Emission Facilities - Erosion & Sediment Control Facilities

Data.gov (United States)

NSGIC Education | GIS Inventory — An Erosion and Sediment Control Facility is a DEP primary facility type related to the Water Pollution Control program. The following sub-facility types related to...

RADON-type disposal facility safety case for the co-ordinated research project on improvement of safety assessment methodologies for near surface radioactive waste disposal facilities (ISAM)

International Nuclear Information System (INIS)

Guskov, A.; Batanjieva, B.; Kozak, M.W.; Torres-Vidal, C.

2002-01-01

The ISAM safety assessment methodology was applied to RADON-type facilities. The assessments conducted through the ISAM project were among the first conducted for these kinds of facilities. These assessments are anticipated to lead to significantly improved levels of safety in countries with such facilities. Experience gained though this RADON-type Safety Case was already used in Russia while developing national regulatory documents. (author)

Current status of the Demonstration Test of Underground Cavern-Type Disposal Facilities

International Nuclear Information System (INIS)

Akiyama, Yoshihiro; Terada, Kenji; Oda, Nobuaki; Yada, Tsutomu; Nakajima, Takahiro

2011-01-01

In Japan, the underground cavern-type disposal facilities for low-level waste (LLW) with relatively high radioactivity, mainly generated from power reactor decommissioning, and for certain transuranic (TRU) waste, mainly from spent fuel reprocessing, are designed to be constructed in a cavern 50-100 m underground and to employ an engineered barrier system (EBS) made of bentonite and cement materials. To advance a disposal feasibility study, the Japanese government commissioned the Demonstration Test of Underground Cavern-Type Disposal Facilities in fiscal year (FY) 2005. Construction of a full-scale mock-up test facility in an actual subsurface environment started in FY 2007. The main test objective is to establish the construction methodology and procedures that ensure the required quality of the EBS on-site. A portion of the facility was constructed by 2010, and the test has demonstrated both the practicability of the construction and the achievement of quality standards: low permeability of less than 5x10 -13 m/s and low-diffusion of less than 1x10 -12 m 2 /s at the completion of construction. This paper covers the test results from the construction of certain parts using bentonite and cement materials. (author)

A model for plasma evolution in Filipov type plasma focus facilities

International Nuclear Information System (INIS)

Siahpoush, V.; Sobhanian, S.; Tafreshi, M. A.; Lamehi, M.

2003-01-01

A model is presented in this paper for the evolution of plasma in Filipov type plasma focus facilities. With the help of this model, one can predict some of the main parameters of the produced plasma and obtain the optimized geometrical an physical properties (anode radius and length, gas pressure, capacitance, bank energy etc) for the primary design purposes. The results obtained by this model will be compared with the experimental data obtained from the 90 kJ plasma focus facility D ena

Involvement of the Public Health Authority in emergency planning and preparedness for nuclear facilities in Hungary

International Nuclear Information System (INIS)

Sztanyik, L.B.

1986-01-01

It is required by the Hungarian Atomic Energy Act and its enacting clause of 1980 that facilities established for the application of atomic energy be designed, constructed and operated in such a manner that abnormal operational occurrences can be avoided and unplanned exposures to radiation and radioactive substances can be prevented. The primary responsibility for planning and implementing emergency actions rests with the management of the operating organization. Thus one of the prerequisites of licensing the first nuclear power plant in Hungary was the preparation and submission for approval of an emergency plan by the operating organization. In addition to this, the council of the county where the power plant is located has also been obliged to prepare a complementary emergency plan, in co-operation with other regional and national authorities, for the prevention of consequences from an emergency that may extend beyond the site boundary of the plant. In preparing the complementary plan, the emergency plan of the facility had to be taken into account. Unlike most national authorities involved in nuclear matters, the Public Health Authority is involved in the preparation of plans for every kind of emergency in a nuclear facility, including even those whose consequences can probably be confined to the plant site. The paper discusses in detail the role and responsibility of the Public Health Authority in emergency planning and preparedness for nuclear facilities. (author)

Identification of Human Intrusion Types into Radwaste Disposal Facility

International Nuclear Information System (INIS)

Budi Setiawan

2007-01-01

Human intrusion has long been recognized as a potentially important post-closure safety issue for rad waste disposal facility. It is due to the difficulties in predicting future human activities. For the preliminary study of human intrusion, identification of human intrusion types need to be recognized and investigated also the approaching of problem solving must be known to predict the prevention act and accepted risk. (author)

The Oskarshamn model for public involvement in the siting of nuclear facilities

Energy Technology Data Exchange (ETDEWEB)

Aahagen, H. [Ahagen and Co (Sweden); CarIsson, Torsten [Mayor, Oskarshamn (Sweden); Hallberg, K. [Local Competence Building, Oskarshamn (Sweden); Andersson, Kjell [Karinta-Konsult, Taeby(Sweden)

1999-12-01

The Oskarshamn model has so far worked extremely well as a tool to achieve openness and public participation. The municipality involvement has been successful in several aspects, e.g.: It has been possible to influence the program, to a large extent, to meet certain municipality conditions and to ensure the local perspective. The local competence has increased to a considerable degree. The activities generated by the six working groups with a total of 40 members have generated a large number of contacts with various organisations, schools, mass media, individuals in the general public and interest groups. For the future, clarification of the disposal method and site selection criteria as well as the site selection process as such is crucial. The municipality has also emphasised the importance of SKB having shown the integration between site selection criteria, the feasibility study and the safety assessment. Furthermore, the programs for the encapsulation facility and the repository must be co-ordinated. For Oskarshamn it will be of utmost importance that the repository is well under way to be realised before the encapsulation facility can be built.

The Oskarshamn model for public involvement in the siting of nuclear facilities

International Nuclear Information System (INIS)

Aahagen, H.; CarIsson, Torsten; Hallberg, K.; Andersson, Kjell

1999-01-01

The Oskarshamn model has so far worked extremely well as a tool to achieve openness and public participation. The municipality involvement has been successful in several aspects, e.g.: It has been possible to influence the program, to a large extent, to meet certain municipality conditions and to ensure the local perspective. The local competence has increased to a considerable degree. The activities generated by the six working groups with a total of 40 members have generated a large number of contacts with various organisations, schools, mass media, individuals in the general public and interest groups. For the future, clarification of the disposal method and site selection criteria as well as the site selection process as such is crucial. The municipality has also emphasised the importance of SKB having shown the integration between site selection criteria, the feasibility study and the safety assessment. Furthermore, the programs for the encapsulation facility and the repository must be co-ordinated. For Oskarshamn it will be of utmost importance that the repository is well under way to be realised before the encapsulation facility can be built

Type A aortic dissection: Are there CT signs suggestive of valvular involvement?

Energy Technology Data Exchange (ETDEWEB)

Platon, Alexandra, E-mail: alexandra.platon@hcuge.ch [Department of Radiology, Emergency Radiology Unit, University Hospital of Geneva, 4 rue Gabrielle-Perret-Gentil, 1211, Geneva (Switzerland); Bernard, Stephane; Perrin, Nils [Department of Radiology, Emergency Radiology Unit, University Hospital of Geneva, 4 rue Gabrielle-Perret-Gentil, 1211, Geneva (Switzerland); Murith, Nicolas [Division of Cardiovascular Surgery, University Hospital of Geneva, 4 rue Gabrielle-Perret-Gentil, 1211, Geneva (Switzerland); John, Gregor [Department of Internal medicine/Geriatrics and Rehabilitation, University Hospital of Geneva, 4 rue Gabrielle-Perret-Gentil, 1211, Geneva (Switzerland); Department of Internal Medicine, Hôpital neuchâtelois, 2300 La Chaux-de-Fonds (Switzerland); Perneger, Thomas [Division of Clinical Epidemiology, University Hospital of Geneva, 4 rue Gabrielle-Perret-Gentil, 1211, Geneva (Switzerland); Rutschmann, Olivier T. [Division of Emergency Medicine, University Hospitals of Geneva and School of Medicine, 4 rue Gabrielle-Perret-Gentil, 1211, Geneva (Switzerland); Poletti, Pierre-Alexandre [Department of Radiology, Emergency Radiology Unit, University Hospital of Geneva, 4 rue Gabrielle-Perret-Gentil, 1211, Geneva (Switzerland)

2016-11-15

Highlights: • Non-ECG gated CT rarely shows valve involvement in type A aortic dissection. • Diameters of the aortic root in type A aortic dissection were measured on initial CT. • Sinus of Valsalva diameter >45 mm is 100% specific to predict aortic valve involvement. - Abstract: Aim: To identify the predictive signs of aortic valve involvement on the non-electrocardiogram (ECG)-gated admission computed tomography (CT) of patients with Type A aortic dissection (AD) according to the Stanford classification. Materials and methods: We retrospectively analyzed the non-ECG-gated CT examinations of patients admitted to the emergency department who underwent surgery for Type A AD over a period of 4 years. The diameter of the following structures was calculated as the mean of the smallest and largest diameters (mm) measured in two different planes: aortic annulus, sinus of Valsalva, sinotubular junction, and proximal ascending aorta. These parameters were compared against operative reports in order to determine whether they were predictive of aortic valve involvement. Results: In total, 20 patients (13 men and 7 women) of a mean age of 59.5 years (29–80) were included, 55% of patients (11/20) having surgically proven valvular involvement. The mean diameters (in mm) of the aortic annulus, sinus of Valsalva, sinotubular junction and proximal ascending aorta in the group with (and without, respectively) valvular involvement was 27.7 (26.7), 44.3 (38.1), 42.6 (36.6), and 47.8 (45.9). Only the measurement of the mean diameter of the sinuses of Valsalva was significantly predictive (p = 0.02) of aortic valve involvement. Conclusion: Our findings suggest that measuring the diameter of the sinuses of Valsalva on non-ECG-gated admission CT examinations allows for predicting aortic valve involvement in Type A AD patients.

Type A aortic dissection: Are there CT signs suggestive of valvular involvement?

International Nuclear Information System (INIS)

Platon, Alexandra; Bernard, Stephane; Perrin, Nils; Murith, Nicolas; John, Gregor; Perneger, Thomas; Rutschmann, Olivier T.; Poletti, Pierre-Alexandre

2016-01-01

Highlights: • Non-ECG gated CT rarely shows valve involvement in type A aortic dissection. • Diameters of the aortic root in type A aortic dissection were measured on initial CT. • Sinus of Valsalva diameter >45 mm is 100% specific to predict aortic valve involvement. - Abstract: Aim: To identify the predictive signs of aortic valve involvement on the non-electrocardiogram (ECG)-gated admission computed tomography (CT) of patients with Type A aortic dissection (AD) according to the Stanford classification. Materials and methods: We retrospectively analyzed the non-ECG-gated CT examinations of patients admitted to the emergency department who underwent surgery for Type A AD over a period of 4 years. The diameter of the following structures was calculated as the mean of the smallest and largest diameters (mm) measured in two different planes: aortic annulus, sinus of Valsalva, sinotubular junction, and proximal ascending aorta. These parameters were compared against operative reports in order to determine whether they were predictive of aortic valve involvement. Results: In total, 20 patients (13 men and 7 women) of a mean age of 59.5 years (29–80) were included, 55% of patients (11/20) having surgically proven valvular involvement. The mean diameters (in mm) of the aortic annulus, sinus of Valsalva, sinotubular junction and proximal ascending aorta in the group with (and without, respectively) valvular involvement was 27.7 (26.7), 44.3 (38.1), 42.6 (36.6), and 47.8 (45.9). Only the measurement of the mean diameter of the sinuses of Valsalva was significantly predictive (p = 0.02) of aortic valve involvement. Conclusion: Our findings suggest that measuring the diameter of the sinuses of Valsalva on non-ECG-gated admission CT examinations allows for predicting aortic valve involvement in Type A AD patients.

Decommissioning of nuclear facilities by the United States Department of Energy Oak Ridge Field Office

International Nuclear Information System (INIS)

DeLozier, M.F.P.

1992-01-01

The Oak Ridge Field Office of the United States Department of Energy is projecting one of the largest decommissioning efforts in the nation during the next ten to twenty years. The nuclear facilities are varied with respect to the types of contaminants and types of structures and equipment involved. The facilities planned for decommissioning include 26 ORNL facilities (e.g., OGR, HRE, MSRE), 70 facilities at Oak Ridge K25 site, and the Y-12 plant at Oak Ridge. Innovative technologies are required to decommission the facilities and dispose of the waste generated. (R.P.)

Strategies for energy benchmarking in cleanrooms and laboratory-type facilities

International Nuclear Information System (INIS)

Sartor, Dale; Piette, Mary Ann; Tschudi, William; Fok, Stephen

2000-01-01

Buildings with cleanrooms and laboratories are growing in terms of total floor area and energy intensity. This building type is common in institutions such as universities and in many industries such as microelectronics and biotechnology. These buildings, with high ventilation rates and special environmental considerations, consume from 4 to 100 times more energy per square foot than conventional commercial buildings. Owners and operators of such facilities know they are expensive to operate, but have little way of knowing if their facilities are efficient or inefficient. A simple comparison of energy consumption per square foot is of little value. A growing interest in benchmarking is also fueled by: A new U.S. Executive Order removing the exemption of federal laboratories from energy efficiency goals, setting a 25% savings target, and calling for baseline guidance to measure progress; A new U.S. EPA and U.S. DOE initiative, Laboratories for the 21st Century, establishing voluntary performance goals and criteria for recognition; and A new PG and E market transformation program to improve energy efficiency in high tech facilities, including a cleanroom energy use benchmarking project. This paper identifies the unique issues associated with benchmarking energy use in high-tech facilities. Specific options discussed include statistical comparisons, point-based rating systems, model-based techniques, and hierarchical end-use and performance-metrics evaluations

Staff's reactions towards partnered sexual expressions involving people with dementia living in long-term care facilities.

Science.gov (United States)

Villar, Feliciano; Celdrán, Montserrat; Serrat, Rodrigo; Fabà, Josep; Martínez, Teresa

2018-05-01

To explore staff responses, in terms of common practices, towards partnered sexual relationships in long-term care facilities where one or both people involved have dementia. It also tries to determine personal and institutional factors influencing these responses. Although some studies, mostly qualitative, have focused on reactions to residents' sexual expressions so far the issue has not been assessed in a study using large and diverse samples. Cross-sectional quantitative study using vignette technique. Participants were 2,295 staff members at 152 Spanish long-term care facilities. Data were collected during 2016. A vignette describing sexual situations involving people with dementia was presented to participants. After the vignette, participants had to answer the question: "What do you think most of your colleagues would do in this situation?" with nine possible responses. Results showed that relationships involving persons with dementia were perceived as potentially problematic by staff. In both conditions, discussing the case with a colleague or supervisor was the most frequently chosen reaction. More restrictive reactions were mentioned when only one person with dementia was involved in the relationship. Factors such as participants" age and years of experience, professional post and commitment to person-centred care practices were related with the frequency of common restriction practices. Results highlight the importance of providing staff with clear guidelines regarding the management of specific sexual situations to avoid stereotyped restrictive reactions. © 2017 John Wiley & Sons Ltd.

Cavity-Type BPMs For The TESLA Test Facility Free Electron Laser

CERN Document Server

Waldmann, H

2003-01-01

For measurements of the beam position at the undulator section of the TESLA Test Facility (TTF) at DESY cavity-type beam position monitors were developed, installed and brought into operation. Besides of some theoretical aspects results of in-beam measurements at the TTF are presented and pros and cons of this monitor concept are discussed.

Workers' exposure to bioaerosols from three different types of composting facilities.

Science.gov (United States)

Bonifait, Laetitia; Marchand, Geneviève; Veillette, Marc; M'Bareche, Hamza; Dubuis, Marie-Eve; Pépin, Carole; Cloutier, Yves; Bernard, Yves; Duchaine, Caroline

2017-10-01

Composting is a natural dynamic biological process used to valorise putrescible organic matter. The composting process can involve vigorous movements of waste material piles, which release high concentrations of bioaerosols into the surrounding environment. There is a lack of knowledge concerning the dispersal of airborne microorganisms emitted by composting plants (CP) as well as the potential occupational exposure of composting workers. The aim of this study was to investigate the workers exposure to bioaerosols during working activities in three different types of composting facilities (domestic, manure, carcass) using two different quantification methods (cultivation and qPCR) for bacteria and moulds concentrations. As expected, even if there are differences between all CP frameworks, independently of the type of the raw compost used, the production of bioaerosols increases significantly during handling activities. Important concentrations of mesophilic moulds and mesophilic bacteria were noted in the working areas with a respective maximal concentration of 2.3 × 10 5 CFU/m 3 and 1.6 × 10 5 CFU/m 3 . A. fumigatus and thermophilic Actinomycetes were also detected in all working areas for the 3 CP. This study emphases the risks for workers to being in contact with aerosolized pathogens such as Mycobacterium and Legionella and more specifically, L. pneumophila. The presence of high concentration of these bacteria in CP suggests a potential occupational health risk. This study may lead to recommendations for the creation of limits for occupational exposure. There is a need for identifying the standards exposure limits to bioaerosols in CP and efficient recommendation for a better protection of workers' health.

Public involvement: the critical path in siting controversial facilities. Proceedings of the Nuclear Energy Low-Level Waste Mangement Program conference

International Nuclear Information System (INIS)

1986-01-01

The purpose of the conference was to: exchange information among those responsible for, or interested in, the development of new low-level waste disposal facilities; acquaint participants with past experiences of states and organizations in enfranchising the public in the siting of controversial facilities; and discuss various mechanisms and techniques for effectively involving the public in decision-making processes. The conference addressed four major topics: lessons from past experiences; mechanisms and techniques for public involvement, conflict resolution, and working constructively with the media. A series of presentations on each topic was followed by questions and discussion among presenters and conference participants. Several key points emerged as the conference proceeded

Safety of magnetic fusion facilities: Guidance

International Nuclear Information System (INIS)

1996-05-01

This document provides guidance for the implementation of the requirements identified in DOE-STD-6002-96, Safety of Magnetic Fusion Facilities: Requirements. This guidance is intended for the managers, designers, operators, and other personnel with safety responsibilities for facilities designated as magnetic fusion facilities. While the requirements in DOE-STD-6002-96 are generally applicable to a wide range of fusion facilities, this Standard, DOE-STD-6003-96, is concerned mainly with the implementation of those requirements in large facilities such as the International Thermonuclear Experimental Reactor (ITER). Using a risk-based prioritization, the concepts presented here may also be applied to other magnetic fusion facilities. This Standard is oriented toward regulation in the Department of Energy (DOE) environment as opposed to regulation by other regulatory agencies. As the need for guidance involving other types of fusion facilities or other regulatory environments emerges, additional guidance volumes should be prepared. The concepts, processes, and recommendations set forth here are for guidance only. They will contribute to safety at magnetic fusion facilities

Integrals involving functions of the type (WS)sup(q)

International Nuclear Information System (INIS)

Srivastava, D.K.

1981-10-01

Analytical expressions for integrals involving functions of the Woods-Saxon type raised to the power of q are given. These are expected to be of immediate application in optical model studies and for obtaining various moments of the potential having such shapes. (author)

Vulnerability Analysis for Physical Protection System at Hypothetical Facility of a Different Type Reactor

International Nuclear Information System (INIS)

Jung, Won-Moog; Kim, Jung-Soo; Kim, Jae-Kwang; Yoo, Ho-Sik; Kwak, Sung-Ho; Jang, Sung-Soon

2007-01-01

Since the 9/11 event in the U.S.A, International terror possibilities has been increased for nuclear facilities including nuclear power plants(NPPs). It is necessary to evaluate the performance of an existing physical protection system(PPS) at nuclear facilities based on such malevolent acts. Detection, delay, and response elements are all important to PPS. They are used for the analysis and evaluation of a PPS and its effectiveness. Methods are available to analyze a PPS and evaluate its effectiveness. Sandia National Laboratory(SNL) in the U.S.A developed a System Analysis of Vulnerability to Intrusion (SAVI) computer code for evaluating the effectiveness of PPS against outsider threats. This study presents the vulnerability analysis of the PPS at hypothetical facility of a different type using SAVI code that the basic input parameters are from PPS of a different type. For analysis, first, the site-specific Adversary Sequence Diagrams(ASDs) of the PPS is designed. It helps to understand the functions of the existing PPS composed of physical areas and Protection Elements(PEs). Then, the most vulnerable path of an ASD as a measure of effectiveness is determined. The results in the analysis can compare with the most vulnerable paths at a different type

A study on hazard types occurring in hydrogen facilities

International Nuclear Information System (INIS)

Cho, Nam Chul; Jae, Moo Sung; Eon, Yang Joon

2004-01-01

Hydrogen has ideal characteristics as an energy carrier. Hydrogen can be used as a clean fuel in a variety of energy end-use sectors including the conversion to electricity. After combustion, it produces only water. Therefore, the concept of hydrogen energy system has attracted much interest worldwide. But hydrogen has a defect that the explosion risk is high to an inflammable gas of a colorless, tasteless and odorless. Therefore, to use the hydrogen to the source of energy, hydrogen accident sequences and causes analysis must be needed. For this, hazard types occurring in hydrogen facilities have been considered through the case of domestic and foreign hydrogen accident in this study and hazard types to be considered are ignition, leaks, hydrogen dispersion, fire an explosion, storage vessel failure, vent and exhaust system, purging, condensation of air, hydrogen embrittlement, physiological hazard, and collisions during transportation

Development of radiation safety monitoring system at gamma greenhouse gamma facility

International Nuclear Information System (INIS)

Hairul Nizam Idris; Azimawati Ahmad, Ahmad Zaki Hussain; Ahmad Fairuz Mohd Nasir

2009-01-01

This paper is discussing about installation of radiation safety monitoring system at Gamma Greenhouse Gamma facility, Agrotechnology and Bioscience Division (BAB). This facility actually is an outdoor type irradiation facility, which first in Nuclear Malaysia and the only one in Malaysia. Source Cs-137 (801 Curie) was use as radiation source and it located at the centre of 30 metres diameter size of open irradiation area. The radiation measurement and monitoring system to be equipped in this facility were required the proper equipment and devices, specially purpose for application at outside of building. Research review, literature study and discussion with the equipment manufacturers was being carried out, in effort to identify the best system should be developed. Factors such as tropical climate, environment surrounding and security were considered during selecting the proper system. Since this facility involving with panoramic radiation type, several critical and strategic locations have been fixed with radiation detectors, up to the distance at 200 meter from the radiation source. Apart from that, this developed system also was built for capable to provide the online real-time reading (using internet). In general, it can be summarized that the radiation safety monitoring system for outdoor type irradiation facility was found much different and complex compared to the system for indoor type facility. Keyword: radiation monitoring, radiation safety, Gamma Greenhouse, outdoor irradiation facility, panoramic radiation. (Author)

The role of public involvement in managing political conflict: A comparative case study of public involvement activities in siting low-level radioactive waste disposal facilities

International Nuclear Information System (INIS)

Tzoumis, K.A.

1992-01-01

A model of political conflict based on the components of scope, intensity and visibility is used to rank the degree of conflict for states hosting a low-level radioactive waste facility in the US. Data were gathered from sixty-five telephone interviews and comparisons made with ten national experts. Public involvement and compensation packages (reviewed in Chapter IV) to be potential conflict management tools for practitioners. The role of the governor and the complexity of the siting process are two additional factors that are important in escalating a conflict. Technical factors of complexity and source of the waste along with the past performance of the company handling the facility have no link to conflict. Conflict escalation is proposed as a means towards understanding the agenda-building process

Facile synthesis of birnessite-type manganese oxide nanoparticles as supercapacitor electrode materials.

Science.gov (United States)

Liu, Lihu; Luo, Yao; Tan, Wenfeng; Zhang, Yashan; Liu, Fan; Qiu, Guohong

2016-11-15

Manganese oxides are environmentally benign supercapacitor electrode materials and, in particular, birnessite-type structure shows very promising electrochemical performance. In this work, nanostructured birnessite was facilely prepared by adding dropwise NH2OH·HCl to KMnO4 solution under ambient temperature and pressure. In order to fully exploit the potential of birnessite-type manganese oxide electrode materials, the effects of specific surface area, pore size, content of K(+), and manganese average oxidation state (Mn AOS) on their electrochemical performance were studied. The results showed that with the increase of NH2OH·HCl, the Mn AOS decreased and the corresponding pore sizes and specific surface area of birnessite increased. The synthesized nanostructured birnessite showed the highest specific capacitance of 245Fg(-1) at a current density of 0.1Ag(-1) within a potential range of 0-0.9V, and excellent cycle stability with a capacitance retention rate of 92% after 3000 cycles at a current density of 1.0Ag(-1). The present work implies that specific capacitance is mainly affected by specific surface area and pore volume, and provides a new method for the facile preparation of birnessite-type manganese oxide with excellent capacitive performance. Copyright © 2016 Elsevier Inc. All rights reserved.

Involvement of family members in life with type 2 diabetes

DEFF Research Database (Denmark)

Grabowski, Dan; Andersen, Tue Helms; Varming, Annemarie

2017-01-01

OBJECTIVES: Family involvement plays a key role in diabetes management. Problems and challenges related to type 2-diabetes often affect the whole family, and relatives are at increased risk of developing diabetes themselves. We highlight these issues in our objectives: (1) to uncover specific...... family problems associated with mutual involvement in life with type 2-diabetes and (2) to analytically look at ways of approaching these problems in healthcare settings. METHODS: Qualitative data were gathered in participatory problem assessment workshops. The data were analysed in three rounds using...... radical hermeneutics. RESULTS: Problems were categorized in six domains: knowledge, communication, support, everyday life, roles and worries. The final cross-analysis focusing on the link between family identity and healthcare authenticity provided information on how the six domains can be approached...

Household Consumption of Food-Away-From-Home: Total Expenditure and by Type of Food Facility

OpenAIRE

Vicki A. McCracken; Jon A. Brandt

1987-01-01

Consistent with prior expectations based on household production theory, household income, time value, size and composition, and the environment in which production and consumption occurred were all important determinants of total household expenditures on food-away-from-home. However, the importance of these factors varied by type of food facility: conventional restaurants, fast-food facilities, and other commercial establishments. Decomposition of the tobit elasticities indicated the differ...

The progress and results of a demonstration test of a cavern-type disposal facility

International Nuclear Information System (INIS)

Akiyama, Yoshihiro; Terada, Kenji; Oda, Nobuaki; Yada, Tsutomu; Nakajima, Takahiro

2011-01-01

The cavern-type disposal facilities for low-level waste (LLW) with relatively high radioactivity levels mainly generated from power reactor decommissioning and for part of transuranic (TRU) waste mainly from spent fuel reprocessing are designed to be constructed in a cavern 50 to 100 meters below ground, and to employ an engineered barrier system (EBS) of a combination of bentonite and cement materials in Japan. In order to advance the feasibility study for these disposal, a government-commissioned research project named Demonstration Test of Cavern-Type Disposal Facility started in fiscal 2005, and since fiscal 2007 a full-scale mock-up test facility has been constructed under actual subsurface environment. The main objective of the test is to establish construction methodology and procedures which ensure the required quality of the EBS on-site. By fiscal 2009 some parts of the facility have been constructed, and the test has demonstrated both practicability of the construction and achievement of the quality. They are respectively taken as low-permeability of less than 5x10 13 m/s and low-diffusivity of less than 1x10 -12 m 2 /s at the time of completion of construction. This paper covers the project outline and the test results obtained by the construction of some parts of a bentonite and cement materials. (author)

Postural control and central motor pathway involvement in type 2 ...

African Journals Online (AJOL)

Mona Mokhtar El Bardawil

2013-04-18

Apr 18, 2013 ... Postural control and central motor pathway involvement in type 2 .... with a high power 90 mm circular coil, capable of generating. 2 T maximum field ..... advanced glycation end products, oxidative damage and microvascular ...

MR imaging of abdominopelvic involvement in neurofibromatosis type 1: a review of 43 patients

Energy Technology Data Exchange (ETDEWEB)

Zacharia, T. Thomas [Massachusetts General Hospital, Department of Radiology, Boston, MA (United States); Jaramillo, Diego [Children' s Hospital of Philadelphia, Department of Radiology, Philadelphia, PA (United States); Poussaint, Tina Young [Children' s Hospital Boston, Department of Radiology, Boston, MA (United States); Korf, Bruce [University of Alabama at Birmingham Hospital, Department of Genetics, Birmingham, AL (United States)

2005-03-01

Plexiform neurofibromas are a frequent complication of neurofibromatosis type 1. This article discusses MR imaging findings and distribution of plexiform neurofibromas in the abdomen and pelvis. To define the most prevalent patterns of involvement and MR imaging findings in abdominopelvic neurofibromatosis type 1. We reviewed the MR appearance of abdominopelvic lesions in 23 male and 20 female patients (median age: 16 years) with type 1 neurofibromatosis. The patients were part of a multi-institutional study of 300 patients. Imaging included coronal or sagittal, and axial short tau inversion recovery images. The most common abdominopelvic involvement was in the abdominopelvic wall (n=28, 65%) and lumbosacral plexus (n=27, 63%). Retroperitoneal involvement was frequent (n=15, 35%). Lesions were less often intraperitoneal (21%) (P=0.001). Pelvic disease (n=27, 63%), neural canal involvement (n=18, 42%), and hydronephrosis (n=4, 9%) were also noted. Target-like appearance of plexiform lesions was noted in more than half the patients. Abdominopelvic involvement in neurofibromatosis type 1 is primarily extraperitoneal. Although lesions are most prevalent in the abdominopelvic wall and lumbosacral plexus, retroperitoneal and pelvic involvement is common and usually affects important organs. MR imaging added information in the initial and follow-up clinical evaluation of these patients. (orig.)

Decommissioning of nuclear facilities: a growing activity in the world

International Nuclear Information System (INIS)

Anasco, Raul

2001-01-01

Nuclear power plants and nuclear facilities are no different from normal buildings and factories. Eventually, they become worn-out or old fashioned, too expensive to maintain or remodel. Decommissioning a nuclear facility is different from retiring other types because of the radioactivity involved. The most important consideration in nuclear decommissioning is to protect workers and the public from exposure to harmful levels of radiation. General criteria and strategies for the decommissioning of nuclear facilities are described as well as the present decommissioning activities of the Argentine CNEA (author)

Task types and error types involved in the human-related unplanned reactor trip events

International Nuclear Information System (INIS)

Kim, Jae Whan; Park, Jin Kyun

2008-01-01

In this paper, the contribution of task types and error types involved in the human-related unplanned reactor trip events that have occurred between 1986 and 2006 in Korean nuclear power plants are analysed in order to establish a strategy for reducing the human-related unplanned reactor trips. Classification systems for the task types, error modes, and cognitive functions are developed or adopted from the currently available taxonomies, and the relevant information is extracted from the event reports or judged on the basis of an event description. According to the analyses from this study, the contributions of the task types are as follows: corrective maintenance (25.7%), planned maintenance (22.8%), planned operation (19.8%), periodic preventive maintenance (14.9%), response to a transient (9.9%), and design/manufacturing/installation (6.9%). According to the analysis of the error modes, error modes such as control failure (22.2%), wrong object (18.5%), omission (14.8%), wrong action (11.1%), and inadequate (8.3%) take up about 75% of the total unplanned trip events. The analysis of the cognitive functions involved in the events indicated that the planning function had the highest contribution (46.7%) to the human actions leading to unplanned reactor trips. This analysis concludes that in order to significantly reduce human-induced or human-related unplanned reactor trips, an aide system (in support of maintenance personnel) for evaluating possible (negative) impacts of planned actions or erroneous actions as well as an appropriate human error prediction technique, should be developed

Task types and error types involved in the human-related unplanned reactor trip events

Energy Technology Data Exchange (ETDEWEB)

Kim, Jae Whan; Park, Jin Kyun [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2008-12-15

In this paper, the contribution of task types and error types involved in the human-related unplanned reactor trip events that have occurred between 1986 and 2006 in Korean nuclear power plants are analysed in order to establish a strategy for reducing the human-related unplanned reactor trips. Classification systems for the task types, error modes, and cognitive functions are developed or adopted from the currently available taxonomies, and the relevant information is extracted from the event reports or judged on the basis of an event description. According to the analyses from this study, the contributions of the task types are as follows: corrective maintenance (25.7%), planned maintenance (22.8%), planned operation (19.8%), periodic preventive maintenance (14.9%), response to a transient (9.9%), and design/manufacturing/installation (6.9%). According to the analysis of the error modes, error modes such as control failure (22.2%), wrong object (18.5%), omission (14.8%), wrong action (11.1%), and inadequate (8.3%) take up about 75% of the total unplanned trip events. The analysis of the cognitive functions involved in the events indicated that the planning function had the highest contribution (46.7%) to the human actions leading to unplanned reactor trips. This analysis concludes that in order to significantly reduce human-induced or human-related unplanned reactor trips, an aide system (in support of maintenance personnel) for evaluating possible (negative) impacts of planned actions or erroneous actions as well as an appropriate human error prediction technique, should be developed.

Test facility of the VVER-440 condensation-type pressure suppression system

International Nuclear Information System (INIS)

Wolff, H.; Arndt, S.

2004-01-01

Since the early nineties, GRS has supported regulatory authorities in Central and Eastern Europe in performing safety assessments of nuclear power plants. Especially studies of the condensation-type pressure suppression system of VVER-440/V-213-type plants have been important in this respect. Major steps in demonstrating complete functioning of the condensation-type pressure suppression system under accident conditions by experiments run in the Russian large scale test facility, BC V-213, have been completed in the past two years within the framework of various international experimental programs. The test results were used to validate specifically for power plants with VVER-400/V-213 reactors the COCOSYS GRS computer code, which is used in the safety assessments. The results of recalculations of the C02 EREC test, which simulates a break of a main steam pipe, demonstrate the present state of validation of COCOSYS for VVER condensation-type pressure suppression systems. (orig.) [de

A Study on the Ion Beam Extraction using Duo-PiGatron Ion source for Vertical Type Ion Beam Facility

Energy Technology Data Exchange (ETDEWEB)

Kim, Bom Sok; Lee, Chan young; Lee, Jae Sang [KAERI, Daejeon (Korea, Republic of)

2015-05-15

In Korea Multipurpose Accelerator Complex (KOMAC), we have started ion beam service in the new beam utilization building since March this year. For various ion beam irradiation services, we are developed implanters such as metal (150keV/1mA), gaseous (200keV/5mA) and high current ion beam facility (20keV/150mA). One of the new one is a vertical type ion beam facility without acceleration tube (60keV/20mA) which is easy to install the sample. After the installation is complete, it is where you are studying the optimal ion beam extraction process. Detailed experimental results will be presented. Vertical Type Ion Beam Facility without acceleration tube of 60keV 20mA class was installed. We successfully extracted 60keV 20mA using Duo- PiGatron Ion source for Vertical Type Ion Beam Facility. Use the BPM and Faraday-cup, is being studied the optimum conditions of ion beam extraction.

Types of parents’ involvement in early childhood development

Directory of Open Access Journals (Sweden)

Barbara Chojnacka-Synaszko

2016-04-01

Full Text Available Depending on their involvement in assisting their child’s development, parents may have various chances of improving and refining their childcare, parenting, and therapeutic methods. The objective of this study was to learn the opinions of the parents of children covered by the early intervention/early assisted-development programme regarding their own involvement in the processes, and determining which types of involvement, whether active or passive, the parents seem to practice. The empirical material was acquired in a survey conducted in the form of a questionnaire in May 2015 and June 2016, covering a total of 143 parents. According to our results, the respondents not only follow the recommendations provided by the specialists based at a given support centre (96.5%, but also actively seek information and knowledge related to activities and measures aimed at assisting their child’s development, incorporating them in daily childcare and education routine (88.8%. Most respondents (65% actively seek the specialists’ advice and opinion related to  the child’s education and development as well as keep the child company at the appointments, sessions, and activities held at the centre (63.65%. A large majority (90.2% combine various types of “active” (self-inspired involvement with “passive” (specialist-inspired involvement of supportive character. Each of the parents covered by the study engages in assisting the child’s development at home according to the specialists’ recommendations, or we might say, as inspired by the specialist team. There is a need for enhancing the parents’ “active” (self-inspired involvement in the child’s situation at the centre (encouraging initiativetaking as well as the parents’ specialist-inspired involvement in the child’s situation at the centre.

Mechanisms of long-term concrete degradation in LLW disposal facilities

International Nuclear Information System (INIS)

Rogers, V.C.

1987-01-01

Most low-level waste (LLW) disposal alternatives, except shallow land burial and improved shallow land burial, involve the use of concrete as an extra barrier for containment. Because concrete is a porous-type material, its moisture retention and transport properties can be characterized with parameters that are also used to characterize the geohydrologic properties of soils. Several processes can occur with the concrete to degrade it and to increase both the movement of water and contaminants through the disposal facility. The effect of these processes must be quantified in designing and estimating the long-term performance of disposal facilities. Modeling the long-term performance of LLW disposal technologies involves, first, estimating the degradation rate of the concrete in a particular facility configuration and environmental setting; second, calculating the water flow through the facility as a function of time; third, calculating the contaminant leaching usually by diffusion or dissolution mechanisms, and then coupling the facility water and contaminant outflow to a hydrogeological and environmental uptake model for environmental releases or doses

Final report on the public involvement process phase 1, Monitored Retrievable Storage Facility Feasibility Study

Energy Technology Data Exchange (ETDEWEB)

Moore, L.; Shanteau, C.

1992-12-01

This report summarizes the pubic involvement component of Phase 1 of the Monitored Retrievable Storage Facility (NM) Feasibility Study in San Juan County, Utah. Part of this summary includes background information on the federal effort to locate a voluntary site for temporary storage of nuclear waste, how San Juan County came to be involved, and a profile of the county. The heart of the report, however, summarizes the activities within the public involvement process, and the issues raised in those various forums. The authors have made every effort to reflect accurately and thoroughly all the concerns and suggestions expressed to us during the five month process. We hope that this report itself is a successful model of partnership with the citizens of the county -- the same kind of partnership the county is seeking to develop with its constituents. Finally, this report offers some suggestions to both county officials and residents alike. These suggestions concern how decision-making about the county's future can be done by a partnership of informed citizens and listening decision-makers. In the Appendix are materials relating to the public involvement process in San Juan County.

Final report on the public involvement process phase 1, Monitored Retrievable Storage Facility Feasibility Study

Energy Technology Data Exchange (ETDEWEB)

Moore, L.; Shanteau, C.

1992-12-01

This report summarizes the pubic involvement component of Phase 1 of the Monitored Retrievable Storage Facility (NM) Feasibility Study in San Juan County, Utah. Part of this summary includes background information on the federal effort to locate a voluntary site for temporary storage of nuclear waste, how San Juan County came to be involved, and a profile of the county. The heart of the report, however, summarizes the activities within the public involvement process, and the issues raised in those various forums. The authors have made every effort to reflect accurately and thoroughly all the concerns and suggestions expressed to us during the five month process. We hope that this report itself is a successful model of partnership with the citizens of the county -- the same kind of partnership the county is seeking to develop with its constituents. Finally, this report offers some suggestions to both county officials and residents alike. These suggestions concern how decision-making about the county`s future can be done by a partnership of informed citizens and listening decision-makers. In the Appendix are materials relating to the public involvement process in San Juan County.

Final report on the public involvement process phase 1, Monitored Retrievable Storage Facility Feasibility Study

International Nuclear Information System (INIS)

Moore, L.; Shanteau, C.

1992-12-01

This report summarizes the pubic involvement component of Phase 1 of the Monitored Retrievable Storage Facility (NM) Feasibility Study in San Juan County, Utah. Part of this summary includes background information on the federal effort to locate a voluntary site for temporary storage of nuclear waste, how San Juan County came to be involved, and a profile of the county. The heart of the report, however, summarizes the activities within the public involvement process, and the issues raised in those various forums. The authors have made every effort to reflect accurately and thoroughly all the concerns and suggestions expressed to us during the five month process. We hope that this report itself is a successful model of partnership with the citizens of the county -- the same kind of partnership the county is seeking to develop with its constituents. Finally, this report offers some suggestions to both county officials and residents alike. These suggestions concern how decision-making about the county's future can be done by a partnership of informed citizens and listening decision-makers. In the Appendix are materials relating to the public involvement process in San Juan County

Education to promote verbal communication by caregivers in geriatric care facilities.

Science.gov (United States)

Fukaya, Yasuko; Koyama, Sachiyo; Kimura, Yusuke; Kitamura, Takanori

2009-12-01

Our previous study divided the verbal communication between caregivers and elderly residents at geriatric care facilities into Type I communication (to elicit activities of daily living) and Type II communication (conversation that occurs in normal social life) and found that Type II communication promotes utterances by elderly residents. This study conducted an education intervention to promote Type II talking by caregivers and evaluated the results. At three geriatric care facilities, 243 caregivers who might care for 36 elderly residents experienced training involving lectures and group discussion to understand the importance of Type II talking and how to apply it to their daily work. A statistical comparison was applied to the changes in Type II talking duration from before the intervention, 1 week after the intervention, and 3 months after the intervention to evaluate the effect of the educational intervention. At two facilities, the Type II talking duration increased significantly from before the educational intervention to 1 week after the intervention and remained higher after 3 months. However, the educational intervention's effect was not clear at one facility. There was no significant difference in the elderly persons' total utterance duration, but it increased from before the intervention to 1 week after the intervention. After the educational intervention, the amount of Type II talking by the caregivers increased significantly 1 week after the intervention for two facilities, but although the amount of Type II talking was higher at 3 months than before the intervention, it was not as high as 1 week after the intervention.

Issues related to the licensing of final disposal facilities for radioactive waste

International Nuclear Information System (INIS)

Medici, M.A.; Alvarez, D.E.; Lee Gonzales, H.; Piumetti, E.H.; Palacios, E.

2010-01-01

The licensing process of a final disposal facility for radioactive waste involves the design, construction, pre-operation, operation, closure and post closure stages. While design and pre-operational stages are, to a reasonable extent, similar to other kind of nuclear or radioactive facilities, construction, operation, closure and post-closure of a radioactive waste disposal facility have unique meanings. As consequence of that, the licensing process should incorporate these particularities. Considering the long timeframes involved at each stage of a waste disposal facility, it is convenient that the development of the project being implemented in and step by step process, be flexible enough as to adapt to new requirements that would arise as a consequence of technology improvements or due to variations in the socio-economical and political conditions. In Argentina, the regulatory Standard AR 0.1.1 establishes the general guideline for the 'Licensing of Class I facilities (relevant facilities)'. Nevertheless, for radioactive waste final disposal facilities a new specific guidance should be developed in addition to the Basic Standard mentioned. This paper describes the particularities of final disposal facilities indicating that a specific licensing system for this type of facilities should be foreseen. (authors) [es

Intelligent type sodium level gauge and its graduation calibration facility

International Nuclear Information System (INIS)

Chen Daolong; Wang Xuan; Li Xinying; Sun Huiqing; Zhu Jie

1998-04-01

The component construction and their performances of the intelligent type sodium level gauge newly-developed and its graduation calibration facility are presented. They can be operated in the temperature limit 100∼550 degree C. Its graduation characteristic calibration test is described. The temperature effect is analyzed. The graduation characteristic equation using the medium temperature as the parameter is given. The calibration errors are analyzed. The measurement system using this sodium level gauge is presented. The tests show that the intelligent type sodium level gauge possesses good linearity. The accurate sodium level measurement data can be obtained by means of its on-line compensation function of the temperature effect. Moreover, it possesses the self-inspection, the electric shutoff protection, the setting of full-scale, the thermocouple breaking alarm, the two upper limits and two lower limits alarms, the standard analog output signal and the digital output signal. Therefore, it is applicable particularly to the instrument, control and protection systems of LMFBR. The basic error of this intelligent type sodium level gauge is +-1.9% of measuring range

First lasings at IR-and FIR range using hybrid type undulator (FEL facility 4) and Halbach type undulator

International Nuclear Information System (INIS)

Takii, T.; Oshita, E.; Okuma, S.; Wakita, K.; Koga, A.; Tomimasu, T.; Ohasi, K.

1997-01-01

First lasing at 18μm was achieved by using a 2.7-m long hybrid type undulator (undulator 4) for far-infrared FELs and a 6.72-m long optical cavity installed at the 33-MeV beam line of the downstream of the FEL facility 1 (FEL-1). We are challenged at two-color FEL oscillation in mid-infrared range using the undulator 1 (λ u=3.4mm) and in far-infrared range using the undulator 4 (λ u=9mm). At first, a 30-MeV, 60-A beam passed through the undulator 1 without lasing is transported using a QFQDBQFQDBQFQDQF system and is used for lasing at the undulator 4. However, six pairs of steering coils had to be attached on the beam duct to reduce the deviation of the electron beam trajectory due to the vertical field distribution induced by the built-in electromagnets. The minimum gap of the undulator 4 was designed to be 35mm. However, the steering coils attached on the beam duct increased the gap up to 52mm. Therefore, the hybrid type undulator was replaced by a new Halbach type one (λ u=8mm, N=30) after the first lasing at 18μm on October 24, '96. The New FEL facility 4 was installed in the middle of December and first lasing at 18.6μm was achieved on December 26, within 10 hours operation. (author)

Status of RIB facilities in Asia

International Nuclear Information System (INIS)

Tanihata, Isao

1998-01-01

Radioactive Ion Beam Facilities in Asia are presented. In China, in-flight separation type facilities are in operation at the Institute of Modern Physics in Lanzhou and the other at Tandem facility in China Institute of Atomic Energy in Beijing. The storage-ring facility is proposed and approved in Lanzhou. In India, the Variable Energy Cyclotron Facility in Calcutta start to construct an ISOL-type facility. In Japan, in-flight separation type facilities are working at Research Center for Nuclear Physics in Osaka, and at RIKEN. Also a separator start its operation in medical facility in Chiba. In RIKEN, the construction of RI Beam Factory has been started. An ISOL-type facility is proposed in the Japan Hadron Facility in KEK. Table I summarize these facilities

E-SCAPE: A scale facility for liquid-metal, pool-type reactor thermal hydraulic investigations

Energy Technology Data Exchange (ETDEWEB)

Van Tichelen, Katrien, E-mail: kvtichel@sckcen.be [SCK-CEN, Boeretang 200, 2400 Mol (Belgium); Mirelli, Fabio, E-mail: fmirelli@sckcen.be [SCK-CEN, Boeretang 200, 2400 Mol (Belgium); Greco, Matteo, E-mail: mgreco@sckcen.be [SCK-CEN, Boeretang 200, 2400 Mol (Belgium); Viviani, Giorgia, E-mail: giorgiaviviani@gmail.com [University of Pisa, Lungarno Pacinotti 43, 56126 Pisa (Italy)

2015-08-15

Highlights: • The E-SCAPE facility is a thermal hydraulic scale model of the MYRRHA fast reactor. • The focus is on mixing and stratification in liquid-metal pool-type reactors. • Forced convection, natural convection and the transition are investigated. • Extensive instrumentation allows validation of computational models. • System thermal hydraulic and CFD models have been used for facility design. - Abstract: MYRRHA (Multi-purpose hYbrid Research Reactor for High-tech Applications) is a flexible fast-spectrum research reactor under design at SCK·CEN. MYRRHA is a pool-type reactor with lead bismuth eutectic (LBE) as primary coolant. The proper understanding of the thermal hydraulic phenomena occurring in the reactor pool is an important issue in the design and licensing of the MYRRHA system and liquid-metal cooled reactors by extension. Model experiments are necessary for understanding the physics, for validating experimental tools and to qualify the design for the licensing. The E-SCAPE (European SCAled Pool Experiment) facility at SCK·CEN is a thermal hydraulic 1/6-scale model of the MYRRHA reactor, with an electrical core simulator, cooled by LBE. It provides experimental feedback to the designers on the forced and natural circulation flow patterns. Moreover, it enables to validate the computational methods for their use with LBE. The paper will elaborate on the design of the E-SCAPE facility and its main parameters. Also the experimental matrix and the pre-test analysis using computational fluid dynamics (CFD) and system thermal hydraulics codes will be described.

INNOVATIVE TECHNIQUES USED BY EPA, SCDHEC, AND DOE TO INCREASE STAKEHOLDER AND PUBLIC INVOLVEMENT IN THE CLEANUP OF NUCLEAR PRODUCTION FACILITIES

International Nuclear Information System (INIS)

Mccollum, L

2007-01-01

This paper will describe the importance of public and stakeholder involvement to the decisions being made at Savannah River Site (SRS) regarding the cleanup of major production facilities. For over a decade the Department of Energy (DOE), the U.S. Environmental Protection Agency (EPA) and the South Carolina Department of Health and Environmental Control (SCDHEC) have operated under a three party agreement (known as the Federal Facilities Agreement or FFA) to clean up the SRS from the remnants of the Cold War plutonium production at SRS. During this time, the 3 agencies have consulted with the surrounding and impacted public to gain stakeholder input on the decisions concerning the clean up of various wastes at the SRS. The primary instrument of public input has been and remains the SRS Community Advisory Board (CAB). Much progress has been made over the years in cleaning up the SRS and the CAB has provided invaluable stakeholder input. Many planned decisions have been modified and changed as a result of the input of the CAB. Recently, DOE has decided to move forward with the Decommissioning of excess facilities at the SRS. These facilities include many buildings involved in the various missions of radioactive isotope production at the SRS, including the reactors and the plutonium processing facilities. The discussions of the 3 agencies on how to best accomplish this work have always included discussions about how to best involve and receive input from all stakeholders. The innovative way the 3 agencies have worked together through the public involvement format has application nationally and DOE-Complex wide. The decisions made will impact the surrounding community and the country for years. Multiple meetings with the CAB and other stakeholders will be required and it will be incumbent on the 3 agencies to reach out to and involve all interested parties. At least 3 different approaches could be used for stakeholder involvement. (1) a typical CERCLA ''proposed plan

Process for decontamination of surfaces in an facility of natural uranium hexafluoride production (UF6)

International Nuclear Information System (INIS)

Almeida, Claudio C. de; Silva, Teresinha M.; Rodrigues, Demerval L.; Carneiro, Janete C.G.G.

2017-01-01

The experience acquired in the actions taken during the decontamination process of an IPEN-CNEN / SP Nuclear and Energy Research Institute facility, for the purpose of making the site unrestricted, is reported. The steps of this operation involved: planning, training of facility operators, workplace analysis and radiometric measurements. The facility had several types of equipment from the natural uranium hexafluoride (UF 6 ) production tower and other facility materials. Rules for the transportation of radioactive materials were established, both inside and outside the facility and release of materials and installation

Types of parental involvement in CBT with anxious youth: a preliminary meta-analysis.

Science.gov (United States)

Manassis, Katharina; Lee, Trevor Changgun; Bennett, Kathryn; Zhao, Xiu Yan; Mendlowitz, Sandra; Duda, Stephanie; Saini, Michael; Wilansky, Pamela; Baer, Susan; Barrett, Paula; Bodden, Denise; Cobham, Vanessa E; Dadds, Mark R; Flannery-Schroeder, Ellen; Ginsburg, Golda; Heyne, David; Hudson, Jennifer L; Kendall, Philip C; Liber, Juliette; Masia-Warner, Carrie; Nauta, Maaike H; Rapee, Ronald M; Silverman, Wendy; Siqueland, Lynne; Spence, Susan H; Utens, Elisabeth; Wood, Jeffrey J

2014-12-01

Meta-analytic studies have not confirmed that involving parents in cognitive behavior therapy (CBT) for anxious children is therapeutically beneficial. There is also great heterogeneity in the type of parental involvement included. We investigated parental involvement focused on contingency management (CM) and transfer of control (TC) as a potential outcome moderator using a meta-analysis with individual patient data. Investigators of randomized controlled trials (RCTs) of CBT for anxious children, identified systematically, were invited to submit their data. Conditions in each RCT were coded based on type of parental involvement in CBT (i.e., low involvement, active involvement without emphasis on CM or TC, active involvement with emphasis on CM or TC). Treatment outcomes were compared using a 1-stage meta-analysis. All cases involved in active treatment (894 of 1,618) were included for subgroup analyses. Across all CBT groups, means of clinical severity, anxiety, and internalizing symptoms significantly decreased posttreatment and were comparable across groups. The group without emphasis on CM or TC showed a higher proportion with posttreatment anxiety diagnoses than the low-involvement group. Between posttreatment and 1-year follow-up, the proportion with anxiety diagnoses significantly decreased in CBT with active parental involvement with emphasis on CM or TC, whereas treatment gains were merely maintained in the other 2 groups. CBT for anxious children is an effective treatment with or without active parental involvement. However, CBT with active parental involvement emphasizing CM or TC may support long-term maintenance of treatment gains. RESULTS should be replicated as additional RCTs are published.

Design Methodology of Process Layout considering Various Equipment Types for Large scale Pyro processing Facility

International Nuclear Information System (INIS)

Yu, Seung Nam; Lee, Jong Kwang; Lee, Hyo Jik

2016-01-01

At present, each item of process equipment required for integrated processing is being examined, based on experience acquired during the Pyropocess Integrated Inactive Demonstration Facility (PRIDE) project, and considering the requirements and desired performance enhancement of KAPF as a new facility beyond PRIDE. Essentially, KAPF will be required to handle hazardous materials such as spent nuclear fuel, which must be processed in an isolated and shielded area separate from the operator location. Moreover, an inert-gas atmosphere must be maintained, because of the radiation and deliquescence of the materials. KAPF must also achieve the goal of significantly increased yearly production beyond that of the previous facility; therefore, several parts of the production line must be automated. This article presents the method considered for the conceptual design of both the production line and the overall layout of the KAPF process equipment. This study has proposed a design methodology that can be utilized as a preliminary step for the design of a hot-cell-type, large-scale facility, in which the various types of processing equipment operated by the remote handling system are integrated. The proposed methodology applies to part of the overall design procedure and contains various weaknesses. However, if the designer is required to maximize the efficiency of the installed material-handling system while considering operation restrictions and maintenance conditions, this kind of design process can accommodate the essential components that must be employed simultaneously in a general hot-cell system

Nerve ultrasound shows subclinical peripheral nerve involvement in neurofibromatosis type 2.

Science.gov (United States)

Telleman, Johan A; Stellingwerff, Menno D; Brekelmans, Geert J; Visser, Leo H

2018-02-01

Neurofibromatosis type 2 (NF2) is mainly associated with central nervous system (CNS) tumors. Peripheral nerve involvement is described in symptomatic patients, but evidence of subclinical peripheral nerve involvement is scarce. We conducted a cross-sectional pilot study in 2 asymptomatic and 3 minimally symptomatic patients with NF2 to detect subclinical peripheral nerve involvement. Patients underwent clinical examination, nerve conduction studies (NCS), and high-resolution ultrasonography (HRUS). A total of 30 schwannomas were found, divided over 20 nerve segments (33.9% of all investigated nerve segments). All patients had at least 1 schwannoma. Schwannomas were identified with HRUS in 37% of clinically unaffected nerve segments and 50% of nerve segments with normal NCS findings. HRUS shows frequent subclinical peripheral nerve involvement in NF2. Clinicians should consider peripheral nerve involvement as a cause of weakness and sensory loss in the extremities in patients with this disease. Muscle Nerve 57: 312-316, 2018. © 2017 Wiley Periodicals, Inc.

Frequency and Type of Hepatic and Gastrointestinal Involvement in Juvenile Systemic Lupus Erythematosus

Directory of Open Access Journals (Sweden)

Leila Tahernia

2017-01-01

Full Text Available Background. Systemic lupus erythematosus (SLE is a frequent rheumatology disorder among children. Since hepatic involvement is a common systemic manifestation in lupus, the frequency and type of hepatic involvement were determined in pediatric cases of SLE admitted to Children’s Medical Hospital from 2005 to 2014. Methods and Patients. In this observational case-series study, 138 pediatric cases of SLE were admitted in Children’s Medical Center (a pediatric rheumatology referral center in Tehran, Iran enrolled from 2005 to 2014 and the outcomes, frequency, and type of hepatic involvement were assessed among them. Results. Hepatic involvement was reported in 48.55% of total SLE patients. Aspartate aminotransferase (AST, alanine aminotransferase (ALT, and both enzymes higher than normal upper limits were detected in 8.7%, 5%, and 34.7% of lupus patients, respectively. Increased level of liver enzymes was categorized as less than 100, between 100 and 1000, and more than 1000 levels in 23.1%, 23.1%, and 2.1% of cases. The only gastrointestinal involvement in lupus patients contributing to hepatic involvement was gastrointestinal bleeding. Rising in liver enzymes was detected mostly in lupus patients without gastrointestinal bleeding (52.2% without versus 25.8% with gastrointestinal bleeding, P=0.007. Conclusion. Approximately half of the pediatric patients suffering from SLE have hepatic involvement. No significant correlation was observed between various organs involvement and abnormal level of liver enzymes.

Automated methodology for estimating waste streams generated from decommissioning contaminated facilities

International Nuclear Information System (INIS)

Toth, J.J.; King, D.A.; Humphreys, K.K.; Haffner, D.R.

1994-01-01

As part of the DOE Programmatic Environmental Impact Statement (PEIS), a viable way to determine aggregate waste volumes, cost, and direct labor hours for decommissioning and decontaminating facilities is required. In this paper, a methodology is provided for determining waste streams, cost and direct labor hours from remediation of contaminated facilities. The method is developed utilizing U.S. facility remediation data and information from several decommissioning programs, including reactor decommissioning projects. The method provides for rapid, consistent analysis for many facility types. Three remediation scenarios are considered for facility D ampersand D: unrestricted land use, semi-restricted land use, and restricted land use. Unrestricted land use involves removing radioactive components, decontaminating the building surfaces, and demolishing the remaining structure. Semi-restricted land use involves removing transuranic contamination and immobilizing the contamination on-site. Restricted land use involves removing the transuranic contamination and leaving the building standing. In both semi-restricted and restricted land use scenarios, verification of containment with environmental monitoring is required. To use the methodology, facilities are placed in a building category depending upon the level of contamination, construction design, and function of the building. Unit volume and unit area waste generation factors are used to calculate waste volumes and estimate the amount of waste generated in each of the following classifications: low-level, transuranic, and hazardous waste. Unit factors for cost and labor hours are also applied to the result to estimate D ampersand D cost and labor hours

Studies involving proposed waste disposal facilities in Turkey

International Nuclear Information System (INIS)

Uslu, I.; Fields, D.E.; Yalcintas, M.G.

1987-01-01

Today principal sources of radioactive wastes are hospitals, research institutions, biological research centers, universities, industries and two research reactors in Turkey. These wastes will be treated in a pilot waste treatment facility located in Cekmece Nuclear Research and Training Center, Istanbul. In this temporary waste disposal facility, the wastes will be stored in 200 liter concrete containers until the establishment of the permanent waste disposal sites in Turkey, in 1990. The PRESTO - II (Prediction of Radiation Effects From Shallow Trench Operations) computer code was applied for the general probable sites for LLW disposal in Turkey. The model is non-site specific screening model for assessing radionuclide transport, ensuring exposure, and health impacts to a static local population for a chosen time period, following the end of the disposal operation. The methodology that this codes takes into consideration is versatile and explicitly considers infiltration and percolation of surface water into the trench, leaching of radionuclides, vertical and horizontal transport of radionuclides and use of this contaminated ground water for farming, irrigation, and ingestion

Comparison and discussion of two types of threat (Hazard) categorization method for nuclear facilities

International Nuclear Information System (INIS)

Tang, Rongyao; Xu, Xiaoxiao; Zhang, Jiangang; Zhao, Bin

2008-01-01

The emergency threat categorization method suggested by international atomic energy agency (IAEA) and hazard categorization standard by the Department of Energy of United States (USDOE) for nuclear facilities are compared and discussed in this paper. The research shows the two types of categorization method for nuclear facility are similar, though each has its own speciality. The categorization method suggested by IAEA is quite completed and sound in scientific basis. The thresholds of radioactive material are connected with the quantity of dangerous source, and the latest radiobiological effect research results are taken in setting the thresholds. While the main purpose is put on emergency management, some of the categorization criteria do not fit for safety surveillance of nuclear facilities. The categorization method of DOE is advanced in its operability, and it fits for safety surveillance. The disadvantage is that the thresholds of radioactive material need to be updated because the parameters used in calculation is outdated, and also the threshold of category 3 is somewhat disputable for many reasons. We should take advantage of both methods and adjust the standards according to the application purpose while establishing the categorization standard of nuclear facilities in China. (author)

Buffer Construction Methodology in Demonstration Test For Cavern Type Disposal Facility

International Nuclear Information System (INIS)

Yoshihiro, Akiyama; Takahiro, Nakajima; Katsuhide, Matsumura; Kenji, Terada; Takao, Tsuboya; Kazuhiro, Onuma; Tadafumi, Fujiwara

2009-01-01

A number of studies concerning a cavern type disposal facility have been carried out for disposal of low level radioactive waste mainly generated by power plant decommissioning in Japan. The disposal facility is composed of an engineered barrier system with concrete pit and bentonite buffer, and planed to be constructed in sub-surface 50 - 100 meters depth. Though the previous studies have mainly used laboratory and mock-up tests, we conducted a demonstration test in a full-size cavern. The main objectives of the test were to study the construction methodology and to confirm the quality of the engineered barrier system. The demonstration test was planned as the construction of full scale mock-up. It was focused on a buffer construction test to evaluate the construction methodology and quality control in this paper. Bentonite material was compacted to 1.6 Mg/m 3 in-site by large vibrating roller in this test. Through the construction of the buffer part, a 1.6 Mg/m 3 of the density was accomplished, and the data of workability and quality is collected. (authors)

Efficiency improvement of the investment and innovation activities in the transport facility construction field with public-private partnership involvement

Science.gov (United States)

Shibayeva, Marina; Serebryakova, Yelena; Shalnev, Oleg

2017-10-01

Growing demand to increase the investment volume in modernization and development projects for transport infrastructure define the urgency of the current study. The amount of private sector investments in the field is insufficient to implement the projects for road construction due to their significant capital intensity and long payoff period. The implementation of social significant infrastructure projects on the principles of public-private partnership is one of the key strategic directions of growth for transport facilities. The authors come up with a concept and methodology for modeling the investment and innovation activity in the transport facility construction. Furthermore, there is developed a model to find the balance between public and private sector investments in implementing construction projects for transport infrastructure with involvement of PPP (further - public-private partnership). The suggested concepts aim to improve the efficiency rate of the investment and innovation activity in the field of transport facility construction on the basis of public and private sectors collaboration.

Results of 15 years experiments in the PMK-2 integral-type facility for VVERs

Energy Technology Data Exchange (ETDEWEB)

Szabados, L.; Ezsoel, G.; Perneczky, L. [KFKI Atomic Energy Research Institute, Budapest (Hungary)

2001-07-01

Due to the specific features of the VVER-440/213-type reactors the transient behaviour of such a reactor system is different from the usual PWR system behaviour. To provide an experimental database for the transient behaviour of VVER systems the PMK integral-type facility, the scaled down model of the Paks NPP was designed and constructed in the early 1980's. Since the start-up of the facility 48 experiments have been performed. It was confirmed through the experiments that the facility is a suitable tool for the computer code validation experiments and to the identification of basic thermal-hydraulic phenomena occurring during plant accidents. High international interest was shown by the four Standard Problem Exercises of the IAEA and by the projects financed by the EU-PHARE. A wide range of small- and medium-size LOCA sequences have been studied to know the performance and effectiveness of ECC systems and to evaluate the thermal-hydraulic safety of the core. Extensive studies have been performed to investigate the one- and two-phase natural circulation, the effect of disturbances coming from the secondary circuit and to validate the effectiveness of accident management measures like bleed and feed. The VVER-specific case, the opening of the SG collector cover was also extensively investigated. Examples given in the report show a few results of experiments and the results of calculation analyses performed for validation purposes of codes like RELAP5, ATHLET and CATHARE. There are some other white spots in Cross Reference Matrices for VVER reactors and, therefore, further experiments are planned to perform tests primarily in further support of accident management measures at low power states of plants to facilitate the improved safety management of VVER-440-type reactors. (authors)

Results of 15 years experiments in the PMK-2 integral-type facility for VVERs

International Nuclear Information System (INIS)

Szabados, L.; Ezsoel, G.; Perneczky, L.

2001-01-01

Due to the specific features of the VVER-440/213-type reactors the transient behaviour of such a reactor system is different from the usual PWR system behaviour. To provide an experimental database for the transient behaviour of VVER systems the PMK integral-type facility, the scaled down model of the Paks NPP was designed and constructed in the early 1980's. Since the start-up of the facility 48 experiments have been performed. It was confirmed through the experiments that the facility is a suitable tool for the computer code validation experiments and to the identification of basic thermal-hydraulic phenomena occurring during plant accidents. High international interest was shown by the four Standard Problem Exercises of the IAEA and by the projects financed by the EU-PHARE. A wide range of small- and medium-size LOCA sequences have been studied to know the performance and effectiveness of ECC systems and to evaluate the thermal-hydraulic safety of the core. Extensive studies have been performed to investigate the one- and two-phase natural circulation, the effect of disturbances coming from the secondary circuit and to validate the effectiveness of accident management measures like bleed and feed. The VVER-specific case, the opening of the SG collector cover was also extensively investigated. Examples given in the report show a few results of experiments and the results of calculation analyses performed for validation purposes of codes like RELAP5, ATHLET and CATHARE. There are some other white spots in Cross Reference Matrices for VVER reactors and, therefore, further experiments are planned to perform tests primarily in further support of accident management measures at low power states of plants to facilitate the improved safety management of VVER-440-type reactors. (authors)

43 CFR 404.9 - What types of infrastructure and facilities may be included in an eligible rural water supply...

Science.gov (United States)

2010-10-01

... facilities may be included in an eligible rural water supply project? 404.9 Section 404.9 Public Lands... RURAL WATER SUPPLY PROGRAM Overview § 404.9 What types of infrastructure and facilities may be included in an eligible rural water supply project? A rural water supply project may include, but is not...

25 CFR 900.234 - What types of personal conflicts of interest involving tribal officers, employees or...

Science.gov (United States)

2010-04-01

... 25 Indians 2 2010-04-01 2010-04-01 false What types of personal conflicts of interest involving... ASSISTANCE ACT Conflicts of Interest § 900.234 What types of personal conflicts of interest involving tribal... in which that person has a financial or employment interest that conflicts with that of the trust...

Standard Guide for Preparing Characterization Plans for Decommissioning Nuclear Facilities

CERN Document Server

American Society for Testing and Materials. Philadelphia

2009-01-01

1.1 This standard guide applies to developing nuclear facility characterization plans to define the type, magnitude, location, and extent of radiological and chemical contamination within the facility to allow decommissioning planning. This guide amplifies guidance regarding facility characterization indicated in ASTM Standard E 1281 on Nuclear Facility Decommissioning Plans. This guide does not address the methodology necessary to release a facility or site for unconditional use. This guide specifically addresses: 1.1.1 the data quality objective for characterization as an initial step in decommissioning planning. 1.1.2 sampling methods, 1.1.3 the logic involved (statistical design) to ensure adequate characterization for decommissioning purposes; and 1.1.4 essential documentation of the characterization information. 1.2 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate saf...

Facility effluent monitoring plan for 242-A Evaporator facility

International Nuclear Information System (INIS)

Crummel, G.M.; Gustavson, R.D.

1993-03-01

A facility effluent monitoring plan is required by the US Department of Energy in DOE Order 5400.1* for any operations that involve hazardous materials and radioactive substances that could affect employee or public safety or the environment. A facility effluent monitoring plan determination was performed during Calendar Year 1991 and the evaluation showed the need for a facility effluent monitoring plan. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility effluent Monitoring Plans, WHC-EP-0438-1**. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements

Demonstration test of underground cavern-type disposal facilities, fiscal 2010 status - 59180

International Nuclear Information System (INIS)

Akiyama, Yoshihiro; Terada, Kenji; Oda, Nobuaki; Yada, Tsutomu; Nakajima, Takahiro

2012-01-01

A test to demonstrate practical construction technology for underground cavern-type disposal facilities is currently underway. Cavern-type disposal facilities are a radioactive waste repository excavated to a depth of 50 to 100 m below ground and constructed with an engineered barrier system (EBS) that is a combination of low-permeable bentonite material and low-diffusive cementitious material. The disposed materials are low-level radioactive waste with relatively high radioactivity, mainly generated from power reactor decommissioning, and certain transuranic wastes that are mainly generated from spent fuel reprocessing. The project started in fiscal 2005*, and since fiscal 2007 a full-scale mock-up of a disposal facility has been constructed in an actual sub-surface environment. The main objective of the demonstration test is to establish construction procedures and methods which ensure the required quality of an EBS on-site. Certain component parts of the facility had been constructed in an underground cavern by fiscal 2010, and tests so far have demonstrated both the practicability of the construction and the achievement of the required quality. This paper covers the project outline and the test results obtained by the construction of certain EBS components. The following results were obtained from the construction test of EBS in the test cavern: 1) The dry density of bentonite buffer at the lower layer constructed by vibratory compaction shows that 95% of core samples have densities within the target range. 2) The specified mix for the low-diffusion layer has uniform density and crack-control properties, and meets the requirements for diffusion performance. 3) The specified mix of the concrete pit has sufficient passing ability through congested reinforcement and meets the requirements of strength performance. 4) The dry density of the bentonite buffer at the lateral layer constructed by the spraying method shows that 65% of the core samples are within the

Studies involving proposed waste disposal facilities in Turkey

International Nuclear Information System (INIS)

Uslu, I.; Fields, D.E.; Yalcintas, M.G.

1987-01-01

The Turkish government is in the process of planning two nuclear reactors in Turkey. The Turkish Atomic Energy Authority has been given the task of developing plans for improved control of low-level wastes (LLW) in Turkey. Principal sources of radioactive wastes are hospitals, research institutions, biological research centers, universities, industries, and two research reactors in Turkey. These wastes will be treated in a pilot water treatment facility located in Cekmece Nuclear Research and Training Center, Istanbul. In this temporary waste disposal facility, the wastes will be stored in 200-l concrete containers until the establishment of the permanent waste disposal sites in Turkey in 1990. The PRESTO-II (prediction of radiation effects from shallow trench operations) computer code has been applied for the general probable sites for LLW disposal in Turkey. The model is intended to serve as a non-site-specific screening model for assessing radionuclide transport, ensuring exposure, and health impacts to a static local population for a chosen time period, following the end of the disposal operation. The methodology that this code takes into consideration is versatile and explicitly considers infiltration and percolation of surface water into the trench, leaching of radionuclides, vertical and horizontal transport of radionuclides, and use of this contaminated ground water for farming, irrigation, and ingestion

Disordered gambling, type of gambling and gambling involvement in the British Gambling Prevalence Survey 2007

OpenAIRE

LaPlante, Debi A.; Nelson, Sarah E.; LaBrie, Richard A.; Shaffer, Howard J.

2009-01-01

Background: The purpose of this study was to examine the relationships between types of gambling and disordered gambling, with and without controlling for gambling involvement (i.e. the number of types of games with which respondents were involved during the past 12 months). Methods: We completed a secondary data analysis of the 2007 British Gambling Prevalence Survey (BGPS), which collected data in England, Scotland and Wales between September 2006 and March 2007. The sample included 9003 re...

Emission Facilities - Air Emission Plants

Data.gov (United States)

NSGIC Education | GIS Inventory — Represents the Primary Facility type Air Emission Plant (AEP) point features. Air Emissions Plant is a DEP primary facility type related to the Air Quality Program....

Health physics considerations at a neutron therapy facility cyclotron

International Nuclear Information System (INIS)

Kleck, J.H.; Krueger, D.J.; Mc Laughlin, J.E.; Smathers, J.B.

1987-01-01

The U.C.L.A. Neutron Therapy Facility (NTF) is one of four such facilities in the United States currently involved in NCI sponsored trials of neutron therapy and reflects the present interest in the use of high energy neutron beams for treating certain types of human cancers. The NTF houses a CP-45 negative ion cyclotron which accelerates a 46 MeV proton beam for production of neutrons from a beryllium target. In addition to patient treatment, the NTF is involved in the production of positron emitting radioisotopes for diagnostic use in Positron Emission Tomography (PET). The activation of therapy treatment collimators, positron and neutron target systems, and a high and rapidly varying external radiation environment in a clinical setting have contributed to the need for a comprehensive radiation control program in which patient care is balanced with the maintenance of occupational exposures to ALARA levels

Facility effluent monitoring plan for the fast flux test facility

International Nuclear Information System (INIS)

Nickels, J.M.; Dahl, N.R.

1992-11-01

A facility effluent monitoring plan is required by the US Department of Energy in US Department of Energy Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could affect employee or public safety or the environment. A Facility Effluent Monitoring Plan determination was performed during calendar year 1991 and the evaluation requires the need for a facility effluent monitoring plan. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements

Enhancing Efficiency of Safeguards at Facilities that are Shutdown or Closed-Down, including those being Decommissioned

Energy Technology Data Exchange (ETDEWEB)

Moran, B. [Brookhaven National Lab. (BNL), Upton, NY (United States); Stern, W. [Brookhaven National Lab. (BNL), Upton, NY (United States); Colley, J. [Brookhaven National Lab. (BNL), Upton, NY (United States); Marzo, M. [Brookhaven National Lab. (BNL), Upton, NY (United States)

2016-12-15

International Atomic Energy Agency (IAEA) safeguards involves verification activities at a wide range of facilities in a variety of operational phases (e.g., under construction, start-up, operating, shutdown, closed-down, and decommissioned). Safeguards optimization for each different facility type and operational phase is essential for the effectiveness of safeguards implementation. The IAEA’s current guidance regarding safeguards for the different facility types in the various lifecycle phases is provided in its Design Information Examination (DIE) and Verification (DIV) procedure. 1 Greater efficiency in safeguarding facilities that are shut down or closed down, including those being decommissioned, could allow the IAEA to use a greater portion of its effort to conduct other verification activities. Consequently, the National Nuclear Security Administration’s Office of International Nuclear Safeguards sponsored this study to evaluate whether there is an opportunity to optimize safeguards approaches for facilities that are shutdown or closed-down. The purpose of this paper is to examine existing safeguards approaches for shutdown and closed-down facilities, including facilities being decommissioned, and to seek to identify whether they may be optimized.

Parenting goals: predictors of parent involvement in disease management of children with type 1 diabetes.

Science.gov (United States)

Robinson, Elizabeth M; Iannotti, Ronald J; Schneider, Stefan; Nansel, Tonja R; Haynie, Denise L; Sobel, Douglas O

2011-09-01

The purpose of this study was to develop a measure of diabetes-specific parenting goals for parents of children with type 1 diabetes and to examine whether parenting goals predict a change in parenting involvement in disease management. An independent sample of primary caretakers of 87 children aged 10 to 16 years with type 1 diabetes completed the measure of parenting goals (diabetes-specific and general goals); both parent and child completed measures of parent responsibility for diabetes management at baseline and 6 months. Parents ranked diabetes-specific parenting goals as more important than general parenting goals, and rankings were moderately stable over time. Parenting goals were related to parent responsibility for diabetes management. The relative ranking of diabetes-specific parenting goals predicted changes in parent involvement over 6 months, with baseline ranking of goals predicting more parental involvement at follow-up. Parenting goals may play an important role in family management of type 1 diabetes.

Facility effluent monitoring plan for the plutonium-uranium extraction facility

International Nuclear Information System (INIS)

Nickels, J.M.; Geiger, J.L.

1992-11-01

A facility effluent monitoring plan is required by the US Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. A facility effluent monitoring plan determination was performed during Calendar Year 1991 and the evaluation requires the need for a facility effluent monitoring plan. This document is prepared using the specific guidelines identified. in. A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements

Activity involvement and quality of life of people at different stages of dementia in long term care facilities.

Science.gov (United States)

Smit, Dieneke; de Lange, Jacomine; Willemse, Bernadette; Twisk, Jos; Pot, Anne Margriet

2016-01-01

Involvement in activities is assumed to positively influence the quality of life of people with dementia, yet activity provision in long-term care remains limited. This study aims to provide more insight into the value of activity involvement for domains of the quality of life of long-term dementia care residents, taking resident characteristics and cognitive status into account. Data were derived from 144 long-term care facilities participating in the second measurement (2010/2011) of the living arrangements for dementia study. Amongst 1144 residents, the relationship between time involved in activities (activity pursuit patterns; RAI-MDS) and quality of life (Qualidem) was studied using multilevel linear regression analyses. Analyses were adjusted for residents' age, gender, neuropsychiatric symptoms, ADL dependency and cognition. To check for effect modification of cognition, interactions terms of the variables activity involvement and cognitive status were added to the analyses. Despite resident's cognitive status, their activity involvement was significantly related to better scores on care relationship, positive affect, restless tense behaviour, social relations, and having something to do. A negative relationship existed between the activity involvement and positive self-image. The explained variance in the quality of life between residents caused by the activity involvement was small. Activity involvement seems to be a small yet important contributor to higher well-being in long-term care resident at all stages of dementia. Adjusting activities to individual preferences and capabilities might enlarge this relationship. Further research is needed to confirm this hypothesis, using measurement instruments less sensitive to recall bias and differentiating between the active and passive activity involvement.

Facility effluent monitoring plan for the tank farm facility

Energy Technology Data Exchange (ETDEWEB)

Crummel, G.M.

1998-05-18

A facility effluent monitoring plan is required by the US Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements.

Audits of radiation sterilization facilities

International Nuclear Information System (INIS)

Kelkar, Prabhakar M.

2001-01-01

Johnson and Johnson is the world leader in sterilization science and technology. A special group of scientists and technologists are engaged in the development of new methods of sterilization, worldwide monitoring of sterilization processes, equipment and approvals for all types of sterilization processes. Kilmer Conference in the alternate year for the benefit of all those involved in improvement in sterilization science is held. Cobalt-60 gamma radiation for sterilization of medical products on commercial scale is used. This kind of mammoth task can only be achieved through systematic method of planning, auditing, expert review and approval of facilities

Restraint effect of water infiltration by soil cover types of LLW disposal facility

International Nuclear Information System (INIS)

Park, S. M.; Lee, E. Y.; Lee, C. K.; Kim, C. L.

2002-01-01

Since soil cover for LLW disposal vault shows quite different restraint effect of water infiltration depending on its type, four different types of soil cover were studied and simulated using HELP code. Simulation result showed that Profile B1 is the most effective type in restraint of water infiltration to the disposal vault. Profile B1 is totally 6m thick and composed of silt, gravelly sand, pea gravel, sand and clayey soil mixed with bentonite 20%. Profile B1 also includes artificial layers, such as asphalt and geomembrane layers. This profile is designed conceptually by NETEC for the soil cover of the near surface disposal facility of the low-level radioactive waste. For comparison, 3 types of different profile were tested. One profile includes bentonite mixed layer only as water barrier layer, or one as same as profile B1 but without geomembrane layer or one without asphalt layer respectively. The simulation using HELP code showed that the water balance in profile B1 was effectively controlled

Safety of laboratories, plants, facilities being dismantled, waste processing, interim storage and disposal facilities. Lessons learned from events reported in 2009 and 2010

International Nuclear Information System (INIS)

2013-01-01

This report presents the cross-disciplinary analysis performed by IRSN relating to significant events reported to the French Nuclear Safety Authority (ASN) during 2009 - 2010 for LUDD-type facilities (laboratories, plants, facilities being dismantled, and waste processing, interim storage and disposal facilities). It constitutes a follow-up to DSU Report 215 published in December 2009, relating to events reported to ASN during 2005 to 2008. The main developments observed since the analysis presented in that report have been underlined here, in order to highlight improvements, opportunities for progress and the main areas requiring careful attention. The present report is a continuation of DSU Report 215. Without claiming to be exhaustive, it presents lessons from IRSN's cross-disciplinary analysis of events reported to ASN during 2009 and 2010 at LUDD facilities while highlighting major changes from the previous analysis in order to underline improvements, areas where progress has been made, and main points for monitoring. The report has four sections: - the first gives a brief introduction to the various kinds of LUDD facilities and highlights changes with DSU Report 215; - the second provides a summary of major trends involving events reported to ASN during 2007-2010 as well as overall results of consequences of events reported during 2009 and 2010 for workers, the general public and the environment; - the third section gives a cross-disciplinary analysis of significant events reported during 2009 and 2010, performed from two complementary angles (analysis of main types of events grouped by type of risk and analysis of generic causes). Main changes from the analysis given in DSU Report 215 are considered in detail; - the last section describes selected significant events that occurred in 2009 and 2010 in order to illustrate the cross-disciplinary analysis with concrete examples. IRSN will publish this type of report periodically in coming years in order to

Decommissioning: guiding principles and best practices for involving local stakeholders

International Nuclear Information System (INIS)

Keyes, D.

2005-01-01

Full text: A wide range of nuclear facilities covering the entire nuclear fuel cycle have been constructed and operated for many years worldwide. For communities where the facilities are located, concerns about safety and environmental contamination are paramount. Working together with elected officials, local community leaders and the public at large during the earliest planning stages will help alleviate concerns about facility operation and ultimate disposition, and will result in better decisions about facility design, location, construction, operation and, ultimately, decommissioning. Such comprehensive community involvement has been the exception rather than the norm. Now that older facilities are being considered for decommissioning, efforts to involve local stakeholders and alleviate their concerns face major challenges. This is particularly true where some residual radioactive contamination will remain onsite and future use of the site may need to be restricted. Plans for stakeholder involvement at the decommissioning stage should be carefully designed and provide for honest, authentic and meaningful involvement of all stakeholders affected by decommissioning decisions. A set of principles and best practices is proposed to help guide the design and implementation of effective community involvement programs. The principles and best practices are drawn from the experiences of public involvement practitioners in a variety of environmental contamination applications. Successful community involvement is the result of a carefully crafted set of coordinated activities conducted over the long term. Ideally, facility decommissioning is simply the end stage of the involvement process, or the beginning of a site stewardship process in those cases where decommissioning does not produce an uncontaminated site. In either case, decommissioning will not be a new, unexpected event, and stakeholders could be involved just as they have been over the life of the facility. In

Formation of wood secondary cell wall may involve two type cellulose synthase complexes in Populus.

Science.gov (United States)

Xi, Wang; Song, Dongliang; Sun, Jiayan; Shen, Junhui; Li, Laigeng

2017-03-01

Cellulose biosynthesis is mediated by cellulose synthases (CesAs), which constitute into rosette-like cellulose synthase complexe (CSC) on the plasma membrane. Two types of CSCs in Arabidopsis are believed to be involved in cellulose synthesis in the primary cell wall and secondary cell walls, respectively. In this work, we found that the two type CSCs participated cellulose biosynthesis in differentiating xylem cells undergoing secondary cell wall thickening in Populus. During the cell wall thickening process, expression of one type CSC genes increased while expression of the other type CSC genes decreased. Suppression of different type CSC genes both affected the wall-thickening and disrupted the multilaminar structure of the secondary cell walls. When CesA7A was suppressed, crystalline cellulose content was reduced, which, however, showed an increase when CesA3D was suppressed. The CesA suppression also affected cellulose digestibility of the wood cell walls. The results suggest that two type CSCs are involved in coordinating the cellulose biosynthesis in formation of the multilaminar structure in Populus wood secondary cell walls.

Partnership Selection Involving Mixed Types of Uncertain Preferences

Directory of Open Access Journals (Sweden)

Li-Ching Ma

2013-01-01

Full Text Available Partnership selection is an important issue in management science. This study proposes a general model based on mixed integer programming and goal-programming analytic hierarchy process (GP-AHP to solve partnership selection problems involving mixed types of uncertain or inconsistent preferences. The proposed approach is designed to deal with crisp, interval, step, fuzzy, or mixed comparison preferences, derive crisp priorities, and improve multiple solution problems. The degree of fulfillment of a decision maker’s preferences is also taken into account. The results show that the proposed approach keeps more solution ratios within the given preferred intervals and yields less deviation. In addition, the proposed approach can treat incomplete preference matrices with flexibility in reducing the number of pairwise comparisons required and can also be conveniently developed into a decision support system.

Factors associated with hypoglycemia episodes in hospitalized type ...

African Journals Online (AJOL)

Purpose: To determine the factors associated with severity of hypoglycemia in hospitalized type 2 diabetes mellitus patients in a tertiary health facility in Malaysia. Methods: This retrospective study involved 207 hospitalised T2DM patients with hypoglycaemia episodes from January 2008 to December 2012 and was ...

Durability of spent nuclear fuels and facility components in wet storage

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-04-01

Wet storage continues to be the dominant option for the management of irradiated fuel elements and assemblies (fuel units). Fuel types addressed in this study include those used in: power reactors, research and test reactors, and defence reactors. Important decisions must be made regarding acceptable storage modes for a broad variety of fuel types, involving numerous combinations of fuel and cladding materials. A broadly based materials database has the following important functions: to facilitate solutions to immediate and pressing materials problems; to facilitate decisions on the most effective long term interim storage methods for numerous fuel types; to maintain and update a basis on which to extend the licenses of storage facilities as regulatory periods expire; to facilitate cost-effective transfer of numerous fuel types to final disposal. Because examinations of radioactive materials are expensive, access to materials data and experience that provide an informed basis to analyse and extrapolate materials behaviour in wet storage environments can facilitate identification of cost-effective approaches to develop and maintain a valuable materials database. Fuel storage options include: leaving the fuel in wet storage, placing the fuel in canisters with cover gases, stored underwater, or transferring the fuel to one of several dry storage modes, involving a range of conditioning options. It is also important to anticipate the condition of the various materials as periods of wet storage are extended or as decisions to transfer to dry storage are implemented. A sound basis for extrapolation is needed to assess fuel and facility component integrity over the expected period of wet storage. A materials database also facilitates assessment of the current condition of specific fuel and facility materials, with minimal investments in direct examinations. This report provides quantitative and semi-quantitative data on materials behaviour or references sources of data to

Durability of spent nuclear fuels and facility components in wet storage

International Nuclear Information System (INIS)

1998-04-01

Wet storage continues to be the dominant option for the management of irradiated fuel elements and assemblies (fuel units). Fuel types addressed in this study include those used in: power reactors, research and test reactors, and defence reactors. Important decisions must be made regarding acceptable storage modes for a broad variety of fuel types, involving numerous combinations of fuel and cladding materials. A broadly based materials database has the following important functions: to facilitate solutions to immediate and pressing materials problems; to facilitate decisions on the most effective long term interim storage methods for numerous fuel types; to maintain and update a basis on which to extend the licenses of storage facilities as regulatory periods expire; to facilitate cost-effective transfer of numerous fuel types to final disposal. Because examinations of radioactive materials are expensive, access to materials data and experience that provide an informed basis to analyse and extrapolate materials behaviour in wet storage environments can facilitate identification of cost-effective approaches to develop and maintain a valuable materials database. Fuel storage options include: leaving the fuel in wet storage, placing the fuel in canisters with cover gases, stored underwater, or transferring the fuel to one of several dry storage modes, involving a range of conditioning options. It is also important to anticipate the condition of the various materials as periods of wet storage are extended or as decisions to transfer to dry storage are implemented. A sound basis for extrapolation is needed to assess fuel and facility component integrity over the expected period of wet storage. A materials database also facilitates assessment of the current condition of specific fuel and facility materials, with minimal investments in direct examinations. This report provides quantitative and semi-quantitative data on materials behaviour or references sources of data to

PMK-2 the Hungarian integral type test facility. Documentations, publications and archivations of experiments

International Nuclear Information System (INIS)

Perneczky, L.; Guba, A.; Ezsoel, G.; Toth, I.; Szabados, L.

2002-01-01

The PMK-2 experimental facility at the KFKI-AEKI, Budapest, is a full pressure, scaled down model of the primary and partly the secondary circuit of the Paks NPP, which is equipped with four VVER-440/213-type reactors. Since the start-up of the facility altogether 48 experiments have been performed for groups of transients as follows: one- and two-phase natural circulation, loss of coolant accidents, special plant transients and experiments in support of accident management procedures. The results have been used for the validation of thermal-hydraulic system codes for VVER applications. Following the experiments a detailed documentation and archiving activity - using an optimised data storage - was required to preserve the essential information and to assure these for a widely utilisation for the international nuclear community. In the publication list related to the facility and the experiments for the moment altogether 280 items - documents, articles in periodicals, papers in proceedings and research reports - in six languages were collected. The paper gives an overview on this activity including the participation in the EU CERTA-TN programme, where AEKI introduced representative databases of two PMK-2 tests in the STRESA Network.(author)

Decommissioning of Nuclear Facilities: Training and Human Resource Considerations

International Nuclear Information System (INIS)

2008-01-01

One of the cornerstones of the success of nuclear facility decommissioning is the adequate competence of personnel involved in decommissioning activities. The purpose of this publication is to provide methodological guidance for, and specific examples of good practices in training as an integral part of human resource management for the personnel performing decommissioning activities. The use of the systematic methodology and techniques described in this publication may be tailored and applied to the development of training for all types of nuclear facilities undergoing decommissioning. Examples of good practices in other aspects of human resources, such as knowledge preservation, management of the workforce and improvement of human performance, are also covered. The information contained in this publication, and the examples provided in the appendices and enclosed CD-ROM, are representative of the experience of decommissioning of a wide variety of nuclear facilities.

Fathers of children with Down's syndrome versus other types of intellectual disability: perceptions, stress and involvement.

Science.gov (United States)

Ricci, L A; Hodapp, R M

2003-01-01

The present study examined fathers' perceptions of, stress relating to and involvement with children with Down's syndrome (DS) (n = 30) versus those with other types of intellectual disability (ID) (n = 20). Fathers and mothers completed questionnaires about their children's personalities and maladaptive behaviours, their own parenting stress, and the fathers' level of involvement. Both fathers and mothers rated their children with DS as having more positive personality traits and fewer maladaptive behaviours. Possibly because of these positive perceptions, fathers of children with DS also reported less child-related stress, particularly in the areas of acceptability, adaptability and demandingness. The two groups of fathers were very similarly involved in child rearing. The personality, age and maladaptive behaviours of the children related to stress levels in the fathers of children with DS, while maladaptive behaviours, gender and the fathers' education levels related to stress levels in the fathers of children with other types of ID. These results highlight the importance of examining parental stress and involvement with children with different types of ID.

The effects of involvement and ad type on attitudes toward direct-to-consumer advertising of prescription drugs.

Science.gov (United States)

Limbu, Yam; Torres, Ivonne M

2009-01-01

This article examines consumers' attitudes toward Direct-to-Consumer (DTC) advertising of prescription drugs that are influenced by the use different types of DTC ads and product involvement. Our findings suggest that product involvement and the type of DTC ad are significant predictors of consumers' attitudinal responses toward DTC advertising. High involvement consumers have more favorable attitudes toward the drug's price, DTC ad and brand name, and a higher intention to ask a doctor about the advertised drug than low involvement consumers. In contrast to Informational and Reminder DTC ads, Persuasive ads have more favorable effects on consumers' reactions to DTC prescription drug advertising.

National Solar Thermal Test Facility

Data.gov (United States)

Federal Laboratory Consortium — The National Solar Thermal Test Facility (NSTTF) is the only test facility in the United States of its type. This unique facility provides experimental engineering...

Assessment of the radiological risks of road transport accidents involving Type A packages

International Nuclear Information System (INIS)

Lange, F.; Fett, H.J.; Schwarz, G.; Raffestin, D.; Schneider, T.; Gelder, R.; S. Hughes, J.; B. Shaw, K.; Hedberg, B.; Simenstad, P.; Svahn, B.; Heinen, J.F.A. van; Jansma, R.

2001-01-01

An assessment and evaluation of the potential radiological risks of transport accidents involving Type A package shipments by road have been performed by five EU Member States, France, Germany, Sweden, The Netherlands, and the UK. The analysis involved collection and analysis of information on a national basis related to the type, volume, and characteristics of Type A package consignments, the associated radioactive traffic, and the expected frequency and consequences of potential vehicular road transport accidents. It was found that the majority of Type A packaged radioactive material shipments by road is related to applications of non-special form radioactive material, i.e. radiopharmaceuticals, radiochemicals etc., in medicine, research, and industry and special form material contained in radiography and other radiation sources, e.g. gauging equipment. The annual volumes of Type A package shipments of radiopharmaceuticals and radiochemicals by road differ considerably between the participating EU Member States from about 12,000 Type A packages in Sweden to about 240,000 in the Netherlands. The broad range reflects to a large extent the supply of radioactive material for the national populations and the production and distribution operations prevailing in the participating EU Member States (some are producer countries, others are not!). Very few standard package designs weighing from about 1-25 kg are predominant in Type A package shipments in all participating countries. Type A packages contain typically a range of radioactivity from a few mega becquerels to a few tens of giga becquerels, the average package activity contents is in terms of fractions of A 2 about 0.01, i.e. about one hundredth of a Type A package contents limits. Based on a probabilistic risk assessment method it has been concluded that the expected frequencies of occurrence of vehicular road transport accidents with the potential to result in an environmental release - including radiologically

Facility of aerosol filtration

Energy Technology Data Exchange (ETDEWEB)

Duverger de Cuy, G; Regnier, J

1975-04-18

Said invention relates to a facility of aerosol filtration, particularly of sodium aerosols. Said facility is of special interest for fast reactors where sodium fires involve the possibility of high concentrations of sodium aerosols which soon clog up conventional filters. The facility intended for continuous operation, includes at the pre-filtering stage, means for increasing the size of the aerosol particles and separating clustered particles (cyclone separator).

Progression of cardiac involvement in patients with limb-girdle type 2 and Becker muscular dystrophies

DEFF Research Database (Denmark)

Petri, Helle; Sveen, Marie-Louise; Thune, Jens Jakob

2015-01-01

AIM: To assess the degree and progression of cardiac involvement in patients with limb-girdle type 2 (LGMD2) and Becker muscular dystrophies (BMD). METHODS: A follow-up study of 100 LGMD2 (types A-L) and 30 BMD patients assessed by electrocardiogram (ECG) and echocardiography, supplemented...

Gas storage facilities. Investigation of their social value

International Nuclear Information System (INIS)

1997-02-01

The socio-economic factors resulting from location of gas storage facilities are evaluated. Various alternatives to the existing projects are estimated, for instance 11 new pipelines, in some cases combined with new production capacity, LNG facilities, differentiated tariffs, reconstruction of decentralized heat/power plants etc. Theoretical considerations and models, among others involving gas storage abroad, are presented. Seasonal storage, emergency storage, storage controlled by economic optimization (profitable purchases, sales at highest market) are described for various types of facilities, like aquifers, caverns and LNG-stores. Natural gas supplies in Europe, infrastructure and resources are compared to the Danish conditions. Sensitivity of the Danish heating market for natural gas consumption is investigated. Reduction in energy use for space heating by 2005 will change the needs of storage of 740 Mm 3 gas to 650 Mm 3 . Extra consumption by the decentralized power/heat plants is not accounted for in this estimation. Dynamic models of the future gas consumption are based on the EU 'European Energy 2020'. (EG)

Fuel conditioning facility zone-to-zone transfer administrative controls

International Nuclear Information System (INIS)

Pope, C. L.

2000-01-01

The administrative controls associated with transferring containers from one criticality hazard control zone to another in the Argonne National Laboratory (ANL) Fuel Conditioning Facility (FCF) are described. FCF, located at the ANL-West site near Idaho Falls, Idaho, is used to remotely process spent sodium bonded metallic fuel for disposition. The process involves nearly forty widely varying material forms and types, over fifty specific use container types, and over thirty distinct zones where work activities occur. During 1999, over five thousand transfers from one zone to another were conducted. Limits are placed on mass, material form and type, and container types for each zone. Ml material and containers are tracked using the Mass Tracking System (MTG). The MTG uses an Oracle database and numerous applications to manage the database. The database stores information specific to the process, including material composition and mass, container identification number and mass, transfer history, and the operators involved in each transfer. The process is controlled using written procedures which specify the zone, containers, and material involved in a task. Transferring a container from one zone to another is called a zone-to-zone transfer (ZZT). ZZTs consist of four distinct phases, select, request, identify, and completion

Biochemical mechanisms involved in the endotoxin-induced type II cell hyperplasia in F344 rat lung

International Nuclear Information System (INIS)

Tesfaigzi, J.; Johnson, N.F.; Lechner, J.F.

1994-01-01

Proliferative lesions and pulmonary epithelial neoplasms induced in the rat by plutonium inhalation have been shown to be of type II cell origin. Defining the gene changes responsible for the development of the type II proliferative lesions would help to elucidate the genetic events involved in the expansion of initiated type II cells into fully transformed tumor cells. One problem in identifying these gene alterations is dissociating changes in gene expression linked to cell replication or repair from those involved in tumor initiation and progression. The long-term goals of these investigations are to first develop and characterize a model of transient type II cell hyperplasia. Second, changes in gene expression associated with remodeling epithelium will be compared to gene changes exhibited by the 239 Pu-induced hyperplastic lesions

A statistical description of the types and severities of accidents involving tractor semi-trailers

International Nuclear Information System (INIS)

Clauss, D.B.; Wilson, R.K.; Blower, D.F.; Campbell, K.L.

1994-06-01

This report provides a statistical description of the types and severities of tractor semi-trailer accidents involving at least one fatality. The data were developed for use in risk assessments of hazardous materials transportation. Several accident databases were reviewed to determine their suitability to the task. The TIFA (Trucks Involved in Fatal Accidents) database created at the University of Michigan Transportation Research Institute was extensively utilized. Supplementary data on collision and fire severity, which was not available in the TIFA database, were obtained by reviewing police reports for selected TIFA accidents. The results are described in terms of frequencies of different accident types and cumulative distribution functions for the peak contact velocity, rollover skid distance, fire temperature, fire size, fire separation, and fire duration

Decommissioning nuclear facilities

International Nuclear Information System (INIS)

Harmon, K.M.; Jenkins, C.E.; Waite, D.A.; Brooksbank, R.E.; Lunis, B.C.; Nemec, J.F.

1976-01-01

This paper describes the currently accepted alternatives for decommissioning retired light water reactor fuel cycle facilities and the current state of decommissioning technology. Three alternatives are recognized: Protective Storage; Entombment; and Dismantling. Application of these alternatives to the following types of facilities is briefly described: light water reactors; fuel reprocessing plants, and mixed oxide fuel fabrication plants. Brief descriptions are given of decommissioning operations and results at a number of sites, and recent studies of the future decommissioning of prototype fuel cycle facilities are reviewed. An overview is provided of the types of operations performed and tools used in common decontamination and decommissioning techniques and needs for improved technology are suggested. Planning for decommissioning a nuclear facility is dependent upon the maximum permitted levels of residual radioactive contamination. Proposed guides and recently developed methodology for development of site release criteria are reviewed. 21 fig, 32 references

Environmental Monitoring, Water Quality - Water Pollution Control Facilities

Data.gov (United States)

NSGIC Education | GIS Inventory — A Water Pollution Control Facility is a DEP primary facility type related to the Water Pollution Control Program. The sub-facility types related to Water Pollution...

Fiscal 1997 survey report. Basic survey on trends of waste use type production facilities and waste fuel production facilities; 1997 nendo chosa hokokusho. Haikibutsu riyogata seizo shisetsu oyobi haikibutsu nenryo seizo shisetsu doko kiso chosa hokokusho

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-03-01

This survey was made to obtain the basic data for future spread and promotion of No.6 type (waste use type production facilities) and No.7 type (waste fuel production facilities) which were added to the objects having been subsidized since fiscal 1997 under `the environmental harmony type energy community project.` In the former, the kiln in the cement industry and the blast furnace in the steel industry can be extremely large places to receive waste plastic since the facilities are distributed in every area and the treatment capacity is large. However, the effective collection, transportation and sorting of large quantity of waste plastic, especially the problem of removal of vinyl chloride, is a big bottleneck. As to the use of waste plastic using gasification technology, there are no actual results on the commercial basis. That is, however, appropriate for treatment of the waste difficult in treatment, and can be expected of the usage in the chemical industry. In the latter, in the facilities using industrial waste raw materials as fuel, solidification and liquefaction are both operated on a commercial basis. In relation to the solidification and use as fuel of general waste, the treatment of combustion ash is preventing the expansion of use of waste in the industrial field because of a large quantity of chlorine included in the products. 92 refs., 54 figs., 35 tabs.

Sustainable Facilities Management

DEFF Research Database (Denmark)

Nielsen, Susanne Balslev; Elle, Morten; Hoffmann, Birgitte

2004-01-01

The Danish public housing sector has more than 20 years of experience with sustainable facilities management based on user involvement. The paper outlines this development in a historical perspective and gives an analysis of different approaches to sustainable facilities management. The focus...... is on the housing departments and strateies for the management of the use of resources. The research methods used are case studies based on interviews in addition to literature studies. The paper explores lessons to be learned about sustainable facilities management in general, and points to a need for new...

Assessment of the radiological risks of road transport accidents involving type A package shipments

International Nuclear Information System (INIS)

Lange, F.; Fett, H.J.; Schwarz, G.; Raffestin, D.; Schneider, T.; Gelder, R.; Hughes, J.S.; Shaw, K.B.; Hedberg, B.; Simenstad, P.; Svahn, B.; Hienen, J.F.A.; Jansma, R.

1998-01-01

This paper is an account of work performed within a multi-lateral research project on the radiological risks associated with the transportation of Type A packaged radioactive material. The research project has been performed on behalf of the European Commission and various national agencies of the participating countries and involved organizations and institutes of five EU Member States, France, Germany, The Netherlands, Sweden, and the UK. The main objectives of the research project were the assessment and appraisal of the potential radiological risks of road transport accidents involving Type A package shipments in participating EU Member States. Data were collected and include harmonized sets information related to the type, quantity and characteristics of Type A package shipments by road. Such databases were basically non-existent until recently. The results are expected to be valuable to both national agencies and international organizations, with responsibilities for the safe transport of radioactive materials by providing some insight in the carriage of radioactive materials by road making up a major fraction of radioactive material transports. Similarly, a wide body of information has been collected and compiled on road transport accidents in terms of the frequency of occurrence and the severity of accidental impact loads potentially experienced by a Type A package.In addition, the results will facilitate judgement of the adequacy of the IAEA Transport Regulations as far as Type A packages are concerned. (O.M.)

New Ideas on Facilities Management.

Science.gov (United States)

Grimm, James C.

1986-01-01

Examines trends in facilities management relating to products and people. Reviews new trends in products, including processes, techniques, and programs that are being expounded by business and industry. Discusses the "people factors" involved in facilities management. (ABB)

Facility effluent monitoring plan for the 2724-W Protective Equipment Decontamination Facility

International Nuclear Information System (INIS)

Nickels, J.M.; Lavey, G.H.

1992-12-01

A facility effluent monitoring plan is required by the US Department of Energy in DOE Order 5400.1* for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. A facility effluent monitoring plan determination was performed during Calendar Year 1991 and the evaluation requires the need for a facility effluent monitoring plan. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438**. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements

Facility effluent monitoring plan for 242-A evaporator facility

International Nuclear Information System (INIS)

Crummel, G.M.; Gustavson, R.D.

1995-02-01

A facility effluent monitoring plan is required by the U.S. Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could affect employee or public safety or the environment. A facility effluent monitoring plan determination was performed during Calendar Year 1991 and the evaluation showed the need for a facility effluent monitoring plan. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438-1. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan shall ensure long-range integrity of the effluent monitoring systems by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and it must be updated, as a minimum, every three years

Cherenkov-type diagnostics of fast electrons beams escaping from MCF facilities

Energy Technology Data Exchange (ETDEWEB)

Jakubowski, L.; Malinowski, K.; Mirowski, R.; Rabinski, M.; Sadowski, M.J.; Zebrowski, J. [Institute for Nuclear Studies - IPJ, 05-400 Otwock-Swierk (Poland)

2011-07-01

The paper presents the feasibility study, the measuring system and the first experimental results of a new method developed for direct detection of high-energy (super-thermal, ripple-born and runaway) electrons generated in magnetic confinement fusion (MCF) facilities. The technique in question is based on registration of the Cherenkov radiation, emitted by energetic electrons, moving through a transparent medium (radiator) with a velocity higher than the velocity of light in this material. The main aim of our studies was to develop a diagnostic technique applicable for measurements of fast electron beams within MCF devices. The IPJ team proposed Cherenkov-type probes because of their high spatial- and temporal-resolutions. The most important results of applications of the presented Cherenkov-type diagnostics have proved that the one- and four-channel versions of the detecting head are useful for studies of the fast (ripple-born and runaway) electrons in different MCF experiments. Experience collected during the described studies allows to introduce some changes in the radiator configuration and to modify the Cherenkov probe design. This document is composed of a paper followed by a poster

New Trends in Facility Asset Management.

Science.gov (United States)

Adams, Matt

2000-01-01

Explains new, positive trends in facility asset management that encompasses greater acceptance and involvement of facility managers in the financial planning process, greater awareness of the need for maintenance, and facility administrators taking a greater role with business officers. The new climate for alternative renewal financing proposals…

Guide to research facilities

Energy Technology Data Exchange (ETDEWEB)

1993-06-01

This Guide provides information on facilities at US Department of Energy (DOE) and other government laboratories that focus on research and development of energy efficiency and renewable energy technologies. These laboratories have opened these facilities to outside users within the scientific community to encourage cooperation between the laboratories and the private sector. The Guide features two types of facilities: designated user facilities and other research facilities. Designated user facilities are one-of-a-kind DOE facilities that are staffed by personnel with unparalleled expertise and that contain sophisticated equipment. Other research facilities are facilities at DOE and other government laboratories that provide sophisticated equipment, testing areas, or processes that may not be available at private facilities. Each facility listing includes the name and phone number of someone you can call for more information.

Neurofibromatosis type 1 with external genitalia involvement presentation of 4 patients.

Science.gov (United States)

Pascual-Castroviejo, Ignacio; Lopez-Pereira, Pedro; Savasta, Salvatore; Lopez-Gutierrez, Juan Carlos; Lago, Carlos Míguelez; Cisternino, Mariangela

2008-11-01

Genitourinary neurofibromas with clitoral involvement in neurofibromatosis type 1 are rare, and even more infrequent are the neurofibromas involving genitalia in males. The most frequent presenting sign of neurofibroma in females is clitoromegaly with pseudopenis, and enlarged penis is the most common sign in males. Labium majus neurofibroma not associated with clitoral involvement is extremely rare. Magnetic resonance imaging demonstration of the neurofibromas has seldom been reported. We report 4 children, 3 girls and 1 boy, with plexiform neurofibromas involving the external genitalia. Three of the 4 patients had histologic confirmation of neurofibroma. Two girls with clitoral hypertrophy had a neurofibroma that infiltrated the clitoris and extended unilaterally to the lower bladder wall. One girl had a plexiform neurofibroma that affected a labium. One boy with asymmetric penile hypertrophy since 2 years of age and ipsilateral gluteal hypertrophy had plexiform neurofibromas that extended between the left lumbogluteal and penile regions, infiltrating the left rectum wall and bladder with compression of both structures, the left prostate, and the left half of the cavernous corpi with hypertrophy of this part and asymmetry of the penis. Magnetic resonance imaging demonstrated in all patients that external genitalia and plexiform neurofibroma formed images of nondetachable structures. However, hermaphroditism was discarded by chromosomal study in all 3 girls before ratifying the diagnosis of external genitalia neurofibroma.

Evaluation on applicability of construction methods and construction quality of low-diffusion layer of cavern type radioactive waste disposal facility

International Nuclear Information System (INIS)

Takechi, Shin-ichi; Yokozeki, Kosuke; Terada, Kenji; Akiyama, Yoshihiro; Yada, Tsutomu; Tsuji, Yukikazu

2014-01-01

A performance verification experiment of cavern type radioactive waste disposal facility with a real scale construction is being conducted to evaluate the applicability of proposed construction methods and construction quality of the facility. In this paper, we confirmed that the low-diffusion layer, which is one of the cementitious materials based members, could be filled with mortar from end to end of the member; cracks of low-diffusion layer would not affect the long-term safety evaluation of the facility. And also we figured out the relationship between the material strength and the accumulated temperature, relationship between diffusion coefficient and porosity of low-diffusion layer. (author)

Gas storage facilities. Investigation of their social value. Supplement

International Nuclear Information System (INIS)

1997-02-01

The socio-economic factors resulting from location of gas storage facilities are evaluated. Various alternatives to the existing projects are estimated, for instance 11 new pipelines, in some cases combined with new production capacity, LNG facilities, differentiated tariffs, reconstruction of decentralized heat/power plants etc. Theoretical considerations and models, among others involving gas storage abroad, are presented. Seasonal storage, emergency storage, storage controlled by economic optimization (profitable purchases, sales at highest market) are described for various types of facilities, like aquifers, caverns and LNG-stores. Natural gas supplies in Europe, infrastructure and resources are compared to the Danish conditions. Sensitivity of the Danish heating market for natural gas consumption is investigated. Reduction in energy use for space heating by 2005 will change the needs of storage of 740 Mm 3 gas to 650 Mm 3 . Extra consumption by the decentralized power/heat plants is not accounted for in this estimation. Dynamic models of the future gas consumption are based on the EU 'European Energy 2020'. (EG)

Training practices to support decommissioning of nuclear facilities

International Nuclear Information System (INIS)

Bourassa, J.; Clark, C.R.; Kazennov, A.; Laraia, M.; Rodriguez, M.; Scott, A.; Yoder, J.

2006-01-01

Adequate numbers of competent personnel must be available during any phase of a nuclear facility life cycle, including the decommissioning phase. While a significant amount of attention has been focused on the technical aspects of decommissioning and many publications have been developed to address technical aspects, human resource management issues, particularly the training and qualification of decommissioning personnel, are becoming more paramount with the growing number of nuclear facilities of all types that are reaching or approaching the decommissioning phase. One of the keys to success is the training of the various personnel involved in decommissioning in order to develop the necessary knowledge and skills required for specific decommissioning tasks. The operating organisations of nuclear facilities normally possess limited expertise in decommissioning and consequently rely on a number of specialized organisations and companies that provide the services related to the decommissioning activities. Because of this there is a need to address the issue of assisting the operating organisations in the development and implementation of human resource management policies and training programmes for the facility personnel and contractor personnel involved in various phases of decommissioning activities. The lessons learned in the field of ensuring personnel competence are discussed in the paper (on the basis of information and experiences accumulated from various countries and organizations, particularly, through relevant IAEA activities). Particularly, the following aspects are addressed: transition of training from operational to decommissioning phase; knowledge management; target groups, training needs analysis, and application of a systematic approach to training (SAT); content of training for decommissioning management and professional staff, and for decommissioning workers; selection and training of instructors; training facilities and tools; and training as

Emotional Creativity and Real-Life Involvement in Different Types of Creative Leisure Activities

Science.gov (United States)

Trnka, Radek; Zahradnik, Martin; Kuška, Martin

2016-01-01

The role of emotional creativity in practicing creative leisure activities and in the preference of college majors remains unknown. This study aims to explore how emotional creativity measured by the Emotional Creativity Inventory (ECI; Averill, 1999) is interrelated with the real-life involvement in different types of specific creative leisure…

Application of an experimental irradiation facility type K-120 for the radiation treatment of agricultural products in large quantity

International Nuclear Information System (INIS)

Stenger, V.; Foeldiak, G.; Horvath, I.; Hargittai, P.; Bartfai, Cs.

1979-01-01

During experimental and pilot irradiation carried out by the 60 Co irradiation facility type K-120 of the Institute of Isotopes of the Hungarian Academy of Sciences an irradiation technology for the treatment of agricultural and food products of considerable density has been developed. Applying transport containers of commercial size the intermittent radiation treatment of great quantity products was made possible with homogeneous dose distribution. The radiation technical characteristics, the utilization coefficient and the capacity of the facility for every agricultural product were calculated. (author)

Implementing RCRA during facility deactivation

International Nuclear Information System (INIS)

Lebaron, G.J.

1997-01-01

RCRA regulations require closure of permitted treatment, storage and disposal (TSD) facilities within 180 days after cessation of operations, and this may essentially necessitate decommissioning to complete closure. A more cost effective way to handle the facility would be to significantly reduce the risk to human health and the environment by taking it from its operational status to a passive, safe, inexpensive-to-maintain surveillance and maintenance condition (deactivation) prior to decommissioning. This paper presents an innovative approach to the cost effective deactivation of a large, complex chemical processing facility permitted under RCRA. The approach takes into account risks to the environment posed by this facility in comparison to risks posed by neighboring facilities at the site. The paper addresses the manner in which: 1) stakeholders and regulators were involved; 2) identifies a process by which the project proceeds and regulators and stakeholders were involved; 3) end points were developed so completion of deactivation was clearly identified at the beginning of the project, and 4) innovative practices were used to deactivate more quickly and cost effectively

Primary NK/T cell lymphoma nasal type of the stomach with skin involvement: a case report

Directory of Open Access Journals (Sweden)

Sebastian Kobold

2009-12-01

Full Text Available Since nasal NK/T cell lymphoma and NK/T cell lymphoma nasal type are rare diseases, gastric involvement has seldom been seen. We report a unique case of a patient with a primary NK/T cell lymphoma nasal type of the stomach with skin involvement. The patient had no history of malignant diseases and was diagnosed with hematemesis and intense bleeding from his gastric primary site. Shortly after this event, exanthemic skin lesions appeared with concordant histology to the primary site. Despite chemotherapy, the patient died one month after the first symptomatic appearance of disease.

Structural integrity monitoring of critical components in nuclear facilities

International Nuclear Information System (INIS)

Roth, Maria; Constantinescu, Dan Mihai; Brad, Sebastian; Ducu, Catalin; Malinovschi, Viorel

2007-01-01

Full text: The paper presents the results obtained as part of the Project 'Integrated Network for Structural Integrity Monitoring of Critical Components in Nuclear Facilities', RIMIS, a research work underway within the framework of the Ministry of Education and Research Programme 'Research of Excellence'. The main objective of the Project is to constitute a network integrating the national R and D institutes with preoccupations in the structural integrity assessment of critical components in the nuclear facilities operating in Romania, in order to elaborate a specific procedure for this field. The degradation mechanisms of the structural materials used in the CANDU type reactors, operated by Unit 1 and Unit 2 at Cernavoda (pressure tubes, fuel elements sheaths, steam generator tubing) and in the nuclear facilities relating to reactors of this type as, for instance, the Hydrogen Isotopes Separation facility, will be investigated. The development of a flexible procedure will offer the opportunity to extend the applications to other structural materials used in the nuclear field and in the non-nuclear fields as well, in cooperation with other institutes involved in the developed network. The expected results of the project will allow the integration of the network developed at national level in the structures of similar networks operating within the EU, the enhancement of the scientific importance of Romanian R and D organizations as well as the increase of our country's contribution in solving the major issues of the nuclear field. (authors)

Facility transition instruction

International Nuclear Information System (INIS)

Morton, M.R.

1997-01-01

The Bechtel Hanford, Inc. facility transition instruction was initiated in response to the need for a common, streamlined process for facility transitions and to capture the knowledge and experience that has accumulated over the last few years. The instruction serves as an educational resource and defines the process for transitioning facilities to long-term surveillance and maintenance (S and M). Generally, these facilities do not have identified operations missions and must be transitioned from operational status to a safe and stable configuration for long-term S and M. The instruction can be applied to a wide range of facilities--from process canyon complexes like the Plutonium Uranium Extraction Facility or B Plant, to stand-alone, lower hazard facilities like the 242B/BL facility. The facility transition process is implemented (under the direction of the US Department of Energy, Richland Operations Office [RL] Assistant Manager-Environmental) by Bechtel Hanford, Inc. management, with input and interaction with the appropriate RL division and Hanford site contractors as noted in the instruction. The application of the steps identified herein and the early participation of all organizations involved are expected to provide a cost-effective, safe, and smooth transition from operational status to deactivation and S and M for a wide range of Hanford Site facilities

Radioactive contamination incidents involving protective clothing

Energy Technology Data Exchange (ETDEWEB)

Reichelt, R.; Clay, M.; Eichorst, J.

1996-10-01

The study focuses on incidents at Department of Energy (DOE) facilities involving the migration of radioactive contaminants through protective clothing. The authors analyzed 68 occurrence reports for the following factors: (1) type of work; (2) working conditions; (3) type of anti-contamination (anti-C) material; (4) area of body or clothing contaminated; and (5) nature of spread of contamination. A majority of reports identified strenuous work activities such as maintenance, construction, or decontamination and decommissioning (D&D) projects. The reports also indicated adverse working conditions that included hot and humid or cramped work environments. The type of anti-C clothing most often identified was cotton or water-resistant, disposable clothing. Most of the reports also indicated contaminants migrating through perspiration-soaked areas, typically in the knees and forearms. On the basis of their survey, the authors recommend the use of improved engineering controls and resilient, breathable, waterproof protective clothing for work in hot, humid, or damp areas where the possibility of prolonged contact with contamination cannot be easily avoided or controlled.

Radioactive contamination incidents involving protective clothing

International Nuclear Information System (INIS)

Reichelt, R.; Clay, M.; Eichorst, J.

1996-10-01

The study focuses on incidents at Department of Energy (DOE) facilities involving the migration of radioactive contaminants through protective clothing. The authors analyzed 68 occurrence reports for the following factors: (1) type of work; (2) working conditions; (3) type of anti-contamination (anti-C) material; (4) area of body or clothing contaminated; and (5) nature of spread of contamination. A majority of reports identified strenuous work activities such as maintenance, construction, or decontamination and decommissioning (D ampersand D) projects. The reports also indicated adverse working conditions that included hot and humid or cramped work environments. The type of anti-C clothing most often identified was cotton or water-resistant, disposable clothing. Most of the reports also indicated contaminants migrating through perspiration-soaked areas, typically in the knees and forearms. On the basis of their survey, the authors recommend the use of improved engineering controls and resilient, breathable, waterproof protective clothing for work in hot, humid, or damp areas where the possibility of prolonged contact with contamination cannot be easily avoided or controlled

Radioactive contamination incidents involving protective clothing

International Nuclear Information System (INIS)

Reichelt, R.A.; Clay, M.E.; Eichorst, A.J.

1998-01-01

The study focuses on incidents at Department of Energy facilities involving the migration of radioactive contaminants through protective clothing. The authors analyzed 68 occurrence reports for the following factors: (1) type of work, (2) working conditions, (3) type of anti-contamination material; (4) area of body or clothing contaminated; and (5) nature of spread of contamination. A majority of reports identified strenuous work activities such as maintenance, construction, or decontamination and decommissioning projects. The reports also indicated adverse working conditions that included hot and humid or cramped work environments. The type of anti-contamination clothing most often identified was cotton or water-resistant disposable clothing. Most of the reports also indicated contaminants migrating through perspiration-soaked areas, typically in the knees and forearms. On the basis of their survey, the authors recommend the use of improved engineering controls and resilient, breathable, waterproof protective clothing for work in hot, humid, or damp areas where the possibility of prolonged contact with contamination cannot be easily avoided or controlled. 1 ref., 6 figs., 1 tab

Shielding of Medical Facilities. Shielding Design Considerations for PET-CT Facilities

International Nuclear Information System (INIS)

Cruzate, J.A.; Discacciatti, A.P.

2011-01-01

The radiological evaluation of a Positron Emission Tomography (PET) facility consists of the assessment of the annual effective dose both to workers occupationally exposed, and to members of the public. This assessment takes into account the radionuclides involved, the facility features, the working procedures, the expected number of patients per year, and so on. The evaluation embraces the distributions of rooms, the thickness and physical material of walls, floors and ceilings. This work detail the methodology used for making the assessment of a PET facility design taking into account only radioprotection aspects. The assessment results must be compared to the design requirements established by national regulations in order to determine whether or not, the facility complies with those requirements, both for workers and for members of the public. The analysis presented is useful for both, facility designers and regulators. In addition, some guidelines for improving the shielding design and working procedures are presented in order to help facility designer's job. (authors)

Facility Effluent Monitoring Plan for the uranium trioxide facility

International Nuclear Information System (INIS)

Lohrasbi, J.; Johnson, D.L.; De Lorenzo, D.S.

1993-12-01

A facility effluent monitoring plan is required by the US Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438-01. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan shall ensure long-range integrity of the effluent monitoring systems by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and it must be updated at a minimum of every three years

Radioactive waste storage facilities, involvement of AVN in inspection and safety assessment

International Nuclear Information System (INIS)

Simenon, R.; Smidts, O.

2006-01-01

The legislative and regulatory framework in Belgium for the licensing and the operation of radioactive waste storage buildings are defined by the Royal Decree of 20 July 2001 (hereby providing the general regulations regarding to the protection of the population, the workers and the environment against the dangers of ionising radiation). This RD introduces in the Belgian law the radiological protection and ALARA-policy concepts. The licence of each nuclear facility takes the form of a Royal Decree of Authorization. It stipulates that the plant has to be in conformity with its Safety Analysis Report. This report is however not a public document but is legally binding. Up to now, the safety assessment for radioactive waste storage facilities, which is implemented in this Safety Analysis Report, has been judged on a case-by-case basis. AVN is an authorized inspection organisation to carry out the surveillance of the Belgian nuclear installations and performs hereby nuclear safety assessments. AVN has a role in the nuclear safety and radiation protection during all the phases of a nuclear facility: issuance of licenses, during design and construction phase, operation (including reviewing and formal approval of modifications) and finally the decommissioning. Permanent inspections are performed on a regular basis by AVN, this by a dedicated site inspector, who is responsible for a site of an operator with nuclear facilities. Besides the day-to-day inspections during operation there are also the periodic safety reviews. AVN assesses the methodological approaches for the analyses, reviews and approves the final studies and results. The conditioned waste in Belgium is stored on the Belgoprocess' sites (region Mol-Dessel) for an intermediate period (about 80 years). In the meantime, a well-defined inspection programme is being implemented to ensure that the conditioned waste continues to be stored safely during this temporary storage period. This programme was draw up by

COSPAS-SARSAT Beacon Certification Facility

Data.gov (United States)

Federal Laboratory Consortium — EPG's COSPAS-SARSAT Beacon Certification Facility is one of five certification facilities in the world. Formal certifications are available for all beacon types and...

Considerations about the licensing process of special nuclear industrial facilities

Energy Technology Data Exchange (ETDEWEB)

Talarico, M.A., E-mail: talaricomarco@hotmail.com [Marinha do Brasil, Rio de Janeiro, RJ (Brazil). Coordenacao do Porgrama de Submarino com Propulsao Nuclear; Melo, P.F. Frutuoso e [Coordenacao dos Programas de Pos-Graduacao em Engenharia (COPPE/UFRJ), Rio de Janeiro, RJ (Brazil). Programa de Engenharia Nuclear

2015-07-01

This paper brings a discussion about the challenges involved in the development of a new kind of nuclear facility in Brazil, a naval base for nuclear submarines, with attention to the licensing process and considerations about the risk-informed decision making application to the licensing process. Initially, a model of such a naval base, called in this work, special industrial facility, is proposed, with its systems and respective sets of basic requirements, in order to make it possible the accomplishment of the special industrial facility support function to the nuclear submarine. A discussion about current challenges to overcome in this project is presented: the challenges due to the new characteristics of this type of nuclear facility; existence of several interfaces between the special industrial facilities systems and nuclear submarine systems in design activities; lack of specific regulation in Brazil to allow the licensing process of special industrial facilities by the nuclear safety authority; and comments about the lack of information from reference nuclear facilities, as is the case with nuclear power reactors (for example, the German Grafenrheinfeld nuclear plant is the reference plant for the Brazilian Angra 2 nuclear plant). Finally, in view of these challenges, an analysis method of special industrial facility operational scenarios to assist the licensing process is proposed. Also, considerations about the application of risk-informed decision making to the special industrial facility activity and licensing process in Brazil are presented. (author)

Considerations about the licensing process of special nuclear industrial facilities

International Nuclear Information System (INIS)

Talarico, M.A.; Melo, P.F. Frutuoso e

2015-01-01

This paper brings a discussion about the challenges involved in the development of a new kind of nuclear facility in Brazil, a naval base for nuclear submarines, with attention to the licensing process and considerations about the risk-informed decision making application to the licensing process. Initially, a model of such a naval base, called in this work, special industrial facility, is proposed, with its systems and respective sets of basic requirements, in order to make it possible the accomplishment of the special industrial facility support function to the nuclear submarine. A discussion about current challenges to overcome in this project is presented: the challenges due to the new characteristics of this type of nuclear facility; existence of several interfaces between the special industrial facilities systems and nuclear submarine systems in design activities; lack of specific regulation in Brazil to allow the licensing process of special industrial facilities by the nuclear safety authority; and comments about the lack of information from reference nuclear facilities, as is the case with nuclear power reactors (for example, the German Grafenrheinfeld nuclear plant is the reference plant for the Brazilian Angra 2 nuclear plant). Finally, in view of these challenges, an analysis method of special industrial facility operational scenarios to assist the licensing process is proposed. Also, considerations about the application of risk-informed decision making to the special industrial facility activity and licensing process in Brazil are presented. (author)

Requirements and design concept for a facility mapping system

International Nuclear Information System (INIS)

Barry, R.E.; Burks, B.L.; Little, C.Q.

1995-01-01

The Department of Energy (DOE) has for some time been considering the Decontamination and Dismantlement (D ampersand D) of facilities which are no longer in use, but which are highly contaminated with radioactive wastes. One of the holdups in performing the D ampersand D task is the accumulation of accurate facility characterizations that can enable a safe and orderly cleanup process. According to the Technical Strategic Plan for the Decontamination and Decommissioning Integrated Demonstration, open-quotes the cost of characterization using current baseline technologies for approximately 100 acres of gaseous diffusion plant at Oak Ridge alone is, for the most part incalculableclose quotes. Automated, robotic techniques will be necessary for initial characterization and continued surveillance of these types of sites. Robotic systems are being designed and constructed to accomplish these tasks. This paper describes requirements and design concepts for a system to accurately map a facility contaminated with hazardous wastes. Some of the technologies involved in the Facility Mapping System are: remote characterization with teleoperated, sensor-based systems, fusion of data sets from multiple characterization systems, and object recognition from 3D data models. This Facility Mapping System is being assembled by Oak Ridge National Laboratory for the DOE Office of Technology Development Robotics Technology Development Program

30 CFR 57.6161 - Auxiliary facilities.

Science.gov (United States)

2010-07-01

... 30 Mineral Resources 1 2010-07-01 2010-07-01 false Auxiliary facilities. 57.6161 Section 57.6161...-Underground Only § 57.6161 Auxiliary facilities. (a) Auxiliary facilities used to store explosive material near work places shall be wooden, box-type containers equipped with covers or doors, or facilities...

25 CFR 1000.463 - What types of personal conflicts of interest involving tribal officers, employees or...

Science.gov (United States)

2010-04-01

... 25 Indians 2 2010-04-01 2010-04-01 false What types of personal conflicts of interest involving...-DETERMINATION AND EDUCATION ACT Conflicts of Interest § 1000.463 What types of personal conflicts of interest... financial or employment interest that conflicts with that of the trust beneficiary, whether the tribe...

Sporadic manipulation in money markets with central bank standing facilities

OpenAIRE

Ewerhart, Christian; Cassola, Nuno; Ejerskov, Steen; Valla, Natacha

2004-01-01

In certain market environments, a large investor may benefit from building up a futures position first and trading subsequently in the spot market (Kumar and Seppi, 1992). The present paper identifies a variation of this type of manipulation that might occur in money markets with an interest rate corridor. We show that manipulation involving the use of central bank facilities would be observable only sporadically. The probability of manipulation decreases when the central bank uses an active ...

Use of base isolation techniques for the design of high-level waste storage facility enclosure at INEL

International Nuclear Information System (INIS)

Vallenas, J.M.; Wong, Chun K.; Beer, M.J.

1993-08-01

Current Department of Energy criteria for facilities subjected to natural hazards provide guidelines to place facilities or portions of facilities into usage categories. Usage categories are based on characteristics such as mission dependence, type of hazardous materials involved, and performance goals. Seismic requirements are significantly more stringent for facilities falling into higher ''hazard facility use categories''. A special problem arises in cases where a facility or portion of a facility is dependent on another facility of lower ''hazard facility use category'' for support or protection. Creative solutions can minimize the cost Unpact of ensuring that the lower category item does not compromise the performance of the higher category item. In this paper, a base isolation solution is provided for a ''low hazard facility use category'' weather enclosure designed so it will not collapse onto a ''high hazard facility use category'' high level waste storage facility at INEL. This solution is compared to other more conventional procedures. Details, practical limitations, licensing and regulatory considerations, and cost comparisons are provided

Involving the public in decision-making at federal facilities: The Department of Energy experience

International Nuclear Information System (INIS)

Gesalman, C.M.

1996-01-01

The Department of Energy is involved in cleanup of a wide variety of sites used in the development and production of nuclear weapons. Substantial and increasing efforts have been made to involve the public in the planning and implementation of the cleanup projects. Early in the program, public participation was mainly an information transfer effort. More recently, innovative techniques have been used to increase public understanding of the tradeoffs required in making cleanup decisions (e.g., more stringent cleanup standards lead to higher costs). Sites now realize that relationships are key and are working to develop them. Advisory boards have been established at several sites. The methods of forming the boards have varied from site to site, as have the size of the group and the issues addressed. The effectiveness of the boards in their goal of improving public participation at the sites will be evaluated in the next fiscal year. DOE has sought public input on an increasing number of issues, such as future use of its facilities, environmental justice concerns, and budget development. Assumptions about future use of sites are crucial to setting realistic cleanup standards and controlling costs. Decisions made in the early phases of the budget process are now based in part on stakeholder input regarding priorities; for example, stakeholder concerns about and support for emphasizing plutonium cleanup at Rocky Flats have led to changes in priorities between the materials stabilization and environmental restoration programs. Environmental justice has become an increasing issue; sites must ensure that public participation programs effectively reach minority and low-income populations

The effect of types of banner ad, Web localization, and customer involvement on Internet users' attitudes.

Science.gov (United States)

Chen, Jengchung Victor; Ross, William H; Yen, David C; Akhapon, Lerdsuwankij

2009-02-01

In this study, three characteristics of Web sites were varied: types of banner ad, Web localization, and involvement in purchasing a product. The dependent variable was attitude toward the site. In laboratory experiments conducted in Thailand and Taiwan, participants browsed versions of a Web site containing different types of banner ads and products. As a within-participants factor, each participant browsed both a standardized English-language Web site and a localized Web site. Results showed that animated (rather than static) banner ads, localized versions (rather than a standardized version) of Web sites, and high (rather than low) product involvement led to favorable attitudes toward the site.

Examining the interaction of parental involvement and parenting style in predicting adherence in youth with type 1 diabetes.

Science.gov (United States)

Landers, Sara E; Friedrich, Elizabeth A; Jawad, Abbas F; Miller, Victoria A

2016-03-01

This study examined whether aspects of parenting style (specifically, warmth, autonomy support, and coercion) moderated the association between parental involvement and adherence in youth with type 1 diabetes. Children ages 8 to 16 years with type 1 diabetes and a parent completed assessments of parental involvement, parenting style, and adherence. Parent autonomy support and coercion were associated with adherence but warmth was not. Child report of more parental involvement was associated with better adherence. Warmth, autonomy support, and coercion were not moderators. The findings underscore the importance of parental involvement, operationalized as responsibility for diabetes tasks, and parenting style, specifically coercion and autonomy support, for adherence in pediatric chronic illness management. Longitudinal research is needed to better understand how and why dimensions of involvement (e.g., responsibility, monitoring, support) vary over time and whether they impact outcomes differentially. (PsycINFO Database Record (c) 2016 APA, all rights reserved).

Factors related to the decision-making for moving the older adults into long-term care facilities in Taiwan.

Science.gov (United States)

Hsieh, Yen-Ping; Huang, Ying-Chia; Lan, Shou-Jen; Ho, Ching-Sung

2017-09-01

To investigate the relationships between demographic characteristics of the elderly, type of long-term care (LTC) facilities, and the reasons for moving into LTC facilities. Research participants included people aged over 65 years, living in LTC facilities. A total of 1280 questionnaires were distributed to 111 LTC facilities in Taiwan; 480 questionnaires were retrieved, and 232 were included in the valid sample. The study used a non-linear canonical correlation analysis, which assesses the relationships among similar sets of categorical variables. The results showed that the older adults in quadrant I were characterized by being involved in the decision-making regarding the choice of LTC facilities and received economic support from their children. The older adults in quadrant II mainly lived in LTC facilities to receive medical care, whereas those in quadrant III typically included individuals with low income, who did not choose to live in LTC facilities. Furthermore, those in quadrant IV had positive cognitions associated with LTC facilities. We believe that the results of the present study will facilitate policy-making in the field of LTC, provide reference to the practitioners and the older adults, and identify the types of decisions older adults make when moving into LTC facilities, thus assisting older adults to improve their strategies regarding staying in LTC facilities. Geriatr Gerontol Int 2017; 17: 1319-1327. © 2016 Japan Geriatrics Society.

Profile of medical waste management in two healthcare facilities in Lagos, Nigeria: a case study.

Science.gov (United States)

Idowu, Ibijoke; Alo, Babajide; Atherton, William; Al Khaddar, Rafid

2013-05-01

Proper management and safe disposal of medical waste (MW) is vital in the reduction of infection or illness through contact with discarded material and in the prevention of environmental contamination in hospital facilities. The management practices for MW in selected healthcare facilities in Lagos, Nigeria were assessed. The cross-sectional study involved the use of questionnaires, in-depth interviews, focused group discussions and participant observation strategies. It also involved the collection, segregation, identification and weighing of waste types from wards and units in the representative facilities in Lagos, Nigeria, for qualitative and quantitative analysis of the MW streams. The findings indicated that the selected Nigerian healthcare facilities were lacking in the adoption of sound MW management (MWM) practices. The average MW ranged from 0.01 kg/bed/day to 3.98 kg/bed/day. Moreover, about 30% of the domestic waste from the healthcare facilities consisted of MW due to inappropriate co-disposal practices. Multiple linear regression was applied to predict the volume of waste generated giving a correlation coefficient (R(2)) value of 0.99 confirming a good fit of the data. This study revealed that the current MWM practices and strategies in Lagos are weak, and suggests an urgent need for review to achieve vital reversals in the current trends.

Huff-type competitive facility location model with foresight in a discrete space

Directory of Open Access Journals (Sweden)

Milad Gorji Ashtiani

2011-01-01

Full Text Available Consider a chain as leader that wants to open p new facilities in a linear market, like metro. In this market, there is a competitor, called follower. The leader and the follower have established some facilities in advance. When the leader opens p new facilities, its competitor, follower, reacts the leader’s action and opens r new facilities. The optimal locations for leader and follower are chosen among predefined potential locations. Demand is considered as demand points and is assumed inelastic. Considering huff model, demand points are probabilistically absorbed by all facilities. The leader’s objective is maximization of its market share after opening follower’s new facilities. For solving leader problem, first the follower’s problem is solved for all leader’s potential locations and the best location for leader is obtained and then, a heuristic model is proposed for leader problem when the leader and the follower want to open one new facility. Computational results show that the proposed method is efficient for large scale problems.

Drug and Alcohol Involvement in Four Types of Fatal Crashes*

Science.gov (United States)

Romano, Eduardo; Voas, Robert B.

2011-01-01

Objective: The aim of this study was to explore the relationship of drunk and drugged driving to the occurrence of fatal crashes associated with speeding, failure to obey/yield, inattention, and seat belt nonuse. Method: We examined data for fatally injured drivers involved in single-vehicle crashes killed in states in which more than 79% of the drivers were tested for drugs other than alcohol and had a known result. Results: About 25% of the drivers tested positive for drugs, a figure almost double that estimated by the 2007 National Roadside Survey. Cannabinoids and stimulants each contributed to about 23% of the drug-positive results (6% among all fatally injured single-vehicle drivers). Stimulants more than cannabinoids were found to be associated with the four types of crashes under study. Some drugs showed a protective effect over the four crash types under study. Significant interactions between drugs and alcohol were observed. Stimulants contributed to the different types of fatal crashes irrespective of the levels of alcohol consumed by the drivers. Conclusions: This study provides further evidence of a link between drug consumption and fatal crashes. It also opens the door to some interesting and sometimes unexpected questions regarding the way drugs contribute to crashes, which we found varies depending on the type of crash considered, the class of drug, and the presence of alcohol. Research is also needed on drugs that could have a protective effect on the occurrence of fatal crashes. These findings could be highly relevant to the design of drug-related traffic laws and programs targeted at curbing drugged driving. PMID:21683038

User involvement and supporting tools in business-to-business service innovations: Insights from Facility Management services

DEFF Research Database (Denmark)

Nardelli, Giulia

is the generalizability of the findings to other business-to-business service sectors. More research conducted both in FM services and other service sectors would help to shed light on the generalizability of these findings. Originality/value – The study contributes with new and detailed insights into the complexity......Purpose – This article investigates and conceptualizes user involvement in business-to-business service innovations as well as the tools that are used to support interactions in such a service innovation process. Design/methodology/approach – The paper uses a qualitative research approach to answer...... the research question. By following Miles and Huberman (1984)’s this study started with a literature review of studies investigating service innovation, service innovations models, user roles and tools in service innovation in general, to conduct an empirical investigation in facility management (FM) services...

An Approach to Safeguards by Design (SBD) for Fuel Cycle Facilities

International Nuclear Information System (INIS)

Sankaran Nair, P.; Gangotra, S.; Karanam, R.

2015-01-01

Implementation of safeguards in bulk handling facilities such as fuel fabrication facilities and reprocessing facilities are a challenging task. This is attributed to the nuclear material present in the facility in the form of powder, pellet, green pellet, solution and gaseous. Additionally material hold up, material unaccounted for (MUF) and the operations carried out round the clock add to the difficulties in implementing safeguards. In facilities already designed or commissioned or operational, implementation of safeguards measures are relatively difficult. The authors have studied a number of measures which can be adopted at the design stage itself. Safeguard By Design (SBD) measures can help in more effective implementation of safeguards, reduction of cost and reduction in radiological dose to the installation personnel. The SBD measures in the power reactors are comparatively easier to implement than in the fuel fabrication plants, since reactors are item counting facilities while the fuel fabrication plants are bulk handling type of facilities and involves much rigorous nuclear material accounting methodology. The safeguards measures include technical measures like dynamic nuclear material accounting, near real time monitoring, remote monitoring, use of automation, facility imagery, Radio Frequency Identification (RFID) tagging, reduction of MUF in bulk handling facilities etc. These measures have been studied in the context of bulk handling facilities and presented in this paper. Incorporation of these measures at the design stage (SBD) is expected to improve the efficiency of safeguardability in such bulk handling and item counting facilities and proliferation resistance of nuclear material handled in such facilities. (author)

Huff-type competitive facility location model with foresight in a discrete space

OpenAIRE

Milad Gorji Ashtiani; Ahmad Makui; Reza Ramezanian

2011-01-01

Consider a chain as leader that wants to open p new facilities in a linear market, like metro. In this market, there is a competitor, called follower. The leader and the follower have established some facilities in advance. When the leader opens p new facilities, its competitor, follower, reacts the leader’s action and opens r new facilities. The optimal locations for leader and follower are chosen among predefined potential locations. Demand is considered as demand points and is assumed inel...

Facility effluent monitoring plan for the tank farms facilities

Energy Technology Data Exchange (ETDEWEB)

Bachand, D.D.; Crummel, G.M.

1995-05-01

A facility effluent monitoring plan is required by the US Department of Energy for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document is prepared using specific guidelines. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan shall ensure long-range integrity of the effluent monitoring systems by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and it must be updated as a minimum every three years.

Facility effluent monitoring plan for the plutonium-uranium extraction facility

International Nuclear Information System (INIS)

Lohrasbi, J.; Johnson, D.L.; De Lorenzo, D.S.

1993-12-01

A facility effluent monitoring plan is required by the US Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438-01. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan shall ensure long-range integrity of the effluent monitoring systems by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and it must be updated at a minimum of every three years

Facility effluent monitoring plan for the plutonium uranium extraction facility

Energy Technology Data Exchange (ETDEWEB)

Wiegand, D.L.

1994-09-01

A facility effluent monitoring plan is required by the US Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438-01. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan shall ensure long-range integrity of the effluent monitoring systems by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and it must be updated at a minimum of every three years.

Facility effluent monitoring plan for the plutonium uranium extraction facility

International Nuclear Information System (INIS)

Wiegand, D.L.

1994-09-01

A facility effluent monitoring plan is required by the US Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438-01. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan shall ensure long-range integrity of the effluent monitoring systems by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and it must be updated at a minimum of every three years

Facility effluent monitoring plan for the Plutonium Uranium Extraction Facility

International Nuclear Information System (INIS)

Greager, E.M.

1997-01-01

A facility effluent monitoring plan is required by the US Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438-01. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether these systems are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan will ensure long-range integrity of the effluent monitoring systems by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and it must be updated, at a minimum, every 3 years

Facility effluent monitoring plan for the plutonium-uranium extraction facility

Energy Technology Data Exchange (ETDEWEB)

Lohrasbi, J.; Johnson, D.L. [Westinghouse Hanford Co., Richland, WA (United States); De Lorenzo, D.S. [Los Alamos Technical Associates, NM (United States)

1993-12-01

A facility effluent monitoring plan is required by the US Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438-01. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan shall ensure long-range integrity of the effluent monitoring systems by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and it must be updated at a minimum of every three years.

Comparison of tritium production facilities

International Nuclear Information System (INIS)

He Kaihui; Huang Jinhua

2002-01-01

Detailed investigation and research on the source of tritium, tritium production facilities and their comparison are presented based on the basic information about tritium. The characteristics of three types of proposed tritium production facilities, i.e., fissile type, accelerator production tritium (APT) and fusion type, are presented. APT shows many advantages except its rather high cost; fusion reactors appear to offer improved safety and environmental impacts, in particular, tritium production based on the fusion-based neutron source costs much lower and directly helps the development of fusion energy source

Type A Dissection Involving Intimo-Intimal Intussusception Through the Aortic Valve.

Science.gov (United States)

Armour, Trygve; Armour, Sarah; Reddy, Pingle; Brinster, Derek

2015-07-15

The presentation, evaluation, management, and outcome of a case of type A circumferential dissection involving repeated retrograde intussusception of the intimal flap through the aortic valve is described in this case report. Fewer than 20 intimo-intimal intussusception cases have been described since the first report was published by Hufnagel in 1962, and outcomes have typically been poor because of delays in diagnosis. This case shows the potential for a positive outcome when the diagnosis of intimo-intimal intussusception is entertained and confirmed early in the course of treatment. Preoperative computed tomography and intraoperative transesophageal echocardiography were essential in diagnosis and operative planning.

Liquid Metal Fast Breeder Reactor Program: Argonne facilities

International Nuclear Information System (INIS)

Stephens, S.V.

1976-09-01

The objective of the document is to present in one volume an overview of the Argonne National Laboratory test facilities involved in the conduct of the national LMFBR research and development program. Existing facilities and those under construction or authorized as of September 1976 are described. Each profile presents brief descriptions of the overall facility and its test area and data relating to its experimental and testing capability. The volume is divided into two sections: Argonne-East and Argonne-West. Introductory material for each section includes site and facility maps. The profiles are arranged alphabetically by title according to their respective locations at Argonne-East or Argonne-West. A glossary of acronyms and letter designations in common usage to describe organizations, reactor and test facilities, components, etc., involved in the LMFBR program is appended

Incidence, types and characteristics of aggressive behaviour in treatment facilities for adults with mild intellectual disability and severe challenging behaviour

NARCIS (Netherlands)

Tenneij, N.H.; Koot, H.M.

2008-01-01

Background: Inpatient aggression in treatment facilities for persons with intellectual disability (ID) can have aversive consequences, for co-clients and staff, but also for the aggressors themselves. To manage and eventually prevent inpatient aggressive incidents, more knowledge about their types

Decommissioning of nuclear facilities: 'it can and has been done'

International Nuclear Information System (INIS)

2009-01-01

Considerable international experience gained over the last 20 years demonstrates that nuclear facilities can be safely dismantled and decommissioned once a decision is made to cease operations and permanently shut them down. The term decommissioning is used to describe all the management and technical actions associated with ceasing operation of a nuclear installation and its subsequent dismantling to facilitate its removal from regulatory control (de-licensing). These actions involve decontamination of structures and components, dismantling of components and demolition of buildings, remediation of any contaminated ground and removal of the resulting waste. Worldwide, of the more than 560 commercial nuclear power plants that are or have been in operation, about 120 plants have been permanently shut down and are at some stage of decommissioning. About 10% of all shutdown plants have been fully decommissioned, including eight reactors of more than 100 MWe. A larger number of various types of fuel cycle and research facilities have also been shut down and decommissioned, including: facilities for the extraction and enrichment of uranium, facilities for fuel fabrication and reprocessing, laboratories, isotope production facilities and particle accelerators. This brochure looks at decommissioning across a spectrum of nuclear facilities and shows worldwide examples of successful projects. Further information can be found in NEA publications and on a number of web-sites

Renal pathological implications in type 2 diabetes mellitus patients with renal involvement.

Science.gov (United States)

Li, Li; Zhang, Xiuhui; Li, Zhicheng; Zhang, Rui; Guo, Ruikun; Yin, Qinghua; Yang, Lichuan; Yue, Rongzheng; Su, Baihai; Huang, Songmin; Xu, Huan; He, Cijiang; Liu, Fang

2017-01-01

To investigate the renal pathological implications in type 2 diabetes mellitus patients with renal involvement. A total of 328 type 2 diabetes mellitus (T2DM) patients with renal involvement who underwent a renal biopsy and received follow-up for at least one year were recruited in our study. The patients were divided into the diabetic nephropathy (DN), non-diabetic renal disease (NDRD), and NDRD superimposed on DN groups based on the pathological diagnosis. Renal outcomes were defined by the initiation of renal replacement therapy or doubling of the serum creatinine. Kaplan-Meier analysis was used to compare renal survival, and Cox proportional hazard analysis was used to determine the predictors of renal outcomes in the DN group. Renal biopsy findings revealed that 188 patients (57.32%) had pure DN, 121 patients (36.89%) had NDRD alone, and 19 patients (5.79%) had NDRD superimposed on DN. The most frequent subclassification of NDRD was membranous nephropathy (MN). Compared with the NDRD and NDRD superimposed on DN groups, patients with pure DN had poorer renal function and lower renal survival rates. In the DN group, the five-year renal survival rates of glomerular classes of I, IIa, IIb, III and IV were 100%, 84.62%, 60%, 47.5% and 33.33%, respectively. Multivariate Cox proportional hazard analysis showed that the glomerular lesions, proteinuria and serum creatinine were independent risk factors for renal outcomes, while interstitial fibrosis/inflammation and arteriolar hyalinosis were not independently associated with renal outcomes in the DN group. Making an accurate pathologic diagnosis by renal biopsy is crucial for diabetes mellitus (DM) patients with renal involvement. The findings of our present study indicated that patients with pure DN had poorer renal outcomes than patients with NDRD or NDRD superimposed on DN. The classification of glomerular lesions, proteinuria and serum creatinine were independent risk factors for renal outcomes in the DN group

Facility effluent monitoring plan for the plutonium-uranium extraction facility

International Nuclear Information System (INIS)

Thompson, R.J.; Sontage, S.

1991-11-01

A facility effluent monitoring plan is required by the US Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan is the first annual report. It shall ensure long-range integrity of the effluent monitoring systems by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and it must be updated as a minimum every three years

Different types of radioactive waste repositories, each suited for a given type of radioactive waste - 59293

International Nuclear Information System (INIS)

Voinis, Sylvie; Boissier, Fabrice; Griffault, Lise; Maillard, Jean Louis; Dutzer, Michel

2012-01-01

Document available in abstract form only. Full text of publication follows: The aim of this article is to present how Andra implements a dedicated solution per waste category. It relies on response to a series of questions concerning the appropriate waste disposal system such as: What type of radiological inventory is involved? What are the half-lives of the radionuclides and the associated timescales concerned for achieving the fundamental protection objective? In that respect, Andra has developed and has implemented methods for all disposal facilities in order to reach common objectives: The immediate and long term protections of human beings and the environment constitute the fundamental objectives of all radioactive-waste disposal facilities. In order to achieve those protections, disposal facilities must be safe. Thus, Andra safety encompasses all design, implementation and operational measures for preventing risks of all kind internal, external during operation and after closure in consistency with defense in depth principles taken into account the peculiarity of waste disposal facilities: (i) balancing operational safety and post-closure safety, (ii) management of nuclear risks in underground repository for some of them, (iii) management of scientific understanding and related uncertainties, and (iv) management of long or very long- timescales. The presentation will illustrate Andra's approach that has or will be conducted and will focus on communalities or peculiarities according to the type of waste and related disposal options regarding the following iterative steps: regulatory safety rules, input data, scenarios, safety assessments. (authors)

Progress towards a new Canadian irradiation-research facility

International Nuclear Information System (INIS)

Lee, A.G.; Lidstone, R.F.

1993-01-01

As reported at the second meeting of the International Group on Research Reactors, Atomic Energy of Canada Limited (AECL) is evaluating its options for future irradiation facilities. During the past year significant progress has been made towards achieving consensus on the irradiation requirements for AECL's major research programs and interpreting those requirements in terms of desirable characteristics for experimental facilities in a research reactor. The next stage of the study involves identifying near-term and long-term options for irradiation-research facilities to meet the requirements. The near-term options include assessing the availability of the NRU reactor and the capabilities of existing research reactors. The long-term options include developing a new irradiation-research facility by adapting the technology base for the MAPLE-X10 reactor design. Because materials testing in support of CANDU power reactors dominates AECL's irradiation requirements, the new reactor concept is called the MAPLE Materials Testing Reactor (MAPLE-MTR). Parametric physics and engineering studies are in progress on alternative MAPLE-MTR configurations to assess the capabilities for the following types of test facilities: - fast-neutron sites, that accommodate materials-irradiation assemblies, - small-diameter vertical fuel test loops that accommodate multielement assemblies, - large-diameter vertical fuel test loops, each able to hold one or more CANDU fuel bundles, - horizontal test loops, each able to hold full-size CANDU fuel bundles or small-diameter multi-element assemblies, and - horizontal beam tubes

Storage facilities of spent nuclear fuel in dry for Mexican nuclear facilities

International Nuclear Information System (INIS)

Salmeron V, J. A.; Camargo C, R.; Nunez C, A.; Mendoza F, J. E.; Sanchez J, J.

2013-10-01

In this article the relevant aspects of the spent fuel storage and the questions that should be taken in consideration for the possible future facilities of this type in the country are approached. A brief description is proposed about the characteristics of the storage systems in dry, the incorporate regulations to the present Nuclear Regulator Standard, the planning process of an installation, besides the approaches considered once resolved the use of these systems; as the modifications to the system, the authorization periods for the storage, the type of materials to store and the consequent environmental impact to their installation. At the present time the Comision Nacional de Seguridad Nuclear y Salvaguardias (CNSNS) considers the possible generation of two authorization types for these facilities: Specific, directed to establish a new nuclear installation with the authorization of receiving, to transfer and to possess spent fuel and other materials for their storage; and General, focused to those holders that have an operation license of a reactor that allows them the storage of the nuclear fuel and other materials that they possess. Both authorizations should be valued according to the necessities that are presented. In general, this installation type represents a viable solution for the administration of the spent fuel and other materials that require of a temporary solution previous to its final disposal. Its use in the nuclear industry has been increased in the last years demonstrating to be appropriate and feasible without having a significant impact to the health, public safety and the environment. Mexico has two main nuclear facilities, the nuclear power plant of Laguna Verde of the Comision Federal de Electricidad (CFE) and the facilities of the TRIGA Reactor of the Instituto Nacional de Investigaciones Nucleares (ININ) that will require in a future to use this type of disposition installation of the spent fuel and generated wastes. (Author)

Reflooding phenomena of German PWR estimated from CCTF [Cylindrical Core Test Facility], SCTF [Slab Core Test Facility] and UPTF [Upper Plenum Test Facility] results

International Nuclear Information System (INIS)

Murao, Y.; Iguchi, T.; Sugimoto, J.

1988-09-01

The reflooding behavior in a PWR with a combined injection type ECCS was studied by comparing the test results from Cylindrical Core Test Facility (CCTF), Slab Core Test Facility (SCTF) and Upper Plenum Test Facility (UPTF). Core thermal-hydraulics is discussed mainly based on SCTF test data. In addition, the water accumulation behavior in hot legs and the break-through characteristics at tie plate are discussed

15 years of The Hungarian integral type test facility: horizontal SG related PMK-2 experiments

International Nuclear Information System (INIS)

Perneczky, L.; Ezsoel, G.; Guba, A.; Szabados, L.

2001-01-01

The PMK-2 experimental facility at the KFKI-AEKI, Budapest, is a full pressure, scaled down model of the primary and partly the secondary circuit of the Paks Nuclear Power Plant. This NPP is equipped with four VVER-440/213-type reactors. Such plants are slightly different from PWRs of usual design and have a number of special features as 6-loop primary circuit, horizontal steam generators, loop seal in hot and cold legs, setpoint pressure of passive safety injection tanks (SIT) higher than secondary pressure, etc. The PMK-2 was primarily designed for investigating operational and off-normal transient processes, as well as small-break loss of coolant accidents of Paks NPP. The volume and power scaling ratios are 1:2070. Due to the importance of gravitational forces in both single- and two-phase flow the elevation ratio is 1:1 except for the lower plenum and pressuriser. The six loops of the plant are modelled by a single active loop. Transients can be started from nominal operating conditions. The pressuriser (PRZ) is connected to the lower part of the hot leg as in the reference system. The core model consists of 19 electrically heated rods. The main circulating pump of the PMK-2 serves to produce the nominal operating conditions and to simulate the flow coast-down following pump trip. The horizontal design of the VVER-440 steam generator is modelled by horizontal heat transfer tubes between hot and cold vertical collectors in the primary side. The emergency core cooling systems including the SITs. High and low pressure injection systems of the Paks NPP are also modelled. The first design of the PMK-NVH facility only modelled the primary circuit of plant. This version was used until 1990. The PMK-2 facility is an upgraded version (first of all by addition of a controlled secondary heat removal system) extending the capability of the test loop to modelling transient processes evoked by initiating events in the secondary circuit or including accident sequences in

Patient Involvement in Safe Delivery: A Qualitative Study.

Science.gov (United States)

Olfati, Forozun; Asefzadeh, Saeid; Changizi, Nasrin; Keramat, Afsaneh; Yunesian, Masud

2015-09-28

Patient involvement in safe delivery planning is considered important yet not widely practiced. The present study aimed at identifythe factors that affect patient involvementin safe delivery, as recommended by parturient women. This study was part of a qualitative research conducted by content analysis method and purposive sampling in 2013.The data were collected through 63 semi-structured interviews in4 hospitalsand analyzed using thematic content analysis. The participants in this research were women before discharge and after delivery. Findings were analyzed using Colaizzi's method. Four categories of factors that could affect patient involvement in safe delivery emerged from our analysis: patient-related (true and false beliefs, literacy, privacy, respect for patient), illness-related (pain, type of delivery, patient safety incidents), health care professional-relatedand task-related factors (behavior, monitoring &training), health care setting-related (financial aspects, facilities). More research is needed to explore the factors affecting the participation of mothers. It is therefore, recommended to: 1) take notice of mother education, their husbands, midwives and specialists; 2) provide pregnant women with insurance coverage from the outset of pregnancy, especially during prenatal period; 3) form a labor pain committee consisting of midwives, obstetricians, and anesthesiologists in order to identify the preferred painless labor methods based on the existing facilities and conditions, 4) carry out research on observing patients' privacy and dignity; 5) pay more attention on the factors affecting cesarean.

Decommissioning engineering systems for nuclear facilities and knowledge inheritance for decommissioning of nuclear facilities

International Nuclear Information System (INIS)

Tachibana, Mitsuo

2016-01-01

Information on construction, operation and maintenance of a nuclear facility is essential in order to plan and implement the decommissioning of the nuclear facility. A decommissioning engineering system collects these information efficiently, retrieves necessary information rapidly, and support to plan the reasonable decommissioning as well as the systematic implementation of dismantling activities. Then, knowledge of workers involved facility operation and dismantling activities is important because decommissioning of nuclear facility will be carried out for a long period. Knowledge inheritance for decommissioning has been carried out in various organizations. This report describes an outline of and experiences in applying decommissioning engineering systems in JAEA and activities related to knowledge inheritance for decommissioning in some organizations. (author)

Cardiac involvement in patients with limb-girdle muscular dystrophy type 2 and Becker muscular dystrophy

DEFF Research Database (Denmark)

Sveen, Marie-Louise; Thune, Jens Jakob; Køber, Lars

2008-01-01

OBJECTIVE: To investigate the extent of cardiac involvement in patients with 1 of the 12 groups of recessively inherited limb-girdle muscular dystrophy type 2 (LGMD2A-L) and Becker muscular dystrophy (BMD). DESIGN: Prospective screening. SETTING: Neuromuscular Clinic and Department of Cardiology...

Mineral facilities of Europe

Science.gov (United States)

Almanzar, Francisco; Baker, Michael S.; Elias, Nurudeen; Guzman, Eric

2010-01-01

This map displays over 1,700 records of mineral facilities within the countries of Europe and western Eurasia. Each record represents one commodity and one facility type at a single geographic location. Facility types include mines, oil and gas fields, and plants, such as refineries, smelters, and mills. Common commodities of interest include aluminum, cement, coal, copper, gold, iron and steel, lead, nickel, petroleum, salt, silver, and zinc. Records include attributes, such as commodity, country, location, company name, facility type and capacity (if applicable), and latitude and longitude geographical coordinates (in both degrees-minutes-seconds and decimal degrees). The data shown on this map and in table 1 were compiled from multiple sources, including (1) the most recently available data from the U.S. Geological Survey (USGS) Minerals Yearbook (Europe and Central Eurasia volume), (2) mineral statistics and information from the USGS Minerals Information Web site (http://minerals.usgs.gov/minerals/pubs/country/europe.html), and (3) data collected by the USGS minerals information country specialists from sources, such as statistical publications of individual countries, annual reports and press releases of operating companies, and trade journals. Data reflect the most recently published table of industry structure for each country at the time of this publication. Additional information is available from the country specialists listed in table 2.

15 CFR 923.13 - Energy facility planning process.

Science.gov (United States)

2010-01-01

... facility planning process. The management program must contain a planning process for energy facilities... 15 Commerce and Foreign Trade 3 2010-01-01 2010-01-01 false Energy facility planning process. 923... affected public and private parties will be involved in the planning process. [61 FR 33806, June 28, 1996...

Structural Test Facility

Data.gov (United States)

Federal Laboratory Consortium — Provides a wide variety of testing equipment, fixtures and facilities to perform both unique aviation component testing as well as common types of materials testing...

Intact long-type DupA protein in Helicobacter pylori is an ATPase involved in multifunctional biological activities.

Science.gov (United States)

Wang, Ming-yi; Chen, Cheng; Shao, Chen; Wang, Shao-bo; Wang, Ai-chu; Yang, Ya-chao; Yuan, Xiao-yan; Shao, Shi-he

2015-04-01

The function of intact long-type DupA protein in Helicobacter pylori was analyzed using immunoblotting and molecular biology techniques in the study. After cloning, expression and purification, ATPase activity of DupA protein was detected. Antibody was produced for localization and interaction proteins analysis. The dupA-deleted mutant was generated for adhesion and CagA protein translocation assay, susceptibility to different pH, IL-8 secretion assay, cytotoxicity to MKN-45 cells and proteins-involved apoptosis analysis. DupA protein exhibited an ATPase activity (129.5±17.8 U/mgprot) and located in bacterial membrane, while it did not involve the adhesion and CagA protein delivery of H. pylori. DupA protein involved the urease secretion as the interaction proteins. The wild type strain had a stronger growth in low pH than the dupA-deleted mutant (p DupA protein located in membrane as ATPase is a true virulence factor associated with duodenal ulcer development involving the IL-8 induction and urease secretion, while it inhibits gastric cancer cell growth in vitro by activating the mitochondria-mediated apoptotic pathway. Copyright © 2015 Elsevier Ltd. All rights reserved.

Type B investigation report of curium-244 exposure at the ORNL TRU Facility, January 15, 1986

International Nuclear Information System (INIS)

Love, G.L.; Butler, H.M.; Duncan, D.T.; Oakes, T.W.

1986-04-01

This Type B Investigative Report provides an evaluation of relevant events and activities that led to, were a part of, or resulted from the release of curium-244 in the Building 7920 facility at ORNL in January 1986. Impacts have been evaluated with respect to employee exposures and the costs and loss of productivity resulting from increased bioassay analyses and activities of investigative committees. Management systems evaluated include (1) training of employees performing lab analyses, (2) adherence to procedures, and (3) response to unusual circumstances

Development of a state radioactive materials storage facility

International Nuclear Information System (INIS)

Schmidt, P.S.

1995-01-01

The paper outlines the site selection and facility development processes of the state of Wisconsin for a radioactive materials facility. The facility was developed for the temporary storage of wastes from abandoned sites. Due to negative public reaction, the military site selected for the facility was removed from consideration. The primary lesson learned during the 3-year campaign was that any project involving radioactive materials is a potential political issue

Facility effluent monitoring plan for the 300 Area Fuels Fabrication Facility

International Nuclear Information System (INIS)

Nickels, J.M.; Brendel, D.F.

1991-11-01

A facility effluent monitoring plan is required by the US Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP- 0438. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan is the first annual report. It shall ensure long-range integrity of the effluent monitoring system by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and it must be updated as a minimum every three years. The Fuel Fabrication Facility in the Hanford 300 Area supported the production reactors from the 1940's until they were shut down in 1987. Prior to 1987 the Fuel Fabrication Facility released both airborne and liquid radioactive effluents. In January 1987 the emission of airborne radioactive effluents ceased with the shutdown of the fuels facility. The release of liquid radioactive effluents have continued although decreasing significantly from 1987 to 1990

Access to Sanitation Facilities among Nigerian Households: Determinants and Sustainability Implications

Directory of Open Access Journals (Sweden)

Ismaila Rimi Abubakar

2017-04-01

Full Text Available Access to improved sanitation facilities is key to the socioeconomic wellbeing and sustainable development of any society. This study examines access to sanitation facilities in Nigeria and explores the socioeconomic and locational factors that influence the type of facility used by households. The study utilizes cross-sectional data from the 2013 Nigeria Demographic and Health Survey, and employs descriptive and inferential statistics for data analyses. The results indicated that 44.2% of households used various kinds of pit latrines, followed by toilets that flush to septic tanks (10.3%. While only 5.3% of the respondents used toilets that connect to sewer systems, about a third (31.5% lacked sanitation facility and the remaining 8.7% used other types of sanitation facilities. Results from chi-square analysis and ANOVA revealed significant statistical differences between the type of sanitation facility households used and their place of residence, geopolitical zone, ethnicity, educational attainment and wealth. Multivariate regression results indicated that the type of household sanitation facility is significantly associated with the mentioned factors as well as household size, gender of the head of the household, type of water sources, number of rooms and access to electricity. Age of the head of the household and type of cooking fuel used were not significant. The study concludes by underscoring the implications of using unimproved sanitation facilities on human health and environmental sustainability.

Enhancing resiliency for elderly populations : Shelter-in-place planning and training at facilities serving elderly populations through the Rhode Island Senior Resiliency Project.

Science.gov (United States)

Smith, Richard; Mozzer, Michael; Albanese, Joseph; Paturas, James; Gold, Julia

2017-06-01

Elderly populations are disproportionately affected by disasters. In part, this is true because for many older adults, special assistance is needed to mitigate the consequences of disasters on their health and wellbeing. In addition, many older adults may reside in diverse living complexes such as long-term care facilities, assisted living facilities and independent-living senior housing complexes. Planning for each type of facility is different and the unique features of these facilities must be considered to develop readiness to deal with disasters. Based on this, the Rhode Island Department of Health established the Senior Resiliency Project to bolster the level of resiliency for the types of living facilities housing older adults. The project involves performing onsite assessments of energy resources, developing site-specific sheltering-inplace and energy resiliency plans, and educating and training facility employees and residents on these plans and steps they can take to be better prepared. Based on the feasibility of conducting these activities within a variety of facilities housing older adults, the project is segmented into three phases. This paper describes survey findings, outcomes of interventions, challenges and recommendations for bridging gaps observed in phases 1 and 2 of the project.

Facility Effluent Monitoring Plan for the Waste Receiving and Processing (WRAP) Facility

Energy Technology Data Exchange (ETDEWEB)

DAVIS, W.E.

2000-03-08

A facility effluent monitoring plan is required by the U.S. Department of Energy in Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee public safety, or the environment. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether these systems are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan ensures long-range integrity of the effluent monitoring systems by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and must be updated, as a minimum, every 3 years.

Facility Effluent Monitoring Plan for the Waste Receiving and Processing (WRAP) Facility

International Nuclear Information System (INIS)

DAVIS, W.E.

2000-01-01

A facility effluent monitoring plan is required by the U.S. Department of Energy in Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee public safety, or the environment. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether these systems are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan ensures long-range integrity of the effluent monitoring systems by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and must be updated, as a minimum, every 3 years

A divergent [5+2] cascade approach to bicyclo[3.2.1]octanes: facile synthesis of ent-kaurene and cedrene-type skeletons.

Science.gov (United States)

He, Chi; Bai, Zengbing; Hu, Jialei; Wang, Bingnan; Xie, Hujun; Yu, Lei; Ding, Hanfeng

2017-07-25

A solvent-dependent oxidative dearomatization-induced divergent [5+2] cascade approach to bicyclo[3.2.1]octanes was described. This novel protocol enables a facile synthesis of a series of diversely functionalized ent-kaurene and cedrene-type skeletons in good yields and excellent diastereoselectivities.

Paternal involvement in pediatric Type 1 diabetes: fathers' and mothers' psychological functioning and disease management.

Science.gov (United States)

Hansen, Jennifer A; Weissbrod, Carol; Schwartz, David D; Taylor, W Patrick

2012-03-01

Psychological functioning in fathers of children with Type 1 diabetes has received relatively little attention compared to mothers. This study examined fathers' perceived involvement in their children's diabetes care as it related to mothers' and fathers' pediatric parenting stress, depression, anxiety, marital satisfaction, and sleep, and to their children's diabetes regimen adherence and glycemic control. Eighty-two mothers and 43 fathers completed questionnaires. Multivariate linear regressions were conducted separately for mothers and fathers to determine the relationships between the perceived amount and the perceived helpfulness of father involvement in child diabetes care on parental psychosocial functioning and child diabetes control. Maternal perceptions of father helpfulness and amount of involvement in illness care were related to improved marital satisfaction and fewer depressive symptoms in mothers. In fathers, perception of their own amount of involvement was related to increased pediatric parenting stress and anxiety. Better child regimen adherence was associated with maternal perceptions of father helpfulness but not the amount of their involvement, while paternal perceptions of their own helpfulness were related to poorer glycemic control. These findings suggest that fathers and mothers may react differently to their roles in childhood illness and that perceptions of their involvement may be differently associated with children's glycemic control and regimen adherence.

Characterization of Iraq's remote nuclear facilities for decommissioning and waste management - 59167

International Nuclear Information System (INIS)

Al-Musawi, Fouad; Jarjies, Adnan; Miller, Ross A.

2012-01-01

The Government of Iraq (GOI) has undertaken efforts to decommission and dismantle former nuclear facilities. The GOI has only preliminary information on some of the former nuclear facilities. This paper will highlight the challenges involved in conducting inspections of the outlying former nuclear facilities in Iraq and present a brief summary of the results of those inspections. The facilities discussed in this paper are located at various sites throughout Iraq, from locations close to Baghdad to those in the north and far western desert areas. Some of the facilities, such as those at the Al Tuwaitha Nuclear Research Center have been visited and characterized. Other facilities, including the following, have not been visited or thoroughly characterized. - Al Jesira, Uranium feed stock production facility; - Adaya, Burial location for contaminated equipment; - Djerf al Naddah, Spent fuel storage facility; - Rashdiya, Centrifuge development center; - Al Qa'im, Uranium (yellowcake) production facility. The visits were conducted to develop an inventory of the buildings/structures that need to be included in decommissioning/dismantlement efforts. The number of buildings, type of construction, size and general condition of the buildings were noted. In addition, attempts were made to determine contamination levels on surfaces, equipment, rubble, etc. This information will be used to support the Iraqi decommissioning and dismantlement project. Because the facilities are scattered throughout the country of Iraq, significant planning and coordination was required to ensure personnel security. Teams consisting of individuals from the Iraqi Ministry of Science and Technology (MoST) and Americans were under military escort when traveling to and visiting the sites. Because of the security issues, time on the ground at each site was limited. This paper will highlight the challenges involved in conducting the inspections of the outlying former nuclear facilities In Iraq and

Durability test of geomembrane liners presumed to avail near surface disposal facilities for low-level waste generated from research, industrial and medical facilities

International Nuclear Information System (INIS)

Nakata, Hisakazu; Amazawa, Hiroya; Sakai, Akihiro; Kurosawa, Ryohei; Sakamoto, Yoshiaki; Kanno, Naohiro; Kashima, Takahiro

2014-02-01

The Low-level Radioactive Waste Disposal Project Center will construct near surface disposal facilities for radioactive wastes from research, industrial and medical facilities. The disposal facilities consist of “concrete pit type” for low-level radioactive wastes and “trench type” for very low level radioactive wastes. As for the trench type disposal facility, two kinds of facility designs are on projects – one for a normal trench type disposal facility without any of engineered barriers and the other for a trench type disposal facility with geomembrane liners that could prevent from causing environmental effects of non radioactive toxic materials contained in the waste packages. The disposal facility should be designed taking basic properties of durability on geomembrane liners into account, for it is exposed to natural environment on a long-term basis. This study examined mechanical strength and permeability properties to assess the durability on the basis of an indoor accelerated exposure experiment targeting the liner materials presumed to avail the conceptual design so far. Its results will be used for the basic and detailed design henceforth by confirming the empirical degradation characteristic with the progress of the exposure time. (author)

Republic of Korea. Closure concept development for LILW disposal facility in Republic of Korea

International Nuclear Information System (INIS)

2001-01-01

Nuclear Environment Technology Institute (NETEC) of Korea Electric Power Corporation (KEPCO) is developing near surface disposal concepts for both a rock cavern type disposal facility, and a vault type facility; two types of facility are being considered to provide more options for LILW repository siting. The conceptual design for the vault type facility will be completed in 1999. As a part of conceptual design effort, a preliminary concept for the disposal facility closure has been identified

Implementing partnerships in nonreactor facility safety analyses

International Nuclear Information System (INIS)

Courtney, J.C.; Perry, W.H.; Phipps, R.D.

1996-01-01

Faculty and students from LSU have been participating in nuclear safety analyses and radiation protection projects at ANL-W at INEL since 1973. A mutually beneficial relationship has evolved that has resulted in generation of safety-related studies acceptable to Argonne and DOE, NRC, and state regulatory groups. Most of the safety projects have involved the Hot Fuel Examination Facility or the Fuel Conditioning Facility; both are hot cells that receive spent fuel from EBR-II. A table shows some of the major projects at ANL-W that involved LSU students and faculty

Next generation storage facility

International Nuclear Information System (INIS)

Schlesser, J.A.

1994-01-01

With diminishing requirements for plutonium, a substantial quantity of this material requires special handling and ultimately, long-term storage. To meet this objective, we at Los Alamos, have been involved in the design of a storage facility with the goal of providing storage capabilities for this and other nuclear materials. This paper presents preliminary basic design data, not for the structure and physical plant, but for the container and arrays which might be configured within the facility, with strong emphasis on criticality safety features

Facility Effluent Monitoring Plan for the 2724-W Protective Equipment Decontamination Facility

International Nuclear Information System (INIS)

Carter, G.J.

1991-11-01

A facility effluent monitoring plan is required by the US Department of Energy in DOE Order 5400.1* for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan is the first annual report. It shall ensure long-range integrity of the effluent monitoring systems by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and it must be updates as a minimum every three years

Analysis of Task Types and Error Types of the Human Actions Involved in the Human-related Unplanned Reactor Trip Events

International Nuclear Information System (INIS)

Kim, Jae Whan; Park, Jin Kyun; Jung, Won Dea

2008-02-01

This report provides the task types and error types involved in the unplanned reactor trip events that have occurred during 1986 - 2006. The events that were caused by the secondary system of the nuclear power plants amount to 67 %, and the remaining 33 % was by the primary system. The contribution of the activities of the plant personnel was identified as the following order: corrective maintenance (25.7 %), planned maintenance (22.8 %), planned operation (19.8 %), periodic preventive maintenance (14.9 %), response to a transient (9.9 %), and design/manufacturing/installation (9.9%). According to the analysis of error modes, the error modes such as control failure (22.2 %), wrong object (18.5 %), omission (14.8 %), wrong action (11.1 %), and inadequate (8.3 %) take up about 75 % of all the unplanned trip events. The analysis of the cognitive functions involved showed that the planning function makes the highest contribution to the human actions leading to unplanned reactor trips, and it is followed by the observation function (23.4%), the execution function (17.8 %), and the interpretation function (10.3 %). The results of this report are to be used as important bases for development of the error reduction measures or development of the error mode prediction system for the test and maintenance tasks in nuclear power plants

Analysis of Task Types and Error Types of the Human Actions Involved in the Human-related Unplanned Reactor Trip Events

Energy Technology Data Exchange (ETDEWEB)

Kim, Jae Whan; Park, Jin Kyun; Jung, Won Dea

2008-02-15

This report provides the task types and error types involved in the unplanned reactor trip events that have occurred during 1986 - 2006. The events that were caused by the secondary system of the nuclear power plants amount to 67 %, and the remaining 33 % was by the primary system. The contribution of the activities of the plant personnel was identified as the following order: corrective maintenance (25.7 %), planned maintenance (22.8 %), planned operation (19.8 %), periodic preventive maintenance (14.9 %), response to a transient (9.9 %), and design/manufacturing/installation (9.9%). According to the analysis of error modes, the error modes such as control failure (22.2 %), wrong object (18.5 %), omission (14.8 %), wrong action (11.1 %), and inadequate (8.3 %) take up about 75 % of all the unplanned trip events. The analysis of the cognitive functions involved showed that the planning function makes the highest contribution to the human actions leading to unplanned reactor trips, and it is followed by the observation function (23.4%), the execution function (17.8 %), and the interpretation function (10.3 %). The results of this report are to be used as important bases for development of the error reduction measures or development of the error mode prediction system for the test and maintenance tasks in nuclear power plants.

Use of the UFTR facilities for precollege nuclear education programs

International Nuclear Information System (INIS)

Vernetson, W.G.

1992-01-01

The University of Florida Training Reactor (UFTR) is a 100-kW light water-cooled, graphite- and light water-moderated modified Argonaut-type reactor, which currently utilizes high enriched (93%) fuel. Since first being licensed to operate at 10 kW in 1959, this facility has had major involvement in college and university level education and research programs both at the University of Florida and at other post-secondary schools around the state of Florida. Utility operator training programs were also a major facility involvement until recent years when the advent of site-specific simulators reduced UFTR usage for such training. Although sometimes not user friendly for innovative research and maintenance programs, the UFTR is an excellent educational and training tool. Service work for outside vendors representing a full spectrum of the nuclear industry has also been significant, especially in the last 15 yr. In contrast, there was little UFTR involvement in precollege education programs prior to 1984. Since that time, the US Dept. of Energy's University Reactor Sharing Program has been a catalyst for developing diverse utilization of the UFTR by both outside educational institutions throughout the state of Florida and faculty members within the University of Florida. With a decline in usage in the early 1980s, the UFTR was in danger of going the way of so many university reactor facilities. The availability of the Reactor Sharing Program has contributed significantly to educational and research opportunities at all levels around the state. Initially, those uses were almost exclusively at the college level. However, the synergistic effects of the internal and external user communities are primarily responsible for the resurgence in usage of the UFTR over the past 8 yr, despite a steady decline in utility operator training

Active use of urban park facilities

DEFF Research Database (Denmark)

Lindberg, Michael; Schipperijn, Jasper

2015-01-01

groups of the facilities. Facilities that provide the opportunity for games and playing activities are more used for PA than facilities directed at individual training of strength and fitness. The opportunity for socializing and playing while being physically active seems important for many users...... was mentioned as a key factor when designing facilities. Our results provide important knowledge to architects, planners and policy makers when aiming at designing activity-promoting facilities in UGS. Future studies need to further investigate the use of facilities among specific target groups, particularly......Abstract Urban green spaces (UGS), and more specific a higher number of facilities in UGS, have been positively associated with physical activity (PA). However, more detailed studies of which facilities generate high levels of PA, for which type of users, are relevant as existing knowledge...

[Cathepsin K as a biomarker of bone involvement in type 1 Gaucher disease].

Science.gov (United States)

Bobillo Lobato, Joaquín; Durán Parejo, Pilar; Núñez Vázquez, Ramiro J; Jiménez Jiménez, Luis M

2015-10-05

Gaucher disease is an inherited disorder caused by deficit of acid β-glucocerebrosidase, responsible for the degradation of glucosylceramide to ceramide and glucose. Although the disorder is primarily hematologic, bone is the second most commonly affected structure. Cathepsin K (CATK) is an enzyme involved in bone remodelling process. It has been proposed that determination of its serum concentrations may provide additional information to other biomarkers. The study included 20 control subjects and 20 Gaucher type 1 patients from Andalusia and Extremadura regions. We analyzed the biomarkers of bone remodelling: the bone alkaline phosphatase (B-ALP), the N-terminal propeptide of type 1 procollagen (P1NP), the β carboxyterminal telopeptide of type 1 collagen (CTx) and the CATK through electrochemiluminescence and immunoassay techniques. There is an increase in levels of CATK, CATK/P1NP and CATK/B-ALP ratios in type 1 Gaucher patients compared to the control group. Considering the existence of skeletal manifestations in the patient group, the CATK and CATK/P1NP ratio showed higher levels in patients with bone damage compared to those without it. Although imaging studies are the gold standard for monitoring bone disease in type 1 Gaucher patients, the utility of CATK should be considered as a possible indicator of bone damage in these patients. Furthermore, this parameter can be used in the monitoring of the treatment of bone pathology. Copyright © 2015 Elsevier España, S.L.U. All rights reserved.

The effects of the Brazilian regulatory inspection programme on nuclear medicine facilities

Energy Technology Data Exchange (ETDEWEB)

Alves, C E G R; Azevedo, E M; Mendes, L C G; Franca, W F L; Gutterres, R F; Goncalves, M [Comissao Nacional de Energia Nuclear-CGMI/CNEN, Rua General Severiano 90, 22290-901, Rio de Janeiro (Brazil); De Sa, L V; Da Rosa, L A R [Instituto de Radioprotecao e Dosimetria-IRD/CNEN, Avenida Salvador Allende s/n, 22780-160, Rio de Janeiro (Brazil)], E-mail: telo@xexeu.org

2009-12-01

This paper aims to demonstrate the importance of the regulatory inspections carried out by the Brazilian regulatory body in the area of nuclear medicine. The main aspects observed during the inspections are presented as well as the time evolution of the non-compliances, according to their occurrence by type. We also evaluate factors concerning the working of the nuclear medicine facility responsible for solving the non-compliances. The results suggest a decrease of occurrence of non-compliances with time that can be related to the strictness of the inspections and the awareness of the personnel in the nuclear medicine facilities. An analysis of radiation dose exposure levels for the professionals involved in nuclear medicine was carried out; although dose values are below regulatory dose limits, their occurrence is not decreasing satisfactorily. Results indicate the need for staff training and commitment of the responsible nuclear medicine facility staff to the radiological protection procedures. Our results also emphasise the importance of continuous coercive actions to improve the level of radiological protection in nuclear medicine facilities in compliance with the standards established by the national regulatory authority and international recommendations.

Nuclear fuel cycle facilities, laboratories, irradiators, particle accelerators, under-decommissioning reactors and radioactive waste management facilities safety. Lessons learned from events notified between 2005 and 2008

International Nuclear Information System (INIS)

2001-01-01

Maintaining high levels of safety in nuclear facilities requires constant vigilance by everyone involved, especially by plant operators who are first and foremost responsible for safety in their facilities. Safety can never be taken for granted; constant efforts must be made to improve it, by taking new knowledge and available operating feedback into account. In this respect, a substantial part of operating feedback is made up of lessons learned from analysing events, incidents or accidents occurring in France or in similar facilities abroad. To encourage the diffusion of operating feedback, IRSN has produced a report concerning events notified to the Nuclear Safety Authority (ASN) by operators of LUDD facilities between 2005 and 2008. The main objective is to make general lessons for safety in this type of facility available based on a cross-disciplinary analysis of notified events and noted evolution trends. IRSN has had tools for managing information concerning events occurring in France and abroad for many years. These tools are used to analyse the events in order to take into account the relevant lessons learned in the safety assessments performed on behalf of ASN and also to define study and research programmes to maintain its expertise and expand its knowledge. The report has 4 sections: - the first section (chapters 2 to 4) presents the LUDD facilities so that the facilities themselves, their diversity and the main associated risks can be better understood. It also includes a brief reminder of plant operator obligations in notifying events and describes the database used by the Institute to manage the data relating to the notified events; - the second section (chapter 5) summarises the main changes noted in the events notified to ASN during 2005 to 2008 and provides an overall assessment of the consequences of these events for the environment, the population and the workers; - the third section (chapter 6) describes significant events occurring in France

Facility effluent monitoring plan for the Waste Receiving and Processing Facility Module 1

International Nuclear Information System (INIS)

Lewis, C.J.

1995-10-01

A facility effluent monitoring plan is required by the US Department of Energy in Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal state, and local requirements. This facility effluent monitoring plan shall ensure lonq-range integrity of the effluent monitoring systems by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and it must be updated as a minimum every three years

Identification of the chemical inventory of different paint types applied in nuclear facilities

International Nuclear Information System (INIS)

Sabrina Tietze; Foreman, M.R.St.J.; Ekberg, CH.H.; Chalmers University of Technology, Chemical and Biological Engineering, Goeteborg; Dongen van, B.E.

2013-01-01

The floors, concrete walls and many of the metal surfaces in nuclear power plant containments are coated with zinc primers or paint films to preserve the metal surfaces and simplify decontamination in the containment after the occurrence of a severe nuclear incident or accident. A chemical examination of paint films from different nuclear installations out of operation, as well as current operating ones, reveals that different types of paints are used whose composition can vary significantly. Results obtained for one type of paint at a certain nuclear site are in most cases unlikely to be comparable with sites painted with another type of paint. During normal operation and particularly during nuclear accidents, the paints will degrade under the high temperature, steam and irradiation influence. As paint and its degradation products can act as sources and depots for volatile iodine compounds, the type and aging conditions of the paint films will have a significant impact on the source term of the volatile fission product iodine. Thus, great care should be taken when extrapolating any results obtained for the interaction of radioactive iodine with one paint product to a different paint product. The main focus of the study is a comparison of the chemical profile of paint films applied in Swedish nuclear power plants. Teknopox Aqua V A, an epoxy paint recently used at Ringhals 2, and an emulsion paint used in the scrubber buildings of Ringhals 1-4 are compared with a paint film from Barsebaeck nuclear power plant unit 1 that had been aged under real reactor conditions for 20 years. In addition, two paint films, an emulsion and a gloss paint, used in an international nuclear fuel reprocessing facility, are compared with the paints from the Swedish nuclear power plants. (author)

Medication errors: classification of seriousness, type, and of medications involved in the reports from a university teaching hospital

Directory of Open Access Journals (Sweden)

Gabriella Rejane dos Santos Dalmolin

2013-12-01

Full Text Available Medication errors can be frequent in hospitals; these errors are multidisciplinary and occur at various stages of the drug therapy. The present study evaluated the seriousness, the type and the drugs involved in medication errors reported at the Hospital de Clínicas de Porto Alegre. We analyzed written error reports for 2010-2011. The sample consisted of 165 reports. The errors identified were classified according to seriousness, type and pharmacological class. 114 reports were categorized as actual errors (medication errors and 51 reports were categorized as potential errors. There were more medication error reports in 2011 compared to 2010, but there was no significant change in the seriousness of the reports. The most common type of error was prescribing error (48.25%. Errors that occurred during the process of drug therapy sometimes generated additional medication errors. In 114 reports of medication errors identified, 122 drugs were cited. The reflection on medication errors, the possibility of harm resulting from these errors, and the methods for error identification and evaluation should include a broad perspective of the aspects involved in the occurrence of errors. Patient safety depends on the process of communication involving errors, on the proper recording of information, and on the monitoring itself.

Development and validation of the collaborative parent involvement scale for youths with type 1 diabetes.

Science.gov (United States)

Nansel, Tonja R; Rovner, Alisha J; Haynie, Denise; Iannotti, Ronald J; Simons-Morton, Bruce; Wysocki, Timothy; Anderson, Barbara; Weissberg-Benchell, Jill; Laffel, Lori

2009-01-01

To develop and test a youth-report measure of collaborative parent involvement in type 1 diabetes management. Initial item development and testing were conducted with 81 youths; scale refinement and validation were conducted with 122 youths from four geographic regions. Descriptive statistics, Cronbach's alpha, and factor analyses were conducted to select items comprising the scale. Correlations with parenting style and parent diabetes responsibility were examined. Multiple regression analyses examining associations with quality of life, adherence, and glycemic control were conducted to assess concurrent validity. The measure demonstrated strong internal consistency. It was modestly associated with parenting style, but not with parent responsibility for diabetes management. A consistent pattern of associations with quality of life and adherence provide support for the measure's concurrent validity. This brief youth-report measure of parent collaborative involvement assesses a unique dimension of parent involvement in diabetes management associated with important youth outcomes.

Involvement of viral envelope GP2 in Ebola virus entry into cells expressing the macrophage galactose-type C-type lectin

International Nuclear Information System (INIS)

Usami, Katsuaki; Matsuno, Keita; Igarashi, Manabu; Denda-Nagai, Kaori; Takada, Ayato; Irimura, Tatsuro

2011-01-01

Highlights: → Ebola virus infection is mediated by binding to and fusion with the target cells. → Structural feature of the viral glycoprotein determines the infectivity. → Surface C-type lectin, MGL, of macrophages and dendritic cells mediate the infection. → GP2, one of glycoprotein subunits, plays an essential role in MGL-mediated infection. → There is a critical amino acid residue involved in high infectivity. -- Abstract: Ebola virus (EBOV) infection is initiated by the interaction of the viral surface envelope glycoprotein (GP) with the binding sites on target cells. Differences in the mortality among different species of the Ebola viruses, i.e., Zaire ebolavirus (ZEBOV) and Reston ebolavirus (REBOV), correspond to the in vitro infectivity of the pseudo-typed virus constructed with the GPs in cells expressing macrophage galactose-type calcium-type lectin (MGL/CD301). Through mutagenesis of GP2, the transmembrane-anchored subunit of GP, we found that residues 502-527 of the GP2 sequence determined the different infectivity between VSV-ZEBOV GP and -REBOV GP in MGL/CD301-expressing cells and a histidine residue at position 516 of ZEBOV GP2 appeared essential in the differential infectivity. These findings may provide a clue to clarify a molecular basis of different pathogenicity among EBOV species.

Involvement of viral envelope GP2 in Ebola virus entry into cells expressing the macrophage galactose-type C-type lectin

Energy Technology Data Exchange (ETDEWEB)

Usami, Katsuaki [Laboratory of Cancer Biology and Molecular Immunology, Graduate School of Pharmaceutical Sciences, University of Tokyo, Tokyo 113-0033 (Japan); Matsuno, Keita; Igarashi, Manabu [Department of Global Epidemiology, Hokkaido University Research Center for Zoonosis Control, Sapporo 001-0020 (Japan); Denda-Nagai, Kaori [Laboratory of Cancer Biology and Molecular Immunology, Graduate School of Pharmaceutical Sciences, University of Tokyo, Tokyo 113-0033 (Japan); Takada, Ayato [Department of Global Epidemiology, Hokkaido University Research Center for Zoonosis Control, Sapporo 001-0020 (Japan); Irimura, Tatsuro, E-mail: irimura@mol.f.u-tokyo.ac.jp [Laboratory of Cancer Biology and Molecular Immunology, Graduate School of Pharmaceutical Sciences, University of Tokyo, Tokyo 113-0033 (Japan)

2011-04-01

Highlights: {yields} Ebola virus infection is mediated by binding to and fusion with the target cells. {yields} Structural feature of the viral glycoprotein determines the infectivity. {yields} Surface C-type lectin, MGL, of macrophages and dendritic cells mediate the infection. {yields} GP2, one of glycoprotein subunits, plays an essential role in MGL-mediated infection. {yields} There is a critical amino acid residue involved in high infectivity. -- Abstract: Ebola virus (EBOV) infection is initiated by the interaction of the viral surface envelope glycoprotein (GP) with the binding sites on target cells. Differences in the mortality among different species of the Ebola viruses, i.e., Zaire ebolavirus (ZEBOV) and Reston ebolavirus (REBOV), correspond to the in vitro infectivity of the pseudo-typed virus constructed with the GPs in cells expressing macrophage galactose-type calcium-type lectin (MGL/CD301). Through mutagenesis of GP2, the transmembrane-anchored subunit of GP, we found that residues 502-527 of the GP2 sequence determined the different infectivity between VSV-ZEBOV GP and -REBOV GP in MGL/CD301-expressing cells and a histidine residue at position 516 of ZEBOV GP2 appeared essential in the differential infectivity. These findings may provide a clue to clarify a molecular basis of different pathogenicity among EBOV species.

Waste isolation facility description: bedded salt

Energy Technology Data Exchange (ETDEWEB)

1976-09-01

The waste isolation facility is designed to receive and store three basic types of solidified wastes: high-level wastes, intermediate level high-gamma transuranic waste, and low-gamma transuranic wastes. The facility under consideration in this report is designed for bedded salt at a depth of approximately 1800 ft. The present design for the facility includes an area which would be used initially as a pilot facility to test the viability of the concept, and a larger facility which would constitute the final storage area. The total storage area in the pilot facility is planned to be 77 acres and in the fuel facility 1601 acres. Other areas for shaft operations and access would raise the overall size of the total facility to slightly less than 2,000 acres. The following subjects are discussed in detail: surface facilities, shaft design and characteristics, design and construction of the underground waste isolation facility, ventilation systems, and design requirements and criteria. (LK)

Waste isolation facility description: bedded salt

International Nuclear Information System (INIS)

1976-09-01

The waste isolation facility is designed to receive and store three basic types of solidified wastes: high-level wastes, intermediate level high-gamma transuranic waste, and low-gamma transuranic wastes. The facility under consideration in this report is designed for bedded salt at a depth of approximately 1800 ft. The present design for the facility includes an area which would be used initially as a pilot facility to test the viability of the concept, and a larger facility which would constitute the final storage area. The total storage area in the pilot facility is planned to be 77 acres and in the fuel facility 1601 acres. Other areas for shaft operations and access would raise the overall size of the total facility to slightly less than 2,000 acres. The following subjects are discussed in detail: surface facilities, shaft design and characteristics, design and construction of the underground waste isolation facility, ventilation systems, and design requirements and criteria

Recent Experiments Involving Few-Nucleon Systems

Science.gov (United States)

Tornow, W.

2014-08-01

Recent experimental results are presented for reactions involving A = 3 to A = 6 nuclear systems. The emphasis is on unique data obtained at new experimental facilities. It is shown that the inertial confinement fusion facilities OMEGA and NIF provide a largely unexpected opportunity for experimental few-body physics to both obtain data of unprecedented quality and extend previous measurements to energies not accessible in the past. Whenever possible, data are compared to state-of-the-art theoretical calculations.

Recent Experiments Involving Few-Nucleon Systems

International Nuclear Information System (INIS)

Tornow, W.

2014-01-01

Recent experimental results are presented for reactions involving A = 3 to A = 6 nuclear systems. The emphasis is on unique data obtained at new experimental facilities. It is shown that the inertial confinement fusion facilities OMEGA and NIF provide a largely unexpected opportunity for experimental few-body physics to both obtain data of unprecedented quality and extend previous measurements to energies not accessible in the past. Whenever possible, data are compared to state-of-the-art theoretical calculations. (author)

Facility type and primary care performance in sub-district health promotion hospitals in Northern Thailand.

Directory of Open Access Journals (Sweden)

Nithra Kitreerawutiwong

Full Text Available Poor and middle-income Thai people rely heavily on primary care health services. These are staffed by a range of professionals. However, it is unknown whether the performance of primary care varies according to the staffing and organization of local service delivery units. Tambon (sub-district health promotion hospitals (THPHs were introduced in 2009 to upgrade the services offered by the previous health centres, but were faced with continuing shortages of doctors and nurses. The Ministry of Public Health (MoPH designated three categories of THPH, defined according to whether they were regularly staffed by a medical practitioner, a qualified nurse or non-clinical public health officers. This study aimed to compare the performance of primary care offered by the three different types of primary care facilities in one public health region of Northern Thailand (Public Health Region 2.A cross-sectional survey was undertaken in 2013. Data were collected on accessibility, continuity, comprehensiveness, co-ordination and community orientation of care from 825 patients attending 23 primary care facilities. These were selected to include the three officially-designated types of Tambon (sub-district health promotion hospitals (THPHs led by medical, nursing or public health personnel. Survey scores were compared in unadjusted and adjusted analyses.THPHs staffed only by public health officers achieved the highest performance score (Mean = 85.14, SD. = 7.30, followed by THPHs staffed by qualified nurses (Mean = 82.86, SD. = 7.06. THPHs staffed by a doctor on rotation returned the lowest scores (Mean = 81.63, SD. = 7.22.Differences in overall scores resulted mainly from differences in reported accessibility, continuity, and comprehensiveness of care, rather than staff skill-mix per se. Policy on quality improvement should therefore focus on improving performance in these areas.

10 CFR 75.10 - Facility information.

Science.gov (United States)

2010-01-01

...) The identification of the facility, stating its general character, purpose, nominal capacity (thermal... used for routine purposes; (2) A description of the general arrangement of the facility with reference... information must be submitted: (1) Regarding a modification of a type described in the license or certificate...

Facility effluent monitoring plan for the tank farms facilities

International Nuclear Information System (INIS)

Crummel, G.M.; Gustavson, R.D.; Kenoyer, J.L.; Moeller, M.P.

1991-11-01

A facility effluent monitoring plan is required by the US Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan is the first annual report. It shall ensure long-range integrity of the effluent monitoring systems by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and it must be updated as a minimum three years. A variety of liquid wastes are generated in processing treatment, and disposal operations throughout the Hanford Site. The Tank Farms Project serves a major role in Hanford Site waste management activities as the temporary repository for these wastes. Stored wastes include hazardous components regulated under the Resource Conservation and Recovery Act of 1976 (RCRA) and as by-product material regulated under the Atomic Energy Act of 1954. A total of 177 single- and double-shell tanks (SST and DST) have been constructed in the 200 East and 200 West Areas of the Hanford Site. These facilities were constructed to various designs from 1943 to 1986. The Tank Farms Project is comprised of these tanks along with various transfer, receiving, and treatment facilities

The Dark Triad and three types of jealousy : Its’ relations among heterosexuals and homosexuals involved in a romantic relationship

NARCIS (Netherlands)

Barelds, Dick P.H.; Dijkstra, Pieternel; Groothof, Hinke A.K.; Pastoor, Charlotte D.

2017-01-01

The current study examined the relations between the three Dark Triad (DT) traits and three types of jealousy, among both heterosexual and homosexual men and women involved in a romantic relationship (n = 439). It was hypothesized that the three DT traits would be related positively to those types

Declassification of radioactive water from a pool type reactor after nuclear facility dismantling

Science.gov (United States)

Arnal, J. M.; Sancho, M.; García-Fayos, B.; Verdú, G.; Serrano, C.; Ruiz-Martínez, J. T.

2017-09-01

This work is aimed to the treatment of the radioactive water from a dismantled nuclear facility with an experimental pool type reactor. The main objective of the treatment is to declassify the maximum volume of water and thus decrease the volume of radioactive liquid waste to be managed. In a preliminary stage, simulation of treatment by the combination of reverse osmosis (RO) and evaporation have been performed. Predicted results showed that the combination of membrane and evaporation technologies would result in a volume reduction factor higher than 600. The estimated time to complete the treatment was around 650 h (25-30 days). For different economical and organizational reasons which are explained in this paper, the final treatment of the real waste had to be reduced and only evaporation was applied. The volume reduction factor achieved in the real treatment was around 170, and the time spent for treatment was 194 days.

2 MeV, 60 kW dual-beam type electron accelerator irradiation facility

International Nuclear Information System (INIS)

Yotsumoto, Keiichi; Kanazawa, Takao; Haruyama, Yasuyuki; Agematsu, Takashi; Mizuhashi, Kiyoshi; Sunaga, Hiromi; Washino, Masamitsu; Tamura, Naoyuki

1984-02-01

The specification of new irradiation facility which has been constructed from 1978 through 1981 as the replacement of 1st Accelerator of JAERI, TRCRE are described. The accelerator is the Cockcroft-Walton type and both vertical and horizontal accelerating tubes are arranged on a single high voltage generator. Transferring of the high voltage to the horizontal accelerating tube is performed with the high voltage changing system in the pressure vessel. The output ratings of the accelerator are 2 MV of acceleration voltage and 30 mA of beam current. By providing the dual beam system, two irradiation rooms, one for vertical and the other for horizontal beam, are independently operationable. Persons can enter the horizontal irradiation room for experimental setting even when the vertical irradiation room is in operation. The specification of the buildings, the exhaust air treatment system, the irradiation conveyor and the safety observation system are also described. (author)

FFTF [Fast Flux Test Facility] management

International Nuclear Information System (INIS)

Bennett, C.L.

1986-11-01

Fuel Management at the Fast Flux Test Facility (FFTF) involves more than just the usual ex-core and in-core management of standard fuel and non-fuel components between storage locations and within the core since it is primarily an irradiation test facility. This mission involves testing an ever increasing variety of fueled and non-fueled experiments, each having unique requirements on the reactor core as well as having its own individual impact on the reload design. This paper describes the fuel management process used by the Westinghouse Hanford Company Core Engineering group that has led to the successful reload design of nine operating cycles and the irradiation of over 120 tests

Solid Waste Management Facilities with Permits by the Iowa DNR

Data.gov (United States)

Iowa State University GIS Support and Research Facility — All types of facilities that handle solid waste, including: sanitary landfills, appliance demanufacturing facilities, transfer stations, land application sites,...

14 CFR 21.43 - Location of manufacturing facilities.

Science.gov (United States)

2010-01-01

... 14 Aeronautics and Space 1 2010-01-01 2010-01-01 false Location of manufacturing facilities. 21.43... CERTIFICATION PROCEDURES FOR PRODUCTS AND PARTS Type Certificates § 21.43 Location of manufacturing facilities... location of the manufacturer's facilities places no undue burden on the FAA in administering applicable...

Decommissioning of Facilities. General Safety Requirements. Pt. 6

Energy Technology Data Exchange (ETDEWEB)

NONE

2014-07-15

Decommissioning is the last step in the lifetime management of a facility. It must also be considered during the design, construction, commissioning and operation of facilities. This publication establishes requirements for the safe decommissioning of a broad range of facilities: nuclear power plants, research reactors, nuclear fuel cycle facilities, facilities for processing naturally occurring radioactive material, former military sites, and relevant medical, industrial and research facilities. It addresses all the aspects of decommissioning that are required to ensure safety, aspects such as roles and responsibilities, strategy and planning for decommissioning, conduct of decommissioning actions and termination of the authorization for decommissioning. It is intended for use by those involved in policy development, regulatory control and implementation of decommissioning.

In situ ion irradiation/implantation studies in the HVEM-Tandem Facility at Argonne National Laboratory

International Nuclear Information System (INIS)

Allen, C.W.; Funk, L.L.; Ryan, E.A.; Taylor, A.

1988-09-01

The HVEM-Tandem User Facility at Argonne National Laboratory interfaces two ion accelerators, a 2 MV tandem accelerator and a 650 kV ion implanter, to a 1.2 MV high voltage electron microscope. This combination allows experiments involving simultaneous ion irradiation/ion implantation, electron irradiation and electron microscopy/electron diffraction to be performed. In addition the availability of a variety of microscope sample holders permits these as well as other types of in situ experiments to be performed at temperatures ranging from 10-1300 K, with the sample in a stressed state or with simultaneous determination of electrical resistivity of the specimen. This paper summarizes the details of the Facility which are relevant to simultaneous ion beam material modification and electron microscopy, presents several current applications and briefly describes the straightforward mechanism for potential users to access this US Department of Energy supported facility. 7 refs., 1 fig., 1 tab

Radiological assessment of the PET facility

International Nuclear Information System (INIS)

Discacciatti, Adrian; Cruzate, Juan A.; Bomben, Ana M.; Carelli, Jorge; Namias, Mario

2008-01-01

The radiological assessment of a Positron Emission Tomography (PET) facility consists of the evaluation of the annual effective dose to workers exposed occupationally and to members of the public. This evaluation takes into account the radionuclide involved, the characteristics of the facility, the working procedure and the expected number of patients per year. This paper details the methodology used by the Nuclear Regulatory Authority (in Spanish ARN) to independently assess the design of PET facilities considering only radioprotection aspects. The results of the evaluation are compared with the design requirements established in the ARN regulations to determine whether or not, the facility complies with those requirements, both for workers and for members of the public. As an example of the above mentioned methodology, this paper presents the assessment of a PET facility located in Buenos Aires called Fundacion Centro Diagnostico Nuclear (FCDN). (author)

Nuclear facilities in the Federal Republic of Germany

International Nuclear Information System (INIS)

1991-01-01

The information brochure is a survey of installed nuclear facilities in Germany, presenting on one page each a picture of a nuclear power plant together with the main relevant data, or of other type of nuclear facilities belonging to the nuclear fuel cycle (such as fuel production plant, fuel production plant, fuel element storage facilities, and facilities for spent fuel and waste management). (UA) [de

Design Standards for School Art Facilities

Science.gov (United States)

National Art Education Association, 2015

2015-01-01

"Design Standards for School Art Facilities" is an invaluable resource for any school or school district looking to build new facilities for the visual arts or renovate existing ones. Discover detailed information about spaces for the breadth of media used in the visual arts. Photographs illustrate all types of features including…

Explotation of irradiation facilities. Safety handbook

International Nuclear Information System (INIS)

Prieto Miranda, Enrique Franscisco; Melo Crespo, Jose Carlos

1997-01-01

At present in the world there are more of 160 gamma radiation facilities and more of 600 electron bean accelerators in operation, at least one in each member state of International Atomic Energy Agency. In this paper is elaborated a Manual with the security criteria to operation of these facility types

Comparison of mass balance, energy consumption and cost of composting facilities for different types of organic waste

International Nuclear Information System (INIS)

Zhang Huijun; Matsuto, Toshihiko

2011-01-01

Mass balance, energy consumption and cost are basic pieces of information necessary for selecting a waste management technology. In this study, composting facilities that treat different types of organic waste were studied by questionnaire survey and via a chemical analysis of material collected at the facilities. The mass balance was calculated on a dry weight basis because the moisture content of organic waste was very high. Even though the ratio of bulking material to total input varied in the range 0-65% on a dry basis, the carbon and ash content, carbon/nitrogen ratio, heavy metal content and inorganic nutrients in the compost were clearly influenced by the different characteristics of the input waste. The use of bulking material was not correlated with ash or elemental content in the compost. The operating costs were categorised into two groups. There was some economy of scale for wages and maintenance cost, but the costs for electricity and fuel were proportional to the amount of waste. Differences in operating costs can be explained by differences in the process characteristics.

Facility effluent monitoring plan for the uranium trioxide facility

International Nuclear Information System (INIS)

Thompson, R.J.; Sontag, S.

1991-11-01

A facility effluent monitoring plant is required by the US Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan is the first annual report. It shall ensure long-range integrity of the effluent monitoring systems by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and it must be updated as a minimum every three years. The UO 3 Plant is located in the south-central portion of the 200 West Area of the Hanford Site. The plant consists of two primary processing buildings and several ancillary facilities. The purpose of the UO 3 Plant is to receive uranyl nitrate hexahydrate (UNH) from the Plutonium-Uranium Extraction (PUREX) Plant, concentrate it, convert the UNH to uranium trioxide (UO 3 ) powder by calcination and package it for offsite shipment. The UO 3 Plant has been placed in a standby mode. There are two liquid discharges, and three gaseous exhaust stacks, and seven building exhausters that are active during standby conditions

The emergence of care facilities in Thailand for older German-speaking people: structural backgrounds and facility operators as transnational actors.

Science.gov (United States)

Bender, Désirée; Hollstein, Tina; Schweppe, Cornelia

2017-12-01

This paper presents findings from an ethnographic study of old age care facilities for German-speaking people in Thailand. It analyses the conditions and processes behind the development and specific designs of such facilities. It first looks at the intertwinement, at the socio-structural level, of different transborder developments in which the facilities' emergence is embedded. Second, it analyses the processes that accompany the emergence, development and organisation of these facilities at the local level. In this regard, it points out the central role of the facility operators as transnational actors who mediate between different frames of reference and groups of actors involved in these facilities. It concludes that the processes of mediation and intertwining are an important and distinctive feature of the emergence of these facilities, necessitated by the fact that, although the facilities are located in Thailand, their 'markets' are in the German-speaking countries of their target groups.

Selection of away-from-reactor facilities for spent fuel storage. A guidebook

International Nuclear Information System (INIS)

2007-09-01

This publication aims to provide information on the approaches and criteria that would have to be considered for the selection of away-from-reactor (AFR) type spent fuel storage facilities, needs for which have been growing in an increasing number of Member States producing nuclear power. The AFR facilities can be defined as a storage system functionally independent of the reactor operation providing the role of storage until a further destination such as a disposal) becomes available. Initially developed to provide additional storage space for spent fuel, some AFR storage options are now providing additional spaces for extended storage of spent fuel with a prospect for long term storage, which is becoming a progressive reality in an increasing number of Member States due to the continuing debate on issues associated with the endpoints for spent fuel management and consequent delays in the implementation of final steps, such as disposal. The importance of AFR facilities for storage of spent fuel has been recognized for several decades and addressed in various IAEA publications in the area of spent fuel management. The Guidebook on Spent Fuel Storage (Technical Reports Series No. 240 published in 1984 and revised in 1991) discusses factors to be considered in the evaluation of spent fuel storage options. A technical committee meeting (TCM) on Selection of Dry Spent Fuel Storage Technologies held in Tokyo in 1995 also deliberated on this issue. However, there has not been any stand-alone publication focusing on the topic of selection of AFR storage facilities. The selection of AFR storage facilities is in fact a critical step for the successful implementation of spent fuel management programmes, due to the long operational periods required for storage and fuel handling involved with the additional implication of subsequent penalties in reversing decisions or changing the option mid-stream especially after the construction of the facility. In such a context, the long

Helmholtz and Diffusion Equations Associated with Local Fractional Derivative Operators Involving the Cantorian and Cantor-Type Cylindrical Coordinates

Directory of Open Access Journals (Sweden)

Ya-Juan Hao

2013-01-01

Full Text Available The main object of this paper is to investigate the Helmholtz and diffusion equations on the Cantor sets involving local fractional derivative operators. The Cantor-type cylindrical-coordinate method is applied to handle the corresponding local fractional differential equations. Two illustrative examples for the Helmholtz and diffusion equations on the Cantor sets are shown by making use of the Cantorian and Cantor-type cylindrical coordinates.

Development and Validation of the Collaborative Parent Involvement Scale for Youths with Type 1 Diabetes

OpenAIRE

Nansel, Tonja R.; Rovner, Alisha J.; Haynie, Denise; Iannotti, Ronald J.; Simons-Morton, Bruce; Wysocki, Timothy; Anderson, Barbara; Weissberg-Benchell, Jill; Laffel, Lori

2008-01-01

Objective To develop and test a youth-report measure of collaborative parent involvement in type 1 diabetes management. Methods Initial item development and testing were conducted with 81 youths; scale refinement and validation were conducted with 122 youths from four geographic regions. Descriptive statistics, Cronbach's α, and factor analyses were conducted to select items comprising the scale. Correlations with parenting style and parent diabetes responsibility were examined. Multiple regr...

Using GIFTS on the Cray-1 for the large coil test facility test: stand design analysis

International Nuclear Information System (INIS)

Baudry, T.V.; Gray, W.H.

1981-06-01

The GIFTS finite element program has been used extensively throughout the Large Coil Test Facility (LCTF) test stand design analysis. Effective use has been made of GIFTS both as a preprocessor to other finite element programs and as a complete structural analysis package. The LCTF test stand design involved stress analysis ranging from simple textbook-type problems to very complicated three-dimensional structural problems. Two areas of the design analysis are discussed

77 FR 33243 - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving...

Science.gov (United States)

2012-06-05

... expansion process, thermal expansion mismatch between the tube and tubesheet, and from the differential... NUCLEAR REGULATORY COMMISSION [NRC-2012-0125] Applications and Amendments to Facility Operating...

Thermal Analysis Of A 9975 Package In A Facility Fire Accident

International Nuclear Information System (INIS)

Gupta, N.

2011-01-01

Surplus plutonium bearing materials in the U.S. Department of Energy (DOE) complex are stored in the 3013 containers that are designed to meet the requirements of the DOE standard DOE-STD-3013. The 3013 containers are in turn packaged inside 9975 packages that are designed to meet the NRC 10 CFR Part 71 regulatory requirements for transporting the Type B fissile materials across the DOE complex. The design requirements for the hypothetical accident conditions (HAC) involving a fire are given in 10 CFR 71.73. The 9975 packages are stored at the DOE Savannah River Site in the K-Area Material Storage (KAMS) facility for long term of up to 50 years. The design requirements for safe storage in KAMS facility containing multiple sources of combustible materials are far more challenging than the HAC requirements in 10 CFR 71.73. While the 10 CFR 71.73 postulates an HAC fire of 1475 F and 30 minutes duration, the facility fire calls for a fire of 1500 F and 86 duration. This paper describes a methodology and the analysis results that meet the design limits of the 9975 component and demonstrate the robustness of the 9975 package.

Recruitment of Mobility Limited Older Adults Into a Facility-Led Exercise-Nutrition Study: The Effect of Social Involvement.

Science.gov (United States)

Corcoran, Michael P; Nelson, Miriam E; Sacheck, Jennifer M; Reid, Kieran F; Kirn, Dylan; Fielding, Roger A; Folta, Sara C

2016-08-01

Older adults are among the most challenging population groups to enroll into health-related research. This article describes two methods used by investigators to recruit mobility limited older adults residing at assisted living or senior housing (SH) facilities into a facility-led exercise-nutrition research study. Sedentary older adults were recruited from 42 different assisted living facilities (ALFs) or SH communities. Two different recruitment approaches were used: At 22 sites, investigators conducted heavily advertised informational sessions to recruit participants (Info only). At 20 locations, these sessions were preceded by attendance of a study team member at various activities offered by the facility over the preceding 2 weeks (activity attendance). Population reach, enrollment, personnel cost, and time required to recruit at least five participants at each facility was measured. Reasons for declining participation and withdrawal rate were also measured. Sixty percent more residents elected to be screened for eligibility when study personnel attended an activity offered by the facility. Activity attendance resulted in significantly less time, costs, and participant withdrawals compared with facilities with no activity attendance. Study team member attendance at activities offered by senior living facilities reduces cost and duration of recruitment and improves study retention. Interventions targeting this demographic are likely to benefit from deliberately building trust and familiarity among the resident population at senior living communities as part of the recruitment process. © The Author 2015. Published by Oxford University Press on behalf of The Gerontological Society of America. All rights reserved. For permissions, please e-mail: journals.permissions@oup.com.

Oak Ridge low-level waste disposal facility designs

International Nuclear Information System (INIS)

Van Hoesen, S.D.; Jones, L.S.

1991-01-01

The strategic planning process that culuminates in the identification, selection, construction, and ultimate operation of treatment, storage, and disposal facilities for all types of low-level waste (LLW) generated on the Oak Ridge Reservation (ORR) was conducted under the Low-Level Waste Disposal Development and Demonstration (LLWDDD) Program. This program considered management of various concentrations of short half-life radionuclides generated principally at Oak Ridge National Laboratory (ORNL) and long half-life radionuclides (principally uranium) generated at the Oak Ridge Y-12 Plant and the Oak Ridge K-25 Plant. The LLWDDD Program is still ongoing and involves four phases: (1) alternative identification and evaluation, (2) technology demonstration, (3) limited operational implementation, and (4) full operational implementation. This document provides a discussion of these phases

Pore pressure measurement plan of near field rock used on three dimensional groundwater flow analysis in demonstration test of cavern type disposal facility

International Nuclear Information System (INIS)

Onuma, Kazuhiro; Terada, Kenji; Matsumura, Katsuhide; Koyama, Toshihiro; Yajima, Kazuaki

2008-01-01

Demonstration test of underground cavern type disposal facilities is planed though carrying out construction of full scale engineering barrier system which simulated in the underground space in full scale and under actual environment. This test consists of three part, these are construction test, performance test and measurement test. Behavior of near field rock mass is measured about hydrological behavior under and after construction to evaluate effect at test facility. To make plan of pore pressure measurement, three dimensional groundwater flow analysis has been carried out. Based on comparison of analysis before and after test, detail plan has been studied. (author)

Sustainability and the facilities management in Malaysia

Directory of Open Access Journals (Sweden)

Asbollah Asra Zaliza

2016-01-01

Full Text Available Facilities Management (FM in the industry of environment involves numerous expertise, especially from the management side. Other than that, technology and finance are the other factors involved as well. One essential aspect of FM, other than the emphasis on technical operation, is its performance. In parallel, the performance does impact occupant behaviour and, at the same time, this performance does affect the environment. In short, this indicates that FM is in a key position to participate in delivering a sustainable environment for the industry of built environment. Sustainable facilities Management (SFM is crucial because buildings consume more resources which will, in consequence, negatively impact the environment and generate large amounts of waste. This justifies the importance of sustainability under the umbrella of facilities management. However, FM is quite new in Malaysia’s environment. Government agencies, such as JKR, have adopted and are practicing FM at the moment. Fortunately, there has been an increasing trend and awareness of SFM adoption. Therefore, this paper aims to understand and identify the contribution and practices of Sustainable Facilities Management (SFM in Malaysia; focusing on the development taken in regards to SFM.

A systems approach to nuclear facility monitoring

International Nuclear Information System (INIS)

Argo, P.E.; Doak, J.E.; Howse, J.W.

1996-01-01

Sensor technology for use in nuclear facility monitoring has reached an advanced stage of development. Research on where to place these sensors in a facility and how to combine their outputs in a meaningful fashion does not appear to be keeping pace. In this paper, the authors take a global view of the problem where sensor technology is viewed as only one piece of a large puzzle. Other pieces of this puzzle include the optimal location and type of sensors used in a specific facility, the rate at which sensors record information, and the risk associated with the materials/processes at a facility. If the data are analyzed off-site, how will they be transmitted? Is real-time analysis necessary? Is one monitoring only the facility itself, or might one also monitor the processing that occurs there (e.g., tank levels and concentrations)? How is one going to combine the outputs from the various sensors to give us an accurate picture of the state of the facility? This paper will not try to answer all these questions, but rather it will attempt to stimulate thought in this area by formulating a systems approach to the problem demonstrated by a prototype system and a system proposed for an actual facility. The focus will be on the data analysis aspect of the problem. Future work in this area should focus on recommendations and guidelines for a monitoring system based upon the type of facility and processing that occurs there

The Generic Data Capture Facility

Science.gov (United States)

Connell, Edward B.; Barnes, William P.; Stallings, William H.

1987-01-01

The Generic Data Capture Facility, which can provide data capture support for a variety of different types of spacecraft while enabling operations costs to be carefully controlled, is discussed. The data capture functions, data protection, isolation of users from data acquisition problems, data reconstruction, and quality and accounting are addressed. The TDM and packet data formats utilized by the system are described, and the development of generic facilities is considered.

Nuclear fuel cycle facility accident analysis handbook

International Nuclear Information System (INIS)

Ayer, J.E.; Clark, A.T.; Loysen, P.; Ballinger, M.Y.; Mishima, J.; Owczarski, P.C.; Gregory, W.S.; Nichols, B.D.

1988-05-01

The Accident Analysis Handbook (AAH) covers four generic facilities: fuel manufacturing, fuel reprocessing, waste storage/solidification, and spent fuel storage; and six accident types: fire, explosion, tornado, criticality, spill, and equipment failure. These are the accident types considered to make major contributions to the radiological risk from accidents in nuclear fuel cycle facility operations. The AAH will enable the user to calculate source term releases from accident scenarios manually or by computer. A major feature of the AAH is development of accident sample problems to provide input to source term analysis methods and transport computer codes. Sample problems and illustrative examples for different accident types are included in the AAH

Association between the time perspective and type of involvement in bullying among adolescents: A cross-sectional study in Japan.

Science.gov (United States)

Mizuta, Akiko; Okada, Eisaku; Nakamura, Mieko; Yamaguchi, Hisayoshi; Ojima, Toshiyuki

2018-04-01

To examine the association between the types of involvement in bullying and the time perspective among Japanese adolescents. A questionnaire was conducted among Japanese junior high school students at eight public schools that were located in two cities in Shizuoka Prefecture, Japan. Shirai's Experiential Time Perspective Scale was used, which comprises four subscales: goal-directedness, hopefulness, self-fulfillment, and acceptance of the past. An analysis of covariance was applied, with the time-perspective subscales as the objective variable, type of involvement in bullying as a fixed factor, and grade, family structure, and economic status as the covariates. The analysis sample included 2630 adolescents (valid response rate: 88.6%). The bullying rate of the boys was 10.8% and 4.1% for the girls, for the male victims it was 10.1% and 14.5% for the female victims, and for both the bully and the victim, it was 8.5% and 5.4%, respectively. The students who were not involved in bullying had the highest scores of hopefulness, self-fulfillment, and acceptance of the past. For both sexes, bullying was significantly associated with hopefulness, self-fulfillment, and acceptance of the past. Goal-directedness was not associated with the type of involvement in bullying. The victims of bullying had low time perspectives of hopefulness, self-fulfillment, and acceptance of the past. Providing support that increases hopefulness, self-fulfillment, and acceptance of the past might help to prevent pessimistic decision-making, such as that seen in cases of suicide. © 2017 Japan Academy of Nursing Science.

Directory of transport packaging test facilities

International Nuclear Information System (INIS)

1983-08-01

Radioactive materials are transported in packagings or containers which have to withstand certain tests depending on whether they are Type A or Type B packagings. In answer to a request by the International Atomic Energy Agency, 13 Member States have provided information on the test facilities and services existing in their country which can be made available for use by other states by arrangement for testing different kinds of packagings. The directory gives the technical information on the facilities, the services, the tests that can be done and in some cases even the financial arrangement is included

ICT Adoption in Facilities Management Supply Chain

DEFF Research Database (Denmark)

Scupola, Ada

2012-01-01

This article involves a qualitative study of factors impacting the adoption of ICT solutions in the Danish facility management supply chain. The results show that there are a number of drivers and barriers that influence the adoption of ICT solutions in this service sector. These have been grouped...... concerned with ICT adoption, operations and service management (especially facilities management) as well as operation managers and ICT managers....

Intense neutron irradiation facility for fusion reactor materials

Energy Technology Data Exchange (ETDEWEB)

Noda, Kenji; Oyama, Yukio; Kato, Yoshio; Sugimoto, Masayoshi [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

1997-03-01

Technical R and D of d-Li stripping type neutron irradiation facilities for development of fusion reactor materials was carried out in Fusion Materials Irradiation Test Facility (FMIT) project and Energy Selective Neutron Irradiation Test Facility (ESNIT) program. Conceptual design activity (CDA) of International Fusion Materials Irradiation Facility (IFMIF), of which concept is an advanced version of FMIT and ESNIT concepts, are being performed. Progress of users` requirements and characteristics of irradiation fields in such neutron irradiation facilities, and outline of baseline conceptual design of IFMIF were described. (author)

Applications of microtron facility

International Nuclear Information System (INIS)

Sanjeev, Ganesh

2013-01-01

An 8 MeV Microtron accelerator installed and commissioned in Mangalore University to strengthen research activities in the area of Radiation Physics and allied sciences is also being used extensively for coordinated research programs in basic and applied areas of science and technology involving researchers from national laboratories and sister universities of the region. The electron accelerator with its versatile features extends energetic electrons, intense photons and neutrons of moderate flux to cater to the needs of the users of the facility. A brief view of this 'first of its kind' facility in the country and the R and D programs with some sample results is presented. (author)

Designing a Physical Security System for Risk Reduction in a Hypothetical Nuclear Facility

International Nuclear Information System (INIS)

Saleh, A.A.; Abd Elaziz, M.

2017-01-01

Physical security in a nuclear facility means detection, prevention and response to threat, the ft, sabotage, unauthorized access and illegal transfer involving radioactive and nuclear material. This paper proposes a physical security system designing concepts to reduce the risk associated with variant threats to a nuclear facility. This paper presents a study of the unauthorized removal and sabotage in a hypothetical nuclear facility considering deter, delay and response layers. More over, the study involves performing any required upgrading to the security system by investigating the nuclear facility layout and considering all physical security layers design to enhance the weakness for risk reduction

Preparation of safety and regulatory document for BARC Facilities

International Nuclear Information System (INIS)

Prasad, S.S.; Jayarajan, K.

2017-01-01

In India, the necessary codes and safety guidelines for achieving the safety objectives are provided by the Atomic Energy Regulatory Board (AERB), which are in conformity with the principles of radiation protection as formulated by the International Council of Radiation Protection (ICRP) and International Atomic Energy Agency (IAEA). The same is followed by BARC Safety Council (BSC), which is the regulatory body for the BARC facilities. In addition to all types of fuel cycle facilities, BSC regulates safety of many types of conventional facilities. Many such types of facilities and projects are not under the regulatory purview of AERB. Therefore, the Council has also initiated a programme for development and publication of safety documents for installations in BARC in the fields/ topics yet not addressed by IAEA or AERB. This makes the task pioneering, as some of the areas taken up for defining the regulatory requirements are new, where standard regulatory documents are not available

Regulation of fuel cycle facilities in the UK

International Nuclear Information System (INIS)

Ascroft-Hutton, H.W.

2001-01-01

The UK has facilities for the production of uranium hexafluoride, its enrichment, conversion into fuel and for the subsequent reprocessing of irradiated fuel and closure of the fuel cycle. All of these facilities must be licensed under UK legislation. HM Nuclear Installations Inspectorate has delegated powers to issue the licence and to attach any conditions it considers necessary in the interests of safety. The fuel cycle facilities in the UK have been licensed since 1971. This paper describes briefly the UK nuclear regulatory framework and the fuel cycle facilities involved. It considers the regulatory practices adopted together with similarities and differences between regulation of fuel cycle facilities and power reactors. The safety issues associated with the fuel cycle are discussed and NII's regulatory strategy for these facilities is set out. (author)

Survey and assessment of radioactive waste management facilities in the United States. Section 2.5. Air-cooled vault storage facilities

International Nuclear Information System (INIS)

1986-01-01

There are two basic types of air-cooled vaults for the storage of spent nuclear fuel or vitrified HLRW. The two types, differentiated by the method of air cooling used, are the open-vault concept and the closed-vault concept. The following aspects of these air-cooled vault storage facility concepts are discussed: description and operation of facilities; strucutral design considerations and analysis; nuclear design considerations and analyses; vault environmental design considerations; unique design features; and accident analysis

WWER type reactor primary loop imitation on large test loop facility in MARIA reactor

International Nuclear Information System (INIS)

Moldysh, A.; Strupchevski, A.; Kmetek, Eh.; Spasskov, V.P.; Shumskij, A.M.

1982-01-01

At present in Poland in cooperation with USSR a nuclear water loop test facility (WL) in 'MARIA' reactor in Sverke is under construction. The program objective is to investigate processes occuring in WWER reactor under emergency conditions, first of all after the break of the mainprimary loop circulation pipe-line. WL with the power of about 600 kW consists of three major parts: 1) an active loop, imitating the undamaged loops of the WWER reactor; 2) a passive loop assignedfor modelling the broken loop of the WWER reactor; 3) the emergency core cooling system imitating the corresponding full-scale system. The fuel rod bundle consists of 18 1 m long rods. They were fabricated according to the standard WWER fuel technology. In the report some general principles of WWERbehaviour imitation under emergency conditions are given. They are based on the operation experience obtained from 'SEMISCALE' and 'LOFT' test facilities in the USA. A description of separate modelling factors and criteria effects on the development of 'LOCA'-type accident is presented (the break cross-section to the primary loop volume ratio, the pressure differential between inlet and outlet reactor chambers, the pressure drop rate in the loop, the coolant flow rate throuh the core etc.). As an example a comparison of calculated flow rate variations for the WWER-1000 reactor and the model during the loss-of-coolant accident with the main pipe-line break at the core inlet is given. Calculations have been carried out with the use of TECH'-M code [ru

Computer Profile of School Facilities Energy Consumption.

Science.gov (United States)

Oswalt, Felix E.

This document outlines a computerized management tool designed to enable building managers to identify energy consumption as related to types and uses of school facilities for the purpose of evaluating and managing the operation, maintenance, modification, and planning of new facilities. Specifically, it is expected that the statistics generated…

Facility safeguards at an LEU fuel fabrication facility in Japan

International Nuclear Information System (INIS)

Kuroi, H.; Osabe, T.

1984-01-01

A facility description of a Japanese LEU BWR-type fuel fabrication plant focusing on safeguards viewpoints is presented. Procedures and practices of MC and A plan, measurement program, inventory taking, and the report and record system are described. Procedures and practices of safeguards inspection are discussed and lessons learned from past experiences are reviewed

Coping with a community stressor: a proposed hazardous waste disposal facility

Energy Technology Data Exchange (ETDEWEB)

Bachrach, K.M.

1983-01-01

This study examined a number of factors believed to influence community involvement. Residents of a rural community near Phoenix, Arizona, where a hazardous waste facility had been proposed to built, were interviewed at home in August 1982. Most residents were chosen at random (n = 70) while a smaller number (n = 29) were selected because of known involvement in activities regarding the hazardous waste facility. Residents who perceived the facility as a threat to their health, safety, and general well-being employed a number of coping strategies. Strategies to change or alter the source of stress, problem-focused coping, were associated with greater community involvement. Strategies to regulate one's emotional response to stress, emotion-focused coping, were associated with less community involvement. Increased self-efficacy and sense of community led to increased community involvement. Both measures indirectly influenced community involvement through different modes of coping. Self-efficacy was negatively related to emotion-focused coping while sense of community was positively related to problem-focused coping. Increased demoralization was associated with decreased self-efficacy, increased emotion-focused coping, and decreased community involvement. The results suggest that the psychologically most fragile residents are underrepresented in community activities, and that the use of high levels of emotion-focused coping may have been maladaptive.

Diffuse reticuloendothelial system involvement in type IV glycogen storage disease with a novel GBE1 mutation: a case report and review.

Science.gov (United States)

Magoulas, Pilar L; El-Hattab, Ayman W; Roy, Angshumoy; Bali, Deeksha S; Finegold, Milton J; Craigen, William J

2012-06-01

Glycogen storage disease type IV is a rare autosomal recessive disorder of glycogen metabolism caused by mutations in the GBE1 gene that encodes the 1,4-alpha-glucan-branching enzyme 1. Its clinical presentation is variable, with the most common form presenting in early childhood with primary hepatic involvement. Histologic manifestations in glycogen storage disease type IV typically consist of intracytoplasmic non-membrane-bound inclusions containing abnormally branched glycogen (polyglucosan bodies) within hepatocytes and myocytes. We report a female infant with classic hepatic form of glycogen storage disease type IV who demonstrated diffuse reticuloendothelial system involvement with the spleen, bone marrow, and lymph nodes infiltrated by foamy histiocytes with intracytoplasmic polyglucosan deposits. Sequence analysis of the GBE1 gene revealed compound heterozygosity for a previously described frameshift mutation (c.1239delT) and a novel missense mutation (c.1279G>A) that is predicted to alter a conserved glycine residue. GBE enzyme analysis revealed no detectable activity. A review of the literature for glycogen storage disease type IV patients with characterized molecular defects and deficient enzyme activity reveals most GBE1 mutations to be missense mutations clustering in the catalytic enzyme domain. Individuals with the classic hepatic form of glycogen storage disease type IV tend to be compound heterozygotes for null and missense mutations. Although the extensive reticuloendothelial system involvement that was observed in our patient is not typical of glycogen storage disease type IV, it may be associated with severe enzymatic deficiency and a poor outcome. Copyright © 2012 Elsevier Inc. All rights reserved.

Scaled Facility Design Approach for Pool-Type Lead-Bismuth Eutectic Cooled Small Modular Reactor Utilizing Natural Circulation

Energy Technology Data Exchange (ETDEWEB)

Park, Sangrok; Shin, Yong-Hoon; Lee, Jueun; Hwang, Il Soon [Seoul National University, Seoul (Korea, Republic of)

2015-10-15

In low carbon era, nuclear energy is the most prominent energy source of electricity. For steady ecofriendly nuclear energy supply, Generation IV reactors which are future nuclear reactor require safety, sustainability, economics and non-proliferation as four criteria. Lead cooled fast reactor (LFR) is one of these reactor type and Generation IV international forum (GIF) adapted three reference LFR systems which are a small and movable systems with long life without refueling, intermediate size and huge electricity generation system for power grid. NUTRECK (Nuclear Transmutation Energy Center of Korea) has been designed reactor called URANUS (Ubiquitous, Rugged, Accident-forgiving, Non-proliferating, and Ultra-lasting Sustainer) which is small modular reactor and using lead-bismuth eutectic coolant. To prove natural circulation capability of URANUS and analyze design based accidents, scaling mock-up experiment facility will be constructed. In this paper, simple specifications of URANUS will be presented. Then based on this feature, scaling law and scaled facility design results are presented. To validate safety feature and thermodynamics characteristic of URANUS, scaled mockup facility of URANUS is designed based on the scaling law. This mockup adapts two area scale factors, core and lower parts of mock-up are scaled for 3D flow experiment. Upper parts are scaled different size to reduce electricity power and LBE tonnage. This hybrid scaling method could distort some thermal-hydraulic parameters, however, key parameters for experiment will be matched for up-scaling. Detailed design of mock-up will be determined through iteration for design optimization.

Assessing School Facilities in Public Secondary Schools in Delta ...

African Journals Online (AJOL)

This study investigated school facilitates in public secondary schools in Delta State, Nigeria. The purpose of the study was to find out the state of the facilities, the types of maintenance carried out on the facilities by school administrators, the factors encouraging school facilities depreciation and the roles of school ...

Evaluation on construction quality of pit filler material of cavern type radioactive waste disposal facility

International Nuclear Information System (INIS)

Takechi, Shin-ichi; Yokozeki, Kosuke; Shimbo, Hiroshi; Terada, Kenji; Akiyama, Yoshihiro; Yada, Tsutomu; Tsuji, Yukikazu

2014-01-01

The pit filler material of the underground cavern-type radioactive waste disposal facility, which is poured directly around the radioactive waste packages where high temperature environment is assumed by their decay heat, is concerned to be adversely affected on the filling behavior and its hardened properties. There also are specific issues that required quality of construction must be achieved by unmanned construction with remote operation, because the pit filler construction shall be done under radiation environment. In this paper, the mix proportion of filler material is deliberated with filling experiments simulating high temperature environment, and also the effect of temperature on hardened properties are confirmed with high temperature curing test. Subsequently, the feasibility of unmanned construction method of filler material by pumping, and by movable bucket, are comparatively discussed through a real size demonstration. (author)

A security/safety survey of long term care facilities.

Science.gov (United States)

Acorn, Jonathan R

2010-01-01

What are the major security/safety problems of long term care facilities? What steps are being taken by some facilities to mitigate such problems? Answers to these questions can be found in a survey of IAHSS members involved in long term care security conducted for the IAHSS Long Term Care Security Task Force. The survey, the author points out, focuses primarily on long term care facilities operated by hospitals and health systems. However, he believes, it does accurately reflect the security problems most long term facilities face, and presents valuable information on security systems and practices which should be also considered by independent and chain operated facilities.

Communication in reducing facility siting risk

International Nuclear Information System (INIS)

Bisconti, A.S.

1992-01-01

Today, social considerations are as important as technical ones in siting new nuclear facilities. Siting any industrial facility has become extremely difficult in this era of not in my backyard (NIMBY). Even if NIMBY does not arise locally, well-organized national opposition groups can be counted on to step in to fan the flames, especially when the industrial facility has to do with anything nuclear. It is now generally recognized that the greatest risk of failure for new nuclear facilities is not technical but social. Applying lessons gained from past experience and social science research can help reduce that risk. From these lessons, six principles for public interaction and communication stand out: (1) create goodwill now; (2) involve the community early; (3) establish the need; (4) communicate controls, not risk; (5) avoid jargon; (6) understand your public

Bone marrow involvement in diffuse large B-cell lymphoma: correlation between FDG-PET uptake and type of cellular infiltrate

International Nuclear Information System (INIS)

Paone, Gaetano; Itti, Emmanuel; Lin, Chieh; Meignan, Michel; Haioun, Corinne; Dupuis, Jehan; Gaulard, Philippe

2009-01-01

To assess, in patients with diffuse large B-cell lymphoma (DLBCL), whether the low sensitivity of 18 F-fluorodeoxyglucose positron emission tomography (FDG-PET) for bone marrow assessment may be explained by histological characteristics of the cellular infiltrate. From a prospective cohort of 110 patients with newly diagnosed aggressive lymphoma, 21 patients with DLBCL had bone marrow involvement. Pretherapeutic FDG-PET images were interpreted visually and semiquantitatively, then correlated with the type of cellular infiltrate and known prognostic factors. Of these 21 patients, 7 (33%) had lymphoid infiltrates with a prominent component of large transformed lymphoid cells (concordant bone marrow involvement, CBMI) and 14 (67%) had lymphoid infiltrates composed of small cells (discordant bone marrow involvement, DBMI). Only 10 patients (48%) had abnormal bone marrow FDG uptake, 6 of the 7 with CBMI and 4 of the 14 with DBMI. Therefore, FDG-PET positivity in the bone marrow was significantly associated with CBMI, while FDG-PET negativity was associated with DBMI (Fisher's exact test, p=0.024). There were no significant differences in gender, age and overall survival between patients with CBMI and DBMI, while the international prognostic index was significantly higher in patients with CBMI. Our study suggests that in patients with DLBCL with bone marrow involvement bone marrow FDG uptake depends on two types of infiltrate, comprising small (DBMI) or large (CBMI) cells. This may explain the apparent low sensitivity of FDG-PET previously reported for detecting bone marrow involvement. (orig.)

Remote maintenance system for nuclear facilities

International Nuclear Information System (INIS)

Maeda, Masafumi

1993-01-01

In the facilities related to atomic energy, from the viewpoint of the reduction of radiation exposure of workers and the heightening of the rate of operation of the facilities, the development of remote maintenance system is regarded as important. Meidensha Electric Manufacturing Co., Ltd. developed the bilateral control type manipulator, BILARM-83, in 1979, and has developed high performance manipulator systems. As the design of the plant that realizes the remote operation maintenance of process machinery and equipment during plant operation, the remote maintenance system by canyon cell techniques, which was adopted in Savannah River plant, USA, and has been operated for nearly 50 years, has been known. The concept of the full remote maintenance system by large scale cell techniques was shown and has been developed by Power Reactor and Nuclear Fuel Development Corp. In order to realize the remote maintenance of such large scale cells, Meidensha is developing the both arm type bilateral servo manipulator, the single arm type power manipulator, the transport system for moving them, the power and signal system and so on. Those systems were adopted for the glass solidification facilities. (K.I.)

The National Ignition Facility and Industry

Science.gov (United States)

Harri, J. G.; Paisner, J. A.; Lowdermilk, W. H.; Boyes, J. D.; Kumpan, S. A.; Sorem, M. S.

1994-09-01

The mission of the National Ignition Facility is to achieve ignition and gain in inertial confinement fusion targets in the laboratory. The facility will be used for defense applications such as weapons physics and weapons effects testing, and for civilian applications such as fusion energy development and fundamental studies of matter at high temperatures and densities. The National Ignition Facility construction project will require the best of our construction industries and its success will depend on the best products offered by hundreds of the nation's high technology companies. Three-fourths of the construction costs will be invested in industry. This article reviews the design, cost and schedule, and required industrial involvement associated with the construction project.

The National Ignition Facility and industry

International Nuclear Information System (INIS)

Harri, J.G.; Lowdermilk, W.H.; Paisner, J.A.; Boyes, J.D.; Kumpan, S.A.; Sorem, M.S.

1994-01-01

The mission of the National Ignition Facility is to achieve ignition and gain in inertial confinement fusion targets in the laboratory. The facility will be used for defense applications such as weapons physics and weapons effects testing, and for civilian applications such as fusion energy development and fundamental studies of matter at high temperatures and densities. The National Ignition Facility construction project will require the best of national construction industries and its success will depend on the best products offered by hundreds of the nation's high technology companies. Three-fourths of the construction costs will be invested in industry. This article reviews the design, cost and schedule, and required industrial involvement associated with the construction project

Systems management of facilities agreements

International Nuclear Information System (INIS)

Blundell, A.

1998-01-01

The various types of facilities agreements, the historical obstacles to implementation of agreement management systems and the new opportunities emerging as industry is beginning to make an effort to overcome these obstacles, are reviewed. Barriers to computerized agreement management systems (lack of consistency, lack of standards, scarcity of appropriate computer software) are discussed. Characteristic features of a model facilities agreement management system and the forces driving the changing attitudes towards such systems (e.g. mergers) are also described

Interleukin-6 autoantibodies are involved in the pathogenesis of a subset of type 2 diabetes

DEFF Research Database (Denmark)

Fosgerau, K; Galle, P; Hansen, T

2010-01-01

Interleukin-6 (IL6) is critically involved in inflammation and metabolism. About 1% of people produce IL6 autoantibodies (aAb-IL6) that impair IL6 signaling in vivo. We tested the hypothesis that the prevalence of such aAb-IL6 is increased in type 2 diabetic patients and that aAb-IL6 plays a direct...... role in causing hyperglycemia. In humans, the prevalence of circulating high-affinity neutralizing aAb-IL6 was 2.5% in the type 2 diabetic patients and 1% in the controls (odds ratio 2.5, 95% confidence interval 1.2-4.9, P=0.01). To test for the role of aAb-IL6 in causing hyperglycemia, such aAb-IL6...... were induced in mice by a validated vaccination procedure. Mice with plasma levels of aAb-IL6 similar to the 2.5% type 2 diabetic patients developed obesity and impaired glucose tolerance (area under the curve (AUC) glucose, 2056+/-62 vs 1793+/-62, P=0.05) as compared with sham-vaccinated mice, when...

Factors affecting minority population proximity to hazardous facilities

Energy Technology Data Exchange (ETDEWEB)

Nieves, L.A. [Argonne National Lab., IL (United States); Nieves, A.L. [Wheaton Coll., IL (United States)]|[Argonne National Lab., IL (United States)

1995-04-01

Disproportionate exposure of minority groups to environmental hazards has been attributed to ``environmental racism`` by some authors, without systematic investigation of the factors underlying this exposure pattern. This study examines regional differences in the proximity of African-Americans, Hispanics, Asians, and non-Hispanic Whites to a broad range of facility types and explores the effects of urban and income factors. A statistically significant inverse relationship is found between the percentage of non-Hispanic Whites and virtually all facility categories in all regions. Except for Hispanics in the South, all such associations for minority groups show a direct relationship, though some are nonsignificant. The geographic concentration of facilities is more closely tied to urbanization than to economic factors. Controlling for both urban and economic factors, minority population concentration is still a significant explanatory variable for some facility types in some regions. This finding is most consistent for African-Americans.

YALINA facility a sub-critical Accelerator- Driven System (ADS) for nuclear energy research facility description and an overview of the research program (1997-2008).

Energy Technology Data Exchange (ETDEWEB)

Gohar, Y.; Smith, D. L.; Nuclear Engineering Division

2010-04-28

The YALINA facility is a zero-power, sub-critical assembly driven by a conventional neutron generator. It was conceived, constructed, and put into operation at the Radiation Physics and Chemistry Problems Institute of the National Academy of Sciences of Belarus located in Minsk-Sosny, Belarus. This facility was conceived for the purpose of investigating the static and dynamic neutronics properties of accelerator driven sub-critical systems, and to serve as a neutron source for investigating the properties of nuclear reactions, in particular transmutation reactions involving minor-actinide nuclei. This report provides a detailed description of this facility and documents the progress of research carried out there during a period of approximately a decade since the facility was conceived and built until the end of 2008. During its history of development and operation to date (1997-2008), the YALINA facility has hosted several foreign groups that worked with the resident staff as collaborators. The participation of Argonne National Laboratory in the YALINA research programs commenced in 2005. For obvious reasons, special emphasis is placed in this report on the work at YALINA facility that has involved Argonne's participation. Attention is given here to the experimental program at YALINA facility as well as to analytical investigations aimed at validating codes and computational procedures and at providing a better understanding of the physics and operational behavior of the YALINA facility in particular, and ADS systems in general, during the period 1997-2008.

Operating instructions for LBL radon measurement facilities

International Nuclear Information System (INIS)

Ingersoll, J.G.

1980-06-01

This manual is intended for users of the radon-measuring facilities of the Radon Project of the Building Ventilation and Indoor Air Quality Program at Lawrence Berkeley Laboratory. The manual comprises three parts. Part 1 sets out the steps involved in collecting, transferring, and counting radon. Part 2 describes the calibration of the transfer system and of the Lucas cells in the counting system. Part 3 outlines the maintenance procedures for the facility

An enantioselective approach toward 3,4-dihydroisocoumarin through the bromocyclization of styrene-type carboxylic acids.

Science.gov (United States)

Chen, Jie; Zhou, Ling; Tan, Chong Kiat; Yeung, Ying-Yeung

2012-01-20

A facile and enantioselective approach toward 3,4-dihydroisocoumarin was developed. The method involved an amino-thiocarbamate catalyzed enantioselective bromocyclization of styrene-type carboxylic acids, yielding 3-bromo-3,4-dihydroisocoumarins with good yields and ee's. 3-Bromo-3,4-dihydroisocoumarins are versatile building blocks for various dihydroisocoumarin derivatives in which the Br group can readily be modified to achieve biologically important 4-O-type and 4-N-type 3,4-dihydroisocoumarin systems. In addition, studies indicated that, by refining some parameters, the synthetically useful 5-exo phthalide products could be achieved with good yields and ee's.

Status of RNB facilities in North America

CERN Document Server

Nolen, J A

1998-01-01

This paper presents the status of accelerator facilities in North America that are involved in research using radioactive nuclear beams (RNB), including existing and operating facilities, ones currently under construction or undergoing major upgrades, and ones being planned or proposed for the future. Existing RNB facilities are located at TRIUMF (TISOL) in Vancouver, B.C., the Holifield Radioactive Ion Beam Facility (HRIBF) at Oak Ridge National Laboratory, the Argonne Tandem Linear Accelerator System (ATLAS) at Argonne National Laboratory, the National Superconducting Cyclotron Laboratory (NSCL) at Michigan State University, the Nuclear Structure Laboratory at the University of Notre Dame, the 88" Cyclotron at Lawrence Berkeley National Laboratory, and the Cyclotron Institute at Texas A&M University. Currently, there are two major RNB facility upgrades in progress in North America, one at TRIUMF, the ISAC project, and one at NSCL, the Intensity Upgrade project. For the future, the U.S. Nuclear Science A...

Typing of Methicillin resistant Staphylococcus aureus: A technical review

Directory of Open Access Journals (Sweden)

P L Mehndiratta

2012-01-01

Full Text Available Increasing prevalence of Methicillin-resistant Staphylococcus aureus (MRSA worldwide is a growing public health concern. MRSA typing is an essential component of an effective surveillance system to describe epidemiological trends and infection control strategies. Current challenges for MRSA typing are focused on selecting the most appropriate technique in terms of efficiency, reliability, ease of performance and cost involved. This review summarises the available information on application, potential and problems of various typing techniques in discriminating the strains and understanding the epidemiology of MRSA strains. The phenotypic methods in general are easier to perform, easier to interpret, cost effective and are widely available, however less discriminatory. The genotypic methods are expensive and technically demanding, however more discriminatory. Newer technologies involving sequencing of various genes are coming up as broadly applicable and high throughput typing systems. Still there is no consensus regarding the single best method for typing of MRSA strains. Phage typing is recommended as first line approach in epidemiological investigation of MRSA strains. PFGE remains the gold standard for characterisation of outbreak strains. DNA sequencing methods including MLST, spa typing, SCCmec typing and toxin gene profile typing are more practical methods for detecting evolutionary changes and transmission events. The choice of typing technique further depends on the purpose of the study, the facilities available and the utility of data generated to answer a desirable research question. A need for harmonisation of typing techniques by following standard protocols is emphasised to establish surveillance networks and facilitate global MRSA control.

Establishment of fecal bioassay facility at Kalpakkam

International Nuclear Information System (INIS)

Krishnan, H.; Yuvaraj, Ramani; Mohanty, B.N.; Sivasubramanian, K.; Venkatraman, B.

2016-01-01

In the event of an unusual occurrence, occupational radiation workers employed in fuel reprocessing/fuel fabrication facilities have potential risk of acquiring internal contamination, in spite of implementation of efficient engineering and administrative control measures. Quantification of internally deposited radionuclides is achieved either by (i) direct methods and/or (ii) indirect methods. In general, urinalysis is preferred for moderately absorbing (Type M-compounds of Americium) compounds, while analysis of fecal samples are preferred for slow absorption (Type S - Oxides of Plutonium) compounds. The predicted clearance of Type S and Type M compounds deposited in respiratory tract via fecal is about three to five orders higher than urinary excretion. In view of this, a facility for ashing fecal samples was established and standardization of radioanalytical procedure for quantification of Pu/Am using synthetic fecal (SF) samples was carried out

Preliminary study for small animal preclinical hadrontherapy facility

Energy Technology Data Exchange (ETDEWEB)

Russo, G. [Institute of Molecular Bioimaging and Physiology, IBFM CNR-LATO, Cefalú (Italy); Pisciotta, P., E-mail: pietro.pisciotta@ibfm.cnr.it [Institute of Molecular Bioimaging and Physiology, IBFM CNR-LATO, Cefalú (Italy); National Institute for Nuclear Physics, Laboratori Nazionali del Sud, INFN-LNS, Catania (Italy); Cirrone, G.A.P.; Romano, F. [National Institute for Nuclear Physics, Laboratori Nazionali del Sud, INFN-LNS, Catania (Italy); Cammarata, F.; Marchese, V.; Forte, G.I.; Lamia, D.; Minafra, L.; Bravatá, V. [Institute of Molecular Bioimaging and Physiology, IBFM CNR-LATO, Cefalú (Italy); Acquaviva, R. [University of Catania, Catania (Italy); Gilardi, M.C. [Institute of Molecular Bioimaging and Physiology, IBFM CNR-LATO, Cefalú (Italy); Cuttone, G. [National Institute for Nuclear Physics, Laboratori Nazionali del Sud, INFN-LNS, Catania (Italy)

2017-02-21

Aim of this work is the study of the preliminary steps to perform a particle treatment of cancer cells inoculated in small animals and to realize a preclinical hadrontherapy facility. A well-defined dosimetric protocol was developed to explicate the steps needed in order to perform a precise proton irradiation in small animals and achieve a highly conformal dose into the target. A precise homemade positioning and holding system for small animals was designed and developed at INFN-LNS in Catania (Italy), where an accurate Monte Carlo simulation was developed, using Geant4 code to simulate the treatment in order to choose the best animal position and perform accurately all the necessary dosimetric evaluations. The Geant4 application can also be used to realize dosimetric studies and its peculiarity consists in the possibility to introduce the real target composition in the simulation using the DICOM micro-CT image. This application was fully validated comparing the results with the experimental measurements. The latter ones were performed at the CATANA (Centro di AdroTerapia e Applicazioni Nucleari Avanzate) facility at INFN-LNS by irradiating both PMMA and water solid phantom. Dosimetric measurements were performed using previously calibrated EBT3 Gafchromic films as a detector and the results were compared with the Geant4 simulation ones. In particular, two different types of dosimetric studies were performed: the first one involved irradiation of a phantom made up of water solid slabs where a layer of EBT3 was alternated with two different slabs in a sandwich configuration, in order to validate the dosimetric distribution. The second one involved irradiation of a PMMA phantom made up of a half hemisphere and some PMMA slabs in order to simulate a subcutaneous tumour configuration, normally used in preclinical studies. In order to evaluate the accordance between experimental and simulation results, two different statistical tests were made: Kolmogorov test and

Preliminary study for small animal preclinical hadrontherapy facility

Science.gov (United States)

Russo, G.; Pisciotta, P.; Cirrone, G. A. P.; Romano, F.; Cammarata, F.; Marchese, V.; Forte, G. I.; Lamia, D.; Minafra, L.; Bravatá, V.; Acquaviva, R.; Gilardi, M. C.; Cuttone, G.

2017-02-01

Aim of this work is the study of the preliminary steps to perform a particle treatment of cancer cells inoculated in small animals and to realize a preclinical hadrontherapy facility. A well-defined dosimetric protocol was developed to explicate the steps needed in order to perform a precise proton irradiation in small animals and achieve a highly conformal dose into the target. A precise homemade positioning and holding system for small animals was designed and developed at INFN-LNS in Catania (Italy), where an accurate Monte Carlo simulation was developed, using Geant4 code to simulate the treatment in order to choose the best animal position and perform accurately all the necessary dosimetric evaluations. The Geant4 application can also be used to realize dosimetric studies and its peculiarity consists in the possibility to introduce the real target composition in the simulation using the DICOM micro-CT image. This application was fully validated comparing the results with the experimental measurements. The latter ones were performed at the CATANA (Centro di AdroTerapia e Applicazioni Nucleari Avanzate) facility at INFN-LNS by irradiating both PMMA and water solid phantom. Dosimetric measurements were performed using previously calibrated EBT3 Gafchromic films as a detector and the results were compared with the Geant4 simulation ones. In particular, two different types of dosimetric studies were performed: the first one involved irradiation of a phantom made up of water solid slabs where a layer of EBT3 was alternated with two different slabs in a sandwich configuration, in order to validate the dosimetric distribution. The second one involved irradiation of a PMMA phantom made up of a half hemisphere and some PMMA slabs in order to simulate a subcutaneous tumour configuration, normally used in preclinical studies. In order to evaluate the accordance between experimental and simulation results, two different statistical tests were made: Kolmogorov test and

Preliminary study for small animal preclinical hadrontherapy facility

International Nuclear Information System (INIS)

Russo, G.; Pisciotta, P.; Cirrone, G.A.P.; Romano, F.; Cammarata, F.; Marchese, V.; Forte, G.I.; Lamia, D.; Minafra, L.; Bravatá, V.; Acquaviva, R.; Gilardi, M.C.; Cuttone, G.

2017-01-01

Aim of this work is the study of the preliminary steps to perform a particle treatment of cancer cells inoculated in small animals and to realize a preclinical hadrontherapy facility. A well-defined dosimetric protocol was developed to explicate the steps needed in order to perform a precise proton irradiation in small animals and achieve a highly conformal dose into the target. A precise homemade positioning and holding system for small animals was designed and developed at INFN-LNS in Catania (Italy), where an accurate Monte Carlo simulation was developed, using Geant4 code to simulate the treatment in order to choose the best animal position and perform accurately all the necessary dosimetric evaluations. The Geant4 application can also be used to realize dosimetric studies and its peculiarity consists in the possibility to introduce the real target composition in the simulation using the DICOM micro-CT image. This application was fully validated comparing the results with the experimental measurements. The latter ones were performed at the CATANA (Centro di AdroTerapia e Applicazioni Nucleari Avanzate) facility at INFN-LNS by irradiating both PMMA and water solid phantom. Dosimetric measurements were performed using previously calibrated EBT3 Gafchromic films as a detector and the results were compared with the Geant4 simulation ones. In particular, two different types of dosimetric studies were performed: the first one involved irradiation of a phantom made up of water solid slabs where a layer of EBT3 was alternated with two different slabs in a sandwich configuration, in order to validate the dosimetric distribution. The second one involved irradiation of a PMMA phantom made up of a half hemisphere and some PMMA slabs in order to simulate a subcutaneous tumour configuration, normally used in preclinical studies. In order to evaluate the accordance between experimental and simulation results, two different statistical tests were made: Kolmogorov test and

Tests of the space gamma spectrometer prototype at the JINR experimental facility with different types of neutron generators

Science.gov (United States)

Litvak, M. L.; Vostrukhin, A. A.; Golovin, D. V.; Dubasov, P. V.; Zontikov, A. O.; Kozyrev, A. S.; Krylov, A. R.; Krylov, V. A.; Mitrofanov, I. G.; Mokrousov, M. I.; Repkin, A. N.; Timoshenko, G. N.; Udovichenko, K. V.; Shvetsov, V. N.

2017-07-01

The results of the tests of the HPGe gamma spectrometer performed with a planetary soil model and different types of pulse neutron generators are presented. All measurements have been performed at the experimental nuclear planetary science facility (Joint Institute for Nuclear Research) for the physical calibration of active gamma and neutron spectrometers. The aim of the study is to model a space experiment on determining the elemental composition of Martian planetary matter by neutron-induced gamma spectroscopy. The advantages and disadvantages of a gas-filled neutron generator in comparison with a vacuum-tube neutron generator are examined.

Transitioning to a New Facility: The Crucial Role of Employee Engagement.

Science.gov (United States)

Slosberg, Meredith; Nejati, Adeleh; Evans, Jennie; Nanda, Upali

Transitioning to a new facility can be challenging for employees and detrimental to operations. A key aspect of the transition is employee understanding of, and involvement in, the design of the new facility. The literature lacks a comprehensive study of the impact of change engagement throughout the design, construction, and activation of a project as well as how that can affect perceptions, expectations, and, eventually, satisfaction of employees. The purpose of this research was to examine employee perceptions and satisfaction throughout a hospital design, construction, and activation process. Three pulse-point surveys were administered throughout the transition of a children's hospital emergency department and neonatal intensive care unit to a new facility. We also administered a postoccupancy survey 3 months after the move into the new facility. We received 544 responses and analyzed them to assess the relationship between involvement in design or change engagement initiatives and overall perceptions. The results revealed a strong relationship between employee engagement and their level of preparedness to move, readiness to adapt, and satisfaction. Early involvement in the design of a facility or new processes can significantly affect staff preparedness and readiness to adapt as well as employees' overall satisfaction with the building after occupancy. In addition, our findings suggest that keeping a finger on the pulse of employee perceptions and expectations throughout the design, construction, and activation phase is critical to employee preparedness and satisfaction in transitioning to a new facility.

Water Supply and Sanitation Facility Accessibility in Off-Campus ...

African Journals Online (AJOL)

Water Supply and Sanitation Facility Accessibility in Off-Campus Houses ... on drinking water source, rate of illness, type and usage of sanitation facilities. ... wells, unprotected dug wells; while others during the wet season harvest rain water.

A Bioinformatics Facility for NASA

Science.gov (United States)

Schweighofer, Karl; Pohorille, Andrew

2006-01-01

Building on an existing prototype, we have fielded a facility with bioinformatics technologies that will help NASA meet its unique requirements for biological research. This facility consists of a cluster of computers capable of performing computationally intensive tasks, software tools, databases and knowledge management systems. Novel computational technologies for analyzing and integrating new biological data and already existing knowledge have been developed. With continued development and support, the facility will fulfill strategic NASA s bioinformatics needs in astrobiology and space exploration. . As a demonstration of these capabilities, we will present a detailed analysis of how spaceflight factors impact gene expression in the liver and kidney for mice flown aboard shuttle flight STS-108. We have found that many genes involved in signal transduction, cell cycle, and development respond to changes in microgravity, but that most metabolic pathways appear unchanged.

MR imaging in adults with Gaucher disease type I: evulation of marrow involvement and disease activity

Energy Technology Data Exchange (ETDEWEB)

Hermann, G. (Dept. of Radiology, Mount Sinai Medical Center, City Univ. of New York, NY (United States)); Shaprio, R.S. (Dept. of Radiology, Mount Sinai Medical Center, City Univ. of New York, NY (United States)); Abdelwahab, I.F. (Dept. of Radiology, Mount Sinai Medical Center, City Univ. of New York, NY (United States)); Grabowski, G. (Dept. of Pediatrics, Mount Sinai Medical Center, City Univ. of New York, NY (United States))

1993-05-01

An investigation was conducted to determine the usefulness of magnetic resonance imaging (MRI) in the evaluation of bone marrow involvement in patients with Gaucher disease type I. T1- and T2-weighted images were obtained of the lower extremities of 29 adult patients. Patients were classified into one of three groups based on marrow signal patterns on T1- and T2-weighted images as well as change in signal intensity from T1- to T2-weighted images. An increase in signal intensity from T1- to T2-weighted images was the criterion for an 'active process' within the bone marrow. Classification of the 29 patients produced the following results: Group A: Normal, 4 patients; group B: Marrow infiltration, 16 patients; group C: Marrow infiltration plus active marrow process, 9 patients. Correlation with clinical findings revealed that all nine patients with evidence of an active marrow process on MRI (group C) had acute bone pain. Conversely, only one of the remaining 20 patients (groups A and B) had bone pain. There was no correlation between disease activity and findings on conventional radiographs. We conclude the MRI provides an excellent noninvasive assessment of the extent and activity of marrow involvement in type I Gaucher disease. (orig.)

MR imaging in adults with Gaucher disease type I: evulation of marrow involvement and disease activity

International Nuclear Information System (INIS)

Hermann, G.; Shaprio, R.S.; Abdelwahab, I.F.; Grabowski, G.

1993-01-01

An investigation was conducted to determine the usefulness of magnetic resonance imaging (MRI) in the evaluation of bone marrow involvement in patients with Gaucher disease type I. T1- and T2-weighted images were obtained of the lower extremities of 29 adult patients. Patients were classified into one of three groups based on marrow signal patterns on T1- and T2-weighted images as well as change in signal intensity from T1- to T2-weighted images. An increase in signal intensity from T1- to T2-weighted images was the criterion for an 'active process' within the bone marrow. Classification of the 29 patients produced the following results: Group A: Normal, 4 patients; group B: Marrow infiltration, 16 patients; group C: Marrow infiltration plus active marrow process, 9 patients. Correlation with clinical findings revealed that all nine patients with evidence of an active marrow process on MRI (group C) had acute bone pain. Conversely, only one of the remaining 20 patients (groups A and B) had bone pain. There was no correlation between disease activity and findings on conventional radiographs. We conclude the MRI provides an excellent noninvasive assessment of the extent and activity of marrow involvement in type I Gaucher disease. (orig.)

Ice condenser testing facility and plans

International Nuclear Information System (INIS)

Kannberg, L.D.; Ross, B.A.; Eschbach, E.J.; Ligotke, M.W.

1987-01-01

A facility is being constructed to experimentally validate the ICEDF computer code. The code was developed to estimate the extent of fission product retention in the ice compartments of pressurized water reactor ice condenser containment systems during severe accidents. The design and construction of the facility is based on a test design that addresses the validation needs of the code for conditions typical of those expected to occur during severe pressurized water reactor accidents. Detailed facility design has followed completion of a test design (i.e., assembled test cases each involving a different set of aerosol and thermohydraulic flow conditions). The test design was developed with the aid of statistical test design software and was scrutinized for applicability with the aid of ICEDF simulations. The test facility will incorporate a small section of a prototypic ice condenser (e.g., a cross section comprising the equivalent of four 1-ft-diameter ice baskets to their full prototypic height of 48 ft). The development of the test design, the detailed facility design, and the construction progress are described in this paper

Mineral facilities of Northern and Central Eurasia

Science.gov (United States)

Baker, Michael S.; Elias, Nurudeen; Guzman, Eric; Soto-Viruet, Yadira

2010-01-01

This map displays almost 900 records of mineral facilities within the countries that formerly constituted the Union of Soviet Socialist Republics (USSR). Each record represents one commodity and one facility type at a single geographic location. Facility types include mines, oil and gas fields, and plants, such as refineries, smelters, and mills. Common commodities of interest include aluminum, cement, coal, copper, gold, iron and steel, lead, nickel, petroleum, salt, silver, and zinc. Records include attributes, such as commodity, country, location, company name, facility type and capacity (if applicable), and latitude and longitude geographical coordinates (in both degrees-minutes-seconds and decimal degrees). The data shown on this map and in table 1 were compiled from multiple sources, including (1) the most recently available data from the U.S. Geological Survey (USGS) Minerals Yearbook (Europe and Central Eurasia volume), (2) mineral statistics and information from the USGS Minerals Information Web site (http://minerals.usgs.gov/minerals/pubs/country/europe.html), and (3) data collected by the USGS minerals information country specialists from sources, such as statistical publications of individual countries, annual reports and press releases of operating companies, and trade journals. Data reflect the most recent published table of industry structure for each country at the time of this publication. Additional information is available from the country specialists listed in table 2

Mineral facilities of Asia and the Pacific

Science.gov (United States)

Baker, Michael S.; Elias, Nurudeen; Guzman, Eric; Soto-Viruet, Yadira

2010-01-01

This map displays over 1,500 records of mineral facilities throughout the continent of Asia and the countries of the Pacific Ocean. Each record represents one commodity and one facility type at a single geographic location. Facility types include mines, oil and gas fields, and plants, such as refineries, smelters, and mills. Common commodities of interest include aluminum, cement, coal, copper, gold, iron and steel, lead, nickel, petroleum, salt, silver, and zinc. Records include attributes, such as commodity, country, location, company name, facility type and capacity (if applicable), and latitude and longitude geographical coordinates (in both degrees-minutes-seconds and decimal degrees). The data shown on this map and in table 1 were compiled from multiple sources, including (1) the 2008 U.S. Geological Survey Minerals Yearbook (Asia and the Pacific volume), (2) minerals statistics and information from the U.S. Geological Survey Minerals Information Web site (http://minerals.usgs.gov/minerals/), and (3) data collected by U.S. Geological Survey minerals information country specialists. Other sources include statistical publications of individual countries, annual reports and press releases of operating companies, and trade journals. Due to the sensitivity of some energy commodity data, the quality of these data should be evaluated on a country-by-country basis. Additional information is available from the country specialists listed in table 2.

Tools for Stakeholder Involvement in Facility Management Service Design

DEFF Research Database (Denmark)

Nardelli, Giulia; Scupola, Ada

that are more in line with the stakeholder needs and expectations, and may thus result in increased customer satisfaction, better services and, at the very end, an increased competitive advantage for the organization. Background: The background of this study lies in user involvement in service design...... in the design process as well as FM service provision processes. Research limitations: The major limitation of the study consists of the relatively small amount of interviews conducted, which is the basis for finding the tools in FM service design processes....

Canadian involvement in international nuclear cooperation

International Nuclear Information System (INIS)

Jennekens, Jon.

1981-01-01

Since 1945 Canada has been actively involved in the development of an international consensus on measures to prevent the proliferation of nuclear weapons. In parallel with this involvement, Canada has entered into cooperation agreements with several countries under which nuclear materials, equipment and facilities have been supplied in connection with the medical, industrial, agricultural and electrical power applications of nuclear energy. This paper summarizes the actions taken by Canada to encourage the peaceful uses of nuclear energy and to avoid the spread of nuclear weapons [fr

Canadian involvement in international nuclear cooperation

International Nuclear Information System (INIS)

Jennekens, J.

1981-01-01

Since 1945 Canada has been actively involved in the development of an international consensus on measures to prevent the proliferation of nuclear weapons. In parallel with this involvement, Canada has entered into cooperative agreements with several countries under which nuclear materials, equipment and facilities have been supplied in connection with the medical, industrial, agricultural and electrical power applications of nuclear energy. This paper summarizes the actions taken by Canada to encourage the peaceful uses of nuclear energy and to avoid the spread of nuclear weapons. (author)

Nuclear-fuel-cycle risk assessment: descriptions of representative non-reactor facilities. Sections 1-14

Energy Technology Data Exchange (ETDEWEB)

Schneider, K.J.

1982-09-01

The Fuel Cycle Risk Assessment Program was initiated to provide risk assessment methods for assistance in the regulatory process for nuclear fuel cycle facilities other than reactors. This report, the first from the program, defines and describes fuel cycle elements that are being considered in the program. One type of facility (and in some cases two) is described that is representative of each element of the fuel cycle. The descriptions are based on real industrial-scale facilities that are current state-of-the-art, or on conceptual facilities where none now exist. Each representative fuel cycle facility is assumed to be located on the appropriate one of four hypothetical but representative sites described. The fuel cycles considered are for Light Water Reactors with once-through flow of spent fuel, and with plutonium and uranium recycle. Representative facilities for the following fuel cycle elements are described for uranium (or uranium plus plutonium where appropriate): mining, milling, conversion, enrichment, fuel fabrication, mixed-oxide fuel refabrication, fuel reprocessing, spent fuel storage, high-level waste storage, transuranic waste storage, spent fuel and high-level and transuranic waste disposal, low-level and intermediate-level waste disposal, and transportation. For each representative facility the description includes: mainline process, effluent processing and waste management, facility and hardware description, safety-related information and potential alternative concepts for that fuel cycle element. The emphasis of the descriptive material is on safety-related information. This includes: operating and maintenance requirements, input/output of major materials, identification and inventories of hazardous materials (particularly radioactive materials), unit operations involved, potential accident driving forces, containment and shielding, and degree of hands-on operation.

Nuclear-fuel-cycle risk assessment: descriptions of representative non-reactor facilities. Sections 1-14

International Nuclear Information System (INIS)

Schneider, K.J.

1982-09-01

The Fuel Cycle Risk Assessment Program was initiated to provide risk assessment methods for assistance in the regulatory process for nuclear fuel cycle facilities other than reactors. This report, the first from the program, defines and describes fuel cycle elements that are being considered in the program. One type of facility (and in some cases two) is described that is representative of each element of the fuel cycle. The descriptions are based on real industrial-scale facilities that are current state-of-the-art, or on conceptual facilities where none now exist. Each representative fuel cycle facility is assumed to be located on the appropriate one of four hypothetical but representative sites described. The fuel cycles considered are for Light Water Reactors with once-through flow of spent fuel, and with plutonium and uranium recycle. Representative facilities for the following fuel cycle elements are described for uranium (or uranium plus plutonium where appropriate): mining, milling, conversion, enrichment, fuel fabrication, mixed-oxide fuel refabrication, fuel reprocessing, spent fuel storage, high-level waste storage, transuranic waste storage, spent fuel and high-level and transuranic waste disposal, low-level and intermediate-level waste disposal, and transportation. For each representative facility the description includes: mainline process, effluent processing and waste management, facility and hardware description, safety-related information and potential alternative concepts for that fuel cycle element. The emphasis of the descriptive material is on safety-related information. This includes: operating and maintenance requirements, input/output of major materials, identification and inventories of hazardous materials (particularly radioactive materials), unit operations involved, potential accident driving forces, containment and shielding, and degree of hands-on operation

Decommissioning of Facilities. General Safety Requirements. Pt. 6 (Spanish Edition)

International Nuclear Information System (INIS)

2017-01-01

Decommissioning is the last step in the lifetime management of a facility. It must also be considered during the design, construction, commissioning and operation of facilities. This publication establishes requirements for the safe decommissioning of a broad range of facilities: nuclear power plants, research reactors, nuclear fuel cycle facilities, facilities for processing naturally occurring radioactive material, former military sites, and relevant medical, industrial and research facilities. It addresses all the aspects of decommissioning that are required to ensure safety, aspects such as roles and responsibilities, strategy and planning for decommissioning, conduct of decommissioning actions and termination of the authorization for decommissioning. It is intended for use by those involved in policy development, regulatory control and implementation of decommissioning.

Decommissioning of Facilities. General Safety Requirements. Pt. 6 (Russian Edition)

International Nuclear Information System (INIS)

2015-01-01

Decommissioning is the last step in the lifetime management of a facility. It must also be considered during the design, construction, commissioning and operation of facilities. This publication establishes requirements for the safe decommissioning of a broad range of facilities: nuclear power plants, research reactors, nuclear fuel cycle facilities, facilities for processing naturally occurring radioactive material, former military sites, and relevant medical, industrial and research facilities. It addresses all the aspects of decommissioning that are required to ensure safety, aspects such as roles and responsibilities, strategy and planning for decommissioning, conduct of decommissioning actions and termination of the authorization for decommissioning. It is intended for use by those involved in policy development, regulatory control and implementation of decommissioning

The IAEA research project on improvement of safety assessment methodologies for near surface disposal facilities

International Nuclear Information System (INIS)

Torres-Vidal, C.; Graham, D.; Batandjieva, B.

2002-01-01

The International Atomic Energy Agency (IAEA) Research Coordinated Project on Improvement of Safety Assessment Methodologies for Near Surface Disposal Facilities (ISAM) was launched in November 1997 and it has been underway for three years. The ISAM project was developed to provide a critical evaluation of the approaches and tools used in long-term safety assessment of near surface repositories. It resulted in the development of a harmonised approach and illustrated its application by way of three test cases - vault, borehole and Radon (a particular range of repository designs developed within the former Soviet Union) type repositories. As a consequence, the ISAM project had over 70 active participants and attracted considerable interest involving around 700 experts from 72 Member States. The methodology developed, the test cases, the main lessons learnt and the conclusions have been documented and will be published in the form of an IAEA TECDOC. This paper presents the work of the IAEA on improvement of safety assessment methodologies for near surface waste disposal facilities and the application of these methodologies for different purposes in the individual stages of the repository development. The paper introduces the main objectives, activities and outcome of the ISAM project and summarizes the work performed by the six working groups within the ISAM programme, i.e. Scenario Generation and Justification, Modelling, Confidence Building, Vault, Radon Type Facility and Borehole test cases. (author)

Noxious facility impact projection: Incorporating the effects of risk aversion

International Nuclear Information System (INIS)

Nieves, L.A.

1993-01-01

Developing new sites for noxious facilities has become a complex process with many potential pitfalls. In addition to the need to negotiate conditions acceptable to the host community, siting success may depend on the facility proposer's ability to identify a candidate site that not only meets technical requirements, but that is located in a community or region whose population is not highly averse to the risks associated with the type of facility being proposed. Success may also depend on the proposer accurately assessing potential impacts of the facility and offering an equitable compensation package to the people affected by it. Facility impact assessments, as typically performed, include only the effects of changes in population, employment and economic activity associated with facility construction and operation. Because of their scope, such assessments usually show a short-run, net economic benefit for the host region, making the intensely negative public reaction to some types and locations of facilities seem unreasonable. The impact component excluded from these assessments is the long-run economic effect of public perceptions of facility risk and nuisance characteristics. Recent developments in psychological and economic measurement techniques have opened the possibility of correcting this flaw by incorporating public perceptions in projections of economic impacts from noxious facilities

Spatial accessibility to specific sport facilities and corresponding sport practice: the RECORD Study.

Science.gov (United States)

Karusisi, Noëlla; Thomas, Frédérique; Méline, Julie; Chaix, Basile

2013-04-20

Physical activity is considered as a major component of a healthy lifestyle. However, few studies have examined the relationships between the spatial accessibility to sport facilities and sport practice with a sufficient degree of specificity. The aim of this study was to investigate the associations between the spatial accessibility to specific types of sports facilities and the practice of the corresponding sports after carefully controlling for various individual socio-demographic characteristics and neighborhood socioeconomic variables. Data from the RECORD Study involving 7290 participants recruited in 2007-2008, aged 30-79 years, and residing in the Paris metropolitan area were analyzed. Four categories of sports were studied: team sports, racket sports, swimming and related activities, and fitness. Spatial accessibility to sport facilities was measured with two complementary approaches that both take into account the street network (distance to the nearest facility and count of facilities around the dwelling). Associations between the spatial accessibility to sport facilities and the practice of the corresponding sports were assessed using multilevel logistic regression after adjusting for individual and contextual characteristics. High individual education and high household income were associated with the practice of racket sports, swimming or related activities, and fitness over the previous 7 days. The spatial accessibility to swimming pools was associated with swimming and related sports, even after adjustment for individual/contextual factors. The spatial accessibility to facilities was not related to the practice of other sports. High neighborhood income was associated with the practice of a racket sport and fitness. Accessibility is a multi-dimensional concept that integrates educational, financial, and geographical aspects. Our work supports the evidence that strategies to increase participation in sport activities should improve the spatial and

Radiation monitoring considerations for radiobiology facilities

International Nuclear Information System (INIS)

McClelland, T.W.; McFall, E.D.

1976-01-01

Battelle, Pacific Northwest Laboratories, conducts a wide variety of radiobiology and radioecology research in a number of facilities on the Hanford Reservation. Review of radiation monitoring problems associated with storage, plant and animal experiments, waste handling and sterile facilities shows that careful monitoring, strict procedural controls and innovative techniques are required to minimize occupational exposure and control contamination. Although a wide variety of radioactivity levels are involved, much of the work is with extremely low level materials. Monitoring low level work is mundane and often impractical but cannot be ignored in today's ever tightening controls

76 FR 73727 - Biweekly Notice; Applications and Amendments to Facility Operating Licenses Involving No...

Science.gov (United States)

2011-11-29

..., Donald C. Cook Nuclear Plant, Unit 2 (DCCNP-2), Berrien County, Michigan; Date of amendment request... Counsel, Indiana Michigan Power Company, One Cook Place, Bridgman, MI 49106. NRC Acting Branch Chief: Thomas J. Wengert. Notice of Issuance of Amendments to Facility Operating Licenses During the period...

[Surgical treatment and prognosis of Borrmann type IIII( gastric cancer involving the whole stomach].

Science.gov (United States)

Dong, Ruizeng; Zhang, Zewei; Zhou, Yiming; Hua, Yonghong; Guo, Jianmin

2018-02-25

To explore the surgical treatment and prognosis of Borrmann type IIII( gastric cancer involving the whole stomach. Clinicopathological characteristics and survival data of 223 patients with Borrmann type IIII( gastric cancer involving the whole stomach (defined as the tumor infiltrating 3 regions of the stomach) receiving surgical treatment at the Department of Abdominal Surgery of Zhejiang Cancer Hospital between January 2002 and December 2015 were analyzed retrospectively. The survival time of patients with different clinicopathological features and different treatment methods was compared. Cox regression was used to analyze the independent prognostic factors. Two hundred and twenty-three patients with Borrmann type IIII( gastric cancer involving the whole stomach accounted for 24.0% (223/930) of all Borrmann type IIII( gastric cancer cases undergoing surgical resection at the same period. There were 147 males and 76 females with an average age of 57.8 years. All the patients underwent total gastrectomy. Of these patients, radical resection was performed in 149 cases(66.8%) and palliative resection in 74 cases (33.2%). Combined organ resection was performed in 43 patients (19.3%), including 25 splenectomies, 6 pancreatic body and tail plus spleen and transverse colon resections, 2 transverse colon plus spleen resections, 2 right colon resections, 2 transverse colon resections, 2 ovariectomies, 1 partial jejunal resection, 1 pancreatoduodenectomy, 1 pancreatic tail plus transverse colon resection, and 1 partial pancreatectomy. Postoperative complications occurred in 28 patients(12.6%), including 10 patients with combined organ resection. Esophagojejunal fistula was the most frequent complication, accounting for 39.3%(11/28). Perioperative mortality occurred in 3 patients (1.3%). Thirty-nine patients underwent preoperative adjuvant chemotherapy (clinical stage: cT4aN0M0 in 1 patient, cT4bN1-2M0 in 12 patients, cT4aN1-2M0 in 20 patients, and cT4aN3M0 in 6 patients

Recruitment of mobility limited older adults into a facility-led exercise-nutrition study: the effect of social involvement

Science.gov (United States)

Purpose of the Study: Older adults are among the most challenging population groups to enroll into health-related research. This article describes two methods used by investigators to recruit mobility limited older adults residing at assisted living or senior housing (SH) facilities into a facility-...

Figure 5, Biofuel refinery facility locations

Data.gov (United States)

U.S. Environmental Protection Agency — This workbook contains the locations and types of current and anticipated biofuel feedstock processing facilities assumed under the simulated scenarios. This dataset...

[Morphological alterations in nailfold capillaroscopy and the clinical picture of vascular involvement in autoimmune diseases: systemic lupus erythematosus and type 1 diabetes].

Science.gov (United States)

Kuryliszyn-Moskal, Anna; Ciołkiewicz, Mariusz; Dubicki, Artur

2010-01-01

Systemic lupus erythematosus (SLE) and type 1 diabetes mellitus (DM) belong to the group of autoimmune diseases presenting with a wide range of organ manifestations. Microvascular abnormalities seem to play a crucial role in the development of persistent multi-organ complications in both diseases. The aim of this study was to determine the relationship between microvascular changes examined with nailfold capillaroscopy and organ involvement. We eurolled 76 SLE patients, 106 patients with type 1 diabetes, and 40 healthy controls. Morphological changes were observed with nailfold capillaroscopy in 86 (81%) diabetics and in 70 (92.1%) SLE patients. Severe capillaroscopic changes were disclosed in 32 out of 54 (59%) diabetic patients with microangiopathy and in only 7 out of 52 (13%) patients without microangiopathy. In the SLE group, severe capillaroscopic abnormalities were found in 18 out of 34 (52.9%) patients with organ involvement and in 9 out of 42 (21.4%) patients without organ involvement. The capillaroscopic score was significantly higher in diabetic patients with microangiopathic complications in comparison to patients without microangiopathy (p nailfold capillaroscopy reflect the extent of microvascular involvement and are associated with organ involvement in SLE and diabetes.

A requirement for Australian research: access to 'big science' facilities, a report by the Australian National Committee for crystallography

International Nuclear Information System (INIS)

1989-03-01

Two types of 'Big Science' research facility - synchrotron radiation sources and intense neutron beams - are now recognised as essential resources for a wide range of research activities in chemistry, physics and biology. The cost of such facilities and the lack of a sufficiently large user base will probably preclude their construction in Australia in the foreseeable future. The needs of Australian crystallographers for access to such facilities are assessed. In relation to synchrotron radiation sources, the Committee considered only the question of access to such facilities overseas. In relation to neutron beam sources, the Committee's inquiries included not only the question of access to powerful facilities overseas but also the special problems which confront Australian crystallographers as a result of the obsolescence of the HIFAR reactor. The arguments about, and options for, funding Australian use of facilities overseas are presented. The Committee concluded there is a strong case for the purchase of a beam-line at an overseas synchrotron radiation facility and a strong, though less urgent, case for substantial Australian involvement in an overseas neutron beam facility. The Committee recommended that the Australian HIFAR reactor be refurbished in its present shell, retaining the present flux and power levels, and that in the upgrading of the neutron scattering instrumentation at HIFAR special consideration be given to including items which are sufficiently specialised to attract the international neutron scattering community

Facility certification program for coal miners pneumoconiosis

International Nuclear Information System (INIS)

Trout, E.D.; Kelley, J.P.; Larson, V.L.; Herbert, G.L.

1976-01-01

Public Law 91-173, often referred to as the Black Lung Law, called for a chest radiograph of all active coal miners at stated intervals. The National Institute for Occupational Safety and Health was responsible for carrying out the provisions of the law. Among other requirements was a provision for certification of radiological facilities where radiological examinations would be provide. A test object to be radiographed by each such facility was designed and sent to those facilities applying for certification. To date, 284 facilities have applied for certification of which 215 have been approved. A record has been kept of the number of times any approved facility submitted radiographs before approval. A complete listing of the types of equipment used, personnel qualifications and other pertinent data will be reported

The operation of post-irradiation examination facility

Energy Technology Data Exchange (ETDEWEB)

Kim, Eun Ka; Park, Kwang Jun; Lee, Won Sang [and others; Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

1994-01-01

The operation and management of PIE facility was executed in 1993. An indigenous 16 x 16 PWR type fuel assembly (ID No. J44) which was discharged from Kori unit 2 power reactor was transported to KAERI`s PIE facility and in-pool nondestructive examination and hot cell examination for the fuel were carried out. Because the above-mentioned 16 x 16 fuel is different from 14 x 14 fuel in its size and array of fuel rods, several examination and handling equipment for the 16 x 16 type fuel were designed and fabricated. PIE facility was operated in normal condition with the periodical check and inspection of the devices. The filter housing on the roof hood in chemical analysis hot cell was modified mounting air pressure gauge to indicate the optimal filter exchanging time. The burst air heating coil plate and the broken blowing fan of the HVAC system were repaired. The defaced grand packing in pool water circulation pump was replaced with the mechanical seal to prevent the leakage from the pump shaft sealing. The radiation monitoring in the facility was carried out to maintain the safe working condition and several radiation monitors were repaired. Spare parts for the radiation monitoring system were prepared to maintain the facility safely. The performance test of the emergency electric power supply system including UPS, battery and diesel generator was carried out. Oxide layer thickness measuring device for the performance test. Several devices including spent fuel handling equipment for the 17 x 17 PWR type fuel assembly were designed and fabricated for the subsequent PIE of nuclear fuels. 35 tabs., 17 figs., 7 refs. (Author) .new.

Facilities Management Practices in Malaysia: A Literature Review

Directory of Open Access Journals (Sweden)

Isa Nordiana Mohd

2016-01-01

Full Text Available Facilities management in Malaysia has been practiced for decades. The development of its formal practice parallels the improvement of the built environment in the nation. Involvement of the public and private sectors teaming up in arranging the National Asset and Facilities Management (NAFAM in demonstrates the vital collaboration in the facilities management area in Malaysia. Facilities management is seen distinctively as indicated by diverse geographical locations, interests and schools of thought. Facilities management is delegated a service-based industry which gives proficient counsel and administration of clients’ building facilities including residential, commercial, industrial, airports terminals and offices. The aim of this paper is to review the gaps that exist, especially on how FM is being practice in comparison with the published FM body of knowledge. Very relying upon literature, this paper discovered a gap that is an unclear description of current FM applications. This research aims to give new bits of knowledge to upgrade comprehension of FM execution in Malaysia.

University multi-user facility survey-2010.

Science.gov (United States)

Riley, Melissa B

2011-12-01

Multi-user facilities serve as a resource for many universities. In 2010, a survey was conducted investigating possible changes and successful characteristics of multi-user facilities, as well as identifying problems in facilities. Over 300 surveys were e-mailed to persons identified from university websites as being involved with multi-user facilities. Complete responses were received from 36 facilities with an average of 20 years of operation. Facilities were associated with specific departments (22%), colleges (22%), and university research centers (8.3%) or were not affiliated with any department or college within the university (47%). The five most important factors to succeed as a multi-user facility were: 1) maintaining an experienced, professional staff in an open atmosphere; 2) university-level support providing partial funding; 3) broad client base; 4) instrument training programs; and 5) an effective leader and engaged strategic advisory group. The most significant problems were: 1) inadequate university financial support and commitment; 2) problems recovering full service costs from university subsidies and user fees; 3) availability of funds to repair and upgrade equipment; 4) inability to retain highly qualified staff; and 5) unqualified users dirtying/damaging equipment. Further information related to these issues and to fee structure was solicited. Overall, there appeared to be a decline in university support for facilities and more emphasis on securing income by serving clients outside of the institution and by obtaining grants from entities outside of the university.

Standard irradiation facilities for use in TRIGA reactors

International Nuclear Information System (INIS)

Kolbasov, B.N.; Luse, R.A.

1972-01-01

The standard neutron irradiation facility (SNIP) was developed under IAEA and FAO co-ordinated research program for the standardization of neutron irradiation facilities for radiobiological research, resulting in the possibility to use fast neutrons from pool-type reactors for radiobiological studies. The studies include irradiation of seeds for crop improvement, of Drosophila for genetic studies, and of microorganisms for developing industrially useful mutants, as well as fundamental studies in radiation biology. The facilities, located in the six pool-type reactors (in Austria, Bulgaria, India, Philippines, Thailand and Taiwan), have been calibrated and utilized to compare the response to fast neutrons of barley seeds (variety Himalaya CI 000620) which were selected as a standard biological monitor by which to estimate neutron fluxes in different reactors. These comparative irradiation studies showed excellent agreement and reproducibility

Overview - Defense Waste Processing Facility Operating Experience

International Nuclear Information System (INIS)

Norton, M.R.

2002-01-01

The Savannah River Site's Defense Waste Processing Facility (DWPF) near Aiken, SC is the world's largest radioactive waste vitrification facility. Radioactive operations began in March 1996 and over 1,000 canisters have been produced. This paper presents an overview of the DWPF process and a summary of recent facility operations and process improvements. These process improvements include efforts to extend the life of the DWPF melter, projects to increase facility throughput, initiatives to reduce the quantity of wastewater generated, improved remote decontamination capabilities, and improvements to remote canyon equipment to extend equipment life span. This paper also includes a review of a melt rate improvement program conducted by Savannah River Technology Center personnel. This program involved identifying the factors that impacted melt rate, conducting small scale testing of proposed process changes and developing a cost effective implementation plan

Waste management considerations in nuclear facility decommissioning

International Nuclear Information System (INIS)

Elder, H.K.; Murphy, E.S.

1981-01-01

Decommissioning of nuclear facilities involves the management of significant quantities of radioactive waste. This paper summarizes information on volumes of waste requiring disposal and waste management costs developed in a series of decommissioning studies performed for the U.S. Nuclear Regulatory Commission by the Pacific Northwest Laboratory. These studies indicate that waste management is an important cost factor in the decommissioning of nuclear facilities. Alternatives for managing decommissioning wastes are defined and recommendations are made for improvements in waste management practices

DOE research and development and field facilities

Energy Technology Data Exchange (ETDEWEB)

1979-06-01

This report describes the roles of DOE's headquarters, field offices, major multiprogram laboratories, Energy Technology and Mining Operations Centers, and other government-owned, contractor-operated facilities which are located in all regions of the United States. It gives brief descriptions of resources, activities, and capabilities of each field facility (sections III through V). These represent a cumulative capital investment of $12 billion and involve a work force of approximately 12,000 government (field) employees and approximately 100,000 contractor employees.

Process for decontamination of surfaces in an facility of natural uranium hexafluoride production (UF{sub 6}); Processo de descontaminação de superfícies em uma instalação de produção de hexafluoreto de urânio natural (UF{sub 6})

Energy Technology Data Exchange (ETDEWEB)

Almeida, Claudio C. de; Silva, Teresinha M.; Rodrigues, Demerval L.; Carneiro, Janete C.G.G., E-mail: calmeida@ipen.br [Instituto de Pesquisas Energéticas e Nucleares(IPEN/CNEN-SP), São Paulo, SP (Brazil). Gerência de Radioproteção

2017-07-01

The experience acquired in the actions taken during the decontamination process of an IPEN-CNEN / SP Nuclear and Energy Research Institute facility, for the purpose of making the site unrestricted, is reported. The steps of this operation involved: planning, training of facility operators, workplace analysis and radiometric measurements. The facility had several types of equipment from the natural uranium hexafluoride (UF{sub 6}) production tower and other facility materials. Rules for the transportation of radioactive materials were established, both inside and outside the facility and release of materials and installation.

Data collection, validation, and description for the Oak Ridge nuclear facilities mortality study

International Nuclear Information System (INIS)

Watkins, J.P.; Reagan, J.L.; Cragle, D.L.; West, C.M.; Tankersley, W.G.; Crawford-Brown, D.J.

1995-01-01

To investigate the long-term health effects of protracted occupational exposure to low levels of ionizing radiation, a mortality study was initiated by pooling data for 118,588 workers hired between 1943 and 1982, at three Department of Energy (DOE) facilities in Oak Ridge, Tennessee, with follow-up through 1984. Topics for this discussion will include issues involving the collection and validation of data for individuals in the study cohort, and characteristics of their demographic and radiation exposure data. Since the data were compiled between the late 1960s and the present under the direction of several principal investigators, it was essential to verify data precision and to understand how exposure data were generated prior to beginning any analysis. A stratified random sample of workers in the cohort was chosen for verification of their computerized data as it appeared in the database. Original source documents were reviewed to verify demographic data, as well as internal and external radiation exposure data. Extensive effort was expended to document the personal radiation monitoring policies and types of dosimeters used at each facility over the 42 years included in the study. Characteristics of internal and external exposure data by facility and year were examined by graphical methods with the intent of combining these monitoring data over time and across facilities

PACTEL and PWR PACTEL Test Facilities for Versatile LWR Applications

Directory of Open Access Journals (Sweden)

Virpi Kouhia

2012-01-01

Full Text Available This paper describes construction and experimental research activities with two test facilities, PACTEL and PWR PACTEL. The PACTEL facility, comprising of reactor pressure vessel parts, three loops with horizontal steam generators, a pressurizer, and emergency core cooling systems, was designed to model the thermal-hydraulic behaviour of VVER-440-type reactors. The facility has been utilized in miscellaneous applications and experiments, for example, in the OECD International Standard Problem ISP-33. PACTEL has been upgraded and modified on a case-by-case basis. The latest facility configuration, the PWR PACTEL facility, was constructed for research activities associated with the EPR-type reactor. A significant design basis is to utilize certain parts of PACTEL, and at the same time, to focus on a proper construction of two new loops and vertical steam generators with an extensive instrumentation. The PWR PACTEL benchmark exercise was launched in 2010 with a small break loss-of-coolant accident test as the chosen transient. Both facilities, PACTEL and PWR PACTEL, are maintained fully operational side by side.

PACTEL and PWR PACTEL Test Facilities for Versatile LWR Applications

International Nuclear Information System (INIS)

Virpi Kouhia, V.; Purhonen, H.; Riikonen, V.; Puustinen, M.; Kyrki-Rajamaki, R.; Vihavainen, J.

2012-01-01

This paper describes construction and experimental research activities with two test facilities, PACTEL and PWR PACTEL. The PACTEL facility, comprising of reactor pressure vessel parts, three loops with horizontal steam generators, a pressurizer, and emergency core cooling systems, was designed to model the thermal-hydraulic behaviour of VVER-440-type reactors. The facility has been utilized in miscellaneous applications and experiments, for example, in the OECD International Standard Problem ISP-33. PACTEL has been upgraded and modified on a case-by-case basis. The latest facility configuration, the PWR PACTEL facility, was constructed for research activities associated with the EPR-type reactor. A significant design basis is to utilize certain parts of PACTEL, and at the same time, to focus on a proper construction of two new loops and vertical steam generators with an extensive instrumentation. The PWR PACTEL benchmark exercise was launched in 2010 with a small break loss-of-coolant accident test as the chosen transient. Both facilities, PACTEL and PWR PACTEL, are maintained fully operational side by side.

Assessment of the facilities on Jackass Flats and other Nevada Test Site facilities for the new nuclear rocket program

International Nuclear Information System (INIS)

Chandler, G.; Collins, D.; Dye, K.; Eberhart, C.; Hynes, M.; Kovach, R.; Ortiz, R.; Perea, J.; Sherman, D.

1992-01-01

Recent NASA/DOE studies for the Space Exploration Initiative have demonstrated a critical need for the ground-based testing of nuclear rocket engines. Experience in the ROVER/NERVA Program, experience in the Nuclear Weapons Testing Program, and involvement in the new nuclear rocket program has motivated our detailed assessment of the facilities used for the ROVER/NERVA Program and other facilities located at the Nevada Test Site (NTS). The ROVER/NERVA facilities are located in the Nevada Research L, Development Area (NRDA) on Jackass Flats at NTS, approximately 85 miles northwest of Las Vegas. To guide our assessment of facilities for an engine testing program we have defined a program goal, scope, and process. To execute this program scope and process will require ten facilities. We considered the use of all relevant facilities at NTS including existing and new tunnels as well as the facilities at NRDA. Aside from the facilities located at remote sites and the inter-site transportation system, all of the required facilities are available at NRDA. In particular we have studied the refurbishment of E-MAD, ETS-1, R-MAD, and the interconnecting railroad. The total cost for such a refurbishment we estimate to be about $253M which includes additional contractor fees related to indirect, construction management, profit, contingency, and management reserves. This figure also includes the cost of the required NEPA, safety, and security documentation

1325-N Liquid Waste Disposal Facility Supplemental Information to the Hanford Facility Contingency Plan (DOE/RL-93-75)

International Nuclear Information System (INIS)

Edens, V.G.

1998-03-01

The 1325-N Liquid Waste Disposal Facility located at the 100-N Area of the Hanford Site started receiving part of the N Reactor liquid radioactive effluent flow in 1983. In September 1985, the 1325-N Facility became the primary liquid waste disposal system for the N Reactor. The facility is located approximately 60 feet above and 2000 feet east of the shore of the Columbia River. Waste stream discharges were ceased in April 1991.Specific information on types of waste discharged to 1325-N are contained within the Part A, Form 3, Permit application of this unit

INVOLVEMENT OF “TYPE-1 HERPES SIMPLEX” IN THE ETIOPATHOGENY OF THE GINGIVAL-PERIODONTAL DISEASES

Directory of Open Access Journals (Sweden)

Simona Ionela GRIGORAS

2012-06-01

Full Text Available Scope of the study: The present clinico-statistical study aimed at evaluating the oral manifestations determined by viral infections, especially herpes virusi, in correlation with some general symptoms and demographic characteristics. Materials and method: 68 cases of herpetic gingivo-stomatitis treated in the Clinical Hospital of Infectious Diseases of Ia[i have been investigated between January 1, 2010 – December 31, 2010. The oral clinical investigations, developed in the Clinics of Infectious Diseases and in the Department of Periodontology, aimed at evaluating the occurrence and evolution of the oral manifestations characteristic to this type of viral infections. Results and discussion: The oral manifestations observed within the experimental group had a polymorphous character. At group level, a relatively high number of patients (40.2% showed no oral lesions in the moment of the clinical examination, the remaining cases (49.8% evidencing more or less specific oral manifestations for the viral pathology involved in the debut and evolution of the disease under consideration. 13 cases (representing 9.0% of the total group evidenced oral lesions of ulceration and vesicle type, and 25 cases (13.6% showed lesion elements of exclusively vesicle type. Conclusions: The clinical-statistical study on the incidence and characteristics of the oral manifestations of the viral infection with type-1 herpes virus, clinically manifested, as well, at the level of the gingival mucous membrane, evidenced the constant presence of a higher incidence of this type of virusi in the population, as well as the polymorphous character of the oral lesions.

Type B Drum packages

International Nuclear Information System (INIS)

Edwards, W.S.

1995-11-01

The Type B Drum package is a container in which a single drum containing Type B quantities of radioactive material will be packaged for shipment. The Type B Drum containers are being developed to fill a void in the packaging and transportation capabilities of the US Department of Energy (DOE), as no double containment packaging for single drums of Type B radioactive material is currently available. Several multiple-drum containers and shielded casks presently exist. However, the size and weight of these containers present multiple operational challenges for single-drum shipments. The Type B Drum containers will offer one unshielded version and, if needed, two shielded versions, and will provide for the option of either single or double containment. The primary users of the Type B Drum container will be any organization with a need to ship single drums of Type B radioactive material. Those users include laboratories, waste retrieval facilities, emergency response teams, and small facilities

Life science experiments performed in space in the ISS/Kibo facility and future research plans.

Science.gov (United States)

Ohnishi, Takeo

2016-08-01

Over the past several years, current techniques in molecular biology have been used to perform experiments in space, focusing on the nature and effects of space radiation. In the Japanese 'Kibo' facility in the International Space Station (ISS), the Japan Aerospace Exploration Agency (JAXA) has performed five life science experiments since 2009, and two additional experiments are currently in progress. The first life science experiment in space was the 'Rad Gene' project, which utilized two human cultured lymphoblastoid cell lines containing a mutated P53 : gene (m P53 : ) and a parental wild-type P53 : gene (wt P53 : ) respectively. Four parameters were examined: (i) detecting space radiation-induced DSBs by observing γH2AX foci; (ii) observing P53 : -dependent gene expression during space flight; (iii) observing P53 : -dependent gene expression after space flight; and (iv) observing the adaptive response in the two cell lines containing the mutated and wild type P53 : genes after exposure to space radiation. These observations were completed and have been reported, and this paper is a review of these experiments. In addition, recent new information from space-based experiments involving radiation biology is presented here. These experiments involve human cultured cells, silkworm eggs, mouse embryonic stem cells and mouse eggs in various experiments designed by other principal investigators in the ISS/Kibo. The progress of Japanese science groups involved in these space experiments together with JAXA are also discussed here. The Japanese Society for Biological Sciences in Space (JSBSS), the Utilization Committee of Space Environment Science (UCSES) and the Science Council of Japan (ACJ) have supported these new projects and new experimental facilities in ISS/Kibo. Currently, these organizations are proposing new experiments for the ISS through 2024. © The Author 2016. Published by Oxford University Press on behalf of The Japan Radiation Research Society and

Life science experiments performed in space in the ISS/Kibo facility and future research plans

International Nuclear Information System (INIS)

Ohnishi, Takeo

2016-01-01

Over the past several years, current techniques in molecular biology have been used to perform experiments in space, focusing on the nature and effects of space radiation. In the Japanese ‘Kibo’ facility in the International Space Station (ISS), the Japan Aerospace Exploration Agency (JAXA) has performed five life science experiments since 2009, and two additional experiments are currently in progress. The first life science experiment in space was the ‘Rad Gene’ project, which utilized two human cultured lymphoblastoid cell lines containing a mutated p53 gene (mp53) and a parental wild-type p53 gene (wtp53) respectively. Four parameters were examined: (i) detecting space radiation–induced DSBs by observing γH2AX foci; (ii) observing p53-dependent gene expression during space flight; (iii) observing p53-dependent gene expression after space flight; and (iv) observing the adaptive response in the two cell lines containing the mutated and wild type p53 genes after exposure to space radiation. These observations were completed and have been reported, and this paper is a review of these experiments. In addition, recent new information from space-based experiments involving radiation biology is presented here. These experiments involve human cultured cells, silkworm eggs, mouse embryonic stem cells and mouse eggs in various experiments designed by other principal investigators in the ISS/Kibo. The progress of Japanese science groups involved in these space experiments together with JAXA are also discussed here. The Japanese Society for Biological Sciences in Space (JSBSS), the Utilization Committee of Space Environment Science (UCSES) and the Science Council of Japan (ACJ) have supported these new projects and new experimental facilities in ISS/Kibo. Currently, these organizations are proposing new experiments for the ISS through 2024

Current status of irradiation facilities in JRR-3 and JRR-4

International Nuclear Information System (INIS)

Hori, Naohiko; Wada, Shigeru; Sasajima, Fumio; Kusunoki, Tsuyoshi

2006-01-01

The Department of Research Reactor has operated two research reactors, JRR-3 and JRR-4. These reactors were constructed in the Tokai Research Establishment. Many researchers and engineers use these joint-use facilities. JRR-3 is a light water moderated and cooled, pool type research reactor using low-enriched silicide fuel. JRR-3's maximum thermal power is 20MW. JRR-3 has nine vertical irradiation holes for RI production, nuclear fuels and materials irradiation at reactor core area. JRR-3 has many kinds of irradiation holes in a heavy water tank around the reactor core. These are two hydraulic rabbit irradiation facilities, two pneumatic rabbit irradiation facilities, one activation analysis irradiation facilities, one uniform irradiation facility, one rotating irradiation facility and one capsule irradiation facility. JRR-3 has nine horizontal experimental holes, that are used by many kinds of neutron beam experimental facilities using these holes. JRR-4 is a light water moderated and cooled, swimming pool type research reactor using low-enriched silicide fuel. JRR-4's maximum thermal power is 3.5MW. JRR-4 has five vertical irradiation tubes at reactor core area, three capsule irradiation facilities, one hydraulic rabbit irradiation facility, and one pneumatic rabbit irradiation facility. JRR-4 has a neutron beam hole, and it has used neutron beam experiments, irradiations for activation analysis and medical neutron irradiations. (author)

Experimental facilities of Valduc critical station

International Nuclear Information System (INIS)

Mangin, D.; Maubert, L.

1975-01-01

The critical facility of Valduc and its experimentation possibilities are described. The different experimental programs carried out since 1962 are briefly reviewed. The last program involving a plutonium nitrate solution (18.9wt% 240 Pu) in a large parallelepipedic tank is presented and main results given [fr

Profiles of facilities used for HTR research and testing

International Nuclear Information System (INIS)

1980-05-01

This report contains a current description of facilities supporting HTR research and development submitted by countries participating in the IWGFR. It has the purpose of providing an overview of the facilities available for use and of the types of experiments that can be conducted therein

Nonreactor nuclear facilities: standards and criteria guide

International Nuclear Information System (INIS)

Brynda, W.J.; Junker, L.; Karol, R.C.; Lobner, P.R.; Goldman, L.A.

1981-09-01

This guide is a source document that identifies standards, codes, and guides that address the nuclear safety considerations pertinent to nuclear facilities as defined in DOE Order 5480.1, Chapter V, Safety of Nuclear Facilities. The guidance and criteria provided are directed toward areas of safety usually addressed in a Safety Analysis Report. The areas of safety include, but are not limited to, siting, principal design criteria and safety system design guidelines, radiation protection, accident analysis, and quality assurance. The guide is divided into two sections: general guidelines and appendices. Those guidelines that are broadly applicable to most nuclear facilities are presented in the general guidelines. These general guidelines may have limited applicability to subsurface facilities such as waste repositories. Guidelines specific to the various types or categories of nuclear facilities are presented in the appendices. These facility-specific appendices provide guidelines and identify standards and criteria that should be considered in addition to, or in lieu of, the general guidelines

Managing highly flexible facilities: an essential complementary asset at risk

NARCIS (Netherlands)

Tierney, Robert; Tierney, R.; Groen, Arend J.; Harms, Rainer; Luizink, M.; Hetherington, D.; Steward, H.; Walsh, Steven Thomas; Linton, Jonathan; Linton, J.D.

2012-01-01

Purpose: Twenty first century problems are increasingly being addressed by multi technology solutions developed by regional entrepreneurial and intreprepreneurial innovators. However, they require an expensive new type of fabrication facility. Multiple technology production facilities (MTPF) have

Reactor Sharing at Rensselaer Critical Facility

International Nuclear Information System (INIS)

D. Steiner, D. Harris, T. Trumbull

2006-01-01

This final report summarizes the reactor sharing activities at the Rensselaer Critical Facility. An example of a typical tour is also included. Reactor sharing at the RCF brings outside groups into the facility for a tour, an explanation of reactor matters, and a reactor measurement. It has involved groups ranging from high school classes to advanced college groups and in size from a few to about 50 visitors. The RCF differs from other university reactors in that its fuel is like that of large power reactors, and its research and curriculum are dedicated to power reactor matters

Earthquake damage to underground facilities

International Nuclear Information System (INIS)

Pratt, H.R.; Stephenson, D.E.; Zandt, G.; Bouchon, M.; Hustrulid, W.A.

1980-01-01

In order to assess the seismic risk for an underground facility, a data base was established and analyzed to evaluate the potential for seismic disturbance. Substantial damage to underground facilities is usually the result of displacements primarily along pre-existing faults and fractures, or at the surface entrance to these facilities. Evidence of this comes from both earthquakes and large explosions. Therefore, the displacement due to earthquakes as a function of depth is important in the evaluation of the hazard to underground facilities. To evaluate potential displacements due to seismic effects of block motions along pre-existing or induced fractures, the displacement fields surrounding two types of faults were investigated. Analytical models were used to determine relative displacements of shafts and near-surface displacement of large rock masses. Numerical methods were used to determine the displacement fields associated with pure strike-slip and vertical normal faults. Results are presented as displacements for various fault lengths as a function of depth and distance. This provides input to determine potential displacements in terms of depth and distance for underground facilities, important for assessing potential sites and design parameters

Complying with the Federal Facilities Compliance Act

International Nuclear Information System (INIS)

Pavetto, C.S.; Watmore, A.S.

1994-01-01

The Federal Facilities Compliance Act (FFCA), signed into law on October 6, 1992, amended the Resource Conservation and Recovery Act (RCRA) to place significant additional environmental compliance responsibilities on federal facilities. The federal government has expressly waived sovereign immunity regarding hazardous waste enforcement action taken against these facilities by the states and the EPA. An exception exists for mixed waste violations. The FFCA defines mixed waste as hazardous waste, as defined by RCRA, combined with source, special nuclear or by-product material that is subject to the Atomic Energy Act of 1954. As the majority owner of mixed waste in the United States, the Department of Energy (DOE) must satisfy several new requirements under the FFCA for their facilities. This paper reviews the FFCA's requirements and how they apply to and may affect the DOE and other federal facilities. Included in the review are responsibilities of federal agencies involved and the role of the EPA and the states. In addition, this paper discusses the intent of the FFCA to encourage development of federal facility agreements (FFA) between federal agencies, the EPA and state environmental regulatory agencies

Ownership type and team climate in elderly care facilities: the moderating effect of stress factors.

Science.gov (United States)

Heponiemi, Tarja; Elovainio, Marko; Kouvonen, Anne; Noro, Anja; Finne-Soveri, Harriet; Sinervo, Timo

2012-03-01

This paper is a report of a study examining the association between ownership type and perceived team climate among older people care staff. In addition, we examined whether work stress factors (time pressure, resident-related stress, role conflicts and role ambiguity) mediated or moderated the above mentioned association. There has been a trend towards contracting out in older people care facilities in Finland and the number of private for-profit firms has increased. Studies suggest that there may be differences in employee well-being and quality of care according to the ownership type of older people care. Cross-sectional survey data was collected during the autumn of 2007 from 1084 Finnish female older people care staff aged 18-69 years were used. Team Climate Inventory was used to measure team climate. Ownership type was divided into four categories: for-profit sheltered homes, not-for-profit sheltered homes, public sheltered homes and not-for-profit nursing homes. Analyses of covariance were used to examine the associations. Team climate dimensions participative safety, vision and support for innovation were higher in not-for-profit organizations (both sheltered homes and nursing homes) compared to for-profit sheltered homes and public sheltered homes. Stress factors did not account for these associations but acted as moderators in a way that in terms of task orientation and participative safety employees working in for-profit organizations seemed to be slightly more sensitive to work-related stress than others. Our results suggest that for-profit organizations and public organizations may have difficulties in maintaining their team climate. In consequence, these organizations should focus more effort on improving their team climate. © 2011 Blackwell Publishing Ltd.

Facility decontamination technology workshop

International Nuclear Information System (INIS)

1980-10-01

Purpose of the meeting was to provide a record of experience at nuclear facilities, other than TMI-2, of events and incidents which have required decontamination and dose reduction activities, and to furnish GPU and others involved in the TMI-2 cleanup with the results of that decontamination and dose reduction technology. Separate abstracts were prepared for 24 of the 25 papers; the remaining paper had been previously abstracted

Facility decontamination technology workshop

Energy Technology Data Exchange (ETDEWEB)

None

1980-10-01

Purpose of the meeting was to provide a record of experience at nuclear facilities, other than TMI-2, of events and incidents which have required decontamination and dose reduction activities, and to furnish GPU and others involved in the TMI-2 cleanup with the results of that decontamination and dose reduction technology. Separate abstracts were prepared for 24 of the 25 papers; the remaining paper had been previously abstracted. (DLC)

Nuclear materials facility safety initiative

International Nuclear Information System (INIS)

Peddicord, K.L.; Nelson, P.; Roundhill, M.; Jardine, L.J.; Lazarev, L.; Moshkov, M.; Khromov, V.V.; Kruchkov, E.; Bolyatko, V.; Kazanskij, Yu.; Vorobeva, I.; Lash, T.R.; Newton, D.; Harris, B.

2000-01-01

Safety in any facility in the nuclear fuel cycle is a fundamental goal. However, it is recognized that, for example, should an accident occur in either the U.S. or Russia, the results could seriously delay joint activities to store and disposition weapons fissile materials in both countries. To address this, plans are underway jointly to develop a nuclear materials facility safety initiative. The focus of the initiative would be to share expertise which would lead in improvements in safety and safe practices in the nuclear fuel cycle.The program has two components. The first is a lab-to-lab initiative. The second involves university-to-university collaboration.The lab-to-lab and university-to-university programs will contribute to increased safety in facilities dealing with nuclear materials and related processes. These programs will support important bilateral initiatives, develop the next generation of scientists and engineers which will deal with these challenges, and foster the development of a safety culture

Seismic safety assessment of nuclear facilities other than NPPs

International Nuclear Information System (INIS)

Coman, O.; Dragomirescu, A.; Kope, F.; Zemtev, N.

2003-01-01

Many research nuclear facilities are much simpler as compared with a Nuclear Power Plant (NPP) and the accident scenarios corresponding to an external initiating events and the relevant shutdown paths are much easier to be identified. Therefore, simpler methods than an EE-PSA can be often involved in the evaluation of the overall risk associated to such nuclear facilities in respect to External Event Hazards. (author)

Seismic qualification program plan for continued operation at DOE-SRS nuclear material processing facilities

International Nuclear Information System (INIS)

Talukdar, B.K.; Kennedy, W.N.

1991-01-01

The Savannah River Facilities for the most part were constructed and maintained to standards that were developed by Du Pont and are not rigorously in compliance with the current General Design Criteria (GDC); DOE Order 6430.IA requirements. In addition, many of the facilities were built more than 30 years ago, well before DOE standards for design were issued. The Westinghouse Savannah River Company (WSRC) his developed a program to address the evaluation of the Nuclear Material Processing (NMP) facilities to GDC requirements. The program includes a facility base-line review, assessment of areas that are not in compliance with the GDC requirements, planned corrective actions or exemptions to address the requirements, and a safety assessment. The authors from their direct involvement with the Program, describe the program plan for seismic qualification including other natural phenomena hazards,for existing NMP facility structures to continue operation Professionals involved in similar effort at other DOE facilities may find the program useful

Facile synthesis of nanorod-type graphitic carbon nitride/Fe2O3 composite with enhanced photocatalytic performance

International Nuclear Information System (INIS)

Wang, Jiangpeng; Li, Changqing; Cong, Jingkun; Liu, Ziwei; Zhang, Hanzhuo; Liang, Mei; Gao, Junkuo; Wang, Shunli; Yao, Juming

2016-01-01

Here we report a facile synthesis of nanorod-type graphitic carbon nitride/Fe 2 O 3 composite (Fe 2 O 3 -g-C 3 N 4 ) by using Fe-melamine supramolecular framework as precursor. The chemical and optical properties of the nanocomposites are well-characterized. The Fe 2 O 3 -g-C 3 N 4 nanocomposite demonstrated excellent photocatalytic activities under visible light due to the efficient utilization of sunlight and the construction of Z-scheme electron transfer pathway. The results indicated that it could be a promising approach for the preparation of efficient g-C 3 N 4 nanocomposites photocatalysts by using metal-melamine supramolecular framework as precursors. - Graphical abstract: Nanorod-type graphitic carbon nitride/Fe 2 O 3 composite (Fe 2 O 3 -g-C 3 N 4 ) was synthesized by using Fe-melamine supramolecular framework as precursor. The Fe 2 O 3 -g-C 3 N 4 nanocomposite demonstrated excellent photocatalytic activities under visible light. Display Omitted - Highlights: • Nanorod-type graphitic carbon nitride/Fe 2 O 3 composite (Fe 2 O 3 -g-C 3 N 4 ) was synthesized. • Fe 2 O 3 -g-C 3 N 4 showed strong optical absorption in the visible-light region. • The Fe 2 O 3 -g-C 3 N 4 nanocomposite demonstrated excellent photocatalytic activities.

Development of the Holifield Radioactive Ion Beam Facility

International Nuclear Information System (INIS)

Tatum, B.A.

1997-01-01

The Holifield Radioactive Ion Beam Facility (HRIBF) construction project has been completed and the first radioactive ion beam has been successfully accelerated. The project, which began in 1992, has involved numerous facility modifications. The Oak Ridge Isochronous Cyclotron has been converted from an energy booster for heavy ion beams to a light ion accelerator with internal ion source. A target-ion source and mass analysis system have been commissioned as key components of the facility's radioactive ion beam injector to the 25MV tandem electrostatic accelerator. Beam transport lines have been completed, and new diagnostics for very low intensity beams have been developed. Work continues on a unified control system. Development of research quality radioactive beams for the nuclear structure and nuclear astrophysics communities continues. This paper details facility development to date

ACP Facility Safety Surveillance System Installation

International Nuclear Information System (INIS)

You, Gil Sung; Kook, D. H.; Choung, W. M.; Ku, J. H.; Cho, I. J.; You, G. S.; Kwon, K. C.; Lee, W. K.; Lee, E. P.

2006-10-01

The Advanced spent fuel Conditioning Process is under development for effective management of spent fuel by converting UO 2 into U-metal. For demonstration of this process, α-γ type new hotcell was built in the IMEF basement. All facilities which treat radioactive materials must manage CCTV system which is under control of Health Physics department. Three main points (including hotcell rear door area) have each camera, but operators who are in charge of facility management need to check the safety of the facility immediately through the network in his office. This needs introduce additional network cameras installation and this new surveillance system is expected to update the whole safety control ability with existing system

Decommissioning of nuclear fuel cycle facilities. Safety guide

International Nuclear Information System (INIS)

2001-01-01

The objective of this Safety Guide is to provide guidance to regulatory bodies and operating organizations on planning and provision for the safe management of the decommissioning of non-reactor nuclear fuel cycle facilities. While the basic safety considerations for the decommissioning of nuclear fuel cycle facilities are similar to those for nuclear power plants, there are important differences, notably in the design and operating parameters for the facilities, the type of radioactive material and the support systems available. It is the objective of this Safety Guide to provide guidance for the shutdown and eventual decommissioning of such facilities, their individual characteristics being taken into account

General considerations for neutron capture therapy at a reactor facility

International Nuclear Information System (INIS)

Binney, S.E.

2001-01-01

In addition to neutron beam intensity and quality, there are also a number of other significant criteria related to a nuclear reactor that contribute to a successful neutron capture therapy (NCT) facility. These criteria are classified into four main categories: Nuclear design factors, facility management and operations factors, facility resources, and non-technical factors. Important factors to consider are given for each of these categories. In addition to an adequate neutron beam intensity and quality, key requirements for a successful neutron capture therapy facility include necessary finances to construct or convert a facility for NCT, a capable medical staff to perform the NCT, and the administrative support for the facility. The absence of any one of these four factors seriously jeopardizes the overall probability of success of the facility. Thus nuclear reactor facility management considering becoming involved in neutron capture therapy, should it be proven clinically successful, should take all these factors into consideration. (author)

Spread of CTX-M-type ESßLs in isolates of E. coli from long-term care and rehabilitation facilities in Northern Italy

Directory of Open Access Journals (Sweden)

Elisabetta Nucleo

2008-09-01

Full Text Available During the period March 2003 – May 2004 at the Laboratory of Clinical Microbiology “Redaelli” LTCRF in Milan, Italy, a total of 529 E. coli, obtained from inpatients of 3 different Long Term Care Rehabilitation Facilities (LTCRFs in Northern Italy, were processed and 77 ESßLs producers (14.5% were identified by Vitek System. The results were confirmed by double-disk synergy test with tazobactam (TZP. 61/77 isolates were characterized by higher levels of resistance to cefotaxime (CTX than to ceftazidime (CAZ. (ß-lactamase production was investigated by analytical isoelectric focusing (IEF coupled with a bioassay and showed multiple (ß-lactamase bands including one enzyme with pI 8.4 that, in a bioassay, was more active on CTX,ATM than on CAZ. The presence of (ß-lactamase genes was investigated by colony blot hybridization and by PCR amplification of blaTEM, blaSHV and blaCTX-M alleles. 43/61 isolates produced both TEM-1 and CTX-M-type enzymes, 14/61 expressed only CTX-M-type while in 4 cases were found blaCTX-M, blaTEM and blaSHV genes.The remainders (16/77, characterized by high levels of resistance to both CTX and CAZ, produced TEM-1 and SHV-5 enzymes (1/16 and TEM type ESßLs (15/16. Conjugation experiments, performed in liquid medium, confermed that the ESßLs determinants were transferable. Pulsed-field gel electrophoresis profiles of genomic DNA, digested with NotI, were analysed and revealed clonal heterogeneity. Our work confirms the emergence of CTX-M-type enzymes and their spread in Northern Italy also in longterm care and rehabilitation facilities that may be an important reservoir of ES?L producing E. coli.

Scaling laws between population and facility densities.

Science.gov (United States)

Um, Jaegon; Son, Seung-Woo; Lee, Sung-Ik; Jeong, Hawoong; Kim, Beom Jun

2009-08-25

When a new facility like a grocery store, a school, or a fire station is planned, its location should ideally be determined by the necessities of people who live nearby. Empirically, it has been found that there exists a positive correlation between facility and population densities. In the present work, we investigate the ideal relation between the population and the facility densities within the framework of an economic mechanism governing microdynamics. In previous studies based on the global optimization of facility positions in minimizing the overall travel distance between people and facilities, it was shown that the density of facility D and that of population rho should follow a simple power law D approximately rho(2/3). In our empirical analysis, on the other hand, the power-law exponent alpha in D approximately rho(alpha) is not a fixed value but spreads in a broad range depending on facility types. To explain this discrepancy in alpha, we propose a model based on economic mechanisms that mimic the competitive balance between the profit of the facilities and the social opportunity cost for populations. Through our simple, microscopically driven model, we show that commercial facilities driven by the profit of the facilities have alpha = 1, whereas public facilities driven by the social opportunity cost have alpha = 2/3. We simulate this model to find the optimal positions of facilities on a real U.S. map and show that the results are consistent with the empirical data.

Understanding the relationship between access to care and facility-based delivery through analysis of the 2008 Ghana Demographic Health Survey.

Science.gov (United States)

Moyer, Cheryl A; McLaren, Zoë M; Adanu, Richard M; Lantz, Paula M

2013-09-01

To determine the types of access to care most strongly associated with facility-based delivery among women in Ghana. Data relating to the "5 As of Access" framework were extracted from the 2008 Ghana Demographic Health Survey and analyzed using multivariate logistic regression. In all, 55.5% of a weighted sample of 1102 women delivered in a healthcare facility, whereas 45.5% delivered at home. Affordability was the strongest access factor associated with delivery location, with health insurance coverage tripling the odds of facility delivery. Availability, accessibility (except urban residence), acceptability, and social access variables were not significant factors in the final models. Social access variables, including needing permission to seek healthcare and not being involved in decisions regarding healthcare, were associated with a reduced likelihood of facility-based delivery when examined individually. Multivariate analysis suggested that these variables reflected maternal literacy, health insurance coverage, and household wealth, all of which attenuated the effects of social access. Affordability was an important determinant of facility delivery in Ghana-even among women with health insurance-but social access variables had a mediating role. Copyright © 2013 International Federation of Gynecology and Obstetrics. Published by Elsevier Ireland Ltd. All rights reserved.

The present status of IAEA safeguards on nuclear fuel cycle facilities

International Nuclear Information System (INIS)

1978-11-01

The present IAEA approach to safeguarding various types of nuclear facilities is examined. The IAEA safeguards objectives, criteria and specific techniques are addressed, with reference e.g. to concepts like timely detection, quantities of safeguards significance, and conversion times. Material accountancy and containment and surveillance as basic features of IAEA safeguards verification are discussed. Safeguards measures for specific facility types are considered and corresponding levels of IAEA safeguards experience are assessed. Outlines of expected IAEA safeguard approaches to large bulk handling facilities are discussed. The evolutionary nature of safeguards based on experience and research and development is mentioned

10 CFR 140.13b - Amount of liability insurance required for uranium enrichment facilities.

Science.gov (United States)

2010-01-01

... enrichment facilities. 140.13b Section 140.13b Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) FINANCIAL... required for uranium enrichment facilities. Each holder of a license issued under Parts 40 or 70 of this chapter for a uranium enrichment facility that involves the use of source material or special nuclear...

Outbreak of OXA-48-Producing Klebsiella pneumoniae Involving a Sequence Type 101 Clone in Batna University Hospital, Algeria.

Science.gov (United States)

Loucif, Lotfi; Kassah-Laouar, Ahmed; Saidi, Mahdia; Messala, Amina; Chelaghma, Widad; Rolain, Jean-Marc

2016-12-01

Seven nonredundant ertapenem-resistant Klebsiella pneumoniae isolates were collected between May 2014 and 19 January 2015 in the nephrology and hematology units of Batna University Hospital in Algeria. All strains coproduced the bla OXA-48 , bla CTX-M-15 , bla SHV-1 , and bla TEM-1D genes. Six of these isolates belonged to the pandemic clone sequence type 101 (ST101). The bla OXA-48 gene was located on a conjugative IncL/M-type plasmid. This is the first known outbreak of OXA-48-producing K. pneumoniae isolates involving an ST101 clone in Batna University Hospital. Copyright © 2016, American Society for Microbiology. All Rights Reserved.

CERN radiation protection (RP) calibration facilities

Energy Technology Data Exchange (ETDEWEB)

Pozzi, Fabio

2016-04-14

Radiation protection calibration facilities are essential to ensure the correct operation of radiation protection instrumentation. Calibrations are performed in specific radiation fields according to the type of instrument to be calibrated: neutrons, photons, X-rays, beta and alpha particles. Some of the instruments are also tested in mixed radiation fields as often encountered close to high-energy particle accelerators. Moreover, calibration facilities are of great importance to evaluate the performance of prototype detectors; testing and measuring the response of a prototype detector to well-known and -characterized radiation fields contributes to improving and optimizing its design and capabilities. The CERN Radiation Protection group is in charge of performing the regular calibrations of all CERN radiation protection devices; these include operational and passive dosimeters, neutron and photon survey-meters, and fixed radiation detectors to monitor the ambient dose equivalent, H*(10), inside CERN accelerators and at the CERN borders. A new state-of-the-art radiation protection calibration facility was designed, constructed and commissioned following the related ISO recommendations to replace the previous ageing (more than 30 years old) laboratory. In fact, the new laboratory aims also at the official accreditation according to the ISO standards in order to be able to release certified calibrations. Four radiation fields are provided: neutrons, photons and beta sources and an X-ray generator. Its construction did not only involve a pure civil engineering work; many radiation protection studies were performed to provide a facility that could answer the CERN calibration needs and fulfill all related safety requirements. Monte Carlo simulations have been confirmed to be a valuable tool for the optimization of the building design, the radiation protection aspects, e.g. shielding, and, as consequence, the overall cost. After the source and irradiator installation

Final decommissioning report for the 183-C Filter Building/Pumproom facility

International Nuclear Information System (INIS)

Marske, S.G.

1997-04-01

This report documents the decommissioning and demolition (D ampersand D) of the 183-C Filter Building/Pumproom facility (located at the Hanford Site in Richland, Washington). The 183-C Facility D ampersand D involved the performance of characterization to support the development of a project plan and final hazard classification

Near-facility environmental monitoring

Energy Technology Data Exchange (ETDEWEB)

Schmidt, J.W.; Johnson, A.R.; Markes, B.M.; McKinney, S.M.; Perkins, C.J.

1995-06-01

This section of the 1994 Hanford Site Environmental Report summarizes the routine near-facility environmental monitoring programs which are presently being conducted at the Hanford Site. Several types of environmental media are sampled near nuclear facilities to monitor the effectiveness of waste management and restoration activities, and effluent treatment and control practices. These media include air, surface water and springs, surface contamination, soil and vegetation, investigative sampling (which can include wildlife), and external radiation. Sampling and analysis information and analytical results for 1994 for each of these media are summarized in this section. Additional data and more detailed information may be found in Westinghouse Hanford Company Operational Environmental Monitoring Annual Report, Calendar Year 1994.

Design Criteria: School Food Service Facilities.

Science.gov (United States)

Florida State Dept. of Education, Tallahassee.

This guide is intended for architects, district superintendents, and food service directors whose responsibility it is to plan food service facilities. It first discusses the factors to be considered in food service planning, presents cost studies, and lists the responsibilities of those involved in the planning. Other sections concern selection,…

Weighted inequalities for Hardy-type operators involving suprema

Czech Academy of Sciences Publication Activity Database

Gogatishvili, Amiran; Opic, Bohumír; Pick, L.

2006-01-01

Roč. 57, č. 3 (2006), s. 227-255 ISSN 0010-0757 R&D Projects: GA ČR(CZ) GA201/01/0333; GA ČR(CZ) GA201/03/0935 Institutional research plan: CEZ:AV0Z10190503; CEZ:AV0Z10100521 Keywords : Hardy operators involving suprema * weighted inequalities Subject RIV: BA - General Mathematics

NIST display colorimeter calibration facility

Science.gov (United States)

Brown, Steven W.; Ohno, Yoshihiro

2003-07-01

A facility has been developed at the National Institute of Standards and Technology (NIST) to provide calibration services for color-measuring instruments to address the need for improving and certifying the measurement uncertainties of this type of instrument. While NIST has active programs in photometry, flat panel display metrology, and color and appearance measurements, these are the first services offered by NIST tailored to color-measuring instruments for displays. An overview of the facility, the calibration approach, and associated uncertainties are presented. Details of a new tunable colorimetric source and the development of new transfer standard instruments are discussed.

Questionnaire survey and technical guideline of blood irradiation on medical facilities

International Nuclear Information System (INIS)

Matsumoto, Mitsuhiro; Hasegawa, Hironori; Okumura, Masahiko; Sonoda, Tatsuo; Osada, Koji.

1997-01-01

We know that transfusion-associated graft versus host disease (TA-GVHD) is a serious side effect associated with blood transfusion and the onset is independent on the immunological conditions of patients. We have only prophylactic treatment against TA-GVHD. The most reliable method is to irradiate the blood for transfusion. In Japanese medical facilities, however, the risk of TA-GVHD is poorly understood and actual conditions of the blood irradiation are unclear. We sent a questionnaire to randomly selected 426 medical facilities in Japan, which had the department of radiology, to investigate the actual conditions of blood irradiation for transfusion and the problems on the irradiation dose measurement of the external apparatus for blood irradiation. The questionnaire involved 19 questions about the blood irradiation for transfusion. The survey took place for one month (June 1-June 30, 1995). Replies were obtained from a total of 306 medical facilities (72%). The results showed that blood irradiation was done by several methods in the 75% of the medical facilities, and the external irradiation apparatus was used in 83%. Some problems were shown, including irradiation period, cost of the irradiation, the operating procedure of the apparatus, requested number of the irradiation, and the request after usual hours. There was no significant problem on the irradiation dose, irradiation method, etc. We also sent a questionnaire to 74 facilities of the Red Cross Blood Center, in which the frequency of blood irradiation have increased since May, 1976. The X-ray apparatus as the external irradiation apparatus has practical advantages; lower cost, compact and out of the legal control on the ionizing radiation, however, it has some problems on the uniformity of the absorption dose when a single X-ray tube-type apparatus is used. We discuss about the possible onset of TA-GVHD or other accidents by the incorrect irradiation of the blood preparations. (K.H.)

Facile synthesis of pyrite-type binary nickel iron diselenides as efficient electrocatalyst for oxygen evolution reaction

Energy Technology Data Exchange (ETDEWEB)

Chi, Jing-Qi; Shang, Xiao [State Key Laboratory of Heavy Oil Processing, China University of Petroleum (East China), Qingdao 266580 (China); Liang, Fei [State Key Laboratory of Heavy Oil Processing, China University of Petroleum (East China), Qingdao 266580 (China); College of Science, China University of Petroleum (East China), Qingdao 266580 (China); Dong, Bin, E-mail: dongbin@upc.edu.cn [State Key Laboratory of Heavy Oil Processing, China University of Petroleum (East China), Qingdao 266580 (China); College of Science, China University of Petroleum (East China), Qingdao 266580 (China); Li, Xiao; Liu, Yan-Ru; Yan, Kai-Li [State Key Laboratory of Heavy Oil Processing, China University of Petroleum (East China), Qingdao 266580 (China); Gao, Wen-Kun [State Key Laboratory of Heavy Oil Processing, China University of Petroleum (East China), Qingdao 266580 (China); College of Science, China University of Petroleum (East China), Qingdao 266580 (China); Chai, Yong-Ming [State Key Laboratory of Heavy Oil Processing, China University of Petroleum (East China), Qingdao 266580 (China); Liu, Chen-Guang, E-mail: cgliu@upc.edu.cn [State Key Laboratory of Heavy Oil Processing, China University of Petroleum (East China), Qingdao 266580 (China)

2017-04-15

Highlights: • Binary pyrite-type Ni{sub 0.5}Fe{sub 0.5}Se{sub 2}/CFC was prepared by a facile two-step process. • The effect of Ni/Fe (Ni{sub x}Fe{sub 1-x}Se{sub 2} x = 0, 0.2, 0.5, 0.8, 1) on OER was investigated. • Ni{sub 0.5}Fe{sub 0.5}Se{sub 2}/CFC (x = 0.5) possesses the better electrocatalytic activity for OER. • The enhanced activity may be attributed to binary Ni{sub 0.5}Fe{sub 0.5}Se{sub 2} and CFC support. - Abstract: Pyrite-type binary nickel iron diselenides (Ni{sub 0.5}Fe{sub 0.5}Se{sub 2}) supported on carbon fiber cloth (CFC) as electrocatalysts for oxygen evolution reaction (OER) have been prepared by a facile two-step process. Firstly, binary Ni{sub 0.5}Fe{sub 0.5} hydroxide nanosheets have been electrodeposited on CFC. Secondly, a solvothermal selenization process has been used to convert Ni{sub 0.5}Fe{sub 0.5}/CFC into Ni{sub 0.5}Fe{sub 0.5}Se{sub 2}/CFC. XRD shows that Ni{sub 0.5}Fe{sub 0.5}Se{sub 2} on CFC has the typically octahedral crystalline. XPS proves the existence and valence of Ni, Fe and Se. SEM images show that Ni{sub 0.5}Fe{sub 0.5}Se{sub 2} has novel pyrite-type octahedral morphology with uniform size and good dispersion on the surface of CFC. SEM elemental mapping images confirm the good distribution of Ni, Fe, Se element on CFC. TEM and SAED provide the clear diffraction rings of octahedral Ni{sub 0.5}Fe{sub 0.5}Se{sub 2}, which is consistent with the results of XRD. Furtherly, the effect of different ratio of Ni/Fe (Ni{sub x}Fe{sub 1-x}Se{sub 2} x = 0, 0.2, 0.5, 0.8, 1) on OER performances has been systematically investigated. The electrochemical measurements results show that Ni{sub 0.5}Fe{sub 0.5}Se{sub 2}/CFC (x = 0.5) possesses the better electrocatalytic activity with the lower overpotential, Tafel slope and long-term stability than other samples. The enhanced activity of Ni{sub 0.5}Fe{sub 0.5}Se{sub 2}/CFC may be attributed to the intrinsic activity of binary Ni{sub 0.5}Fe{sub 0.5}Se{sub 2} and faster electron

National Ignition Facility (NIF) Control Network Design and Analysis

International Nuclear Information System (INIS)

Bryant, R M; Carey, R W; Claybourn, R V; Pavel, G; Schaefer, W J

2001-01-01

The control network for the National Ignition Facility (NIF) is designed to meet the needs for common object request broker architecture (CORBA) inter-process communication, multicast video transport, device triggering, and general TCP/IP communication within the NIF facility. The network will interconnect approximately 650 systems, including the embedded controllers, front-end processors (FEPs), supervisory systems, and centralized servers involved in operation of the NIF. All systems are networked with Ethernet to serve the majority of communication needs, and asynchronous transfer mode (ATM) is used to transport multicast video and synchronization triggers. CORBA software infra-structure provides location-independent communication services over TCP/IP between the application processes in the 15 supervisory and 300 FEP systems. Video images sampled from 500 video cameras at a 10-Hz frame rate will be multicast using direct ATM Application Programming Interface (API) communication from video FEPs to any selected operator console. The Ethernet and ATM control networks are used to broadcast two types of device triggers for last-second functions in a large number of FEPs, thus eliminating the need for a separate infrastructure for these functions. Analysis, design, modeling, and testing of the NIF network has been performed to provide confidence that the network design will meet NIF control requirements

Innovative Procurement and Partnerships in Facilities Management

DEFF Research Database (Denmark)

Jensen, Per Anker

2011-01-01

A major study of facilities management best practice covering 36 cases from the Nordic countries in Europe shows, that the most outstanding examples of innovation in FM are initiated from the demand side and involves new forms of procurement with long term contracts. This paper considers in depth......-called operational partnerships with private providers concerning all municipal buildings and sports facilities in parts of a city. Each of the case studies has involved both the client and the provider side of the collaboration. The cases show that an essential element in a successful procurement and partnership...... is that the client allows the providers freedom to plan their activities. Thereby the providers can optimize the use of their productive capacity and utilize their competences with incentives to profit from such improvements. A major challenge is to balance the risks between the client and provider and to create...

Usability Briefing - a process model for healthcare facilities

DEFF Research Database (Denmark)

Fronczek-Munter, Aneta

2014-01-01

Background: In complex buildings with many types of users it can be difficult to satisfy the numerous, often contradictory requirements. Research in usability mostly focuses on evaluating products or facilities with users, after they were built. This paper is part of a PhD project “Usability...... with various users/stakeholders, using creative boundary objects at workshops.  Practical Implications: The research results have relevance to researchers, client organisations, facility managers and architects planning new complex facilities.  Research limitations: The proposed model is theoretical and needs...... briefing for hospitals”, where methods for capturing user needs and experiences at hospital facilities are investigated in order to feed into design processes and satisfy the users’ needs and maximise the effectiveness of facilities. Purpose: This paper introduces the concept of usability briefing...

Adaptive management: a paradigm for remediation of public facilities

Energy Technology Data Exchange (ETDEWEB)

Janecky, David R [Los Alamos National Laboratory; Whicker, Jeffrey J [Los Alamos National Laboratory; Doerr, Ted B [NON LANL

2009-01-01

Public facility restoration planning traditionally focused on response to natural disasters and hazardous materials accidental releases. These plans now need to integrate response to terrorist actions. Therefore, plans must address a wide range of potential vulnerabilities. Similar types of broad remediation planning are needed for restoration of waste and hazardous material handling areas and facilities. There are strong similarities in damage results and remediation activities between unintentional and terrorist actions; however, the uncertainties associated with terrorist actions result in a re-evaluation of approaches to planning. Restoration of public facilities following a release of a hazardous material is inherently far more complex than in confined industrial settings and has many unique technical, economic, social, and political challenges. Therefore, they arguably involve a superset of drivers, concerns and public agencies compared to other restoration efforts. This superset of conditions increases complexity of interactions, reduces our knowledge of the initial conditions, and even condenses the timeline for restoration response. Therefore, evaluations of alternative restoration management approaches developed for responding to terrorist actions provide useful knowledge for large, complex waste management projects. Whereas present planning documents have substantial linearity in their organization, the 'adaptive management' paradigm provides a constructive parallel operations paradigm for restoration of facilities that anticipates and plans for uncertainty, multiple/simUltaneous public agency actions, and stakeholder participation. Adaptive management grew out of the need to manage and restore natural resources in highly complex and changing environments with limited knowledge about causal relationships and responses to restoration actions. Similarities between natural resource management and restoration of a facility and surrounding area

Adaptive Management: A Paradigm for Remediation of Public Facilities

International Nuclear Information System (INIS)

Janecky, D.R.; Whicker, J.J.; Doerr, T.B.

2009-01-01

Public facility restoration planning traditionally focused on response to natural disasters and hazardous materials accidental releases. These plans now need to integrate response to terrorist actions. Therefore, plans must address a wide range of potential vulnerabilities. Similar types of broad remediation planning are needed for restoration of waste and hazardous material handling areas and facilities. There are strong similarities in damage results and remediation activities between unintentional and terrorist actions; however, the uncertainties associated with terrorist actions result in a re-evaluation of approaches to planning. Restoration of public facilities following a release of a hazardous material is inherently far more complex than in confined industrial settings and has many unique technical, economic, social, and political challenges. Therefore, they arguably involve a superset of drivers, concerns and public agencies compared to other restoration efforts. This superset of conditions increases complexity of interactions, reduces our knowledge of the initial conditions, and even condenses the timeline for restoration response. Therefore, evaluations of alternative restoration management approaches developed for responding to terrorist actions provide useful knowledge for large, complex waste management projects. Whereas present planning documents have substantial linearity in their organization, the 'adaptive management' paradigm provides a constructive parallel operations paradigm for restoration of facilities that anticipates and plans for uncertainty, multiple/simultaneous public agency actions, and stakeholder participation. Adaptive management grew out of the need to manage and restore natural resources in highly complex and changing environments with limited knowledge about causal relationships and responses to restoration actions. Similarities between natural resource management and restoration of a facility and surrounding area(s) after a

Tumulus Disposal Demonstration Facility for the Oak Ridge Reservation

International Nuclear Information System (INIS)

Clapp, R.B.; van Hoesen, S.D.

1987-01-01

This disposal concept is based on the Tumulus design developed by the French at the La Manche facility. Waste units are stacked above-grade on a concrete pad. The facility currently under development at the Oak Ridge National Laboratory (ORNL) involves sealing waste in concrete vaults, placing the vaults on a grade level concrete pad, and covering the pad and vaults with a soil cover after vault emplacement is complete. Emplacement is expected to continue until the facility exhausts its approximate 800 m 3 (28,000 ft 3 ) capacity. The facility incorporates engineered barriers to radionuclide migration; a monitoring system to ensure barrier performance; and a newly developed set of Demonstration Waste Acceptance Criteria to reduce the likelihood of groundwater contamination

PACCOM: A nuclear waste packaging facility cost model: Draft technical report

International Nuclear Information System (INIS)

Dippold, D.G.; Tzemos, S.; Smith, D.J.

1985-05-01

PACCOM is a computerized, parametric model used to estimate the capital, operating, and decommissioning costs of a variety of nuclear waste packaging facility configurations. The model is based upon a modular waste packaging facility concept from which functional components of the overall facility have been identified and their design and costs related to various parameters such as waste type, waste throughput, and the number of operational shifts employed. The model may be used to either estimate the cost of a particular waste packaging facility configuration or to explore the cost tradeoff between plant capital and labor. That is, one may use the model to search for the particular facility sizes and associated cost which when coupled with a particular number of shifts, and thus staffing level, leads to the lowest overall total cost. The functional components which the model considers include hot cells and their supporting facilities, transportation, cask handling facilities, transuranic waste handling facilities, and administrative facilities such as warehouses, security buildings, maintenance buildings, etc. The cost of each of these functional components is related either directly or indirectly to the various independent design parameters. Staffing by shift is reported into direct and indirect support labor. These staffing levels are in turn related to the waste type, waste throughput, etc. 2 refs., 11 figs., 3 tabs

Storm water permitting for oil and gas facilities

International Nuclear Information System (INIS)

de Blanc, P.C.

1991-01-01

After several false starts, the US Environmental Protection Agency (EPA) published new federal storm water regulations in the November 16, 1990 Federal Register. These regulations identify facilities which must apply for a storm water permit and detail permit application requirements. The regulations appear at 40 CFR 122 Subpart B and became effective December 17, 1990. An outline of these regulations and their applicability to oil and gas facilities is presented. They are: facilities which require a storm water permit; types of storm water permits; permit application deadlines; permit application forms; facilities with existing storm water permits; storm water permit application data requirements; storm water sampling and analysis requirements; and EPA contacts for additional information

Hanford facility dangerous waste permit application

International Nuclear Information System (INIS)

1991-01-01

This document, Set 2, the Hanford Facility Dangerous Waste Part B Permit Application, consists of 15 chapters that address the content of the Part B checklists prepared by the Washington State Department of Ecology (Ecology 1987) and the US Environmental Protection Agency (40 CFR 270), with additional information requirements mandated by the Hazardous and Solid Waste Amendments of 1984 and revisions of WAC 173-303. For ease of reference, the Washington State Department of Ecology checklist section numbers, in brackets, follow the chapter headings and subheadings. This permit application contains ''umbrella- type'' documentation with overall application to the Hanford Facility. This documentation is broad in nature and applies to all TSD units that have final status under the Hanford Facility Permit

Waste Management Facilities Cost Information Report

Energy Technology Data Exchange (ETDEWEB)

Feizollahi, F.; Shropshire, D.

1992-10-01

The Waste Management Facility Cost Information (WMFCI) Report, commissioned by the US Department of Energy (DOE), develops planning life-cycle cost (PLCC) estimates for treatment, storage, and disposal facilities. This report contains PLCC estimates versus capacity for 26 different facility cost modules. A procedure to guide DOE and its contractor personnel in the use of estimating data is also provided. Estimates in the report apply to five distinctive waste streams: low-level waste, low-level mixed waste, alpha contaminated low-level waste, alpha contaminated low-level mixed waste, and transuranic waste. The report addresses five different treatment types: incineration, metal/melting and recovery, shredder/compaction, solidification, and vitrification. Data in this report allows the user to develop PLCC estimates for various waste management options.

Waste Management Facilities Cost Information Report

International Nuclear Information System (INIS)

Feizollahi, F.; Shropshire, D.

1992-10-01

The Waste Management Facility Cost Information (WMFCI) Report, commissioned by the US Department of Energy (DOE), develops planning life-cycle cost (PLCC) estimates for treatment, storage, and disposal facilities. This report contains PLCC estimates versus capacity for 26 different facility cost modules. A procedure to guide DOE and its contractor personnel in the use of estimating data is also provided. Estimates in the report apply to five distinctive waste streams: low-level waste, low-level mixed waste, alpha contaminated low-level waste, alpha contaminated low-level mixed waste, and transuranic waste. The report addresses five different treatment types: incineration, metal/melting and recovery, shredder/compaction, solidification, and vitrification. Data in this report allows the user to develop PLCC estimates for various waste management options

Emergency reactor core cooling facility

International Nuclear Information System (INIS)

Yoshikawa, Kazuhiro; Kinoshita, Shoichiro; Iwata, Yasutaka.

1996-01-01

The present invention provides an emergency reactor core cooling device for a BWR type nuclear power plant. Namely, D/S pit (gas/water separator storage pool) water is used as a water source for the emergency reactor core cooling facility upon occurrence of loss of coolant accidents (LOCA) by introducing the D/S pit water to the emergency reactor core cooling (ECCS) pump. As a result, the function as the ECCS facility can be eliminated from the function of the condensate storage tank which has been used as the ECCS facility. If the function is unnecessary, the level of quality control and that of earthquake resistance of the condensate storage tank can be lowered to a level of ordinary facilities to provide an effect of reducing the cost. On the other hand, since the D/S pit as the alternative water source is usually a facility at high quality control level and earthquake resistant level, there is no problem. The quality of the water in the D/S pit can be maintained constant by elevating pressure of the D/S pit water by a suppression pool cleanup (SPCU) pump to pass it through a filtration desalter thereby purifying the D/S pit water during the plant operation. (I.S.)

Emergency reactor core cooling facility

Energy Technology Data Exchange (ETDEWEB)

Yoshikawa, Kazuhiro; Kinoshita, Shoichiro; Iwata, Yasutaka

1996-11-01

The present invention provides an emergency reactor core cooling device for a BWR type nuclear power plant. Namely, D/S pit (gas/water separator storage pool) water is used as a water source for the emergency reactor core cooling facility upon occurrence of loss of coolant accidents (LOCA) by introducing the D/S pit water to the emergency reactor core cooling (ECCS) pump. As a result, the function as the ECCS facility can be eliminated from the function of the condensate storage tank which has been used as the ECCS facility. If the function is unnecessary, the level of quality control and that of earthquake resistance of the condensate storage tank can be lowered to a level of ordinary facilities to provide an effect of reducing the cost. On the other hand, since the D/S pit as the alternative water source is usually a facility at high quality control level and earthquake resistant level, there is no problem. The quality of the water in the D/S pit can be maintained constant by elevating pressure of the D/S pit water by a suppression pool cleanup (SPCU) pump to pass it through a filtration desalter thereby purifying the D/S pit water during the plant operation. (I.S.)

Conflict resolution styles: a comparison of assisted living and nursing home facilities.

Science.gov (United States)

Small, Jeff A; Montoro-Rodriguez, Julian

2006-01-01

In this exploratory study, the authors investigated how interpersonal conflict is resolved in assisted living and nursing home facilities. In particular, the authors examined whether conflict resolution styles differed between type of facility and between residents and staff in each type of facility. Four focus groups were conducted--two with residents and two with staff from each type of facility. The focus groups centered on discussing the occurrence of conflict and how each participant handled it. Discourse analysis was employed to identify participants' use of three styles of conflict resolution: controlling, solution-oriented, and non-confrontational. The results indicate that staff in each care context showed a preference for the solution-oriented approach. Residents in each setting reported equal use of the non-confrontational and solution-oriented styles. The findings suggest that preferred conflict resolution styles may vary more as a function of the role of each communicator than the context of the care setting.

Patient involvement in Danish health care

DEFF Research Database (Denmark)

Vrangbaek, Karsten

2015-01-01

PURPOSE: The purpose of this paper is to investigate different types of patient involvement in Denmark, and to discuss the potential implications of pursuing several strategies for patient involvement simultaneously. DESIGN/METHODOLOGY/APPROACH: The paper presents a preliminary framework for anal......PURPOSE: The purpose of this paper is to investigate different types of patient involvement in Denmark, and to discuss the potential implications of pursuing several strategies for patient involvement simultaneously. DESIGN/METHODOLOGY/APPROACH: The paper presents a preliminary framework...... for analysis of patient involvement in health care. This framework is used to analyze key governance features of patient involvement in Denmark based on previous research papers and reports describing patient involvement in Danish health care. FINDINGS: Patient involvement is important in Denmark...... be identified when pursuing the strategies at the same time. RESEARCH LIMITATIONS/IMPLICATIONS: Because of the chosen research approach, the research results may lack generalizability. Therefore, researchers are encouraged to test the proposed framework further. PRACTICAL IMPLICATIONS: The paper includes...

Nonreactor nuclear facilities: Standards and criteria guide

International Nuclear Information System (INIS)

Brynda, W.J.; Scarlett, C.H.; Tanguay, G.E.; Lobner, P.R.

1986-09-01

This guide is a source document that identifies standards, codes, and guides that address the nuclear safety considerations pertinent to nuclear facilities as defined in DOE 5480.1A, Chapter V, ''Safety of Nuclear Facilities.'' The guidance and criteria provided is directed toward areas of safety usually addressed in a Safety Analysis Report. The areas of safety include, but are not limited to, siting, principal design criteria and safety system design guidelines, radiation protection, accident analysis, conduct of operations, and quality assurance. The guide is divided into two sections: general guidelines and appendices. Those guidelines that are broadly applicable to most nuclear facilities are presented in the general guidelines. Guidelines specific to the various types or categories of nuclear facilities are presented in the appendices. These facility-specific appendices provide guidelines and identify standards and criteria that should be considered in addition to, or in lieu of, the general guidelines. 25 figs., 62 tabs

Development of cables for nuclear fuel processing facilities

International Nuclear Information System (INIS)

Kamimura, Seiji; Seki, Ikuo; Yamamoto, Yasuaki; Matsuyama, Shigeki; Endo, Shigeru; Yagi, Toshiaki; Kawakami, Waichiro.

1988-01-01

Accompanying the development of nuclear power stations, the expansion and repletion of the facilities for nuclear fuel cycle such as fuel reprocessing facilities and waste treatment facilities are requested. In these facilities, there is the environment which is exposed to very high level radiation, and in this case, the cables withstanding 10 MGy radiation dose are required. As the cables meeting such requirement, the new cables having excellent flexibility and radiation resistance were developed. In this paper, the points of material development and the characteristics of cables are reported. Considering the radiation resistance and others, ethylene propylene rubber was selected as the base polymer of the insulator, and polyethylene chlorosulfonate was selected as the sheath material. In order to give excellent radiation resistance, as the anti-rad, energy transfer type aromatic oil that absorbs and dissipates radiation energy and radical trap type anti-oxidant of amine group that catches and stabilizes the radicals generated in the polymer were added. The bromine group burning retarding agent having excellent radiation resistance was applied. In this way, the cables withstanding high radiation dose up to 10 MGy were able to be developed. (K.I.)

The present status of IAEA safeguards on nuclear fuel cycle facilities

International Nuclear Information System (INIS)

1979-02-01

This paper examines the present approach of the International Atomic Energy Agency (IAEA) to safeguarding various types of facilities in the nuclear fuel cycle, in the hope that it will serve as useful background material for several of the various working groups of the International Nuclear Fuel Cycle Evaluation (INFCE). The objectives and criteria of safeguards as well as the specific safeguards techniques which are utilized by the Agency, are addressed. In Part I, a general overview of safeguards as well as a discussion of procedures applicable to most if not all IAEA safeguarded facilities are included. Part II is broken down into specific facility types and focusses on the particular safeguards measures applied to them. Safeguards have reached different degrees of development for different types of facilities, in part because the Agency's experience in safeguarding certain types is considerably greater than for other types. Thus the Agency safeguards described herein are not static, but are continuously evolving. This evolution results not only from the fact that larger and more complex facilities have been coming under safeguards. Changes are also continually being introduced based on practical experience and research and development aimed at improving safeguards efficiency, reducing intrusiveness into plant operations, minimizing operator and inspector radiation exposure, and reducing subjective evaluations in determining the effectiveness of safeguards. To these ends, the technical support programmes of various countries are playing an important role. It is emphasized that this paper is not intended to evaluate the effectiveness of Agency safeguards or to highlight problem areas. It is simply aimed at providing a picture of what safeguards are or are planned to be at various stages of the fuel cycle

Image quality of mammography in Croatian nationwide screening program: Comparison between various types of facilities

International Nuclear Information System (INIS)

Brnić, Zoran; Blašković, Darko; Klasić, Branimir; Ramač, Jelena Popić; Flegarić-Bradić, Mirjana; Štimac, Damir; Lubina, Ivan Zvonimir; Brnić, Vedran; Faj, Dario

2012-01-01

Purpose: The study was aimed to provide objective evidence about the mammographic image quality in Croatia, to compare it between different types of MG facilities and to identify the most common deficiencies and possible reasons as well as the steps needed to improve image quality. Materials and methods: A total of 420 mammographic examinations collected from 84 mammographic units participating in the Croatian nationwide breast cancer screening program were reviewed in terms of four image quality categories: identification of patient and examination, breast positioning and compression, exposure and contrast, and artifacts. Those were rated using image evaluating system based on American College of Radiology and European Commission proposals. The results were compared among different types of mammographic units, and common image quality deficiencies were identified. Results: Total image quality scores of 12.8, 16.1, 13.0 and 13.7 were found for general hospitals, university hospitals, private clinics and public healthcare centres, respectively. Average score for all mammographic units was 13.5 (out of 25 points). University hospitals were significantly better than all other mammography units in overall image quality, which was mostly contributed by better breast positioning practices. Private clinics showed the worst results in identification, exposure, contrast and artifacts. Conclusions: Serious deficiencies in identification and breast positioning, which might compromise breast cancer screening outcome, were detected in our material. They occur mainly due to subjective reasons and could be corrected through additional staff training and improvement of working discipline.

Radiation activities and application of ionizing radiation on cultural heritage at ENEA Calliope gamma facility (Casaccia R.C., Rome, Italy

Directory of Open Access Journals (Sweden)

Baccaro Stefania

2017-12-01

Full Text Available Since the 1980s, research and qualification activities are being carried out at the 60Co gamma Calliope plant, a pool-type irradiation facility located at the Research Centre ENEA-Casaccia (Rome, Italy. The Calliope facility is deeply involved in radiation processing research and on the evaluation and characterization of the effects induced by gamma radiation on materials for different applications (crystals, glasses, optical fibres, polymers and biological systems and on devices to be used in hostile radiation environment such as nuclear plants, aerospace and high energy physics experiments. All the activities are carried out in the framework of international projects and collaboration with industries and research institutions. In the present work, particular attention will be paid to the cultural heritage activities performed at the Calliope facility, focused on two different aspects: (a conservation and preservation by bio-deteriogen eradication in archived materials, and (b consolidation and protection by degraded wooden and stone porous artefacts consolidation.

Security culture for nuclear facilities

Science.gov (United States)

Gupta, Deeksha; Bajramovic, Edita

2017-01-01

Natural radioactive elements are part of our environment and radioactivity is a natural phenomenon. There are numerous beneficial applications of radioactive elements (radioisotopes) and radiation, starting from power generation to usages in medical, industrial and agriculture applications. But the risk of radiation exposure is always attached to operational workers, the public and the environment. Hence, this risk has to be assessed and controlled. The main goal of safety and security measures is to protect human life, health, and the environment. Currently, nuclear security considerations became essential along with nuclear safety as nuclear facilities are facing rapidly increase in cybersecurity risks. Therefore, prevention and adequate protection of nuclear facilities from cyberattacks is the major task. Historically, nuclear safety is well defined by IAEA guidelines while nuclear security is just gradually being addressed by some new guidance, especially the IAEA Nuclear Security Series (NSS), IEC 62645 and some national regulations. At the overall level, IAEA NSS 7 describes nuclear security as deterrence and detection of, and response to, theft, sabotage, unauthorized access, illegal transfer or other malicious acts involving nuclear, other radioactive substances and their associated facilities. Nuclear security should be included throughout nuclear facilities. Proper implementation of a nuclear security culture leads to staff vigilance and a high level of security posture. Nuclear security also depends on policy makers, regulators, managers, individual employees and members of public. Therefore, proper education and security awareness are essential in keeping nuclear facilities safe and secure.

The public’s preferences for establishing nephrology facilities in Greenland

DEFF Research Database (Denmark)

Kjaer, T.; Bech, M.; Kronborg, C.

2013-01-01

in which they were asked to consider the trade-offs of establishing nephrology facilities in Greenland as opposed to the current situation. This involved trading off the benefits of having such facilities in their home country against the costs of the intervention. Besides including a payment attribute...... robust. Establishing facilities in Greenland therefore would appear to be welfare-improving, deriving positive net benefits. Despite the relatively narrow policy focus, we believe that our findings provide some insight into individuals' preferences for decentralization of public services and on citizens...... facilities in Greenland were preferred to the current treatment in Denmark. The welfare estimate from the DCE, at DKK 18.74 million, exceeds the estimated annual costs of establishing treatment facilities for patients with chronic renal failure. Given the estimated confidence interval this result seems...

Licensing procedures for Low-Level Waste disposal facilities

International Nuclear Information System (INIS)

Roop, R.D.; Van Dyke, J.W.

1985-09-01

This report describes the procedures applicable to siting and licensing of disposal facilities for low-level radioactive wastes. Primary emphasis is placed on those procedures which are required by regulations, but to the extent possible, non-mandatory activities which will facilitate siting and licensing are also considered. The report provides an overview of how the procedural and technical requirements for a low-level waste (LLW) disposal facility (as defined by the Nuclear Regulatory Commission's Rules 10 CFR Parts 2, 51, and 61) may be integrated with activities to reduce and resolve conflict generated by the proposed siting of a facility. General procedures are described for site screening and selection, site characterization, site evaluation, and preparation of the license application; specific procedures for several individual states are discussed. The report also examines the steps involved in the formal licensing process, including docketing and initial processing, preparation of an environmental impact statement, technical review, hearings, and decisions. It is concluded that development of effective communication between parties in conflict and the utilization of techniques to manage and resolve conflicts represent perhaps the most significant challenge for the people involved in LLW disposal in the next decade. 18 refs., 6 figs

Instrumentation and measurement method for the ATLAS test facility

Energy Technology Data Exchange (ETDEWEB)

Yun, Byong Jo; Chu, In Chul; Eu, Dong Jin; Kang, Kyong Ho; Kim, Yeon Sik; Song, Chul Hwa; Baek, Won Pil

2007-03-15

An integral effect test loop for pressurized water reactors (PWRs), the ATLAS is constructed by thermal-hydraulic safety research division in KAERI. The ATLAS facility has been designed to have the length scale of 1/2 and area scale of 1/144 compared with the reference plant, APR1400 which is a Korean evolution type nuclear reactors. A total 1300 instrumentations is equipped in the ATLAS test facility. In this report, the instrumentation of ATLAS test facility and related measurement methods were introduced.

Radiological performance assessment for the E-Area Vaults Disposal Facility

Energy Technology Data Exchange (ETDEWEB)

Cook, J.R.; Hunt, P.D. [Westinghouse Savannah River Co., Aiken, SC (United States)

1994-04-15

The E-Area Vaults (EAVs) located on a 200 acre site immediately north of the current LLW burial site at Savannah River Site will provide a new disposal and storage site for solid, low-level, non-hazardous radioactive waste. The EAV Disposal Facility will contain several large concrete vaults divided into cells. Three types of structures will house four designated waste types. The Intermediate Level Non-Tritium Vaults will receive waste radiating greater than 200 mR/h at 5 cm from the outer disposal container. The Intermediate Level Tritium Vaults will receive waste with at least 10 Ci of tritium per package. These two vaults share a similar design, are adjacent, share waste handling equipment, and will be closed as one facility. The second type of structure is the Low Activity Waste Vaults which will receive waste radiating less than 200 mR/h at 5 cm from the outer disposal container and containing less than 10 Ci of tritium per package. The third facility, the Long Lived Waste Storage Building, provides covered, long term storage for waste containing long lived isotopes. Two additional types of disposal are proposed: (1) trench disposal of suspect soil, (2) naval reactor component disposal. To evaluate the long-term performance of the EAVs, site-specific conceptual models were developed to consider: (1) exposure pathways and scenarios of potential importance; (2) potential releases from the facility to the environment; (3) effects of degradation of engineered features; (4) transport in the environment; (5) potential doses received from radionuclides of interest in each vault type.

Radiological performance assessment for the E-Area Vaults Disposal Facility

International Nuclear Information System (INIS)

Cook, J.R.; Hunt, P.D.

1994-01-01

The E-Area Vaults (EAVs) located on a 200 acre site immediately north of the current LLW burial site at Savannah River Site will provide a new disposal and storage site for solid, low-level, non-hazardous radioactive waste. The EAV Disposal Facility will contain several large concrete vaults divided into cells. Three types of structures will house four designated waste types. The Intermediate Level Non-Tritium Vaults will receive waste radiating greater than 200 mR/h at 5 cm from the outer disposal container. The Intermediate Level Tritium Vaults will receive waste with at least 10 Ci of tritium per package. These two vaults share a similar design, are adjacent, share waste handling equipment, and will be closed as one facility. The second type of structure is the Low Activity Waste Vaults which will receive waste radiating less than 200 mR/h at 5 cm from the outer disposal container and containing less than 10 Ci of tritium per package. The third facility, the Long Lived Waste Storage Building, provides covered, long term storage for waste containing long lived isotopes. Two additional types of disposal are proposed: (1) trench disposal of suspect soil, (2) naval reactor component disposal. To evaluate the long-term performance of the EAVs, site-specific conceptual models were developed to consider: (1) exposure pathways and scenarios of potential importance; (2) potential releases from the facility to the environment; (3) effects of degradation of engineered features; (4) transport in the environment; (5) potential doses received from radionuclides of interest in each vault type

Adverse event reporting in Czech long-term care facilities.

Science.gov (United States)

Hěib, Zdenřk; Vychytil, Pavel; Marx, David

2013-04-01

To describe adverse event reporting processes in long-term care facilities in the Czech Republic. Prospective cohort study involving a written questionnaire followed by in-person structured interviews with selected respondents. Long-term care facilities located in the Czech Republic. Staff of 111 long-term care facilities (87% of long-term care facilities in the Czech Republic). None. Sixty-three percent of long-term health-care facilities in the Czech Republic have adverse event-reporting processes already established, but these were frequently very immature programs sometimes consisting only of paper recording of incidents. Compared to questionnaire responses, in-person interview responses only partially tended to confirm the results of the written survey. Twenty-one facilities (33%) had at most 1 unconfirmed response, 31 facilities (49%) had 2 or 3 unconfirmed responses and the remaining 11 facilities (17%) had 4 or more unconfirmed responses. In-person interviews suggest that use of a written questionnaire to assess the adverse event-reporting process may have limited validity. Staff of the facilities we studied expressed an understanding of the importance of adverse event reporting and prevention, but interviews also suggested a lack of knowledge necessary for establishing a good institutional reporting system in long-term care.

Decommissioning the UHTREX Reactor Facility at Los Alamos, New Mexico

International Nuclear Information System (INIS)

Salazar, M.; Elder, J.

1992-08-01

The Ultra-High Temperature Reactor Experiment (UHTREX) facility was constructed in the late 1960s to advance high-temperature and gas-cooled reactor technology. The 3-MW reactor was graphite moderated and helium cooled and used 93% enriched uranium as its fuel. The reactor was run for approximately one year and was shut down in February 1970. The decommissioning of the facility involved removing the reactor and its associated components. This document details planning for the decommissioning operations which included characterizing the facility, estimating the costs of decommissioning, preparing environmental documentation, establishing a system to track costs and work progress, and preplanning to correct health and safety concerns in the facility. Work to decommission the facility began in 1988 and was completed in September 1990 at a cost of $2.9 million. The facility was released to Department of Energy for other uses in its Los Alamos program

Computed tomography of iliopsoas involvement in uterine cervix cancer

International Nuclear Information System (INIS)

Chung, Jin Uk; Choi, Byung Ihn; Kim, Seung Hyup; Han, Man Chung; Kim, Chu Wan

1987-01-01

Uterine cervix carcinomas spread by direct local extension, lymphatic permeation and hematogenous dissemination. Their metastatic foci are closely related to iliopsoas compartment anatomically no matter what the pattern of spread is. Therefore, iliopsoas involvement in uterine cervix cancer may occur frequently. The authors reviewed pelvis CT of 218 cervix cancer patients for recent one year from March 1986 to February 1987 at Seoul National University Hospital. Among them, 10 cases showed iliopsoas involvement. Pattern of iliopsoas involvement was classified into four types: infiltrative type (three cases), localized mass type (three cases), mass with bone destruction type (two cases), paraaortic lymphadenopathy type (two cases). In all cases except 3 cases of infiltrative type, lymphadenopathy or bone metastasis adjacent to iliopsoas lesion was identified. And this finding suggested that the route of iliopsoas involvement in cervix cancer would be secondary infiltration from metastatic focus of adjacent lymph node or bone. Recognition of iliopsoas involvement of cervix caner may prevent misdiagnosis and predict the degree of disease dissemination

Intelligence and Security Standards on Industrial Facilities Protection in Case of Terrorism and Military Attack

International Nuclear Information System (INIS)

Stipetic, D.

2007-01-01

Industrial facilities, which use toxic chemicals in their production processes, are tempting targets for military and terrorist strategists. They know that these facilities when attacked could produce effects not realizable with conventional weapons. The resulting legal, policy and political consequences would be minimal as compared to that of disseminating toxic chemicals or chemical agents as weapons on enemy territory. At this time there is no clear definition of the legality or illegality of these types of actions used against specific industrial targets for the purpose of mass destruction or disruption. Without clearly defined international regulations covering these actions, we must depend solely on national defense systems. Not only are these regulation not defined, there are no implementation tools, which would be available if the various treaties (CWC/BWC) etc., were able to incorporate needed legislative action. Consequently we must depend on and put into practice defense security standards for industrial facilities for protection against both possible terrorist and military attacks. Emergency responses to incidents involving violent criminals and terrorists are extremely dangerous. Incidents involving weapons of mass destruction, firearms, and hazardous materials have resulted in the injury and death of many firefighters, police officers and medical personnel. We wish to intend display place and role of intelligence and counter intelligence system to prevention potential target and military attack. Security needs to be incorporated into the public safety culture and it must become the routine for how we operate. The recognition and identification process is an important skill that needs continual refinement. The use of transportation or facility paperwork assists in recognizing what potential hazards. A key factor in the successful command and management of a hazmat incident or terrorism event is the ability of public safety agencies to function as a

Separations canyon decontamination facilities

International Nuclear Information System (INIS)

Hershey, J.H.

1975-01-01

Highly radioactive process equipment is decontaminated at the Savannah River Plant in specially equipped areas of the separations canyon building so that direct mechanical repairs or alterations can be made. Using these facilities it is possible to decontaminate and repair equipment such as 10- x 11-ft storage tanks, 8- x 8-ft batch evaporator pots and columns, 40-in. Bird centrifuges, canyon pumps and agitators, and various canyon piping systems or ''jumpers.'' For example, centrifuge or evaporator pots can be decontaminated and rebuilt for about 60 percent of the 1974 replacement cost. The combined facilities can decontaminate and repair 6 to 10 pieces of major equipment per year. Decontamination time varies with type of equipment and radioactivity levels encountered

Separations canyon decontamination facilities

International Nuclear Information System (INIS)

Hershey, J.H.

1975-05-01

Highly radioactive process equipment is decontaminated at the Savannah River Plant in specially equipped areas of the separations canyon buildings so that direct mechanical repairs or alterations can be made. Using these facilities it is possible to decontaminate and repair equipment such as 10- x 11-ft storage tanks, 8- x 8-ft batch evaporator pots and columns, 40-in. Bird centrifuges, canyon pumps and agitators, and various canyon piping systems or ''jumpers.'' For example, centrifuge or evaporator pots can be decontaminated and rebuilt for about 60 percent of the 1974 replacement cost. The combined facilities can decontaminate and repair 6 to 10 pieces of major equipment per year. Decontamination time varies with type of equipment and radioactivity levels encountered. (U.S.)

Comparative study on various attenuation theories usually used for aseismatic design of reactor facilities

International Nuclear Information System (INIS)

Muto, Kiyoshi; Kobayashi, Toshio.

1977-01-01

In the vibration analysis for the aseismatic design of reactor facilities, various attenuation theories have been used case by case. In this study, three attenuation theories of internal viscosity type, strain energy type and kinetic energy type were applied to the vibration analysis for a BWR type reactor building, and the respective results were compared. The three theories are explained briefly. Different damping factors were taken for the RC building, steel internal equipments and ground. The reactor building for a BWR of Mark 1 type was studied, and the mathematic vibration model involving those for the building, shield wall, primary containment vessel, gamma shield wall, reactor pressure vessel and foundation is shown. Natural frequency analysis, frequency response analysis and earthquake response analysis were carried out. Regarding the response of the building, the internal viscosity type and the strain energy type gave almost same values, but the kinetic energy type gave the value 1.2 times as large as the former values. In the response of the building, the first mode element is predominant, and the damping factors to the first mode caused these results. Regarding the maximum response acceleration and floor response spectra of internal equipments, the strain energy type and the kinetic energy type gave similar results, and the internal viscosity type gave smaller values. (Kako, I.)

Construction of new critical experiment facilities in JAERI

International Nuclear Information System (INIS)

Takeshita, Isao; Itahashi, Takayuki; Ogawa, Kazuhiko; Tonoike, Kotaro; Matsumura, Tatsuro; Miyoshi, Yoshinori; Nakajima, Ken; Izawa, Naoki

1995-01-01

Japan Atomic Energy Research Institute (JAERI) has promoted the experiment research program on criticality safety since early in 1980s and two types of new critical facilities, Static Experiment Critical Facility (STACY) and Transient Experiment Critical Facility (TRACY) were completed on 1994 in Nuclear Fuel Cycle Safety Engineering Research Facility (NUCEF) of JAERI Tokai Research Establishment. STACY was designed so as to obtain critical mass data of low enriched uranium and plutonium solution which is extensively handled in LWR fuel reprocessing plant. TRACY is the critical facility where critical accident phenomenon is demonstrated with low enriched uranium nitrate solution. For criticality safety experiments with both facilities, the Fuel Treatment System is attached to them, where composition and concentration of uranium and plutonium nitrate solutions are widely varied so as to obtain experiments data covering fuel solution conditions in reprocessing plant. Design performances of both critical facilities were confirmed through mock-up tests of important components and cold function tests. Hot function test has started since January of 1995 and some of the results on STACY are to be reported. (author)

Development of Experimental Facilities for Advanced Spent Fuel Management Technology

Energy Technology Data Exchange (ETDEWEB)

You, G. S.; Jung, W. M.; Ku, J. H. [and others

2004-07-01

The advanced spent fuel management process(ACP), proposed to reduce the overall volume of the PWR spent fuel and improve safety and economy of the long-term storage of spent fuel, is under research and development. This technology convert spent fuels into pure metal-base uranium with removing the highly heat generating materials(Cs, Sr) efficiently and reducing of the decay heat, volume, and radioactivity from spent fuel by 1/4. In the next phase(2004{approx}2006), the demonstration of this technology will be carried out for verification of the ACP in a laboratory scale. For this demonstration, the hot cell facilities of {alpha}-{gamma} type and auxiliary facilities are required essentially for safe handling of high radioactive materials. As the hot cell facilities for demonstration of the ACP, a existing hot cell of {beta}-{gamma} type will be refurbished to minimize construction expenditures of hot cell facility. In this study, the design requirements are established, and the process detail work flow was analysed for the optimum arrangement to ensure effective process operation in hot cell. And also, the basic and detail design of hot cell facility and process, and safety analysis was performed to secure conservative safety of hot cell facility and process.

Annual report to the Laser Facility Committee 1984

International Nuclear Information System (INIS)

1984-01-01

The report describes the work carried out at, or in association with, the Central Laser Facility (CLF), during the year ending March 1984. The CLF programme is divided into three main sections. The first, the glass laser scientific programme, is concerned with applications of the high power Nd glass laser. The second, the ultra violet radiation facility scientific programme, involves the excimer pumped frequency tunable lasers. The last, high power KrF laser development, describes Research and development work on this laser. (U.K.)

US DOE surplus facilities management program (SFMP). International technology exchange activities

International Nuclear Information System (INIS)

Broderick, J.

1986-01-01

The Surplus Facilities Management Program is one of five remedial action programs established by the US Department of Energy (DOE) to eliminate potential hazards to the public and environment from radioactive contamination. These programs provide remedial actions at various facilities and sites previously used by the US Government in national atomic energy programs. Included are uranium ore milling sites, nuclear materials production plants, and research and development facilities. The DOE's five remedial action programs are: the Grand Junction Remedial Action Project; the Formerly Utilized Sites Remedial Action Project; the West Valley Demonstration Project; and the Surplus Facilities Management Program. The Surplus Facilities Management Program (SWMP) was established by DOE in 1978. There are presently over 300 shutdown facilities in the SFMP located at sites across the United States and in Puerto Rico. In some cases, remedial action involves decontaminating and releasing a facility for some other use. In other instances, facilities are completely demolished and removed from the site

Use of compensation and incentives in siting low-level radioactive waste disposal facilities

International Nuclear Information System (INIS)

Smith, T.P.; Jaffe, M.

1984-09-01

In discussing the use of compensation and incentives in siting low-level radioactive waste disposal facilities, chapters are devoted to: compensation and incentives in disposal facility siting (definitions and effects of compensation and incentives and siting decisions involving the use of compensation and incentives); the impacts of regional and state low-level radioactive waste facilities; the legal framework of compensation; and recommendations regarding the use of compensation

Neuromuscular involvement in various types of Ehlers-Danlos syndrome.

NARCIS (Netherlands)

Voermans, N.C.; Alfen, N. van; Pillen, S.; Lammens, M.M.Y.; Schalkwijk, J.; Zwarts, M.J.; Rooij, I.A.L.M. van; Hamel, B.C.J.; Engelen, B.G.M. van

2009-01-01

OBJECTIVE: Ehlers-Danlos syndrome (EDS) is a clinically and genetically heterogeneous group of heritable connective tissue disorders characterized by joint hypermobility, skin hyperextensibility, and tissue fragility. Muscle involvement is plausible based on recently discovered interactions between

2005 dossier: clay. Tome: architecture and management of the geologic disposal facility

International Nuclear Information System (INIS)

2005-01-01

This document makes a status of the researches carried out by the French national agency of radioactive wastes (ANDRA) about the design of a geologic disposal facility for high-level and long-lived radioactive wastes in argilite formations. Content: 1 - approach of the study: goal, main steps of the design study, iterative approach, content; 2 - general description: high-level and long-lived radioactive wastes, purposes of a reversible disposal, geologic context of the Meuse/Haute-Marne site - the Callovo-Oxfordian formation, design principles of the disposal facility architecture, role of the different disposal components; 3 - high-level and long-lived wastes: production scenarios, description of primary containers, inventory model, hypotheses about receipt fluxes of primary containers; 4- disposal containers: B-type waste containers, C-type waste containers, spent fuel disposal containers; 5 - disposal modules: B-type waste disposal modules, C-type waste disposal modules, spent-fuel disposal modules; 6 - overall underground architecture: main safety questions, overall design, dimensioning factors, construction logic and overall exploitation of the facility, dimensioning of galleries, underground architecture adaptation to different scenarios; 7 - boreholes and galleries: general needs, design principles retained, boreholes description, galleries description, building up of boreholes and galleries, durability of facilities, backfilling and sealing up of boreholes and galleries; 8 - surface facilities: general organization, nuclear area, industrial and administrative area, tailings area; 9 - nuclear exploitation means of the facility: receipt of primary containers and preparation of disposal containers, transfer of disposal containers from the surface to the disposal alveoles, setting up of containers inside alveoles; 10 - reversible management of the disposal: step by step disposal process, mastery of disposal behaviour and action capacity, observation and

Regionalised tertiary psychiatric residential facilities.

Science.gov (United States)

Lesage, Alain; Groden, David; Goldner, Elliot M; Gelinas, Daniel; Arnold, Leslie M

2008-01-01

Psychiatric hospitals remain the main venue for long-term mental health care and, despite widespread closures and downsizing, no country that built asylums in the last century has done away with them entirely--with the recent exception of Italy. Differentiated community-based residential alternatives have been developed over the past decades, with staffing levels that range from full-time professional, to daytime only, to part-time/on-call. This paper reviews the characteristics of community-based psychiatric residential care facilities as an alternative to long-term care in psychiatric hospitals. It describes five factors decision makers should consider: 1. number of residential places needed; 2. staffing levels; 3. physical setting; 4. programming; and 5. governance and financing. In Italy, facilities with full-time professional staff have been developed since the mid-1990s to accommodate the last cohorts of patients discharged from psychiatric hospitals. In the United Kingdom, experiments with hostel wards since the 1980s have shown that home-like, small-scale facilities with intensive treatment and rehabilitation programming can be effective for the most difficult-to-place patients. More recently in Australia, Community Care Units (CCUs) have been applying this concept. In the Canadian province of British Columbia (BC), Tertiary Psychiatric Residential Facilities (TPRFs) have been developed as part of an effort to regionalise health and social services and downsize and ultimately close its only psychiatric hospital. This type of service must be further developed in addition to the need for forensic, acute-care and intermediate-level beds, as well as for community-based care such as assertive community treatment and intensive case management. All these types of services, together with long-term community-based residential care, constitute the elements of a balanced mental health care system. As part of a region's balanced mental health care plan, these Tertiary

Facility effluent monitoring plan for the B plant

International Nuclear Information System (INIS)

Lesser, J.E.

1994-09-01

A facility effluent monitoring plan is required by the U.S. Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438-1. This facility effluent monitoring plant assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan shall ensure long-range integrity of the effluent monitoring systems by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and it must be updated every three years

Field Lysimeter Test Facility for protective barriers: Experimental plan

International Nuclear Information System (INIS)

Kirkham, R.R.; Gee, G.W.; Downs, J.L.

1987-12-01

This document was first written in October 1986 and has been used to guide the design of the Field Lysimeter Test Facility (FLTF) and to promote discussions between research and engineering staff regarding the selection of barrier treatments for inclusion in the FLTF. The construction of the lysimeter facility was completed June 28, 1987. This document describes the facility, the treatments placed in each lysimeter, types of measurements made in each lysimeter, and a brief discussion of project activities related to quality assurance, safety, and funding requirements. The treatment description and figures have been updated to reflect the lysimeter facility as constructed. 12 refs., 6 figs., 5 tabs

Sanford Underground Research Facility - The United State's Deep Underground Research Facility

Science.gov (United States)

Vardiman, D.

2012-12-01

/LIDAR), surveying instruments, and surveying benchmarks and optical survey points. Currently an array of single and multipoint extensometers monitors the Davis Campus. A facility-wide micro seismic monitoring system is anticipated to be deployed during the latter half of 2012. This system is designed to monitor minor events initiated within the historical mined out portions of the facility. The major science programs for the coming five years consist of the MAJORANA DEMONSTRATOR (MJD) neutrinoless double beta decay experiment; the Large Underground Xenon (LUX) dark matter search, the Center for Ultralow Background Experiments at DUSEL (CUBED), numerous geoscience installations, Long-Baseline Neutrino Experiment (LBNE), a nuclear astrophysics program involving a low energy underground particle accelerator, second and third generation dark matter experiments, and additional low background counting facilities. The Sanford Lab facility is an active, U.S. based, deep underground research facility dedicated to science, affording the science community the opportunity to conduct unprecedented scientific research in a broad range of physics, biology and geoscience fields at depth. SURF is actively interested in hosting additional research collaborations and provides resources for full facility design, cost estimation, excavation, construction and support management services.

Characterisation study of radionuclides in Hot Cell Facility

International Nuclear Information System (INIS)

Ghare, P.T.; Rath, D.P.; Govalkar, Atul; Mukherjee, Govinda; AniIKumar, S.; Yadav, R.K.B.; Mallik, G.K.

2016-01-01

Examination of different types of experimental as well as power reactor irradiated fuels and validation of fuel modeling codes is carried out in general Hot cell facility. The Hot cell facility has six concrete shielded hot cells, capable of handling radioactivity varying from 3.7 TBQ to 3700 TBq gamma activity. The facility was augmented with two hot cells having designed capacity to handle radioactivity of 9250 TBQ of equivalent activity of 60 Co. The study of characterization of various radionuclides present inside the hot cell of PIE facility was taken up. This study will help in providing valuable inputs for various radiological safety parameters to keep personnel exposure to ALARA level as per the mandate of radiation safety program

Academic Computing Facilities and Services in Higher Education--A Survey.

Science.gov (United States)

Warlick, Charles H.

1986-01-01

Presents statistics about academic computing facilities based on data collected over the past six years from 1,753 institutions in the United States, Canada, Mexico, and Puerto Rico for the "Directory of Computing Facilities in Higher Education." Organizational, functional, and financial characteristics are examined as well as types of…

Calcined solids storage facility closure study

International Nuclear Information System (INIS)

Dahlmeir, M.M.; Tuott, L.C.; Spaulding, B.C.

1998-02-01

The disposal of radioactive wastes now stored at the Idaho National Engineering and Environmental Laboratory is currently mandated under a open-quotes Settlement Agreementclose quotes (or open-quotes Batt Agreementclose quotes) between the Department of Energy and the State of Idaho. Under this agreement, all high-level waste must be treated as necessary to meet the disposal criteria and disposed of or made road ready to ship from the INEEL by 2035. In order to comply with this agreement, all calcined waste produced in the New Waste Calcining Facility and stored in the Calcined Solids Facility must be treated and disposed of by 2035. Several treatment options for the calcined waste have been studied in support of the High-Level Waste Environmental Impact Statement. Two treatment methods studied, referred to as the TRU Waste Separations Options, involve the separation of the high-level waste (calcine) into TRU waste and low-level waste (Class A or Class C). Following treatment, the TRU waste would be sent to the Waste Isolation Pilot Plant (WIPP) for final storage. It has been proposed that the low-level waste be disposed of in the Tank Farm Facility and/or the Calcined Solids Storage Facility following Resource Conservation and Recovery Act closure. In order to use the seven Bin Sets making up the Calcined Solids Storage Facility as a low-level waste landfill, the facility must first be closed to Resource Conservation and Recovery Act (RCRA) standards. This study identifies and discusses two basic methods available to close the Calcined Solids Storage Facility under the RCRA - Risk-Based Clean Closure and Closure to Landfill Standards. In addition to the closure methods, the regulatory requirements and issues associated with turning the Calcined Solids Storage Facility into an NRC low-level waste landfill or filling the bin voids with clean grout are discussed

Calcined solids storage facility closure study

Energy Technology Data Exchange (ETDEWEB)

Dahlmeir, M.M.; Tuott, L.C.; Spaulding, B.C. [and others

1998-02-01

The disposal of radioactive wastes now stored at the Idaho National Engineering and Environmental Laboratory is currently mandated under a {open_quotes}Settlement Agreement{close_quotes} (or {open_quotes}Batt Agreement{close_quotes}) between the Department of Energy and the State of Idaho. Under this agreement, all high-level waste must be treated as necessary to meet the disposal criteria and disposed of or made road ready to ship from the INEEL by 2035. In order to comply with this agreement, all calcined waste produced in the New Waste Calcining Facility and stored in the Calcined Solids Facility must be treated and disposed of by 2035. Several treatment options for the calcined waste have been studied in support of the High-Level Waste Environmental Impact Statement. Two treatment methods studied, referred to as the TRU Waste Separations Options, involve the separation of the high-level waste (calcine) into TRU waste and low-level waste (Class A or Class C). Following treatment, the TRU waste would be sent to the Waste Isolation Pilot Plant (WIPP) for final storage. It has been proposed that the low-level waste be disposed of in the Tank Farm Facility and/or the Calcined Solids Storage Facility following Resource Conservation and Recovery Act closure. In order to use the seven Bin Sets making up the Calcined Solids Storage Facility as a low-level waste landfill, the facility must first be closed to Resource Conservation and Recovery Act (RCRA) standards. This study identifies and discusses two basic methods available to close the Calcined Solids Storage Facility under the RCRA - Risk-Based Clean Closure and Closure to Landfill Standards. In addition to the closure methods, the regulatory requirements and issues associated with turning the Calcined Solids Storage Facility into an NRC low-level waste landfill or filling the bin voids with clean grout are discussed.

Dynamic instrumentation for the K-1600 seismic test facility recommissioning

International Nuclear Information System (INIS)

VanHoy, B.W.

1991-01-01

Martin Marietta Energy Systems, Inc. is the site contractor to the Department of Energy (DOE) for three Oak Ridge, Tennessee sites, the site in Portsmouth, Ohio, and the site in Paducah, Kentucky. To provide a focus for all natural phenomena engineering related problems, Martin Marietta Energy Systems, Inc. established the Center for Natural Phenomena Engineering under the technical direction of Dr. James E. Beavers. One of the Center's mandates is the determination of seismic properties of building structures containing sensitive processes. This has led to the recommissioning of the K-1600 Seismic Test Facility. The biaxial shake table in this facility was constructed during the eighties for seismic qualification of equipment of the Gas Centrifuge Enrichment Plant. After construction of the plant was terminated the Seismic Test Facility was placed in standby where it was left for six years. The facility's original instrumentation was evaluated versus the required instrumentation to augment its new expanded mission parameters. Instrumentation selection involving technology changes, age and attrition, and the new mission goals are discussed in this paper along with the rationale and budget that were involved with each decision. The testing potential of this facility along with the instrumentation upgrades necessary to accomplish these new tasks for the Center for Natural Phenomena Engineering are considered. New uses such as seismic qualification of equipment utilized in DOE's missions at various sites and waste treatment are proposed. This instrumentation selection is discussed in detail to show the rationale and proposed used of the facility as well as the capabilities of this DOE resource

Planning and Managing School Facilities for Agriculture

Science.gov (United States)

Staller, Bernie

1976-01-01

The Agribusiness Department at Janesville Parker Senior High in Wisconsin involves 360 students and three instructors in three different buildings. Facilities were provided through a variety of methods with major emphasis on utilizing the urban setting. Future Farmers of America students operate projects in orchards, greenhouse, gardens, and…

A system approach to nuclear facility monitoring

Energy Technology Data Exchange (ETDEWEB)

Argo, P.E.; Doak, J.E.; Howse, J.W.

1996-09-01

Sensor technology for use in nuclear facility monitoring has reached and advanced stage of development. Research on where to place these sensors in a facility and how to combine their outputs in a meaningful fashion does not appear to be keeping pace. In this paper, we take a global view of the problem where sensor technology is viewed as only one piece of a large puzzle. Other pieces of this puzzle include the optimal location and type of sensors used in a specific facility, the rate at which sensors record information, and the risk associated with the materials/processes at a facility. If the data are analyzed off-site, how will they be transmitted? Is real-time analysis necessary? Are we monitoring only the facility itself, or might we also monitor the processing that occurs there? How are we going to combine the output from the various sensors to give us an accurate picture of the state of the facility? This paper will not try to answer all these questions, but rather it will attempt to stimulate thought in this area by formulating a systems approach to the problem demonstrated by a prototype system and a systems proposed for an actual facility. Our focus will be on the data analysis aspect of the problem.

Status and Plans for a Superconducting RF Accelerator Test Facility at Fermilab

International Nuclear Information System (INIS)

Andrews, R.; Baffes, C.M.; Carlson, K.; Chase, B.; Church, M.D.; Harms, E.R.; Klebaner, A.L.; Leibfritz, J.R.; Martinez, A.; Nagaitsev, S.; Nobrega, L.E.

2012-01-01

The Advanced Superconducting Test Accelerator (ASTA) is being constructed at Fermilab. The existing New Muon Lab (NML) building is being converted for this facility. The accelerator will consist of an electron gun, injector, beam acceleration section consisting of 3 TTF-type or ILC-type cryomodules, multiple downstream beam lines for testing diagnostics and conducting various beam tests, and a high power beam dump. When completed, it is envisioned that this facility will initially be capable of generating a 750 MeV electron beam with ILC beam intensity. An expansion of this facility was recently completed that will provide the capability to upgrade the accelerator to a total beam energy of 1.5 GeV. Two new buildings were also constructed adjacent to the ASTA facility to house a new cryogenic plant and multiple superconducting RF (SRF) cryomodule test stands. In addition to testing accelerator components, this facility will be used to test RF power systems, instrumentation, and control systems for future SRF accelerators such as the ILC and Project-X. This paper describes the current status and overall plans for this facility.

Safety Assessment for Decommissioning of Nuclear Facilities - From Methodology to the Use of Results in Decision Making

International Nuclear Information System (INIS)

Batandjieva, B.; Ferch, R.; Joubert, A.; Kaulard, J.; Manson, P.; Percival, K.; Thierfeldt, St.

2008-01-01

approach for reviewing safety assessments for decommissioning activities and as a basis for the regulatory decision making; - To provide a forum for exchange of experience in evaluation and demonstration of safety during decommissioning of various types of nuclear facilities. The project has involved over one hundred interested experts, of which fifty were actively involved throughout, from thirty plus countries working in eight working groups over the period 2004-2007. The experts presented and analyzed their experiences and on this basis developed recommendations on good practice in the development and review of safety assessments for decommissioning. According to the objectives, the project initially focused on the development of a harmonized methodology to undertake safety assessment. Later on the project entailed working groups testing out the methodology by applying it to a number of test cases representative of the typical facilities presently undergoing decommissioning. These included a nuclear power plant, a research reactor and a plutonium laboratory. The outcomes from the project and the key lessons learned are presented below. (authors)

Evaluation methods for hospital facilities

DEFF Research Database (Denmark)

Fronczek-Munter, Aneta

2013-01-01

according to focus areas and proposes which evaluation methods to use in different building phases of healthcare facilities. Hospital evaluations with experts and users are also considered; their subjective view on space, function, technology, usability and aesthetics. Results & solutions: This paper...... presents the different methods for evaluating buildings in use in a new model, the Evaluation Focus Flower, and proposes which evaluation methods are suitable for various aims and building phases, i.e. which is giving best input for the initial briefing process of new hospital facilities with ambition...... of creating buildings with enhanced usability. Additionally various evaluation methods used in hospital cases in Denmark and Norway are presented. Involvement of users is proposed, not just in defining requirements but also in co-creation/design and evaluation of solutions. The theories and preliminary...

Development of Accident Scenario for Interim Spent Fuel Storage Facility Based on Fukushima Accident

Energy Technology Data Exchange (ETDEWEB)

Lee, Dongjin; Choi, Kwangsoon; Yoon, Hyungjoon; Park, Jungsu [KEPCO-E and C, Yongin (Korea, Republic of)

2014-05-15

700 MTU of spent nuclear fuel is discharged from nuclear fleet every year and spent fuel storage is currently 70.9% full. The on-site wet type spent fuel storage pool of each NPP(nuclear power plants) in Korea will shortly exceed its storage limit. Backdrop, the Korean government has rolled out a plan to construct an interim spent fuel storage facility by 2024. However, the type of interim spent fuel storage facility has not been decided yet in detail. The Fukushima accident has resulted in more stringent requirements for nuclear facilities in case of beyond design basis accidents. Therefore, there has been growing demand for developing scenario on interim storage facility to prepare for beyond design basis accidents and conducting dose assessment based on the scenario to verify the safety of each type of storage.

Post-closure safety assessment of near surface disposal facilities for disused sealed radioactive sources

International Nuclear Information System (INIS)

Lee, Seunghee; Kim, Juyoul

2017-01-01

Highlights: • Post-closure safety assessment of near surface disposal facility for DSRS was performed. • Engineered vault and rock-cavern type were considered for normal and well scenario. • 14 C, 226 Ra, 241 Am were primary nuclides contributing large portion of exposure dose. • Near surface disposal of DSRSs containing 14 C, 226 Ra and 241 Am should be restricted. - Abstract: Great attention has been recently paid to the post-closure safety assessment of low- and intermediate-level radioactive waste (LILW) disposal facility for disused sealed radioactive sources (DSRSs) around the world. Although the amount of volume of DSRSs generated from industry, medicine and research and education organization was relatively small compared with radioactive wastes from commercial nuclear power plants, some DSRSs can pose a significant hazard to human health due to their high activities and long half-lives, if not appropriately managed and disposed. In this study, post-closure safety assessment was carried out for DSRSs generated from 1991 to 2014 in Korea in order to ensure long-term safety of near surface disposal facilities. Two kinds of disposal options were considered, i.e., engineered vault type disposal facility and rock-cavern type disposal facility. Rock-cavern type disposal facility has been under operation in Gyeongju city, republic of Korea since August 2015 and engineered vault type disposal facility will be constructed until December 2020 in the vicinity of rock-cavern disposal facility. Assessment endpoint was individual dose to the member of critical group, which was modeled by GoldSim, which has been widely used as probabilistic risk analysis software based on Monte Carlo simulation in the area of safety assessment of radioactive waste facilities. In normal groundwater scenario, the maximum exposure dose was extremely low, approximately 1 × 10 −7 mSv/yr, for both disposal options and satisfied the regulatory limit of 0.1 mSv/yr. However, in the

Waste from decommissioning of research reactors and other small nuclear facilities

International Nuclear Information System (INIS)

Massaut, V.

2001-01-01

Full text: Small nuclear facilities were often built for research or pilot purposes. It includes the research reactors of various types and various aims (physics research, nuclear research, nuclear weapons development, materials testing reactor, isotope production, pilot plant, etc.) as well as laboratories, hot cells and accelerators used for a broad spectrum of research or production purposes. These installations are characterized not only by their size (reduced footprint) but also, and even mostly, by the very diversified type of materials, products and isotopes handled within these facilities. This large variety can sometimes enhance the difficulties encountered for the dismantling of such facilities. The presence of materials like beryllium, graphite, lead, PCBs, sodium, sometimes in relatively large quantities, are also challenges to be faced by the dismantlers of such facilities, because these types of waste are either toxic or no solutions are readily available for their conditioning or long term disposal. The paper will review what is currently done in different small nuclear facilities, and what are the remaining problems and challenges for future dismantling and waste management. The question of whether Research and Development for waste handling methods and processes is needed is still pending. Even for the dismantling operation itself, important improvements can be brought in the fields of characterization, decontamination, remote handling, etc. by further developments and innovative systems. The way of funding such facilities decommissioning will be reviewed as well as the very difficult cost estimation for such facilities, often one-of-a-kind. The aspects of radioprotection optimization (ALARA principle) and classical operators safety will also be highlighted, as well as the potential solutions or improvements. In fact, small nuclear facilities encounter often, when dismantling, the same problems as the large nuclear power plants, but have in

Standby status report Hot Semiworks facility

Energy Technology Data Exchange (ETDEWEB)

Cooley, C.R.

1957-09-01

This report is written to provide information concerning the status of the Hot Semiworks facility as it is placed in stand-by on July 1, 1957. The plant was constructed in 1951 and early 1952. It vas operated on Redox type investigations until the last of 1953. The plant was then converted to the Purex flowsheet under Project CA 513 D. Operations on the Purex type investigations were started in early 1955 and continued until early in 1956. At that time a maintenance program for plant improvement and repair was initiated. This program was completed on July 1, 1957. Statements are contained in this report which pertain to the present status of physical equipment and facilities and the adequacy, operating experience, recommendations for improvement, previous work, and future considerations of the plant. However, the primary intent of the report is to provide pertinent information to personnel associated with a future start-up. For this reason, certain parts of the report are quite detailed. Only statements concerning the existing or previous state of the facility and equipment are factual. Others are opinions or experiences of plant operating personnel. Emphasis has also been placed on the faults encountered rather than the good features of the plant, in order that these faults might be corrected in the future.

Control system of test and research facilities for nuclear energy industry

International Nuclear Information System (INIS)

1983-01-01

IHI manufactures several kinds of test and research facilities used for research and development of new type power reactor and solidification system of high level radioactive liquid waste and safety research of light water reactor. These facilities are usually new type plants themselves, so that their control systems have to be designed individually for each plant with the basic conception. They have many operation modes because of their purposes of research and development, so the operation has to be automatized and requires the complicated sequence control system. In addition to these requirements, the detail design is hardly fixed on schedule and often modified during the initial start up period. Therefore, the computer control system was applied to these facilities with CRT display for man-machine communication earlier than to commercial power plants, because in the computer system the control logic is not hard wired but soft programmed and can be easily modified. In this paper, two typical computer control systems, one for PWR reflood test facility and another for mock-up test facility for solidification of liquid waste, are introduced. (author)

Assistance Dogs: Historic Patterns and Roles of Dogs Placed by ADI or IGDF Accredited Facilities and by Non-Accredited U.S. Facilities.

Science.gov (United States)

Walther, Sandra; Yamamoto, Mariko; Thigpen, Abigail Paige; Garcia, Anaissa; Willits, Neil H; Hart, Lynette A

2017-01-01

Dogs' roles to support people with disabilities are increasing. Existing U.S. laws and regulations pertaining to the use of dogs for people with disabilities are only minimally enforced. Pushback legislation against some aspects of uses of assistance dogs currently is being passed or proposed in several states. Further, the U.S. Department of the Army and the Veterans' Administration support only dogs trained by an Assistance Dogs International (ADI) or International Guide Dog Federation (IGDF) accredited facility. Lacking a mandatory national process for screening the selection, training, and placement of assistance dogs with persons who have disabilities, the U.S. offers a creative but confusing opportunity for people to train their own dogs for any disability. While no U.S. surveillance system monitors assistance dogs, other countries generally have a legislated or regulatory process for approving assistance dogs or a cultural convention for obtaining dogs from accredited facilities. We conducted an online survey investigating current demographics of assistance dogs placed in 2013 and 2014 with persons who have disabilities, by facilities worldwide that are associated with ADI or IGDF and by some non-accredited U.S. facilities. Placement data from ADI and IGDF facilities revealed that in most countries aside from the U.S., guide dogs were by far the main type of assistance dog placed. In the U.S., there were about equal numbers of mobility and guide dogs placed, including many placed by large older facilities, along with smaller numbers of other types of assistance dogs. In non-accredited U.S. facilities, psychiatric dogs accounted for most placements. Dogs for families with an autistic child were increasing in all regions around the world. Of dog breeds placed, accredited facilities usually mentioned Labrador Retrievers and Golden Retrievers, and sometimes, German Shepherd Dogs. The facilities bred their dogs in-house, or acquired them from certain breeders

Opportunities for Process Monitoring Techniques at Delayed Access Facilities

Energy Technology Data Exchange (ETDEWEB)

Curtis, Michael M.; Gitau, Ernest TN; Johnson, Shirley J.; Schanfein, Mark; Toomey, Christopher

2013-09-20

Except for specific cases where the International Atomic Energy Agency (IAEA) maintains a continuous presence at a facility (such as the Japanese Rokkasho Reprocessing Plant), there is always a period of time or delay between the moment a State is notified or aware of an upcoming inspection, and the time the inspector actually enters the material balance area or facility. Termed by the authors as “delayed access,” this period of time between inspection notice and inspector entrance to a facility poses a concern. Delayed access also has the potential to reduce the effectiveness of measures applied as part of the Safeguards Approach for a facility (such as short-notice inspections). This report investigates the feasibility of using process monitoring to address safeguards challenges posed by delayed access at a subset of facility types.

Metering management at the plutonium research and development facilities

International Nuclear Information System (INIS)

Hirata, Masaru; Miyamoto, Fujio; Kurosawa, Makoto; Abe, Jiro; Sakai, Haruyuki; Suzuki, Tsuneo.

1996-01-01

Nuclear fuel research laboratory of the Oarai Research Laboratory of the Japan Atomic Energy Research Institute is an R and D facility to treat with plutonium and processes various and versatile type samples in chemical and physical form for use of various experimental researches even though on much small amount. Furthermore, wasted and plutonium samples are often transported to other KMP and MBA such as radioactive waste management facility, nuclear reactor facility and so forth. As this facility is a place to treat plutonium important on the safeguards, it is a facility necessary for detection and allowance actions and for detail managements on the metering management data to report to government and IAEA in each small amount sample and different configuration. In this paper, metering management of internationally regulated matters and metering management system using a work station newly produced in such small scale facility were introduced. (G.K.)

Profiles of facilities used for FBR research and testing

International Nuclear Information System (INIS)

1976-12-01

This document contains a concise up-to date of supporting ''Liquid Metal Fast Breeder'' facilities submitted by countries (Federal Republic of Germany, Italy, France, Belgium, Netherlands, UK, USA, USSR and Japan) and international organizations. It has the purpose of providing an over-view of the facilities currently used or under construction and of the type of experiments that can be conducted therein

I. Do chronic pain patients' perceptions about their preinjury jobs determine their intent to return to the same type of job post-pain facility treatment?

Science.gov (United States)

Fishbain, D A; Rosomoff, H L; Cutler, R B; Steele-Rosomoff, R

1995-12-01

To demonstrate that chronic pain patients' (CPPs') perceptions about their preinjury jobs determine their intent to return to the same type of job post pain facility treatment. A total of 225 CPPs completed a series of rating scales and yes/no questions relating to their preinjury job perceptions and a question relating to intent to return to the same type of preinjury job post-pain facility treatment. The CPPs were broken down into subgroups (males, females, college males, noncollege males, college females, noncollege females), and within each subgroup those not intending to return to the same type of pre-injury job were compared to those intending to return on the preinjury job perception questions. In addition for the whole group, stepwise discriminant analysis was used to predict who planned to return to the preinjury job utilizing the job perceptions questions. Multidisciplinary Pain Center. Consecutive chronic pain patients. For the whole group, CPPs not intending to return were more likely to complain of job excessive physical demands, job satisfaction, and job dislike. Job perception complaints that were significantly different between the intending and not intending to return groups differed between the subgroups. For example, noncollege males not intending to return were more likely to complain of excessive physical demands only versus satisfaction and liking as significant items for college males who did not intend to return. Within the discriminant analysis, the combination of job satisfaction, excessive physical demands, employee conflicts, job liking, job dangerousness, supervisory conflicts, job stress, and age classified 73.46% of the CPPs correctly as to intent to return to the same type of preinjury job. There appears to be a relationship between preinjury job perceptions and intent to return to the same type of job post pain treatment. However, subgroups of CPPs will differ by which job perceptions are important towards making that decision.

UGCT: New X-ray radiography and tomography facility

International Nuclear Information System (INIS)

Masschaele, B.C.; Cnudde, V.; Dierick, M.; Jacobs, P.; Hoorebeke, L. van; Vlassenbroeck, J.

2007-01-01

The UGCT (University Gent Computer Tomography) facility, a cooperation between the Radiation Physics research group and the Sedimentary Geology and Engineering Geology research group is a new CT facility providing a large range of scanning possibilities. Formerly a Skyscan 1072 was used to perform X-ray micro-CT scans at the UGCT facility and although this is a very powerful instrument, there were needs for a higher resolution and more flexibility. Therefore, the UCGT facility started the construction of a multidisciplinary micro-CT scanner inside a shielded room with a maximum flexibility of the set-up. The X-ray tube of this high-resolution CT scanner is a state-of-the-art open-type device with dual head: one head for high power micro-CT and one for sub-micro- or also called nano-CT. An important advantage of this scanner is that different detectors can be used to optimize the scanning conditions of the objects under investigation. The entire set-up is built on a large optical table to obtain the highest possible stability. Due to the flexible set-up and the powerful CT reconstruction software 'Octopus', it is possible to obtain the highest quality and the best signal-to-noise of the reconstructed images for each type of sample

UGCT: New X-ray radiography and tomography facility

Energy Technology Data Exchange (ETDEWEB)

Masschaele, B.C. [Department of Subatomic and Radiation Physics, Ghent University, Proeftuinstraat 86, B-9000 Gent (Belgium)], E-mail: bert.masschaele@ugent.be; Cnudde, V. [Department of Geology and Soil Science, Ghent University, Krijgslaan 281, B-9000 Gent (Belgium); Dierick, M. [Department of Subatomic and Radiation Physics, Ghent University, Proeftuinstraat 86, B-9000 Gent (Belgium); Jacobs, P. [Department of Geology and Soil Science, Ghent University, Krijgslaan 281, B-9000 Gent (Belgium); Hoorebeke, L. van; Vlassenbroeck, J. [Department of Subatomic and Radiation Physics, Ghent University, Proeftuinstraat 86, B-9000 Gent (Belgium)

2007-09-21

The UGCT (University Gent Computer Tomography) facility, a cooperation between the Radiation Physics research group and the Sedimentary Geology and Engineering Geology research group is a new CT facility providing a large range of scanning possibilities. Formerly a Skyscan 1072 was used to perform X-ray micro-CT scans at the UGCT facility and although this is a very powerful instrument, there were needs for a higher resolution and more flexibility. Therefore, the UCGT facility started the construction of a multidisciplinary micro-CT scanner inside a shielded room with a maximum flexibility of the set-up. The X-ray tube of this high-resolution CT scanner is a state-of-the-art open-type device with dual head: one head for high power micro-CT and one for sub-micro- or also called nano-CT. An important advantage of this scanner is that different detectors can be used to optimize the scanning conditions of the objects under investigation. The entire set-up is built on a large optical table to obtain the highest possible stability. Due to the flexible set-up and the powerful CT reconstruction software 'Octopus', it is possible to obtain the highest quality and the best signal-to-noise of the reconstructed images for each type of sample.

Facility design, construction, and operation

International Nuclear Information System (INIS)

1995-04-01

France has been disposing of low-level radioactive waste (LLW) at the Centre de Stockage de la Manche (CSM) since 1969 and now at the Centre de Stockage de l'Aube (CSA) since 1992. In France, several agencies and companies are involved in the development and implementation of LLW technology. The Commissariat a l'Energie Atomic (CEA), is responsible for research and development of new technologies. The Agence National pour la Gestion des Dechets Radioactifs is the agency responsible for the construction and operation of disposal facilities and for wastes acceptance for these facilities. Compagnie Generale des Matieres Nucleaires provides fuel services, including uranium enrichment, fuel fabrication, and fuel reprocessing, and is thus one generator of LLW. Societe pour les Techniques Nouvelles is an engineering company responsible for commercializing CEA waste management technology and for engineering and design support for the facilities. Numatec, Inc. is a US company representing these French companies and agencies in the US. In Task 1.1 of Numatec's contract with Martin Marietta Energy Systems, Numatec provides details on the design, construction and operation of the LLW disposal facilities at CSM and CSA. Lessons learned from operation of CSM and incorporated into the design, construction and operating procedures at CSA are identified and discussed. The process used by the French for identification, selection, and evaluation of disposal technologies is provided. Specifically, the decisionmaking process resulting in the change in disposal facility design for the CSA versus the CSM is discussed. This report provides' all of the basic information in these areas and reflects actual experience to date

Journal of EEA, Vol. 30, 2013 COMPUTERIZED FACILITIES ...

African Journals Online (AJOL)

dell

Key words: Computer Aided Layout Design,. Construction ... Commonly used software are ... popular improvement-type methods are. Computerized Relative Allocation of Facilities .... closeness ratings values are given different numerical.

Disposal facility data for the interim performance

International Nuclear Information System (INIS)

Eiholzer, C.R.

1995-01-01

The purpose of this report is to identify and provide information on the waste package and disposal facility concepts to be used for the low-level waste tank interim performance assessment. Current concepts for the low-level waste form, canister, and the disposal facility will be used for the interim performance assessment. The concept for the waste form consists of vitrified glass cullet in a sulfur polymer cement matrix material. The waste form will be contained in a 2 x 2 x 8 meter carbon steel container. Two disposal facility concepts will be used for the interim performance assessment. These facility concepts are based on a preliminary disposal facility concept developed for estimating costs for a disposal options configuration study. These disposal concepts are based on vault type structures. None of the concepts given in this report have been approved by a Tank Waste Remediation Systems (TWRS) decision board. These concepts will only be used in th interim performance assessment. Future performance assessments will be based on approved designs

Safeguards implementation at US facilities during 1986 and 1987

International Nuclear Information System (INIS)

Wredberg, L.

1987-01-01

Safeguards procedures were implemented at three nuclear facilities in the United States during 1986 and 1987, namely, the Westinghouse fuel fabrication plant in Columbia, South Carolina; the Salem No. 1 light water reactor (LWR) in New Jersey; and the Turkey Point No. 4 LWR in Florida. These three facilities have been under International Atomic Energy Agency (IAEA) safeguards since early 1986 in accordance with the voluntary offer agreement between the IAEA and the United States, which went into force in 1980. Because of limited manpower and budget resources allocated to safeguards in nuclear weapon states, only a limited number of facilities can be under IAEA safeguards inspections at a time. Facilities are, therefore, subject to inspection only during a 2-yr period in the case of the United States. After that period other facilities are selected for another 2-yr period from the list of facilities subject to safeguards under the agreement. The facilities have been selected so that they form a fuel cycle, i.e., the inspected reactors are fueled with fuel assemblies manufactured by the inspected fabrication plant. The IAEA applies full scope safeguards at the selected facilities based upon established implementation practice for the facility types

Is Male Involvement in ANC and PMTCT Associated with Increased ...

African Journals Online (AJOL)

AJRH Managing Editor

in antenatal care (ANC) services and pregnant women delivering at health facilities and being attended to by skilled birth ... Male involvement seems to be a key factor in women's health- seeking ..... already collected data to perform secondary.

Facility effluent monitoring plan for the 284-E and 284-W power plants

International Nuclear Information System (INIS)

Nickels, J.M.; Herman, D.R.

1992-11-01

A facility effluent monitoring plan is required by the US Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. A facility effluent monitoring plan determination was performed during calendar year 1991 and the evaluation requires the need for a facility effluent monitoring plan. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements

Decommissioning Strategies Selection for Facilities Using Radioactive Material

International Nuclear Information System (INIS)

Husen Zamroni; Jaka Rachmadetin

2008-01-01

The facilities using radioactive material that have been stopped operation will require some form of the decommissioning for public and environment safety. The approaches are identified by three decommissioning strategies: immediate dismantling, deferred dismantling and entombment. If a facility undergoes immediate dismantling, most radio nuclides will have no such sufficient time to decay and therefore this strategy may not provide reduction in the worker exposure. A facility that undergoes deferred dismantling may advantage from the radioactive decay of residual radio nuclides during the long term storage period and entombment could be a viable option for other nuclear facilities containing only short lived or limited concentrations of long lived radionuclides. Mostly, only two types of the decommissioning used to be done in the world, immediate and deferred dismantling. (author)

C-188 Co-60 sources installation and source rack loading optimization processes in a gamma irradiation facility

Energy Technology Data Exchange (ETDEWEB)

Santos, Paulo de S.; Vasquez, Pablo A.S., E-mail: psantos@ipen.br, E-mail: pavsalva@ipen.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

2017-11-01

Since 2004, the Multipurpose Gamma Facility at the Nuclear and Energy Research Institute has been providing services on radiation processing for disinfection and sterilization of health care and disposable medical products as well to support research studies on modification of physical, chemical and biological properties of several materials. Recently, there was an increment in irradiation of the Cultural Heritages. This facility uses C-188 double-encapsulated radioactive Cobalt-60 sources known as pencils from manufactures outside of country. The activity of the cobalt sources decays into a stable nickel isotope with a half-life around 5.27 years, which means a loss of 12.3% annually. Then, additional pencils of Cobalt-60 are added periodically to the source rack to maintain the required capacity or installed activity of the facility. The manufacturer makes shipping of the radioactive sources inside a high density container type B(U) , by sea. This one involves many administrative, transport and radiation safety procedures. Once in the facility, the container is opened inside a deep pool water to remove the pencils. The required source geometry of the facility is obtained by loading these source pencils into predetermined diagram or positions in source modules and distributing these modules over the source rack of the facility. The dose variation can be reduced placing the higher activity source pencils near the periphery of the source rack. In this work are presented the procedures for perform the boiling leaching tests applied to the container, the Cobalt-60 sources installation, the loading processes and the source rack loading optimization. (author)

Methods to estimate equipment and materials that are candidates for removal during the decontamination of fuel processing facilities

International Nuclear Information System (INIS)

Duncan, D.R.; Valero, O.J.; Hyre, R.A.; Pottmeyer, J.A.; Millar, J.S.; Reddick, J.A.

1995-02-01

The methodology presented in this report provides a model for estimating the volume and types of waste expected from the removal of equipment and other materials during Decontamination and Decommissioning (D and D) of canyon-type fuel reprocessing facilities. This methodology offers a rough estimation technique based on a comparative analysis for a similar, previously studied, reprocessing facility. This approach is especially useful as a planning tool to save time and money while preparing for final D and D. The basic methodology described here can be extended for use at other types of facilities, such as glovebox or reactor facilities

Decommissioning of the Hermes facility at AERE Harwell

International Nuclear Information System (INIS)

Brant, A.W.

1988-01-01

The contract for decommissioning the HERMES (Heavy Element and Radioactive Materials Electromagnetic Separator) Facility at AERE Harwell was the first contract of its type awarded to Private Industry by the Public Sector. The work required operatives to work in pressure suits for extended periods in decommissioning a heavily alpha contaminated facility. The work required the setting up of a temporary changeroom, waste posting facilities, air suit supplies and controls and temporary ventilation for a completely self-contained site set-up. The Contractor had to provide and train his own operatives, provide all health physics supervision and control and take full responsibility for all technical matters. (author)

Characterization of uranium corrosion products involved in the March 13, 1998 fuel manufacturing facility pyrophoric event

International Nuclear Information System (INIS)

Totemeier, T.C.

1999-01-01

Uranium metal corrosion products from ZPPR fuel plates involved in the March 13, 1998 pyrophoric event in the Fuel Manufacturing Facility at Argonne National Laboratory-West were characterized using thermo-gravimetric analysis, X-ray diffraction, and BET gas sorption techniques. Characterization was performed on corrosion products in several different conditions: immediately after separation from the source metal, after low-temperature passivation, after passivation and extended vault storage, and after burning in the pyrophoric event. The ignition temperatures and hydride fractions of the corrosion product were strongly dependent on corrosion extent. Corrosion products from plates with corrosion extents less than 0.7% did not ignite in TGA testing, while products from plates with corrosion extents greater than 1.2% consistently ignited. Corrosion extent is defined as mass of corrosion products divided by the total mass of uranium. The hydride fraction increased with corrosion extent. There was little change in corrosion product properties after low-temperature passivation or vault storage. The burned products were not reactive and contained no hydride; the principal constituents were UO 2 and U 3 O 7 . The source of the event was a considerable quantity of reactive hydride present in the corrosion products. No specific ignition mechanism could be conclusively identified. The most likely initiator was a static discharge in the corrosion product from the 14th can as it was poured into the consolidation can. The available evidence does not support scenarios in which the powder in the consolidation can slowly self-heated to the ignition point, or in which the powder in the 14th can was improperly passivated

Characterization of uranium corrosion products involved in the March 13, 1998 fuel manufacturing facility pyrophoric event.

Energy Technology Data Exchange (ETDEWEB)

Totemeier, T.C.

1999-04-26

Uranium metal corrosion products from ZPPR fuel plates involved in the March 13, 1998 pyrophoric event in the Fuel Manufacturing Facility at Argonne National Laboratory-West were characterized using thermo-gravimetric analysis, X-ray diffraction, and BET gas sorption techniques. Characterization was performed on corrosion products in several different conditions: immediately after separation from the source metal, after low-temperature passivation, after passivation and extended vault storage, and after burning in the pyrophoric event. The ignition temperatures and hydride fractions of the corrosion product were strongly dependent on corrosion extent. Corrosion products from plates with corrosion extents less than 0.7% did not ignite in TGA testing, while products from plates with corrosion extents greater than 1.2% consistently ignited. Corrosion extent is defined as mass of corrosion products divided by the total mass of uranium. The hydride fraction increased with corrosion extent. There was little change in corrosion product properties after low-temperature passivation or vault storage. The burned products were not reactive and contained no hydride; the principal constituents were UO{sub 2} and U{sub 3}O{sub 7}. The source of the event was a considerable quantity of reactive hydride present in the corrosion products. No specific ignition mechanism could be conclusively identified. The most likely initiator was a static discharge in the corrosion product from the 14th can as it was poured into the consolidation can. The available evidence does not support scenarios in which the powder in the consolidation can slowly self-heated to the ignition point, or in which the powder in the 14th can was improperly passivated.

Co-Digestion of the Organic Fraction of Municipal Waste With Other Waste Types

DEFF Research Database (Denmark)

Hartmann, H.; Angelidaki, Irini; Ahring, Birgitte Kiær

2002-01-01

Several characteristics make anaerobic digestion of the organic fraction of municipal solid waste (OFMSW) difficult. By co-digestion of OFMSW with several other waste types it will be possible to optimize the anaerobic process by waste management. The co-digestion concept involves the treatment...... of several waste types in a single treatment facility. By combining many types of waste it will be possible to treat a wider range of organic waste types by the anaerobic digestion process (figure 1). Furthermore, co-digestion enables the treatment of organic waste with a high biogas potential that makes...... the operation of biogas plants more economically feasible (Ahring et al., 1992a). Thus, co-digestion gives a new attitude to the evaluation of waste: since anaerobic digestion of organic waste is both a waste stabilization method and an energy gaining process with production of a fertilizer, organic waste...

Facile preparation of hierarchically porous diatomite/MFI-type zeolite composites and their performance of benzene adsorption: the effects of NaOH etching pretreatment.

Science.gov (United States)

Yu, Wenbin; Yuan, Peng; Liu, Dong; Deng, Liangliang; Yuan, Weiwei; Tao, Bo; Cheng, Hefa; Chen, Fanrong

2015-03-21

Hierarchically porous diatomite/MFI-type zeolite (Dt/Z) composites with excellent benzene adsorption performance were prepared. The hierarchical porosity was generated from the microporous zeolite coated at the surface of diatom frustules and from the macroporous diatomite support. A facile NaOH etching method was employed for the first time to treat the frustule support, followed by hydrothermal growth of MFI-type zeolite at the surface of frustules previously seeded with nanocrystalline silicalite-1 (Sil-1). NaOH etching enlarged the pores on diatom frustules and further increased the coated zeolite contents (W(z)). The central macropore size of the diatom frustules increased from approximately 200-500 nm to 400-1000 nm after NaOH etching. The W(z) could reach 61.2%, while the macroporosity of the composites was largely preserved due to more voids for zeolite coating being formed by NaOH etching. The Dt/Z composites exhibited higher benzene adsorption capacity per unit mass of zeolite and less mass transfer resistance than Sil-1, evaluated via a method of breakthrough curves. These results demonstrate that etching of a diatomite support is a facile but crucial process for the preparation of Dt/Z composites, enabling the resulting composites to become promising candidates for uses in volatile organic compounds emission control. Copyright © 2014 Elsevier B.V. All rights reserved.