through this systematic and graded approach, that led to the standardization of all processes involved in reactor operation and maintenance, all the aspects of the reactor management mentioned in the IAEA publication The Management System for Facilities and Activities (IAEA Safety Standards Series No. GS-R-3) were also satisfied. This publication, in facts, provides a guidance for establishing, implementing, assessing and continually improving a management system for facilities and activities that integrates safety, health, environmental, security, quality and economic elements. (author)

  19. 75 FR 58433 - Notice of Inventory Completion: Brigham Young University, Museum of Peoples and Cultures, Provo, UT

    Science.gov (United States)

    2010-09-24

    ... moccasin, 1 pipe, 1 onyx pipe bowl, 14 turkey feathers, 1 bundle of human hair, 1 mug, 1 leather pouch, 1... Anasazi culture. At an unknown date, human remains representing a minimum of three individuals were... the burials date to either the late Basketmaker or early Pueblo era of the Anasazi culture. Based...

  20. Status of Japanese university reactors

    Energy Technology Data Exchange (ETDEWEB)

    Fujita, Yoshiaki [Research Reactor Institute, Kyoto Univ., Kumatori, Osaka (Japan)

    1999-08-01

    Status of Japanese university reactors, their role and value in research and education, and the spent fuel problem are presented. Some of the reactors are now faced by severe difficulties in continuing their operation services. The point of measures to solve the difficulties is suggested. (author)

  1. Status of Japanese university reactors

    International Nuclear Information System (INIS)

    Status of Japanese university reactors, their role and value in research and education, and the spent fuel problem are presented. Some of the reactors are now faced by severe difficulties in continuing their operation services. The point of measures to solve the difficulties is suggested. (author)

  2. The Oarai Branch of IMR, Tohoku University as open facility for university researchers utilizing fission reactors

    International Nuclear Information System (INIS)

    For advanced future research activities utilizing fission reactors and hot laboratories, effective interlinks among fission reactors and hot laboratories are indispensable. Oarai Branch of Institute for Materials Research in Tohoku University has been playing an important role for supplying related tools for university researchers, in fission reactor irradiation and post irradiation examinations, under tight collaboration with JAERI and JNC. Now the Oarai Branch is planning to expand its collaborative functions, utilizing multi-reactors over the world and making effective interlinks among related hot laboratories in several institutions. The talk will give rough view of the present plan of the Oarai Branch, IMR, Tohoku University for tight and effective collaboration among institutions. (author)

  3. Universe Awareness For Young Children

    Science.gov (United States)

    Scorza, C.; Miley, G.; Ödman, C.; Madsen, C.

    2006-08-01

    Universe Awareness (UNAWE) is an international programme that will expose economically disadvantaged young children aged between 4 and 10 years to the inspirational aspects of modern astronomy. The programme is motivated by the premise that access to simple knowledge about the Universe is a basic birth right of everybody. These formative ages are crucial in the development of a human value system. This is also the age range in which children can learn to develop a 'feeling' for the vastness of the Universe. Exposing young children to such material is likely to broaden their minds and stimulate their world-view. The goals of Universe Awareness are in accordance with two of the United Nations Millennium goals, endorsed by all 191 UN member states, namely (i) the achievement of universal primary education and (ii) the promotion of gender equality in schools. We propose to commence Universe Awareness with a pilot project that will target disadvantaged regions in about 4 European countries (possibly Spain, France, Germany and The Netherlands) and several non-EU countries (possibly Chile, Colombia, India, Tunisia, South Africa and Venezuela). There will be two distinct elements in the development of the UNAWE program: (i) Creation and production of suitable UNAWE material and delivery techniques, (ii) Training of educators who will coordinate UNAWE in each of the target countries. In addition to the programme, an international network of astronomy outreach will be organised. We present the first results of a pilot project developed in Venezuela, where 670 children from different social environments, their teachers and members of an indigenous tribe called Ye´kuana from the Amazon region took part in a wonderful astronomical and cultural exchange that is now being promoted by the Venezuelan ministry of Education at the national level.

  4. Kyoto University Reactor diagnostic system

    International Nuclear Information System (INIS)

    For the safety of a nuclear reactor, it is very important that the operators and manager make exact judgement about the various conditions of the nuclear reactor occurring at times. The research is advanced for the purpose of adopting a computer system for the research reactor of Kyoto University (KUR), offering effective information to operators and maintenance workers, making the advice for exactly judging the conditions of the reactor by sufficiently grasping them, consequently, developing the system for increasing the safety of the reactor. For the development of this system, also technical officials took part positively and cooperated in the research and development based on the experience of the maintenance and operation of the research reactor carried out daily. The system comprises the data acquisition part, data base, abnormality diagnostic part, man-machine interface part, and individual dealing part. The abnormality of the reactor is identified by the judgement of operators by referring to the data memorized in the data base, then, the reactor is operated. The constitution of the computer system used is shown. The CPU is a minicomputer ECLIPSE S-140, and the main memory is 512 kB. The auxiliary memories are a fixed disk equipment of 73 MB, two floppy disk equipments and a magnetic tape equipment. Respective subsystems are explained. (Kako, I.)

  5. Arkansas Tech University reactor project

    International Nuclear Information System (INIS)

    The purpose of this paper is to describe the nuclear reactor project at Arkansas Tech University (ATU). The reactor will be a part of the Center for Energy Studies (CES) located on the ATU campus in Russellville, Arkansas. It will be used for education, training, and research. The Arkansas Tech University TRIGA Reactor (ATUTR) is a TRIGA Mark I that will be operated in two basic modes: steady state and pulsing. The maximum power level for steady-state operation is 250 kW(thermal), and the maximum step reactivity insertion will be 2.0$. The inherent safety of this reactor comes from the large negative temperature coefficient of the uranium-zirconium-hydride fuel-moderator elements. Principal design parameters for the reactor are summarized. The application for reactor construction and operating license was submitted to the US Nuclear Regulatory Commission in November 1989. The review process is continuing. ATU plans to continue to work with local industry and the public to provide a wide variety of services related to nuclear science and engineering

  6. Universe Awareness Among Young Poles

    Science.gov (United States)

    Ratajczak, Milena

    Astronomy, the most accessible of all the sciences, grabs and holds the attention not only of the elders, but also that of the youngsters from all over the world. Sharing the same sky provides the unique opportunity to use it as a tool to inspire children, to encourage them to develop an interest in science and technology, but also to increase awareness of global citizenship and tolerance. We shall present a wide spectrum of educational activities dedicated to young children, especially those from less privileged backgrounds, carried out under the Universe Awareness (UNAWE) project in Poland. We will also introduce the way we follow to support teachers and educators in discovering our wonderful cosmos.

  7. Laboratory instrumentation modernization at the WPI Nuclear Reactor Facility

    International Nuclear Information System (INIS)

    With partial funding from the Department of Energy (DOE) University Reactor Instrumentation Program several laboratory instruments utilized by students and researchers at the WPI Nuclear Reactor Facility have been upgraded or replaced. Designed and built by General Electric in 1959, the open pool nuclear training reactor at WPI was one of the first such facilities in the nation located on a university campus. Devoted to undergraduate use, the reactor and its related facilities have been since used to train two generations of nuclear engineers and scientists for the nuclear industry. The low power output of the reactor and an ergonomic facility design make it an ideal tool for undergraduate nuclear engineering education and other training. The reactor, its control system, and the associate laboratory equipment are all located in the same room. Over the years, several important milestones have taken place at the WPI reactor. In 1969, the reactor power level was upgraded from 1 kW to 10 kW. The reactor's Nuclear Regulatory Commission operating license was renewed for 20 years in 1983. In 1988, under DOE Grant No. DE-FG07-86ER75271, the reactor was converted to low-enriched uranium fuel. In 1992, again with partial funding from DOE (Grant No. DE-FG02-90ER12982), the original control console was replaced

  8. Oregon State University TRIGA Reactor annual report

    Energy Technology Data Exchange (ETDEWEB)

    Anderson, T.V.; Johnson, A.G.; Bennett, S.L.; Ringle, J.C.

    1979-08-31

    The use of the Oregon State University TRIGA Reactor during the year ending June 30, 1979, is summarized. Environmental and radiation protection data related to reactor operation and effluents are included.

  9. Oregon State University TRIGA Reactor annual report

    International Nuclear Information System (INIS)

    The use of the Oregon State University TRIGA Reactor during the year ending June 30, 1979, is summarized. Environmental and radiation protection data related to reactor operation and effluents are included

  10. Reactor physics experiments at Kyoto University Critical Assembly (KUCA)

    International Nuclear Information System (INIS)

    Kyoto University Critical Assembly (KUCA) is a multi-core type critical assembly established in 1974. It has three independent cores, namely, two solid-moderated cores (A, B cores) and one light water-moderated core (C core). A pulsed neutron generator by D-T reactions and new FFAG proton accelerator are installed, which can be used in combination with the A-core. In the KUCA, basic studies on reactor physics are being performed. Recent research topics includes 1) nuclear characteristics of thorium fueled reactor, 2) critical experiments loaded with erbium at various spectrum indices, 3) subcriticality measurements, 4) development of innovative neutron detector and 5) simulation experiments of accelerator driven system (ADS). For education, the reactor laboratory course on reactor physics is offered for 12 Japanese universities since 1975. More than 150 graduate or undergraduate students majoring in nuclear engineering are joining this course every year and same reactor laboratory course has been offered for Korean and Swedish students.

  11. Utilisation of British University Research Reactors.

    Science.gov (United States)

    Duncton, P. J.; And Others

    British experience relating to the employment of university research reactors and subcritical assemblies in the education of nuclear scientists and technologists, in the training of reactor operators and for fundamental pure and applied research in this field is reviewed. The facilities available in a number of British universities and the uses…

  12. EURACOS II facility in the modified thermal column of the TRIGA Mark II reactor at the University of Pavia LENA Laboratory

    International Nuclear Information System (INIS)

    The EURACOS II (Enriched Uranium Converter Source) project foresees the installation of an U--Al alloy converter plate at the end of the thermal column in the Pavia University LENA reactor. The incident thermal flux on the 5 Kg of 235U generates a fast neutron source whose power is 0.4 kW. The fast flux near the center exceeds 109 neutrons/cm2-sec. The fission plate is cooled by a forced air flow of 500 m3/h; the use of air instead of water reduces to a minimum the initial spectrum deformation of source neutrons. An irradiation chamber of 3.75 x 1.5 x 1.8 m3 is placed in front of the source and contains the mock-up under investigation. The facility is principally intended for benchmark-and mock-up-experiments in the reactor shielding field, but irradiations to different types and materials not directly related to shielding can be extended. The modification of the TRIGA thermal column, the characteristics of the EURACOS II facility, and the experiments now in preparation are described. The source intensity allows the study of neutron attenuation factor of 105 for fast, and 108 for thermal neutrons. The neutron spectra are investigated with the sandwich technique in the epithermal range, and with threshold detectors, organic and telescopic spectrometers in the fast energy range. (U.S.)

  13. Sandia National Laboratories Medical Isotope Reactor concept.

    Energy Technology Data Exchange (ETDEWEB)

    Coats, Richard Lee; Dahl, James J.; Parma, Edward J., Jr.

    2010-04-01

    This report describes the Sandia National Laboratories Medical Isotope Reactor and hot cell facility concepts. The reactor proposed is designed to be capable of producing 100% of the U.S. demand for the medical isotope {sup 99}Mo. The concept is novel in that the fuel for the reactor and the targets for the {sup 99}Mo production are the same. There is no driver core required. The fuel pins that are in the reactor core are processed on a 7 to 21 day irradiation cycle. The fuel is low enriched uranium oxide enriched to less than 20% {sup 235}U. The fuel pins are approximately 1 cm in diameter and 30 to 40 cm in height, clad with Zircaloy (zirconium alloy). Approximately 90 to 150 fuel pins are arranged in the core in a water pool {approx}30 ft deep. The reactor power level is 1 to 2 MW. The reactor concept is a simple design that is passively safe and maintains negative reactivity coefficients. The total radionuclide inventory in the reactor core is minimized since the fuel/target pins are removed and processed after 7 to 21 days. The fuel fabrication, reactor design and operation, and {sup 99}Mo production processing use well-developed technologies that minimize the technological and licensing risks. There are no impediments that prevent this type of reactor, along with its collocated hot cell facility, from being designed, fabricated, and licensed today.

  14. University Reactor Conversion Lessons Learned Workshop for the University of Florida

    Energy Technology Data Exchange (ETDEWEB)

    Eric C. Woolstenhulme; Dana M. Meyer

    2007-04-01

    The Department of Energy’s (DOE) Idaho National Laboratory (INL), under its programmatic responsibility for managing the University Research Reactor Conversions, has completed the conversion of the reactor at the University of Florida. This project was successfully completed through an integrated and collaborative effort involving the INL, Argonne National Laboratory (ANL), DOE (Headquarters and Field Office), the Nuclear Regulatory Commission, the Universities, and contractors involved in analyses, fuel design and fabrication, and SNF shipping and disposition. With the work completed with these two universities, and in anticipation of other impending conversion projects, INL convened and engaged the project participants in a structured discussion to capture lessons learned. The objectives of this meeting were to capture the observations, insights, issues, concerns, and ideas of those involved in the reactor conversions so that future efforts can be conducted with greater effectiveness, efficiency, and with fewer challenges.

  15. Radiation monitoring programme in a university hot laboratory

    International Nuclear Information System (INIS)

    The Department of Radiochemistry in the University of Helsinki is the only institute teaching radiochemistry at the university level in Finland. The research programme of the Deparment must therefore include the uses of radiation and radionuclides in many branches of science. The students must receive adequate instruction in radiation protection for safe work in laboratories. This also has the educational benefit that the radiochemists will subsequently be able to observe the necessary safety precautions when employing ionizing radiation professionally. The Department of Radiochemistry consists of the following laboratories: a radiotracer laboratory, a neutron/electron and a gamma irradiation laboratory, an environmental low activity level laboratory, a whole-body counting laboratory, a reactor chemistry laboratory and a waste-treatment facility. The radiation protection organization of the Department is presented. Various methods of monitoring, including advantages and disadvantages are discussed. Emphasis is placed on the reactor chemistry laboratory where transuranic elements are utilized. These elements are highly radiotoxic and their monitoring in most cases requires destructive analysis. Different methods of determining external and internal doses are evaluated with regard to sensitivity and accuracy. Detection limits for radionuclides utilized in the laboratory are presented for different measurement systems, including non-destructive monitoring, spectrometry after chemical analysis, liquid scintillation counting and low-energy gamma spectrometry using a CsI-NaI scintillation detector. The guidelines laid down in the IAEA Safety Series Manuals are discussed in the light of practical experience. (author)

  16. The first university research reactor in India

    International Nuclear Information System (INIS)

    As the first university research reactor in India, the low power, pool type with fixed core and low enriched uranium fuel research reactor is under construction in the Andhra university campus, Andhra Pradesh, India. The reactor is expected to be commissioned during 2001-2002. The mission of the reactor is to play the research center as a regional research facility catering to the needs of academic institutions and industrial organizations of this region of the country. Further, to encourage interdisplinary and multidisplinary research activities, to supply radioisotope and labelled compounds to the user institutions and to create awareness towards the peaceful uses of atomic energy. This report describes its objectives, status and future plans in brief. (H. Itami)

  17. TRIGA reactor relocation at the University of Texas at Austin

    International Nuclear Information System (INIS)

    The University of Texas at Austin (UT) is in the process of relocating its TRIGA reactor facilities. This undertaking includes the construction of a new reactor building with laboratories and offices and the decommissioning of the existing facility. The main campus of The University of Texas at Austin is becoming congested, and several major research projects (mostly engineering) are moving to the Balcones Research Center ∼ 8 miles from the main campus. The process of constructing a new nuclear facility in today's regulatory environment can best be described as challenging. Fortunately, research reactor licensing is not as complicated as that for commercial power facilities, although many procedures are similar. Unfortunately, the university has its own challenging procedures for building construction. Considerable time has been expended coordinating the US Nuclear Regulatory Commission (NRC) and UT licensing and construction activities. The paper summarizes the major steps and dates accomplished. The new reactor facility at the Balcones Research Center will enhance the universities ability to carry on teaching and research activities. The increased power level and the Mark II arrangement will allow us to perform new and additional projects. Considerable time and effort were devoted by the Nuclear Engineering Laboratory staff to ensure that the facility would provide educational and research flexibility over the next several years

  18. Pennsylvania State University Breazeale Nuclear Reactor. Thirtieth annual progress report, July 1, 1984-June 30, 1985

    International Nuclear Information System (INIS)

    This report is the thirtieth annual progress report of the Pennsylvania State University Breazeale Nuclear Reactor and covers such topics as: personnel; reactor facility; cobalt-60 facility; education and training; Radionuclear Application Laboratory; Low Level Radiation Monitoring Laboratory; and facility research utilization

  19. Joint reactor laboratory course for students in KUCA

    International Nuclear Information System (INIS)

    This book is based on Joint Reactor Laboratory Course for Students, which we have given over 30 years from 1975 at Kyoto University Critical Assembly (KUCA), and is one translated from Japanese into English. The major objective of this course is to help the students for understanding the essence of nuclear reactor physics through the experiments carried out in KUCA C-core. At the same time, it is expected that by the end of the course the students will be able to obtain good and fruitful results by their efforts through this course. This textbook is composed of these following chapters; Introduction to Kyoto University Critical Assembly (KUCA). Chapter 1: Approach to Criticality. Chapter 2: Control Rod Calibration. Chapter 3: Measurement of Reaction Rate Distribution. Chapter 4: Neutron Correlation Experiment Feynman-α Method. Chapter 5: Measurement of Reactivity by the Pulsed Neutron Method. (author)

  20. A Case Study: Implementation of a Management System for the TRIGA Mark II Research Reactor at the Laboratory of Applied Nuclear Energy (LENA) of the University of Pavia, Italy. Annex I

    International Nuclear Information System (INIS)

    This annex provides an example for the implementation of a management system for operating organizations of research reactors, based on a case study in which the implementation of such a system has been completed. The case study relates the experience of the Applied Nuclear Energy Laboratory (hereafter referred to as LENA) of the University of Pavia, Italy. This example is used because of the recent completion of the implementation of an integrated management system, and also because of the specific characteristics of the organization (such as the limited number of staff, limited financial resources, etc.), which are often typical for organizations that operate smaller research reactors. Section I-1 gives a brief presentation of the organization, including the scope of work, the main activities performed, the organizational structure, the identification of interested parties and the applicable requirements and standards. Section I-2 describes the LENA Management System, the reasons for its implementation, the stages of its development and the processes involved. Some practical examples related to the development of the LENA Management System are discussed in Section I-3, indicating the choices made by the organization. In particular, Section I-3.12 shows the correlation between the LENA Management System processes and the processes considered in the main body of this publication.

  1. Final report. U.S. Department of Energy University Reactor Sharing Program

    International Nuclear Information System (INIS)

    Activities supported at the MIT Nuclear Reactor Laboratory under the U.S. DOE University Reactor Sharing Program are reported for Grant DE FG02-95NE38121 (September 16, 1995 through May 31, 2002). These activities fell under four subcategories: support for research at thesis and post-doctoral levels, support for college-level laboratory exercises, support for reactor tours/lectures on nuclear energy, and support for science fair participants

  2. Final report. U.S. Department of Energy University Reactor Sharing Program

    Energy Technology Data Exchange (ETDEWEB)

    Bernard, John A

    2003-01-21

    Activities supported at the MIT Nuclear Reactor Laboratory under the U.S. DOE University Reactor Sharing Program are reported for Grant DE FG02-95NE38121 (September 16, 1995 through May 31, 2002). These activities fell under four subcategories: support for research at thesis and post-doctoral levels, support for college-level laboratory exercises, support for reactor tours/lectures on nuclear energy, and support for science fair participants.

  3. Portuguese Universities Sharing Remote Laboratories

    Directory of Open Access Journals (Sweden)

    Maria Teresa Restivo

    2009-11-01

    Full Text Available This paper describes a pedagogical assignment based on a cooperative work involving teachers/students from two Portuguese universities. As it happens one is the oldest in the country – University of Coimbra (UC - and the other the largest - University of Porto (UP, about 120 km apart. The authors, believing in the relevance of Information and Communication Technologies (ITs in teaching/learning methodologies and in cooperative teaching methods worked together to plan this pedagogical experience and to run it in a one semester course. Students from UC have been introduced to the remote lab at UP and got the first contact with the remote experiments using easily available sound and image resources based on Skype and an IP camera for better image quality. This first contact has been conducted by the first author at UP with support of the second author at UC. The work will describe briefly the remote experiments used, their inclusion in the course at UC, the associated assessment criteria and, finally, student comments.

  4. University Reactor Conversion Lessons Learned Workshop for Texas A&M University Nuclear Science Center Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Eric C. Woolstenhulme; Dana M. Meyer

    2007-04-01

    The objectives of this meeting were to capture the observations, insights, issues, concerns, and ideas of those involved in the Texas A&M University Nuclear Science Center (TAMU NSC) TRIGA Reactor Conversion so that future efforts can be conducted with greater effectiveness, efficiency, and with fewer challenges. This workshop was held in conjunction with a similar workshop for the University of Florida Reactor Conversion. Some of the generic lessons from that workshop are included in this report for completeness.

  5. Reactor physics education at Seoul National University

    International Nuclear Information System (INIS)

    The reactor physics education and research programs of Seoul National University (SNU), which focus on high fidelity and efficient reactor simulation and uncertainty evaluation, are presented. In order to foster the students to have proper knowledge and experience in both deterministic and probabilistic reactor analysis methods with clear understanding of the physical behaviors of nuclear reactors, the undergraduate and graduate courses cover various mathematical and numerical methods as well as the principles of nuclear characteristics and physical behaviors. The research areas span from the development of the methods and computer programs for direct whole core calculation involving the method of characteristics transport calculation to the Monte Carlo uncertainty analysis. Those covers cross section generation, resonance treatment, depletion method, advanced nodal methods, space-time kinetics method, Monte Carlo whole core calculation with thermal feedback and et cetera. The reactor physics curriculum, the contents of the relevant courses, and the cutting edge research topics and the achievements of SNU reactor physics education are detailed. (author)

  6. University of Florida training reactor. Annual progress report, September 1, 1984-August 31, 1985

    International Nuclear Information System (INIS)

    This annual progress report of the University of Florida Training Reactor discusses: reactor operation; personnel; modifications made to the reactors; reactor maintenance; and testing of reactor systems

  7. Experiences with fast breeder reactor education in laboratory and short course settings

    International Nuclear Information System (INIS)

    The breeder reactor industry throughout the world has grown impressively over the last two decades. Despite the uncertainties in some national programs, breeder reactor technology is well established on a global scale. Given the magnitude of this technological undertaking, there has been surprisingly little emphasis on general breeder reactor education - either at the university or laboratory level. Many universities assume the topic too specialized for including appropriate courses in their curriculum - thus leaving students entering the breeder reactor industry to learn almost exclusively from on-the-job experience. The evaluation of four course presentations utilizing visual aids is presented

  8. University and national laboratory roles in nuclear engineering

    International Nuclear Information System (INIS)

    Nuclear engineering education is being significantly challenged in the US. The decline in enrollment generally and the reduction of the number of nuclear engineering departments has been well documented. These declines parallel a lack of new construction for nuclear power plants and a decline in research and development to support new plant design. Precisely at a time when innovation is needed to deal with the many issues facing nuclear power, the number of qualified people to do so is being reduced. It is important that the university and national laboratory communities cooperate to address these issues. To be drawn into the technology, the best students must see a future, a need, and must identify challenges to meet. The university community can provide that vision with help from the national laboratories. It has been a major goal within the reactor development program at Argonne National Laboratory to establish the kind of program that can help accomplish this. The integral fast reactor (IFR) program represents opportunities for joint research in fuel technology, fuel reprocessing, and waste handling, reactor-plant design to emphasize passive response to upsets, development and testing of advanced diagnostic and control-system technology core designs to enhance breeding while minimizing sodium void effects and reducing the magnitude of reactivity changes with burnup, development of approaches to the probabilistic risk assessment that fully integrate passive responses, and many others. To involve students and faculty, they have established the IFR fellows program

  9. Accreditation in university environmental radioactivity laboratories

    International Nuclear Information System (INIS)

    Full text: The experimental work performed in university laboratories comes from many different fields and it is assumed to be of high quality. In general, the results are published in national or international journals or presented at conferences. Only a few laboratories have a clear understanding of the importance of implementing Quality Assurance Systems and the accreditation of their activities according to the international standards, such as ISO 17025. Today, few universities include this issue in the ir programmes. Most laboratories associate quality assurance with the fact that referees before publication have revised their works. Here the authors describe their experience in two university laboratories involved in environmental radioactivity control. Both laboratories have implanted a Quality Assurance System based on ISO 17025, the standard used for accreditation of the technical competence of laboratories. One of them (LARA-UPC) belongs to a research institute and the other (LRAUB) belongs to a university department with different logistic organisation. Both laboratories provide services to public and private institutions along side their teaching and research activities. The Quality Assurance Unit (UGQ-UB) is responsible for activities related to technical support in implementation and assessment in quality systems. In the case of these laboratories this UGQ performs internal audits. Accreditation is particularly important in environmental radioactivity analysis, where objective evidence of the quality of the data is required. Moreover, the results of radioactivity analysis are important: e.g. quality of water for human consumption (Directive 98/83/CE), environmental surveys (PVRA, Art. 35 of the Euratom Treaty for EU members), imports of agricultural products (Directive 99/1661/EC), export certificate required for agricultural products (2001/1621/EC), measurements in support of health and safety. It is important to assure the accuracy and precision of

  10. Accreditation in university environmental radioactivity laboratories

    International Nuclear Information System (INIS)

    Full text: The experimental work performed in university laboratories comes from many different fields and it is assumed to be of high quality. In general, the results are published in national or international journals or presented at conferences. Only a few laboratories have a clear understanding of the importance of implementing Quality Assurance Systems and the accreditation of their activities according to the international standards, such as ISO 17025. Today, few universities include this issue in their programmes. Most laboratories associate quality assurance with the fact that referees before publication have revised their works. Here the authors describe their experience in two university laboratories involved in environmental radioactivity control. Both laboratories have implanted a Quality Assurance System based on ISO 17025, the standard used for accreditation of the technical competence of laboratories. One of them (LARA-UPC) belongs to a research institute and the other (LRA-UB) belongs to a university department with different logistic organisation. Both laboratories provide services to public and private institutions along side their teaching and research activities. The Quality Assurance Unit (UGQ-UB) is responsible for activities related to technical support in implementation and assessment in quality systems. In the case of these laboratories this UGQ performs internal audits. Accreditation is particularly important in environmental radioactivity analysis, where objective evidence of the quality of the data is required. Moreover, the results of radioactivity analysis are important: e.g. quality of water for human consumption (Directive 98/83/CE), environmental surveys (PVRA, Art. 35 of the Euratom Treaty for EU members), imports of agricultural products (Directive 99/1661/EC), export certificate required for agricultural products (2001/1621/EC), measurements in support of health and safety. It is important to assure the accuracy and precision of

  11. Annual report of Nuclear Reactor Laboratory, Kinki University. Vol 1. (1961). Studies on the radioactive contamination due to nuclear detonations I-VI

    International Nuclear Information System (INIS)

    An unusually large amount of strong radioactive ash was produced by the thermonuclear test conducted on March 1954 at the Bikini Atoll in the South Pacific by the United States Atomic Energy Commission. Under such circumstances, to meet the urgent needs of public health, the studies on the radioactivity of Bikini ash and the radioactive contamination of environment have been started, from the health physics standpoint, with the initiative of the author under close cooperation with the public health officers of local governments in Osaka district since the middle of March 4 1954, when the author was the head of the Department of Biophysics, Osaka City University, School of Medicine. The estimation of the probable dose of radiation the might have been received during their dosage and the accurate estimation of beta-ray energies and the detection of alpha-ray activity as well as the identification of various radioactive nuclides included in the Bikini ash were considered to be urgently needed items of information in estimating the possible hazard due to the internal as well as the external irradiation from the health physics point of view

  12. Education for university students, high school teachers and the general public using the Kinki University Reactor

    International Nuclear Information System (INIS)

    Atomic Energy Research Institute of Kinki University is equipped with a nuclear reactor which is called UTR-KINKI. UTR is the abbreviation for University Teaching and Research Reactor. The reactor is the first one installed in Japanese universities. Though the reactor is owned and operated by Kinki University, its use is widely open to scientists and students from other universities and research institutions. The reactor is made the best of teaching instrument for the training of high school teachers. In addition, the reactor is utilized for general public education concerning atomic energy. (author)

  13. Students' assessment of interactive distance experimentation in nuclear reactor physics laboratory education

    Science.gov (United States)

    Malkawi, Salaheddin; Al-Araidah, Omar

    2013-10-01

    Laboratory experiments develop students' skills in dealing with laboratory instruments and physical processes with the objective of reinforcing the understanding of the investigated subject. In nuclear engineering, where research reactors play a vital role in the practical education of students, the high cost and long construction time of research reactors limit their accessibility to few educational programmes around the world. The concept of the Internet Reactor Laboratory (IRL) was introduced earlier as a new approach that utilises distance education in nuclear reactor physics laboratory education. This paper presents an initial assessment of the implementation of the IRL between the PULSTAR research reactor at North Carolina State University in the USA and the Department of Nuclear Engineering at Jordan University of Science and Technology (JUST) in Jordan. The IRL was implemented in teaching the Nuclear Reactor laboratory course for two semesters. Feedback from surveyed students verifies that the outcomes attained from using IRL in experimentation are comparable to that attainable from other on-campus laboratories performed by the students.

  14. Present status of BNCT at Kyoto University Research Reactor Institute

    International Nuclear Information System (INIS)

    At Kyoto University Research Reactor Institute, we have two facilities for BNCT such as a reactor-based and an accelerator-based neutron source. In this article, we will present the characteristics overview of both facilities. (author)

  15. Reactor D and D at Argonne National Laboratory - lessons learned

    International Nuclear Information System (INIS)

    This paper focuses on the lessons learned during the decontamination and decommissioning (D and D) of two reactors at Argonne National Laboratory-East (ANL-E). The Experimental Boiling Water Reactor (EBWR) was a 100 MW(t), 5 MSV(e) proof-of-concept facility. The Janus Reactor was a 200 kW(t) reactor located at the Biological Irradiation Facility and was used to study the effects of neutron radiation on animals

  16. Universities and national laboratory roles in nuclear engineering

    International Nuclear Information System (INIS)

    Nuclear Engineering Education is being significantly challenged in the United States. The decline in enrollment generally and the reduction of the number of nuclear engineering departments has been well documented. These declines parallel a lack of new construction for nuclear power plants and a decline in research and development to support new plant design. Precisely at a time when innovation is is needed to deal with many issues facing nuclear power, the number of qualified people to do so is being reduced. It is important that the University and National Laboratory Communities cooperate to address these issues. The Universities must increasingly identify challenges facing nuclear power that demand innovative solutions and pursue them. To be drawn into the technology the best students must see a future, a need and identify challenges that they can meet. The University community can provide that vision with help from the National Laboratories. It has been a major goal within the reactor development program at Argonne National Laboratory to establish the kind of program that can help accomplish this

  17. 77 FR 60430 - Brigham Oil & Gas, L.P.; Notice for Temporary Waiver of Filing and Reporting Requirements

    Science.gov (United States)

    2012-10-03

    ... Federal Energy Regulatory Commission Brigham Oil & Gas, L.P.; Notice for Temporary Waiver of Filing and... Rules of Practice and Procedure, 18 CFR 385.204 (2012), Brigham Oil & Gas, L.P., (Brigham Oil & Gas.... Brigham Oil & Gas requested review on an expedited basis and that a Commission order granting...

  18. University of Washington, Nuclear Physics Laboratory annual report, 1995

    International Nuclear Information System (INIS)

    The Nuclear Physics Laboratory of the University of Washington supports a broad program of experimental physics research. The current program includes in-house research using the local tandem Van de Graff and superconducting linac accelerators and non-accelerator research in double beta decay and gravitation as well as user-mode research at large accelerator and reactor facilities around the world. This book is divided into the following areas: nuclear astrophysics; neutrino physics; nucleus-nucleus reactions; fundamental symmetries and weak interactions; accelerator mass spectrometry; atomic and molecular clusters; ultra-relativistic heavy ion collisions; external users; electronics, computing, and detector infrastructure; Van de Graff, superconducting booster and ion sources; nuclear physics laboratory personnel; degrees granted for 1994--1995; and list of publications from 1994--1995

  19. University of Washington, Nuclear Physics Laboratory annual report, 1995

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-04-01

    The Nuclear Physics Laboratory of the University of Washington supports a broad program of experimental physics research. The current program includes in-house research using the local tandem Van de Graff and superconducting linac accelerators and non-accelerator research in double beta decay and gravitation as well as user-mode research at large accelerator and reactor facilities around the world. This book is divided into the following areas: nuclear astrophysics; neutrino physics; nucleus-nucleus reactions; fundamental symmetries and weak interactions; accelerator mass spectrometry; atomic and molecular clusters; ultra-relativistic heavy ion collisions; external users; electronics, computing, and detector infrastructure; Van de Graff, superconducting booster and ion sources; nuclear physics laboratory personnel; degrees granted for 1994--1995; and list of publications from 1994--1995.

  20. Nuclear reactor simulator for a teaching laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Kosilov, A.N. (Moscow Engineering Physics Inst. (USSR))

    A nuclear reactor simulator is described which has been developed by the Department of Automatics and Telemechanics of the Moscow Engineering Physics Institute to provide students with an insight into, and familiarity with the characteristics of a nuclear reactor and its systems through evaluation, manipulation and experimentation.

  1. TIT reactor laboratory course using JAERI and PNC large experimental facilities

    International Nuclear Information System (INIS)

    This report is presented on a reactor laboratory course for graduate students using large facilities in national laboratories in Japan. A reactor laboratory course is offered every summer since 1990 for all graduate students in the Nuclear Engineering Course in Tokyo Institute of Technology (TIT), where the students can choose one of the experiments prepared at Japan Atomic Energy Research Institute (JAERI), Power Reactor and Nuclear Fuel Development Corporation (PNC) and Research Reactor Institute, Kyoto University (KUR). Both JAERI and PNC belong to Science and Technology Agency (STA). This is the first university curriculum of nuclear engineering using the facilities owned by the STA laboratories. This type of collaboration is promoted in the new Long-Term Program for Research, Development and Utilization of Nuclear Energy adopted by Atomic Energy Commission. Most students taking this course reported that they could learn so much about reactor physics and engineering in this course and the experiment done in large laboratory was a very good experience for them. (author)

  2. An Account of Oak Ridge National Laboratory's Thirteen Research Reactors

    International Nuclear Information System (INIS)

    The Oak Ridge National Laboratory has built and operated 13 nuclear reactors in its 66-year history. The first was the graphite reactor, the world's first operational nuclear reactor, which served as a plutonium production pilot plant during World War II. It was followed by two aqueous-homogeneous reactors and two red-hot molten-salt reactors that were parts of power-reactor development programs and by eight others designed for research and radioisotope production. One of the eight was an all-metal fast burst reactor used for health physics studies. All of the others were light-water cooled and moderated, including the famous swimming-pool reactor that was copied dozens of times around the world. Two of the reactors were hoisted 200 feet into the air to study the shielding needs of proposed nuclear-powered aircraft. The final reactor, and the only one still operating today, is the High Flux Isotope Reactor (HFIR) that was built particularly for the production of californium and other heavy elements. With the world's highest flux and recent upgrades that include the addition of a cold neutron source, the 44-year-old HFIR continues to be a valuable tool for research and isotope production, attracting some 500 scientific visitors and guests to Oak Ridge each year. This report describes all of the reactors and their histories.

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

    International Nuclear Information System (INIS)

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

  4. Update on the University of Missouri-Columbia Research Reactor Upgrade

    International Nuclear Information System (INIS)

    The University of Missouri-Columbia (MU) is in the process of upgrading the research and operational capabilities of the MU Research Reactor (MURR) and associated facilities. The plans include an expanded research building that will double the laboratory space, the addition of new research programs, instrumentation and equipment, a cold neutron source, and improved reactor systems. These enhancements, which are in various stages of completion, will greatly expand the present active multidisciplinary research programs at MURR

  5. A view of technology maturity assessment to realize fusion reactor by Japanese young researchers

    International Nuclear Information System (INIS)

    Japanese young researchers who have interest in realizing fusion reactor have analyzed Technology Readiness Levels (TRL) in Young Scientists Special Interest Group on Fusion Reactor Realization. In this report, brief introduction to TRL assessment and a view of TRL assessment against fusion reactor projects conducting in Japan. (J.P.N.)

  6. Nuclear Physics Laboratory, University of Washington annual report

    International Nuclear Information System (INIS)

    The Nuclear Physics Laboratory at the University of Washington in Seattle pursues a broad program of nuclear physics. These activities are conducted locally and at remote sites. The current programs include in-house research using the local tandem Van de Graaff and superconducting linac accelerators and non-accelerator research in solar neutrino physics at the Sudbury Neutrino Observatory in Canada and at SAGE in Russia, and gravitation as well as user-mode research at large accelerators and reactor facilities around the world. Summaries of the individual research projects are included. Areas of research covered are: fundamental symmetries, weak interactions and nuclear astrophysics; neutrino physics; nucleus-nucleus reactions; ultra-relativistic heavy ions; and atomic and molecular clusters

  7. Nuclear Physics Laboratory, University of Washington annual report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-04-01

    The Nuclear Physics Laboratory at the University of Washington in Seattle pursues a broad program of nuclear physics. These activities are conducted locally and at remote sites. The current programs include in-house research using the local tandem Van de Graaff and superconducting linac accelerators and non-accelerator research in solar neutrino physics at the Sudbury Neutrino Observatory in Canada and at SAGE in Russia, and gravitation as well as user-mode research at large accelerators and reactor facilities around the world. Summaries of the individual research projects are included. Areas of research covered are: fundamental symmetries, weak interactions and nuclear astrophysics; neutrino physics; nucleus-nucleus reactions; ultra-relativistic heavy ions; and atomic and molecular clusters.

  8. Undergraduate Skills Laboratories at Sonoma State University

    Science.gov (United States)

    Gill, Amandeep; Zack, K.; Mills, H.; Cunningham, B.; Jackowski, S.

    2014-01-01

    Due to the current economic climate, funding sources for many laboratory courses have been cut from university budgets. However, it is still necessary for undergraduates to master laboratory skills to be prepared and competitive applicants when entering the professional world and/or graduate school. In this context, student-led programs may be able to compensate for this lack of formal instruction and reinforce concepts from lecture by applying research techniques to develop hands-on comprehension. The Sonoma State University Chapter of Society of Physics Students has established a peer-led skills lab to teach research techniques in the fields of astronomy and physics. The goal is to alleviate the pressures of both independently learning and efficiently applying techniques to junior and senior-level research projects. These skill labs are especially valuable for nontraditional students who, due to work or family duties, may not get a chance to fully commit to research projects. For example, a topic such as Arduino programming has a multitude of applications in both astronomy and physics, but is not taught in traditional university courses. Although some programming and electronics skills are taught in (separate) classes, they are usually not applied to actual research projects, which combined expertise is needed. For example, in astronomy, there are many situations involving programming telescopes and taking data with electronic cameras. Often students will carry out research using these tools but when something goes wrong, the students will not have the skills to trouble shoot and fix the system. Another astronomical topic to be taught in the skills labs is the analysis of astronomical data, including running remote telescopes, analyzing photometric variability, and understanding the concepts of star magnitudes, flat fields, and biases. These workshops provide a setting in which the student teacher may strengthen his or her understanding of the topic by presenting

  9. Annual report of Nuclear Engineering Research Laboratory, University of Tokyo in fiscal 1989

    International Nuclear Information System (INIS)

    This report summerizes the research and educational activities at the Nuclear Engineering Research Laboratory, Faculty of Engineering, University of Tokyo. The Laboratory holds four main facilities, which are Yayoi reactor, an electron accelerator, fusion blanket research facility, and heavy ion irradiation research facility. And they are open to the researchers both inside and outside the University. The application of the facilities are described. The activities and achievements of the Laboratory staffs, and theses for graduate, master, and doctor degrees are also summerized. (J.P.N.)

  10. CFD Simulation of Laboratory Scale Airlift Reactor

    Czech Academy of Sciences Publication Activity Database

    Šimčík, Miroslav; Havlica, Jaromír; Růžička, Marek; Drahoš, Jiří

    Bratislava: Slovak Society of Chemical Engineering, 2008 - (Markoš, J.), s. 310 ISBN 978-80-227-2903-1. [35th International Conference of Slovak Society of Chemical Engineering. Tatranské Matliare (SK), 26.05.2008-30.05.2008] R&D Projects: GA ČR GA104/07/1110; GA ČR GA104/06/1418 Institutional research plan: CEZ:AV0Z40720504 Keywords : cfd simulation * airlift reactor Subject RIV: CI - Industrial Chemistry, Chemical Engineering

  11. Operational Experience with the TRIGA Mark II Reactor of the University of Pavia

    International Nuclear Information System (INIS)

    The Laboratory of Applied Nuclear Energy (LENA) is an Interdepartmental Research Centre of the University of Pavia which operates a 250 kW TRIGA Mark II Research Nuclear Reactor, a Cyclotron for the production of radioisotopes and other irradiation facilities. The reactor is in operation since 1965 and many home-made upgrading were realized in the past years in order to assure a continuous operation of the reactor for the future. The annual reactor operational time at nominal power is in the range of 300 - 400 hours depending upon the time schedule of some experiments and research activities. The reactor is mainly used for NAA activities, BNCT research, samples irradiation and training. In specific, few tens of hours of reactor operation per year are dedicated to training courses for University students and for professionals. Besides, the LENA Centre hosts every year more than one thousand high school students in visit. Lately, LENA was certified ISO 9001:2008 for the ''operation and maintenance of the reactor'' and for the ''design and delivery of the irradiation service''. Nowadays the reactor shows a good technical state and, at the moment, there are no political or economical reason to consider the reactor shut-down. (author)

  12. Operational Experience with the TRIGA Mark II Reactor of the University of Pavia

    Energy Technology Data Exchange (ETDEWEB)

    Tigliole, A. Borio Di; Alloni, D.; Cagnazzo, M.; Coniglio, M.; Lana, F.; Losi, A.; Magrotti, G.; Manera, S.; Marchetti, F.; Pappalardo, P.; Prata, M.; Provasi, M.C.; Salvini, A.; Scian, G.; Vinciguerra, G. [University of Pavia, Laboratory of Applied Nuclear Energy (L.E.N.A), Via Aselli 41, 27100 Pavia (Italy)

    2011-07-01

    The Laboratory of Applied Nuclear Energy (LENA) is an Interdepartmental Research Centre of the University of Pavia which operates a 250 kW TRIGA Mark II Research Nuclear Reactor, a Cyclotron for the production of radioisotopes and other irradiation facilities. The reactor is in operation since 1965 and many home-made upgrading were realized in the past years in order to assure a continuous operation of the reactor for the future. The annual reactor operational time at nominal power is in the range of 300 - 400 hours depending upon the time schedule of some experiments and research activities. The reactor is mainly used for NAA activities, BNCT research, samples irradiation and training. In specific, few tens of hours of reactor operation per year are dedicated to training courses for University students and for professionals. Besides, the LENA Centre hosts every year more than one thousand high school students in visit. Lately, LENA was certified ISO 9001:2008 for the ''operation and maintenance of the reactor'' and for the ''design and delivery of the irradiation service''. Nowadays the reactor shows a good technical state and, at the moment, there are no political or economical reason to consider the reactor shut-down. (author)

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

    International Nuclear Information System (INIS)

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

  14. Wanna be in health physics? Try a university research reactor

    International Nuclear Information System (INIS)

    Ultimately, the key radiation protection issue is each individual's understanding - i.e., understanding of the technical aspects, the safety implications, and the need for their commitment to the overall program. University research reactors can offer a wide range of radiation protection experiences to develop this understanding for not only the health physicist but also any individual involved with nuclear science and technology applications. This paper discusses such topics as radiopharmaceutical research and development, nutritional studies, and reactor maintenance as activities associated with the University of Missouri - Columbia Research Reactor Center (MURR). 3 refs., 1 tab

  15. U.S. Department of Energy University Reactor Instrumentation Program Final Report for 1992-94 Grant for the University of Florida Training Reactor

    International Nuclear Information System (INIS)

    Overall, the instrumentation obtained under the first year 1992-93 University Reactor Instrumentation Program grant assured that the goals of the program were well understood and met as well as possible at the level of support provided for the University of Florida Training Reactor facility. Though the initial grant support of $21,000 provided toward the purchase of $23,865 of proposed instrumentation certainly did not meet many of the facility's needs, the instrumentation items obtained and implemented did meet some critical needs and hence the goals of the Program to support modernization and improvement of reactor facilities such as the UFTR within the academic community. Similarly, the instrumentation obtained under the second year 1993-94 University Reactor Instrumentation Program grant again met some of the critical needs for instrumentation support at the UFTR facility. Again, though the grant support of $32,799 for proposed instrumentation at the same cost projection does not need all of the facility's needs, it does assure continued facility viability and improvement in operations. Certainly, reduction of forced unavailability of the reactor is the most obvious achievement of the University Reactor Instrumentation Program to date at the UFTR. Nevertheless, the ability to close out several expressed-inspection concerns of the Nuclear Regulatory Commission with acquisition of the low level survey meter and the area radiation monitoring system is also very important. Most importantly, with modest cost sharing the facility has been able to continue and even accelerate the improvement and modernization of a facility, especially in the Neutron Activation Analysis Laboratory, that is used by nearly every post-secondary school in the State of Florida and several in other states, by dozens of departments within the University of Florida, and by several dozen high schools around the State of Florida on a regular basis. Better, more reliable service to such a broad

  16. Development of a new virtual nuclear reactor laboratory

    International Nuclear Information System (INIS)

    Full text: Nowadays the education industry benefits from computer programs and software in various ways as well as many other industries. Here the e-learning technology uses some forms of software platform to present its contents. Virtual laboratories are superior tools in this technology. A virtual laboratory is interactive graphical user interface software that is based on known scientific laws of its virtual elements, which responses to user acts as desired in the real case. There are some known commercial and non-commercial ones. There are also some simulation software in the field of nuclear industry that has some uses in operator learning and some other applications such as analyzing the effects of human mistakes on plant safety. In this paper we discuss more about the ways to develop a virtual nuclear reactor laboratory and propose our first release of such tool. Our target reactor is Tehran Research Reactor (TRR), which is a pool type reactor. We used WIMS and COSTANZA to develop the simulator kernel of virtual laboratory. (Author)

  17. Treatment of Laboratory Wastewater by Sequence Batch reactor technology

    International Nuclear Information System (INIS)

    These studies were conducted on the characterization and treatment of sewage mixed with waste -water of research and testing laboratory (PCSIR Laboratories Lahore). In this study all the parameters COD, BOD and TSS etc of influent (untreated waste-water) and effluent (treated waste-water) were characterized using the standard methods of examination for water and waste-water. All the results of the analyzed waste-water parameters were above the National Environmental Quality Standards (NEQS) set at National level. Treatment of waste-water was carried out by conventional sequencing batch reactor technique (SBR) using aeration and settling technique in the same treatment reactor at laboratory scale. The results of COD after treatment were reduced from (90-95 %), BOD (95-97 %) and TSS (96-99 %) and the reclaimed effluent quality was suitable for gardening purposes. (author)

  18. Application of PCs to a nuclear reactor laboratory course

    International Nuclear Information System (INIS)

    Most nuclear engineering curricula contain a nuclear reactor laboratory course. Traditionally these courses involve a tremendous amount of manual data collection and hand processing. With the advent of personal computers (PCs), it is now possible to perform virtually all data collection, storage, and analysis with the aid of a PC. The four 12-bit ADC input ports and a 16-bit input counter of an IBM data acquisition and display adapter (DACA) have been used as an interface between the nuclear reactor and the PC. The DACA is supplied with DOS subroutines (BASIC, C, or FORTRAN) to perform various data manipulations and control functions. Analog input subroutines have been used to measure a set of analog parameters at a user-determined rate, such as for the simultaneous measurement of reactor power and fuel temperature. Adoption of the DACA and its support software has resulted in a significant improvement to the nuclear reactor laboratory course. A considerable amount of time is saved in data taking, and students tend to perform more detailed data analyses. Appearance of laboratory reports has also improved due to the use of word processors and data plotting routines

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

    International Nuclear Information System (INIS)

    Research reactor utilization has been an integral part of the North Carolina State University's (NCSU's) nuclear engineering program since its inception. The undergraduate curriculum has a strong teaching laboratory component. Graduate classes use the reactor for selected demonstrations, experiments, and projects. The reactor is also used for commercial power reactor operator training programs, neutron radiography, neutron activation analysis (NAA), and sample and tracer activation for industrial short courses and services as part of the university's land grant mission. The PULSTAR reactor is a 1-MW pool-type reactor that uses 4% enriched UO2 pellet fuel in Zircaloy II cladding. Standard irradiation facilities include wet exposure ports, a graphite thermal column, and a pneumatic transfer system. In the near term, general facility upgrades include the installation of signal isolation and computer data acquisition and display functions to improve the teaching and research interface with the reactor. In the longer term, the authors foresee studies of new core designs and the development of beam experiment design tools. These would be used to study modifications that may be desired at the end of the current core life and to undertake the development of new research instruments

  20. Taking samples from the reactor components in preparation for dismantling the TRIGA reactor at the Medical University of Hannover

    International Nuclear Information System (INIS)

    After shutting down the facility at the end of 1996 the spent TRIGA fuel elements from the research reactor at the Medical University of Hanover (MHH) were returned to the United States in the summer of 1999 and thus disposed of for the MHH. Consequently one of the main prerequisites for dismantling the TRIGA reactor as planned has been fulfilled. In preparation for dismantling the facility a number of samples were taken from the various reactor components in 2000. The aim of the samples being taken was to establish the radiological condition of the facility in more detail, in particular the condition of the activated components in the reactor tank and the biological shield in the core area. Up to now the calculated estimates for these components had been based mainly on the details provided in the facility documentation when operation started at the beginning of the 1970s, showing that the evaluation of the activity and dose rates was too high. This was confirmed in 1998 in the course of measuring contamination and dose rates when samples were taken from some reactor components before the fuel elements were removed. For example, drill samples were taken from the bottom part of a graphite blind element and from the central radiation beam tube in the core area and then analyzed by the U.R.A. Laboratory of the University of Regensburg. As it is planned to dismantle the reactor facility completely by hand, it is necessary to have realistic radiological data in order to prepare for the dismantling procedure. Furthermore, both the release of radioactive materials into the environment and the costs for external disposal of the radioactive waste from the dismantling of the reactor are to be kept to a minimum. (orig.)

  1. Safeguards experience at the Sandia Laboratories reactor site

    International Nuclear Information System (INIS)

    Sandia Laboratories has an extensive activity in the safeguards area with application to the Technical Area V reactors. The security, development, and operations groups are working together to establish systems which comply with the manual chapters as well as advanced safeguards systems. It appears that to bring an existing facility into compliance with current requirements may be expensive in terms of hardware, facility modifications, manpower, and loss of reactor operating time. The reactor operations and the security groups at Sandia are fortunate to the extent that we are reaping the benefit from DSS funding the work of the development group. The activities conducted thus far have had no measurable impact on the operational safety of the facility. However, we are currently at the midpoint of a five year program with many major modifications, systems development, and decisions yet to be made. Hopefully, the favorable experience will continue

  2. Universe Awareness: Inspiring young children around the world

    Science.gov (United States)

    Ödman, Carolina J.

    2011-06-01

    Universe Awareness (UNAWE) has over three years of experience enthusing young children with the scale and beauty of the Universe. UNAWE is an outreach programme with a strong social vision aiming at broadening children's minds, awakening their curiosity in science and stimulating global citizenship. UNAWE uses the inspirational aspects of astronomy to instil a culture of peace and tolerance. We present the main principles of the programme, describe how it functions as a community-driven organisation and share some of the UNAWE experience. We describe projects and opportunities for IYA2009 and the future of the global programme.

  3. The need to address the larger universe of HEU-fueled reactors, including critical assemblies, pulsed reactors and propulsion reactors

    International Nuclear Information System (INIS)

    Full text: The RERTR program has focused thus far primarily on ending shipments of HEU fuel to research reactors. This has resulted in giving highest priority to reactors with steady thermal powers of 1 megawatt or more, because they require regular refuelling. Critical facilities and pulsed reactors can also of serious concern, because some of them contain very large amounts of barely-irradiated HEU and plutonium. They could be costly to convert - and conversion to LEU may be impractical for fast-neutron critical assemblies. An assessment should be carried out first, therefore, as to which are still needed. Critical assemblies are required today primarily to benchmark Monte Carlo neutron-transport codes. Perhaps the world nuclear community could share a few instead of each reactor-design institute having its own. There is also a whole universe of HEU-fuelled pressurized-water reactors used to power submarines and other types of nuclear-powered ships. These reactors collectively require much more HEU fuel each year than research reactors. The risk of HEU diversion from their fuel cycles is not zero but it is difficult for outsiders to discuss conversion because of the fuel designs are classified. This makes the conversion of Russia's civilian icebreaker reactors of particular interest because issues of classified fuel design are less problematic and these reactors load annually fuel containing about 400 kg of U-235. Another reason for interest in developing LEU fuel for these reactors is that the KLT-40 icebreaker reactor is being adapted for a floating nuclear power plant. Finally, the research-reactor community is, in any case, faced with developing fuels that can operate at power-reactor-fuel temperatures because there are a few high-powered research reactors that operate in this temperature range. (author)

  4. Universe Awareness . An inspirational programme for economically disadvantaged young children.

    Science.gov (United States)

    Ödman, C. J.; Scorza, C.; Miley, G. K.; Madsen, C.

    The beauty of the sky and its connection with the human development have inspired generations with wonder. Astronomy conveys the excitement of science to the public. Considerable resources are devoted to outreach in developed countries, with spectacular images produced by modern astronomical facilities and astronomical discoveries that change our views of the Universe. Universe Awareness (UNAWE) is a programme for children between 4 and 10 years old. The formative ages of 4 to 10 years are crucial in child development. Children of that age can appreciate the beauty of astronomical objects and develop a ``feeling'' for the vastness of the Universe. Exposing young children to such material is likely to broaden their minds and stimulate their world-view. The programme concentrates on economically disadvantaged young children because most other children will be exposed to some knowledge about the Universe and disparities between advantaged and disadvantaged children increase with age. Venezuela hosted a successful pilot project in 2006. From spontaneous observation of the sky to a teacher-training workshop in the "Centro de Investigaciones de Astronomía" in Mérida, this was a wonderful experience for participants and organisers alike. This shows how successful the UNAWE programme can be.

  5. 75 FR 56597 - University of Wisconsin; University of Wisconsin Nuclear Reactor Environmental Assessment and...

    Science.gov (United States)

    2010-09-16

    ... Engineering Physics. The Mechanical Engineering Building is near the southwestern border of the University of.... The UWNR is located in the Mechanical Engineering Building on the main campus of the University of... conventional construction within the Mechanical Engineering Building. Throughout most of the Reactor...

  6. Annual report of Laboratory of Nuclear Studies, Osaka University

    International Nuclear Information System (INIS)

    Activities of the Laboratory of Nuclear Studies, Osaka University, in 1975, are presented in individual summaries, and also a list of publications in journals: Cyclotron Division, High Voltage Accelerator Division, Mass Spectroscopy Division, Radioisotope Division, and Theoretical Division. (Mori, K.)

  7. Biennial activity report of Reactor Engineering Laboratory - 1983 and 1984

    International Nuclear Information System (INIS)

    This report summarises activities of the Reactor Engineering Laboratory for the period January 1983 to December 1984. The report consists of four sections dealing with development of reactor components, prototype tests in sodium, instrumentation development and measurement techniques and noise analysis techniques respectively. As is customary, the activities have been reported in brief but where detailed reports have been prepared the same are referred. The main thrust of the work of the laboratory was still in support of the FBTR which is in an advanced stage of construction and commissioning at Kalpakkam site. Purification of 100 tonnes of commercial grade sodium to reactor grade, pouring of the liquid metal seals and the construction and commissioning of a sodium loop for calibration of the hydrogen leak detector in all represented significant contribution towards FBTR. The section on development of reactor components describes efforts on construction of both electromagnetic and small mechanical sodium pumps. Sodium removal from the control rod drive mechanism by means of vacuum distillation technique has been a useful experience despite some difficulties faced due, possibly, to the presence of extraneous matter in the decontamination set-up. The section on instrumentation development and measurement techniques describes interesting development concerning ultrasonic imaging for under sodium viewing. The last section on noise analysis techniques describes some experience gained in the detection of cavitation in dummy fuel subassembly by means of acoustic technique. The developmental efforts on construction of high temperature acoustic sensors of both piezoelectric and magnetostrictive type have been encouraging. At the end of the report is included a list of technical publications of the laboratory. (author)

  8. Utilization of research reactors in universities and their medical applications

    International Nuclear Information System (INIS)

    In Japan, five research reactors and a critical assembly are operated by the universities. They are opened to all university researchers, the system of which is financially supported by the Ministry of Education, Culture and Science of the Japanese government. Usually KUR is operated eight cycles per year. One cycle consists of the following four week operation: 1. Mainly for researchers from other universities; 2. Mainly for researchers in the institute; 3. Mainly for beam experiment; 4. Sort time experiment. In the weeks of 1 ∼ 3 the KUR is operated continously from Tuesday morning to Friday evening. The experiment include studies on physics, chemistry, biology, medicine, engineering etc. Recently the medical application of research reactors has become popular in Japan. The new technique of the boron neutron capture thereby has been successfully applied to brain tumors and will be to melanoma (skin cancer) in near future. (author)

  9. Progress toward the Laboratory Simulation of Young Supernova Remnants

    International Nuclear Information System (INIS)

    Progress in experiments to simulate the hydrodynamics of supernova remnants (SNRs) in the laboratory is reported. The experiment design involves shock heating of a dense material, which expands to become the ejecta that drive a blast wave through low-density foam. In the design, a variety of issues, such as radiative preheat of the unshocked matter, had to be addressed. A careful analysis of the scaling between hydrodynamic systems shows that the experiment is a good, scaled model of a local region in a young SNR. Measurements of the basic hydrodynamic behavior for two blast-wave velocities are nearly complete. Measurements of hydrodynamic instabilities at the contact surface between the ejecta and the low-density matter will commence in the near future. (c) 2000 The American Astronomical Society

  10. Annual Report 2002 of Warsaw University, Heavy Ion Laboratory

    International Nuclear Information System (INIS)

    The Annual Report of Warsaw University Heavy Ion Laboratory is the overview of the Laboratory and assembly of scientific activities of the team especially in the range of instrumental development, experiments and experimental set-ups and experiments using outside facilities of Warsaw Cyclotron

  11. Assessment of RELAP5 model for the University of Massachusetts Lowell Research Reactor

    Directory of Open Access Journals (Sweden)

    Bousbia-Salah Anis

    2006-01-01

    Full Text Available RELAP5 is a system code developed at the Idaho National Environmental and Engineering Laboratory for thermal hydraulic analysis of nuclear reactors. The code RELAP5 is widely used for safety analysis studies of commercial nuclear power plants. However, recent released version of RELAP5/3.2 and over present significant capabilities for analysis of nuclear reactor research systems. As a contribution to the assessment of RELAP5/3.3 for research reactor safety analysis, experimental data from the University of Massachusetts Lowell Research Reactor - UMLRR are used. The UMLRR is a 1 MW light water moderated and cooled, graphite-reflected, open-pool type research reactor. This paper presents the development and the validation of a UMLRR-RELAP model using experimental data. For this purpose, a series of experiments were performed for benchmarking RELAP5 calculations for research reactor systems. As a result of this study, the UMLRR nodalization is shown to be representative of the experimental data reactor behavior.

  12. Use of university research reactors to teach control engineering

    International Nuclear Information System (INIS)

    University research reactors (URRs) have provided generations of students with the opportunity to receive instruction and do hands-on work in reactor dynamics, neutron scattering, health physics, and neutron activation analysis. Given that many URRs are currently converting to programmable control systems, the opportunity now exists to provide a similar learning experience to those studying systems control engineering. That possibility is examined here with emphasis on the need for the inclusion of experiment in control engineering curricula, the type of activities that could be performed, and safety considerations

  13. The Michigan State University Cyclotron Laboratory: Its Early Years

    Science.gov (United States)

    Austin, Sam M.

    2016-01-01

    The Michigan State University Cyclotron Laboratory was founded in 1958 and over the years grew in stature, becoming the highest-ranked university-based program in nuclear science. Its K50 cyclotron had unmatched capability as a light-ion accelerator and helped to define what a modern cyclotron could do to advance our understanding of nuclei. This paper describes the first twenty years of the Cyclotron Laboratory's evolution and gives some insight into the cultural characteristics of the laboratory, and of its early members, that led it to thrive.

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

    International Nuclear Information System (INIS)

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

  15. [Future roles of clinical laboratories and clinical laboratory technologists in university hospitals].

    Science.gov (United States)

    Yokota, Hiromitsu; Yatomi, Yutaka

    2013-08-01

    Clinical laboratories in university hospitals should be operated with a good balance of medical practice, education, research, and management. The role of a clinical laboratory is to promptly provide highly reliable laboratory data to satisfy the needs of clinicians involved in medical practice and health maintenance of patients. Improvement and maintenance of the quality of the laboratory staff and environment are essential to achieve this goal. In order to implement these requirements efficiently, an appropriate quality management system should be introduced and established, and evaluated objectively by a third party (e.g. by obtaining ISO 15189 certification). ISO 15189 is an international standard regarding the quality and competence of clinical laboratories, and specifies a review of the efficient operational system and technical requirements such as competence in implementing practical tests and calibration. This means the results of laboratory tests reported by accredited laboratories withstand any international evaluation, which is very important to assure the future importance of the existence and management of clinical laboratories as well as internationalization of medical practice. "Education" and "research" have important implications in addition to "medical practice" and "management", as the roles that clinical laboratories should play in university hospitals. University hospital laboratories should be operated by keeping these four factors in good balance. Why are "education" and "research" required in addition to "medical practice" services? If individual clinical laboratory technologists can provide an appropriate response to this question, the importance of the existence of clinical laboratories would be reinforced, without being compromised. PMID:24218765

  16. Oak Ridge National Laboratory Research Reactor Experimenters' Guide

    International Nuclear Information System (INIS)

    The Oak Ridge National Laboratory has three multipurpose research reactors which accommodate testing loops, target irradiations, and beam-type experiments. Since the experiments must share common or similar facilities and utilities, be designed and fabricated by the same groups, and meet the same safety criteria, certain standards for these have been developed. These standards deal only with those properties from which safety and economy of time and money can be maximized and do not relate to the intent of the experiment or quality of the data obtained. The necessity for, and the limitations of, the standards are discussed; and a compilation of general standards is included

  17. Development of neutron beam projects at the University of Texas TRIGA Mark II Reactor

    International Nuclear Information System (INIS)

    Recently, the UT-TRIGA research reactor was licensed and has become fully operational. This reactor, the first new US university reactor in 17 years, is the focus of a new reactor laboratory facility which is located on the Balcones Research Center at The University of Texas at Austin. The TRIGA Mark II reactor is licensed for 1.1 MW steady power operation, 3 dollar pulsing, and includes five beam ports. Various neutron beam-line projects have been assigned to each beam port. Neutron Depth Profiling (NDP) and the Texas Cold Neutron Source (TCNS) are close to completion and will be operational in the near future. The design of the NDP instrument has been completed, a target chamber has been built, and the thermal neutron collimator, detectors, data acquisition electronics, and data processing computers have been acquired. The target chamber accommodates wafers up to 12'' in diameter and provides remote positioning of these wafers. The design and construction of the TCNS has been completed. The TCNS consists of a moderator (mesitylene), a neon heat pipe, a cryogenic refrigerator, and neutron guide tubes. In addition, fission-fragment research (HIAWATHA), Neutron Capture Therapy, and Neutron Radiography are being pursued as projects for the other three beam ports. (author)

  18. Coalescence kinetics of dispersed crude oil in a laboratory reactor

    International Nuclear Information System (INIS)

    A study was conducted to examine the effects of salinity and mixing energy on the resurfacing and coalescence rates of chemically dispersed crude oil droplets. This kinetic study involved the use of mean shear rates to characterize the mixing energy in a laboratory reactor. Coagulation kinetics of dispersed crude oil were determined within a range of mean shear rates of 5, 10, 15, and 20 per second, and with salinity values of 10 and 30 per cent. Observed droplet distributions were fit to a transport-reaction model to estimate collision efficiency values and their dependence on salinity and mixing energy. Dispersant efficiencies were compared with those derived from other laboratory testing methods. Experimentally determined dispersant efficiencies were found to be 10 to 50 per cent lower than predicted using a non-interacting droplet model, but dispersant efficiencies were higher than those predicted using other testing methods. 24 refs., 1 tab., 3 figs

  19. Status of the University of Virginia reactor LEU conversion

    International Nuclear Information System (INIS)

    The University of Virginia began working on converting the CAVALIER and UVAR reactors to LEU fuel in the Spring of 1986. Early in 1987, based on reactor use considerations, a decision was made to shut down the CAVALIER. A decommissioning plan was submitted to the NRC, and the decommissioning order was issued in early 1992. There is now a tentative agreement to donate the CAVALIER equipment without fuel to the University of North Texas. Design calculations for the UVAR were completed, and the Safety Analysis Report was submitted to the NRC in late 1989. The DOE/EG ampersand G order to manufacture UVAR fuel was placed at B ampersand W in March 1992, and conversion is expected to take place early in 1993

  20. Work as representation: the view of young university students

    Directory of Open Access Journals (Sweden)

    Sidinei Rocha de Oliveira

    2010-01-01

    Full Text Available One period of particular importance in the relation of the individual to the world of work is the transition from youth to adulthood, when, among other modifications (biological, psychological and social, entry into the job market has a fundamental role, marking a new stage of life. Hence, this study seeks to analyse which social representations are present in the speech of young students of a Management course with regard their understanding of the “work”. For this purpose, 120 young university students attending the first semesters of an evening Management course at a university in the south of Brazil were consulted. The responses regarding “what is work” and “what is not work” were written by the informants themselves and later analysed in relation to the frequency with which they occur and their diversity. In general, it is noted that work continues to be understood as the central activity that structures the life of individuals and of society in general, a form of social integration, in which its image prevails as an element that inserts the individual in the environment, capable of leading to personal and professional fulfilment as well as to financial sustenance.

  1. Control of occupational exposure in a university research reactor

    International Nuclear Information System (INIS)

    A university institute operating a research reactor and other installations is an institution where occupational exposure may occur, but has some typical characteristics not necessarily fully consistent with Radiation Protection Standards. As the dose records indicate a trend to lower doses, the problems are rather of a formal than of a technical nature. Some of the problems in practical radiation protection are addressed and solutions are discussed. (author)

  2. Annual report of Nuclear Engineering Research Laboratory, University of Tokyo in fiscal 1991

    International Nuclear Information System (INIS)

    In this annual report, the activities of education and research, the state of operation of research facilities and others in Nuclear Engineering Research Laboratory, University of Tokyo in fiscal year 1991 are summarized. In this Laboratory, there are four large research facilities, that is, the fast neutron source reactor 'Yayoi', the electron beam linac, the nuclear fusion reactor blanket experiment facility and the heavy irradiation research facility. Those are used for carrying out education and research in the wide fields of nuclear engineering, and are offered also for joint utilization. The results of the research by using respective research facilities were summarized in separate reports. In this annual report, the course of the management and operation of respective research facilities is described, and the research activities, the theses for doctorate and graduation theses of the teachers, personnel and graduate students in the Laboratory are summarized. In the research, those on first wall engineering for fusion reactors, fuel cycle engineering, electromagnetic structure engineering, AI and robotics, quantum beam engineering, new type reactor design and so on are included. (K.I.)

  3. Building a Laboratory: the Work of Global University Rankers

    DEFF Research Database (Denmark)

    Lim, Miguel Antonio

    2015-01-01

    This paper uses the science laboratory as a metaphor to understand the work of university rankers. I suggest that we need a better understanding of who makes the rankings and a better sense of the work of experimentation, in a broad sense, that rankers carry out in order to produce new, ‘better...... education evaluation. I present some of the ways in which these leaders are part of the process from the lesser known point-of-view of the ranking organisations. I propose three questions: 1) Can the university ranker be thought of as a ‘laboratory’? 2) How does the university ranking laboratory produce its...... ‘science’, data and facts? and 3) To what end does this laboratory work? Why does it experiment? To answer these questions, I draw upon an analysis of my participation in and observation of ranking events and ranking production over a two year period, from November 2013 until October 2015. Firstly, I...

  4. A STUDY OF INDOOR AIR QUALITY IN UNIVERSITY LABORATORY BUILDINGS

    Directory of Open Access Journals (Sweden)

    ADE ASMI

    2012-09-01

    Full Text Available This paper is a study of Indoor Air Quality (IAQ of laboratory in university buildings at faculty of civil and environmental engineering, Universiti Tun Hussein Onn Malaysia (UTHM. This study assessed the existing indoor air quality in two selected laboratory buildings, which equipped with natural ventilation. The importantIAQ parameters considered in this study are temperature, relative humidity, air movement, and airborne particles. However, airborne particles were categorized based on its size characterization concentration of particles ≥ 0.3 μm and particles ≥ 5.0 μm. The measurements were carried out during the peak hours within these laboratories using Met One GT-521 particle counter and Anemometer. Ultimately, area, time of measurement conducted, the number of activities, ventilation, air movement, and materials, were found as the major contributors to the IAQ performance in these laboratories.

  5. University of Helsinki Music Research Laboratory and Electronic Music Studio

    OpenAIRE

    Lassfolk, Kai; Ojanen, Mikko

    2014-01-01

    The University of Helsinki Music Research Laboratory and Electronic Music Studio is one of the oldest studios and research facilities of its kind in the Nordic countries. Originally named "ÄÀniteknillinen laboratorio" (Laboratory of sound technology), the studio was the leading electronic music facility in Finland from the early 1960s to the late 1970s. Built and maintained by Erkki Kurenniemi, the studio served also as an important center for the development of electronic musical instrumen...

  6. Annual report of Nuclear Engineering Research Laboratory, Faculty of Engineering, University of Tokyo, fiscal year 1994

    International Nuclear Information System (INIS)

    This annual report is the summary of the research and education activities, the state of operating research facilities and others in fiscal year 1994 in this Research Laboratory. In this Research Laboratory, there are four main installations, namely the fast neutron source reactor 'Yayoi', the electron linear accelerator, the basic experiment facility for the design of nuclear fusion reactor blanket and the heavy irradiation research facility. The former two are put to the joint utilization by all Japanese universities, the blanket is to that within Faculty of Engineering, and the HIT is to that within this university. The fast neutron science research facility, the installation of which was approved in 1993 as the ancillary equipment of the Yayoi, has been put to the joint utilization for all Japan, and achieved good results. In this report, the management and operation of these main installations, research activities, the publication of research papers,graduation and degree theses, the publication of research papers, graduation and degree theses, the events in the Laboratory for one year, the list of the visitors to the Laboratory, the list of the records of official trips to foreign countries and others, and the list of UTNL reports are described. (K.I.)

  7. Decommissioning Experience: University of Virginia Reactors, United States of America

    International Nuclear Information System (INIS)

    Full text: There were two research reactors at the University of Virginia. CAVALIER operated at a maximum power of 100 W from 1974 to 1988. The other reactor (generally referred to as the UVA reactor) operated at a maximum power of 1 MW or 2 MW from 1960 to 1998. The water contained in the pool was utilized to provide shielding during the segmenting and removal of highly contaminated components in the pool. This work was performed by divers using plasma arc cutting equipment. A cask liner was first placed in the reactor pool. The higher activity items were preferentially loaded nearest the centre of the cask, and the lower activity items loaded in the liner annulus to provide shielding. Because air sampling performed during segmentation proved that no airborne contamination was produced, no confinement structure was necessary. After shipment of the removed components, the remaining pool water was sampled and confirmed suitable for discharge to the sanitary sewer (through filters). Decontamination of the pool structures was performed using a water jet cutting process. Once the pool surfaces had been cleaned to bare concrete, surfaces were sampled for activation. The only activated concrete was detected radially around the beam tubes through the pool wall (author)

  8. Major Refurbishment of the University of Florida Training Reactor

    International Nuclear Information System (INIS)

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

  9. The role of the Iowa State University research reactor in nuclear engineering education

    International Nuclear Information System (INIS)

    On October 19, 1959, the Iowa State University Research Reactor (ISURR) was made critical for the first time. In the 29 yr since then, the reactor has been an integral part of the nuclear engineering program. Throughout its history, the major use of the ISURR has been as an educational tool. The reactor is currently used in both the undergraduate and graduate programs at ISU. The paper provides the reactor description and discusses reactor experiments for undergraduates and reactor use in graduate education

  10. MIT nuclear reactor laboratory high school teaching program

    International Nuclear Information System (INIS)

    For the last 6 years, the Massachusetts Institute of Technology (MIT) Nuclear Reactor Laboratory's academic and scientific staffa have been conducting evening seminars for precollege science teachers, parents, and high school students from the New England area. These seminars, as outlined in this paper, are intended to give general information on nuclear technologies with specific emphasis on radiation physics, nuclear medicine, nuclear chemistry, and ongoing research activities at the MIT research reactor. The ultimate goal is to create interest or build on the already existing interest in science and technology by, for example, special student projects. Several small projects have already been completed ranging from environmental research to biological reactions with direct student involvement. Another outcome of these seminars was the change in attitudes of science teachers toward nuclear technology. Numerous letters have been received from the teachers and parents stating their previous lack of knowledge on the beneficial aspects of nuclear technologies and the subsequent inclusion of programs in their curriculum for educating students so that they may also develop a more positive attitude toward nuclear power

  11. Hybrid simulation of boiling water reactor dynamics using a university research reactor

    International Nuclear Information System (INIS)

    A ''hybrid'' reactor/simulation (HRS) testing arrangement has been developed and experimentally verified using The Pennsylvania State University (Penn State) TRIGA Reactor. The HRS uses actual plant components to supply key parameters to a digital simulation (and vice versa). To implement the HRS on the Penn State TRIGA reactor, an experimental or secondary control rod drive mechanism is used to introduce reactivity feedback effects that are characteristic of a boiling water reactor (BWR). The simulation portion of the HRS provides a means for introducing reactivity feedback caused by voiding via a reduced order thermal-hydraulic model. With the model bifurcation parameter set to the critical value, the nonlinearity caused by the neutronic-simulated thermal/hydraulic coupling of the hybrid system is evident upon attaining a limit cycle, thereby verifying that these effects are indeed present. The shape and frequency of oscillation (∼ 0.4 Hz) of the limit cycles obtained with the HRS are similar to those observed in operating commercial BWRs. A control or diagnostic system specifically designed to accommodate (or detect) this type of anomaly can be experimentally verified using the research reactor based HRS

  12. The Missouri University Research Reactor (MURR) nuclear analysis program

    International Nuclear Information System (INIS)

    The University of Missouri-Columbia (MU) Research (MURR) began operations in 1966 and has operated at 10 megawatts over 90 percent of the time since 1977. The MURR organizational structure includes reactor operations, health physics and technical service and research groups. The Nuclear Analysis Program is one of the major research areas and also includes mission components of teaching and service utilizing neutron activation analysis, isotope production and gamma-ray spectroscopy in the diverse study of both the physical and life sciences. (author) 1 fig.; 5 tabs

  13. Research on the reactor physics using the Kyoto University Critical Assembly (KUCA)

    International Nuclear Information System (INIS)

    The Kyoto University Critical Assembly [KUCA] is a multi-core type critical assembly established in 1974, as a facility for the joint use study by researchers of all universities in Japan. Thereafter, many reactor physics experiments have been carried out using three cores (A-, B-, and C-cores) in the KUCA. In the A- and B-cores, solid moderator such as polyethylene or graphite is used, whereas light-water is utilized as moderator in the C-core. The A-core has been employed mainly in connection with the Cockcroft-Walton type accelerator installed in the KUCA, to measure (1) the subcriticality by the pulsed neutron technique for the critical safety research and (2) the neutron spectrum by the time-of-flight technique. Recently, a basic study on the tight lattice core has also launched using the A-core. The B-core has been employed for the research on the thorium fuel cycle ever since. The C-core has been employed (1) for the basic studies on the nuclear characteristics of light-water moderated high-flux research reactors, including coupled-cores, and (2) for a research related to reducing enrichment of uranium fuel used in research reactors. The C-core is being utilized in the reactor laboratory course experiment for students of ten universities in Japan. The data base of the KUCA critical experiments is generated so far on the basis of approximately 350 experimental reports accumulated in the KUCA. Besides, the assessed KUCA code system has been established through analyses on the various KUCA experiments. In addition to the KUCA itself, both of them are provided for the joint use study by researchers of all universities in Japan. (author)

  14. Technical basis in support of the conversion of the University of Missouri Research Reactor (MURR) core from highly-enriched to low-enriched uranium - core neutron physics

    Energy Technology Data Exchange (ETDEWEB)

    Stillman, J. [Argonne National Lab. (ANL), Argonne, IL (United States); Feldman, E. [Univ. of Missouri, Columbia, MO (United States). Columbia Research Reactor; Foyto, L [Univ. of Missouri, Columbia, MO (United States). Columbia Research Reactor; Kutikkad, K [Univ. of Missouri, Columbia, MO (United States). Columbia Research Reactor; McKibben, J C [Univ. of Missouri, Columbia, MO (United States). Columbia Research Reactor; Peters, N. [Univ. of Missouri, Columbia, MO (United States). Columbia Research Reactor; Stevens, J. [Argonne National Lab. (ANL), Argonne, IL (United States)

    2012-09-01

    This report contains the results of reactor design and performance for conversion of the University of Missouri Research Reactor (MURR) from the use of highly-enriched uranium (HEU) fuel to the use of low-enriched uranium (LEU) fuel. The analyses were performed by staff members of the Global Threat Reduction Initiative (GTRI) Reactor Conversion Program at the Argonne National Laboratory (ANL) and the MURR Facility. The core conversion to LEU is being performed with financial support of the U. S. government.

  15. Utilization of a university reactor for public acceptance

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Myung Hyun [Kyung Hee Univ., Gyeonggi-do (Korea, Republic of). Reactor Research and Education Center

    2015-06-15

    AGN-201K is a university reactor in Kyung Hee University (KHU) mainly used for student education as training short course as well as academic course for senior-level. After the Fukushima accident, public concern on radiation hazard has been increased beyond rational level at a neighboring country. It was found that AGN-201K be the perfect tool for interaction with general public. It is very safe to operate with general participants because it is adapted to the very low power. However, radiation level is reasonably high to detect and shield for practice. KHU has a Regional Radiation Monitoring Post where environmental radiation level at Suwon city is continuously measured. In this facility, radiation level at soil, rain, and local agricultural products were measured and reported to the national monitoring headquarter. A new mission of reactor research and education center of KHU has been tried from last summer. Facilities were opened for high school students and teachers for their science camps during summer and winter. A special public acceptance program named as experience camp for understanding the nuclear power and radiation was held 6 times for the last one-year period. Even though number of attendee was limited and small, feedback from participants was hot and positive enough to make professors be ready to sacrifice their personal time.

  16. Utilization of a university reactor for public acceptance

    International Nuclear Information System (INIS)

    AGN-201K is a university reactor in Kyung Hee University (KHU) mainly used for student education as training short course as well as academic course for senior-level. After the Fukushima accident, public concern on radiation hazard has been increased beyond rational level at a neighboring country. It was found that AGN-201K be the perfect tool for interaction with general public. It is very safe to operate with general participants because it is adapted to the very low power. However, radiation level is reasonably high to detect and shield for practice. KHU has a Regional Radiation Monitoring Post where environmental radiation level at Suwon city is continuously measured. In this facility, radiation level at soil, rain, and local agricultural products were measured and reported to the national monitoring headquarter. A new mission of reactor research and education center of KHU has been tried from last summer. Facilities were opened for high school students and teachers for their science camps during summer and winter. A special public acceptance program named as experience camp for understanding the nuclear power and radiation was held 6 times for the last one-year period. Even though number of attendee was limited and small, feedback from participants was hot and positive enough to make professors be ready to sacrifice their personal time.

  17. Heavy Ion Laboratory - Warsaw University - Annual Report 2003

    International Nuclear Information System (INIS)

    In the presented report the research activities of Heavy Ion Laboratory (HIL) of the Warsaw University in year of 2003 are described. The report is divided into four parts: Laboratory Overview, Experiments and Experimental Set-ups, Experiments using outside facilities and General information on HIL activities which contain the lists of personnel, seminars held at the HIL as well as external ones, the list of published papers and conference contributions. A summary of the (HIL) activities is briefly presented in ''Introduction'' written by HIL director prof. J. Jastrzebski

  18. University of Tennessee Comparative Animal Research Laboratory accident in 1971

    International Nuclear Information System (INIS)

    On 4 February 1971, a 32-year-old research technologist performing seed irradiated experiments at the University of Tennessee Comparative Animal Research Laboratory was exposed to a Cobalt 60 source of 7700 curies for 40 seconds. Details of the accident, dose estimates from dosimetry studies, and acute biological clinical findings are discussed. Follow-up clinical data on the hematopoietic system, biochemistry, fingers, and blood counts are discussed

  19. Status report on the University of Manitoba Accelerator Laboratory

    International Nuclear Information System (INIS)

    The University of Manitoba cyclotron completed an extensive upgrading program in late 1984. Since then, the cyclotron has operated very reliably and has realized the upgrading objectives for acceleration of H- ions. Future plans for upgrading and operation will be discussed. Recent trends in the funding of small accelerator laboratories have necessitated a search for financial support in fields not directly related to nuclear physics. Some facilities and services for use in these areas of research will be described. (author)

  20. A Semi-Batch Reactor Experiment for the Undergraduate Laboratory

    Science.gov (United States)

    Derevjanik, Mario; Badri, Solmaz; Barat, Robert

    2011-01-01

    This experiment and analysis offer an economic yet challenging semi-batch reactor experience. Household bleach is pumped at a controlled rate into a batch reactor containing pharmaceutical hydrogen peroxide solution. Batch temperature, product molecular oxygen, and the overall change in solution conductivity are metered. The reactor simulation…

  1. Experience with an accrediated INAA service laboratory at a University - will research be next?

    International Nuclear Information System (INIS)

    Quality assurance, total quality management, and accreditation are the recognizable attributes of an attitude and consideration of a work process that is being introduced to industry, utilities, and (industrial) laboratories. International reference documents-the International Standard Organization (ISO)- IEC guides - have been developed to harmonize the ways of implementing and evaluating QA practices in connection with accreditation. The life-styles of working under quality practices and working at a university demonstrate a large contrast. Many of the basic principles of quality practices, such as full documentation, written procedures and instructions, and careful consideration of the conditions under which work will be performed, are characteristically absent at universities. Universities nowadays also have a mission to teach quality practices to the present and future generations of scientists. Within a few years, society may call for academics who are not only knowledgeable on the principles of quality practices but who also have been educated, trained, and practiced in such an environment. Conflicts will be avoided when such academics occupy leading positions in organizations that already use quality practices or when they become responsible for the introduction of quality practices. The neutron activation analysis (NAA) laboratory and associated analysis systems at the Interfaculty Reactor Institute (IRI) of the Delft University of Technology has been reorganized and brought into accord with the requirements of EN45001 and ISO guide 25. After an audit by the official accreditation body in the Netherlands, STERLAB, the laboratory received its accreditation in early 1993, making it the first accredited laboratory of both kinds (university and instrumental (INAA)) in the Netherlands and possibly in the world

  2. DOE/NE University Program in robotics for advanced reactors

    International Nuclear Information System (INIS)

    The US Department of Energy has provided support to four universities and the Oak Ridge National Laboratory in order to pursue research leading to the development and deployment of advanced robotic systems capable of performing tasks that are hazardous to humans, that generate significant occupational radiation exposure, and/or whose execution times can be reduced if performed by an automated system. The goal is to develop a generation of advanced robotic systems capable of economically performing surveillance, maintenance, and repair tasks in nuclear facilities and other hazardous environments. The approach to achieving the program objective is a transition from teleoperation to the capability of autonomous operation within three successive generations of robotic systems. The strategy adopted in order to achieve the program goals in an efficient and timely manner consists in utilizing, and advancing where required, state-of-the-art robotics technology through close interaction between the universities and the manufacturers and operators of nuclear power plants. There is a potentially broad range of applications for the robotic systems developed in the course of this project. Therefore, it is expected that efforts to obtain additional support from other agencies, e.g., DOD and NASA, will be successful. Areas of cooperation with other nations (e.g., Japan, France, Germany) are being explored. This Program features a unique teaming arrangement among the Universities of Florida, Michigan, Tennessee, Texas, and the Oak Ridge National Laboratory, and their industrial partners, Odetics, Gulf State Utilities, Florida Power and Light Company, Remotec, and Telerobotics International

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

    International Nuclear Information System (INIS)

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

  4. Structural biology facilities at Brookhaven National Laboratory`s high flux beam reactor

    Energy Technology Data Exchange (ETDEWEB)

    Korszun, Z.R.; Saxena, A.M.; Schneider, D.K. [Brookhaven National Laboratory, Upton, NY (United States)

    1994-12-31

    The techniques for determining the structure of biological molecules and larger biological assemblies depend on the extent of order in the particular system. At the High Flux Beam Reactor at the Brookhaven National Laboratory, the Biology Department operates three beam lines dedicated to biological structure studies. These beam lines span the resolution range from approximately 700{Angstrom} to approximately 1.5{Angstrom} and are designed to perform structural studies on a wide range of biological systems. Beam line H3A is dedicated to single crystal diffraction studies of macromolecules, while beam line H3B is designed to study diffraction from partially ordered systems such as biological membranes. Beam line H9B is located on the cold source and is designed for small angle scattering experiments on oligomeric biological systems.

  5. The Los Alamos universe: Using multimedia to promote laboratory capabilities

    Energy Technology Data Exchange (ETDEWEB)

    Kindel, J.

    2000-03-01

    This project consists of a multimedia presentation that explains the technological capabilities of Los Alamos National Laboratory. It takes the form of a human-computer interface built around the metaphor of the universe. The project is intended promote Laboratory capabilities to a wide audience. Multimedia is simply a means of communicating information through a diverse set of tools--be they text, sound, animation, video, etc. Likewise, Los Alamos National Laboratory is a collection of diverse technologies, projects, and people. Given the ample material available at the Laboratory, there are tangible benefits to be gained by communicating across media. This paper consists of three parts. The first section provides some basic information about the Laboratory, its mission, and its needs. The second section introduces this multimedia presentation and the metaphor it is based on along with some basic concepts of color and user interaction used in the building of this project. The final section covers construction of the project, pitfalls, and future improvements.

  6. 77 FR 27487 - License Amendment Request From The State University of New York, University of Buffalo Reactor...

    Science.gov (United States)

    2012-05-10

    ... accordance with the NRC E-Filing rule (72 FR 49139, August 28, 2007). The E-Filing process requires... COMMISSION License Amendment Request From The State University of New York, University of Buffalo Reactor....resource@nrc.gov . The University of Buffalo Decommissioning Plan and License Amendment Request...

  7. Gas-cooled reactor application for a university campus

    International Nuclear Information System (INIS)

    Large urban areas with unfavourable topographic and meteorological conditions suffer severe air pollution during the winter months. Use of low grade lignites, imported higher quality coal or imported fuel oil are the sources of air pollution in the form of sulphur dioxide, fly ash and soot. Large housing complexes or old and historical locations within the city are in need of pollution free centralized district heating systems. Natural gas imported from the Soviet Union is a solution for this problem. Lack of gas distribution network for high pressure gas within the city is the main bottle-neck for the heating systems utilizing natural gas. Concern of the safety of flammable high pressure gas circulating within the city is another drawback for the natural gas heating systems. Nuclear district heating is an environmentally viable option worth looking into it. Localized urban nuclear heating is an interesting solution for large urban areas with old and historical character. The results of a feasibility study on the HGR application for the Hacettepe University presented here, summarizes the concept of gas-cooled heating reactors specially designed for urban centers. The inherently safe characteristics of the pebble bed heating reactor makes localized urban nuclear heating a viable alternative to other heat sources. An economical analysis of various heat sources with equal power levels is done for the Beytepe campus of Hacettepe University in Ankara. Under special boundary conditions, the price for heat generation can be much lower for nuclear heating with GHR 20 than for hard coal or fuel oil. It is also possible that if the price escalation rate for natural gas exceeds 3%, then nuclear heating with GHR can be more competitive. It is concluded that the nuclear heating of Beytepe campus with a GHR 20 is feasible and economical. (author) 3 figs., 5 refs

  8. Ten years of TRIGA reactor research at the University of Texas

    International Nuclear Information System (INIS)

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

  9. Combined Reactor and Microelectrode Measurements in Laboratory Grown Biofilms

    DEFF Research Database (Denmark)

    Larsen, Tove; Harremoës, Poul

    1994-01-01

    A combined biofilm reactor-/microelectrode experimental set-up has been constructed, allowing for simultaneous reactor mass balances and measurements of concentration profiles within the biofilm. The system consists of an annular biofilm reactor equipped with an oxygen microelectrode. Experiments...... were carried out with aerobic glucose and starch degrading biofilms. The well described aerobic glucose degradation biofilm system was used to test the combined reactor set-up. Results predicted from known biofilm kinetics were obtained. In the starch degrading biofilm, basic assumptions were tested...

  10. Radioactive waste management in Research Reactor Institute, Kyoto University

    International Nuclear Information System (INIS)

    The joint utilization by the researchers of the universities and others in whole Japan of the reactor facilities in Kyoto University was begun in 1965. The facility for abandoning radioactive waste was constructed in fiscal year 1963, and comprises 500 kg/h vaporization and concentration facility, 2 systems of 5 m3/h flocculation, precipitation and filtration facility, and 2 systems of 5 m3/h ion exchange facility for liquid waste, 50x103 kg pressing capacity, four-column type press for reducing volume of solid waste, and waste store for 400 standard drums. Radioactive Waste Treatment Department was organized, and the stipulations on security and radiation injury prevention were enforced in 1964. Liquid and solid wastes have been accepted since 1964. The radioactivity in discharged water in each year is shown. About 600 m3 of waste liquid has been accepted in one year since 1980. The trust of solid waste treatment to Japan Radioisotope Association has been carried out 51 times. The radioactive waste which is temporarily stored in the waste store is reported. Hereafter, the construction of the facility for storing large finished equipment and the appearance of waste treatment enterprises are desirable. (K.I.)

  11. Unique educational opportunities at the Missouri University research reactor

    International Nuclear Information System (INIS)

    Since the Missouri University Research Reactor (MURR) went critical in 1966, it has been a center where students from many departments conduct their graduate research. In the past three decades, hundreds of graduate students from the MU departments of chemistry, physics, anthropology, nuclear engineering, etc., have received masters and doctoral degrees based on research using neutrons produced at MURR. More recently, the educational opportunities at MURR have been expanded to include undergraduate students and local high school students. Since 1989 MURR has participated in the National Science Foundation-funded Research Experience for Undergraduates (REU) program. As part of this program, undergraduate students from universities and colleges throughout the United States come to MURR and get hands-on research experience during the summer. Another program, started in 1994 by the Nuclear Analysis Program at MURR, allows students from a local high school to conduct a neutron activation analysis (NAA) experiment. We also conduct tours of the center, where we describe the research and educational programs at MURR to groups of elementary school children, high school science teachers, state legislators, professional organizations, and many other groups

  12. Radioactive waste management in Research Reactor Institute, Kyoto University

    Energy Technology Data Exchange (ETDEWEB)

    Shimoura, Kazukuni [Kyoto Univ., Kumatori, Osaka (Japan). Research Reactor Inst.

    1997-02-01

    The joint utilization by the researchers of the universities and others in whole Japan of the reactor facilities in Kyoto University was begun in 1965. The facility for abandoning radioactive waste was constructed in fiscal year 1963, and comprises 500 kg/h vaporization and concentration facility, 2 systems of 5 m{sup 3}/h flocculation, precipitation and filtration facility, and 2 systems of 5 m{sup 3}/h ion exchange facility for liquid waste, 50x10{sup 3} kg pressing capacity, four-column type press for reducing volume of solid waste, and waste store for 400 standard drums. Radioactive Waste Treatment Department was organized, and the stipulations on security and radiation injury prevention were enforced in 1964. Liquid and solid wastes have been accepted since 1964. The radioactivity in discharged water in each year is shown. About 600 m{sup 3} of waste liquid has been accepted in one year since 1980. The trust of solid waste treatment to Japan Radioisotope Association has been carried out 51 times. The radioactive waste which is temporarily stored in the waste store is reported. Hereafter, the construction of the facility for storing large finished equipment and the appearance of waste treatment enterprises are desirable. (K.I.)

  13. Nuclear Reactor Laboratory annual report, fiscal year 1981-1982

    International Nuclear Information System (INIS)

    Information related to the use of the UWNR reactor is presented concerning instructional use by the Nuclear Engineering Department; reactor sharing program; utility personnel training; sample irradiations and neutron activation analysis services; changes in personnel, facility, and procedures; and results of surveillance tests

  14. A nuclear reactor simulator for a teaching laboratory

    International Nuclear Information System (INIS)

    A nuclear reactor simulator is described which has been developed by the Department of Automatics and Telemechanics of the Moscow Engineering Physics Institute to provide students with an insight into and familiarity with the characteristics of a nuclear reactor and its systems through evaluation, manipulation and experimentation. (U.K.)

  15. Neutron Scattering Simulations at the University of Kentucky Accelerator Laboratory

    Science.gov (United States)

    Nguyen, Thienan; Jackson, Daniel; Hicks, S. F.; Rice, Ben; Vanhoy, J. R.

    2015-10-01

    The Monte-Carlo N-Particle Transport code (MCNP) has many applications ranging from radiography to reactor design. It has particle interaction capabilities, making it useful for simulating neutron collisions on surfaces of varying compositions. The neutron flux within the accelerator complex at the University of Kentucky was simulated using MCNP. With it, the complex's capabilities to contain and thermalize 7 MeV neutrons produced via 2H(d,n)3He source reaction to an acceptable level inside the neutron hall and adjoining rooms were analyzed. This will aid in confirming the safety of researchers who are working in the adjacent control room. Additionally, the neutron transport simulation was used to analyze the impact of the collimator copper shielding on various detectors located around the neutron scattering hall. The purpose of this was to attempt to explain any background neutrons that are observed at these detectors. The simulation shows that the complex performs very well with regards to neutron containment and thermalization. Also, the tracking information for the paths taken by the neutrons show that most of the neutrons' lives are spent inside the neutron hall. Finally, the neutron counts were analyzed at the positions of the neutron monitor detectors located at 90 and 45 degrees relative to the incident beam direction. This project was supported in part by the DOE NEUP Grant NU-12-KY-UK-0201-05 and the Donald A. Cowan Physics Institute at the University of Dallas.

  16. Instrumentation upgrade at the Training Reactor of Budapest University

    International Nuclear Information System (INIS)

    After more than 30 years of operation, parts of the instrumentation of the Training Reactor of Budapest University is still working with original circuit boards, components from the 70's. Nowadays, with the convenience of using integrated circuits and computers, it is expectable to change from the old technology to a newer, more up-to-date measurement system, with higher reliability and with services that cannot be made with current instrumentation. Our radiation control system will be soon upgraded to a new, self-developed hightech data acquisition system. Its heart is a microcontroller based, standalone circuit. With this change reliability will dramatically improve due to small number of components, to modular firmware witten in assembly, and to the simple power supply unit. We solved the problem of remote data access (data representation), data archivation, and on-line measurements using ethernet network connection, a linux based database system with automated data upload softwares, and common, off the shelf web browsers. Software reliability was maximized by using only commercial, proven software applications which was tested by million of people. Data security is made by storing collected data on more computers, in more formats (raw text file, database file), updating them minute by minute. Using only local network addresses, encrypted data transfers, and secure connections very good access security is achieved. This way of measurement system development helps us to save time, and to make cheap systems with high flexibility. In my presentation I will show these systems in detail, with all the novel and useful features we made and are using currently at our training reactor. (author)

  17. Hydraulics of laboratory and full-scale upflow anaerobic sludge blanket (UASB) reactors.

    Science.gov (United States)

    Batstone, D J; Hernandez, J L A; Schmidt, J E

    2005-08-01

    Laboratory-scale upflow anaerobic sludge blanket (UASB) reactors are often used as test platforms to evaluate full-scale applications. However, for a given volume specific hydraulic loading rate and geometry, the gas and liquid flows increase proportionally with the cube root of volume. In this communication, we demonstrate that a laboratory-scale reactor had plug-flow hydraulics, while a full-scale reactor had mixed flow hydraulics. The laboratory-scale reactor could be modeled using an existing biochemical model, and parameters identified, but because of computational speed with plug-flow hydraulics, mixed systems are instead recommended for parameter identification studies. Because of the scaling issues identified, operational data should not be directly projected from laboratory-scale results to the full-scale design. PMID:15977253

  18. LOSS-OF-COOLANT ACIDENT SIMULATIONS IN THE NATIONAL RESEARCH UNIVERSAL REACTOR

    Energy Technology Data Exchange (ETDEWEB)

    Bennett, W D; Goodman, R L; Heaberlin, S W; Hesson, G M; Nealley, C; Kirg, L L; Marshall, R K; McNair, G W; Meitzler, W D; Neally, G W; Parchen, L J; Pilger, J P; Rausch, W N; Russcher, G E; Schreiber, R E; Wildung, N J

    1981-02-01

    Pressurized water reactor loss-of-coolant accident (LOCA) phenomena are being simulated with a series of experiments in the U-2 loop of the National Research Universal Reactor at Chalk River, Ontario, Canada. The first of these experiments includes up to 45 parametric thermal-hydraulic tests to establish the relationship among the reflood delay time of emergency coolant, the reflooding rate, and the resultant fuel rod cladding peak temperature. Subsequent experiments establish the fuel rod failure characteristics at selected peak cladding temperatures. Fuel rod cladding pressurization simulates high burnup fission gas pressure levels of modern PWRs. This document contains both an experiment overview of the LOCA simulation program and a review of the safety analyses performed by Pacific Northwest Laboratory (PNL) to define the expected operating conditions as well as to evaluate the worst case operating conditions. The primary intent of this document is to supply safety information required by the Chalk River Nuclear Laboratories (CRNL), to establish readiness to proceed from one test phase to the next and to establish the overall safety of the experiment. A hazards review summarizes safety issues, normal operation and three worst case accidents that have been addressed during the development of the experiment plan.

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

    International Nuclear Information System (INIS)

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

  20. A Radiation Laboratory Curriculum Development at Western Kentucky University

    International Nuclear Information System (INIS)

    We present the latest developments for the radiation laboratory curriculum at the Department of Physics and Astronomy of Western Kentucky University. During the last decade, the Applied Physics Institute (API) at WKU accumulated various equipment for radiation experimentation. This includes various neutron sources (computer controlled d-t and d-d neutron generators, and isotopic 252 Cf and PuBe sources), the set of gamma sources with various intensities, gamma detectors with various energy resolutions (NaI, BGO, GSO, LaBr and HPGe) and the 2.5-MeV Van de Graaff particle accelerator. XRF and XRD apparatuses are also available for students and members at the API. This equipment is currently used in numerous scientific and teaching activities. Members of the API also developed a set of laboratory activities for undergraduate students taking classes from the physics curriculum (Nuclear Physics, Atomic Physics, and Radiation Biophysics). Our goal is to develop a set of radiation laboratories, which will strengthen the curriculum of physics, chemistry, geology, biology, and environmental science at WKU. The teaching and research activities are integrated into real-world projects and hands-on activities to engage students. The proposed experiments and their relevance to the modern status of physical science are discussed.

  1. Annual report of Laboratory of Nuclear Studies, Osaka University, 1980

    International Nuclear Information System (INIS)

    This is the progress report of the research activities in the Laboratory of Nuclear Studies during the period from April, 1980, to March, 1981. The activities were carried out by the OULNS staffs and also by outsiders at the OULNS. In this period, the X-ray astrophysics group, the radiation physics group and the high energy physics group joined the OULNS. The main accelerators in the OULNS are a 110 cm variable energy cyclotron and a 4.7 MeV Van de Graaff machine. The detailed experimental studies on inbeam e-gamma spectroscopy and beta-decay were carried out at two accelerator laboratories. The radiochemistry facility and a mass spectrometer were fully used. The research activities extended to high energy physics by utilizing national facilities, such as a 230 cm cyclotron in the Research Center for Nuclear Physics and a proton synchrotron in the National Laboratory for High Energy Physics. The theoretical studies on elementary particles and nuclear physics were carried out also. It is important that the facilities in the OULNS were used by the outsiders in Osaka University, such as solid state physics group and particle-induced X-ray group. The activities of the divisions of cyclotron, Van de Graaff, high energy physics, accelerator development and nuclear instrumentation, mass spectroscopy, radioisotope, solid state and theoretical physics are reported. (Kako, I.)

  2. Ten-year history of the Nuclear Engineering Research Laboratory, University of Tokyo

    International Nuclear Information System (INIS)

    The objectives of establishing this laboratory were the general researches on nuclear engineering, the education and research of graduate students, and the research cooperation with other research institutes. It was recognized that a laboratory with a nuclear reactor and other large installations must be constructed in other place than central Tokyo, and it was desirable to use various installations in Japan Atomic Energy Research Institute in common. The concept of the laboratory comprises five divisions, namely reactor design technology, reactor equipment technology, reactor chemistry, reactor safety and strong radioactive substance treatment technology. The laboratory started the operation in June, 1967. The nuclear reactor ''Yayoi'' was constructed by Japanese own technology, and only 93% enriched uranium was imported from the U.S. The reactor attained the criticality on April 10, 1971. The organization and the operation of the laboratory are described. The fast neutron source reactor ''Yayoi'', The 35 MeV electron linear accelerator, and the basic experiment setup for nuclear fusion reactor blanket design are the large installations used. The research activities on 19 subjects are reported. Also 31 persons having taken part in the laboratory wrote the memoirs of their activities. (Kako, I.)

  3. An Account of Oak Ridge National Laboratory's Thirteen Research Reactors

    Energy Technology Data Exchange (ETDEWEB)

    Rosenthal, Murray Wilford [ORNL

    2009-08-01

    The Oak Ridge National Laboratory has built and operated 13 nuclear reactors in its 66-year history. The first was the graphite reactor, the world's first operational nuclear reactor, which served as a plutonium production pilot plant during World War II. It was followed by two aqueous-homogeneous reactors and two red-hot molten-salt reactors that were parts of power-reactor development programs and by eight others designed for research and radioisotope production. One of the eight was an all-metal fast burst reactor used for health physics studies. All of the others were light-water cooled and moderated, including the famous swimming-pool reactor that was copied dozens of times around the world. Two of the reactors were hoisted 200 feet into the air to study the shielding needs of proposed nuclear-powered aircraft. The final reactor, and the only one still operating today, is the High Flux Isotope Reactor (HFIR) that was built particularly for the production of californium and other heavy elements. With the world's highest flux and recent upgrades that include the addition of a cold neutron source, the 44-year-old HFIR continues to be a valuable tool for research and isotope production, attracting some 500 scientific visitors and guests to Oak Ridge each year. This report describes all of the reactors and their histories.

  4. Information and education programs at the Washington State University research reactor

    International Nuclear Information System (INIS)

    Tours of the Nuclear Radiation Center are a common activity throughout the year, conducted for University classes, organized tour groups from other universities, private tour groups, and individuals. Increased awareness of nuclear activity and the existence of a research reactor on-campus has led to a heightened interest in reactor operations. The information and education programs at Washington State University have been directed at the individual needs and requirements of diverse interests. (author)

  5. The Vanderbilt University nanoscale science and engineering fabrication laboratory

    Science.gov (United States)

    Hmelo, Anthony B.; Belbusti, Edward F.; Smith, Mark L.; Brice, Sean J.; Wheaton, Robert F.

    2005-08-01

    Vanderbilt University has realized the design and construction of a 1635 sq. ft. Class 10,000 cleanroom facility to support the wide-ranging research mission associated with the Vanderbilt Institute for Nanoscale Science and Engineering (VINSE). By design we have brought together disparate technologies and researchers formerly dispersed across the campus to work together in a small contiguous space intended to foster interaction and synergy of nano-technologies not often found in close proximity. The space hosts a variety of tools for lithographic patterning of substrates, the deposition of thin films, the synthesis of diamond nanostructures and carbon nanotubes, and a variety of reactive ion etchers for the fabrication of nanostructures on silicon substrates. In addition, a separate 911 sq. ft. chemistry laboratory supports nanocrystal synthesis and the investigation of biomolecular films. The design criteria required an integrated space that would support the scientific agenda of the laboratory while satisfying all applicable code and safety concerns. This project required the renovation of pre-existing laboratory space with minimal disruption to ongoing activities in a mixed-use building, while meeting the requirements of the 2000 edition of the International Building Code for the variety of potentially hazardous processes that have been programmed for the space. In this paper we describe how architectural and engineering challenges were met in the areas of mitigating floor vibration issues, shielding our facility against EMI emanations, design of the contamination control facility itself, chemical storage and handling, toxic gas use and management, as well as mechanical, electrical, plumbing, lab security, fire and laboratory safety issues.

  6. The University of Missouri Research Reactor facility can melter system

    International Nuclear Information System (INIS)

    At the University of Missouri Research Reactor (MURR), a waste compacting system for reducing the volume of radioactive aluminum cans has been designed, built and put into operation. In MURR's programs of producing radioisotopes and transmutation doping of silicon, a large volume of radioactive aluminum cans is generated. The Can Melter System (CMS) consists of a sorting station, a can masher, an electric furnace and a gas fired furnace. This system reduces the cans and other radioactive metal into barrels of solid metal close to theoretical density. The CMS has been in operation at the MURR now for over two years. Twelve hundred cu ft of cans and other metals have been reduced into 150 cu ft of shipable waste. The construction cost of the CMS was $4950.84 plus 1680 man hours of labor, and the operating cost of the CMS is $18/lb. The radiation exposure to the operator is 8.6 mR/cu ft. The yearly operating savings is $30,000. 20 figs., 10 tabs

  7. Universal family-focused intervention with young adolescents: effects on health-risking sexual behaviors and STDs among young adults.

    Science.gov (United States)

    Spoth, Richard; Clair, Scott; Trudeau, Linda

    2014-02-01

    Considering the prevalence and consequences of health-risking sexual behaviors (HRSBs) and STDs among young adults, their prevention is a public health priority. Emerging etiological and prevention outcome literatures suggested study of the long-term effects of universal family-focused interventions on young adult HRSBs and STDs. Although earlier studies have demonstrated intervention impact on adolescent substance misuse, no study has examined universal family-focused intervention effects on young adult HRSBs and STDs via reductions in adolescent misuse. Sixth grade students and their families enrolled in 33 rural Midwestern schools were randomly assigned to experimental conditions. Self-report questionnaires provided data at pretest (Ns = 238, 221, and 208 for the Iowa Strengthening Families Program [ISFP], Preparing for the Drug Free Years [PDFY], and control groups, respectively), with seven data points through young adulthood (age 21). In latent growth modeling, three young adult HRSB measures (number of sexual partners, condom use, substance use with sex) and lifetime STDs were specified as distal outcomes mediated by adolescent substance initiation growth factors (average level and rate of change). Results showed that the models fit the data and, except for condom use, there were significant indirect effects, with a higher frequency of significant findings for ISFP. The model additions of direct intervention effects on young adult outcomes generally were not supported, consistent with a model positing that long-term intervention effects on young adult HRSBs and STDs outcomes are indirect. As an indication of the practical significance of long-term effects, analyses revealed relative reduction rates ranging from 6% to 46% for significant outcomes. PMID:23408278

  8. 76 FR 69296 - University of Utah, University of Utah TRIGA Nuclear Reactor, Notice of Issuance of Renewed...

    Science.gov (United States)

    2011-11-08

    ... published in the Federal Register on July 21, 2011 (76 FR 43733-43737). The NRC received no request for a..., 2011 (76 FR 60091-60094), and concluded that renewal of the facility operating license will not have a... COMMISSION University of Utah, University of Utah TRIGA Nuclear Reactor, Notice of Issuance of...

  9. Report on the operation, utilization and technical development of research reactors and Hot Laboratory

    International Nuclear Information System (INIS)

    This is an annual report describing the whole activities of the Division of Research Reactor Operation in fiscal 1974. Main works of the Division are operation and maintenance of JRR-2, JRR-3 and JRR-4, and post-irradiation test at Hot Laboratory. In performance of the works mentioned above, research and development were made in various fields of reactor engineering such as operation and maintenance of reactors, technical management of fuels and coolants, radiation control and irradiation technique, etc. Post-irradiation tests of various fuels and materials were performed at the Hot Laboratory as well as the technical development of test procedures. (auth.)

  10. Request for Naval Reactors Comment on Proposed PROMETHEUS Space Flight Nuclear Reactor High Tier Reactor Safety Requirements and for Naval Reactors Approval to Transmit These Requirements to Jet Propulsion Laboratory

    International Nuclear Information System (INIS)

    The purpose of this letter is to request Naval Reactors comments on the nuclear reactor high tier requirements for the PROMETHEUS space flight reactor design, pre-launch operations, launch, ascent, operation, and disposal, and to request Naval Reactors approval to transmit these requirements to Jet Propulsion Laboratory to ensure consistency between the reactor safety requirements and the spacecraft safety requirements. The proposed PROMETHEUS nuclear reactor high tier safety requirements are consistent with the long standing safety culture of the Naval Reactors Program and its commitment to protecting the health and safety of the public and the environment. In addition, the philosophy on which these requirements are based is consistent with the Nuclear Safety Policy Working Group recommendations on space nuclear propulsion safety (Reference 1), DOE Nuclear Safety Criteria and Specifications for Space Nuclear Reactors (Reference 2), the Nuclear Space Power Safety and Facility Guidelines Study of the Applied Physics Laboratory

  11. DOE/NE University Program in robotics for advanced reactors research

    International Nuclear Information System (INIS)

    The document presents the bimonthly progress reports published during 1990 regarding the US Department of Energy/NE-sponsored research at the University of Tennessee Knoxville under the DOE Robitics for Advanced Reactors Research Grant. Significant accomplishments are noted in the following areas: development of edge-segment based stereo matching algorithm; vision system integration in the CESAR laboratory; evaluation of algorithms for surface characterization from range data; comparative study of data fusion techniques; development of architectural framework, software, and graphics environment for sensor-based robots; algorithms for acquiring tactile images from planer surfaces; investigations in geometric model-based robotic manipulation; investigations of non-deterministic approaches to sensor fusion; and evaluation of sensor calibration techniques. (MB)

  12. The need to address the larger universe of HEU-fueled reactors, including: Critical assemblies, pulsed reactors and propulsion reactors

    International Nuclear Information System (INIS)

    The RERTR program has focused on ending shipments of HEU fuel to research reactors. Highest priority has been given to reactors with steady thermal powers ≥ 1 megawatt. Since the cores of critical assemblies and pulsed reactors can contain huge amounts of HEU, they should be a second focus. Also, since many aging and specialized HEU-fuelled reactors may no longer be needed, more emphasis should be given to initiatives that could assist in their shutdown and decommissioning, including providing access to regional reactors with superior facilities. HEU-fuelled ship-propulsion reactors should also be addressed. Russia's civilian icebreaker reactors are of particular interest because their fuel design is considered less sensitive than that of naval reactor fuel. Moreover, Russia's KLT-40 icebreaker reactor is being adapted for a floating nuclear power plant and LEU icebreaker fuel could be used for converting Russian research reactors such as PIK and SM-3, that operate at power-reactor temperatures. (author)

  13. Annual report on operation, utilization and technical development of research reactors and hot laboratory

    International Nuclear Information System (INIS)

    This report describes the activities of the Department of Research Reactor Operation in fiscal year of 1989. It also presents some technical topics on the reactor operation and utilization in details. The Department is responsible for operation of the research reactors, JRR-2 and JRR-4, and the Hot Laboratory. The research reactor JRR-3 was reconstructed to enhance the performance for utilization. The first criticality was achieved on March 22, 1989, and it subsequently went into operation. In connection with the reactor operation, the various research and development activities in the area of fuel management, water chemistry, radiation monitoring and material irradiation have been made. In the Hot Laboratory, post-irradiation examinations of fuels and materials have been carried out along with the development of related techniques. (author)

  14. Annual report on operation, utilization and technical development of research reactors and hot laboratory

    International Nuclear Information System (INIS)

    This report covers the activities of the Department of Research Reactor Operation in fiscal 1988. It also presents some technical topics on the reactor operation and utilization in details. The Department is responsible for operation of the research reactors, JRR-2 and JRR-4, and the Hot Laboratory. The research reactor JRR-3 is now under reconstruction to enhance the performance for utilization. In connection with the reactor operation, the various research and development activities in the area of fuel management, water chemistry, radiation monitoring and material irradiation have been made. In the Hot Laboratory, post-irradiation examinations of fuels and materials have been carried out along with the development of related techniques. (author)

  15. Operation and utilization experience of UTR-KINKI, a low flux university research reactor

    International Nuclear Information System (INIS)

    Kinki University Reactor, UTR-KINKI, is the first and smallest university reactor in Japan. Since 1961, it had been operated at 0.1 W for the first 13 years mainly for teaching and training of university student. It increased its power to 1.0 W in 1974 and thereafter has been operated both for educational and research purposes. General uses of UTR-KINKI are teaching and training of university student, miscellaneous reactor physics experiments, reactor noise analysis, irradiation of wide variety of samples including small animals and maggots of drosophia, neutron radiography, radio-chemistry, radiation chemistry and activation analysis. At present time, it is being operated about 40 days for educational purposes and about 70 days for miscellaneous research uses for one year. Besides these, it has been operated since 1981 for about 80 days per year for visiting researchers from other universities all over Japan. (author)

  16. Preparation for shipment of spent TRIGA fuel elements from the research reactor of the Medical University of Hannover

    International Nuclear Information System (INIS)

    In the early seventies a research reactor of type TRIGA Mark I was installed in the Department of Nuclear Medicine at the Medical University of Hannover (MHH) for the production of isotopes with short decay times for medical use. Since new production methods have been developed, the reactor has become obsolete and the MHH decided to decommission it. Probably in the second quarter of 1999 all 76 spent TRIGA fuel elements will be shipped to Idaho National Engineering and Environmental Laboratory (INEEL), USA, in one cask of type GNS 16. Due to technical reasons within the MHH a special Mobile Transfer System, which is being developed by the company Noell-KRC, will be used for reloading the fuel elements and transferring them from the reactor to the cask GNS 16. A description of the main components of this system as well as the process for transferring the fuel elements follows. (author)

  17. Preparation for shipment of spent TRIGA fuel elements from the research reactor of the Medical University of Hannover

    Energy Technology Data Exchange (ETDEWEB)

    Hampel, Gabriele; Cordes, Harro [Medical University of Hannover, D-30625 Hannover (Germany); Ebbinghaus, Kurt; Haferkamp, Dirk [NOELL-KRC, D-97064 Wuerzburg (Germany)

    1998-07-01

    In the early seventies a research reactor of type TRIGA Mark I was installed in the Department of Nuclear Medicine at the Medical University of Hannover (MHH) for the production of isotopes with short decay times for medical use. Since new production methods have been developed, the reactor has become obsolete and the MHH decided to decommission it. Probably in the second quarter of 1999 all 76 spent TRIGA fuel elements will be shipped to Idaho National Engineering and Environmental Laboratory (INEEL), USA, in one cask of type GNS 16. Due to technical reasons within the MHH a special Mobile Transfer System, which is being developed by the company Noell-KRC, will be used for reloading the fuel elements and transferring them from the reactor to the cask GNS 16. A description of the main components of this system as well as the process for transferring the fuel elements follows. (author)

  18. Decommissioning Experience: Ames Laboratory Research Reactor, United States of America

    International Nuclear Information System (INIS)

    Full text: One of the earliest decommissioning projects was the dismantling of the small research reactor at Richland, in the United States of America, completed in 1982. The pool was lined with stainless steel embedded in grout on the walls and floor. This was all cut away, and the pool was released as substantially clean. However, the site remained as a controlled area because of some low level contamination in the reactor building. The cost was given as US $4.3 million. The whole decommissioning project took from 1977 to 1981. (author)

  19. Students' Assessment of Interactive Distance Experimentation in Nuclear Reactor Physics Laboratory Education

    Science.gov (United States)

    Malkawi, Salaheddin; Al-Araidah, Omar

    2013-01-01

    Laboratory experiments develop students' skills in dealing with laboratory instruments and physical processes with the objective of reinforcing the understanding of the investigated subject. In nuclear engineering, where research reactors play a vital role in the practical education of students, the high cost and long construction time of…

  20. Kyushu University Tandem Accelerator Laboratory report, 1988-1990

    International Nuclear Information System (INIS)

    Ten years have elapsed since the first beam was obtained from the Kyushu University tandem accelerator. Although the laboratory has achieved successful scientific results, the performance of the accelerator has been on a decline mainly due to the aging. In the last two and a half years, the tandem accelerator has suffered from the fall of terminal voltage to around 8 MV. However, the experimental studies in the laboratory have been active. The utilization of the polarized beams of protons and deuterons to study the scattering of the p+d system, the use of heavy ion beam for the systematic search for the molecular resonance in relatively heavy systems and for the study on reaction mechanism, the use of both light and heavy ion beams for the studies on nuclear engineering, material science and geological science and so on were carried out. The gamma ray spectroscopic study on the state near yrast line was largely hampered by the accelerator troubles, instead, the collaboration with the Niels Bohr Institute provided a wonderful research ground for the studies. (K.I.)

  1. Science and production laboratories: integration between the industry and universities

    International Nuclear Information System (INIS)

    Industry laboratories provide students with an opportunity to resolve real serious tasks and be exposed to a wide range of professional activities. Staffing in the Russian nuclear industry is a serious concern. There is a shortage of experienced specialists, and it is impossible to train a replacement for them quickly. Creation of a true professional is a long and thorough process, whereby the amount of knowledge and experience very slowly transforms into quality of performance. The authors underline that the teacher of a modern technical university should not and must not act as a middle man between the textbook and the students. The teacher must instead become a holder of the latest technological knowledge, which he will pass to students during lessons. The authors report on the ERGOLAB, a problematic science and research laboratory for ergonomic research and development in the nuclear field. Ergonomic support is one of the more important factors in the prevention of human errors, maintenance of professional health and improvement of performance efficiency

  2. Association Euratom - Risø National Laboratory, Technical University of Denmark - Annual Progress Report 2007

    DEFF Research Database (Denmark)

    Michelsen, Poul; Korsholm, Søren Bang; Juul Rasmussen, Jens

    The programme of the Research Unit of the Fusion Association Euratom - Risø National Laboratory, Technical University of Denmark, covers work in fusion plasma physics and in fusion technology. The fusion plasma physics research focuses on turbulence and transport, and its interaction with the pla......The programme of the Research Unit of the Fusion Association Euratom - Risø National Laboratory, Technical University of Denmark, covers work in fusion plasma physics and in fusion technology. The fusion plasma physics research focuses on turbulence and transport, and its interaction...... with the plasma equilibrium and particles. The effort includes both first principles based modelling, and experimental observations of turbulence and of fast ion dynamics by collective Thomson scattering. The activities in technology on investigations of radiation damage of fusion reactor materials have been...... phased out during 2007. Minor activities are system analysis, initiative to involve Danish industry in ITER contracts and public information. A summary is presented of the results obtained in the Research Unit during 2007....

  3. Involvement of students and postgraduates into megagrant laboratory under supervision of leading scientist Romeo Ortega at ITMO University*

    Directory of Open Access Journals (Sweden)

    Kremlev Artem

    2016-01-01

    Full Text Available In 2010 the Government of the Russian Federation established particularly large grants aimed to attract world-renowned scientists, including compatriots living abroad, to Russian scientific and educational centres. These grants, known as Megagrants, ensure the creation of research teams that can compete with the leading world laboratories and achieve world-class scientific results. Involvement of young Russian scientists in the projects became one of the main Megagrant features: half of the participants are people under the age of 35 years. Founded as a part of this project in ITMO University the laboratory “Nonlinear Adaptive Control Systems” under Romeo Ortega’s leadership is described in the paper. This laboratory was created at the Department of Control Systems and Informatics. The priority of the laboratory is the preparation and formation of a stable team able to conduct advanced research in the field of nonlinear, adaptive and robust control of various technical objects.

  4. Data base of reactor physics experimental results in Kyoto University critical assembly experimental facilities

    International Nuclear Information System (INIS)

    The Kyoto University critical assembly experimental facilities belong to the Kyoto University Research Reactor Institute, and are the versatile critical assembly constructed for experimentally studying reactor physics and reactor engineering. The facilities are those for common utilization by universities in whole Japan. During more than ten years since the initial criticality in 1974, various experiments on reactor physics and reactor engineering have been carried out using many experimental facilities such as two solidmoderated cores, a light water-moderated core and a neutron generator. The kinds of the experiment carried out were diverse, and to find out the required data from them is very troublesome, accordingly it has become necessary to make a data base which can be processed by a computer with the data accumulated during the past more than ten years. The outline of the data base, the data base CAEX using personal computers, the data base supported by a large computer and so on are reported. (Kako, I.)

  5. Athletics for children and young people: a university extension project

    OpenAIRE

    Aline Gomes; Sara Matthiesen; Guy Ginciene

    2011-01-01

    The extension project "Athletics for children and young people" which has been developed at Unesp-Rio Claro since 1999, had, in 2008, the objective of promoting, among students of the community, different experiences in the athletics field, with emphasis on regular classes, pictures exhibition and visit to the athletic track. These activities have provided among other things a greater knowledge about the athletics and different experiences such as games and specific competitions contributing ...

  6. Work as representation: the view of young university students

    OpenAIRE

    Sidinei Rocha de Oliveira; Valmiria Carolina Piccinini; Cássia da Silva Silveira

    2010-01-01

    One period of particular importance in the relation of the individual to the world of work is the transition from youth to adulthood, when, among other modifications (biological, psychological and social), entry into the job market has a fundamental role, marking a new stage of life. Hence, this study seeks to analyse which social representations are present in the speech of young students of a Management course with regard their understanding of the “work”. For this purpose, 120 ...

  7. An evaluation of alternative reactor vessel cutting technologies for the experimental boiling water reactor at Argonne National Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Boing, L.E.; Henley, D.R. (Argonne National Lab., IL (USA)); Manion, W.J.; Gordon, J.W. (Nuclear Energy Services, Inc., Danbury, CT (USA))

    1989-12-01

    Metal cutting techniques that can be used to segment the reactor pressure vessel of the Experimental Boiling Water Reactor (EBWR) at Argonne National Laboratory (ANL) have been evaluated by Nuclear Energy Services. Twelve cutting technologies are described in terms of their ability to perform the required task, their performance characteristics, environmental and radiological impacts, and cost and schedule considerations. Specific recommendations regarding which technology should ultimately be used by ANL are included. The selection of a cutting method was the responsibility of the decommissioning staff at ANL, who included a relative weighting of the parameters described in this document in their evaluation process. 73 refs., 26 figs., 69 tabs.

  8. An evaluation of alternative reactor vessel cutting technologies for the experimental boiling water reactor at Argonne National Laboratory

    International Nuclear Information System (INIS)

    Metal cutting techniques that can be used to segment the reactor pressure vessel of the Experimental Boiling Water Reactor (EBWR) at Argonne National Laboratory (ANL) have been evaluated by Nuclear Energy Services. Twelve cutting technologies are described in terms of their ability to perform the required task, their performance characteristics, environmental and radiological impacts, and cost and schedule considerations. Specific recommendations regarding which technology should ultimately be used by ANL are included. The selection of a cutting method was the responsibility of the decommissioning staff at ANL, who included a relative weighting of the parameters described in this document in their evaluation process. 73 refs., 26 figs., 69 tabs

  9. Report of the research results with University of Tokyo, Nuclear Engineering Research Laboratory's Facilities in fiscal 1986

    International Nuclear Information System (INIS)

    This book contains a large number of reports of studies made in 1986 through joint utilization of the nuclear reactor 'Yayoi' and electron beam type accelerator which are installed in the Nuclear engineering Research Laboratory, Faculty of Engineering, University of Tokyo. The reports presented deal with 'Behaviors of Neutrons in Fast Reactor Blanket Shield', 'Effect of Fast Neutron Radiation on Organic Materials', 'Production and Recovery of Tritium in Nuclear Fusion Reactor Blanket System', 'Bench Mark Experiment of Effect of Atmospheric Scattering of Neutron', 'Experimental Evaluation of Nuclear Heat Rate', 'Fast Neutron Shielding Experiment', 'Effect of Fast Neutron Radiation on Hot Water', 'Neutron Shielding Experiment', 'Biological and Medical Application of 'Yayoi' Neutron', 'Effect of Fission-Fusion Correlation Radiation on Semiconductors (Si, GaAs)', 'Application of Fast Neutron to Radiography Technology', 'Streaming in Offset Slit', 'Design and Evaluation of New Reactor', 'LET Effect on Organic Material', 'Handling, Separation and Recovery of Transuranium Elements', 'Reactor Operation Support System Using Knowledge Engineering Technique', 'Application of Shape Memory Alloys to Nuclear Reactor Devices', 'Numerical Simulation of Turbulent Hear Transfer', and many other studies. (Nogami, K.)

  10. NO2 Catalytic Decomposition - from Laboratory Experiment to Industry Reactor

    Czech Academy of Sciences Publication Activity Database

    Obalová, L.; Jirátová, Květa; Kovanda, F.

    Kraków : Wydawnictwo Uniwersitetu Jagiellonskiego, 2011, s. 97. ISBN 978-83-233-3249-7. [International Symposium on Nitrogen Oxides Emission Abatement NOEA 2011. Zakopane (PL), 04.09.2011-07.09.2011] R&D Projects: GA TA ČR TA01020336 Institutional research plan: CEZ:AV0Z40720504 Keywords : catalytic decomposition of CO2 * reactor * kinetic data Subject RIV: CI - Industrial Chemistry, Chemical Engineering

  11. Verification of the MCNP model for the University of Texas TRIGA reactor

    International Nuclear Information System (INIS)

    An MCNP model of The University of Texas TRIGA reactor has been used for design calculations for the neutron collimator system in the through beam port. The TRIGA MCNP model was verified by comparing its results with experimentally determined values

  12. Introduction to the status of reactor physics education in Tsinghua University

    International Nuclear Information System (INIS)

    This paper introduces the general situation of reactor physics education in Tsinghua University, including its history, the course series of the undergraduates and graduates and the reactor physics experiment education. This paper also simply introduces the students studying in nuclear engineering field and other nuclear engineering related courses. (author)

  13. URI Program Final Report FY 2001 Grant for the University of Florida Training Reactor

    International Nuclear Information System (INIS)

    The purpose of the URI program is to upgrade and improve university nuclear research and training reactors and to contribute to strengthening the academic community's nuclear engineering infrastructure. It should be noted that the proposed UFTR facility instrumentation and equipment can generally be subdivided into three categories: (1) to improve reactor operations, (2) to improve existing facility/NAA Laboratory operations, and (3) to expand facility capability. All of these items were selected recognizing the objectives of the University Reactor Instrumentation Program to respond to the widespread needs in the academic reactor community for modernization and improvement of research and training reactor facilities, especially at large and diverse institutions such as the University of Florida. These needs have been particularly pressing at the UFTR which is the only such research and training reactor in the State of Florida which is undergoing rapid growth in a variety of technical areas. As indicated in Table 2, the first item is a security system control panel with associated wiring and detectors. The existing system is over 30 years old and has been the subject of repeated maintenance over the past 5 years. Some of its detection devices are no longer replaceable from stock. Modifications made many years ago make troubleshooting some parts of the system such as the backup battery charging subsystem essentially impossible, further increasing maintenance frequency to replace batteries. Currently, various parts of the system cable trays remain open for maintenance access further degrading facility appearance. In light of relicensing plans, this item is also a key consideration for housekeeping appearance considerations. The cost of a replacement ADEMCO Vista 20 security system including turnkey installation by a certified vendor was to be $2,206. Replacement of this system was expected to save up to 5 days of maintenance per year, decrease security alarm response

  14. Conversion and standardization of university reactor fuels using low-enrichment uranium: Plans and schedules

    Energy Technology Data Exchange (ETDEWEB)

    Young, H.H.; Brown, K.R.; Matos, J.E.

    1986-01-01

    The highly-enriched uranium (HEU) fuel used in twenty United States university reactors can be viewed as contributing to the risk of theft or diversion of weapons-useable material. To minimize this risk, the US Nuclear Regulatory Commission issued its final rule on ''Limiting the Use of Highly Enriched Uranium in Domestically Licensed Research and Test Reactors,'' in February 1986. This paper describes the plans and schedules developed by the US Department of Energy to coordinate an orderly transition from HEU to LEU fuel in most of these reactors. An important element in the planning process has been the desire to standardize the LEU fuels used in US university reactors and to enhance the performance and utilization of a number of these reactors. The program is estimated to cost about $10 million and to last about five years.

  15. Science Hall of Atomic Energy in Research Reactor Institute, Kyoto University

    International Nuclear Information System (INIS)

    The Science Hall of Atomic Energy was built as a subsidiary facility of the Research Reactor Institute, Kyoto University. The purpose of this facility is to accept outside demands concerning the application of the research reactor. The building is a two story building, and has the floor area of 901.47 m2. There are an exhibition room, a library, and a big lecture room. In the exhibition room, models of the Kyoto University Research Reactor and the Kyoto University Critical Assembly are placed. Various pictures concerning the application of the reactor are on the wall. In the library, people from outside of the Institute can use various books on science. Books for boys and girls are also stocked and used for public use. At the lecture room, various kinds of meeting can be held. (Kato, T.)

  16. Perception of masculinity amongst young Malaysian men: a qualitative study of university students

    OpenAIRE

    Fazli Khalaf, Zahra; Low, Wah Yun; GHORBANI, Behzad; Merghati Khoei, Effat

    2013-01-01

    Background Perception of Masculinity plays an important role in men’s lifestyles and health behaviors. Although, the importance of masculinity has been widely discussed in men’s health literature, very little is known about the meanings of masculinity in the Malaysian setting. This research aimed to explore the meanings of masculinity among Malaysian university men. Methods This qualitative study utilized in-depth interviews with 34 young Malaysian university men, aged 20–30 years from three ...

  17. Irradiated Hardware Characterization and Packaging During Decommissioning of the Ford Nuclear Reactor at University of Michigan

    International Nuclear Information System (INIS)

    Characterization of all irradiated hardware during decommissioning of experimental and research reactors always presents a host of challenges not normally associated with characterization of irradiated hardware from commercial nuclear reactors. The campaign to characterize all of the irradiated hardware from the Ford Nuclear Reactor at the University of Michigan was no exception. The Ford Nuclear Reactor was an MTR pool style reactor that was in continual use up to the point of decommissioning. Some of the unique challenges involved with experimental pool reactors are the lack of symmetry around the core for neutron activation analysis calculations, the large inventory of activated components, the high degree of variability within that inventory, and the packaging of the entire inventory into the most efficient liner combinations. The entire high activity inventory was successfully packaged into two (2) steel fuel pool liners and shipped in two (2) cask shipments. (authors)

  18. Annual report of the Nuclear Physics Laboratory, University of Washington

    International Nuclear Information System (INIS)

    The Nuclear Physics Laboratory of the University of Washington has for over 40 years supported a broad program of experimental physics research. Some highlights of the research activities during the past year are given. Work continues at a rapid pace toward completion of the Sudbury Neutrino Observatory in January 1997. Following four years of planning and development, installation of the acrylic vessel began last July and is now 50% complete, with final completion scheduled for September. The Russian-American Gallium Experiment (SAGE) has completed a successful 51Cr neutrino source experiment. The first data from 8B decay have been taken in the Mass-8 CVC/Second Class Current study. The analysis of the measured barrier distributions for Ca-induced fission of prolate 192Os and oblate 194Pt has been completed. In a collaboration with a group from the Bhabha Atomic Research Centre they have shown that fission anisotropies at energies well above the barrier are not influenced by the mass asymmetry of the entrance channel relative to the Businaro-Gallone critical asymmetry. They also have preliminary evidence at higher bombarding energy that noncompound nucleus fission scales with the mean square angular momentum, in contrast to previous suggestions. The authors have measured proton and alpha particle emission spectra from the decay of A ∼ 200 compound nuclei at excitation energies of 50--100 MeV, and used these measurements to infer the nuclear temperature. The investigations of multiparticle Bose-Einstein interferometry have led to a new algorithm for putting Bose-Einstein and Coulomb correlations of up to 6th order into Monte Carlo simulations of ultra-relativistic collision events, and to a new fast algorithm for extracting event temperatures

  19. Annual report of the Nuclear Physics Laboratory, University of Washington

    Energy Technology Data Exchange (ETDEWEB)

    Snover, K.; Fulton, B. [eds.

    1996-04-01

    The Nuclear Physics Laboratory of the University of Washington has for over 40 years supported a broad program of experimental physics research. Some highlights of the research activities during the past year are given. Work continues at a rapid pace toward completion of the Sudbury Neutrino Observatory in January 1997. Following four years of planning and development, installation of the acrylic vessel began last July and is now 50% complete, with final completion scheduled for September. The Russian-American Gallium Experiment (SAGE) has completed a successful {sup 51}Cr neutrino source experiment. The first data from {sup 8}B decay have been taken in the Mass-8 CVC/Second Class Current study. The analysis of the measured barrier distributions for Ca-induced fission of prolate {sup 192}Os and oblate {sup 194}Pt has been completed. In a collaboration with a group from the Bhabha Atomic Research Centre they have shown that fission anisotropies at energies well above the barrier are not influenced by the mass asymmetry of the entrance channel relative to the Businaro-Gallone critical asymmetry. They also have preliminary evidence at higher bombarding energy that noncompound nucleus fission scales with the mean square angular momentum, in contrast to previous suggestions. The authors have measured proton and alpha particle emission spectra from the decay of A {approximately} 200 compound nuclei at excitation energies of 50--100 MeV, and used these measurements to infer the nuclear temperature. The investigations of multiparticle Bose-Einstein interferometry have led to a new algorithm for putting Bose-Einstein and Coulomb correlations of up to 6th order into Monte Carlo simulations of ultra-relativistic collision events, and to a new fast algorithm for extracting event temperatures.

  20. Report on operation utilization and technical development of research reactors and hot laboratory

    International Nuclear Information System (INIS)

    Activities of the Division of Research Reactor Operation in fiscal 1980 are described. The division is responsible for operation and maintenance of JRR-2, JRR-3, JRR-4 and Hot Laboratory. In the above connection, various other works are performed, including technical management of fuel and coolant, radiation control, irradiation technique, etc. In Hot Laboratory, postirradiation examinations of fuels and materials are made, and also development of examination methods. (author)

  1. Report on operation, utilization and technical development of research reactors and hot laboratory

    International Nuclear Information System (INIS)

    Activities of the Division of Research Reactor Operation in fiscal 1979 are described. The division is responsible for operation and maintenance of JRR-2, JRR-3, JRR-4 and Hot Laboratory. In the above connection, various other works are performed, including technical management of fuel and coolant, radiation control, irradiation technique, etc. In Hot Laboratory, postirradiation examinations of fuels and materials are made, and also development of examination methods. (author)

  2. Operational Experience On Ageing Management At The TRIGA Research Reactor Of LENA (Laboratory of Applied Nuclear Energy) - Univ. of Pavia (Italy) -

    International Nuclear Information System (INIS)

    The Laboratory of Applied Nuclear Energy ('LENA') of the University of Pavia operates, since 1965, a 250 kW TRIGA Mark II nuclear research reactor providing training and services to private enterprises and public institutions as well as being involved in several research projects carried out by the University and other research groups. Being an almost fifty years old facility, ageing, together with its potential premature failures, is a key point in the reactor safety. For these reason, in order to mitigate ageing effects, the facility has had to deal with several issues due to the time-dependent degradation of its structures, systems and components (SSCs). After an accurate assessment of SSCs conditions and the identification of ageing mechanisms, during the past years, several activities were successfully carried out. The paper will provide an overview of the above-mentioned topics and the forthcoming plans, together with lessons learned on ageing management in a small-sized reactor facility

  3. Report of the research results with University of Tokyo, Nuclear Engineering Research laboratory's Facilities in fiscal 1992

    International Nuclear Information System (INIS)

    This publication summarizes the results of the joint utilization of the research 'Yayoi' and the electron beam accelerator in the Nuclear Engineering Research Laboratory, University of Tokyo, in the fiscal year 1992. The Yayoi was operated smoothly through the year, and the number of research themes, for which the reactor Yayoi was jointly utilized and the related themes reached 23 cases. The research themes of the linac count up to 17, after its reconstruction to be twin-linac. In this publication, in addition to the utilization reports, also the 16 reports of Yayoi Study Meetings held in fiscal year 1992 are collected. (J.P.N.)

  4. Sperm counts may have declined in young university students in Southern Spain

    DEFF Research Database (Denmark)

    Mendiola, Jaime; Jørgensen, Niels; Mínguez-Alarcón, Lidia;

    2013-01-01

    Several studies have investigated temporal trends in semen quality in Northern Europe, but none has examined this question in Southern Europe. A prior study conducted in Almeria Province (Southern Spain) reported higher sperm count and concentration among Spanish young men recruited from 2001 to...... 2002 compared with young men from Northern Europe. The aim of this new study was to examine whether semen quality has changed among Spanish young men in the last decade. In this cross-sectional study, questionnaires and semen samples were collected from 215 healthy young university students from Murcia...... Region between 2010 and 2011. The 273 men from the Almeria study previously studied were included in a trend analysis of the two populations from Southern Spain. Descriptive statistics were calculated for the Murcia study population and these and semen variables for the Murcia and Almeria study...

  5. Surprise Discovery of Highly Developed Structure in the Young Universe

    Science.gov (United States)

    2005-03-01

    ESO-VLT and ESA XMM-Newton Together Discover Earliest Massive Cluster of Galaxies Known Summary Combining observations with ESO's Very Large Telescope and ESA's XMM-Newton X-ray observatory, astronomers have discovered the most distant, very massive structure in the Universe known so far. It is a remote cluster of galaxies that is found to weigh as much as several thousand galaxies like our own Milky Way and is located no less than 9,000 million light-years away. The VLT images reveal that it contains reddish and elliptical, i.e. old, galaxies. Interestingly, the cluster itself appears to be in a very advanced state of development. It must therefore have formed when the Universe was less than one third of its present age. The discovery of such a complex and mature structure so early in the history of the Universe is highly surprising. Indeed, until recently it would even have been deemed impossible. PR Photo 05a/05: Discovery X-Ray Image of the Distant Cluster (ESA XMM-Netwon) PR Photo 05b/05: False Colour Image of XMMU J2235.3-2557 (FORS/VLT and ESA XMM-Newton) Serendipitous discovery ESO PR Photo 05a/05 ESO PR Photo 05a/05 Discovery X-Ray Image of the Distant Cluster (ESA XMM-Newton) [Preview - JPEG: 400 x 421 pix - 106k] [Normal - JPEG: 800 x 842 pix - 843k] [Full Res - JPEG: 2149 x 2262 pix - 2.5M] Caption: ESO PR Photo 05a/05 is a reproduction of the XMM-Newton observations of the nearby active galaxy NGC7314 (bright object in the centre) from which the newly found distant cluster (white box) was serendipitously identified. The circular field-of-view of XMM-Newton is half-a-degree in diameter, or about the same angular size as the Full Moon. The inset shows the diffuse X-ray emission from the distant cluster XMMU J2235.3-2557. Clusters of galaxies are gigantic structures containing hundreds to thousands of galaxies. They are the fundamental building blocks of the Universe and their study thus provides unique information about the underlying architecture of the

  6. Review of Army Research Laboratory Programs for Historically Black Colleges and Universities and Minority Institutions

    Science.gov (United States)

    National Academies Press, 2014

    2014-01-01

    "Review of Army Research Laboratory Programs for Historically Black Colleges and Universities and Minority Institutions" examines the ways in which historically black colleges and universities and minority institutions have used the Army Research Laboratory (ARL) funds to enhance the science, technology, engineering, and mathematics…

  7. Radiological survey support activities for the decommissioning of the Ames Laboratory Research Reactor Facility, Ames, Iowa

    International Nuclear Information System (INIS)

    At the request of the Engineering Support Division of the US Department of Energy-Chicago Operations Office and in accordance with the programmatic overview/certification responsibilities of the Department of Energy Environmental and Safety Engineering Division, the Argonne National Laboratory Radiological Survey Group conducted a series of radiological measurements and tests at the Ames Laboratory Research Reactor located in Ames, Iowa. These measurements and tests were conducted during 1980 and 1981 while the reactor building was being decontaminated and decommissioned for the purpose of returning the building to general use. The results of these evaluations are included in this report. Although the surface contamination within the reactor building could presumably be reduced to negligible levels, the potential for airborne contamination from tritiated water vapor remains. This vapor emmanates from contamination within the concrete of the building and should be monitored until such time as it is reduced to background levels. 2 references, 8 figures, 6 tables

  8. Analyses in support of the Laboratory Microfusion Facility and ICF commercial reactor designs

    International Nuclear Information System (INIS)

    Our work on this contract was divided into two major categories; two thirds of the total effort was in support of the Laboratory Microfusion Facility (LMF), and one third of the effort was in support of Inertial Confinement Fusion (ICF) commercial reactors. This final report includes copies of the formal reports, memoranda, and viewgraph presentations that were completed under this contract

  9. Radiation chemistry in the nuclear power reactor environment: from laboratory study to practical application

    International Nuclear Information System (INIS)

    This paper discusses the work carried out at the Chalk River Nuclear Laboratories in underlying and applied radiation chemical research performed to optimise the processes occurring in the four aqueous systems in and around the core. The aqueous systems subject to radiolysis in CANDU reactors are Heat Transport System, Moderator, Liquid Zone Controls and End Shields.

  10. Decontamination and decommissioning of the JANUS reactor at the Argonne National Laboratory-East site

    International Nuclear Information System (INIS)

    Argonne National Laboratory has begun the decontamination and decommissioning (D ampersand D) of the JANUS Reactor Facility. The project is managed by the Technology Development Division's D ampersand D Program personnel. D ampersand D procedures are performed by sub-contractor personnel. Specific activities involving the removal, size reduction, and packaging of radioactive components and facilities are discussed

  11. University Reactor Instrumentation Program. Final report, September 30, 1993--March 31, 1996

    International Nuclear Information System (INIS)

    The University of Massachusetts Lowell Research Reactor has received a total of $115,723.00 from the Department of Energy (DOE) Instrumentation Program (DOE Grant No. DE-FG02-91ID13083) and $40,000 in matching funds from the University of Massachusetts Lowell administration. The University of Massachusetts Lowell Research Reactor has been serving the University and surrounding communities since it first achieved criticality in May 1974. The principle purpose of the facility is to provide a multidisciplinary research and training center for the University of Massachusetts Lowell and other New England academic institutions. The facility promotes student and industrial research, in addition to providing education and training for nuclear scientists, technicians, and engineers. The 1 MW thermal reactor contains a variety of experimental facilities which, along with a 0.4 megacurie cobalt source, effectively supports the research and educational programs of many university departments including Biology, Chemistry, Nuclear and Plastics Engineering, Radiological Sciences, Physics, and other campuses of the University of Massachusetts system. Although the main focus of the facility is on intra-university research, use by those outside the university is fully welcomed and highly encouraged

  12. A Multi-Phased Sampling Effort to Characterize a University TRIGA Research Reactor

    International Nuclear Information System (INIS)

    A radiological characterization project was conducted at the University of Illinois (University) TRIGA research nuclear reactor in July 2005 as part of the long-term facility decommissioning project. The characterization effort included multiple survey and sampling techniques designed to assess both contamination of the reactor building and equipment and activation of reactor components and the reactor bio-shield. Radiation measurements included alpha and beta surface contamination measurements, gamma dose rate measurements, and gross gamma radiation measurements. Modeling was conducted based on the field measurements to predict concentrations of activation products in reactor components that were not directly sampled. The sampling effort included collecting removable contamination swipes, concrete samples from the reactor room floor and bio-shield, soil samples from below and around the perimeter of the reactor building, graphite samples from graphite moderator, and metal samples from reactor components. Concrete samples were obtained using an innovative technology that allowed for quick sample collection and analysis. Concrete, soil, graphite, and metal samples were analyzed on-site using liquid scintillation counters and gamma spectroscopy. Additional samples were sent off-site for analysis. (authors)

  13. Sludge combustion in fluidized bed reactors at laboratory scale

    International Nuclear Information System (INIS)

    The combustion of a dried sewage sludge in laboratory scale fluidized bed has been studied in Naples by the Istituto di ricerche sulla combustione (Irc) in the framework of a National project named Thermal Process with Energy Recovery to be used in laboratory and pre-pilot scale apparatus. The attention has been focused on emissions of unreacted carbon as elutriated fines, on the emissions of pollutant gases and on the assessment of the inventory of fly- and bottom ashes. The combustion behaviour of sewage sludge has been compared with those of a market available Tyre Derived Fuel (TDF) and a biomass from Mediterranean area (Robinia Pseudoacacia) and with that of a South African bituminous coal. Stationary combustion tests were carried out at 8500 C by feeding particles in the size range 0-1 mm into a bed of silica sand without any sorbent addition. The fluidized bed combustor has been operated, at a superficial gas velocity of 0.4 m/s and different excesses of air ranging between 14 and 98%. Relatively high combustion efficiency, larger than 98.9% has been obtained in experiments carried out with sewage sludge and excess of air larger than 20%. These values, are comparable with those obtained in previously experimental activity carried out under similar operative conditions with a South Africa Bituminous coal (97-98%). It is larger than those obtained by using a Tyre Derived Fuel (89-90%) and the Robinia Pseudoacacia Biomass (93-93%). The relative importance of carbon fines elutriation, CO emissions and volatile bypassing the bed in determining the loss of combustion efficiency has been evaluated for the different fuels tested

  14. Decontamination and dismantlement of the JANUS Reactor at Argonne National Laboratory-East. Project final report

    International Nuclear Information System (INIS)

    The decontamination and dismantlement of the JANUS Reactor at Argonne National Laboratory-East (ANL-E) was completed in October 1997. Descriptions and evaluations of the activities performed and analyses of the results obtained during the JANUS D and D Project are provided in this Final Report. The following information is included: objective of the JANUS D and D Project; history of the JANUS Reactor facility; description of the ANL-E site and the JANUS Reactor facility; overview of the D and D activities performed; description of the project planning and engineering; description of the D and D operations; summary of the final status of the JANUS Reactor facility based upon the final survey results; description of the health and safety aspects of the project, including personnel exposure and OSHA reporting; summary of the waste minimization techniques utilized and total waste generated by the project; and summary of the final cost and schedule for the JANUS D and D Project

  15. Decontamination and decommissioning preparation of Oak Ridge National Laboratory research reactors

    International Nuclear Information System (INIS)

    During the past seven years, four research reactors at Oak Ridge National Laboratory (ORNL) have been shut down by the US Department of Energy (DOE) because of a lack of funding and mission. Before the reactors are eligible to receive DOE funding for decontamination and decommissioning (D and D), certain preparations are required, including resolution of significant environmental concerns. This paper describes the results of the D and D preparations for one of these four reactors, the Oak Ridge Research Reactor (ORR), with the emphasis on the environmental aspects. The three tasks that must be completed before a facility can be transferred to the D and D program are: Completion of environmental compliance, industrial safety, and radiological reviews; Removal of all spent fuel and nuclear material; and Assurance that buildings and support systems are structurally sound so as to permit deferred final decommissioning for up to five years

  16. Princeton University Plasma Physics Laboratory, Princeton, New Jersey

    International Nuclear Information System (INIS)

    This report discusses the following topics: Principal parameters of experimental devices; Tokamak Fusion Test Reactor; Burning Plasma Experiment; Princeton Beta Experiment-Modification; Current Drive Experiment-Upgrade; International Thermonuclear Experimental Reactor; International Collaboration; X-Ray Laser Studies; Hyperthermal Atomic Beam Source; Pure Electron Plasma Experiments; Plasma Processing: Deposition and Etching of Thin Films; Theoretical Studies; Tokamak Modeling; Engineering Department; Environment, Safety, and Health and Quality Assurance; Technology Transfer; Office of Human Resources and Administration; PPPL Patent Invention Disclosures; Office of Resource Management; Graduate Education: Plasma Physics; Graduate Education: Program in Plasma Science and Technology; and Science Education Program

  17. Heterosexual and nonheterosexual young university students' involvement in traditional and cyber forms of bullying.

    Science.gov (United States)

    Wensley, Kate; Campbell, Marilyn

    2012-12-01

    Research has consistently found that school students who do not identify as self-declared completely heterosexual are at increased risk of victimization by bullying from peers. This study examined heterosexual and nonheterosexual university students' involvement in both traditional and cyber forms of bullying, as either bullies or victims. Five hundred twenty-eight first-year university students (M=19.52 years old) were surveyed about their sexual orientation and their bullying experiences over the previous 12 months. The results showed that nonheterosexual young people reported higher levels of involvement in traditional bullying, both as victims and perpetrators, in comparison to heterosexual students. In contrast, cyberbullying trends were generally found to be similar for heterosexual and nonheterosexual young people. Gender differences were also found. The implications of these results are discussed in terms of intervention and prevention of the victimization of nonheterosexual university students. PMID:23078337

  18. Report of the research results with University of Tokyo, Nuclear Engineering Research Laboratory's Facilities in fiscal 1991

    International Nuclear Information System (INIS)

    This publication summarizes the results of the joint utilization of the nuclear reactor 'Yayoi' and the electron beam accelerator in the Nuclear Engineering Research Laboratory, University of Tokyo, in fiscal year 1991. The Yayoi was operated smoothly throughout the year, and the number of research themes, for which the reactor Yayoi was jointly utilized, and the related themes reached 21 cases. After the linear accelerator was reconstructed as the twin linac, the joint utilization was resumed in October, 1989, and the number of research themes, was 15 cases. In this publication, in addition to the utilization reports, also the reports of 15 cases of Yayoi Study Meetings held in fiscal year 1991 are collected. (K.I.)

  19. Decommissioning Small Research and Training Reactors; Experience on Three Recent University Projects - 12455

    International Nuclear Information System (INIS)

    Decommissioning small reactors within the confines of an active University environment presents unique challenges. These range from the radiological protection of the nearby University population and grounds, to the logistical challenges of working in limited space without benefit of the established controlled, protected, and vital areas common to commercial facilities. These challenges, and others, are discussed in brief project histories of three recent (calendar year 2011) decommissioning activities at three University training and research reactors. These facilities include three separate Universities in three states. The work at each of the facilities addresses multiple phases of the decommissioning process, from initial characterization and pre-decommissioning waste removal, to core component removal and safe storage, through to complete structural dismantlement and site release. The results of the efforts at each University are presented, along with the challenges that were either anticipated or discovered during the decommissioning efforts, and results and lessons learned from each of the projects. (authors)

  20. The Relationships between University Students' Chemistry Laboratory Anxiety, Attitudes, and Self-Efficacy Beliefs

    Science.gov (United States)

    Kurbanoglu, N. Izzet; Akin, Ahmet

    2010-01-01

    The aim of this study is to examine the relationships between chemistry laboratory anxiety, chemistry attitudes, and self-efficacy. Participants were 395 university students. Participants completed the Chemistry Laboratory Anxiety Scale, the Chemistry Attitudes Scale, and the Self-efficacy Scale. Results showed that chemistry laboratory anxiety…

  1. A human reliability analysis of the University of New Mexico's AGN- 201M nuclear research reactor

    International Nuclear Information System (INIS)

    During 1990--1991, a probabilistic risk assessment was conducted on the University of New Mexico's AGN-201M nuclear research reactor to address the risk and consequence of a maximum hypothetical release accident. The assessment indicated a potential for consequential human error to precipitate Chis scenario. Subsequently, a human reliability analysis was performed to evaluate the significance of human interaction on the reactor's safety systems. This paper presents the results of that investigation

  2. University of Florida Training Reactor: Annual progress, September 1, 1985-August 31, 1986

    International Nuclear Information System (INIS)

    Information is presented concerning: University of Florida personnel associated with the reactor; Facility operation; Modifications to the operating characteristics or capabilities of the UFTR facility; Significant maintenance, tests and survelliances of UFTR reactor systems and facilities; Changes to technical specifications, standard operating prceedures and other documents; Radioactive releases and environmental surveillance; Education, research and training utilization; and Theses, publications, reports and oral presentations of work related to the use and operation of the UFTR

  3. Modular Pebble-Bed Reactor Project: Laboratory-Directed Research and Development Program FY 2002 Annual Report

    Energy Technology Data Exchange (ETDEWEB)

    Petti, David Andrew; Dolan, Thomas James; Miller, Gregory Kent; Moore, Richard Leroy; Terry, William Knox; Ougouag, Abderrafi Mohammed-El-Ami; Oh, Chang H; Gougar, Hans D

    2002-11-01

    This report documents the results of our research in FY-02 on pebble-bed reactor technology under our Laboratory Directed Research and Development (LDRD) project entitled the Modular Pebble-Bed Reactor. The MPBR is an advanced reactor concept that can meet the energy and environmental needs of future generations under DOE’s Generation IV initiative. Our work is focused in three areas: neutronics, core design and fuel cycle; reactor safety and thermal hydraulics; and fuel performance.

  4. Study of a new automatic reactor power control for the TRIGA Mark II reactor at University of Pavia

    International Nuclear Information System (INIS)

    The installation of a new Instrumentation and Control (IC) system for the TRIGA Mark-II reactor at University of Pavia has recently been completed in order to assure a safe and continuous reactor operation for the future. The intervention involved nearly the whole IC system and required a channel-by-channel component substitution. One of the most sensitive part of the intervention concerned the Automatic Reactor Power Controller (ARPC) which permits to keep the reactor at an operator-selected power level acting on the control rod devoted to the fine regulation of system reactivity. This controller installed can be set up using different control logics: currently the system is working in relay mode. The main goal of the work presented in this paper is to set up a Proportional-Integral-Derivative (PID) configuration of the new controller installed on the TRIGA reactor of Pavia so as to optimize the response to system perturbations. The analysis have shown that a continuous PID offers generally better results than the relay mode which causes power oscillations with an amplitude of 3% of the nominal power

  5. Experience in operation and maintenance of the TRIGA Mark II reactor at the University of Pavia

    International Nuclear Information System (INIS)

    Experience in the operation and maintenance of the 250 kW steady state/250 MW pulsed TRIGA Mark II Reactor of the University of Pavia in the past two years is reported. Data for the reactor utilization and of Health Physics activity are also presented. Since the Second European Conference of TRIGA Reactor Users in 1972, reactor operation continued normally. No major troubles occurred during this time except for rotary specimen rack rotation. Maintenance of reactor facilities, including the substitution of the rotary specimen rack with a new one manufactured on-site is described. In June 1974 measurements of fluxes in the thermal column, with most of the graphite elements removed, were carried out in order to install a neutron converter in thermal column. Some results of fluxes and cadmium ratio values are reported. A description of the converter facility set up is given. (U.S.)

  6. Why do young Arabs in Denmark choose to study their heritage language at the university?

    DEFF Research Database (Denmark)

    Dhahir, Omar

    2016-01-01

    ; whether the informants had learned/maintained Arabic before starting at the university; and the role of the families in motivating the informants to learn and study Arabic. The informants are students just enrolled at the University of Southern Denmark in autumn 2012. A mixed method was used: a......This article reports on a study of the phenomenon that an increasing number of young Arabs in Denmark are choosing to study their heritage language at the university. The study aimed at investigating three elements: the motivation behind choosing to study the heritage language at the university...... quantitative method, where 18 informants completed a questionnaire, and a qualitative, where 11 out of the 18 were interviewed. The study found that the motivation behind the decision to study Arabic at the university is multiple, primarily to understand the holy book of Islam and Arabic culture, besides the...

  7. 75 FR 54657 - University of Florida; University of Florida Training Reactor; Environmental Assessment and...

    Science.gov (United States)

    2010-09-08

    ... UFTR. In addition, samples are collected of water, soil, and vegetation at twenty-two locations within...-central part of Florida about midway between the Gulf of Mexico and the Atlantic Ocean. The reactor is housed in a vault-type building which serves as a confinement. The Nuclear Reactor Building and its...

  8. Utilization Status and Development Layout of Research Reactors in Tsinghua University, China

    International Nuclear Information System (INIS)

    The Institute of Nuclear and New Energy Technology of Tsinghua University (INET), as the largest education institute of nuclear science in P.R. China, operates three research reactors. How to broaden the utilization of our RRs is the challenge we have to face. In this article, current utilization status of the swimming pool reactor will be introduced. The feasibility of developing the RRs into training center and the advantages of High Temperature Gas-Cooled Reactor (HTR-10) for nuclear hydrogen production will be put forward. (author)

  9. Design and Laboratory Evaluation of Future Elongation and Diameter Measurements at the Advanced Test Reactor

    Energy Technology Data Exchange (ETDEWEB)

    K. L. Davis; D. L. Knudson; J. L. Rempe; J. C. Crepeau; S. Solstad

    2015-07-01

    New materials are being considered for fuel, cladding, and structures in next generation and existing nuclear reactors. Such materials can undergo significant dimensional and physical changes during high temperature irradiations. In order to accurately predict these changes, real-time data must be obtained under prototypic irradiation conditions for model development and validation. To provide such data, researchers at the Idaho National Laboratory (INL) High Temperature Test Laboratory (HTTL) are developing several instrumented test rigs to obtain data real-time from specimens irradiated in well-controlled pressurized water reactor (PWR) coolant conditions in the Advanced Test Reactor (ATR). This paper reports the status of INL efforts to develop and evaluate prototype test rigs that rely on Linear Variable Differential Transformers (LVDTs) in laboratory settings. Although similar LVDT-based test rigs have been deployed in lower flux Materials Testing Reactors (MTRs), this effort is unique because it relies on robust LVDTs that can withstand higher temperatures and higher fluxes than often found in other MTR irradiations. Specifically, the test rigs are designed for detecting changes in length and diameter of specimens irradiated in ATR PWR loops. Once implemented, these test rigs will provide ATR users with unique capabilities that are sorely needed to obtain measurements such as elongation caused by thermal expansion and/or creep loading and diameter changes associated with fuel and cladding swelling, pellet-clad interaction, and crud buildup.

  10. MYRRHA a fast reactor to be operated by the young generation

    International Nuclear Information System (INIS)

    MYRRHA, the Multi-purpose hybrid Research Reactor for High-tech Applications, is an innovative research facility that is able to carry out a wide variety of applications: 1) transmutation of minor actinides, 2) qualification of fuel for new reactors, 3) material testing for Gen IV and fusion reactors, 4) production of medical radio-isotopes and 5) silicon doping for renewable electrical power. By means of these applications MYRRHA is the successor of BR2, it will validate the ADS (Accelerator Driven System) full concept and the use of heavy metal coolants (particularly the lead-bismuth eutectic - LBE). The MYRRHA plant consists of 3 main parts being the primary systems, the accelerator and the balance of plant which groups all structures, systems and components that are not included in the first two items. The scientific and technological knowledge that will be acquired with MYRRHA will be the basis for new lead cooled reactors having a higher performance and for industrial transmutation facilities capable of significantly reducing the amount and the burden time of high-level waste produced in power plants. It is the responsibility of the young and next generations to operate these upcoming facilities but our duty to obtain the crucial data. To profit from nuclear applications in the coming decades, the safety of these systems obviously has to be guaranteed. The safety approach of MYRRHA is based on the defence-in-depth principle. Initiating events are grouped in probability classes in order to determine the number of lines of defence needed to mitigate their consequences. Initiating events are preferably prevented, certainly those with potentially severe consequences or difficult to mitigate. For the design of MYRRHA we consider events up to a probability of occurrence of 10-6/year. This article describes the present state of the MYRRHA design. The article is followed by the slides of the presentation

  11. Job and Task Analysis project at Brookhaven National Laboratory's high flux beam reactor

    International Nuclear Information System (INIS)

    The presenter discussed the Job and Task Analysis (JTA) project conducted at Brookhaven National Laboratory's High Flux Beam Reactor (HFBR). The project's goal was to provide JTA guidelines for use by DOE contractors, then, using the guidelines conduct a JTA for the reactor operator and supervisor positions at the HFBR. Details of the job analysis and job description preparation as well as details of the task selection and task analysis were given. Post JTA improvements to the HFBR training programs were covered. The presentation concluded with a listing of the costs and impacts of the project

  12. Los Alamos National Laboratory case studies on decommissioning of research reactors and a small nuclear facility

    International Nuclear Information System (INIS)

    Approximately 200 contaminated surplus structures require decommissioning at Los Alamos National Laboratory. During the last 10 years, 50 of these structures have undergone decommissioning. These facilities vary from experimental research reactors to process/research facilities contaminated with plutonium-enriched uranium, tritium, and high explosives. Three case studies are presented: (1) a filter building contaminated with transuranic radionuclides; (2) a historical water boiler that operated with a uranyl-nitrate solution; and (3) the ultra-high-temperature reactor experiment, which used enriched uranium as fuel

  13. U.S. university reactors: What they are and what they do

    International Nuclear Information System (INIS)

    One of the most underappreciated facts in the academic and industrial communities today is that there are 35 licensed university nuclear research and training reactors in operation on 33 campuses (two universities have two reactors each) in 25 states. These facilities, in conjunction with their respective nuclear engineering and science departments, provide the professional expertise and the backbone of our nation's human resources for exploiting the nuclear sciences and technology on which so much of society depends today. Areas of contribution and service include biomedical applications (therapy and diagnosis), radioisotope tracer applications, neutron activation analysis and detection, materials testing and enhancement, neutron radiography applications, and radioisotope production, to name just a few

  14. Utilization of research and training reactors in the study program of students at Slovak University of Technology

    International Nuclear Information System (INIS)

    technologies, but also to travel to perform practical exercises at foreign training or experimental reactors as: TRIGA II Reactor in Atomic Institute of the Austrian Universities, Vienna, Austria (3 practical exercises per study for about 10 students yearly since 1990); School Reactor of the Technical University of Budapest, Hungary (one week per study, about 10 students yearly since 1983); Training Reactor of the CVUT, Prague, Czech Republic (3 days per study, about 10 students yearly since 1998); Experimental reactor ASTRA in Austrian Research Center Seibersdorf (1999-2000) A 4 weeks' IAEA Regional Training Course 'Safety management and utilisation of research reactors' on Safety, Management and Utilization of Research Reactors was held in Bratislava (Slovakia) and Vienna (Austria) during March 05-30th 2001. IAEA in co-operation with the Department of Nuclear Physics and Technology of the Slovak University of Technology and the Atominstitut of Austrian Universities Vienna prepared and realized this training course with the aim to train junior staff from research reactors in various aspects of safety, management and utilization of research reactors. All participants had to have at least 4 years experiences in operation, management, utilization or regulation of research reactors. Lectures covered the topics in nuclear design and operation, neutron physics, reactor physics, health physics, dosimetry, reactor instrumentation, fuel management decontamination procedures, preparation of experiments at research reactors and others. Beside theoretical part of the course, the practical exercises at TRIGA II reactor in Vienna constituted an important part of training. ENEN - European Nuclear Education Network: Feasibility Study for Central-European Region. In frame of this project, prepared for the Central-European region, students participating in nuclear engineering education will visit participating institute to carry out laboratory practices and student as well as diploma work. We

  15. Educational laboratory based on a multifunctional analyzer of a reactor of a nuclear power plant with a water-moderated water-cooled reactor

    International Nuclear Information System (INIS)

    Authors presents an educational laboratory Safety and Control of a Nuclear Power Facility established by the Department of Automation for students and specialists of the nuclear power industry in the field of control, protection, and safe exploitation of reactor facilities at operating, constructing, and designing nuclear power plants with water-moderated water-cooled reactors

  16. Verification Survey of the Building 315 Zero Power Reactor-6 Facility, Argonne National Laboratory-East, Argonne, Illinois

    International Nuclear Information System (INIS)

    Oak Ridge Institute for Science and Education (ORISE) conducted independent verification radiological survey activities at Argonne National Laboratory's Building 315, Zero Power Reactor-6 facility in Argonne, Illinois. Independent verification survey activities included document and data reviews, alpha plus beta and gamma surface scans, alpha and beta surface activity measurements, and instrumentation comparisons. An interim letter report and a draft report, documenting the verification survey findings, were submitted to the DOE on November 8, 2006 and February 22, 2007, respectively (ORISE 2006b and 2007). Argonne National Laboratory-East (ANL-E) is owned by the U.S. Department of Energy (DOE) and is operated under a contract with the University of Chicago. Fundamental and applied research in the physical, biomedical, and environmental sciences are conducted at ANL-E and the laboratory serves as a major center of energy research and development. Building 315, which was completed in 1962, contained two cells, Cells 5 and 4, for holding Zero Power Reactor (ZPR)-6 and ZPR-9, respectively. These reactors were built to increase the knowledge and understanding of fast reactor technology. ZPR-6 was also referred to as the Fast Critical Facility and focused on fast reactor studies for civilian power production. ZPR-9 was used for nuclear rocket and fast reactor studies. In 1967, the reactors were converted for plutonium use. The reactors operated from the mid-1960's until 1982 when they were both shut down. Low levels of radioactivity were expected to be present due to the operating power levels of the ZPR's being restricted to well below 1,000 watts. To evaluate the presence of radiological contamination, DOE characterized the ZPRs in 2001. Currently, the Melt Attack and Coolability Experiments (MACE) and Melt Coolability and Concrete Interaction (MCCI) Experiments are being conducted in Cell 4 where the ZPR-9 is located (ANL 2002 and 2006). ANL has performed final

  17. The Role of Computer-Based Educational Laboratories in Nuclear Engineering University Programmes

    International Nuclear Information System (INIS)

    The specialized Educational and research laboratory 'Reactor physics, control and safe operation of WWER type NPP’ is based on the computer simulator of WWER -1000 and offers the real-time monitoring of data available to the WWER -1000 NPP control room operators, and provides a possibility to investigate reactor behavior in normal and abnormal situations. The laboratory supports interactive technologies and team-based activities that enable students to build their knowledge through required gateway courses and explore problems relevant to real life situations

  18. Ohio State University reactor sharing program. Progress report, September 1, 1980-April 30, 1981

    International Nuclear Information System (INIS)

    The utilization of the OSURR and GRSS by colleges and universities is summarized. Two student laboratory exercises were developed during this period and are included: control rod calibration and approach to critical

  19. Project plan for the decontamination and decommissioning of the Argonne National Laboratory Experimental Boiling Water Reactor

    International Nuclear Information System (INIS)

    In 1956, the Experimental Boiling Water Reactor (EBWR) Facility was first operated at Argonne National Laboratory (ANL) as a test reactor to demonstrate the feasibility of operating an integrated power plant using a direct cycle boiling water reactor as a heat source. In 1967, ANL permanently shut down the EBWR and placed it in dry lay-up. This project plan presents the schedule and organization for the decontamination and decommissioning of the EBWR Facility which will allow it to be reused by other ANL scientific research programs. The project total estimated cost is $14.3M and is projected to generate 22,000 cubic feet of low-level radioactive waste which will be disposed of at an approved DOE burial ground. 18 figs., 3 tabs

  20. The job satisfaction gender gap among young recent university graduates: Evidence from Catalonia

    OpenAIRE

    Mora, Toni; Ferrer-i-Carbonell, Ada

    2009-01-01

    The present paper focuses on the gender differences in job satisfaction reported by recent university graduates in Catalonia (Spain). The data allows distinguishing five areas of job satisfaction: work content, promotion possibilities, earnings, applicability of acquired knowledge, and job security. Young and highly educated women in this study report a lower satisfaction with some aspects of their job. For two of the five job satisfaction domains, the lower reported level can be explained by...

  1. Annual report on operation, utilization and technical development of research reactors and Hot Laboratory

    International Nuclear Information System (INIS)

    The department is responsible for the operation, maintenance, utilization and related R and D works of the research reactors including JRR-2, JRR-3M (new JRR-3) and JRR-4 and the Hot Laboratory. The JRR-3M received an operational license from the authority on October 16th, 1991 and initiate a steady operation since November. This report describes the activities of our department in fiscal year of 1990 and it also includes some of the technical topics on the works mentioned above. As for the research reactors, we carried out the operation, maintenance, irradiation utilization, neutron beam experiments, technical management including fuels and water chemistry, radiation monitoring as well as related R and D works. In the Hot Laboratory, post-irradiation examinations of fuels and materials were conducted along with the development of related techniques. The international cooperations between the developing countries and our department were also made concerning the operation, utilization and safety analysis for nuclear facilities. (author)

  2. Laboratory analysis of sodium and related materials in the United States Breeder Reactor Program

    Energy Technology Data Exchange (ETDEWEB)

    Keough, R.F.; Ebersole, E.R.

    1978-04-01

    It is essential for the long term operation of a Liquid Metal Fast Breeder Reactor (LMFBR) to control the levels of some sodium and cover gas impurities and to monitor the levels of many others. Chemical analyses are the means of confirming that specific impurities are within established limits. Changes in impurity levels can be most useful in evaluating purification systems and detecting problems such as leaks or excessive corrosion. Extensive analyses are also required with experimental sodium systems related to the Breeder Reactor Program (BRP) since reactor quality sodium is needed to insure relevancy of test data. All of the laboratories use the same procedures for sodium and cover gas analysis. Each year the representatives of the eight laboratories meet to discuss problems they may have and to suggest improvements they would like to see in the methods. Many of these methods are described and their application related to the operation of the Experimental Breeder Reactor II (EBR-II) and Fast Flux Test Facility (FFTF).

  3. Laboratory Scale Study of Activated Sludge Process in Jet Loop Reactor for Waste WaterTreatment

    OpenAIRE

    M. S. Patil; G. A. Usmani

    2014-01-01

    The present study was undertaken to evaluate the feasibility of Activated Sludge Process (ASP) for the treatment of synthetic wastewater and to develop a simple design criteria under local conditions.A laboratory scale Compact jet loop reactor model comprising of an aeration tank and final clarifier was used for this purpose.Settled synthetic wastewater was used as influent to the aeration tank. The Chemical Oxygen Demand (COD) of the influent and effluent was measured to find...

  4. Planning and implementation of Istanbul Technical University TRIGA research reactor program

    International Nuclear Information System (INIS)

    The Istanbul Technical University TRIGA Research Reactor at the Institute for Nuclear Energy, which went critical on March 11, 1979 is basically a pulsing type TRIGA Mark - II reactor. Completion of the ITU-TRR contributed to broaden the role of the Institute for Nuclear Energy of the Technical University in Istanbul in the nuclear field by providing for the first time adequate on-campus experimental facilities for nuclear engineering studies to ITU students. The research program which is currently under planning at ITU-NEE encompasses: a) Neutron activation analysis studies by techniques and applications to chemistry, mining, materials research, archaeological and biomedical studies; b) applications of Radioisotopes; c) Radiography with reactor neutron beams; d) Radiation Pulsing

  5. Planning the procedure for dismantling the TRIGA Reactor at the Medical University of Hannover

    International Nuclear Information System (INIS)

    The aim of this contribution is to provide an overview of the procedure for dismantling the TRIGA reactor at the Medical University of Hannover (MHH). In particular, the dismantling concept and techniques, the amount and the handling of radioactive material, the measurements for release, radiation protection for persons and the environment are presented. (author)

  6. The development of a universal diagnostic probe system for Tokamak fusion test reactor

    Science.gov (United States)

    Mastronardi, R.; Cabral, R.; Manos, D.

    1982-01-01

    The Tokamak Fusion Test Reactor (TFTR), the largest such facility in the U.S., is discussed with respect to instrumentation in general and mechanisms in particular. The design philosophy and detailed implementation of a universal probe mechanism for TFTR is discussed.

  7. 78 FR 5840 - Notice of License Termination for University of Illinois Advanced TRIGA Reactor, License No. R-115

    Science.gov (United States)

    2013-01-28

    ... COMMISSION Notice of License Termination for University of Illinois Advanced TRIGA Reactor, License No. R-115... No. R-115, for the University of Illinois Advanced TRIGA Reactor (ATR). The NRC has terminated the..., Facility Operating License No. R-115 is terminated. The above referenced documents may be examined,...

  8. 77 FR 13376 - Notice of License Termination for the University of Arizona Research Reactor, License No. R-52

    Science.gov (United States)

    2012-03-06

    ... COMMISSION Notice of License Termination for the University of Arizona Research Reactor, License No. R-52 The... No. R-52, for the University of Arizona Research Reactor (UARR). The NRC has terminated the license... released for unrestricted use. Therefore, Facility Operating License No. R-52 is terminated. For...

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

    International Nuclear Information System (INIS)

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

  10. A multidisciplinary protocol for face transplantation at Brigham and Women's Hospital.

    Science.gov (United States)

    Bueno, E M; Diaz-Siso, J R; Pomahac, B

    2011-12-01

    Face transplantation introduces an unprecedented potential to restore form and function in patients with severe facial disfigurement. A successful face transplantation programme requires a sound research protocol, a solid infrastructure, expert personnel and adequate funding. There are only a few active face transplant programmes in the world and interest in the development of new such programmes continues to grow. After 2 years of working on the development of the face transplant programme, in 2009 the team at Brigham and Women's Hospital (BWH) performed the 2nd face transplant in the United States. Since then, the team has continued to evaluate several possible face transplant candidates and performed three additional facial transplants. These experiences have helped refine a highly effective multidisciplinary protocol that carries a patient through recruitment, informed consent, screening, preoperative planning, face transplantation surgery and postoperative long-term follow-up. The members of the BWH face transplantation team responsible for carrying out this protocol include a team leader, a programme manager/coordinator, clinical and rehabilitation specialists, social workers, bioethicists, nurses and administrative staff. The roles of each team member during the various stages of the face transplant process are presented here. Additional insight into the interaction between the face transplant team, the Institutional Review Board and the regional Organ Procurement Organization is given. The BWH team's experience has shown that true collaboration, creativity and a unique approach to each candidate translate into the optimal care of the face transplant patient both before and after surgery. PMID:21872546

  11. Brigham Fracture Intervention Team Initiatives for Hospital Patients with Hip Fractures: A Paradigm Shift

    Directory of Open Access Journals (Sweden)

    Julie Glowacki

    2010-01-01

    Full Text Available We designed, implemented, and revised the Brigham Fracture Intervention Team (B-FIT initiatives to improve in-hospital care of fracture (Fx patients. Effectiveness was evaluated for 181 medical records of 4 cohorts in four successive years of consecutive patients who were admitted with a fragility hip Fx. The Discharge Initiative (DI (computer-based includes 1200 mg calcium and 1000 IU vitamin D3 daily. The Admission Initiative (AI was introduced one year later with reminders for serum 25OHD measurement, initiation of daily calcium (1200 mg and vitamin D (800 IU, and an order for Endocrinology consultation, with an amendment for a computer-assisted reminder and a dose of D2 (50 000 IU. Initially, the computer-based DI was more effective (67% than the surgeon-driven AI (33%, P<.001. After introduction of a computer-assisted reminder, AI effectiveness increased to 68%. The marked prevalence of vitamin D insufficiency reaffirms the importance of incorporating vitamin D recommendations in Fx care pathways.

  12. Opportunities for Laboratory Opacity Chemistry Studies to Facilitate Characterization of Young Giant Planets and Brown Dwarfs

    Science.gov (United States)

    Marley, Mark; Freedman, Richard S.

    2015-01-01

    The thermal emission spectra of young giant planets is shaped by the opacity of atoms and molecules residing in their atmospheres. While great strides have been made in improving the opacities of important molecules, particularly NH3 and CH4, at high temperatures, much more work is needed to understand the opacity and chemistry of atomic Na and K. The highly pressure broadened fundamental band of Na and K in the optical stretches into the near-infrared, strongly influencing the shape of the Y and K spectral bands. Since young giant planets are bright in these bands it is important to understand the influences on the spectral shape. Discerning gravity and atmospheric composition is difficult, if not impossible, without both good atomic opacities as well as an excellent understanding of the relevant atmospheric chemistry. Since Na and K condense at temperatures near 500 to 600 K, the chemistry of the condensation process must be well understood as well, particularly any disequilibrium chemical pathways. Comparisons of the current generation of sophisticated atmospheric models and available data, however, reveal important shortcomings in the models. We will review the current state of observations and theory of young giant planets and will discuss these and other specific examples where improved laboratory measurements for alkali compounds have the potential of substantially improving our understanding of these atmospheres.

  13. Nudging young Danish men to eat more vegetables:A food laboratory pilot experiment

    OpenAIRE

    Kongsbak, Ida; Skov, Laurits Rohden; Køpke Nielsen, Brit; Wichmann, Maria; Schaldemose, Hanna; Atkinson, Louise; Ahlmann, Fie Kathrine; Perez-Cueto, Armando

    2014-01-01

    Objective: This study assessed the combined effect of two choice archi- tectural nudges as a means to increase fruit and vegetable consumption among male university students.Methodology: This single one-day lunch meal study was conducted in a Food Scape Laboratory. A control group (n=32) and an intervention group (n=33) were recruited to attend an ad libitum self-serve buffet at two different timeslots. Two choice architectural nudges were applied in the intervention group; the fruit and vege...

  14. KNOWLEDGE, ATTITUDES AND PRACTICE OF LABORATORY TECHNICIANS REGARDING UNIVERSAL WORK PRECAUTION

    Directory of Open Access Journals (Sweden)

    Jitendra Zaveri

    2012-02-01

    Full Text Available Objective: Objective of the present study is to determine the knowledge, attitude, and practice of universal work precautions amongst medical laboratory technicians in private hospitals. Methodology: Cross-sectional study of health care workers was conducted using a pretested self-administered questionnaire, which enquired about knowledge, attitude and practices of universal work precautions. The hepatitis B vaccination statuses were also asked. Results: 200 questionnaires were administered to laboratory technicians and 154 of them were returned giving a response rate of 77%. All the participants wear gloves during laboratory work but 81.2% wear a single pair. 17.5 % of the participants claimed to know what to do if exposed to infection. 45.6% of the participants eat in the laboratory, 47.0% of them store foods and water in the refrigerators, 31.5% of them put on cosmetics in the laboratory, 12.6% smoke in the laboratory, 10.0% cut their finger nails with teeth in the laboratory. 91.5% are not immunized against hepatitis B virus (HBV. 99.0% of them do not take shower immediately after laboratory work. 82.0% of the participants do not feel that the use of masks is necessary in laboratory. Conclusion: It is concluded that the knowledge, attitude, perception, and compliance with universal work precautions amongst laboratory technicians are poor. [National J of Med Res 2012; 2(1.000: 113-115

  15. Annual report of Nuclear Engineering Research Laboratory, University of Tokyo in fiscal 1993

    International Nuclear Information System (INIS)

    In this annual report, the activities of research and education, the state of operation of research facilities and others in fiscal year 1993 are summarized. Four main research facilities are the fast neutron source reactor 'Yayoi', the electron linear accelerator, the basic experiment facility for nuclear fusion reactor blanket design and the heavy irradiation research facility. The reactor and the accelerator are for the joint utilization by all universities in Japan, the blanket is used by the Faculty of Engineering, and the HIT is for the joint utilization in University of Tokyo. In fiscal year 1993, the installation of the fast neutron science research facility was approved. In this annual report, the management and operation of the above research facilities are described, and the research activities, the theses for doctorate and graduation theses of teachers, are summarized. (K.I.)

  16. Applied research and service activities at the University of Missouri Research Reactor Facility (MURR)

    International Nuclear Information System (INIS)

    The University Of Missouri operates MURR to provide an intense source of neutron and gamma radiation for research and applications by experimenters from its four campuses and by experimenters from other universities, government and industry. The 10 MW reactor, which has been operating an average of 155 hours per week for the past eight years, produces thermal neutron fluxes up to 6-7x1014 n/cm2-s in the central flux trap and beamport source fluxes of up to 1.2x1014 n/cm2-s. The mission of the reactor facility, to promote research, education and service, is the same as the overall mission of the university and therefore, applied research and service supported by industrial firms have been welcomed. The university recognized after a few years of reactor operation that in order to build utilization, it would be necessary to develop in-house research programs including people, equipment and activity so that potential users could more easily and quickly obtain the results needed. Nine research areas have been developed to create a broadly based program to support the level of activity needed to justify the cost of operating the facility. Applied research and service generate financial support for about one-half of the annual budget. The applied and service programs provide strong motivation for university/industry association in addition to the income generated. (author)

  17. Safety evaluation report related to the renewal of the operating license for the research reactor at North Carolina State University

    International Nuclear Information System (INIS)

    This safety evaluation report (SER) summarizes the findings of a safety review conducted by the staff of the U.S. Nuclear Regulatory Commission (NRC), Office of Nuclear Reactor Regulation (NRR). The staff conducted this review in response to a timely application filed by North Carolina State University (the licensee or NCSU) for a 20-year renewal of Facility Operating License R-120 to continue to operate the NCSU PULSTAR research reactor. The facility is located in the Burlington Engineering Laboratory complex on the NCSU campus in Raleigh, North Carolina. In its safety review, the staff considered information submitted by the licensee (including past operating history recorded in the licensee's annual reports to the NRC), as well as inspection reports prepared by NRC Region H personnel and first-hand observations. On the basis of this review, the staff concludes that NCSU can continue to operate the PULSTAR research reactor, in accordance with its application, without endangering the health and safety of the public. 16 refs., 31 figs., 7 tabs

  18. A Place for Materials Science: Laboratory Buildings and Interdisciplinary Research at the University of Pennsylvania

    Science.gov (United States)

    Choi, Hyungsub; Shields, Brit

    2015-01-01

    The Laboratory for Research on the Structure of Matter (LRSM), University of Pennsylvania, was built in 1965 as part of the Advanced Research Projects Agency's (ARPA) Interdisciplinary Laboratories (IDL) program intended to foster interdisciplinary research and training in materials science. The process that led to the construction of the…

  19. "Venturing in Education": Teaching at the University of Chicago's Laboratory School, 1896-1904

    Science.gov (United States)

    Durst, Anne

    2010-01-01

    In 1896, John Dewey opened the Laboratory School at the University of Chicago. While much is known about this legendary school and its founder, the teachers whose daily work brought the school to life remain mostly anonymous. This essay attempts to remedy this historical invisibility by investigating four of the Laboratory School teachers--Anna…

  20. 3-Dimensional and Interactive Istanbul University Virtual Laboratory Based on Active Learning Methods

    Science.gov (United States)

    Ince, Elif; Kirbaslar, Fatma Gulay; Yolcu, Ergun; Aslan, Ayse Esra; Kayacan, Zeynep Cigdem; Alkan Olsson, Johanna; Akbasli, Ayse Ceylan; Aytekin, Mesut; Bauer, Thomas; Charalambis, Dimitris; Gunes, Zeliha Ozsoy; Kandemir, Ceyhan; Sari, Umit; Turkoglu, Suleyman; Yaman, Yavuz; Yolcu, Ozgu

    2014-01-01

    The purpose of this study is to develop a 3-dimensional interactive multi-user and multi-admin IUVIRLAB featuring active learning methods and techniques for university students and to introduce the Virtual Laboratory of Istanbul University and to show effects of IUVIRLAB on students' attitudes on communication skills and IUVIRLAB. Although…

  1. Evaluation of the Young Children with Neurodevelopmental Disability: A Prospective Study at Hamadan University of Medical Sciences Clinics

    Directory of Open Access Journals (Sweden)

    Afshin FAYYAZI

    2013-01-01

    Full Text Available ObjectiveDevelopmental impairment is a common problem in children health that occurs in approximately 5–10% of the childhood population. The aim of this study was to determine the etiologic yield of subspecialists’ evaluation of young children with developmental disability.Materials & MethodsAll children aged between 2 months and 5 years referred over a 15-month period to Hamadan University of Medical Sciences subspecialty services for initial evaluation of a suspected developmental Disability, were enrolled in the present study. Diagnostic yield was determined after the completion of clinical assessments and laboratory tests requested by the evaluating physician.ResultsA total of 198 children (129 boys and 69 girls were eligible for our study.108 children had global developmental delay and 90 children had isolated developmental delay. Approximately ¼ of all patients did not have any specific etiology for developmental disability. Cerebral palsy (CP was the most common clinical syndrome in all patients (41.4%. Hypoxic ischemic encephalopathy (13.8%, brain dysgenesis (13%, genetic disorder (13%, and neurodegenerative diseases (11% were determined in more than one half of all children with global developmental disability. in our study, “developmental speech delay” was the common cause of isolated speech delay.ConclusionDetermination of an underlying etiology is an essential part of specialty evaluation of young children with developmental disability. The results of this study were similar closely to the results of other studies.

  2. Internet Addiction among Greek University Students: Demographic Associations with the Phenomenon, Using the Greek Version of Young's Internet Addiction Test

    OpenAIRE

    Frangos, Christos C.; Constantinos C. Frangos; Kiohos, Apostolos P.

    2010-01-01

    Internet addiction (IA) is a new disorder described in 1996 by the psychologist Kimberly Young. The aim of this paper is to estimate the percentage of IA among Greek university students. Results of a sample survey among 1876 Greek university students, 18-27 years old, are presented. The questionnaire consisted of eight questions from Young's Diagnostic Test for Internet Addiction (YDTIA) as well as an inventory including demographic factors and questions about academic performance, computer a...

  3. Internet Addiction among Greek University Students: Demographic Associations with the Phenomenon, using the Greek version of Young's Internet Addiction Test

    OpenAIRE

    Christos C. Frangos; Frangos, Constantinos C; Kiohos, Apostolos P.

    2010-01-01

    Internet addiction (IA) is a new disorder described in 1996 by the psychologist Kimberly Young. The aim of this paper is to estimate the percentage of IA among Greek university students. Results of a sample survey among 1876 Greek university students, 18-27 years old, are presented. The questionnaire consisted of eight questions from Young's Diagnostic Test for Internet Addiction (YDTIA) as well as an inventory including demographic factors and questions about academic performance, computer a...

  4. Annual review of Plasma Physics Laboratory, Kyoto University, July, 1981

    International Nuclear Information System (INIS)

    The construction of the Heliotron E was completed in June, 1980. After the preliminary examination for two months and the improvement of the power supply, the Joule heating experiment was carried out from September, 1980, to January, 1981. The experiment of electron cyclotron resonance heating was also carried out in January, 1981. Then, experiment was stopped to install the neutral beam injection apparatus. The results obtained by both experiments are reported. The target may be attained by producing high density plasma with low plasma current, and heating the plasma by NBI additionally. In the ECRH experiment, plasma was produced and heated successfully without Joule heating current, by the Gyrotron with 200 kW power output. The favorable results of the confinement experiment with current-free plasma indicate the possibility of a stationary fusion reactor of Heliotron type. The Heliotron magnetic field configuration was proposed in 1959, and since then, the experiments of Heliotron A, B, C, D and DM were carried out in succession. Now, the purpose of the experiment to prove the principle is being achieved with Heliotron E. Hope is placed on the NBI experiment in preparation. (Kako, I.)

  5. Annual review of Plasma Physics Laboratory, Kyoto University, April, 1983

    International Nuclear Information System (INIS)

    The devices for additionally heating joul-heated plasma in the Heliotron E, such as electron cyclotron resonance heating and neutral beam injection, were in operation in 1982. In the ECRH experiment, the microwaves of 200 kW at 28 GHz were generated by a gyrotron, but the pulse width was extended from 10 ms to 40 ms this year. By this, a currentless plasma of Te-1 keV was achieved. In the NB1 experiment, the neutral beam of about 1.5 MW was injected into joule-heated plasma, and the plasma of Ti(O)-950 eV, Te(O)-800 eV and Ne = 3 x 1019/m3 was attained. The first experiment to inject neutral beam into ECRH currentless plasma was carried out. By this method, the density of the plasma increased as well as the ion temperature and electron temperature. As to the theory, a critical beta was calculated by using stellarator expansion, which should be 3 to 7 % in the Heliotron E. Two gyrotrons of 200 kW at 53 GHz each and an ion cyclotron resonance heating equipment of 1.5 MW at 26.7 MHz are prepared. As to the reactor study, the design of Heliotron H in the first phase was completed. The location of impurity sources in NB1 ion sources and beam lines was found. (Kako, I.)

  6. Contribution of a small university reactor to nuclear research in education and training

    International Nuclear Information System (INIS)

    The Triga Mark II reactor in Vienna, operated by the Vienna University of Technology, is the research reactor facility closest to the IAEA. Its main tasks are nuclear education and training in the fields of neutron and solid state physics, nuclear technology, reactor safety, radiochemistry, radiation protection and dosimetry, and low temperature physics and fusion research. Academic research is carried out by students in the fields mentioned. The students are coordinated and supervised by about 70 staff members with the aim of a Master's Degree or PhD in one of the areas mentioned. In addition, the Atomic Institute of the Austrian Universities cooperates closely with the IAEA, located nearby, in research projects, coordinated research projects (CRPs) and in supplying expert services. Regular training courses are performed for the IAEA for safeguard trainees. Moreover, fellowship places are offered for scientists from developing countries and staff members carry out expert missions to research centres in Africa, Asia and South America. Special nuclear material (SNM) belonging to the IAEA is stored for calibration purposes at the Atomic Institute. A summary follows of how and to what extent low power research reactors can efficiently be used to serve university education and training, cooperation with international and national networks, as well as for the IAEA in various fields, such as nuclear safeguards and participation in international coordinated projects

  7. Universal routine HPV vaccination for young girls in Uganda: a review of opportunities and potential obstacles

    Directory of Open Access Journals (Sweden)

    Banura Cecily

    2012-09-01

    Full Text Available Abstract This article reviews the existing realities in Uganda to identify opportunities and potential obstacles of providing universal routine HPV vaccination to young adolescent girls. Cervical cancer is a public health priority in Uganda where it contributes to about 50–60% of all female malignancies. It is associated with a dismal 5-year relative survival of approximately 20%. With adequate financial resources, primary prevention through vaccination is feasible using existing education and health infrastructure. Cost-effectiveness studies show that at a cost of US$2 per dose, the current vaccines would be cost effective. With optimal (≥70% coverage of the target population, the lifetime risk of cervical cancer could be reduced by >50%. Uganda fulfils 4 out of the 5 criteria set by the WHO for the introduction of routine HPV vaccination to young adolescent girls. The existing political commitment, community support for immunization and the favorable laws and policy environment all provide an opportunity that should not be missed to introduce this much needed vaccine to the young adolescent girls. However, sustainable financing by the government without external assistances remains a major obstacle. Also, the existing health delivery systems would require strengthening to cope with the delivery of HPV vaccine to a population that is normally not targeted for routine vaccination. Given the high incidence of cervical cancer and in the absence of a national screening program, universal HPV vaccination of Ugandan adolescent girls is critical for cervical cancer prevention.

  8. Neutron activation analysis in an industrial laboratory using an off-site nuclear reactor

    International Nuclear Information System (INIS)

    A multifunctional research laboratory, such as Procter and Gamble's Miami Valley Laboratories, requires elemental analyses on many materials. A general survey technique is important even if the information it provides is incomplete or is less precise than single element analyses. Procter and Gamble has developed neutron activation analysis (NAA) capabilities using a nuclear reactor several hundred miles away. The concentration of 40 to 50 elements can be determined in a variety of matrices. We have found NAA to be a powerful supplement to some of the more classical analytical techniques even without having an on-site neutron source. We have also found an automated data acquisition system to be essential for the successful application of NAA in an industrial laboratory

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

    International Nuclear Information System (INIS)

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

  10. Operational experience with the TRIGA reactor of the University of Pavia

    International Nuclear Information System (INIS)

    The TRIGA Mark II research reactor of the University of Pavia is in operation since 1965. The annual operational time at nominal power (250 kW) is in the range of 300 - 400 hours depending upon the time schedule of some experiments and research activities. The reactor is mainly used for NAA activities and BNCT research. Few tens of hours per year are dedicated also to electronic devices irradiation and student training courses. Few homemade upgrading of the reactor were realized in the past two years: components of the secondary/tertiary cooling circuit were substituted and a new radiation area monitoring system was installed. Also the Instrumentation and Control (I and C) system was almost completely refurbished. The presentation describes the major extraordinary maintenance activities implemented and the status of main reactor systems: - The I and C System: complete substitution, channel-by-channel without changing the operating and safety logics; - Tertiary and secondary water-cooling circuits: complete substitution of the tertiary water-cooling circuit and partial substitution of the components of the secondary water-cooling circuit; - Reactor Building Air Filtering and Ventilation System: installation of a computerized air filtering and ventilation system; - Radiation Area Monitoring System: new system based on a commercial micro-computer and an home-made software developed on Lab-View platform. The system is made of a network of different instruments coupled, trough a serial bus line RS232, with a data acquisition station; - Fuel Elements: at the moment, the core is made of 48 Aluminium clad and 34 SST clad TRIGA fuel elements controlled periodically for their elongation and/or bowing. All components and systems undergo ordinary maintenance according to the Technical Prescriptions and to the 'Good Practice Procedures'. In summary, the TRIGA reactor of the University of Pavia shows a very good technical state and, at the moment, there are no political or

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2015-05-15

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

  12. Report of the research results with University of Tokyo, Nuclear Engineering Research Laboratory's Facilities in fiscal 1983

    International Nuclear Information System (INIS)

    Much achievement was obtained also in fiscal 1983 by the common utilization of the nuclear reactor ''Yayoi'' and the linear accelerator in the Nuclear Engineering Research Laboratory, University of Tokyo. These results were summarized, and this report is published. In the utilization of the reactor ''Yayoi'', the period of operation and the maximum output were limited very much, because long cooling period is necessary to prepare for the repair of fuel cladding in the next year. Also foreign research students commonly utilized the reactor ''Yayoi''. The common utilization of the linear accelerator was begun six years ago, and now it is carried out widely and smoothly. The total number of those who commonly utilized the facilities reached 3,179. The summaries of the results of 5 on-pile researches, 17 off-pile researches, and 16 researches using the linear accelerator are collected. The committee meetings and study meetings held in fiscal 1983 are listed. The names of the members of various committees and the names of those in charge of various experiments are given. (Kako, I.)

  13. Status of the University of Missouri-Columbia Research Reactor upgrade

    International Nuclear Information System (INIS)

    The University of Missouri-Columbia (MU) Research Reactor Facility staff is in the process of upgrading the operational and research capabilities of the reactor and associated facilities. The upgrades include an extended life aluminide fuel element, a power increase, improved instrumentation and control equipment, a cold neutron source, a building addition, and improved research instrumentation and equipment. These upgrades will greatly enhance the capabilities of the facility and the research programs. This paper discusses the parts of the upgrade and current status of implementation. (author)

  14. Fuel burnup analysis of the TRIGA Mark II Reactor at the University of Pavia

    OpenAIRE

    Chiesa, Davide; Clemenza, Massimiliano; Pozzi, Stefano; Previtali, Ezio; Sisti, Monica; Alloni, Daniele; Magrotti, Giovanni; Manera, Sergio; Prata, Michele; Salvini, Andrea; Cammi, Antonio; Zanetti, Matteo; Sartori, Alberto

    2015-01-01

    A time evolution model was developed to study fuel burnup for the TRIGA Mark II reactor at the University of Pavia. The results were used to predict the effects of a complete core reconfiguration and the accuracy of this prediction was tested experimentally. We used the Monte Carlo code MCNP5 to reproduce system neutronics in different operating conditions and to analyse neutron fluxes in the reactor core. The software that took care of time evolution, completely designed in-house, used the n...

  15. Reference site selection report for the advanced liquid metal reactor at the Idaho National Engineering Laboratory

    International Nuclear Information System (INIS)

    This Reference Site Selection Report was prepared by EG ampersand G, Idaho Inc., for General Electric (GE) to provide information for use by the Department of Energy (DOE) in selecting a Safety Test Site for an Advanced Liquid Metal Reactor. Similar Evaluation studies are planned to be conducted at other potential DOE sites. The Power Reactor Innovative Small Module (PRISM) Concept was developed for ALMR by GE. A ALMR Safety Test is planned to be performed on a DOE site to demonstrate features and meet Nuclear Regulatory Commission Requirements. This study considered possible locations at the Idaho National Engineering Laboratory that met the ALMR Prototype Site Selection Methodology and Criteria. Four sites were identified, after further evaluation one site was eliminated. Each of the remaining three sites satisfied the criteria and was graded. The results were relatively close. Thus concluding that the Idaho National Engineering Laboratory is a suitable location for an Advanced Liquid Metal Reactor Safety Test. 23 refs., 13 figs., 9 tabs

  16. Progress state of the decommissioning of Rikkyo University reactor in FY2012

    International Nuclear Information System (INIS)

    Rikkyo University Atomic Energy Research Institute submitted the file for the decommissioning plan change in 2012 toward the reactor facility demolishment, received the approval, and is promoting the decommissioning work on the research reactor with a schedule for two years from 2012. Since the decommissioning work of FY2012 has finished, this paper reports this progress state. The contents of the decommissioning work plan are to make the reactor facilities stationary condition by performing the following works: (1) implementation of decontamination and removal of the core internals within nuclear reactor facilities, (2) attainment of the state, in which the operation associated with the generation of radioactive waste, does not occur, (3) stop of partial functions of the facilities under performance maintaining, including the disposal facilities of liquid waste, and (4) storage of dismantled materials in vessels after partial dismantling and removal. This paper reports the operations conducted in FY2012, such as the decontamination and removal of the core internals of the nuclear reactor, removal of pneumatic tubes and sample transfer tubes, and function stop measures for plumbing system belonging to the reactor accessory facilities. (A.O.)

  17. Advanced liquid metal reactor development at Argonne National Laboratory during the 1980s

    International Nuclear Information System (INIS)

    Argonne National Laboratory's (ANL'S) effort to pursue the exploitation of liquid metal cooled reactor (LMR) characteristics has given rise to the Integral Fast Reactor (IFR) concept, and has produced substantial technical advancement in concept implementation which includes demonstration of high burnup capability of metallic fuel, demonstration of injection casting fabrication, integral demonstration of passive safety response, and technical feasibility of pyroprocessing. The first half decade of the 90's will host demonstration of the IFR closed fuel cycle technology at the prototype scale. The EBR-II reactor will be fueled with ternary alloy fuel in HT-9 cladding and ducts, and pyroprocessing and injection casting refabrication of EBR-II fuel will be conducted using near-commercial sized equipment at the Fuel cycle Facility (FCF) which is co-located adjacent to EBR-II. Demonstration will start in 1992. The demonstration of passive safety response achievable with the IFR design concept, (already done in EBR-II in 1986) will be repeated in the mid 90's using the IFR prototype recycle fuel from the FCF. The demonstration of scrubbing of the reprocessing fission product waste stream, with recycle of the transuranics to the reactor for consumption, will also occur in the mid 90's. 30 refs

  18. Clinical and Laboratory evaluation of measleslike rash in children and young adults

    Directory of Open Access Journals (Sweden)

    Stewien Klaus Eberhard

    2000-01-01

    Full Text Available A clinical and laboratory evaluation of 11 children and young adults with measleslike rash was done during the measles outbreak in the Greater São Paulo Metropolitan area at the end of 1996 and spread over the country during 1997. Measles was laboratory confirmed in 07 patients by specific IgM detection in acute serum specimens using an IgM-capture EIA, by specific IgG seroconversion in serum pairs, and by reverse transcription PCR and virus isolation in peripheral blood lymphocytes. Clinical presentations were not always classic; one of the 07 cases had received measles vaccine and corresponded to modified clinical case of measles. The 4 remaining cases were negative for measles and were diagnosed as exanthem subitum (2 cases, scarlet fever and Kawasaki disease. The present study reinforces the view that clinical features alone are not sufficient for establishing an accurate diagnosis in the post-vaccine era, and a surveillance system based on sensitive laboratory results is needed so that it can confirm IgM-negative measles cases.

  19. Princeton University, Plasma Physics Laboratory annual report, October 1, 1988--September 30, 1989

    International Nuclear Information System (INIS)

    This report contains discussions on the following topics: principal parameters achieved in experimental devices (FY89); tokamak fusion test reactor; compact ignition tokamak; princeton beta experiment- modification; current drive experiment; international collaboration; x-ray laser studies; spacecraft glow experiment; plasma deposition and etching of thin films; theoretical studies; tokamak modeling; international thermonuclear experimental reactor; engineering department; project planning and safety office; quality assurance and reliability; technology transfer; administrative operations; PPPL patent invention disclosures for (FY89); graduate education: plasma physics; graduate education: plasma science and technology; and Princeton Plasmas Physics Laboratory Reports (FY89)

  20. Princeton University, Plasma Physics Laboratory annual report, October 1, 1988--September 30, 1989

    Energy Technology Data Exchange (ETDEWEB)

    1989-01-01

    This report contains discussions on the following topics: principal parameters achieved in experimental devices (FY89); tokamak fusion test reactor; compact ignition tokamak; princeton beta experiment- modification; current drive experiment; international collaboration; x-ray laser studies; spacecraft glow experiment; plasma deposition and etching of thin films; theoretical studies; tokamak modeling; international thermonuclear experimental reactor; engineering department; project planning and safety office; quality assurance and reliability; technology transfer; administrative operations; PPPL patent invention disclosures for (FY89); graduate education: plasma physics; graduate education: plasma science and technology; and Princeton Plasmas Physics Laboratory Reports (FY89).

  1. Princeton University, Plasma Physics Laboratory annual report, October 1, 1988--September 30, 1989

    Energy Technology Data Exchange (ETDEWEB)

    1989-12-31

    This report contains discussions on the following topics: principal parameters achieved in experimental devices (FY89); tokamak fusion test reactor; compact ignition tokamak; princeton beta experiment- modification; current drive experiment; international collaboration; x-ray laser studies; spacecraft glow experiment; plasma deposition and etching of thin films; theoretical studies; tokamak modeling; international thermonuclear experimental reactor; engineering department; project planning and safety office; quality assurance and reliability; technology transfer; administrative operations; PPPL patent invention disclosures for (FY89); graduate education: plasma physics; graduate education: plasma science and technology; and Princeton Plasmas Physics Laboratory Reports (FY89).

  2. Undergraduate reactor control experiment

    International Nuclear Information System (INIS)

    A sequence of reactor and related experiments has been a central element of a senior-level laboratory course at Pennsylvania State University (Penn State) for more than 20 yr. A new experiment has been developed where the students program and operate a computer controller that manipulates the speed of a secondary control rod to regulate TRIGA reactor power. Elementary feedback control theory is introduced to explain the experiment, which emphasizes the nonlinear aspect of reactor control where power level changes are equivalent to a change in control loop gain. Digital control of nuclear reactors has become more visible at Penn State with the replacement of the original analog-based TRIGA reactor control console with a modern computer-based digital control console. Several TRIGA reactor dynamics experiments, which comprise half of the three-credit laboratory course, lead to the control experiment finale: (a) digital simulation, (b) control rod calibration, (c) reactor pulsing, (d) reactivity oscillator, and (e) reactor noise

  3. Introduction of Kyoto University Research Reactor with low enriched uranium core

    International Nuclear Information System (INIS)

    Kyoto University Research Reactor (KUR) is a light water moderated / cooled tank-type reactor. The project to convert the KUR fuel from HEU to LEU was achieved on March 24, 2010. After the successful achievement of first criticality on April 15 and the reactor has been operating since May 28. The nuclear design of KUR with LEU core is calculated using SRAC code system with JENDL-3.3 and the burn-up calculations are performed using SRAC-COREBN. In this paper, the purpose of the project to convert the KUR fuel, the fuel transport, the experimental results, the burn-up characteristics and calculation of KUR LEU core are presented. (author)

  4. Associated Western Universities summer participant program at the Lawrence Livermore National Laboratory, Summer 1997

    Energy Technology Data Exchange (ETDEWEB)

    Williams, B.

    1997-08-01

    The Associated Western Universities, Inc. (AWU) supports a student summer program at Lawrence Livermore National Laboratory (LLNL). This program is structured so that honors undergraduate students may participate in the Laboratory`s research program under direct supervision of senior Laboratory scientists. Included in this report is a list of the AWU participants for the summer of 1997. All students are required to submit original reports of their summer activities in a format of their own choosing. These unaltered student reports constitute the major portion of this report.

  5. University of Florida--US Department of Energy 1994-1995 reactor sharing program

    Energy Technology Data Exchange (ETDEWEB)

    Vernetson, W.G.

    1996-06-01

    The grant support of $24,250 (1994-95?) was well used by the University of Florida as host institution to support various educational institutions in the use of UFTR Reactor. All users and uses were screened to assure the usage was for educational institutions eligible for participation in the Reactor Sharing Program; where research activities were involved, care was taken to assure the research was not funded by grants for contract funding from outside sources. Over 12 years, the program has been a key catalyst for renewing utilization of UFTR both by external users around the State of Florida and the Southeast and by various faculty members within the University of Florida. Tables provide basic information about the 1994-95 program and utilization of UFTR.

  6. Ten-year utilization of the Oregon State University TRIGA Reactor (OSTR)

    International Nuclear Information System (INIS)

    The Oregon State University TRIGA Reactor (OSTR) has been used heavily throughout the past ten years to accommodate exclusively university research, teaching, and training efforts. Averages for the past nine years show that the OSTR use time has been as follows: 14% for academic and special training courses; 44% for OSU research projects; 6% for non-OSU research projects; 2% for demonstrations for tours; and 34% for reactor maintenance, calibrations, inspections, etc. The OSTR has operated an average of 25.4 hours per week during this nine-year period. Each year, about 20 academic courses and 30 different research projects use the OSTR. Visitors to the facility average about 1,500 per year. No commercial radiations or services have been performed at the OSTR during this period. Special operator training courses are given at the OSTR at the rate of at least one per year. (author)

  7. Analysis of kyoto university reactor physics critical experiments using NCNSRC calculation methodology

    International Nuclear Information System (INIS)

    The kyoto university reactor physics experiments on the university critical assembly is used to benchmark validate the NCNSRC calculations methodology. This methodology has two lines, diffusion and Monte Carlo. The diffusion line includes the codes WIMSD4 for cell calculations and the two dimensional diffusion code DIXY2 for core calculations. The transport line uses the MULTIKENO-Code vax Version. Analysis is performed for the criticality, and the temperature coefficients of reactivity (TCR) for the light water moderated and reflected cores, of the different cores utilized in the experiments. The results of both Eigen value and TCR approximately reproduced the experimental and theoretical Kyoto results. However, some conclusions are drawn about the adequacy of the standard wimsd4 library. This paper is an extension of the NCNSRC efforts to assess and validate computer tools and methods for both Et-R R-1 and Et-MMpr-2 research reactors. 7 figs., 1 tab

  8. University of Florida--US Department of Energy 1994-1995 reactor sharing program

    International Nuclear Information System (INIS)

    The grant support of $24,250 (1994-95?) was well used by the University of Florida as host institution to support various educational institutions in the use of UFTR Reactor. All users and uses were screened to assure the usage was for educational institutions eligible for participation in the Reactor Sharing Program; where research activities were involved, care was taken to assure the research was not funded by grants for contract funding from outside sources. Over 12 years, the program has been a key catalyst for renewing utilization of UFTR both by external users around the State of Florida and the Southeast and by various faculty members within the University of Florida. Tables provide basic information about the 1994-95 program and utilization of UFTR

  9. Decommissioning of an argonaut type reactor at the Technical University of Catalonia in Barcelona (Spain)

    International Nuclear Information System (INIS)

    The reactor ARGOS is a training nuclear reactor that was active, from 1962 to 1976, at the Technical University of Catalonia (UPC) in Barcelona (Spain). It is an Argonaut type experimental Reactor with 10 kW of maximal thermal power, and was set up by the main Spanish Nuclear Research Centre, presently named CIEMAT, in the period 1958-1962. In 1977, the nuclear installation was halted for technical, economical and administrative reasons. The fuel burn-up of the reactor was 2.7 kWh. In 1992 the fuel was removed from the site and a dismantling project was launched by an academic team of the UPC Nuclear Energy Department. In 1998 the Spanish authorities approved the dismantling plan which was based on the IAEA document Planning and Management of the Decommissioning of Research and Other Small Nuclear Facilities, IAEA 1993. In this plan the University proposed to set up its own dismantling group mainly based on its own academic staff and experimental facilities

  10. Evaporation Basin Test Reactor Area, Idaho National Engineering Laboratory: Environmental assessment

    International Nuclear Information System (INIS)

    The Department of Energy (DOE) has prepared an environmental assessment (EA), DOE/EA-0501, on the construction and operation of the proposed Evaporation Basin at the Test Reactor Area (TRA) at the Idaho National Engineering Laboratory (INEL) near Idaho Falls, Idaho. Based on the analyses in the EA, DOE has determined that the proposed action is not a major Federal action significantly affecting the quality of the human environment, within the meaning of the National Environmental Policy Act (NEPA) of 1969. Therefore, the preparation of an environmental impact statement (EIS) is not required, and the Department is issuing this Finding of No Significant Impact

  11. Scottish Universities Research and Reactor Centre, East Kilbride. Report on session 1982-1983

    International Nuclear Information System (INIS)

    The activities over the 1982-3 session are reviewed and all the research projects listed. These include reactor related activities (physics and radiochemistry, health physics and nuclear medicine and engineering), those of the isotope geology unit and NERC radiocarbon laboratory, the computing department and the teaching programme. The demand for irradiations, particularly for activation analysis has continued. There was no major maintenance shut-down in the year. (U.K.)

  12. Report of the research results with University of Tokyo, Nuclear Engineering Research Laboratory's Facilities in fiscal 1982

    International Nuclear Information System (INIS)

    The results of the research carried out in fiscal 1982 commonly using the facilities in the Nuclear Engineering Research Laboratory, University of Tokyo, are summarized in this report. In the utilization of the nuclear reactor, the maximum output was limited to 500W, because it was necessary to examine the growth of the abnormal protrusion having arisen on fuel cladding. The linear accelerator was utilized almost perfectly. The total number of those who commonly utilized the facilities was 2,468, suggesting the importance of the role of common utilization. The summaries of the results of 12 on-pile researches, 11 off-pile researches and 18 researches using the linear accelerator are collected. The committee meetings held in fiscal 1982 are listed. The names of the members of various committees and the names of those in charge of various experiments are given. (Kako, I.)

  13. Fuel burnup analysis of the TRIGA Mark II Reactor at the University of Pavia

    CERN Document Server

    Chiesa, Davide; Pozzi, Stefano; Previtali, Ezio; Sisti, Monica; Alloni, Daniele; Magrotti, Giovanni; Manera, Sergio; Prata, Michele; Salvini, Andrea; Cammi, Antonio; Zanetti, Matteo; Sartori, Alberto

    2015-01-01

    A time evolution model was developed to study fuel burnup for the TRIGA Mark II reactor at the University of Pavia. The results were used to predict the effects of a complete core reconfiguration and the accuracy of this prediction was tested experimentally. We used the Monte Carlo code MCNP5 to reproduce system neutronics in different operating conditions and to analyse neutron fluxes in the reactor core. The software that took care of time evolution, completely designed in-house, used the neutron fluxes obtained by MCNP5 to evaluate fuel consumption. This software was developed specifically to keep into account some features that differentiate experimental reactors from power ones, such as the daily ON/OFF cycle and the long fuel lifetime. These effects can not be neglected to properly account for neutron poison accumulation. We evaluated the effect of 48 years of reactor operation and predicted a possible new configuration for the reactor core: the objective was to remove some of the fuel elements from the...

  14. 'Experience with decommissioning of research and test reactors at Argonne National Laboratory'

    International Nuclear Information System (INIS)

    A large number of research reactors around the world have reached the end of their useful operational life. Many of these are kept in a controlled storage mode awaiting decontamination and decommissioning (D and D). At Argonne National Laboratory located near Chicago in the United States of America, significant experience has been gained in the D and D of research and test reactors. These experiences span the entire range of activities in D and D - from planning and characterization of the facilities to the eventual disposition of all waste. A multifaceted D nd D program has been in progress at the Argonne National Laboratory - East site for nearly a decade. The program consists of three elements: - D and D of nuclear facilities on the site that have reached the end of their useful life; - Development and demonstrations of technologies that help in safe and cost effective D and D; - Presentation of training courses in D and D practices. Nuclear reactor facilities have been constructed and operated at the ANL-E site since the earliest days of nuclear power. As a result, a number of these early reactors reached end-of-life long before reactors on other sites and were ready for D and D earlier. They presented an excellent set of test beds on which D and D practices and technologies could be demonstrated in environments that were similar to commercial reactors, but considerably less hazardous. As shown, four reactor facilities, plutonium contaminated glove boxes and hot cells, a cyclotron facility and assorted other nuclear related facilities have been decommissioned in this program. The overall cost of the program has been modest relative to the cost of comparable projects undertaken both in the U.S. and abroad. The safety record throughout the program was excellent. Complementing the actual operations, a set of D and D technologies are being developed. These include robotic methods of tool handling and operation, chemical and laser decontamination techniques, sensors

  15. Wildlife, Snow, Coffee, and Video: The IPY Activities of the University of Alaska Young Researchers' Network

    Science.gov (United States)

    Pringle, D.; Alvarez-Aviles, L.; Carlson, D.; Harbeck, J.; Druckenmiller, M.; Newman, K.; Mueller, D.; Petrich, C.; Roberts, A.; Wang, Y.

    2007-12-01

    The University of Alaska International Polar Year (IPY) Young Researchers' Network is a group of graduate students and postdoctoral fellows. Our interdisciplinary group operates as a volunteer network to promote the International Polar Year through education and outreach aimed at the general public and Alaskan students of all ages. The Young Researchers' Network sponsors and organizes science talks or Science Cafés by guest speakers in public venues such as coffee shops and bookstores. We actively engage high school students in IPY research concerning the ionic concentrations and isotopic ratios of precipitation through Project Snowball. Our network provides hands-on science activities to encourage environmental awareness and initiate community wildlife monitoring programs such as Wildlife Day by Day. We mentor individual high school students pursuing their own research projects related to IPY through the Alaska High School Science Symposium. Our group also interacts with the general public at community events and festivals to share the excitement of IPY for example at the World Ice Art Championship and Alaska State Fair. The UA IPY Young Researchers' Network continues to explore new partnerships with educators and students in an effort to enhance science and education related to Alaska and the polar regions in general. For more information please visit: http://ipy-youth.uaf.edu or e-mail: ipy-youth@alaska.edu

  16. Academic Self-Concept and Motivation in Young Talents of a Private University in Tarapoto

    Directory of Open Access Journals (Sweden)

    Renzo F. Carranza

    2015-03-01

    Full Text Available The objective of this study was to determine the relationship between academic self-concept and academic motivation in young talents (Scholarship 18 at a Private University in Tarapoto city, Peru. The sample was obtained through a probabislitic sampling and there were 92 young talents, being 47,8% male and 52,2% female between 17 and 22 years old. I used a descriptive, correlational and non-experimental design. The sample was evaluated using the AF5 Self-concept Scale (García and Musitu academic section that consists of 6 items, and the Academic Motivation Scale that consists of 28 items. The psychometric properties of the instruments indicated that they are valid and reliable. Data were processed in SPSS (Statistical Package for the Social Sciences version 20.0. The results show that there is a direct and highly significant relationship between academic self-concept and academic motivation in young talents (r = .301**, p<.004, which indicates the higher the academic self-concept, the greater the academic motivation.

  17. University of Illinois at Urbana-Champaign, Materials Research Laboratory progress report for FY 1991

    International Nuclear Information System (INIS)

    The Materials Research Laboratory at the University of Illinois is an interdisciplinary laboratory operated in the College of Engineering. Its focus is the science of materials and it supports research in the areas of condensed matter physics, solid state chemistry, and materials science. This report addresses topics such as: an MRL overview; budget; general programmatic and institutional issues; new programs; research summaries for metallurgy, ceramics, solid state physics, and materials chemistry

  18. University of Illinois at Urbana-Champaign, Materials Research Laboratory progress report for FY 1991

    Energy Technology Data Exchange (ETDEWEB)

    1991-10-01

    The Materials Research Laboratory at the University of Illinois is an interdisciplinary laboratory operated in the College of Engineering. Its focus is the science of materials and it supports research in the areas of condensed matter physics, solid state chemistry, and materials science. This report addresses topics such as: an MRL overview; budget; general programmatic and institutional issues; new programs; research summaries for metallurgy, ceramics, solid state physics, and materials chemistry.

  19. The filter-press FM01-LC laboratory flow reactor and its applications

    International Nuclear Information System (INIS)

    The FM01-LC is a laboratory-scale, electrochemical filter-press cell with a projected electrode area of 64 cm2 and a rectangular electrolyte flow channel which was originally based on the larger FM21-SP electrolyser of 2100 cm2 projected electrode area designed for the chlor-alkali industry then diversified to other applications. Many laboratories and industries have utilised this type of controlled flow reactor containing plane parallel electrodes in a rectangular channel for industrial and commercial applications. The diverse range of electrodes possible in such cells is emphasized with examples including 3-D metals and carbon, coated metal electrodes and nanostructured surfaces offering a high surface area. The experimental characterization and computational modelling of its reaction environment are concisely described discussed to appreciate the features of this type of electrochemical reactor. The cell construction and reaction environment are summarized, followed by an illustration of its use for a range of applications that include organic and inorganic electrosynthesis, metal ion removal, energy storage, environmental remediation (e.g., precious metal recycling or anodic destruction of organics) and drinking water treatment. Examples of the cell for energy conversion and storage (flow batteries and proton exchange membrane fuel cells) are briefly illustrated. The use of such a flow cell for the characterization of new electrochemical processes and to provide data enabling scale-up is considered

  20. Laboratory Scale Study of Activated Sludge Process in Jet Loop Reactor for Waste WaterTreatment

    Directory of Open Access Journals (Sweden)

    M. S. Patil

    2014-03-01

    Full Text Available The present study was undertaken to evaluate the feasibility of Activated Sludge Process (ASP for the treatment of synthetic wastewater and to develop a simple design criteria under local conditions.A laboratory scale Compact jet loop reactor model comprising of an aeration tank and final clarifier was used for this purpose.Settled synthetic wastewater was used as influent to the aeration tank. The Chemical Oxygen Demand (COD of the influent and effluent was measured to find process efficiency at various mixed liquorvolatile suspended solids (MLVSS and hydraulic retention time (θ. The results of the studydemonstrated that an efficiency of above 95% could be obtained for COD if the ASP is operated atan MLVSS concentration of 3000 mg/L keeping an aeration time of 1 hour.In the present investigation the preliminary studies were carried out in a lab scale Jet loop reactor made of glass. Synthetic waste water having a composition of 1000 mg/L mixed with other nutrients such as Urea, Primary and secondary Potassium phosphates, Magnesium sulfate, Iron chloriderequired for the bacteria was prepared in the laboratory and reduction in COD and the increase inSuspended Solids (SSand the Sludge Volume Index (SVI were determined.

  1. Sexual Education of Young University Students: Some Key Factors and Challenges

    Directory of Open Access Journals (Sweden)

    María Luisa Preinfalk-Fernández

    2015-09-01

    Full Text Available In general terms, higher education institutions not only face the challenge of teaching some discipline to their students, but also of strengthening their life skills. Since university students are majorly young, the desire to provide them with comprehensive training is particularly relevant, since it is at this stage of life when they model their behavior for adulthood. In this training challenge, sex education plays a decisive role. This research paper aims to show that factors such as information gaps, unsafe sexual practices, myths, prejudices and stereotypes persist in the university student population and do not allow them to live sexuality safely and pleasurable. Moreover, these factors show Costa Rica’s need for higher education institutions to strengthen their actions in sex education. A brief tour is made from various angles through the sexual experiences of the university student population, namely: their perceptions about the training requirements they face, their main concerns, their unsafe sexual practices, their inability to negotiate sexual and reproductive health care, their knowledge and preventive practices in terms of sexual and reproductive health, the existence of forms of violence within university life, among others. The findings set out are part of a larger research, based on contributions from the theory of gender and social constructionism. Such data derives from the application of a questionnaire to a sample stratified by unequal conglomerates composed of 766 regular students of undergraduate courses, enrolled in the first cycle of 2011, at Universidad Nacional de Costa Rica. The margin of error is 1.5% and the confidence level, 95%. The data was tabulated using the software CSPRO and analyzed with software R. After obtaining the results of the instrument’s application, a focus group was created with the participation of professionals who teach sexuality courses in this university, and two other groups with

  2. Decontamination and decommissioning of the Experimental Boiling Water Reactor at Argonne National Laboratory

    International Nuclear Information System (INIS)

    The Experimental Boiling Water Reactor (EBWR), located on the Argonne National Laboratory-East (ANL-E) site, started operations in 1957. The initial rating was 20 MW(t). The rating was eventually increased to 70 MW(t) in 1959 and 100 MW(t) in 1962. The reactor was shut down in 1967 and all of the fuel was removed from the facility. The facility was placed in dry lay-up until 1986. ANL-E personnel started the decontamination and decommissioning (D ampersand D) effort in 1986. Supporting equipment such as the external steam system and some of the upper reactor components, the core riser and the top fuel shroud, were removed at that time. Characterization of the facility was also undertaken. The contract to complete the EBWR D ampersand D Project was issued in December 1993. The initial schedule called for the final effort to be divided into five phases that were to be completed over a four year period. However, this schedule was subsequently consolidated, at the request of ANL-E, to a thirteen month period, with the on-site work to be completed by the end of 1994. The EBWR D ampersand D Project is approximately 88% complete. A small quantity of reactor internals remains to be volume reduced along with the removal of the SFSP water treatment system. Upon completion of this work the facility will be decontaminated and a final survey completed. The planned completion of on-site work is scheduled for July 1995

  3. Accelerator Laboratory of the University and the Technical University of Munich. Annual report 1992

    International Nuclear Information System (INIS)

    This report contains extended abstracts about the work performed at the named laboratory together with a list of publications and reports. The abstracts concern experiments on nuclear reactions, nuclear spectroscopy, atomic physics, accelerator mass spectroscopy with heavy ions, and applications of nuclear techniques, theoretical work on nuclear reactions, nuclear structure, atomic physics, and astrophysics, developments of accelerators and radiation instrumentation, as well as data processing. (HSI)

  4. Radiochemistry at the University of Missouri-Columbia. A joint venture with chemistry, nuclear engineering, molecular biology, biochemistry, and the Missouri University Research Reactor (MURR)

    International Nuclear Information System (INIS)

    Missouri University, a recipient of a U.S. Department of Energy Radiochemistry Education Award Program (REAP) grant in 1999, has significantly expanded its education and research mission in radiochemistry. While MU had a viable radiochemistry program through existing faculty expertise and the utilization of the Missouri University Research Reactor, the REAP award allowed MU to leverage its resources in significantly expanding capabilities in radiochemistry. Specifically, the grant enabled the: (1) hiring of a new faculty member in actinide radiochemistry (Dr. Paul Duval); (2) support of six graduate students in radiochemistry; (3) purchase of new radiochemistry laboratory equipment; (4) more extensive collaboration with DOE scientists through interactions with faculty and graduate students, and (5) revised radiochemical curriculum (joint courses across disciplines and new courses in actinide chemistry). The most significant impact of this award has been in encouraging interdisciplinary education and research. The proposal was initiated by a joint effort between Nuclear Engineering and Chemistry, but also included faculty in biochemistry, radiology, and molecular biology. Specific outcomes of the REAP grant thus far are: (1) increased educational and research capabilities in actinide chemistry (faculty hire and equipment acquisition); (2) increased integration of biochemistry and radiochemistry (e.g., radiochemical analysis of uranium speciation in biological systems); (3) stronger interdisciplinary integration of molecular biology and radiochemical sciences (alpha-emitters for treating cancer); (4) new and more extensive interactions with national laboratory facilities (e.g., student internships at LANL and LLBL, faculty and lab scientist exchange visits, analytical measurements and collaboration with the Advanced Photon Source), and (7) new research funding opportunities based on REAP partnership. (author)

  5. The perceptions, views and opinions of university students about physics learning during undergraduate laboratory work

    International Nuclear Information System (INIS)

    The physics laboratory has long been a distinctive feature of physics education. It has been given a central role in the teaching and learning of physics at school and undergraduate levels in universities. The literature indicates that science educators have suggested that there are academically rich benefits in the learning and understanding of physics based on laboratory work. However, some educators have begun to raise serious and valid questions about the effectiveness of the learning through laboratory work in science subjects and the heavy cost for the establishment and maintenance of laboratories. This research paper provides perspectives on these issues through a brief review of the history, goals and objectives related to the physics undergraduate laboratory. An empirical research study was conducted to determine the university students' perceptions, views and opinions with regard to physics learning during undergraduate laboratory work. This involved 143 students from first and higher years and the evidence was gathered by survey and focus group interviews, the former using a variety of types of questions. The evidence from the students is positive and suggests that undergraduate physics laboratory work may well be contributing towards the achievement of specific desirable goals

  6. Management of nuclear knowledge on an international scale using a small university research reactor

    International Nuclear Information System (INIS)

    Full text: The Atominstitut Vienna operates a 250 kW TRIGA Mark-II reactor since March 1962 used for nuclear education and training in the fields of neutron- and solid state physics, nuclear technology, reactor safety, radiochemistry, radiation protection, dosimetry, low temperature physics and fusion research. During the past 20 years about 640 students graduated with a diploma - or PhD degree from the Atominstitut attached to the University of Technology Vienna. To perform nuclear relevant academic studies the Atominstitut offers about 100 highly specialised theoretical lectures and about 10 practical courses where students have to perform experiments in small groups of four on subjects mentioned above. Although the TRIGA reactor is a rather low power research reactor it is very easy and cheap to operate and an excellent tool to transfer knowledge and experience to the younger generation. This reactor is therefore not only used by other European universities such as University of Manchester or Bratislava Technical University but also by nuclear institutions such as the GRS/Germany, NPP Bohunice and NPP Mochovce for nuclear training. On an international scale the Atominstitut co-operates closely with the nearby located IAEA in international research projects, coordinated research programs (CRP) and supplying expert services. Regular training courses are carried out for the IAEA for Safeguard Trainees, fellowship places are offered for scientists from developing countries and staff members carry out expert missions to research centres in Africa, Asia and South America. In the past 20 years more than 120 IAEA fellows from all over the world have been trained at the Atominstitut. The fellows spend between one to twelve month at the Atominstitut and are integrated in the respective work program. Experience showed that out of this fellowship a long-term relation between the institutes continues. The paper focuses especially on the transfer of knowledge between

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

    International Nuclear Information System (INIS)

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

  8. The relationship between alcohol consumption and related harm among young university students.

    Science.gov (United States)

    Hart, Ellen; Burns, Sharyn

    2016-04-01

    Issue addressed Research has shown that Australian university students consume alcohol at a higher level than their peers from the general population and are therefore more likely to witness and experience alcohol-related harm. This study measured the prevalence of alcohol consumption among 18-24-year-old university students and the association between alcohol consumption and witnessed and experienced harms. Methods A random cross-sectional sample of university students aged 18-24 years (n=2466) was recruited via the University Survey Office and through random intercept at campus market day. All participants completed an online survey that included the Alcohol Use Disorders Identification Test, Alcohol Problems Scale and an additional scale measuring witnessed harm. Results Principal Components Analysis revealed three factors within the Alcohol Problems Scale; i.e. Criminal and Aggressive Behaviour, Health and Emotional Harms and Sexual Harms. Students who consume alcohol at high-risk levels were significantly more likely to score highly on each factor, 1.6 times more likely to experience harm and 1.1 times more likely to witness harm than students who consume alcohol at low-risk levels. Conclusions The positive association between alcohol consumption and alcohol-related harm supports previous findings. This study adds previous research through the categorisation of harm into factors. So what? Integrated and comprehensive interventions addressing alcohol consumption among young university students that are informed by evidence-based research can be tailored to ensure that they meet the needs of the target group. PMID:26827614

  9. Education and research at clean room laboratory for silicon device technology at Masaryk University

    Czech Academy of Sciences Publication Activity Database

    Mikulík, P.; Humlíček, J.; Kulha, P.; Hovorka, Miloš; Kadlec, Filip

    Warsaw: University of Warsaw, 2010. s. 242. ["Jaszowiec" International School and Conference on the Physics of Semiconductors /39./. 19.06.2010-24.06.2010, Krynica Zdroj] Institutional research plan: CEZ:AV0Z20650511; CEZ:AV0Z10100520 Keywords : silicon * clean room * microelectronics laboratory Subject RIV: BM - Solid Matter Physics ; Magnetism

  10. Annual report of Radiation Laboratory Department of Nuclear Engineering Faculty of Engineering, Kyoto University

    International Nuclear Information System (INIS)

    This publication is the collection of the papers presented research activities of Radiation laboratory, Department of Nuclear Engineering, Kyoto University during the 1992 academic/fiscal year (April, 1992 - March, 1993). The 48 of the presented papers are indexed individually. (J.P.N.)

  11. The Perceptions, Views and Opinions of University Students about Physics Learning during Undergraduate Laboratory Work

    Science.gov (United States)

    Hanif, M.; Sneddon, P. H.; Al-Ahmadi, F. M.; Reid, N.

    2009-01-01

    The physics laboratory has long been a distinctive feature of physics education. It has been given a central role in the teaching and learning of physics at school and undergraduate levels in universities. The literature indicates that science educators have suggested that there are academically rich benefits in the learning and understanding of…

  12. Annual report of Radiation Laboratory Department of Nuclear Engineering Kyoto University for fiscal 1993

    International Nuclear Information System (INIS)

    This publication is the collection of the papers presented research activities of Radiation Laboratory, Department of Nuclear Engineering, Kyoto University during the 1993 academic/fiscal year (April, 1993 - March, 1994). The 47 of the presented papers are indexed individually. (J.P.N.)

  13. Building a Low-Cost Gross Anatomy Laboratory: A Big Step for a Small University

    Science.gov (United States)

    Goldman, Evan

    2010-01-01

    This article illustrates details of the planning, building, and improvement phases of a cost-efficient, full-dissection gross anatomy laboratory on a campus of an historically design-centric university. Special considerations were given throughout the project to the nature of hosting cadavers in a building shared amongst all undergraduate majors.…

  14. Annual report of Laboratory of Nuclear Studies, Osaka University, Jan. 1974 - Dec. 1974

    International Nuclear Information System (INIS)

    Activities of the Laboratory of Nuclear Studies, Osaka University, for the period of January to December 1974, are presented in short individual summaries, including outside publications: Cyclotron Division, High Voltage Accelerator Division, Mass Spectroscopy Division, Radioisotope Division, and Theoretical Division. (Mori, K.)

  15. Building an optomechatronics group in a young university in Western Romania

    Science.gov (United States)

    Duma, Virgil-Florin; Hutiu, Gheorghe; Cira, Octavian; Demian, Dorin; Mnerie, Corina; Kaposta, Iosif

    2014-07-01

    We present our experience regarding the establishing of an interdisciplinary group with Optics as one of its main topic at the Aurel Vlaicu University of Arad (UAVA) - linked with the improvement through research of our educational activities. The 3OM Group (in Opto-Mechatronics, Optical Metrology, and Optics and Mechanics) is described in its evolution from optomechanics to photonics, the latter with a focus on OCT (Optical Coherence Tomography) - with the national and the international collaborations established, with universities from Romania, Europe and USA. While the research directions of the 3OM Group are presented, they are linked with the educational components implemented in the various subjects we teach, for both undergraduate and graduate students, both in Mechanical and in Electrical Engineering. The main effort is to integrate education and research, to move teaching beyond the classical aspects to put the stress on hands-on-experiments, as well as on research-based activities - even with undergraduates. The main goals of this approach are to obtain an early orientation towards innovation and discovery, with a taste for novelties and with a clear focus on international standards. While this account is only one of many, it offers our experience in passing through the difficulties of developing both research and education in Optics in a young university in an emergent economy in Eastern Europe.

  16. Reliability and validity of job content questionnaire for university research laboratory staff in Malaysia.

    Science.gov (United States)

    Nehzat, F; Huda, B Z; Tajuddin, S H Syed

    2014-03-01

    Job Content Questionnaire (JCQ) has been proven a reliable and valid instrument to assess job stress in many countries and among various occupations. In Malaysia, both English and Malay versions of the JCQ have been administered to automotive workers, schoolteachers, and office workers. This study assessed the reliability and validity of the instrument with research laboratory staff in a university. A cross sectional study was conducted among 258 research laboratory staff in Universiti Putra Malaysia (UPM). Malaysian laboratory staff who have worked for at least one year were randomly selected from nine faculties and institutes in the university that have research laboratory. A self-administered English and Malay version of Job Content Questionnaire (JCQ) was used. Three major scales of JCQ: decision latitude, psychological job demands, and social support were assessed. Cronbach's alpha coefficients of two scales were acceptable, decision latitude and psychological job demands (0.70 and 0.72, respectively), while Cronbach's alpha coefficient for social support (0.86) was good. Exploratory factor analysis showed five factors that correspond closely to the theoretical construct of the questionnaire. The results of this research suggest that the JCQ is reliable and valid for examining psychosocial work situations and job strain among research laboratory staff. Further studies should be done for confirmative results, and further evaluation is needed on the decision authority subscale for this occupation. PMID:24968690

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

    International Nuclear Information System (INIS)

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

  18. Status of University of Cincinnati reactor-site nuclear engineering graduate programs

    International Nuclear Information System (INIS)

    The University of Cincinnati (UC) nuclear engineering program faculty has now had 12 yr of experience in delivering reactor-site educational programs to nuclear power plant technical personnel. Currently, with the sponsorship of the Toledo-Edison Company (TED), we are conducting a multiyear on-site graduate program with more than 30 participants at the Davis-Besse nuclear power plant. The program enables TED employees with the proper academic background to earn a master of science (MS) degree in nuclear engineering (mechanical engineering option). This paper presents a brief history of tile evolution of UC reactor-site educational programs together with a description of the progress of the current program

  19. Evidence of possible flooding of the reflector at the Oregon State University TRIGA reactor

    International Nuclear Information System (INIS)

    There is evidence to indicate that water may have flooded the void spaces inside the aluminum cladding which surrounds the graphite reflector at the Oregon State University TRIGA reactor (OSTR). This paper presents and discusses this evidence, as well as data from a number of experiments which were performed in an attempt to confirm whether or not flooding actually has occurred. The safety implications of a flooded reflector are presented and shown to be of little concern based in part on the OSTR's history of high water purity in the reactor tank. It is concluded that the sole concern is a reduction in the usefulness of certain beam ports. Proposed methods of surveillance to detect corrosion of the reflector cladding are also briefly discussed. (author)

  20. The research reactor TRIGA Mark II of the Johannes Gutenberg-University Mainz

    Energy Technology Data Exchange (ETDEWEB)

    Hampel, Gabriele; Eberhardt, Klaus [Mainz Univ. (Germany). Inst. of Nuclear Chemistry

    2012-10-15

    The TRIGA Mark II research reactor of the University of Mainz was built in the 1960ies on the initiative of Fritz Strassmann, co-discoverer of the fission, at that time the director of the Institute for Inorganic and Nuclear Chemistry. On August 3{sup rd}, 1965 the TRIGA Mainz reached first criticality with the insertion of the 57{sup th} fuel element in the reactor core. Two years later, in April 1967, the Nobel Prize laureate Otto Hahn initiated the first of now more than 18,000 pulses at the official inauguration. Since then, the TRIGA Mainz has operated without failure about 200 days per year. The TRIGA Mainz can be operated in the steady state mode at power levels ranging up to 100 kW{sub th}, depending on the requirements of the different experiments. Pulse-mode operation is also possible. (orig.)

  1. The research reactor TRIGA Mark II of the Johannes Gutenberg-University Mainz

    International Nuclear Information System (INIS)

    The TRIGA Mark II research reactor of the University of Mainz was built in the 1960ies on the initiative of Fritz Strassmann, co-discoverer of the fission, at that time the director of the Institute for Inorganic and Nuclear Chemistry. On August 3rd, 1965 the TRIGA Mainz reached first criticality with the insertion of the 57th fuel element in the reactor core. Two years later, in April 1967, the Nobel Prize laureate Otto Hahn initiated the first of now more than 18,000 pulses at the official inauguration. Since then, the TRIGA Mainz has operated without failure about 200 days per year. The TRIGA Mainz can be operated in the steady state mode at power levels ranging up to 100 kWth, depending on the requirements of the different experiments. Pulse-mode operation is also possible. (orig.)

  2. A climatological study on winds at the Kyoto University Reactor site

    International Nuclear Information System (INIS)

    A climatological study of winds at the Kyoto University Reactor (KUR) site is done by using the data from the Automated Meteorological Data Acquisition System of Japan Meteorological Agency, with a view to supporting the operations for environmental protection in case of reactor accident. At the KUR site, the land and sea breeze is appeared for one-third, a considerable part, of the year. The sea breezes from the Osaka Bay and the Kii Channel are clearly discernible, for each of which the different patterns of the diurnal variation of wind are built up at the site. For strong southerly wind experienced at the site under conditions that winds owing to synoptic pressure pattern are predominant, variable wind directions are seen in some observing stations in the Osaka plain, which is in contrast with strong westerly wind which shows a uniform flow in the Osaka plain. (author)

  3. Annual report 1991 of Munich University and Technical University Accelerator Laboratory

    International Nuclear Information System (INIS)

    The experimental work in the Accelerator Laboratory contains investigations of nuclear reactions and nuclear structure, studies of atom physics and the application of nuclear physics methods in physics and in interdisciplinary research. These applications are acceleration mass spectrometry to detect traces of radio-isotopes and material analysis with particle beams. The development of apparatus in the fields of accelereator construction, ion sources and targets are at the heart of the laboratory and help to establish its reputation. They are of the greatest importance for the education of students. The development stage for the superconducting post-accelerator TRITRON is complete and prototypes of the magnets and resonators were successfully tested and operated. The mass-production of all the components is under way or already finished. The standard injector for the tandem axxelerator and an injector for accelerator mass spectroscopy with stable isotopes are being newly designed. The experimental work is supplemented by the calculations of our theoretical collagues of core reaction mechanisms, core de-excitation and the Cerenkov radiation of core structures and transition strengths, by relativistic Hartree-Fock calculations and by star model calculations. (orig.)

  4. Safety Re-evaluation of Kyoto University Research Reactor by reflecting the Accident of Fukushima Daiichi Nuclear Power Plant

    Energy Technology Data Exchange (ETDEWEB)

    Nakajima, K.; Yamamoto, T. [Kyoto Univ., Kyoto (Japan)

    2013-07-01

    Kyoto University Research Reactor (KUR) is a light-water moderated tank-type reactor operated at rated thermal power of 5MW. After the accident of Fukushima Daiichi nuclear power plant, we have settled a 40-ton water tank near the reactor room, and prepared a mobile fire pump and a mobile power generator as additional safety measures for beyond design basis accidents (BDBAs). We also have conducted the safety re-evaluation of KUR, and confirmed that the integrity of KUR fuels could be kept against the BDBA with the use of the additional safety measures when the several restrictions were imposed on the reactor operation.

  5. Intrinsic religiousness and spirituality as predictors of mental health and positive psychological functioning in Latter-Day Saint adolescents and young adults.

    Science.gov (United States)

    Sanders, Peter W; Allen, G E Kawika; Fischer, Lane; Richards, P Scott; Morgan, David T; Potts, Richard W

    2015-06-01

    We investigated the relationships between religiousness and spirituality and various indicators of mental health and positive psychosocial functioning in three separate samples of college students. A total of 898 students at Brigham Young University participated in the three studies. The students ranged in age from 17 to 26 years old, with the average age of 20.9 across all three samples. Our results indicate that intrinsic religiousness, spiritual maturity, and self-transcendence were significantly predictive of better mental health and positive functioning, including lower levels of depression, anxiety, and obsessive-compulsiveness, and higher levels of global self-esteem, identity integration, moral self-approval, and meaning in life. Intrinsic religiousness was not predictive of shame, perfectionism, and eating disorder symptoms. These findings are consistent with many prior studies that have found religiousness and spirituality to be positively associated with better mental health and positive psychosocial functioning in adolescents and young adults. PMID:25854319

  6. Operational Experience On Ageing Management At The TRIGA Research Reactor Of LENA (Laboratory of Applied Nuclear Energy) - Univ. of Pavia (Italy) -

    Energy Technology Data Exchange (ETDEWEB)

    Magrotti, G.; Alloni, D.; Bellani, G.; Giordand, M.; Lana, F.; Manera, S.; Marchetti, F.; Prata, M.; Salvini, A.; Vinciguerra, G. [Univ. of Pavia, Pavia (Italy)

    2013-07-01

    The Laboratory of Applied Nuclear Energy ('LENA') of the University of Pavia operates, since 1965, a 250 kW TRIGA Mark II nuclear research reactor providing training and services to private enterprises and public institutions as well as being involved in several research projects carried out by the University and other research groups. Being an almost fifty years old facility, ageing, together with its potential premature failures, is a key point in the reactor safety. For these reason, in order to mitigate ageing effects, the facility has had to deal with several issues due to the time-dependent degradation of its structures, systems and components (SSCs). After an accurate assessment of SSCs conditions and the identification of ageing mechanisms, during the past years, several activities were successfully carried out. The paper will provide an overview of the above-mentioned topics and the forthcoming plans, together with lessons learned on ageing management in a small-sized reactor facility.

  7. Pacific Northwest Laboratory Monthly Activities Report APRIL 1966 on AEC Division of Reactor Development and Technology

    Energy Technology Data Exchange (ETDEWEB)

    S. L. Fawcett

    1966-05-01

    This report has the following sections: Summary of Activities; Civilian Power Reactors; Applied and Reactor Physics; Reactor Fuels and Materials; Engineering Development; Plutonium Recycle Program; Advanced Systems; and Nuclear Safety.

  8. The Metaphysics of The Healing. Al-Šifā’: al-Ilāhiyyāt. A parallel English-Arabic text translated, introduced, and annotated by Michael E. Marmura, Provo, Utah, Brigham Young University - Islamic Translation Series, 2005, xxvii + 441 + 378 p. [ang

    OpenAIRE

    Landau, Justine

    2007-01-01

    Cette version de la Métaphysique d’Avicenne est la quatrième traduction intégrale de l’ouvrage dans une langue occidentale, après la traduction allemande de Max J.H. Horten (1907), la version française du Père Georges C. Anawati (1978-1985), et la récente édition trilingue arabe/latin/italien de Pasquale Porro et Olga Lizzini (Bompiani, 2002). Elle constitue aussi une nouvelle édition critique du texte arabe. L’éditeur s’est largement fondé sur l’édition du Caire (1960), en intégrant la plupa...

  9. Effects of Adolescent Universal Substance Misuse Preventive Interventions on Young Adult Depression Symptoms: Mediational Modeling.

    Science.gov (United States)

    Trudeau, Linda; Spoth, Richard; Mason, W Alex; Randall, G Kevin; Redmond, Cleve; Schainker, Lisa

    2016-02-01

    Depression symptoms are associated with impairments in functioning and have substantial health and economic consequences. Universal substance misuse prevention programs have shown effects on non-targeted mental health-related symptoms, but long-term effects are understudied. This cluster randomized controlled trial examined effects of both the LifeSkills Training (LST) and Strengthening Families Program: For Parents and Youth 10-14 (SFP 10-14) interventions, delivered during seventh grade, on age 22 young adult depression symptoms. The study was conducted in US rural Midwestern communities with a randomly-selected sample from a larger study (N = 670). Experimental conditions were LST+SFP 10-14, LST-only, and a control condition. Effects on age 22 depression symptoms were hypothesized as mediated through effects on age 21 relationship problems and illicit use of substances. Structural equation modeling with manifest and latent variables was conducted to test hypotheses; the intervention conditions were combined and compared with the control condition because analyses indicated a comparable pattern of effects between intervention conditions. Significant indirect intervention effects were found on age 22 depression symptoms via effects on the mediating variables (indirect effect: β = -0.06, 95 % CI [-0.10, -0.01], p = 0.011). Effect sizes for the young adult variables were between d = 0.17 and 0.29, which can be considered small, but nontrivial, especially in the context of public health benefits. Results support scaled-up implementation of school-based and family-focused universal substance misuse preventive interventions. PMID:25795013

  10. PERSONIFICATION OF WAY OF LIFE TYPES OF YOUNG MEN AND WOMEN – GRADUATES OF THE UNIVERSITY

    Directory of Open Access Journals (Sweden)

    Svetlana Tigranovna Dzhaneryan

    2015-12-01

    Full Text Available The article presents the results of a study aimed at research of the characteristics of personification as the substantive characteristic of each type of the way of life ideals (matrimonial, bohemian, health, career, community, social, social-protection, gnostic of young men and women – graduates of the university.Research methods: survey (questionnaire for study the way of life ideal, a content analysis of the open questions of the questionnaire, expert evaluation categories, methods of nonparametric statistics.Results. The article presents ideas about the way of life ideals, discloses its components and characteristics. In the article designated types of way of life ideals: matrimonial, bohemian, health, career, community, social-protection, gnostic. Established the features of personification of each type of boys and girl’s ideals (who are graduates of the university. The results show that all kinds of way of life ideals are personified; that there are attractive to young people personality traits of real people (or groups whose way of life influences on the construction of their own ideals of life. It is shown that the differentiation of male and female personification of ideals occurs on different parameters: for the ideals of «matrimonial life» and «career life» appears only in the parameter singularity / community; for the ideal of «social life» – in the parameters singularity / community, the psychological portrait, similarities; for the ideal of «health life» – in the parameters singularity / community, the psychological portrait, a means of implementing, similarities.Application of the results: psychological services in high schools and personnel services in different companies.

  11. Similarities in Populations of Young Star Clusters: Evidence for Quasi-Universal Processes

    Science.gov (United States)

    Fall, Michael

    2015-08-01

    Star clusters are the link between interstellar clouds and star-forming galaxies - the topics of this symposium. They are important in the ecology of galaxies, as the sites of star formation and stellar feedback and as the building blocks of stellar populations. This talk presents observations of the mass functions of young star clusters (i.e., the spectrum of cluster masses) in different galaxies, including dwarf and giant, interacting and quiescent galaxies. These observations reveal some remarkable similarities in the mass functions of clusters in these different environments, analogous to the similarities in stellar initial mass functions (IMFs). Thus, we have evidence for universal or quasi-universal processes regulating the formation and early evolution of star clusters. This in turn is highly suggestive of universal or quasi-universal processes regulating the structure of the interstellar medium on the scales of protoclusters. This talk presents some theoretical explanations for these similarities. Specifically, we focus on the similarity of the mass functions of star clusters and their progenitor molecular clouds (protoclusters); both are power laws with indices near -2 (after correcting the observed distributions for life-time effects). This similarity indicates that the average efficiency of star formation in the protoclusters is independent of their masses (or nearly so), which in turn places interesting constraints on the dominant types of stellar feedback within the protoclusters. In particular, momentum-driven processes such as radiation pressure are favored. This talk also presents some theoretical explanations for the observed similarity of the mass functions of star clusters of different ages. These gas-free objects are affected primarily by stellar mass loss, tidal interactions with passing molecular clouds, and internal two-body relaxation. All these processes reduce the masses of clusters, progressively lowering the amplitude of their mass

  12. Development of Volumetric Methane Measurement Instrument for Laboratory Scale Anaerobic Reactors

    Directory of Open Access Journals (Sweden)

    Abdul Razaque Sahito

    2015-07-01

    Full Text Available In the present study, a newly developed VMMI (Volumetric Methane-Measuring Instrument for laboratory scale anaerobic reactors is presented. The VMMI is a reliable, inexpensive, easy to construct, easy to use, corrosion resistant device that does not need maintenance, can measure a wide flow range of gas at varying pressure and temperature. As per the results of the error analysis, the accuracy of the VMMI is unilateral, i.e. -6.91%. The calibration of VMMI was investigated and a linear variation was found; hence, in situ calibration is recommended for this type of instrument. As per chromatographic analysis, it absorbs almost 100% of the carbon dioxide present in the biogas, results only the methane, and thus eliminates the need of cost intensive composition analysis of biogas through gas chromatograph

  13. Containment performance analyses for the Advanced Neutron Source Reactor at the Oak Ridge National Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Kim, S.H.; Taleyarkhan, R.P.; Georgevich, V.

    1992-10-01

    This paper discusses salient aspects of methodology, assumptions, and modeling of various features related to estimation of source terms from two conservatively scoped severe accident scenarios in the Advanced Neutron Source (ANS) reactor at the Oak Ridge National Laboratory. Various containment configurations are considered for steaming-pool-type accidents and an accident involving molten core-concrete interaction. Several design features (such as rupture disks) are examined to study containment response during postulated severe accidents. Also, thermal-hydraulic response of the containment and radionuclide transport and retention in the containment are studied. The results are described as transient variations of source terms for each scenario, which are to be used for studying off-site radiological consequences and health effects for these postulated severe accidents. Also highlighted will be a comparison of source terms estimated by two different versions of the MELCOR code.

  14. Twenty-ninth annual progress report of the Pennsylvania State University Breazeale Nuclear Reactor, July 1, 1983-June 30, 1984

    International Nuclear Information System (INIS)

    The twenty-ninth annual progress report of the operation of the Pennsylvania State University Breazeale Reactor is submitted in accordance with the requirements of Contract DE-AC02-76ER03409 with the United States Department of Energy. This report also provides the University administration with a summary of the operation of the facility for the past year

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

    International Nuclear Information System (INIS)

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2014-08-15

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

  17. Kinetic parameters of the University of Maryland reactor by the interval distribution method

    International Nuclear Information System (INIS)

    The Rossi alpha of the University of Maryland Reactor was measured at criticality and at shutdown by the Babala interval-distribution method. At criticality, α/sub c/ = 145.8 +- 2.9 s-1. At shutdown, α/sub s/ = 1025.8 +- 4.1 s-1. The shutdown reactivity was found to be rho/sub s/β = -6.04 +- 0.14 dollars. An inverse kinetics analysis of a rod-drop experiment gave rho/sub s//β = -6.23 +- 0.13 dollars, which is considered with the interval-distribution result

  18. University of Florida Training Reactor. Annual progress report, September 1, 1983-August 31, 1984

    International Nuclear Information System (INIS)

    The University of Florida Training Reactor's overall utilization for the past reporting year has increased dramatically compared to previous years, even exceeding the levels of utilization characteristic of the early 1970's in some areas such as energy generation. Indeed, the total energy generation (kWh) for this reporting year is at the highest level ever and represents an increase of over 300% over the 1982-1983 reporting year which itself had an increase of 50% over the 1981-1982 reporting year

  19. Laboratory-Scale Membrane Reactor for the Generation of Anhydrous Diazomethane.

    Science.gov (United States)

    Dallinger, Doris; Pinho, Vagner D; Gutmann, Bernhard; Kappe, C Oliver

    2016-07-15

    A configurationally simple and robust semibatch apparatus for the in situ on-demand generation of anhydrous solutions of diazomethane (CH2N2) avoiding distillation methods is presented. Diazomethane is produced by base-mediated decomposition of commercially available Diazald within a semipermeable Teflon AF-2400 tubing and subsequently selectively separated from the tubing into a solvent- and substrate-filled flask (tube-in-flask reactor). Reactions with CH2N2 can therefore be performed directly in the flask without dangerous and labor-intensive purification operations or exposure of the operator to CH2N2. The reactor has been employed for the methylation of carboxylic acids, the synthesis of α-chloro ketones and pyrazoles, and palladium-catalyzed cyclopropanation reactions on laboratory scale. The implementation of in-line FTIR technology allowed monitoring of the CH2N2 generation and its consumption. In addition, larger scales (1.8 g diazomethane per hour) could be obtained via parallelization (numbering up) by simply wrapping several membrane tubings into the flask. PMID:27359257

  20. Young

    Science.gov (United States)

    1972-01-01

    Astronaut John W. Young, commander of the Apollo 16 lunar landing mission, jumps up from the lunar surface as he salutes the U.S. Flag at the Descartes landing site during the first Apollo 16 extravehicular activity (EVA-1). Astronaut Charles M. Duke Jr., lunar module pilot, took this picture. The Lunar Module (LM) 'Orion' is on the left. The Lunar Roving Vehicle is parked beside the LM. The object behind Young in the shade of the LM is the Far Ultraviolet Camera/Spectrograph. Stone Mountain dominates the background in this lunar scene.

  1. Interim report on construction of data base for atomic energy science documents (concerning Kyoto University Reactor)

    International Nuclear Information System (INIS)

    The Kyoto University Research Reactor Institute was established in 1963 as a research institute for all universities in Japan utilizing the facilities in common. The construction of a document data base has been undertaken in commemoration of the 20th anniversary of the institute. The data base concerns the research works performed at the institute and also the publications and reports on the research made by the personnel belonging to the institute. Input data are gathered from concerned researchers. In this interim report, the structure and contents of this data base are shortly described. One of the features of this data base is that it handles data with both Japanese and English at the same time. (Aoki, K.)

  2. The University of Birmingham, nuclear power, and start of UK reactor programme

    International Nuclear Information System (INIS)

    As long ago as 1919 Sir Oliver Lodge, the first principal of The University of Birmingham presented a remarkable prescient account of the potential of nuclear power. However, he could not have predicted that a mere 20 years later, in that university, Peierls and Frisch would begin to lay the foundations with their calculation that the critical mass of 235U was only of the order of 1 kg. It is generally the case that work in the field of pure physics leads to the initiating discovery; metallurgy follows with the development of the resultant technology. In this paper, it is illustrated how the shortage of suitable materials (and facilities) forced the UK to follow a route which would lead to the development of gas cooled reactors. (author)

  3. Scottish Universities Research and Reactor Centre annual report 1987-1988

    International Nuclear Information System (INIS)

    The Scottish Universities Research and Reactor Centre (SURRC) provides facilities for research in isotopic, nuclear and earth sciences and collaborates with Scottish University departments on a wide range of research topics. One of its main areas of work is the Isotope Geology Unit. This has worked with the Nuclear Medicine Unit on the application of enriched stable isotope tracers in the biological and clinical sciences. The measurement of radioactive isomers is applied to quaternary geology, archaeology, nuclear medicine, health physics, oceanography, atomospheric sciences, environmental chemistry, nuclear waste disposal and mathematical modelling of the environment. There are also radiocarbon dating facilities. The facilities and the research undertaken at the Centre in the year 1987-1988, the Centre's twenty-fifth year are summarized in this report. (U.K.)

  4. Evaluation of Solid Waste Management in the Chemistry Laboratories of Tehran Universities

    Directory of Open Access Journals (Sweden)

    A.R Akbarzadeh Baghban

    2011-10-01

    Full Text Available Background and Objectives: Particular importance of hazardous wastes is due to having characteristics such as toxicity, flammability, corrosively and reactivity. Some of the chemical wastes due to having hazardous materials must be collected and managed in a proper manner, since they are potentially harmful to the environment. Owing to the fact that educational centers have important roles in developing countries, so the main objective of the present study was to investigate, hazardous waste management in chemistry laboratories of Ministry of Science universities, in Tehran, Iran.Materials and Methods: Study area of this research includes all chemistry laboratories in Tehran universities which were covered by Ministry of Science. To obtain the number of samples, based on Scientific Principles and identification formula, 64 samples were calculated. In addition, sampling was done by Stratified sampling. Validated checklists were used for data gathering. Data analysis were done by Descriptive statistics (mean, frequency and etc. and inferential statistics (kruskal- wallis test.Results: results obtained in this study indicate that Sharif University by obtaining the mean score of 60.5 and Tehran University by obtaining the mean score of 4.5-6 are placed in best and worst rank, respectively. Beheshty, Alzahra and Tarbiat Moallem univesities by acquiring the mean score of 20-28.5 have a same position in ranking table.  Conclusion: Results show that most of the studied laboratories do not have any collection program and only 26.5 percent of them have acceptable programs.The separation and storing program observed in about 12.5 percent . Hazardous wastes management in chemistry laboratory of Tehran Universities was not in good status. And from the standpoint of management, only 12.5 percent of studied cases are in good status, while 75 percent was in undesirable status.

  5. History of the 185-/189-D thermal hydraulics laboratory and its effects on reactor operations at the Hanford Site

    Energy Technology Data Exchange (ETDEWEB)

    Gerber, M.S.

    1994-09-01

    The 185-D deaeration building and the 189-D refrigeration building were constructed at Hanford during 1943 and 1944. Both buildings were constructed as part of the influent water cooling system for D reactor. The CMS studies eliminated the need for 185-D function. Early gains in knowledge ended the original function of the 189-D building mission. In 1951, 185-D and 189-D were converted to a thermal-hydraulic laboratory. The experiments held in the thermal-hydraulic lab lead to historic changes in Hanford reactor operations. In late 1951, the exponential physics experiments were moved to the 189-D building. In 1958, new production reactor experiments were begun in 185/189-D. In 1959, Plutonium Recycle Test Reactor experiments were added to the 185/189-D facility. By 1960, the 185/189-D thermal hydraulics laboratory was one of the few full service facilities of its type in the nation. During the years 1961--1963 tests continued in the facility in support of existing reactors, new production reactors, and the Plutonium Recycle Test Reactor. In 1969, Fast Flux Test Facility developmental testings began in the facility. Simulations in 185/189-D building aided in the N Reactor repairs in the 1980`s. In 1994 the facility was nominated to the National Register of Historic Places, because of its pioneering role over many years in thermal hydraulics, flow studies, heat transfer, and other reactor coolant support work. During 1994 and 1995 it was demolished in the largest decontamination and decommissioning project thus far in Hanford Site history.

  6. History of the 185-/189-D thermal hydraulics laboratory and its effects on reactor operations at the Hanford Site

    International Nuclear Information System (INIS)

    The 185-D deaeration building and the 189-D refrigeration building were constructed at Hanford during 1943 and 1944. Both buildings were constructed as part of the influent water cooling system for D reactor. The CMS studies eliminated the need for 185-D function. Early gains in knowledge ended the original function of the 189-D building mission. In 1951, 185-D and 189-D were converted to a thermal-hydraulic laboratory. The experiments held in the thermal-hydraulic lab lead to historic changes in Hanford reactor operations. In late 1951, the exponential physics experiments were moved to the 189-D building. In 1958, new production reactor experiments were begun in 185/189-D. In 1959, Plutonium Recycle Test Reactor experiments were added to the 185/189-D facility. By 1960, the 185/189-D thermal hydraulics laboratory was one of the few full service facilities of its type in the nation. During the years 1961--1963 tests continued in the facility in support of existing reactors, new production reactors, and the Plutonium Recycle Test Reactor. In 1969, Fast Flux Test Facility developmental testings began in the facility. Simulations in 185/189-D building aided in the N Reactor repairs in the 1980's. In 1994 the facility was nominated to the National Register of Historic Places, because of its pioneering role over many years in thermal hydraulics, flow studies, heat transfer, and other reactor coolant support work. During 1994 and 1995 it was demolished in the largest decontamination and decommissioning project thus far in Hanford Site history

  7. Preliminary study: Formaldehyde exposure in laboratories of Sharjah university in UAE

    Directory of Open Access Journals (Sweden)

    Hafiz Omer Ahmed

    2011-01-01

    Full Text Available Objectives : Laboratory technicians, students, and instructors are at high risk, because they deal with chemicals including formaldehyde. Thus, this preliminary study was conducted to measure the concentration of formaldehyde in the laboratories of the University of Sharjah in UAE. Materials and Methods: Thirty-two air samples were collected and analyzed for formaldehyde using National Institute for Occupational Safety and Health (NIOSH method 3500. In this method, formaldehyde reacts with chromotropic acid in the presence of sulfuric acid to form a colored solution. The absorbance of the colored solution is read in spectrophotometer at wavelength 580 nm and is proportional to the quantity of the formaldehyde in the solution. Results: For the anatomy laboratory and in the presence of the covered cadaver, the mean concentration of formaldehyde was found to be 0.100 ppm with a range of 0.095-0.105 ppm. Whereas for the other laboratories, the highest mean concentration of formaldehyde was 0.024 ppm in the general microbiology laboratory and the lowest mean concentration of formaldehyde was 0.001 ppm in the environmental health laboratory. The 8-hour (time-weighted average concentration of formaldehyde was found to be ranging between 0.0003 ppm in environmental health laboratory and 0.026 ppm in the anatomy laboratory. Conclusions: The highest level of concentration of formaldehyde in the presence of the covered cadaver in anatomy laboratory exceeded the recommended ceiling standard established by USA-NIOSH which is 0.1 ppm, but below the ceiling standard established by American Conference of Governmental Industrial Hygienists which is 0.3 ppm. Thus, it is recommended that formaldehyde levels should be measured periodically specially during the dissection in the anatomy laboratory, and local exhaust ventilation system should be installed and personal protective equipment such as safety glass and gloves should be available and be used to prevent

  8. The New Emergency Core Cooling (NECC) system for the National Research Universal (NRU) reactor

    International Nuclear Information System (INIS)

    The New Emergency Core Cooling (NECC) system is the penultimate of seven major safety upgrades being implemented at the National Research Universal (NRU) Reactor in Chalk River. The NECC upgrade was designed to improve the original systems for core cooling in the event of an unisolable failure within the primary cooling circuit. The NECC upgrade ensures that water is automatically made available to the emergency cooling circuit pumps in the event of a break. Reactor core cooling is achieved from the discharge of these pumps which distribute emergency coolant to the individual fuel rods. Heated water from the vessel returns to the heat exchangers within the emergency cooling circuits for heat removal to the secondary coolant. The NECC upgrade significantly improves protection for a wide range of Loss Of Coolant Accidents (LOCAs) through the use of design features such as component redundancy, automatic initiation and hazard qualification. The introduction of the NECC upgrade combined with previous improvements in liquid confinement capability provide a closed loop system that ensures stable long term reactor core cooling. CATHENA (Canadian Algorithm for THErmalhydraulic Network Analysis) analysis was performed to assess the NECC upgrade and to validate the design for credible leak scenarios. (author)

  9. Intermediate energy neutron beams from the MURR [University of Missouri Research Reactor

    International Nuclear Information System (INIS)

    Several reactors in the US are potential candidates to deliver beams of intermediate energy neutrons for NCT. At this time, moderators, as compared to filters, appear to be the more effective means of tailoring the flux of these reactors. The objective is to sufficiently reduce the flux of fast neutrons while producing enough intermediate energy neutrons for treatments. At the University of Missouri Research Reactor (MURR), the code MCNP has recently been used to calculate doses in a phantom. First, ideal beams of 1, 35, and 1,000 eV neutrons were analyzed to determine doses and advantage depths in the phantom. Second, a high quality beam that had been designed to fit in the thermal column of the MURR, was reanalyzed. MCNP calculations of the dose in phantom in this beam confirmed previous calculations and showed that this beam would be a nearly ideal one with neutrons of the desired energy and also a high neutron current. However, installation of this beam will require a significant modification of the thermal column of the MURR. Therefore, a second beam that is less difficult to build and install, but of lower neutron current, has been designed to fit in MURR port F. This beam is designed using inexpensive Al, S, and Pb. The doses calculated in the phantom placed in this beam show that it will be satisfactory for sample tests, animal tests, and possible initial patient trials. Producing this beam will require only modest modifications of the existing tube

  10. Neutronic Analysis of the Pavia University TRIGA Mark II Reactor Core

    Energy Technology Data Exchange (ETDEWEB)

    Tigliole, A. Borio Di [University of Pavia, Department of Nuclear and Theoretical Physics, Via Bassi 4, 27100 Pavia (Italy); University of Pavia, Laboratory of Applied Nuclear Energy, Via Aselli 41, 27100 Pavia (Italy); Cammi, A. [Polytechnic of Milano, Department of Energy, Via La Masa 34, 20156 Milano (Italy); Chiesa, D.; Clemenza, M. [University of Milano-Bicocca, Physics Department, Piazza della Scienza 3, 20126, Milano (Italy); Pattavina, L.; Previtali, E. [University of Milano-Bicocca, Physics Department, Piazza della Scienza 3, 20126, Milano (Italy); INFN section of Milano-Bicocca, Piazza della Scienza 3, 20126, Milano (Italy); Scian, G. [University of Pavia, Laboratory of Applied Nuclear Energy, Via Aselli 41, 27100 Pavia (Italy)

    2011-07-01

    An advanced computational tool based on Monte Carlo code was developed for the neutronic analysis of the TRIGA Mark II research reactor of the University of Pavia and the results from simulations were benchmarked with the experimental data. The neutron analysis was performed by means of the 3-D continuous-energy Monte Carlo codes MCNP4C and MCNP5. All core components were reproduced in good detail and the model allows the description of different core and fuel configurations with good versatility. In a first step, the results from the simulations with fresh fuel at room temperature were compared with the experimental data about critical core parameters at zero power level, quoted in the reactor First Criticality Final Report; a very good agreement was found and the goodness of the model was proved. Afterwards, neutron flux and reactivity dependence on the fuel and moderator temperature was studied in detail; all the available methods for the simulation of thermal effects were analyzed in order to model the reactor in the stationary operating condition at 250 kW. The model was updated to the present configuration and the use of specific S({alpha},{beta}) cross sections was found to be of primary importance for a correct simulation of low-energy neutrons scattering within moderator. (author)

  11. Neutronic Analysis of the Pavia University TRIGA Mark II Reactor Core

    International Nuclear Information System (INIS)

    An advanced computational tool based on Monte Carlo code was developed for the neutronic analysis of the TRIGA Mark II research reactor of the University of Pavia and the results from simulations were benchmarked with the experimental data. The neutron analysis was performed by means of the 3-D continuous-energy Monte Carlo codes MCNP4C and MCNP5. All core components were reproduced in good detail and the model allows the description of different core and fuel configurations with good versatility. In a first step, the results from the simulations with fresh fuel at room temperature were compared with the experimental data about critical core parameters at zero power level, quoted in the reactor First Criticality Final Report; a very good agreement was found and the goodness of the model was proved. Afterwards, neutron flux and reactivity dependence on the fuel and moderator temperature was studied in detail; all the available methods for the simulation of thermal effects were analyzed in order to model the reactor in the stationary operating condition at 250 kW. The model was updated to the present configuration and the use of specific S(α,β) cross sections was found to be of primary importance for a correct simulation of low-energy neutrons scattering within moderator. (author)

  12. Osaka University, Laboratory of Nuclear Studies publication lists 1955-1980

    International Nuclear Information System (INIS)

    List of publications by the members of the Osaka University Laboratory of Nuclear Studies (OULNS) for the 25 years from 1955 to 1980. Most of experimental works were carried out by using the OULNS facilities. Included are also works made by the OULNS staffs partly by using national facilities and other laboratory's facilities. This lists original papers, letters, invited papers (or oral contribution) at international conferences and symposiums, review articles, and contributions to international conferences and symposiums. Doctor and master theses by the OULNS graduate students in the experimental nuclear physics group (cyclotron division and Van de Graaff division) are added. (author)

  13. TECHNICAL UNIVERSITY AS A MULTILEVEL EDUCATIONAL COMPLEX: FROM THE EXPERIENCE OF EDUCATION OF YOUNG STUDENTS

    Directory of Open Access Journals (Sweden)

    S. V. Sergeeva

    2016-01-01

    Full Text Available The purpose of the article is summarizing the experience and determination of the main vectors of educational work organization and implementation in a technical university as a multi-level educational complex (MEC.Methods. Theoretical methods such as the analysis of scientific literature, the synthesis of the main concepts and approaches to the problem under consideration, the generalization of experience are used.The results and scientific novelty. A long-term positive experience of educational system constructing in Penza State Technological University as a multi-level educational complex is presented. On its basis the main vectors of the educational work organization and implementation in a modern multi-level educational organization of a technical profile are determined: the formation of social competence of students, pedagogical support of their adaptation and professional selfdetermination, the student government development. The complex of the programs developed by the authors to educate young students in a technical university as a multi-level educational complex is characterized. Their realization involves a phased implementation of the initial diagnosis, constructive, transformative, evaluative and productive activities. The necessity of the organization and implementation of additional psychological and pedagogical training of teachers who do not have the basic pedagogical education as a condition for the effective implementation of the programs developed and put into educational practice in a multi-level educational organization of a technical profile is determined.Practical significance. The presented materials can be used in the educational practice of multi-level educational complexes of a technical profile as well as in other educational institutions of vocational education.

  14. The AKR training reactor of the University of Technology Dresden and its experimental programme for education

    International Nuclear Information System (INIS)

    The training and research reactor AKR (from the German Ausbildungskernreaktor) of the University of Technology Dresden was put into operation in the late 1970s, i.e. at a time when experts in Western and Eastern European countries expected an extensive development of nuclear energy generation. In the eastern part of Germany, i.e. the former German Democratic Republic, a 70 MW(el) WWER nuclear power plant (NPP) was in operation at Rheinsberg since 1966. A further five NPPs of the Russian WWER type (440 MW(e)) were put into operation at Greifswald on the Baltic Sea coast between 1973 and 1989. Three more plants were under construction at that site. At the end of the 1980s, a new NPP was being planned at Stendal, a 1000 MW(e) WWER plant. For construction, licensing, operation and maintenance of these NPPs, a well educated and trained staff was required. Authorities and technical surveillance organizations should have qualified experts at their disposal, too. Consequently, in 1968 the University of Technology Dresden introduced appropriate courses for the education of nuclear engineers in order to contribute to fulfilling the demands of industry, science and administration. Students were taught in lectures, but theoretical knowledge had to be combined with practical experience based on an extensive programme of fundamental experiments in the fields of reactor physics, neutron physics, nuclear technology, radiation measurement techniques, radiation protection, radiation dosimetry and others. The full scale of this experimental programme can preferably be made available by small training reactors which can be operated with great diversity in terms of experimental intentions and without commercial restrictions

  15. METHODS OF LABORATORY ANIMALS" CARCASSES COLLECTION, STORAGE AND DESTRUCTION IN ISFAHAN UNIVERSITY OF MEDICAL SCIENCES

    Directory of Open Access Journals (Sweden)

    N SHAMANSOURI

    2003-12-01

    Full Text Available Introduction: Environmental problems due to hazardous wastes production are increasing everyday. Laboratories of Isfahan University of Medical Sciences produce hazardous wastes in their daily research avtivities. These hazardous wastes are produced from laboratory animals" carcasses, which were used in educational and research activities. These carcasses are mixed with other wastes while they are contaminated with pathogenic organisms, toxic and chemical agents. These wastes can contaminate environment and threaten human s health. So, carcasses produced in laboratories should be collected and handle with a specific method in order to destruct in an incinerator. Methods: In this study, methods of collection, storge and destruction of laboratory animals" carcasses in Isfahan university of medical Sciences were evaluated during four months. Specific questionnaires were used for data collection. The mean weight of carcasses of each labratories, produced within a week, were calculated. DRE (Destruction and Removal Efficacy in different Temperatures in the incinerator were calculated. Results: Mean weight of laboratory animals" carcasses produced during a week in all the laboratories were 20kg. DRE in the incinerator were 9S.39% in 750.C temperature during 1 hour, 94.20% in 850°c temperature during 30 minutes, 94.10% in 950°c temperature during 20 minutes and 94.80% in 1000°c temperature during 15 minutes. Discussion: According to laboratory animals" carcasses contamination with pathogenic organisms, toxic and chemical agents, present methods of collection, storage and destruction aren"t standard and healthy. Also, due to low amout of carcasses daily production, everyday destruction of these carcasses isn"t economic. As a result, carcasses produced everyday should be stored in a collecting box under zero temperature and destruct at the end of the week in the designed incinerator in 1000°c temperature .

  16. Contribution to international safeguards and security by a small university research reactor

    International Nuclear Information System (INIS)

    Full text: In recent years international safeguards and security of radioactive sources has become an increasing concern to countries, to the public and to international organisations. The main target of all international efforts is to prevent the spread and the illicit trafficking of special nuclear materials or radioactive sources. The development of highly specialised instruments being hand-held, portable or fixed installed is performed in cooperation with the IAEA mainly in the USA and in Europe. However even small research institutions such as the Atom institute in Vienna can contribute significantly to the improvement both of hardware and software as well as to the practical test in different radiation fields under laboratory conditions. The Atom institute belongs to the Technical University of Vienna and operates a 250 kW TRIGA type reactor mainly for education and training of students in the nuclear field. All relevant information can be found in the homepage www.ati.ac.at. One advantage of the Atom Institute is the proximity to the IAEA, in fact it is the closest nuclear facility to the IAEA headquarters. In the past years the Atom Institute co-operated very closely with several divisions in the IAEA to test soft- and hardware of newly developed nuclear instruments under variable environmental conditions. Following are some typical examples of recent research programmes: One field of research and investigations was the behaviour of various types of Cd-Zn-Te (CZT) detectors in different radiation fields. These types of detectors are room temperature semiconductor detectors with a resolution between HP Ge detectors and NaJ detectors. They have the advantage of being very small and rugged and therefore easy to be transported and applied in the field. However their resolution as a function of their geometric configuration has to be tested in mixed radiation fields, also the evaluation software has to be improved. Starting in 1996 two CZT detectors have been

  17. Compliance with Universal Precautions Among Nurses and Laboratory Technicians in Mansoura International Specialized Hospital

    OpenAIRE

    Sahar Mamoud Sayed Ahmed; Salwa Abbas Aly Hassan

    2008-01-01

    Compliance with universal precautions by nurses and laboratory technicians in hospitals is very important because it prevent cross infection and decrease costs of antibiotics and antipyretics. Also, it decreases spread of infection, which leads to decrease morbidity and mortality rate. A cross-sectional descriptive design was used for conducting this study. The sample of the study consisted of 150 nurses and lab technicians working at morning shift in a hospital at Mansoura City, Dakahlia Gov...

  18. The Agent of Dermatophytosis in Patients Attending to the Mycrobiology Laboratory of Dicle University Medical Faculty

    OpenAIRE

    Tuncer Özekinci; Erdal Özbek; Murat Gedik; Mehmet Topçu; Fikret Tekay; Mahmut Mete

    2006-01-01

    The clinical specimens of 538 patients, sent to Microbiology Laboratory of Medical Faculty, Dicle University, with pre-diagnosis of dermatophytosis, were investigated by direct microscopic and culture methods. Of 106 patients diagnosed as having dermatophytosis, the causative dermatophytes were isolated in 75 (70,6 %); while in 31 (29,3%), dermatophytes could not be isolated. Among dermatophytes Trichophyton rubrum (69,2%) was the most frequently isolated dermatophyte followed by Trichophyton...

  19. Presentation to Ohio State University Dept. of Electrical Engineering ElectroScience Laboratory

    Science.gov (United States)

    Fujikawa, Gene

    2002-01-01

    Presentation made during visit to The Ohio State University, ElectroScience Laboratory, on November 14, 2002. An overview of NASA and selected technology products from the Digital Communications Technology Branch (5650) for fiscal year 2003 are highlighted. The purpose of the meeting was to exchange technical information on current aeronautics and space communications research and technology being conducted at NASA Glenn Research Center and to promote faculty/student collaborations of mutual interest.

  20. U.S. Department of Energy University Reactor Sharing Program at the University of Florida. Final report for period August 15, 2000 - May 31, 2001

    Energy Technology Data Exchange (ETDEWEB)

    Vernetson, William G.

    2002-01-01

    Department of Energy Grant Number DE-FG02-96NE38152 was supplied to the University of Florida Training Reactor (UFTR) facility through the U.S. Department of Energy's University Reactor Sharing Program. The renewal proposal submitted in January 2000 originally requested over $73,000 to support various external educational institutions using the UFTR facilities in academic year 2000-01. The actual Reactor Sharing Grant was only in the amount of $40,000, all of which has been well used by the University of Florida as host institution to support various educational institutions in the use of our reactor and associated facilities as indicated in the proposal. These various educational institutions are located primarily within the State of Florida. However, when the 600-mile distance from Pensacola to Miami is considered, it is obvious that this Grant provides access to reactor utilization for a broad geographical region and a diverse set of user institutions serving over fourteen million inhabitants throughout the State of Florida and still others throughout the Southeast.

  1. Utilization of the High Flux Isotope Reactor at Oak Ridge National Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Selby, Douglas L [ORNL; Bilheux, Hassina Z [ORNL; Meilleur, Flora [ORNL; Jones, Amy [ORNL; Bailey, William Barton [ORNL; Vandergriff, David H [ORNL

    2015-01-01

    This paper addresses several aspects of the scientific utilization of the Oak Ridge National Laboratory High Flux Isotope Reactor (HFIR). Topics to be covered will include: 1) HFIR neutron scattering instruments and the formal instrument user program; 2) Recent upgrades to the neutron scattering instrument stations at the reactor, and 3) eMod a new tool for addressing instrument modifications and providing configuration control and design process for scientific instruments at HFIR and the Spallation Neutron Source (SNS). There are 15 operating neutron instrument stations at HFIR with 12 of them organized into a formal user program. Since the last presentation on HFIR instruments at IGORR we have installed a Single Crystal Quasi-Laue Diffractometer instrument called IMAGINE; and we have made significant upgrades to HFIR neutron scattering instruments including the Cold Triple Axis Instrument, the Wide Angle Neutron Diffractometer, the Powder Diffractometer, and the Neutron Imaging station. In addition, we have initiated upgrades to the Thermal Triple Axis Instrument and the Bio-SANS cold neutron instrument detector system. All of these upgrades are tied to a continuous effort to maintain a high level neutron scattering user program at the HFIR. For the purpose of tracking modifications such as those mentioned and configuration control we have been developing an electronic system for entering instrument modification requests that follows a modification or instrument project through concept development, design, fabrication, installation, and commissioning. This system, which we call eMod, electronically leads the task leader through a series of questions and checklists that then identifies such things as ES&H and radiological issues and then automatically designates specific individuals for the activity review process. The system has been in use for less than a year and we are still working out some of the inefficiencies, but we believe that this will become a very

  2. Use of training reactor VR-1 Vrabec in training specialists for nuclear power facilities at Czech universities

    International Nuclear Information System (INIS)

    Training reactor VR-1 VRABEC is being built at the Faculty of Nuclear Science and Physical Engineering, Czech Technical University in Prague. It is a pool type reactor with enriched uranium (36% 235U); demineralized light water serves as the moderator and reflector, the reactor core is cooled by natural convection. The rated output is 100 W, short-term operation at 1 kW being possible. The neutron flux density is 1 to 3 x 1014 m-2 s-1. The reactor will find application in education (75% time) in the courses: heat and nuclear engines and equipment, electricity generation, nuclear engineering, and nuclear chemical engineering. The reactor workshop is equipped with ample instrumentation such as multichannel analyzers, dosimetric instruments, activity meters and state-of-the-art computers. (Z.M.)

  3. Waste Stream Generated and Waste Disposal Plans for Molten Salt Reactor Experiment at Oak Ridge National Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Haghighi, M. H.; Szozda, R. M.; Jugan, M. R.

    2002-02-26

    The Molten Salt Reactor Experiment (MSRE) site is located in Tennessee, on the U.S. Department of Energy (DOE) Oak Ridge Reservation (ORR), south of the Oak Ridge National Laboratory (ORNL) main plant across Haw Ridge in Melton Valley. The MSRE was run by ORNL to demonstrate the desirable features of the molten-salt concept in a practical reactor that could be operated safely and reliably. It introduced the idea of a homogeneous reactor using fuel salt media and graphite moderation for power and breeder reactors. The MSRE reactor and associated components are located in cells beneath the floor in the high-bay area of Building 7503 (Figure 1). The reactor was operated from June 1965 to December 1969. When the reactor was shut down, fuel salt was drained from the reactor circuit to two drain tanks. A ''clean'' salt was then circulated through the reactor as a decontamination measure and drained to a third drain tank. When operations ceased, the fuel and flush salts were allowed t o cool and solidify in the drain tanks. At shutdown, the MSRE facility complex was placed in a surveillance and maintenance program. As a result of the S&M program, it was discovered in 1994 that gaseous uranium (233U/232U) hexafluoride (UF6) had moved throughout the MSRE process systems. The UF6 was generated when radiolysis of the fluorine salts caused the individual constituents to dissociate to their component atoms, including free fluorine.Some of the free fluorine combined with uranium fluorides (UF4) in the salt to form UF6. UF6 is gaseous at slightly above ambient temperatures; thus, periodic heating of the fuel salts (which was intended to remedy the radiolysis problems) and simple diffusion had allowed the UF6 to move out of the salt and into the process systems of MSRE.

  4. Preparation of mandatory documentation before the start up of the RA-0 'zero power' nuclear reactor at Cordoba National University

    International Nuclear Information System (INIS)

    Before the start up of the RA-0 'zero power' nuclear reactor installed at Cordoba National University, it was necessary to send to the Regulatory Authority the mandatory documentation which is required in the licensing process. With the previous papers existing for the operation in the first years of the '70, a work program for the future operational training personnel was elaborated. Based on the Authority's applicable rules and the recommendations and with particular criteria originated in the working university conditions, the SAFETY report of RA-0 nuclear reactor was prepared. This paper describes the principal contents, items and documents involved in the safety report. (Author)

  5. Validation of Accelerometer Thresholds and Inclinometry for Measurement of Sedentary Behavior in Young Adult University Students.

    Science.gov (United States)

    Peterson, Neil E; Sirard, John R; Kulbok, Pamela A; DeBoer, Mark D; Erickson, Jeanne M

    2015-12-01

    Sedentary behavior (SB) is a major contributor to obesity and significant morbidity and mortality in adolescence and adulthood, yet measurement of SB is still evolving. The purpose of this study was to assess the degree of construct validity of the inclinometer function and single-axis and vector magnitude accelerometry metrics of the ActiGraph GT3X+ in objectively measuring SB and physical activity in 28 young adult university students who performed nine semi-structured activities, each for five minutes: lying, sitting, reading, seated video gaming, video watching, seated conversation, standing, stationary biking, and treadmill walking. Inclinometry and four output metrics from the ActiGraph were analyzed in comparison to direct observation by a researcher recorded each minute. For overall accuracy in measuring both SB and physical activity, all four accelerometer metrics (94.7-97.8%) outperformed the inclinometer function (70.9%). Vector magnitude accelerometry with a threshold of 150 counts per minute as the cut point for sedentary behavior was superior to other methods. While accelerometry was more accurate overall at detecting the behaviors tested, inclinometry had some advantages over accelerometry methods at detecting walking, biking, and standing. The findings support use of accelerometry as a valid objective measure of body movement, while use of inclinometry as a sole measure is not recommended. Additional research would be beneficial to improve the calibration of the inclinometer and explore ways of combining this with accelerometer data for objectively measuring SB and physical activity. PMID:26444969

  6. Prevalence of signs and symptoms of temporomandibular disorders and their association with young university students

    Directory of Open Access Journals (Sweden)

    Renata Cunha Matheus Rodrigues Garcia

    2008-01-01

    Full Text Available Objective: To verify the prevalence of signs and symptoms of temporomandibular disorder and their association with joint noise, joint hypermobility, occlusal interference, orthodontic treatment and bruxism in a specific population composed of young university students. Methods: One hundred and seventeen (117 volunteers (mean age of 22 years were selected from the undergraduate course in Dentistry at the School of Dentistry of the “Centro Universitário Hermínio Ometto” (Araras, São Paulo, Brazil. The volunteers answered a questionnaire and were submitted to clinical and electrovibratography exams. Afterwards, the volunteers were classified as either having temporomandibular disorder or not, considering the presence of painful sensitivity in the temporomandibular joint and/or presence of joint noise. The prevalenceof the studied factors was calculated together with the association between each factor, and the presence of temporomandibular disorderwas analyzed by the Chi-square test. Results: The prevalence of temporomandibular disorder in the evaluated sample was 42.9% and significant association was found between temporomandibular disorder and joint noise (p<0.05; and between temporomandibular disorder and bruxism (p<0.05. Conclusion: The results suggest that patients with presence of precisely diagnosed bruxism and joint noise should be monitored with regard to the appearance of signs and symptoms of temporomandibular disorder.

  7. N Reactor

    Data.gov (United States)

    Federal Laboratory Consortium — The last of Hanfordqaodmasdkwaspemas7ajkqlsmdqpakldnzsdflss nine plutonium production reactors to be built was the N Reactor.This reactor was called a dual purpose...

  8. Laboratories Performance after Outsourcing in the Hospitals of Shahid Beheshti University of Medical Sciences

    Directory of Open Access Journals (Sweden)

    Omrani, MD. (PhD

    2013-01-01

    Full Text Available Background and Objective: Nowadays, downsizing the government to have aneffective and flexible organization is considered to be government’s top priority inthe world and outsourcing is one of the ways to achieve this goal. Accordingly,Shahid Beheshti University of Medical Sciences has delegated some of itshospitals' duties to the private sectors. The present study has been carried out toassess the performance of outsourced clinical laboratories.Material and Methods: This Descriptive Evaluation study was carried out during6 month (May 2011 till February 2012. The data was collected by twoquestionnaires with close-ended questions and one with open-ended questions, andanalyzed by Wilcoxon, using SPSS software.Results: There is an improvement in outsourcing laboratory services. Forexample, increase in the number of tests (32% and in the type of tests (37%.Consequently, increase of hospital income (51%. The number of personnel isdecreased and their responsibility and behavior are improved.Conclusion: Overall, it seems that outsourcing laboratory program could achieveits major goals such as: Absorbing non-governmental resources in bothadministrative and financial aspects, omitting extra expenditure, acquiringbenefits, and upgrading productivity of laboratories.Keywords: Outsourcing; Laboratory; Performance

  9. The contribution of a small triga university research reactor to nuclear research on an international level

    International Nuclear Information System (INIS)

    The paper focuses especially on the important results in neutron- and solid state physics and the co-operation between the low power TRIGA reactor with high flux neutron sources in Europe such as the Institute Laue-Langevin (ILL) in Grenoble, the Paul Scherrer Institut (PSI) in Villigen, the Rutherford Appleton Laboratory (RAL) in Didcot and the Research Center Juelich. Experiments are set up for test purposes at the TRIGA reactor and then transferred to the powerful neutron sources. Different new perfect silicon channel-cut and interferometer crystals are prepared and then tested at the Bonse-Hart camera, which is a double crystal (or triple axis) diffractometer and at the interferometer set-up. Historically, the first verification of neutron interferometry at a perfect crystal device has been achieved at the 250 kW TRIGA-reactor in Vienna in the year 1974. Also the co-operation with the PSI and the TU Munich in the field of neutron radiography and neutron tomography and VESTA, an experiment for storing cold neutrons with a wavelength of 6.27 A, installed at the pulsed neutron source ISIS at RAL will be mentioned. The second topic treated in this paper shows the international co-operation in the field of superconductors. This research work is carried out under two European TMR-Network programs. The third topic in this paper focuses on the co-operation in the field of safeguard. Several projects have been carried out during the past years in co-operation with the IAEA such as establishing a gamma spectrum reference catalogue for CdZnTe detectors and tests of safeguard video cameras under neutron irradiation. Further an integrated safeguard surveillance network composed of a video camera, a gamma monitor and a neutron monitor is under development. (orig.)

  10. The contribution of a small TRIGA university research reactor to nuclear research on an international level

    International Nuclear Information System (INIS)

    The paper focuses especially on the important results in neutron- and solid state physics and the co-operation between the low power TRIGA reactor with high flux neutron sources in Europe such as the Institute Laue-Langevin (ILL) in Grenoble, the Paul Scherrer Institut (PSI) in Villigen, the Rutherford Appleton Laboratory (RAL) in Didcot and the Research Center Juelich. Experiments are set up for test purposes at the TRIGA reactor and then transferred to the powerful neutron sources. Different new perfect silicon channel-cut and interferometer crystals are prepared and then tested at the Bonse-Hart camera, which is a double crystal (or triple axis) diffractometer and at the interferometer set-up. Historically, the first verification of neutron interferometry at a perfect crystal device has been achieved at the 250 kW TRIGA-reactor in Vienna in the year 1974. Also the co-operation with the PSI and the TU Munich in the field of neutron radiography and neutron tomography and VESTA, an experiment for storing cold neutrons with a wavelength of 6.27A, installed at the pulsed neutron source ISIS at RAL are mentioned. The second topic in this paper focuses on the co-operation in the field of safeguard. Several projects have been carried out during the past years in co-operation with the IAEA such as establishing a gamma spectrum reference catalogue for CdZnTe detectors and tests of safeguard video cameras under neutron irradiation. Further an integrated safeguard surveillance network composed of a video camera, a gamma monitor and a neutron monitor is under development

  11. Design of Mixed Batch Reactor and Column Studies at Oak Ridge National Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Wu, Weimin [Stanford Univ., CA (United States); Criddle, Craig S. [Stanford Univ., CA (United States)

    2015-11-16

    We (the Stanford research team) were invited as external collaborators to contribute expertise in environmental engineering and field research at the ORNL IFRC, Oak Ridge, TN, for projects carried out at the Argonne National Laboratory and funded by US DOE. Specifically, we assisted in the design of batch and column reactors using ORNL IFRC materials to ensure the experiments were relevant to field conditions. During the funded research period, we characterized ORNL IFRC groundwater and sediments in batch microcosm and column experiments conducted at ANL, and we communicated with ANL team members through email and conference calls and face-to-face meetings at the annual ERSP PI meeting and national meetings. Microcosm test results demonstrated that U(VI) in sediments was reduced to U(IV) when amended with ethanol. The reduced products were not uraninite but unknown U(IV) complexes associated with Fe. Fe(III) in solid phase was only partially reduced. Due to budget reductions at ANL, Stanford contributions ended in 2011.

  12. Laboratory scale development of coating for improving characteristics of candidate materials for fusion reactor

    International Nuclear Information System (INIS)

    Application of coatings of refractory low atomic number materials on to different components of Tokamak type controlled thermonuclear reactor are expected to provide a degree of design flexibility. The project envisages to deal with the challenging problem on laboratory scale. Coatings investigated include carbon, beryllium, boron, titanium carbide and alumina and substrates chosen have been 304, 316 stainless steels, monel-400, molybdenum, copper, graphite, etc. For their deposition, different techniques (e.g. evaporation, sputtering and their different variants) have been tried, appropriate ones chosen and their parameters optimized. The coating composition has been analyzed using X-ray diffraction (XRD), Auger electron spectroscopy (AES), X-ray photoelectron spectroscopy (XPS), Rutherford backscattering analysis (RBS) and secondary ions mass spectroscopy (SIMS). Surface morphology has been studied using scanning electron microscopy (SEM). Sebastian coating adherence tester has been used for adhesion measurement and Wilson's Tukon microhardness tester for their microhardness measurement. The coatings have been subjected to pulses from YAG laser to evaluate their thermal cycling behaviour. Deuterium ion bombardment (Energy: 20-120 keV; doses: 1019-9.3x1020 ions/cm2) behaviour has also been studied. In general, adherent and hard coatings capable of withstanding thermal cycling could be deposited. Out of the coatings studied, titanium carbide shows best results. The following pages are reprints and not mircrofiched: p. 25-32, 39-41, 57-81. Bibliographic description is on page 13

  13. Design of Mixed Batch Reactor and Column Studies at Oak Ridge National Laboratory

    International Nuclear Information System (INIS)

    We (the Stanford research team) were invited as external collaborators to contribute expertise in environmental engineering and field research at the ORNL IFRC, Oak Ridge, TN, for projects carried out at the Argonne National Laboratory and funded by US DOE. Specifically, we assisted in the design of batch and column reactors using ORNL IFRC materials to ensure the experiments were relevant to field conditions. During the funded research period, we characterized ORNL IFRC groundwater and sediments in batch microcosm and column experiments conducted at ANL, and we communicated with ANL team members through email and conference calls and face-to-face meetings at the annual ERSP PI meeting and national meetings. Microcosm test results demonstrated that U(VI) in sediments was reduced to U(IV) when amended with ethanol. The reduced products were not uraninite but unknown U(IV) complexes associated with Fe. Fe(III) in solid phase was only partially reduced. Due to budget reductions at ANL, Stanford contributions ended in 2011.

  14. Clinical experience of BNCT for brain and skin tumors at Kyoto University Reactor

    International Nuclear Information System (INIS)

    The research nuclear reactor of Kyoto University (KUR), which was established in 1963, has the power of 5 MW and has rendered services to scientists in various fields including biology and medicine. The first clinical application was carried out on a brain tumor patient by Professor Hatanaka in 1974. Eight Japanese, 2 German and one American patients were treated. The ages of patients were 9-66 years and all were male. Skin tumors were irradiated at KUR to measure 10B content in the tissues by Nickel Mirror Neutron Guide Tube (NMNGT) attached to KUR, before BNCT. Except in a few cases, patients had recurrent tumours after previous treatment by chemotherapy, radiotherapy or surgical treatments. The absorbed dose used in the previous radiotherapy before BNCT was a curative dose. The time intervals between previous radiotherapy and BNCT varied. The treated skin tumours included various grades of melanoma. Some cases appeared to be astrocytoma grade IV

  15. Biomedical irradiation system for boron neutron capture therapy at the Kyoto University reactor

    International Nuclear Information System (INIS)

    Physics studies related to radiation source, spectroscopy, beam quality, dosimetry, and biomedical applications using the Kyoto University Reactor Heavy Water Facility are described. Also, described are a Nickel Mirror Neutron Guide Tube and a Super Mirror Neutron Guide Tube that are used both for the measurement of boron concentration in phantom and living tissue and for precise measurements of neutron flux in phantom in the presence of both light and heavy water. Discussed are: (1) spectrum measurements using the time of flight technique, (2) the elimination of gamma rays and fast neutrons from a thermal neutron irradiation field, (3) neutron collimation without producing secondary gamma rays, (4) precise neutron flux measurements, dose estimation, and the measurement of boron concentration in tumor and its periphery using guide tubes, (5) the dose estimation of boron-10 for the first melanoma patient, and (6) special-purpose biological irradiation equipment. Other related subjects are also described

  16. Design study of multi-imaging plate system for BNCT irradiation field at Kyoto university reactor.

    Science.gov (United States)

    Tanaka, Kenichi; Sakurai, Yoshinori; Kajimoto, Tsuyoshi; Tanaka, Hiroki; Takata, Takushi; Endo, Satoru

    2016-09-01

    The converter configuration for a multi-imaging plate system was investigated for the application of quality assurance in the irradiation field profile for boron neutron capture therapy. This was performed by the simulation calculation using the PHITS code in the fields at the Heavy Water Neutron Irradiation Facility of Kyoto University Reactor. The converter constituents investigated were carbon for gamma rays, and polyethylene with and without LiF at varied (6)Li concentration for thermal, epithermal, and fast neutrons. Consequently, potential combinations of the converters were found for two components, gamma rays and thermal neutrons, for the standard thermal neutron mode and three components of gamma rays, epithermal neutrons, and thermal or fast neutrons, for the standard mixed or epithermal neutron modes, respectively. PMID:27423022

  17. Summary reports of activities under visiting research program in Research Reactor Institute, Kyoto University, 1988

    International Nuclear Information System (INIS)

    The Technical Report of Research Reactor Institute, Kyoto University, is published on occasion summarizing in the form of prompt report the results of the functional test on various experimental facilities, the test results of the articles made for trial, the circumstance of radiation control and waste treatment, the data required for research and experiment such as the reports of study meetings, the remarkable results obtained amid research, new method, the discussion on other papers and reports and others. In this report, 40 summaries of the Visiting Research Projects utilizing the KUR and 13 summaries of those utilizing the KUCA in 1988, and 2 unreported summaries before 1988 are collected. In each summary, the number of adoption, title, the names of reporters and the gist of report are given. (K.I.)

  18. A multifaceted approach to radionuclide radiotherapy: The MURR [Missouri University Research Reactor] radioisotope program

    International Nuclear Information System (INIS)

    Internal radionuclide radiotherapy of malignancies began with various forms of radium injections, solutions, and implants early in this century and achieved its most wide-spread success in the application of 131I iodide for the treatment of thyroid metastases. Implants such as 198Au and 192Ir, and colloids such as 32P chromic phosphate, have also proved useful, but the greatest utility would be found for radiotherapeutic drugs possessing the selectivity for other forms of cancer that radioiodine shows for thyroid carcinoma. The objective of tumor radiotherapy is the selective destruction of malignant cells by radiation while sparing normal tissue. Recent improvements in the guidance mechanisms of radiopharmaceuticals have made possible a third wave of radiotherapeutics that may revolutionize the treatment of malignancies. The basic guidance methods include direct placement (implants), anatomical-physiological deposition, chemical-physiological concentration, and immunochemical uptake. These new drugs are primarily based on reactor-produced beta emitters, because typical beta ranges of 1 to 10 mm are the most appropriate for radiotherapy. The Missouri University research reactor (MURR) Radioisotope Applications Group has been involved for 10 yr in collaborative research to bring about this new generation of cancer-fighting drugs and is currently producing isotopes for clinical trials of all these types of treatment

  19. Water flow characteristics of Baumkuchen type fuel elements for Kyoto University high neutron flux reactor

    International Nuclear Information System (INIS)

    The Kyoto University high neutron flux reactor is a light water-moderated and cooled, divided core type reactor with heavy water reflector. In the core, six inside fuel elements and twelve outside fuel elements are arranged in double ring form, and two cylindrical, divided cores are placed at 15 cm distance. The flow rate distribution and pressure loss in the fuel elements constitute the base of the thermo-hydraulic design of the core, therefore the model fuel elements of full size were made, and the water flow experiment was carried out to examine their characteristics. It was found that the flow velocity in channels was strongly affected by the accuracy of channel gaps. The calculation of pressure loss in fuel elements, the experiments on inside fuel elements and outside fuel elements, and the results of experiments such as the calibration of the cooling channels in outside fuel elements, the relation between total flow rate and pressure loss, and the characteristics of flow at the time of reverse flow are reported. The general characteristics of flow in fuel elements were in good agreement with the prediction. In the pressure loss in fuel elements, the friction between fuel plates and the resistance of nozzles were the controlling factors under the rated operating conditions of the HFR. (Kako, I.)

  20. Assessment of the implications of conversion of university research and training reactors to low enrichment uranium fuel

    International Nuclear Information System (INIS)

    The tasks associated with conversion of a research reactor from HEU to LEU fuel are: initial program planning; safety analysis and license amendment; core physics calculations; operating thermal-hydraulics analysis; plant engineering modifications; LEU fuel specifications, procurement of fuel, and calculational confirmation of design; training of staff personnel; HEU core physics measurements and fuel disposal; and experimental verification of reactor behavior with LEU fuel. LEU fuel conversion of the 25 NRC licensed, university-owned reactors considered in this study is based upon the reactor fuel cycle, the type of license modification, and fuel meat technology. Reactors that operate on routine refueling cycles could periodically replace depleted HEU elements with fresh LEU elements. Ultimate full core conversion would depend on the average element residence time in the core. Reactors with lifetime cores would convert by full core replacement as a one-time event. For some reactors, LEU conversion depends upon high density uranium fuel meat technology development. The majority should be able to convert using a direct substitution of current fuel meat technology though some fuel plate or rod internal modifications may be necessary for 16 of the reactors

  1. The Contribution to International Safeguards and Security by a Small University Research Reactor

    International Nuclear Information System (INIS)

    Due to the proximity of the Atominstitut der Osterreichischen Universitaeten to the IAEA, many research projects have been carried out and completed successfully during the past years, especially in the field of nuclear safeguards and security, some of them have just started recently. In the paper, a survey on selected cooperation projects is given to show how a small university institute can contribute significantly to international safeguards and security research. Small university laboratories have the advantage of low cost but highly qualified personnel who can concentrate on investigation and test series which would largely exceed the possibilities of international organizations and are, therefore, a typical example of successful outsourcing for the benefit of both partners. (author)

  2. United States Domestic Research Reactor Infrastructure TRIGA Reactor Fuel Support

    International Nuclear Information System (INIS)

    The purpose of this technical paper is to provide status of the United State domestic Research Reactor Infrastructure (RRI) Program at the Idaho National Laboratory. This paper states the purpose of the program, lists the universities operating TRIGA reactors that are supported by the program, identifies anticipated fresh fuel needs for the reactor facilities, discusses spent fuel activities associated with the program, and addresses successes and planned activities for the program. (author)

  3. Cancer risk assessment for Tehran research reactor and radioisotope laboratory with CAP88-PC code (Gaussian plume model)

    International Nuclear Information System (INIS)

    Research highlights: → Impact of Tehran's reactor and radioisotope laboratory stacks has been studied. → Gaussian Plume Dispersion Model and laboratory analyses were used. → Glass-fiber filters were used in the exclusion area in different direction. → The released radionuclide concentration was calculated by the code and measurements. → Dose calculations best compared to procedures presented in the Regulatory Guide. - Abstract: The amount of released radionuclide from Tehran's research reactor and radioisotope laboratory stacks and their impact have been studied. The aim of this work is to determine the amount and type of radioactive materials and to estimate their risk once they are released into the environment. To perform the above two tasks, CAP88-PC computer code which simulates Gaussian dispersion air transport Plume Model and laboratory analysis of air samples around the site were used. Computer code input data are provided by the Safety Analysis Report and Reactor Annual Reports. Air samples were collected using the filter and sampling pumps and analyzed by gamma spectroscopy counter. Results of computer program showed that the risk of cancer death (lifetime risk) is below the regulatory limit. Results of analysis of available radionuclide in the air samples also showed that concentrations are close to the background and confirm the code results.

  4. The survey on the supporting ground on the construction site of High Flux Reactor Building in Research Reactor Institute of Kyoto University

    International Nuclear Information System (INIS)

    As part of the seismic design of the High Flux Reactor building which is planned to be constructed by Kyoto University Research Reactor Institute, the stability of the supporting ground has been analyzed. This report concerns the ground survey which has been carried out to obtain the basic data on the supporting ground. The outline of the ground around the construction site of High Flux Reactor has been already made clear by the last survey. Therefore, the purpose of this ground survey is mainly to make clear the mechanical properties of the soil. The survey has been carried out concerning the supporting ground and several layers deeper than that. The main items obtained are as follows. (1) modulus of deformation (2) breaking strength and creep strength (3) coefficient of permeability (4) ground water level. (author)

  5. The Australian Institute of Nuclear Science and Engineering - a model for university-national laboratory collaboration

    International Nuclear Information System (INIS)

    This paper describes the aims and activities of the Australian Institute of Nuclear Science and Engineering (AINSE), from its foundation in 1958 through to 1993. The philosophy, structure and funding of the Institute are briefly reviewed, followed by an account of the development of national research facilities at the Lucas Heights Research Laboratories, with particular emphasis on nuclear techniques of analyses using neutron scattering instruments and particle accelerators. AINSE's program of Grants, fellowships and studentships are explained with many examples given of projects having significance in the context of Australia's national goals. Conference and training programs are also included. The achievements during these years demonstrate that AINSE has been an efficient and cost-effective model for collaboration between universities and a major national laboratory. In recent years, industry, government organisations and the tertiary education system have undergone major re-structuring and rationalization. A new operational structure for AINSE has evolved in response to these changes and is described

  6. Making Stuff Outreach at the Ames Laboratory and Iowa State University

    Energy Technology Data Exchange (ETDEWEB)

    Ament, Katherine; Karsjen, Steven; Leshem-Ackerman, Adah; King, Alexander

    2011-04-01

    The U. S. Department of Energy's Ames Laboratory in Ames, Iowa was a coalition partner for outreach activities connected with NOVA's Making Stuff television series on PBS. Volunteers affiliated with the Ames Laboratory and Iowa State University, with backgrounds in materials science, took part in activities including a science-themed Family Night at a local mall, Science Cafes at the Science Center of Iowa, teacher workshops, demonstrations at science nights in elementary and middle schools, and various other events. We describe a selection of the activities and present a summary of their outcomes and extent of their impact on Ames, Des Moines and the surrounding communities in Iowa. In Part 2, results of a volunteer attitude survey are presented, which shed some light on the volunteer experience and show how the volunteers participation in outreach activities has affected their views of materials education.

  7. A DOE University-national laboratory waste-management education and research consortium (WERC)

    International Nuclear Information System (INIS)

    This paper presents the results and current status of a consortium of three universities and two national laboratories working closely with industry for an Education and Research program on waste-management and environmental restoration. The program sponsored by the US Department of Energy has been in effect for 18 months and has achieved significant progress towards establishing: undergraduate, graduate and associate degree programs involving environmental management, interactive TV courses from the consortium members transmitted throughout the United States, Mexico ampersand Canada, a satellite TV network, a professional development teleconference series, research programs at the leading edge of technology training multi-disciplinary students, research laboratories for analyses, testing, and student training, technology transfer programs, including a TV series on research applications, outreach programs, including pre-college and minority education, community monitoring

  8. University students’ ideas about data processing and data comparison in a physics laboratory course

    Directory of Open Access Journals (Sweden)

    Rebecca Lippmann Kung

    2012-10-01

    Full Text Available This study investigates undergraduate students’ ability to use the ideas of measurement and uncertainty to process and compare experimental data. These ideas include not only knowing what it means to use an instrument to take a measurement, but also being able to apply that knowledge, including the ideas that make up uncertainty analysis, to every aspect of an experiment. A physics laboratory course for the Energy Systems Engineering programme at Uppsala University has been designed to focus on teaching students the ideas of measurement and the associated laboratory skills. In the reported study, we use an open-ended survey to investigate students’ ideas about data processing and data comparison before and after this laboratory course. The results show that several students, even after the course, are still unable to appropriately use the ideas of uncertainty. This suggests that these ideas must be continuously revisited and explored as a fundamental part of all undergraduate laboratory experiences.

  9. Publications and geothermal sample library facilities of the Earth Science Laboratory, University of Utah Research Institute

    Energy Technology Data Exchange (ETDEWEB)

    Wright, Phillip M.; Ruth, Kathryn A.; Langton, David R.; Bullett, Michael J.

    1990-03-30

    The Earth Science Laboratory of the University of Utah Research Institute has been involved in research in geothermal exploration and development for the past eleven years. Our work has resulted in the publication of nearly 500 reports, which are listed in this document. Over the years, we have collected drill chip and core samples from more than 180 drill holes in geothermal areas, and most of these samples are available to others for research, exploration and similar purposes. We hope that scientists and engineers involved in industrial geothermal development will find our technology transfer and service efforts helpful.

  10. Target fabrication for high density target experiments at the University of Rochester's Laboratory for Laser Energetics

    International Nuclear Information System (INIS)

    A theoretical and experimental program is in progress at the University of Rochester's Laboratory for Laser Energetics to demonstrate high density compression using the 351-nm, uniform illumination, OMEGA laser facility. The targets that have the best chance of meeting the objectives of this campaign are low-Z polymer shells with liquid or solid DT layers. This paper describes fabrication activities of such targets. These activities include polymer shell fabrication, development of a cryogenic fuel facility, a tritium filling facility, development of low-mass target supports, and development of levitated target coating

  11. Status of the Laboratory for Electron Beam Research and Application of Nihon University

    International Nuclear Information System (INIS)

    Operation time of the 125-MeV electron linac was approximately 2000 hours in 2010 at the Laboratory for Electron Beam Research and Application in Nihon University, serving total of 1400 hours of beam time for users' experiments. In addition to conventional full-beam acceleration, a burst-beam acceleration mode was implemented in the renewed electron gun system. The x-ray intensity in the parametric x-ray radiation beam has been measured using thin-wall ion chambers developed for in-line monitoring. (author)

  12. Evaluation of the Young Children with Neurodevelopmental Disability: A Prospective Study at Hamadan University of Medical Sciences Clinics

    OpenAIRE

    FAYYAZI, Afshin; Leila KHEZRIAN; Zohreh KHERADMAND; DAMADI, Somayeh; Ali KHAJEH

    2013-01-01

    How to Cite This Article: Fayyazi A, Kheizrian L, Kheradmand Z, Damadi S, Khajeh A. Evaluation of the Young Children with Neurodevelopmental Disability: A Prospective Study at Hamadan University of Medical Sciences Clinics. Iran J Child Neurol. 2013 Winter; 7 (1):29-33. ObjectiveDevelopmental impairment is a common problem in children health that occurs in approximately 5–10% of the childhood population. The aim of this study was to determine the etiologic yield of subspecialists’ evaluation ...

  13. University of Arizona TRIGA reactor. Annual utilization report, July 1, 1983-June 30, 1984 (Docket 50-113)

    International Nuclear Information System (INIS)

    This is the Annual Report covering the period July 1, 1983 through June 30, 1984, for the activities of the TRIGA Mark I Reactor at the University of Arizona, Tucson, Arizona. This report is submitted in compliance of Section 6.7e of the Facility Technical Specifications and Paragraph 50.59(b) of Title 10, Code of Federal Regulations

  14. Safety Evaluation Report related to the renewal of the operating license for the training and research reactor at the University of Michigan (Docket No. 50-2)

    International Nuclear Information System (INIS)

    This Safety Evaluation Report for the application filed by the University of Michigan (UM) for renewal of the Ford Nuclear Reactor (FNR) operating license number R-28 to continue to operate its research reactor has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is located on the North Campus of the University of Michigan in Ann Arbor, Michigan. The staff concludes that the reactor can continue to be operated by the University of Michigan without endangering the health and safety of the public

  15. Final report on the University of Florida U.S. Department of Energy 1995--96 Reactor Sharing Program

    Energy Technology Data Exchange (ETDEWEB)

    Vernetson, W.G.

    1996-11-01

    Grant support has been well used by the University of Florida as host institution to support various educational institutions in the use of the reactor and associated facilities as indicated in the proposal. These various educational institutions are located primarily within Florida. However, when the 600-mile distance from Pensacola to Miami is considered, it is obvious that this Grant provides access to reactor utilization for a broad geographical region and a diverse set of user institutions serving over twelve million inhabitants throughout the State of Florida and still others throughout the nation. All users and uses were carefully screened to assure the usage was for educational institutions eligible for participation in the Reactor Sharing Program; where research activities were involved, care was taken to assure the research activities were not funded by grants for contract funding from outside sources. In some cases external grant funding is limited or is used up, in which case the Reactor Sharing Grant and frequent cost sharing by the UFTR facility and the University of Florida provide the necessary support to complete a project or to provide more results to make a complete project even better. In some cases this latter usage has aided renewal of external funding. The role of the Reactor Sharing Program, though relatively small in dollars, has been the single most important occurrence in assuring the rebirth and continued high utilization of the UFTR in a time when many better equipped and better placed facilities have ceased operations. Through dedicated and effective advertising efforts, the UFTR has seen nearly every four-year college and university in Florida make substantive use of the facility under the Reactor Sharing Program with many now regular users. Some have even been able to support usage from outside grants where the Reactor Sharing Grant has served as seed money; still others have been assisted when external grants were depleted.

  16. Final report on the University of Florida U.S. Department of Energy 1995--96 Reactor Sharing Program

    International Nuclear Information System (INIS)

    Grant support has been well used by the University of Florida as host institution to support various educational institutions in the use of the reactor and associated facilities as indicated in the proposal. These various educational institutions are located primarily within Florida. However, when the 600-mile distance from Pensacola to Miami is considered, it is obvious that this Grant provides access to reactor utilization for a broad geographical region and a diverse set of user institutions serving over twelve million inhabitants throughout the State of Florida and still others throughout the nation. All users and uses were carefully screened to assure the usage was for educational institutions eligible for participation in the Reactor Sharing Program; where research activities were involved, care was taken to assure the research activities were not funded by grants for contract funding from outside sources. In some cases external grant funding is limited or is used up, in which case the Reactor Sharing Grant and frequent cost sharing by the UFTR facility and the University of Florida provide the necessary support to complete a project or to provide more results to make a complete project even better. In some cases this latter usage has aided renewal of external funding. The role of the Reactor Sharing Program, though relatively small in dollars, has been the single most important occurrence in assuring the rebirth and continued high utilization of the UFTR in a time when many better equipped and better placed facilities have ceased operations. Through dedicated and effective advertising efforts, the UFTR has seen nearly every four-year college and university in Florida make substantive use of the facility under the Reactor Sharing Program with many now regular users. Some have even been able to support usage from outside grants where the Reactor Sharing Grant has served as seed money; still others have been assisted when external grants were depleted

  17. Evaluation of the Young Children with Neurodevelopmental Disability: A Prospective Study at Hamadan University of Medical Sciences Clinics

    Directory of Open Access Journals (Sweden)

    Afshin FAYYAZI

    2013-02-01

    Full Text Available How to Cite This Article: Fayyazi A, Kheizrian L, Kheradmand Z, Damadi S, Khajeh A. Evaluation of the Young Children with Neurodevelopmental Disability: A Prospective Study at Hamadan University of Medical Sciences Clinics. Iran J Child Neurol. 2013 Winter; 7 (1:29-33. ObjectiveDevelopmental impairment is a common problem in children health that occurs in approximately 5–10% of the childhood population. The aim of this study was to determine the etiologic yield of subspecialists’ evaluation of young children with developmental disability.Materials & MethodsAll children aged between 2 months and 5 years referred over a 15-month period to Hamadan University of Medical Sciences subspecialty services for initial evaluation of a suspected developmental Disability, were enrolled in the present study. Diagnostic yield was determined after the completion of clinical assessments and laboratory tests requested by the evaluating physician.ResultsA total of 198 children (129 boys and 69 girls were eligible for our study.108 children had global developmental delay and 90 children had isolated developmental delay. Approximately ¼ of all patients did not have any specific etiology for developmental disability. Cerebral palsy (CP was the most common clinical syndrome in all patients (41.4%. Hypoxic ischemic encephalopathy (13.8%, brain dysgenesis (13%, genetic disorder (13%, and  neurodegenerative  diseases  (11%  were  determined  in  more  than one half of all children with global developmental disability. in our study, “developmental speech delay” was the common cause of isolated speech delay.ConclusionDetermination of an underlying etiology is an essential part of specialty evaluation of young children with developmental disability. The results of this study were similar closely to the results of other studies. ReferencesBernard LM. Current Management in Child Neurology. 3rd ed. London: BC Decker Inc; 2005. pp. 3-8 and 246-50.Cleary M A

  18. Laboratory instruction for nuclear engineering application experiments

    International Nuclear Information System (INIS)

    This report contains several laboratory instruction texts for 'Nuclear Engineering Application Experiments', which has been offered to Graduate students of Graduate School of Engineering at Kyoto University from 1970's. These experiments have been carried out by using experimental facilities; a research reactor, a critical assembly, accelerators, and a hot laboratory at Kyoto University Research Institute. (author)

  19. 2015 Annual Reuse Report for the Idaho National Laboratory Site’s Advanced Test Reactor Complex Cold Waste Ponds

    Energy Technology Data Exchange (ETDEWEB)

    Lewis, Michael George [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2016-02-01

    This report describes conditions and information, as required by the state of Idaho, Department of Environmental Quality Reuse Permit I-161-02, for the Advanced Test Reactor Complex Cold Waste Ponds located at Idaho National Laboratory from November 1, 2014–October 31, 2015. The effective date of Reuse Permit I-161-02 is November 20, 2014 with an expiration date of November 19, 2019.

  20. Identification of a leaking TRIGA fuel element at the nuclear reactor facility of the University of Pavia

    International Nuclear Information System (INIS)

    During a periodical activity of characterization of the ionic-exchange resins of the demineralizer of the primary cooling circuit of the TRIGA Mark-2 reactor of the University of Pavia a small but detectable amount of Cs137 contamination was measured. Since the reactor has been running for several hundreds of hours at full power without showing any anomaly in the radiometric and thermo-hydraulic parameters, the reactor was brought to the nominal power of 250 kW for one hour and a sample of water was collected from the reactor tank and analysed in a low-background gamma ray detector. As a result a small amount of fission products were detected in the reactor pool water (a few Bq/g) suggesting the existence of a possible clad defect in one or more fuel elements. Since no halogens such as iodine and bromine were detected in the sampled water, the more likely hypothesis, also supported by literature, seemed to be a micro-fissure in the neck of an instrumented fuel element. A dedicated apparatus for reactor pool water sampling and on-line spectroscopy measurements was realized. As expected, the fission product leakage was due to a micro-fissure of a fuel element that released noble gas only when the fuel element was heated up to a temperature around 90 Celsius degrees. The leaking fuel element was identified and removed from its position and the reactor was back in regular operation after 2 months from leakage detection. (authors)

  1. 普通高校青年教师职业压力调查%Young University Teachers' Occupational Stress

    Institute of Scientific and Technical Information of China (English)

    王莉; 赵光珍

    2013-01-01

    目的 探讨普通高校青年教师职业压力的特点并分析原因.方法 采用前期研究所编制的《高校青年教师职业压力调查问卷》对3所普通高校的青年教师进行调查,并分析不同群体之间的差异.结果 ①高校青年教师的职业压力由大到小依次为:科研压力、教学压力、学生压力和人际压力;②在科研压力维度上,不同年龄段之间存在显著差异(t=-4.147,P<0.01);③不同职称高校青年教师在科研压力方面存在显著差异(F=4.119,P<0.01).结论 普通高校青年教师总体压力处于中度压力水平,科研压力相对较大.%Objective To explore features of young university teachers' occupational stress,and analyze the reasons. Methods The study investigated young university teachers from 3 universities with The Questionnaire of Young College Teachers Occupation Stress,and analyzed the differences among different groups. Results ①Young college teachers' occupation pressure from large to small in turn was:Scientific research,teaching,students' pressure and interpersonal stress.②In scientific research dimension,significant differences existed between different age(t= -4. 147,P<0. 01). ③Different titles of young college teachers occupation stress had the significant difference in scientific research pressure aspect(F = 4. 119,P<0. 01). Conclusion Young university teachers' overall pressure is at moderate pressure level,scientific research pressure is relatively large.

  2. Utilisation of research and training reactors in the study programme of students at the Slovak University of Technology

    International Nuclear Information System (INIS)

    Preparing operating staff for the nuclear industry is and also will be one of the most serious education processes, mainly in the Central-European countries where about 40-50% of the electricity is produced in nuclear power plants. In the Central-European region there exists a very extensive and also effective international collaboration in nuclear industry and education. Similarly, the level of education in universities and technical high schools of this area is also good. Slovak University of Technology Bratislava has established contacts with many universities abroad for utilisation of research and training reactors. (author)

  3. Report of the research results with University of Tokyo Nuclear Engineering Research Laboratory's facilities in fiscal 1975

    International Nuclear Information System (INIS)

    Results of the research works by educational institutions using fast neutron source reactor 'Yayoi' etc. of Nuclear Engineering Research Laboratory in fiscal 1975 are reported in individual summaries. Fields of research are the following: shielding benchmark experiment, research on medical irradiation, irradiation experiments, experiments by small research groups, fast neutron streaming experiment, and so on. (Mori, K.)

  4. Development of the University of Washington Biofuels and Biobased Chemicals Process Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Gustafson, Richard [University of Washington

    2014-02-04

    The funding from this research grant enabled us to design and build a bioconversion steam explosion reactor and ancillary equipment such as a high pressure boiler and a fermenter to support the bioconversion process research. This equipment has been in constant use since its installation in 2012. Following are research projects that it has supported: • Investigation of novel chip production method in biofuels production • Investigation of biomass refining following steam explosion • Several studies on use of different biomass feedstocks • Investigation of biomass moisture content on pretreatment efficacy. • Development of novel instruments for biorefinery process control Having this equipment was also instrumental in the University of Washington receiving a $40 million grant from the US Department of Agriculture for biofuels development as well as several other smaller grants. The research that is being done with the equipment from this grant will facilitate the establishment of a biofuels industry in the Pacific Northwest and enable the University of Washington to launch a substantial biofuels and bio-based product research program.

  5. License renewal and power upgrade of the Cornell University TRIGA reactor

    International Nuclear Information System (INIS)

    The Cornell Mark II TRIGA reactor has been a principal facility for instruction and research in nuclear science and engineering at Cornell, and it has been extensively used by other departments at Cornell and by nearby universities and industries. Initially the fuel was low hydride, 8.5w/o 19%-enriched, aluminum clad; in 1974 it was changed to high-hydride, stainless-steel-clad. The maximum power has been 100 kW, with pulses to $2, and operation has been on a one-shift demand basis. Annual energy generation of 50 MWH has been typical. Standard features include a 4-inch tangential port and our 6-inch radial ports, a thermal column with hohlraum and vertical access, a central thimble, a 'rabbit', and a set of dry irradiation tubes, replacing the 'Lazy Susan'. The license was renewed and amended in November 1983; the new limits are 500 kW and $3 pulses. Physical changes to the facility included addition of a water-to-water heat exchanger and of a diffuser at the water outlet ∼ 60 cm above the core. The flow rate is 300 liters per minute in the primary (reactor) side of the heat exchanger. The temperature of the chilled water entering the secondary of the exchanger is ∼ 12?C; its flow rate is adjusted by a servo-controlled by-pass valve to maintain the desired range of pool water temperature. Steps taken to go to higher power included rearrangement of fuel elements to increase excess reactivity, recalibration of control rods, and power vs ion chamber current calibrations at successively higher power by comparing the rate of rise of pool temperature with a known rate using electrical heating elements. Steady-state operation has been done up to 480 kW (nominal) but pulsing at the newly allowed higher levels has not been tested as yet

  6. Severe transient analysis of the Penn State University Advanced Light Water Reactor

    International Nuclear Information System (INIS)

    The Penn State University Advanced Light Water Reactor (PSU ALWR) incorporates various passive and active ultra-safe features, such as continuous online injection and letdown for pressure control, a raised-loop primary system for enhanced natural circulation, a dedicated primary reservoir for enhanced thermal hydraulic control, and a secondary shutdown turbine. Because of the conceptual design basis of the project, the dynamic system modeling was to be performed using a code with a high degree of flexibility. For this reason the modeling has been performed with the Modular Modeling System (MMS). The basic design and normal transients have been performed successfully with MMS. However, the true test of an inherently safe concept lies in its response to more brutal transients. Therefore, such a demonstrative transient is chosen for the PSU ALWR: a turbine trip and reactor scram, concurrent with total loss of offsite ac power. Diesel generators are likewise unavailable. This transient demonstrates the utility of the pressure control system, the shutdown turbine generator, and the enhanced natural circulation of the PSU ALWR. The low flow rates, low pressure drops, and large derivative states encountered in such a transient pose special problems for the modeler and for MMS. The results of the transient analyses indicate excellent performance by the PSU ALWR in terms of inherently safe operation. The primary coolant enters full natural circulation, and removes all decay heat through the steam generators. Further, the steam generators continually supply sufficient steam to the shutdown power system, despite the abrupt changeover to the auxiliary feedwater system. Finally, even with coincident failures in the pressurization system, the primary repressurizes to near-normal values, without overpressurization. No core boiling or uncovery is predicted, and consequently fuel damage is avoided. 17 refs., 19 figs., 4 tabs

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

    International Nuclear Information System (INIS)

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

  8. The LABGENE - Nucleus-Electric Energy Generation Laboratory small scale reactor

    International Nuclear Information System (INIS)

    This paper approaches the small nuclear reactors and also some advantages and technological aspects of the fabrication of LABGENE nuclear reactor. This enterprise which is pioneer in Brazil, demonstrates the viability of execution these projects in the country, considering the engineering capacity and availability of the brazilian industrial park

  9. Implementation of a Program on Experiencing and Application of Research Reactor for University Students Majoring in Science and Technology

    International Nuclear Information System (INIS)

    This report was written as following contents, to develop a program for university students majoring in science and technology, which is intended to provide the students with opportunities to obtain hands on experience and knowledge on various nuclear technology, through experiments using HANARO and its facilities. Thus obtain experience and knowledge are expected to be a great help for their current study and for their selection of a specific future study area. The purpose of this research is as follows: - Development of various curricula for specific research using HANARO and continuous operation of the developed curricula to provided university students with opportunities to use HANARO as part of their university study. - Continuous operation of research reactor experimental programs for university students in nuclear field to make contribution to cultivating specialists. - Development and operation of training programs of experiments using research reactor for university students majoring in nuclear engineering and also for university students majoring in diverse fields of science and technology such as Physics, Radiation, Mechanical engineering, Fire fighting, Medicine and Biology to cultivate future potential users of HANARO as well as broadening the user group. As a whole, 244 students from 15 universities have completed the courses of the programs developed and offered by this project. Also, 5 textbooks have been developed to support the programs

  10. Aspects of Reactor Physics Research at the Victoria University of Manchester

    International Nuclear Information System (INIS)

    The Nuclear Engineering Department at Manchester University was established in 1959. Since that time post-graduate reactor physics studies have gradually enlarged and developed, starting virtually from scratch; experimental studies have concentrated on light-water systems and centred on the accelerator-driven, natural-uranium, light-water exponential. The paper contains a survey of the work to date, discussion of the results obtained, outlines of proposed future work, and, as they arise in the text, descriptions of various low-cost, labour-saving experimental techniques which have been adopted. The various divisions of the work are described below. The authors have studied neutron diffusion in light water using both pulsed source and steady source methods. In the former method they have particularly stressed full harmonic analysis to the extent of actually studying the higher modes as opposed to most former work which has tried only to eliminate them. In the study of steady source methods they have concentrated on eliminating all effects from finite source and detector size, resonance activation, flux perturbation and so on. The results of both are discussed and compared. A very careful measurement of absorption cross-sections by the pulsed technique, taking care to eliminate harmonic and other effects likely to lead to error is also in progress and is described. Thermal neutron spectra in ''poisoned'' light water are being measured as a means of investigating and developing integral detector techniques. This discussion includes some interesting time- and cost-saving examples. Large foil activation and counting techniques for measuring spatially averaged neutron densities, and hence a number of reactor parameters, have been studied. Some interesting points have arisen, particularly with regard to spectrum measurement. The method makes possible many reactor physics investigations with limited resources. A low-cost natural uranium, light-water exponential has been

  11. Evaluation of Tuberculosis Laboratory results in Çanakkale Onsekiz Mart University Research and Education Hospital for 2009-2011

    OpenAIRE

    Nilgun ÖZBEY; Alper AKÇALI; Tatman-Otkun, Müşerref

    2012-01-01

    Objective: Tuberculosis microbiological laboratorydiagnosis was firstly started in year 2009, in MicrobiologyLaboratory of Onsekiz Mart University Research andEducation Hospital in Çanakkale. We aimed at thisstudy to present our laboratory data and to evaluatethe methods which were used for the diagnosis ofmicobacteria.Method: Samples sent to our laboratory fortuberculosis culture were stained by Ehrlich-Ziehl-Neelsen (EZN) method and evaluated microscopically.After processing of samples, eac...

  12. IAEA Activities supporting education and training at research reactors

    International Nuclear Information System (INIS)

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

  13. [Laboratory medicine in the post-genome era: experiences in Chiba University Hospital].

    Science.gov (United States)

    Nomura, Fumio

    2008-12-01

    Since the completion of the human genome project, there is growing interest in the clinical application of genome sciences. For this purpose, particular attention toward identifying at-risk individuals and understanding the complexities of the testing process are essential. In this article, I describe the importance of clinical genetics and genetic counseling, and explain how and why the division of laboratory medicine is involved in these tasks in Chiba University Hospital. Our genetic counseling team consists of a clinical laboratory physician qualified as a clinical geneticist, medical technologist qualified as a genetic counselor, clinical psychologists, and a medical social worker. We treat more than 100 cases including late-onset, incurable neurological diseases, hereditary tumors, prenatal diagnosis, and chromosomal abnormalities. The sequencing of the human genome has paved the way for comprehensive transcriptome and proteome analyses. Since the detailed understanding of biological processes, both in healthy and pathological states, requires the direct study of relevant proteins, proteomics bridges the gap between the information coded in the genome sequence and cellular behavior. Therefore, proteomics is among the most promising technologies for the development of novel diagnostic tools. Recent advances in sophisticated technologies in proteomics should identify promising ways to discover novel markers in various fields of clinical medicine. In this presentation, I will give a definition of the proteome, and outline the basic methodologies for proteome analyses. I will also present our experiences in identifying novel biomarker candidates in hepatobiliary diseases, and discuss future perspectives of clinical proteomics in laboratory medicine. PMID:19175078

  14. QA experience at the University of Wisconsin accredited dosimetry calibration laboratory

    International Nuclear Information System (INIS)

    The University of Wisconsin Accredited Dosimetry Calibration Laboratory (UW ADCL) employs procedure manuals as part of its Quality Assurance (QA) program. One of these manuals covers the QA procedures and results for all of the UW ADCL measurement equipment. The QA procedures are divided into two main areas: QA for laboratory equipment and QA for external chambers sent for calibration. All internal laboratory equipment is checked and recalibrated on an annual basis, after establishing its consistency on a 6-month basis. QA for external instruments involves checking past calibration history as well as comparing to a range of calibration values for specific instrument models. Generally, the authors find that a chamber will have a variation of less than 0.5 % from previous Co-60 calibration factors, and falls within two standard deviations of previous calibrations. If x-ray calibrations are also performed, the energy response of the chamber is plotted and compared to previous instruments of the same model. These procedures give the authors confidence in the transfer of calibration values from National Institute of Standards and Technology (NIST)

  15. QA experience at the University of Wisconsin accredited dosimetry calibration laboratory

    Energy Technology Data Exchange (ETDEWEB)

    DeWard, L.A.; Micka, J.A. [Univ. of Wisconsin, Madison, WI (United States)

    1993-12-31

    The University of Wisconsin Accredited Dosimetry Calibration Laboratory (UW ADCL) employs procedure manuals as part of its Quality Assurance (QA) program. One of these manuals covers the QA procedures and results for all of the UW ADCL measurement equipment. The QA procedures are divided into two main areas: QA for laboratory equipment and QA for external chambers sent for calibration. All internal laboratory equipment is checked and recalibrated on an annual basis, after establishing its consistency on a 6-month basis. QA for external instruments involves checking past calibration history as well as comparing to a range of calibration values for specific instrument models. Generally, the authors find that a chamber will have a variation of less than 0.5 % from previous Co-60 calibration factors, and falls within two standard deviations of previous calibrations. If x-ray calibrations are also performed, the energy response of the chamber is plotted and compared to previous instruments of the same model. These procedures give the authors confidence in the transfer of calibration values from National Institute of Standards and Technology (NIST).

  16. Handbook of materials testing reactors and ancillary hot laboratories in the European Community

    International Nuclear Information System (INIS)

    The purpose of this Handbook is to make available to those interested in 'in-pile' irradiation experiments important data on Materials Testing Reactors in operation in the European Community. Only thermal reactors having a power output of more than 5 MW(th) are taken into consideration. In particular, detailed technical information is given on the experimental irradiation facilities of the reactors, their specialized irradiation devices (loops and instrumented capsules), and the associated hot cell facilities for post-irradiation examination of samples

  17. Home-made refurbishment of the instrumentation and control system of the TRIGA reactor of the University of Pavia

    International Nuclear Information System (INIS)

    The Instrumentation and Control (I and C) System of the TRIGA reactor of the University of Pavia was dated and, in order to grant a safe and continuous reactor operation for the future, it became necessary to substitute or to upgrade the system. Since the substitution of the I and C system with a new-made one was very difficult to be performed due to long authorization procedures, an home-made refurbishment was planned. Using commercial components of high quality, almost a complete substitution, channel-by-channel, of the I and C system was realized without changing the operating and safety logics. The system includes: - the Reactor Linear Power Channel and Chart Recorder; - the Reactor Percent Power Safety Channel; - the High Voltage and Low Voltage Power Supply; - the Automatic Reactor Power Control; - the Fuel Elements and Cooling-Water Temperatures Measuring Channels; - the Water Conductivity Measuring Channel. The refurbished I and C system shows a very good operational behavior and reliability and will assure a continuous operation of the reactor for the future

  18. A gendered study of young adult contraceptive use at one university in KwaZulu-N atal

    Directory of Open Access Journals (Sweden)

    OA Oyedeji

    2006-09-01

    Full Text Available This study explores contraceptive use among young adult male and female students (aged 18-25 who visit the campus clinic at a university in KwaZulu-Natal. Both a descriptive survey and face to face interviews were used for data collection. In this study, it is affirmed that gender stratification, societal attitudes, and misconceptions about contraceptive use play an important role in the attitudes of young adults, male and female towards contraception and its use. Evidence of this is the high use of condoms amongst both male and female students’ compared with other available methods. Among female students this was highly attributed to personal convenience and comfort with condom use as an unmarried young woman. It was clear from the data collected that respondents themselves attached some stigma to being associated with the use of contraceptive pills or having to visit the clinic regularly for injections as young unmarried women. Male respondents affirmed the use of the condom, although this was hardly with the view of taking reproductive/contraceptive responsibility, but rather, it was attributed to the function of the condom as a safe sex method that offered protection against sexually transmitted diseases and infections. Also evident from the study was the fact that male respondents felt more comfortable with their sexual functioning than the female respondents. This was easily attributed to the role of societal gender stratification in an individual’s life.

  19. Stabilization of fine fraction from landfill mining in anaerobic and aerobic laboratory leach bed reactors.

    Science.gov (United States)

    Mönkäre, Tiina J; Palmroth, Marja R T; Rintala, Jukka A

    2015-11-01

    Fine fraction (FF, mined landfill was stabilized in four laboratory-scale leach bed reactors (LBR) over 180 days. The aim was to study feasibility of biotechnological methods to treat FF and if further stabilization of FF is possible. Four different stabilization methods were compared and their effects upon quality of FF were evaluated. Also during the stabilization experiment, leachate quality as well as gas composition and quantity were analyzed. The methods studied included three anaerobic LBRs (one without water addition, one with water addition, and one with leachate recirculation) and one aerobic LBR (with water addition). During the experiment, the most methane was produced in anaerobic LBR without water addition (18.0 L CH4/kg VS), while water addition and leachate recirculation depressed methane production slightly, to 16.1 and 16.4 L CH4/kg VS, respectively. Organic matter was also removed via the leachate and was measured as chemical oxygen demand (COD). Calculated removal of organic matter in gas and leachate was highest in LBR with water addition (59 g COD/kg VS), compared with LBR without water addition or with leachate recirculation (51 g COD/kg VS). Concentrations of COD, ammonium nitrogen and anions in leachate decreased during the experiment, indicating washout mechanism caused by water additions. Aeration increased sulfate and nitrate concentrations in leachate due to oxidized sulfide and ammonium. Molecular weight distributions of leachates showed that all the size categories decreased, especially low molecular weight compounds, which were reduced the most. Aerobic stabilization resulted in the lowest final VS/TS (13.1%), lowest respiration activity (0.9-1.2 mg O2/g TS), and lowest methane production after treatment (0.0-0.8 L CH4/kg VS), with 29% of VS being removed from FF. Anaerobic stabilization methods also reduced organic matter by 9-20% compared with the initial amount. Stabilization reduced the quantity of soluble nitrogen in FF and did

  20. A Fully-reconstituted Safety Basis for the University of Florida Training Reactor

    International Nuclear Information System (INIS)

    The University of Florida Training Reactor, (UFTR), is restructuring its licensing framework to help facilitate its upgrade to a digital controls system. The strategy focuses on creating an encompassing safety analysis to prove, unequivocally, that the UFTR represents a negligible risk to the health and safety of the public. This will allow a change in the Limiting Safety System Settings (LSSS) and for a reduction in the number of safety system and components (SSCs) that are defined as safety related by the Code of Federal Regulations. The safety analysis is predicated on two postulated events: a rapid insertion of a large amount of positive reactivity and the release of fission products caused by mechanical damage to a spent fuel plate. These have been selected as limiting scenarios, whose extremity bound all other accidents of consequence. The rapid insertion of positive reactivity was modeled using PARET/ANL software. Analysis shows that a reactivity insertion of $2.00 creates a maximum peak fuel temperature approximately 250 .deg. below the failure limit of 530C. The radioisotope inventory of the fission products is modeled using the ORIGEN-S module in SCALE6.1. The doses to the workers and members of the public are determined with COMPLY software and shows that the worstcase hypothetical exposures are approximately 6.5% of the annual regulatory limit

  1. Development and implementation of an automatic control algorithm for the University of Utah nuclear reactor

    International Nuclear Information System (INIS)

    The emphasis of this work is the development and implementation of an automatic control philosophy which uses the classical operational philosophies as a foundation. Three control algorithms were derived based on various simplifying assumptions. Two of the algorithms were tested in computer simulations. After realizing the insensitivity of the system to the simplifications, the most reduced form of the algorithms was implemented on the computer control system at the University of Utah (UNEL). Since the operational philosophies have a higher priority than automatic control, they determine when automatic control may be utilized. Unlike the operational philosophies, automatic control is not concerned with component failures. The object of this philosophy is the movement of absorber rods to produce a requested power. When the current power level is compared to the requested power level, an error may be detected which will require the movement of a control rod to correct the error. The automatic control philosophy adds another dimension to the classical operational philosophies. Using this philosophy, normal operator interactions with the computer would be limited only to run parameters such as power, period, and run time. This eliminates subjective judgements, objective judgements under pressure, and distractions to the operator and insures the reactor will be operated in a safe and controlled manner as well as providing reproducible operations

  2. Reactor Sharing Program

    International Nuclear Information System (INIS)

    Support utilization of the RINSC reactor for student and faculty instructions and research. The Department of Energy award has provided financial assistance during the period 9/29/1995 to 5/31/2001 to support the utilization of the Rhode Island Nuclear Science Center (RINSC) reactor for student and faculty instruction and research by non-reactor owning educational institutions within approximately 300 miles of Narragansett, Rhode Island. Through the reactor sharing program, the RINSC (including the reactor and analytical laboratories) provided reactor services and laboratory space that were not available to the other universities and colleges in the region. As an example of services provided to the users: Counting equipment, laboratory space, pneumatic and in-pool irradiations, demonstrations of sample counting and analysis, reactor tours and lectures. Funding from the Reactor Sharing Program has provided the RINSC to expand student tours and demonstration programs that emphasized our long history of providing these types of services to the universities and colleges in the area. The funding have also helped defray the cost of the technical assistance that the staff has routinely provided to schools, individuals and researchers who have called on the RINSC for resolution of problems relating to nuclear science. The reactor has been featured in a Public Broadcasting System documentary on Pollution in the Arctic and how a University of Rhode Island Professor used Neutron Activation Analysis conducted at the RINSC to discover the sources of the ''Arctic Haze''. The RINSC was also featured by local television on Earth Day for its role in environmental monitoring

  3. In-core dosimetry in CAGR - measurements on power reactors and laboratory facilities

    International Nuclear Information System (INIS)

    The problem of radiolytic corrosion of the graphite moderator in CAGR has led to a need for more accurate information on the radiation dose to the coolant gas in the pores of the graphite. An experimental in-core dosimetry programme is in progress to acquire this data. The problems of in-core dosimetry, particularly that of measuring gamma dose in the presence of high thermal neutron fluences, are described with reference to calorimetry, ionisation chambers and thermoluminescence dosimeters. Progress made in the refinement of these techniques for reactor dosimetry is described. An experiment is described in which dosimetry measurements in components of a Heysham Power Station reactor were made during its commissioning. The major facility of this dosimetry programme is a zero-energy research reactor constructed from CAGR components; this reactor and its experimental facilities are described, together with the results of some of the first experiments. (author)

  4. A versatile reactor for continuous monitoring of biofilm properties in laboratory and industrial conditions

    OpenAIRE

    M.O. Pereira; Morin, P.; Vieira, M. J.; Melo, L. F.

    2002-01-01

    Aims: The understanding of the dynamics of surface microbial colonization with concomitant monitoring of biofilm formation requires the development of biofilm reactors that enable direct and real-time evaluation under different hydrodynamic conditions. Methods and Results: This work proposes and discusses a simple flow cell reactor that provides a means to monitoring biofilm growth by periodical removing biofilm-attached slides for off-line, both non-destructive and destructive biofilm ana...

  5. Government-industry-uUniversity and rResearch lLaboratories cCoordination for new product development: Session 2. Government research laboratory perspective

    Energy Technology Data Exchange (ETDEWEB)

    Kuzay, T.M.

    1997-09-01

    This talk is the second in an expanded series of presentations on the Government-Industry-University and Research Laboratories Coordination for new product development, which is a timely and important public policy issue. Such interactions have become particularly timely in light of the present decline in funding for research and development (R&D) in the nation`s budget and in the private sector. These interactions, at least in principle, provide a means to maximize benefits for the greater good of the nation by pooling the diminishing resources. National laboratories, which traditionally interacted closely with the universities in educational training, now are able to also participate closely with industry in joint R&D thanks to a number of public laws legislated since the early 80s. A review of the experiences with such interactions at Argonne National Laboratory, which exemplifies the national laboratories, shows that, despite differences in their traditions and the missions, the national laboratory-industry-university triangle can work together.

  6. Government-industry-uUniversity and rResearch lLaboratories cCoordination for new product development: Session 2. Government research laboratory perspective

    International Nuclear Information System (INIS)

    This talk is the second in an expanded series of presentations on the Government-Industry-University and Research Laboratories Coordination for new product development, which is a timely and important public policy issue. Such interactions have become particularly timely in light of the present decline in funding for research and development (R ampersand D) in the nation''s budget and in the private sector. These interactions, at least in principle, provide a means to maximize benefits for the greater good of the nation by pooling the diminishing resources. National laboratories, which traditionally interacted closely with the universities in educational training, now are able to also participate closely with industry in joint R ampersand D thanks to a number of public laws legislated since the early 80s. A review of the experiences with such interactions at Argonne National Laboratory, which exemplifies the national laboratories, shows that, despite differences in their traditions and the missions, the national laboratory-industry-university triangle can work together

  7. Report of the research results with University of Tokyo, Nuclear Engineering Research Laboratory's Facilities in fiscal 1989

    International Nuclear Information System (INIS)

    This is the report of the results of research carried out by the common utilization of the reactor 'Yayoi' and an electron accelerator in the Nuclear Engineering Research Laboratory in fiscal year 1989. In fiscal year 1989, the research themes using the reactor Yayoi or related to it were 15, and those using the linear accelerator reached 12, thus the common utilization attracted the strong interest of users. The Yayoi has been operated satisfactorily without trouble. The results of the research carried out by the common utilization of the Yayoi and a linac and the reports of 12 Yayoi research meetings in fiscal year 1989 are collected. (J.P.N.)

  8. The Agent of Dermatophytosis in Patients Attending to the Mycrobiology Laboratory of Dicle University Medical Faculty

    Directory of Open Access Journals (Sweden)

    Tuncer Özekinci

    2006-01-01

    Full Text Available The clinical specimens of 538 patients, sent to Microbiology Laboratory of Medical Faculty, Dicle University, with pre-diagnosis of dermatophytosis, were investigated by direct microscopic and culture methods. Of 106 patients diagnosed as having dermatophytosis, the causative dermatophytes were isolated in 75 (70,6 %; while in 31 (29,3%, dermatophytes could not be isolated. Among dermatophytes Trichophyton rubrum (69,2% was the most frequently isolated dermatophyte followed by Trichophyton mentagrophytes (8,0% ve Trichophyton violaceum (8,0%. As a result, our findings were similar to those studies in Turkey. It was also determined that direct microscopy and media shold be used together when examining dermatophytes.

  9. Radiation Laboratory, University of Notre Dame quarterly report, October 1--December 31, 1990

    Energy Technology Data Exchange (ETDEWEB)

    1991-01-23

    This report, on research preformed at the Radiation Laboratory, University of Notre Dame, contain contributions on such topics as: formation of carbenium ions or yields from carbenes, photochemical oxidations and reductions, photoreactivity of molybdates, radiolysis of water, spin trapping kinetics, pulse radiolysis, photogenerated radical anions, photochemistry of Fe and Re complexes, hyperfine coupling calculations, electron energy loss in hydrocarbons, radiolysis of halophenols, conductivity in lipid monolayers, solitonsin polyacetylene, triplet-triplet annhilation, random walk problems, proton and electron impact on water luminescence quenching, raman spectrum of ozonide ion, time-resolved spectra of supercritical fluids, sequential biphotonic photochemistry, reduction of CO{sub 2} with Cu(I) macrocycles,and studies on photosensitizing dyes and on air-water interface problems. (CBS)

  10. Association Euratom - Risoe National Laboratory for Sustainable Energy, Technical University of Denmark. Annual progress report 2010

    Energy Technology Data Exchange (ETDEWEB)

    Korsholm, S.B.; Michelsen, P.K.; Rasmussen, J.J.; Westergaard, C.M. (eds.)

    2011-04-15

    The programme of the Research Unit of the Fusion Association Euratom - Risoe National Laboratory for Sustainable Energy, Technical University of Denmark, covers work in fusion plasma physics and in fusion technology. The fusion plasma physics research focuses on turbulence and transport, and its interaction with the plasma equilibrium and particles. The effort includes both first principles based modelling, and experimental observations of turbulence and of fast ion dynamics by collective Thomson scattering. Within fusion technology there are activities related to development of high temperature superconductors. Other activities are system analysis, initiative to involve Danish industry in ITER contracts and public information. A summary is presented of the results obtained in the Research Unit during 2010. (Author)

  11. Association Euratom - Risoe National Laboratory for Sustainable Energy, Technical University of Denmark. Annual progress report 2009

    Energy Technology Data Exchange (ETDEWEB)

    Korsholm, S.B.; Michelsen, P.K.; Rasmussen, J.J.; Westergaard, C.M. (eds.)

    2010-04-15

    The programme of the Research Unit of the Fusion Association Euratom - Risoe National Laboratory for Sustainable Energy, Technical University of Denmark, covers work in fusion plasma physics and in fusion technology. The fusion plasma physics research focuses on turbulence and transport, and its interaction with the plasma equilibrium and particles. The effort includes both first principles based modelling, and experimental observations of turbulence and of fast ion dynamics by collective Thomson scattering. Within fusion technology there are activities related to development of high temperature superconductors. Minor activities are system analysis, initiative to involve Danish industry in ITER contracts and public information. A summary is presented of the results obtained in the Research Unit during 2009. (Author)

  12. The University of Wisconsin-Madison Torsatron/Stellarator Laboratory program, FY 1991--1993

    International Nuclear Information System (INIS)

    This document summarizes results obtained during the first eight months of the current three year grant for research at the University of Wisconsin-Madison Torsatron/Stellarator Laboratory (TSL) and presents plans for future activity during fiscal years 1992 and 1993. Research efforts have focused on fundamental physics issues associated with toroidal confinement, predominantly through experimental investigations on the Interchangeable Module Stellarator (IMS). The program direction has been guided into studies of fluctuations, potentials and electric fields, plasma currents and flows, and effects of magnetic islands by a desire for increased relevance and impact on the general toroidal confinement program. Theoretical and computational activities are also being undertaken to support the experimental research and to identify interesting new toroidal confinement concepts which could contribute to the understanding of tokamak transport

  13. [The Codex of the Laboratory of Pharmacognosy of the University of Athens, Part. I].

    Science.gov (United States)

    Philianos, Skevos; Skaltsa, Hélène

    2015-06-01

    This work concerns the first part of a manuscript written in the 18th century and stored in the Laboratory of Pharmacognosy of the University of Athens. This part includes an introduction based on the theories of Hippocrates and Galen concerning the four humors: blood, phlegm, yellow bile and black bile, which should be in balance. During the seasons and depending of the age, these humors are converted to each other. Blood increases in the spring and in children, phlegm is growing in winter and in old man, yellow bile in adulthood and black bile in the fall and the third age. The disease is due to the increase or decrease in these fluids. Many formulas with purgative and cholagogue effects are described for each humor. The chapter ends with advice on the necessary diet, hygiene and lifestyle to keep health care. PMID:26189314

  14. Association Euratom - Risoe National Laboratory for Sustainable Energy, Technical University of Denmark. Annual progress report 2008

    Energy Technology Data Exchange (ETDEWEB)

    Korsholm, S.B.; Michelsen, P.K.; Rasmussen, J.J.; Westergaard, C.M. (eds.)

    2009-04-15

    The programme of the Research Unit of the Fusion Association Euratom - Risoe National Laboratory for Sustainable Energy, Technical University of Denmark, covers work in fusion plasma physics and in fusion technology. The fusion plasma physics research focuses on turbulence and transport, and its interaction with the plasma equilibrium and particles. The effort includes both first principles based modelling, and experimental observations of turbulence and of fast ion dynamics by collective Thomson scattering. New activities in technology related to development of high temperature superconductors have been initiated in 2008. Minor activities are system analysis, initiative to involve Danish industry in ITER contracts and public information. A summary is presented of the results obtained in the Research Unit during 2008. (Author)

  15. Association Euratom - Risoe National Laboratory for Sustainable Energy, Technical University of Denmark. Annual progress report 2009

    International Nuclear Information System (INIS)

    The programme of the Research Unit of the Fusion Association Euratom - Risoe National Laboratory for Sustainable Energy, Technical University of Denmark, covers work in fusion plasma physics and in fusion technology. The fusion plasma physics research focuses on turbulence and transport, and its interaction with the plasma equilibrium and particles. The effort includes both first principles based modelling, and experimental observations of turbulence and of fast ion dynamics by collective Thomson scattering. Within fusion technology there are activities related to development of high temperature superconductors. Minor activities are system analysis, initiative to involve Danish industry in ITER contracts and public information. A summary is presented of the results obtained in the Research Unit during 2009. (Author)

  16. Association Euratom - Risoe National Laboratory for Sustainable Energy, Technical University of Denmark. Annual progress report 2008

    International Nuclear Information System (INIS)

    The programme of the Research Unit of the Fusion Association Euratom - Risoe National Laboratory for Sustainable Energy, Technical University of Denmark, covers work in fusion plasma physics and in fusion technology. The fusion plasma physics research focuses on turbulence and transport, and its interaction with the plasma equilibrium and particles. The effort includes both first principles based modelling, and experimental observations of turbulence and of fast ion dynamics by collective Thomson scattering. New activities in technology related to development of high temperature superconductors have been initiated in 2008. Minor activities are system analysis, initiative to involve Danish industry in ITER contracts and public information. A summary is presented of the results obtained in the Research Unit during 2008. (Author)

  17. Association Euratom - Risoe National Laboratory for Sustainable Energy, Technical University of Denmark. Annual progress report 2010

    International Nuclear Information System (INIS)

    The programme of the Research Unit of the Fusion Association Euratom - Risoe National Laboratory for Sustainable Energy, Technical University of Denmark, covers work in fusion plasma physics and in fusion technology. The fusion plasma physics research focuses on turbulence and transport, and its interaction with the plasma equilibrium and particles. The effort includes both first principles based modelling, and experimental observations of turbulence and of fast ion dynamics by collective Thomson scattering. Within fusion technology there are activities related to development of high temperature superconductors. Other activities are system analysis, initiative to involve Danish industry in ITER contracts and public information. A summary is presented of the results obtained in the Research Unit during 2010. (Author)

  18. QA Programme of the TLD laboratory of the University of Costa Rica: IEC 61066 testing

    International Nuclear Information System (INIS)

    The Thermoluminescence Personal Dosimetry Laboratory of the University of Costa Rica provides dose measurements for around 90% of occupational radiation workers in the country. The assessment of doses to workers routinely exposed to external sources of radiation constitutes an integral part of any radiation protection programme and helps national authorities to ensure acceptably safe and satisfactory radiological conditions in workplaces. Harshaw Readers Model 4000 and 4500, dosimeter holders Type 8814 with TLD-100 in 0110 cards and loose TLD-100 chips are used to monitor personal dose equivalent, Hp(10) and Hp(0.07). In order to provide a reliable measurement of the operational quantities, a study was undertaken to verify the fulfillment of international requirements in our system (Model 4500 with cards) against the Thermoluminescence dosimetry systems for personal and environmental monitoring CEI IEC 61066 (1991 -2012). The type tests performed were nine in total: batch homogeneity, reproducibility, linearity, detection threshold, effect of climate conditions on reader, effect of light exposure on dosimeters, isotropy, transient voltage and dropping on dosimeters. A Cesium-137 source was used to irradiate the dosimeters and all procedures follow the indications given on the standard. Results showed that all IEC criteria were met by our Laboratory. Acceptable uncertainties were also studied under the ICRP recommendations; the analysis of the Trumpet Curve was done with satisfactory results (for doses above 0.5 mSv; quotient of measure to real dose less than 3%). For purposes of accreditation (ISO/IEC 17025:2005) and performance testing this work is very relevant since the University of Costa Rica wants to establish a solid individual monitoring programme for external radiation exposure that will provide users, registrants, licensees and regulatory bodies with information that can be used for the optimization of protection and dose limitation of Costa Rican workers

  19. Advances in boron neutron capture therapy (BNCT) at kyoto university - From reactor-based BNCT to accelerator-based BNCT

    Science.gov (United States)

    Sakurai, Yoshinori; Tanaka, Hiroki; Takata, Takushi; Fujimoto, Nozomi; Suzuki, Minoru; Masunaga, Shinichiro; Kinashi, Yuko; Kondo, Natsuko; Narabayashi, Masaru; Nakagawa, Yosuke; Watanabe, Tsubasa; Ono, Koji; Maruhashi, Akira

    2015-07-01

    At the Kyoto University Research Reactor Institute (KURRI), a clinical study of boron neutron capture therapy (BNCT) using a neutron irradiation facility installed at the research nuclear reactor has been regularly performed since February 1990. As of November 2014, 510 clinical irradiations were carried out using the reactor-based system. The world's first accelerator-based neutron irradiation system for BNCT clinical irradiation was completed at this institute in early 2009, and the clinical trial using this system was started in 2012. A shift of BCNT from special particle therapy to a general one is now in progress. To promote and support this shift, improvements to the irradiation system, as well as its preparation, and improvements in the physical engineering and the medical physics processes, such as dosimetry systems and quality assurance programs, must be considered. The recent advances in BNCT at KURRI are reported here with a focus on physical engineering and medical physics topics.

  20. Modified ADM1 for modelling an UASB reactor laboratory plant treating starch wastewater and synthetic substrate load tests.

    Science.gov (United States)

    Hinken, L; Huber, M; Weichgrebe, D; Rosenwinkel, K-H

    2014-11-01

    A laboratory plant consisting of two UASB reactors was used for the treatment of industrial wastewater from the wheat starch industry. Several load tests were carried out with starch wastewater and the synthetic substrates glucose, acetate, cellulose, butyrate and propionate to observe the impact of changing loads on gas yield and effluent quality. The measurement data sets were used for calibration and validation of the Anaerobic Digestion Model No. 1 (ADM1). For a precise simulation of the detected glucose degradation during load tests with starch wastewater and glucose, it was necessary to incorporate the complete lactic acid fermentation into the ADM1, which contains the formation and degradation of lactate and a non-competitive inhibition function. The modelling results of both reactors based on the modified ADM1 confirm an accurate calculation of the produced gas and the effluent concentrations. Especially, the modelled lactate effluent concentrations for the load cases are similar to the measurements and justified by literature. PMID:25043796

  1. Use of the TRIGA Reactor by the Radiochemistry Group of the Atominstitute of the Austrian Universities

    International Nuclear Information System (INIS)

    The Radiochemistry Group of the Atominstitute of the Austrian Universities uses the TRIGA Mark II Reactor mainly for neutron activation analysis. Transport of samples to and from the irradiation positions in the reactor is performed by fast pneumatic transfer systems (transfer time 20 msec and 300 msec) and slow conventional transport facilities. Gamma-spectrometric instrumentation equipped with loss free counting systems is used to handle the high count rates up to 500 000 counts/sec. During the last years neutron activation analysis was applied to investigate environmental samples (soil, dust, incineration ash), geological samples (rocks, sediments, fossils, volcanic gases), biological materials (lichens, mushrooms and other plant materials, human diet, biological reference materials), raw materials (phosphate, coal) and archaeological materials (ancient glass). Lichen analysis was used for environmental monitoring. The content of some of the trace elements can be correlated with industrial activities, like manganese content with steel industry, the occurrence of vanadium and nickel with oil firing plants and stainless steel industry, selenium is found in lichen near coal firing plants. The amount of chlorine and sodium indicates the application of salt for road treatment during winter time, aluminum, scandium and hafnium content depends on the amount of dust in the environment. A further environmental application of neutron activation analysis is the determination of trace elements in volcanic gases. The halogens, arsenic, antimony, selenium, tellurium and mercury were determined and their daily output was calculated. The distribution of trace elements in fossils of known age gives us a geochemical key to condition and development of the paleo-environment. For this purpose we determined rare earth elements in 250 million years old microfossils (conodonts). Neutron activation analysis served also for some non scientific but nevertheless useful purposes: Organic

  2. Mission-Aware Payloads for Unmanned Platforms Project

    Data.gov (United States)

    National Aeronautics and Space Administration — Sentix and Brigham Young University propose the research and development of embedded payload intelligence for inflight optimization of surveillance, reconnaissance,...

  3. Summary report of activities under visiting research program in Research Reactor Institute, Kyoto University, second half of 1989

    International Nuclear Information System (INIS)

    The Technical Report is published on occasion by summarizing in the form of prompt report the data required at the time of research and experiment, such as the results of the functional test on various experimental facilities, the test results for the articles made for trial, the state of radiation control and waste treatment, the reports of study meetings and so on, or the remarkable results and new methods obtained in research, the discussion on other papers and reports and others in the Research Reactor Institute, Kyoto University. In this report, the gists of 69 studies carried out by using the Research Reactor and 15 studies by using the Kyoto University Critical Assembly are collected. Adoption number, classification, title, the names of reporters and gist are given for each report. (K.I.)

  4. Energy Programs at the Johns Hopkins University Applied Physics Laboratory, Quarterly Report, April-June 1980

    Energy Technology Data Exchange (ETDEWEB)

    None

    1980-06-01

    The Johns Hopkins University Applied Physics Laboratory, under contracts with several agencies of the federal government and an agency of the State of Maryland, is engaged in developing energy resources, utilization concepts, and monitoring and storage methods. This Quarterly Report summarizes the work on the various tasks as of 30 June 1980. The Energy Quarterly Report is divided into three sections. The first, Geothermal Energy Development Planning and Technical Assistance, supported by the Department of Energy/Division of Geothermal Energy (DOE/DGE), contains reports on the progress of geothermal-related tasks on which effort was concentrated during the quarter. The second section, Operational Research, Hydroelectric Power Development, supported by the Department of Energy/Resource Applications (DOE/RA), contains reports on small-scale hydroelectric investigations in the southeastern states. The third section, Energy Conversion and Storage Techniques, contains three articles. The first is on data analysis of OTEC core unit condenser tests, and is supported by the Department of Energy/Division of Central Solar Technology (DOE/CST). The second is on the current status of the Community Annual Storage Energy System at the U.S. Naval Air Station, Norfolk, Va., and is supported by the Department of Energy and the Department of Defense, Naval Facilities Engineering Command/Atlantic Division. The third is on utilization of landfill methane and is supported by Argonne National Laboratory.

  5. Health centres' view of the services provided by a university hospital laboratory: use of satisfaction surveys.

    Science.gov (United States)

    Oja, Paula; Kouri, Timo; Pakarinen, Arto

    2010-03-01

    Customer orientation has gained increasing attention in healthcare. A customer satisfaction survey is one way to raise areas and topics for quality improvement. However, it seems that customer satisfaction surveys have not resulted in quality improvement in healthcare. This article reports how the authors' university hospital laboratory has used customer satisfaction surveys targeted at the health centres in their hospital district. Closed-ended statements of the questionnaire were planned to cover the essential aspects of laboratory services. In addition, an open-ended question asked what was considered to be the most important problem in services. The questionnaires were sent to the medical directors of the health centres. The open-ended question proved to be very useful because the responses specified the main problems in service. Based on the responses, selected dissatisfied customers were contacted to specify their responses and possible corrective actions were taken. It is concluded that a satisfaction survey can be used as a screening tool to identify topics of dissatisfaction. In addition, further clarifications with selected customers are needed to specify the causes for their dissatisfaction and to undertake proper corrective actions. PMID:20205616

  6. The study on the stability of the supporting ground on the construction site of High Flux Reactor building in Research Reactor Institute of Kyoto University

    International Nuclear Information System (INIS)

    This report provides the results of the study on the stability of the supporting gwound which has been carried out as a part of the seismic design of the High Flux Reactor building which is planned to be constructed by Kyoto University, Research Reactor Institute. In this work the finite element method is used. The stresses and displacements of the ground are calculated under the following conditions; (1) Stress-strain relationships for the individual elements are linear. (2) The problem is analyzed on two-dimensional plane strain distributions. (3) No-tension analysis is applied to the calculation for earthquake load. (4) The mechanical properties of the ground are obtained from the soil survey which has been performed at the construction site of High Flux Reactor building. The results are summarized as follows; (1) The settlement of the building is estimated to be about 2 -- 5 cm for long-time loading, including the result from elastic theory, while the relative settlement is about 0.3 cm at both ends of the building. (2) Safety factor is larger than 1.4 for long-time loading. (3) Maximum angle of the deformation of the building due to the earthquake load is estimated to be about 9.2 x 10-3 degree (1.6 x 10-4 rad). (4) Safety factor is larger than 1.2 -- 1.3 for earthquake load. Judging from these results described above, the ground at the construction site of the High Flux Reactor is appropriate for the supporting ground of the reactor building, and the mat foundation can be adopted for the foundation form. (author)

  7. Assessment of released heavy metals from electrical and electronic equipment (EEE) existing in shipwrecks through laboratory-scale simulation reactor

    International Nuclear Information System (INIS)

    Highlights: ► A laboratory-scale reactor was built to simulate the “Sea Diamond” shipwreck. ► EEE was thrown into the reactor for heavy metal release rate assessment. ► 15 seawater samples were taken and analyzed in a nine month experimental period. ► Zinc, mercury and copper were found in concentrations above the CMC criterion. ► Nickel and lead were found in concentrations higher than the CCC criterion. -- Abstract: In a passenger ship, the existence of EEE is obvious. In time, under shipwreck's conditions, all these materials will undergo an accelerated severe corrosion, due to salt water, releasing, consequently, heavy metals and other hazardous substances in the aquatic environment. In this study, a laboratory-scale reactor was manufactured in order to simulate the conditions under which the “Sea Diamond” shipwreck lies (14 bars of pressure and 16 °C of temperature) and remotely observe and assess any heavy metal release that would occur, from part of the EEE present in the ship, into the sea. Ten metals were examined and the results showed that zinc, mercury and copper were abundant in the water samples taken from the reactor and in significantly higher concentrations compared to the US EPA CMC (criterion maximum concentration) criterion. Moreover, nickel and lead were found in concentrations higher than the CCC (criterion constant concentration) criterion set by the US EPA for clean seawater. The rest of the elements were measured in concentrations within the permissible limits. It is therefore of environmental benefit to salvage the wreck and recycle all the WEEE found in it

  8. Pyrolysis of aseptic packages (tetrapak) in a laboratory screw type reactor and secondary thermal/catalytic tar decomposition

    International Nuclear Information System (INIS)

    Highlights: ► Pyrolysis of aseptic packages was carried out in a laboratory flow reactor. ► Distribution of tetrapak into the product yields was obtained. ► Composition of the pyrolysis products was estimated. ► Secondary thermal and catalytic decomposition of tars was studied. ► Two types of catalysts (dolomite and red clay marked AFRC) were used. - Abstract: Pyrolysis of aseptic packages (tetrapak cartons) in a laboratory apparatus using a flow screw type reactor and a secondary catalytic reactor for tar cracking was studied. The pyrolysis experiments were realized at temperatures ranging from 650 °C to 850 °C aimed at maximizing of the amount of the gas product and reducing its tar content. Distribution of tetrapak into the product yields at different conditions was obtained. The presence of H2, CO, CH4, CO2 and light hydrocarbons, HCx, in the gas product was observed. The Aluminum foil was easily separated from the solid product. The rest part of char was characterized by proximate and elemental analysis and calorimetric measurements. The total organic carbon in the tar product was estimated by elemental analysis of tars. Two types of catalysts (dolomite and red clay marked AFRC) were used for catalytic thermal tar decomposition. Three series of experiments (without catalyst in a secondary cracking reactor, with dolomite and with AFRC) at temperatures of 650, 700, 750, 800 and 850 °C were carried out. Both types of catalysts have significantly affected the content of tars and other components in pyrolytic gases. The effect of catalyst on the tetrapack distribution into the product yield on the composition of gas and on the total organic carbon in the tar product is presented in this work

  9. Pyrolysis of aseptic packages (tetrapak) in a laboratory screw type reactor and secondary thermal/catalytic tar decomposition

    Energy Technology Data Exchange (ETDEWEB)

    Haydary, J., E-mail: juma.haydary@stuba.sk [Institute of Chemical and Environmental Engineering, Faculty of Chemical and Food Technology, Slovak University of Technology, Radlinského 9, 812 37 Bratislava (Slovakia); Susa, D.; Dudáš, J. [Institute of Chemical and Environmental Engineering, Faculty of Chemical and Food Technology, Slovak University of Technology, Radlinského 9, 812 37 Bratislava (Slovakia)

    2013-05-15

    Highlights: ► Pyrolysis of aseptic packages was carried out in a laboratory flow reactor. ► Distribution of tetrapak into the product yields was obtained. ► Composition of the pyrolysis products was estimated. ► Secondary thermal and catalytic decomposition of tars was studied. ► Two types of catalysts (dolomite and red clay marked AFRC) were used. - Abstract: Pyrolysis of aseptic packages (tetrapak cartons) in a laboratory apparatus using a flow screw type reactor and a secondary catalytic reactor for tar cracking was studied. The pyrolysis experiments were realized at temperatures ranging from 650 °C to 850 °C aimed at maximizing of the amount of the gas product and reducing its tar content. Distribution of tetrapak into the product yields at different conditions was obtained. The presence of H{sub 2}, CO, CH{sub 4}, CO{sub 2} and light hydrocarbons, HCx, in the gas product was observed. The Aluminum foil was easily separated from the solid product. The rest part of char was characterized by proximate and elemental analysis and calorimetric measurements. The total organic carbon in the tar product was estimated by elemental analysis of tars. Two types of catalysts (dolomite and red clay marked AFRC) were used for catalytic thermal tar decomposition. Three series of experiments (without catalyst in a secondary cracking reactor, with dolomite and with AFRC) at temperatures of 650, 700, 750, 800 and 850 °C were carried out. Both types of catalysts have significantly affected the content of tars and other components in pyrolytic gases. The effect of catalyst on the tetrapack distribution into the product yield on the composition of gas and on the total organic carbon in the tar product is presented in this work.

  10. Characterization of control rod worths and fuel rod power peaking factors in the university of Utah TRIGA Mark I reactor

    Directory of Open Access Journals (Sweden)

    Alroumi Fawaz

    2016-01-01

    Full Text Available Control rod reactivity (worths for the three control rods and fuel rod power peaking factors in the University of Utah research reactor (100 kW TRIGA Mark I are characterized using the AGENT code system and the results described in this paper. These values are compared to the MCNP6 and existing experimental measurements. In addition, the eigenvalue, neutron spatial flux distributions and reaction rates are analyzed and discussed. The AGENT code system is widely benchmarked for various reactor types and complexities in their geometric arrangements of the assemblies and reactor core material distributions. Thus, it is used as a base methodology to evaluate neutronics variables of the research reactor at the University of Utah. With its much shorter computation time than MCNP6, AGENT provides agreement with the MCNP6 within a 0.5 % difference for the eigenvalue and a maximum difference of 10% in the power peaking factor values. Differential and integral control rod worths obtained by AGENT show well agreement with MCNP6 and the theoretical model. However, regulating the control rod worth is somewhat overestimated by both MCNP6 and AGENT models when compared to the experimental/theoretical values. In comparison to MCNP6, the total control rod worths and shutdown margin obtained with AGENT show better agreement to the experimental values.

  11. Safety evaluation report related to the renewal of the operating license for the University of New Mexico Research Reactor (Docket No. 50-252)

    International Nuclear Information System (INIS)

    This Safety Evaluation Report for the application filed by the University of New Mexico (UNM) for renewal of Operating License No. R-102 to continue to operate its research reactor has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is located on the campus of the University of New Mexico in Albuquerque, New Mexico. The staff concludes that the reactor can continue to be operated by the University of New Mexico without endangering the health and safety of the public. 7 refs., 7 figs., 2 tabs

  12. Safety evaluation report related to the renewal of the operating license for the University of Virginia open-pool research reactor. Docket No. 50-062

    International Nuclear Information System (INIS)

    This Safety Evaluation Report for the application filed by the University of Virginia for a renewal of Operating Licence R-66 to continue to operate a research reactor has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is owned by the University of Virginia and is located on the campus in Charlottesville, Virginia. Based on its technical review, the staff concludes that the reactor facility can continue to be operated by the University without endangering the health and safety of the public or endangering the environment

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

    International Nuclear Information System (INIS)

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

  14. Safety Evaluation Report related to renewal of the operating license for the CAVALIER Training Reactor at the University of Virginia (Docket No. 50-396)

    International Nuclear Information System (INIS)

    This Safety Evaluation Report for the application filed by the University of Virginia for a renewal of Operating License R-123 to continue to operate the CAVALIER (Cooperatively Assembled Virginia Low Intensity Educational Reactor) has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is owned and operated by the University of Virginia and is located on the campus in Charlottesville, Virginia. Based on its technical review, the staff concludes that the reactor facility can continue to be operated by the university without endangering the health and safety of the public or the environment

  15. Safety Evaluation Report related to the renewal of the operating license for the TRIGA training and research reactor at the University of Arizona (Docket No. 50-113)

    International Nuclear Information System (INIS)

    This Safety Evaluation Report for the application filed by the University of Arizona for the renewal of Operating License R-52 to continue operating its research reactor at an increased operating power level has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is located on the University of Arizona campus in Tucson, Arizona. The staff concludes that the reactor can continue to be operated by the University of Arizona without endangering the health and safety of the public. 20 refs., 8 figs., 5 tabs

  16. Safety evaluation report related to the renewal of the operating license for the University of Oklahoma Research Reactor (Docket No. 50-112)

    International Nuclear Information System (INIS)

    This Safety Evaluation Report for the application filed by the University of Oklahoma for a renewal of Operating License R-53 to continue to operate a research reactor has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is owned and operated by the University of Oklahoma and is located on the campus in Norman, Cleveland County, Oklahoma. The staff concludes that the Aerojet General Nucleonics (AGN) reactor facility can continue to be operated by University of Oklahoma without endangering the health and safety of the public

  17. Safety Evaluation Report related to the renewal of the operating license for the research reactor at Purdue University: Docket No. 50-182

    International Nuclear Information System (INIS)

    This Safety Evaluation Report for the application filed by Purdue University for a renewal of Operating License R-87 to continue to operate a research reactor has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is owned by Purdue University and is located on the campus in West Lafayette, Indiana. On the basis of its technical review, the staff concludes that the reactor facility can continue to be operated by the university without endangering the health and safety of the public or the enviroment

  18. Safety Evaluation Report related to the renewal of the operating license for the research reactor at Michigan State University (Docket No. 50-294)

    International Nuclear Information System (INIS)

    This Safety Evaluation Report for the application filed by the Michigan State University (MSU) for a renewal of operating license number R-114 to continue to operate the TRIGA Mark I research reactor has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is owned and operated by the Michigan State University and is located on the campus of Michigan State University in East Lansing, Ingham County, Michigan. The staff concludes that the TRIGA reactor facility can continue to be operated by MSU without endangering the health and safety of the public

  19. Safety Evaluation Report related to the renewal of the operating license for the training and research reactor at the University of Lowell (Docket No. 50-223)

    International Nuclear Information System (INIS)

    This Safety Evaluation Report for the application filed by the University of Lowell (UL) for renewal of operating license number R-125 to continue to operate its research reactor has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is located on the North Campus of the University of Lowell in Lowell, Massachusetts. The staff concludes that the reactor can continue to be operated by the University of Lowell without endangering the health and safety of the public

  20. Characteristics of neutron irradiation facility and dose estimation method for neutron capture therapy at Kyoto University research reactor institute

    International Nuclear Information System (INIS)

    The neutron irradiation characteristics of the Heavy Water Neutron Irradiation Facility (HWNIF) at the Kyoto University Research Reactor Institute (KIJRRI) for boron neutron capture therapy (BNCT), is described. The present method of dose measurement and its evaluation at the KURRI, is explained. Especially, the special feature and noticeable matters were expounded for the BNCT with craniotomy, which has been applied at present only in Japan. (author)

  1. Characterization of control rod worths and fuel rod power peaking factors in the university of Utah TRIGA Mark I reactor

    OpenAIRE

    Alroumi Fawaz; Kim Donghoon; Schow Ryan; Jevremovic Tatjana

    2016-01-01

    Control rod reactivity (worths) for the three control rods and fuel rod power peaking factors in the University of Utah research reactor (100 kW TRIGA Mark I) are characterized using the AGENT code system and the results described in this paper. These values are compared to the MCNP6 and existing experimental measurements. In addition, the eigenvalue, neutron spatial flux distributions and reaction rates are analyzed and discussed. The AGENT code system is ...

  2. 75 FR 27372 - University of New Mexico; University of New Mexico AGN-201M Reactor; Environmental Assessment and...

    Science.gov (United States)

    2010-05-14

    ... as a result of license renewal. Radiation monitoring instrumentation available to the reactor... that may be released off site. There should be no increase in occupational or public radiation exposure... released from the facility nor was there any solid waste released. In addition, no environmental...

  3. Ohio State University Nuclear Reactor Laboratory HEU fuel shipment summary. Final

    International Nuclear Information System (INIS)

    In November 1988, OSURR converted from HEU fuel to LEU fuel. As a result they needed to get rid of their HEU fuel by shipping it to Savannah River. The players in the fuel shipping game are: OSURR as the keeper of the fuel; DOE as the owner of fuel and shipper of record; Tri-State Motor Transit Co. for transporting the cask; Muth Brothers as the rigger responsible for getting the cask on and off the truck and in and out of the building; Hoffman LaRoche/Cintichem as the owner of the cask; Savannah River as the receiver of the fuel; and the NRC for approval of the Security Plan, QA Plan, etc. This report gives a chronological history of the events from February 1989 to June 1, 1995, the actual day of shipment. The cask was received at Savannah River on June 2, 1995

  4. Undergraduates Prefer Federated Searching to Searching Databases Individually. A Review of: Belliston, C. Jeffrey, Jared L. Howland, & Brian C. Roberts. “Undergraduate Use of Federated Searching: A Survey of Preferences and Perceptions of Value-Added Functionality.” College & Research Libraries 68.6 (Nov. 2007): 472-86.

    OpenAIRE

    Genevieve Gore

    2008-01-01

    Objective – To determine whether use offederated searching by undergraduates saves time, meets their information needs, is preferred over searching databases individually, and provides results of higher quality. Design – Crossover study.Setting – Three American universities, all members of the Consortium of Church Libraries & Archives (CCLA): BYU (Brigham Young University, a large research university); BYUH (Brigham Young University – Hawaii, a small baccalaureate college); and BYUI (Brigham...

  5. Monitoring and Control Research Using a University Reactor and SBWR Test-Loop

    International Nuclear Information System (INIS)

    The existing hybrid simulation capability of the Penn State Breazeale nuclear reactor was expanded to conduct research for monitoring, operations and control. Hybrid simulation in this context refers to the use of the physical time response of the research reactor as an input signal to a real-time simulation of power-reactor thermal-hydraulics which in-turn provides a feedback signal to the reactor through positioning of an experimental changeable reactivity device. An ECRD is an aluminum tube containing an absorber material that is positioned in the central themble of the reactor kinetics were used to expand the hybrid reactor simulation (HRS) capability to include out-of-phase stability characteristics observed in operating BWRs

  6. Argon-41 production and evolution at the Oregon State University TRIGA Reactor (OSTR)

    International Nuclear Information System (INIS)

    In this study, argon-41 concentrations were measured at various locations within the reactor facility to assess the accuracy of models used to predict argon-41 evolution from the reactor tank, and to determine the relationship between argon gas evolution from the tank and subsequent argon-41 concentrations throughout the reactor room. In particular, argon-41 was measured directly above the reactor tank with the reactor tank lids closed, at other accessible locations on the reactor top with the tank lids both closed and open, and at several locations on the first floor of the reactor room. These measured concentrations were then compared to values calculated using a modified argon-41 production and evolution model for TRIGA reactor tanks and ventilation values applicable to the OSTR facility. The modified model was based in part on earlier TRIGA models for argon-41 production and release, but added features which improved the agreement between predicted and measured values. The approximate dose equivalent rate due to the presence of argon-41 in reactor room air was calculated for several different locations inside the OSTR facility. These dose rates were determined using the argon-41 concentration measured at each specific location, and were subsequently converted to a predicted quarterly dose equivalent for each location based on the reactor's operating history. The predicted quarterly dose equivalent values were then compared to quarterly doses measured by film badges deployed as dose-integrating area radiation monitors at the locations of interest. The results indicate that the modified production and evolution model is able to predict argon-41 concentrations to within a factor of ten when compared to the measured data. Quarterly dose equivalents calculated from the measured argon-41 concentrations and the reactor's operating history seemed consistent with results obtained from the integrating area radiation monitors. Given the argon-41 concentrations measured

  7. Radon Laboratory: A Proposal for Scientific Culture Dissemination Among Young Students in Italy

    International Nuclear Information System (INIS)

    In Italy the 'nuclear issue' was for a long time a taboo. A way to approach this theme to make the public more trusting of nuclear issues is to discuss radioactivity and ionizing radiation starting from young students. An experimental activity that involves secondary school students has been developed. The approach is to have students engaged in activities that will allow them to understand how natural radioactivity is a part of our everyday environment. This would include how radiation enters our lives in different ways, to demonstrate that natural radioactive sources found in soil, water, and air contribute to our exposure to natural ionizing radiation and how this exposure effects human health. Another objective is to develop a new technique for teaching physics which will enhance scientific interest of students in applications of nuclear physics in both environmental and physical sciences.

  8. Policies and practices pertaining to the selection, qualification requirements, and training programs for nuclear-reactor operating personnel at the Oak Ridge National Laboratory

    International Nuclear Information System (INIS)

    This document describes the policies and practices of the Oak Ridge National Laboratory (ORNL) regarding the selection of and training requirements for reactor operating personnel at the Laboratory's nuclear-reactor facilities. The training programs, both for initial certification and for requalification, are described and provide the guidelines for ensuring that ORNL's research reactors are operated in a safe and reliable manner by qualified personnel. This document gives an overview of the reactor facilities and addresses the various qualifications, training, testing, and requalification requirements stipulated in DOE Order 5480.1A, Chapter VI (Safety of DOE-Owned Reactors); it is intended to be in compliance with this DOE Order, as applicable to ORNL facilities. Included also are examples of the documentation maintained amenable for audit

  9. Sandia National Laboratories results for the 2010 criticality accident dosimetry exercise, at the CALIBAN reactor, CEA Valduc France.

    Energy Technology Data Exchange (ETDEWEB)

    Ward, Dann C.

    2011-09-01

    This document describes the personal nuclear accident dosimeter (PNAD) used by Sandia National Laboratories (SNL) and presents PNAD dosimetry results obtained during the Nuclear Accident Dosimeter Intercomparison Study held 20-23 September, 2010, at CEA Valduc, France. SNL PNADs were exposed in two separate irradiations from the CALIBAN reactor. Biases for reported neutron doses ranged from -15% to +0.4% with an average bias of -7.7%. PNADs were also exposed on the back side of phantoms to assess orientation effects.

  10. Lessons Learned from Sandia National Laboratories' Operational Readiness Review of the Annular Core Research Reactor (ACRR)

    International Nuclear Information System (INIS)

    The Sandia ACRR (a Hazard Category 2 Nuclear Reactor Facility) was defueled in June 1997 to modify the reactor core and control system to produce medical radioisotopes for the Department of Energy (DOE) Isotope Production Program. The DOE determined that an Operational Readiness Review (ORR) was required to confirm readiness to begin operations within the revised safety basis. This paper addresses the ORR Process, lessons learned from the Sandia and DOE ORRS of the ACRR, and the use of the ORR to confirm authorization basis implementation

  11. Proceedings of the school for young high energy physicists, September 1990 [held at the Rutherford Appleton Laboratory, Chilton (GB)

    International Nuclear Information System (INIS)

    The 1990 School of Young High Energy Physicists took place in September and was attended by virtually all first year graduate students in experimental HEP at British Universities. The School consisted of two weeks of intensive lectures, written versions of which are published in this book. The four lecture courses; symmetries and gauge theories in Quantum Field Theory, Relativisitc quantum mechanics, QED and QeD; The Standard Model and Beyond and Selected Topics in Phenomenology of the Standard Model are all indexed separately. These were supplemented by problems and tutorials to give a thorough grounding in the Standard Model of elementary particle physics, putting understanding of the theory on a firm foundation for experimental investigations. (author)

  12. Thermal-hydraulic modeling of the Pennsylvania State University Breazeale Nuclear Reactor (PSBR)

    Science.gov (United States)

    Chang, Jong E.

    2005-11-01

    Earlier experiments determined that the Pennsylvania State University Breazeale Nuclear Reactor (PSBR) core is cooled, not by an axial flow, but rather by a strong cross flow due to the thermal expansion of the coolant. To further complicate the flow field, a nitrogen-16 (N-16) pump was installed above the PSBR core to mix the exiting core buoyant thermal plume in order to delay the rapid release of radioactive N-16 to the PSBR pool surface. Thus, the interaction between the N-16 jet flow and the buoyancy driven flow complicates the analysis of the flow distribution in the PSBR pool. The main objectives of this study is to model the thermal-hydraulic behavior of the PSBR core and pool. During this study four major things were performed including the Computational Fluid Dynamics (CFD) model for the PSBR pool, the stand-alone fuel rod model for a PSBR fuel rod, the velocity measurements in and around the PSBR core, and the temperature measurements in the PSBR pool. Once the flow field was predicted by the CFD model, the measurement devices were manufactured and calibrated based on the CFD results. The major contribution of this study is to understand and to explain the flow behavior in the PSBR subchannels and pool using the FLOW3D model. The stand-alone dynamic fuel rod model was developed to determine the temperature distribution inside a PSBR fuel rod. The stand-alone fuel rod model was coupled to the FLOW3D model and used to predict the temperature behavior during steady-state and pulsing. The heat transfer models in the stand-alone fuel rod code are used in order to overcome the disadvantage of the CFD code, which does not calculate the mechanical stress, the gap conductance, and the two phase heat transfer. (Abstract shortened by UMI.)

  13. The Assessment of Young Children through the Lens of Universal Design for Learning (UDL)

    Science.gov (United States)

    Dalton, Elizabeth M.; Brand, Susan Trostle

    2012-01-01

    Early Childhood Education (EDE) describes the education of young children from birth through age 8. EDE reports have concluded that traditional approaches to curriculum, such as those emphasizing drill and practice of isolated, academic skills, are not in line with current knowledge of human learning and neuropsychology. These approaches fail to…

  14. Shipment of 255 DIDO fuel elements to the Savannah River Site to empty the storage and reactor pools at Risoe National Laboratory

    International Nuclear Information System (INIS)

    The DR-3 reactor, owned and operated by the Danish National Laboratory, was built in the late 1950's and initiated operation in January 1960. At that time the DR-1 and DR-2 reactors were already in operation. The main purpose if of Danish research reactor DR-3 was material and fuel testing. Until 1989 the reactor utilized HEU fuel elements. Conversion to the LEU fuel cycle was accomplished in 1990. DOE restarted the return program of for Foreign Research Reactor fuel elements to the United States in 1994. From that time, through 1998, three IUO4 casks (one cask in 1994) operated by Transnucleaire (now named Cogema Logistics, ACL) were used to transport Risoe's fuel to the Savannah River Site (SRS) near Aiken, SC in the USA. In 1999, Risoe elected to issue a request for proposal to transport DR-3 the DIDO fuel elements to SRS with a new licensed cask designed to replace the IUO4 cask. ACL was awarded the contract to transport the irradiated fuel from DR-3 to SRS for the remainder of the FRR Fuel Return program (2009). However, on September 28, 2000, the Board of Governors of Risoe National Laboratory decided to shut down the Danish research reactor of DR3. There had been of R2 technical problems (corrosion on the aluminum reactor tank) and, due to anticipated increasing operational expenses, the Board elected to close the reactor facility. Shortly thereafter, the Danish Government asked the National Laboratory to empty the reactor and its reactor and storage pools containing a total of 255 Dido irradiated fuel elements and ship them to Savannah Rive Site. At that time, ACL was in the process of licensing the new TN-MTR package in the USA. The early shut down of the DR-3 reactor and consequently the resultant new shipping schedule was not compatible with ACL's equipment and licensing schedule for the cask. (author)

  15. The Radiopharmaceuticals Production and Research Centre established by the Heavy Ion Laboratory of the University of Warsaw

    OpenAIRE

    Choiński J.; Jastrzębskia J.; Kilian K.; Mazur I.; Napiorkowski P.J.; Pękal A.; Szczepaniak D.

    2014-01-01

    The Radiopharmaceuticals Production and Research Centre was recently installed on the premises of the Heavy Ion Laboratory, University of Warsaw. Equipped with a medical PETtrace p/d cyclotron , radiochemistry synthesis and dispensing units and a modern quality control laboratory the Centre is intended to produce regularly for commercial purposes the classic PET radiopharmaceuticals ( such -as e.g. FDG- ). Situated on the largest Warsaw scientific campus OCHOTA, an important part of the Centr...

  16. N2O Catalytic Decomposition – from Laboratory Experiment to Industry Reactor

    Czech Academy of Sciences Publication Activity Database

    Obalová, L.; Jirátová, Květa; Karásková, K.; Chromčáková, Ž.

    2012-01-01

    Roč. 191, č. 1 (2012), s. 116-120. ISSN 0920-5861 R&D Projects: GA TA ČR TA01020336 Institutional support: RVO:67985858 Keywords : N2O * catalytic decomposition * fixed bed reactor Subject RIV: CI - Industrial Chemistry, Chemical Engineering Impact factor: 2.980, year: 2012

  17. HWMA/RCRA CLOSURE PLAN FOR THE MATERIALS TEST REACTOR WING (TRA-604) LABORATORY COMPONENTS VOLUNTARY CONSENT ORDER ACTION PLAN VCO-5.8 D REVISION2

    Energy Technology Data Exchange (ETDEWEB)

    KIRK WINTERHOLLER

    2008-02-25

    This Hazardous Waste Management Act/Resource Conservation and Recovery Act closure plan was developed for the laboratory components of the Test Reactor Area Catch Tank System (TRA-630) that are located in the Materials Test Reactor Wing (TRA-604) at the Reactor Technology Complex, Idaho National Laboratory Site, to meet a further milestone established under Voluntary Consent Order Action Plan VCO-5.8.d. The TRA-604 laboratory components addressed in this closure plan were deferred from the TRA-630 Catch Tank System closure plan due to ongoing laboratory operations in the areas requiring closure actions. The TRA-604 laboratory components include the TRA-604 laboratory warm wastewater drain piping, undersink drains, subheaders, and the east TRA-604 laboratory drain header. Potentially contaminated surfaces located beneath the TRA-604 laboratory warm wastewater drain piping and beneath the island sinks located in Laboratories 126 and 128 (located in TRA-661) are also addressed in this closure plan. The TRA-604 laboratory components will be closed in accordance with the interim status requirements of the Hazardous Waste Management Act/Resource Conservation and Recovery Act as implemented by the Idaho Administrative Procedures Act 58.01.05.009 and 40 Code of Federal Regulations 265, Subparts G and J. This closure plan presents the closure performance standards and the methods for achieving those standards.

  18. Experimental and MCNP5 based evaluation of neutron and gamma flux in the irradiation ports of the University of Utah research reactor

    OpenAIRE

    Noble Brooklyn; Choe Dong-Ok; Jevremovic Tatjana

    2012-01-01

    Neutron and gamma flux environment of various irradiation ports in the University of Utah training, research, isotope production, general atomics reactor were experimentally assessed and fully modeled using the MCNP5 code. The experimental measurements were based on the cadmium ratio in the irradiation ports of the reactor, flux profiling using nickel wire, and gamma dose measurements using thermo luminescence dosimeter. Full 3-D MCNP5 reactor model was developed to obtain the neutron f...

  19. Treatment of arsenic contaminated water in a laboratory scale up-flow bio-column reactor

    International Nuclear Information System (INIS)

    The present paper describes the observations on the treatment of arsenic contaminated synthetic industrial effluent in a bio-column reactor. Ralstonia eutropha MTCC 2487 has been immobilized on the granular activated carbon (GAC) bed in the column reactor. The synthetic water sample containing As(T) (As(III):As(V) = 1:1), Fe, Mn, Cu and Zn at the initial concentrations of 25, 10, 2, 5, 10 ppm, respectively, was used. Concentrations of all the elements have been found to be reduced below their permissible limits in the treated water. The significant effect of empty bed contact time (EBCT) and bed height on the arsenic removal was observed in the initial stage. However, after some time of operation (approximately 3-4 days) no such effect was observed. Removal of As(III) and As(V) was almost similar after ∼2 days of operation. However, at the initial stage As(V) removal was slightly more than that of As(III). In absence of washing, after ∼4-5 days of operation, the bio-column reactor was observed to act as a GAC column reactor based on physico-chemical adsorption. Like arsenic, the percent removals of Fe, Mn, Cu and Zn also attained minimum after ∼1 day and increased significantly to the optimum value within 3-4 days of operation. Dissolved oxygen (DO) has been found to decrease along with the increasing bed height from the bottom. The pH of the solution in the reactor has increased slightly and oxidation-reduction potential (ORP) has decreased with the time of operation

  20. TRIGA research reactors

    International Nuclear Information System (INIS)

    TRIGA (Training, Research, Isotope production, General-Atomic) has become the most used research reactor in the world with 65 units operating in 24 countries. The original patent for TRIGA reactors was registered in 1958. The success of this reactor is due to its inherent level of safety that results from a prompt negative temperature coefficient. Most of the neutron moderation occurs in the nuclear fuel (UZrH) because of the presence of hydrogen atoms, so in case of an increase of fuel temperature, the neutron spectrum becomes harder and neutrons are less likely to fission uranium nuclei and as a consequence the power released decreases. This inherent level of safety has made this reactor fit for training tool in university laboratories. Some recent versions of TRIGA reactors have been designed for medicine and industrial isotope production, for neutron therapy of cancers and for providing a neutron source. (A.C.)

  1. Pyrolysis of aseptic packages (tetrapak) in a laboratory screw type reactor and secondary thermal/catalytic tar decomposition.

    Science.gov (United States)

    Haydary, J; Susa, D; Dudáš, J

    2013-05-01

    Pyrolysis of aseptic packages (tetrapak cartons) in a laboratory apparatus using a flow screw type reactor and a secondary catalytic reactor for tar cracking was studied. The pyrolysis experiments were realized at temperatures ranging from 650 °C to 850 °C aimed at maximizing of the amount of the gas product and reducing its tar content. Distribution of tetrapak into the product yields at different conditions was obtained. The presence of H2, CO, CH4, CO2 and light hydrocarbons, HCx, in the gas product was observed. The Aluminum foil was easily separated from the solid product. The rest part of char was characterized by proximate and elemental analysis and calorimetric measurements. The total organic carbon in the tar product was estimated by elemental analysis of tars. Two types of catalysts (dolomite and red clay marked AFRC) were used for catalytic thermal tar decomposition. Three series of experiments (without catalyst in a secondary cracking reactor, with dolomite and with AFRC) at temperatures of 650, 700, 750, 800 and 850 °C were carried out. Both types of catalysts have significantly affected the content of tars and other components in pyrolytic gases. The effect of catalyst on the tetrapack distribution into the product yield on the composition of gas and on the total organic carbon in the tar product is presented in this work. PMID:23428565

  2. The use of ilmenite as oxygen carrier with kerosene in a 300 W CLC laboratory reactor with continuous circulation

    International Nuclear Information System (INIS)

    Graphical abstract: Experiments with sulfur-free and sulfurous kerosene were performed using ilmenite oxygen carrier. Fuel conversion improved significantly and lasting when sulfurous kerosene was used. - Highlights: • Experiments were performed in a 300 W reactor with continuous circulation. • Sulfurous and sulfur-free kerosene were used directly as fuel. • Ilmenite oxygen carrier (Norwegian rock ilmenite) was tested. • Combustion experiments were performed for 50 h (sulfur-free) and 30 h (sulphurous), respectively. • A significant and lasting improvement in the oxygen carrier’s reactivity was achieved by using sulfurous kerosene. - Abstract: An ilmenite oxygen carrier was tested in a laboratory scale chemical-looping reactor with a nominal thermal capacity of 300 Wth. Ilmenite is a mineral iron–titanium oxide, which has been used extensively as an oxygen carrier in chemical-looping combustion. Two different kinds of fuels were used, a sulfur-free kerosene and one kerosene that contained 0.57 mass% sulfur. Both fuels were continuously evaporated and directly fed into the chemical-looping reactor. Experiments were conducted for 50 h with the sulfur-free kerosene and for 30 h with the sulfurous kerosene. CO2 yields above 99% were achieved with both types of fuel. A significant and lasting improvement in the oxygen carrier’s reactivity was observed, presumably an effect of using sulfurous kerosene. No evidence of sulfur was found on the particles’ surface

  3. Deposition of hematite particles on alumina seal faceplates of nuclear reactor coolant pumps: Laboratory experiments and industrial feedback

    Directory of Open Access Journals (Sweden)

    Lefèvre Grégory

    2012-01-01

    Full Text Available In the primary circuit of pressurized water reactors (PWR, the dynamic sealing system in reactor coolant pumps is ensured by mechanical seals whose ceramic parts are in contact with the cooling solution. During the stretch-out phase in reactor operation, characterized by low boric acid concentration, the leak-off flow has been observed to abnormally evolve in industrial plants. The deposition of hematite particles, originating from corrosion, on alumina seals of coolant pumps is suspected to be the cause. As better understanding of the adhesion mechanism is the key factor in the prevention of fouling and particle removal, an experimental study was carried out using a laboratory set-up. With model materials, hematite and sintered alumina, the adhesion rate and surface potentials of the interacting solids were measured under different chemical conditions (solution pH and composition in analogy with the PWR ones. The obtained results were in good agreement with the DLVO (Derjaguin-Landau-Verwey- Overbeek theory and used as such to interpret this industrial phenomenon.

  4. Proceedings of the specialist research meeting on 'introduction of total micro-element analysis system and its application in Kyoto University Reactor'

    International Nuclear Information System (INIS)

    The lecture contents are here summarized that have been presented in the specialist research meeting of research reactor institute of Kyoto University held under the theme 'Introduction of total micro-element analysis system and its application in Kyoto University Reactor'. Here 12 lectures were presented and the current states of radiochemical neutron activation analysis in Thailand and Korea were also mentioned. (M.H.)

  5. Mainstream partial nitritation and anammox in a 200,000 m(3)/day activated sludge process in Singapore: scale-down by using laboratory fed-batch reactor.

    Science.gov (United States)

    Yeshi, Cao; Hong, Kwok Bee; van Loosdrecht, Mark C M; Daigger, Glen T; Yi, Png Hui; Wah, Yuen Long; Chye, Chua Seng; Ghani, Yahya Abd

    2016-01-01

    A laboratory fed-batch reactor has been used to study under controlled conditions the performance of partial nitritation/anammox for the 200,000 m(3)/day step-feed activated sludge process at the Changi Water Reclamation Plant, Singapore. The similarity of the concentrations of NH4, NO2, NO3, PO4, suspended chemical oxygen demand (sCOD), pH, and alkalinity (ALK) between the on-site process and laboratory reactor illustrates that the laboratory fed-batch reactor can be used to simulate the site performance. The performance of the reactor fed by primary effluent illustrated the existence of anammox and heterotrophic denitrification and apparent excessive biological phosphorus removal as observed from the site. The performance of the reactor fed by final effluent proved the presence of anammox process on site. Both the laboratory reactor and on-site process showed that higher influent 5-day biochemical oxygen demand/total nitrogen (BOD5/TN) (COD/TN) ratio increases the nitrogen removal efficiency of the process. PMID:27386982

  6. Training reactor VR 1 at the Czech Technical University in Prague is operational

    International Nuclear Information System (INIS)

    Detailed information on the construction work of the VR 1 VRABEC training reactor is presented (building and assembling work, inactive tests) and its technical description is given, with emphasis on the conception of the device and the crucial parts of its technology. The basic parameters of the reactor are as follows: rated power output 1 kW(thermal); fuel of the IRT-2M type (36% 235U enrichment, imported from the former USSR); reactor vessels (pools) made of stainless steel, 2300 mm in diameter, 4720 mm high, wall thickness 15 mm, bottom thickness 20 mm; reactor shielding: 3000 mm water layer above the reactor core, lateral shielding: about 850 mm of water plus a 950 mm layer of special heavy concrete; working temperature inside the reactor, which is affected by the ambient temperature, is about 20 degC; reactor core cooling proceeds by natural convection; pressure is atmospheric; control system consists of 5 to 7 UR-70 type control rods distributed as follows: 3 scram rods, 2 control rods, 0 to 2 experimental rods; neutron source: Am-Be, 185 GBq. (Z.S.). 10 figs

  7. Pyrolysis of biomass and refuse-derived fuel performance in laboratory scale batch reactor

    OpenAIRE

    Kluska Jacek; Klein Marek; Kazimierski Paweł; Kardaś Dariusz

    2014-01-01

    The results of pyrolysis of pine chips and refuse derived fuel fractions are presented. The experiments were carried out in a pilot pyrolysis reactor. The feedstock was analyzed by an elemental analyzer and the X-ray fluorescence spectrometer to determine the elemental composition. To find out optimum conditions for pyrolysis and mass loss as a function of temperature the thermogravimetric analysis was applied. Gases from the thermogravimetric analysis were directed to the infrared spectromet...

  8. Report of researches by common utilization of facilities in Kyoto University Research Reactor Institute, first half of fiscal year 1981

    International Nuclear Information System (INIS)

    The technical report of the Kyoto University Research Reactor Institute is published any time to immediately report on the results of the functional tests of various experimental facilities, the test results for the products made for trial, radiation control, the situation of waste treatment, the data required for research and experiment such as the reports of study meetings, the conspicuous results obtained amid researches, new processes, and the discussion on other papers and reports. In this report, the title, the names of reporters and the summary of 57 researches carried out by the common utilization of the facilities in the Kyoto University Research Reactor Institute are collected. The themes of the researches are such as neutron radiography using a research reactor, measurement of Zr/Hf ratio in zirconium, interstitial germanium atoms in thermal neutron irradiation study, measurement of induced radioactivity due to neutrons in Nagasaki and Hiroshima atomic bombings, properties of semiconductor electrons in radiation study, induction of mutation in crops by neutron irradiation and utilization for breeding, thermal fluorescence mechanism of alkali halide and MgO single crystals, atomic configuration in PZT rhombohedron phase, modulated structure of Cu-Co alloys, excitation of nuclei by positron annihilation and others. (Kako, I.)

  9. Report of researches by common utilization of facilities in Kyoto University Research Reactor Institute, latter half of fiscal year 1981

    International Nuclear Information System (INIS)

    The technical report of the Kyoto University Research Reactor Institute is published any time to immediately report on the results of the functional tests of various experimental facilities, the test results for the products made for trial, radiation control, the situation of waste treatment, the data required for research and experiment such as the reports of study meetings, the conspicuous results obtained amid researches, new processes, and the discussion on other papers and reports. In this report, the title, the names of reporters and the summary of 61 researches carried out by the common utilization of the facilities in the Kyoto University Research Reactor Institute are collected. The themes of the researches are such as radioactivation analysis of trace elements in rocks and minerals, anodic oxidation films of GaAs and structure, measurement of yield of uranium isotopes produced by reactor neutron irradiation of thorium, geochemical study of trace elements in hydrosphere by radio-activation analysis, various diseases and variation of elements in rat furs, Moessbauer spectroscopic study of gold compounds with singular coupling by Au-197, measurement of grass-eating quantity and rate of digestion of cows using Au and Eu, sickness biochemical study of trace elements in hair samples of patients and others. (Kako, I.)

  10. Study of the comprehension of the scientific method by members of a university health research laboratory.

    Science.gov (United States)

    Burlamaque-Neto, A C; Santos, G R; Lisbôa, L M; Goldim, J R; Machado, C L B; Matte, U; Giugliani, R

    2012-02-01

    In Brazil, scientific research is carried out mainly at universities, where professors coordinate research projects with the active participation of undergraduate and graduate students. However, there is no formal program for the teaching/learning of the scientific method. The objective of the present study was to evaluate the comprehension of the scientific method by students of health sciences who participate in scientific projects in an academic research laboratory. An observational descriptive cross-sectional study was conducted using Edgar Morin complexity as theoretical reference. In a semi-structured interview, students were asked to solve an abstract logical puzzle - TanGram. The collected data were analyzed using the hermeneutic-dialectic analysis method proposed by Minayo and discussed in terms of the theoretical reference of complexity. The students' concept of the scientific method is limited to participation in projects, stressing the execution of practical procedures as opposed to scientific thinking. The solving of the TanGram puzzle revealed that the students had difficulties in understanding questions and activities focused on subjects and their processes. Objective answers, even when dealing with personal issues, were also reflected on the students' opinions about the characteristics of a successful researcher. Students' difficulties concerning these issues may affect their scientific performance and result in poorly designed experiments. This is a preliminary study that should be extended to other centers of scientific research. PMID:22249427

  11. Study of the comprehension of the scientific method by members of a university health research laboratory

    Directory of Open Access Journals (Sweden)

    A.C. Burlamaque-Neto

    2012-02-01

    Full Text Available In Brazil, scientific research is carried out mainly at universities, where professors coordinate research projects with the active participation of undergraduate and graduate students. However, there is no formal program for the teaching/learning of the scientific method. The objective of the present study was to evaluate the comprehension of the scientific method by students of health sciences who participate in scientific projects in an academic research laboratory. An observational descriptive cross-sectional study was conducted using Edgar Morin complexity as theoretical reference. In a semi-structured interview, students were asked to solve an abstract logical puzzle - TanGram. The collected data were analyzed using the hermeneutic-dialectic analysis method proposed by Minayo and discussed in terms of the theoretical reference of complexity. The students’ concept of the scientific method is limited to participation in projects, stressing the execution of practical procedures as opposed to scientific thinking. The solving of the TanGram puzzle revealed that the students had difficulties in understanding questions and activities focused on subjects and their processes. Objective answers, even when dealing with personal issues, were also reflected on the students’ opinions about the characteristics of a successful researcher. Students’ difficulties concerning these issues may affect their scientific performance and result in poorly designed experiments. This is a preliminary study that should be extended to other centers of scientific research.

  12. Compliance with Universal Precautions Among Nurses and Laboratory Technicians in Mansoura International Specialized Hospital

    Directory of Open Access Journals (Sweden)

    Sahar Mamoud Sayed Ahmed; Salwa Abbas Aly Hassan

    2008-03-01

    Full Text Available Compliance with universal precautions by nurses and laboratory technicians in hospitals is very important because it prevent cross infection and decrease costs of antibiotics and antipyretics. Also, it decreases spread of infection, which leads to decrease morbidity and mortality rate. A cross-sectional descriptive design was used for conducting this study. The sample of the study consisted of 150 nurses and lab technicians working at morning shift in a hospital at Mansoura City, Dakahlia Governorate. Data were collected using a questionnaire sheet and an observation checklist. The study revealed that majority (86.66% of the studied sample of nurses and lab technicians aged less than 30 years. Also, majority of the studied sample have poor knowledge about sign and symptom and transmission of AIDS. In addition, about 94% of the studied samples have poor knowledge about signs, symptoms and mode of transmissions of hepatitis B and C virus infection. All of the studied sample reported that there are no eye protections in the hospital. Positive correlations between nurses' and lab technicians' practice and available supplies in the hospital were found, but the relations were not statistically significant. The exception was the item of the infection prevention ways which has a significant statistical relation. Also, positive correlations between lab technicians' and nurses' practice and their attending for training courses about infection control were found, but the relations were not statistically significant.

  13. Upgrade of a radiation measurement laboratory course at the University of Florida

    International Nuclear Information System (INIS)

    The open-quotes Nuclear Radiation Detection and Instrumentation Laboratoryclose quotes course at the University of Florida provides health physics students with virtually their only hands-on exposure to the radiation measurement equipment used in professional practice. To better prepare students for employment, the course is currently under revision, with implementation of the revised course scheduled for fall semester 1996. The primary goal is to improve student understanding of the inherent strengths and limitations of various gas-filled, scintillation, and semiconductor detectors. A secondary goal is to improve student writing skills. To devise lab exercises that meet these goals, a six-step method for systematic laboratory course improvement was developed and used to guide the revision process. First, course objectives were delineated. Second, obstacles to achieving these course objectives were candidly assessed. Third, the course objectives were prioritized to ensure that the most important ones were met within the given time and equipment constraints. Fourth, performance-based learning objectives were written for each exercise. Fifth, exercises were developed that enable students to achieve the learning objectives specified. Sixth, when the revised course is implemented, its teaching effectiveness will be measured and steps will be taken to improve further. Course revision is nearly complete, and the new exercises promise to significantly improve both student technical knowledge and communication skill

  14. Intestinal and hepatic parasites determined in a university hospital parasitology laboratory

    Directory of Open Access Journals (Sweden)

    Zeynep Taş Cengiz

    2015-09-01

    Full Text Available Objective: The aim of this study is to present the prevalence of intestinal and hepatic parasites determined in Yüzüncü Yıl University Medical Faculty Parasitology Laboratory. Methods: The study was performed in 2008, and a total of 5985 stool samples were examined. Stool samples were examined with native-Lugol, sedimentation, flotation, trichrome staining and modified acid-fast staining methods. The stool samples of patient suspected to have Entamoeba histolytica/E.dispar infection were stained by trichrome staining method and evaluated by ELISA method for the antigen. ELISA method was used to confirm the results of Fasciola hepatica positive patients in stool examination. Results: In this study intestinal parasites were identified in 29.6% out of the 5985 people. In the study Giardia intestinalis (9.4%, plenty Blastocystis hominis (5.5%, Hymenolepis nana (1.7%, Ascaris lumbricoides (1.2%, Enterobius vermicularis (0.2%; in the stool examination, F.hepatica (0.1%, Cyclospora cayetanensis (0.1%, E.histolytica/E.dispar (0.06%, Taenia saginata (0.05%, Dicrocoelium dendriticum (0.05%, Trichuris trichiura (0.03% and Cryptosporidium spp. (0.02%, pathogenic parasites, were detected. Conclusion: In the study it is also understood that pathogenic intestinal parasites have still been reported at high rates and the problem of parasitosis continues in Van Province.

  15. Feasibility study of the University of Utah TRIGA reactor power upgrade in respect to control rod system

    Science.gov (United States)

    Cutic, Avdo

    The objectives of this thesis are twofold: to determine the highest achievable power levels of the current University of Utah TRIG Reactor (UUTR) core configuration with the existing three control rods, and to design the core for higher reactor power by optimizing the control rod worth. For the current core configuration, the maximum reactor power, eigenvalue keff, shutdown margin, and excess reactivity have been measured and calculated. These calculated estimates resulted from thermal power calibrations, and the control rod worth measurements at various power levels. The results were then used as a benchmark to verify the MCNP5 core simulations for the current core and then to design a core for higher reactor power. This study showed that the maximum achievable power with the current core configuration and control rod system is 150kW, which is 50kW higher than the licensed power of the UUTR. The maximum achievable UUTR core power with the existing fuel is determined by optimizing the core configuration and control rod worth, showing that a power upgrade of 500 kW is achievable. However, it requires a new control rod system consisting of a total of four control rods. The cost of such an upgrade is $115,000.

  16. Bioremediation of endosulfan contaminated soil and water-Optimization of operating conditions in laboratory scale reactors

    International Nuclear Information System (INIS)

    A mixed bacterial culture consisted of Staphylococcus sp., Bacillus circulans-I and -II has been enriched from contaminated soil collected from the vicinity of an endosulfan processing industry. The degradation of endosulfan by mixed bacterial culture was studied in aerobic and facultative anaerobic conditions via batch experiments with an initial endosulfan concentration of 50 mg/L. After 3 weeks of incubation, mixed bacterial culture was able to degrade 71.58 ± 0.2% and 75.88 ± 0.2% of endosulfan in aerobic and facultative anaerobic conditions, respectively. The addition of external carbon (dextrose) increased the endosulfan degradation in both the conditions. The optimal dextrose concentration and inoculum size was estimated as 1 g/L and 75 mg/L, respectively. The pH of the system has significant effect on endosulfan degradation. The degradation of alpha endosulfan was more compared to beta endosulfan in all the experiments. Endosulfan biodegradation in soil was evaluated by miniature and bench scale soil reactors. The soils used for the biodegradation experiments were identified as clayey soil (CL, lean clay with sand), red soil (GM, silty gravel with sand), sandy soil (SM, silty sand with gravel) and composted soil (PT, peat) as per ASTM (American society for testing and materials) standards. Endosulfan degradation efficiency in miniature soil reactors were in the order of sandy soil followed by red soil, composted soil and clayey soil in both aerobic and anaerobic conditions. In bench scale soil reactors, endosulfan degradation was observed more in the bottom layers. After 4 weeks, maximum endosulfan degradation efficiency of 95.48 ± 0.17% was observed in red soil reactor where as in composted soil-I (moisture 38 ± 1%) and composted soil-II (moisture 45 ± 1%) it was 96.03 ± 0.23% and 94.84 ± 0.19%, respectively. The high moisture content in compost soil reactor-II increased the endosulfan concentration in the leachate. Known intermediate metabolites of

  17. Studies of nuclear processes at the Triangle Universities Nuclear Laboratory. Progress report, 1 September 1994--31 August 1995

    International Nuclear Information System (INIS)

    The Triangle Universities Nuclear Laboratory (TUNL)--a collaboration of Duke University, North Carolina State University, and the University of North Carolina at Chapel Hill--has had a very productive year. This report covers the second year of a three-year grant between the US Department of Energy and the three collaborating universities. The TUNL research program focuses on the following areas of nuclear physics: parity violation in neutron and charged-particle resonances--the mass and energy dependence of the weak interaction spreading width; chaotic behavior in 30P from studies of eigenvalue fluctuations in nuclear level schemes; studies of few-body systems; nuclear astrophysics; nuclear data evaluation for A = 3--20, for which TUNL is now the international center; high-spin spectroscopy and superdeformation in nuclei, involving collaborations at Argonne National Laboratory. Developments in technology and instrumentation have been vital to the research and training program. In this progress report the author describes: a proposed polarized γ-beam facility at the Duke Free Electron Laser Laboratory; cryogenic systems and microcalorimeter development; continuing development of the Low Energy Beam Facility. The research summaries presented in this progress report are preliminary

  18. Reactors

    International Nuclear Information System (INIS)

    Purpose: To provide a spray cooling structure wherein the steam phase in a bwr reactor vessel can sufficiently be cooled and the upper cap and flanges in the vessel can be cooled rapidly which kept from direct contaction with cold water. Constitution: An apertured shielding is provided in parallel spaced apart from the inner wall surface at the upper portion of a reactor vessel equipped with a spray nozzle, and the lower end of the shielding and the inner wall of the vessel are closed to each other so as to store the cooling water. Upon spray cooling, cooling water jetting out from the nozzle cools the vapor phase in the vessel and then hits against the shielding. Then the cooling water mostly falls as it is, while partially enters through the apertures to the back of the shielding plate, abuts against stoppers and falls down. The stoppers are formed in an inverted L shape so that the spray water may not in direct contaction with the inner wall of the vessel. (Horiuchi, T.)

  19. Radioisotope radiotherapy research and achievements at the University of Missouri research reactor

    International Nuclear Information System (INIS)

    The University of Missouri Research Reactor (MURR) along with various other departments of the University of Missouri have been involved for many years in developing new means of internal radioisotopic therapy for cancer. These efforts have centered on methods of targeting radioisotopes such as brachytherapy, embolization of liver tumors with radioactive microspheres, small molecule-labeled chelate guidance for the treatment of bone cancer, and various means of radioimmunotherapy or labeled receptor agent targeting. All of this medical research and practical application of radioisotope therapy has been built on MURR's high neutron flux and outstanding reliability of operation, as well as MURR's flexibility in meeting the needs of researchers and the radiopharmaceutical industry. For many years MURR has produced Au-198 and Ir-192 wires for subsequent fabrication into brachytherapy sources for treatment of isolated tumors. An extension of this approach is embodied in Y-90 TheraSphere, which consists of Y-89-containing glass microspheres which are activated to contain Y-90 and injected in the blood supply of liver tumors. This approach leads to embolisation and very high radiation doses to tumor with minimal side effects, and is currently in use at six centers in the U.S. MURR has been instrumental in the development of bone agents such as Re-186 HEDP and Sm-153 Quadramet, the latter of which is now an approved drug for palliation of the pain from metastatic bone cancer. A related development is MURR's participation in trials using Ho-166 DOP to ablate diseased bone marrow in patients afflicted with multiple myeloma prior to reinfusion of cleansed, autologous marrow. This procedure has passed Phase I and II trials in the U.S., achieving approx. 50% complete remissions in multiple myeloma patients. MURR is currently upgrading its facilities to meet U.S. Food and Drug Administration (FDA) Current Good Manufacturing Practices (cGMP) requirements for Phase III of this

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

    International Nuclear Information System (INIS)

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

  1. Safety Evaluation Report related to the renewal of the operating license for the TRIGA training and research reactor at the University of Utah (Docket No. 50-407)

    International Nuclear Information System (INIS)

    This Safety Evaluation Report for the application filed by the University of Utah (UU) for a renewal of operating license R-126 to continue to operate a training and research reactor facility has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is owned and operated by the University of Utah and is located on its campus in Salt Lake City, Salt Lake County, Utah. The staff concludes that this training reactor facility can continue to be operated by UU without endangering the health and safety of the public

  2. Safety Evaluation Report related to the renewal of the operating license for the research reactor at the University of Kansas (Docket No. 50-148)

    International Nuclear Information System (INIS)

    This Safety Evaluation Report for the application filed by the University of Kansas (KU) for a renewal of Operating License R-78 to continue to operate the KU 250-kW open-pool training reactor has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is owned and operated by the University of Kansas and is located on the KU campus in Lawrence, Douglas County, Kansas. The staff concludes that the reactor facility can continue to be operated by KU without endangering the health and safety of the public. 17 references, 11 figures, 4 tables

  3. Safety evaluation report related to the renewal of the operating license for the research reactor at the University of Florida. Docket No. 50-83

    International Nuclear Information System (INIS)

    This Safety Evaluation Report for the application filed by the University of Florida (UF) for a renewal of Operating License R-56 to continue to operate its Argonaut-type research reactor has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is owned and operated by the University of Florida and is located on the UF campus in Gainesville, Alachua County, Florida. The staff concludes that the reactor facility can continue to be operated by UF without endangering the health and safety of the public

  4. Safety evaluation report related to the renewal of the operating license for the Washington State University TRIGA reactor. Docket No. 50-27

    International Nuclear Information System (INIS)

    This Safety Evaluation Report for the application filed by the Washington State University (WSU) for a renewal of operating license number R-76 to continue to operate a research reactor has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is owned and operated by the Washington State University and is located on the WSU campus in Pullman, Whitman County, Washington. The staff concludes that the TRIGA reactor facility can continue to be operated by WSU without endangering the health and safety of the public

  5. Safety-evaluation report related to the renewal of the operating license for the Cornell University TRIGA Research Reactor. Docket No. 50-157

    International Nuclear Information System (INIS)

    This Safety Evaluation Report for the application filed by the Cornell University for a renewal of Operating License R-80 to continue to operate a research reactor has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is owned and operated by Cornell University and is located on the Cornell campus in Ithaca, New York. The staff concludes that the TRIGA reactor facility can continue to be operated by Cornell without endangering the health and safety of the public

  6. Safety Evaluation Report Related to the Renewal of the Operating License for the TRIGA Training and Research Reactor at the University of Utah

    OpenAIRE

    United States Nuclear Regulatory Commission, Office of Nuclear Reactor Regulations

    1985-01-01

    This Safety Evaluation Report for the application filed by the University of Utah (UU) for a renewal of operating license R-126 to continue to operate a training and research reactor facility has been prepared by the Office of Nuclear Reactor Regulation of the U.S. Nuclear Regulatory Commission. The facility is owned and operated by the University of Utah and is located on its campus in Salt Lake City, Salt Lake County, Utah. The staff concludes that this training reactor facility can conti...

  7. Preventing depression and anxiety in young people: a review of the joint efficacy of universal, selective and indicated prevention.

    Science.gov (United States)

    Stockings, E A; Degenhardt, L; Dobbins, T; Lee, Y Y; Erskine, H E; Whiteford, H A; Patton, G

    2016-01-01

    Depression and anxiety (internalizing disorders) are the largest contributors to the non-fatal health burden among young people. This is the first meta-analysis to examine the joint efficacy of universal, selective, and indicated preventive interventions upon both depression and anxiety among children and adolescents (5-18 years) while accounting for their co-morbidity. We conducted a systematic review of reviews in Medline, PsycINFO and the Cochrane Library of Systematic Reviews, from 1980 to August 2014. Multivariate meta-analysis examined the efficacy of preventive interventions on depression and anxiety outcomes separately, and the joint efficacy on both disorders combined. Meta-regressions examined heterogeneity of effect according to a range of study variables. Outcomes were relative risks (RR) for disorder, and standardized mean differences (Cohen's d) for symptoms. One hundred and forty-six randomized controlled trials (46 072 participants) evaluated universal (children with no identified risk, n = 54) selective (population subgroups of children who have an increased risk of developing internalizing disorders due to shared risk factors, n = 45) and indicated prevention (children with minimal but detectable symptoms of an internalizing disorder, n = 47), mostly using psychological-only strategies (n = 105). Reductions in internalizing disorder onset occurred up to 9 months post-intervention, whether universal [RR 0.47, 95% confidence interval (CI) 0.37-0.60], selective (RR 0.61, 95% CI 0.43-0.85) or indicated (RR 0.48, 95% CI 0.29-0.78). Reductions in internalizing symptoms occurred up to 12 months post-intervention for universal prevention; however, reductions only occurred in the shorter term for selective and indicated prevention. Universal, selective and indicated prevention interventions are efficacious in reducing internalizing disorders and symptoms in the short term. They might be considered as repeated exposures in school settings across childhood

  8. From Secondary School To University: Attracting Young Students Towards A Career In Nuclear

    OpenAIRE

    Jimenez Varas, Gonzalo; A. Alvarez; Ortega, S.; Rubio, Rafael; M. Sánchez

    2011-01-01

    From its creation, Spanish Young Generation in Nuclear (Jóvenes Nucleares, JJNN), a non-profit organization that depends on the Spanish Nuclear Society (SNE), has as an important scope to help spread knowledge about nuclear energy, not only pointing out its advantages and its role in our society, but also trying to correct some of the ideas that are due to the biased information and to the lack of knowledge. To try to have success in that goal, some high school lectures were taught and it has...

  9. United States Domestic Research Reactor Infrastructure TRIGA Reactor Fuel Support

    International Nuclear Information System (INIS)

    The United State Domestic Research Reactor Infrastructure Program at the Idaho National Laboratory manages and provides project management, technical, quality engineering, quality inspection and nuclear material support for the United States Department of Energy sponsored University Reactor Fuels Program. This program provides fresh, unirradiated nuclear fuel to Domestic University Research Reactor Facilities and is responsible for the return of the DOE-owned, irradiated nuclear fuel over the life of the program. This presentation will introduce the program management team, the universities supported by the program, the status of the program and focus on the return process of irradiated nuclear fuel for long term storage at DOE managed receipt facilities. It will include lessons learned from research reactor facilities that have successfully shipped spent fuel elements to DOE receipt facilities.

  10. United States Domestic Research Reactor Infrastrucutre TRIGA Reactor Fuel Support

    Energy Technology Data Exchange (ETDEWEB)

    Douglas Morrell

    2011-03-01

    The United State Domestic Research Reactor Infrastructure Program at the Idaho National Laboratory manages and provides project management, technical, quality engineering, quality inspection and nuclear material support for the United States Department of Energy sponsored University Reactor Fuels Program. This program provides fresh, unirradiated nuclear fuel to Domestic University Research Reactor Facilities and is responsible for the return of the DOE-owned, irradiated nuclear fuel over the life of the program. This presentation will introduce the program management team, the universities supported by the program, the status of the program and focus on the return process of irradiated nuclear fuel for long term storage at DOE managed receipt facilities. It will include lessons learned from research reactor facilities that have successfully shipped spent fuel elements to DOE receipt facilities.

  11. Report of the research results with University of Tokyo, Nuclear Engineering Research Laboratory's Facilities in fiscal 1979

    International Nuclear Information System (INIS)

    The common utilization of the fast neutron source reactor ''Yayoi'' in the University of Tokyo has been continued for nine years, and many results have been obtained. As for the linac, the common utilization was commenced in the last fiscal year. 1663 men utilized the reactor, and 1063 men utilized the linac in 1979. At present, the on-pile researches centering around these two large installations and the off-pile researches toward new large-scale ones are two pillars. It is delightful to collect universal knowledge in the form of the common utilization, to promote researches effectively and to feed the results of researches back to education. Now the learning is devided finely, and the fields in which solution requires the concentration of the expertises in various fields have increased, accordingly the importance of such common utilization has grown more and more. In the common utilization of the reactors, many results were obtained in the researches on the utilization of fast neutron irradiation, the irradiation for medical use, shielding, nuclear fusion neutronics and so on. In the experiments using the linac, the number of the themes is too much, and the machine time allotted to respective themes is very much in short. The night operation system was adopted to ease the situation. Picosecond pulse radiolysis, pulse irradiation in gas, liquid and solid phases, and TOF experiment produced the results. (Kako, I.)

  12. A review of research activities at the Research Reactor Institute of Kyoto University in view of research publication information

    International Nuclear Information System (INIS)

    A database of research publication was constructed for the purpose of grasping all of the research activities at the Research Reactor Institute, Kyoto University. The database named KURRIP collects all of the research publications of the Institute by not only its own staff but also visiting scientists. The publications are in the form of original papers, review papers, papers in proceedings, short notes and letters, synopses over 3 pages presented orally at scientific meeting, books and doctoral theses. At present, the KURRIP database contains the information on 6,210 items which have been published for 30 years since the Institute was established as an interuniversity research institute for joint use of a research reactor and other related large facilities in 1963. By utilizing the KURRIP database, the analyses have been done: (1) affiliation of the authors, (2) kind of publications, (3) classification of publishers, (4) research fields, and (5) experimental facilities. The KURRIP database is now stored in the Data Processing Center of Kyoto University and can be utilized through a computer center at one of the main national universities in Japan. (author)

  13. Laboratory Experiments and Modeling for Interpreting Field Studies of Secondary Organic Aerosol Formation Using an Oxidation Flow Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Jimenez, Jose-Luis [Univ. of Colorado, Boulder, CO (United States)

    2016-02-01

    This grant was originally funded for deployment of a suite of aerosol instrumentation by our group in collaboration with other research groups and DOE/ARM to the Ganges Valley in India (GVAX) to study aerosols sources and processing. Much of the first year of this grant was focused on preparations for GVAX. That campaign was cancelled due to political reasons and with the consultation with our program manager, the research of this grant was refocused to study the applications of oxidation flow reactors (OFRs) for investigating secondary organic aerosol (SOA) formation and organic aerosol (OA) processing in the field and laboratory through a series of laboratory and modeling studies. We developed a gas-phase photochemical model of an OFR which was used to 1) explore the sensitivities of key output variables (e.g., OH exposure, O3, HO2/OH) to controlling factors (e.g., water vapor, external reactivity, UV irradiation), 2) develop simplified OH exposure estimation equations, 3) investigate under what conditions non-OH chemistry may be important, and 4) help guide design of future experiments to avoid conditions with undesired chemistry for a wide range of conditions applicable to the ambient, laboratory, and source studies. Uncertainties in the model were quantified and modeled OH exposure was compared to tracer decay measurements of OH exposure in the lab and field. Laboratory studies using OFRs were conducted to explore aerosol yields and composition from anthropogenic and biogenic VOC as well as crude oil evaporates. Various aspects of the modeling and laboratory results and tools were applied to interpretation of ambient and source measurements using OFR. Additionally, novel measurement methods were used to study gas/particle partitioning. The research conducted was highly successful and details of the key results are summarized in this report through narrative text, figures, and a complete list of publications acknowledging this grant.

  14. Safety-evaluation report related to the renewal of the operating license for the research reactor at the Iowa State University (Docket No. 50-116)

    International Nuclear Information System (INIS)

    This Safety Evaluation Report for the application filed by the Iowa State University (ISU) for a renewal of the Class 104 Operating License R-59 to continue to operate its Argonaut-type research reactor has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is owned and operated by the Iowa State University, and is located on the ISU campus in Ames, Story County, Iowa. The staff concludes that the reactor facility can continue to be operated by ISU without endangering the health and safety of the public. The principal matters reviewed are: design, testing, and performance of the reactor components and systems; the expected consequences of credible accidents; the licensee's management organization; the method used for the control of radiological effluents; the licensee's technical specifications; financial data and information; the physical protection program; procedures for training reactor operators; and emergency plans. 11 references, 15 figures, 13 tables

  15. Experimental and MCNP5 based evaluation of neutron and gamma flux in the irradiation ports of the University of Utah research reactor

    Directory of Open Access Journals (Sweden)

    Noble Brooklyn

    2012-01-01

    Full Text Available Neutron and gamma flux environment of various irradiation ports in the University of Utah training, research, isotope production, general atomics reactor were experimentally assessed and fully modeled using the MCNP5 code. The experimental measurements were based on the cadmium ratio in the irradiation ports of the reactor, flux profiling using nickel wire, and gamma dose measurements using thermo luminescence dosimeter. Full 3-D MCNP5 reactor model was developed to obtain the neutron flux distributions of the entire reactor core and to compare it with the measured flux focusing at the irradiation ports. Integration of all these analysis provided the updated comprehensive neutron-gamma flux maps of the existing irradiation facilities of the University of Utah TRIGA reactor.

  16. Operating characteristic analysis of a 400 mH class HTS DC reactor in connection with a laboratory scale LCC type HVDC system

    Science.gov (United States)

    Kim, Sung-Kyu; Kim, Kwangmin; Park, Minwon; Yu, In-Keun; Lee, Sangjin

    2015-11-01

    High temperature superconducting (HTS) devices are being developed due to their advantages. Most line commutated converter based high voltage direct current (HVDC) transmission systems for long-distance transmission require large inductance of DC reactor; however, generally, copper-based reactors cause a lot of electrical losses during the system operation. This is driving researchers to develop a new type of DC reactor using HTS wire. The authors have developed a 400 mH class HTS DC reactor and a laboratory scale test-bed for line-commutated converter type HVDC system and applied the HTS DC reactor to the HVDC system to investigate their operating characteristics. The 400 mH class HTS DC reactor is designed using a toroid type magnet. The HVDC system is designed in the form of a mono-pole system with thyristor-based 12-pulse power converters. In this paper, the investigation results of the HTS DC reactor in connection with the HVDC system are described. The operating characteristics of the HTS DC reactor are analyzed under various operating conditions of the system. Through the results, applicability of an HTS DC reactor in an HVDC system is discussed in detail.

  17. Description of a materials/coolant laboratory for support of the Breeder Reactor Technology Shipping Program

    International Nuclear Information System (INIS)

    A description of a facility devoted to evaluating the environmental compatibility and mechanical response of materials suitable for a breeder reactor spent-fuel shipping cask is given. The facility presently consists of a closed-loop servo-controlled hydraulic, horizontal test system coupled to an environmental chamber, generalized mechanical test equipment and high-rate mechanical behavior apparatus. Future plans include the procurement of real-time computer control equipment which will be used to assess the effects of complex load-time histories on spent-fuel shipping cask materials

  18. Validation of NESTLE against static reactor benchmark problems

    International Nuclear Information System (INIS)

    The NESTLE advanced nodal code was developed at North Carolina State University with support from Los Alamos National Laboratory and Idaho National Engineering Laboratory. It recently has been benchmarked successfully against measured data from pressurized water reactors (PWRs). However, NESTLE's geometric capabilities are very flexible, and it can be applied to a variety of other types of reactors. This study presents comparisons of NESTLE results with those from other codes for static benchmark problems for PWRs, boiling water reactors (BWRs), high-temperature gas-cooled reactors (HTGRs), and Canada deuterium uranium (CANDU) heavy-water reactors (HWRs)

  19. Validation of NESTLE against static reactor benchmark problems

    International Nuclear Information System (INIS)

    The NESTLE advanced modal code was developed at North Carolina State University with support from Los Alamos National Laboratory and Idaho National Engineering Laboratory. It recently has been benchmarked successfully against measured data from pressurized water reactors (PWRs). However, NESTLE's geometric capabilities are very flexible, and it can be applied to a variety of other types of reactors. This study presents comparisons of NESTLE results with those from other codes for static benchmark problems for PWRs, boiling water reactors (BWRs), high-temperature gas-cooled reactors (HTGRs) and CANDU heavy- water reactors (HWRs)

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

    International Nuclear Information System (INIS)

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