Energy Technology Data Exchange (ETDEWEB)
Public Law 95-209 includes a requirement that the Advisory Committee on Reactor Safeguards submit an annual report to Congress on the safety research program of the Nuclear Regulatory Commission. This report presents the results of the ACRS review and evaluation of the NRC safety research program for Fiscal Year 1983. The report contains a number of comments and recommendations.
1982-02-01
Energy Technology Data Exchange (ETDEWEB)
Public Law 95-209 includes a requirement that the Advisory Committee on Reactor Safeguards submit an annual report to Congress on the safety research program of the Nuclear Regulatory Commission. This report presents the results of the ACRS review and evaluation of the NRC safety research program for Fiscal Year 1982. The report contains a number of comments and recommendations.
1981-02-01
Role of FFTF in assessing structural feedbacks and inherent safety of LMR's
International Nuclear Information System (INIS)
The possibility of developing reactor designs with inherent safety characteristics sufficient to provide walk away safety is receiving additional emphasis in the LMR program. A key element in this effort is the recognition that LMR's possess safety characteristics above and beyond those employed in past safety review processes. Some of these additional safety characteristics are due to reactivity feedback effects caused by small structural movements during hypothetical severe design transients. The effects of these characteristics upon the behavior of the FFTF under such transients has been assessed and is discussed in this paper. The paper also presents a preliminary test matrix which might allow experimental verification of the structural reactivity feedback effects. Such experimental verification should be very useful to innovative ...
1985-07-01
Role of FFTF in assessing structural feedbacks and inherent safety of LMR's
International Nuclear Information System (INIS)
The possibility of developing reactor designs with inherent safety characteristics sufficient to provide ''walk away'' safety is receiving additional emphasis in the LMR program. A key element in this effort is the recognition that LMR's possess safety characteristics above and beyond those employed in past safety review processes. Some of these additional safety characteristics are due to reactivity feedback effects caused by small structural movements during hypothetical severe design transients. The effect of these characteristics upon the behavior of the FFTF under such transients has been assessed and is discussed in this paper. The paper also presents a preliminary test matrix which might allow experimental verification of the structural reactivity feedback effects. Such experimental verification should be very useful to innovative ...
1985-04-21
Energy Technology Data Exchange (ETDEWEB)
To address the potential threat that suspect/counterfeit parts could pose to DOE workers and the public, the Office of the Deputy Assistant Secretary for Oversight initiated a number of activities beginning in mid-1995. Oversight placed increased emphasis on the field`s quality assurance-suspect/counterfeit parts programs during safety management evaluations, in keeping with the Office of Environment, Safety and Health (EH) oversight responsibilities, which include oversight of the Department`s quality assurance (QA) programs. In addition, Oversight reviewed relevant policy documents and occurrence reports to determine the nature and magnitude of the problem within the Department. The results of that review, contained in an Office of Oversight report, Independent Oversight Analysis of Suspect/Counterfeit Parts Within the Department of Energy (November 1995), ...
1996-05-01
Energy Technology Data Exchange (ETDEWEB)
The Department of Energy (DOE) policy requires that all activities be conducted in a manner that protects the safety of the public and provides a safe and healthful workplace for employees. DOE has also prescribed that all personnel be protected in any explosives operation undertaken. The level of safety provided shall be at least equivalent to that of the best industrial practice. The risk of death or serious injury shall be limited to the lowest practicable minimum. DOE and contractors shall continually review their explosives operations with the aim of achieving further refinements and improvements in safety practices and protective features. This manual describes the Department's explosive safety requirements applicable to operations involving the development, testing, handling, and processing of explosives or assemblies containing explosives. It is intended to reflect ...
1990-05-01
Energy Technology Data Exchange (ETDEWEB)
This is the seventh report by the Advisory Committee on Reactor Safeguards (ACRS) in response to the Congressional requirement for an annual report on the Nuclear Regulatory Commission (NRC) Reactor Safety Research Program. As previously requested by the Congress, the timing of this report has been adjusted to enable the ACRS to address the proposed budget for FY 1985 that has been submitted to the Congress by the President. Part I is a compilation of our comments and recommendations regarding the NRC Safety Research Program budget for FY 1985. It is intended to serve as an Executive Summary. Part II is divided into eight chapters, each of which represents a Decision Unit of the NRC research program. In each chapter, specific comments are included on the research involved in the Decision Unit, an assessment of priorities, and recommendations regarding new directions and levels of ...
1984-02-01
Energy Technology Data Exchange (ETDEWEB)
This is the sixth report by the Advisory Committee on Reactor Safeguards (ACRS) that has been prepared in response to the Congressional requirement for an annual report on the Nuclear Regulatory Commission (NRC) Reactor Safety Research Program. Part I is a compilation of our general comments and recommendations regarding the NRC Safety Research Program, and includes budget recommendations and an identification of matters of special importance that deserve increased emphasis. It is intended to serve as an Executive Summary. Part II is divided into ten chapters, each of which represents a Decision Unit of the NRC research program. In each chapter, specific comments are included on the research involved in the Decision Unit, an assessment of priorities, and recommendations regarding new directions and levels of funding.
1983-02-01
Energy Technology Data Exchange (ETDEWEB)
The Department of Energy (DOE) policy requires that all DOE activities be conducted in a manner that protects the safety of the public and provides a safe and healthful workplace for employees. DOE has also prescribed that all personnel be protected in any explosives operation undertaken. The level of safety provided shall be at least equivalent to that of the best industrial practice. The risk of death or serious injury shall be limited to the lowest practicable minimum. DOE and contractors shall continually review their explosives operations with the aim of achieving further refinements and improvements in safety practices and protective features. This manual describes the Department's explosive safety requirements applicable to operations involving the development, testing, handling, and processing of explosives or assemblies containing explosives. It is intended to ...
1991-10-01
International Nuclear Information System (INIS)
Due to current social and economical framework, in last years many nuclear power plant owners started a program for the Long Term Operation (LTO)/PLIM (Plant Life Management) of their older nuclear facilities. PLIM/PLEX has already been implemented in many countries (USA, Russia, etc.). This process has many nuclear safety implications, other than strategic and political ones. The need for tailoring the available safety assessment tools to such applications has become urgent in recent years and triggered many research actions. In particular, a PLIM framework requires both a detailed review of the features of the main safety programs (Maintenance, ISI, Surveillance) and a complete integration of these programs into the general management system of the plant. New external factors, such as: large use of subcontractors, need for efficient ...
2007-10-15
Energy Technology Data Exchange (ETDEWEB)
This is the eighth report by the Advisory Committee on Reactor Safeguards (ACRS) that has been prepared in response to the Congressional requirement for an annual report on the Nuclear Regulatory Commission (NRC) Reactor Safety Research Program. As previously requested by the Congress, the timing of this report has been adjusted to enable the ACRS to address the proposed budget for FY 1986 and 1987 that has been submitted to the Congress by the President. Detailed comments and recommendations are provided for the research programs and budget proposed for FY 1986. Because both the budget for FY 1987 and the research programs for that period are highly uncertain at this time, comments on these are not provided. Part I is a compilation of general comments and recommendations regarding the NRC Safety Research Program budget for FY 1986. It is intended to serve as ...
1985-02-01
A study for good regulation of the CANDU's in Korea
Energy Technology Data Exchange (ETDEWEB)
The objective of project is to derive the policy recommendations to improve the efficiency of CANDU plants regulation. These policy recommendations will eventually contribute to the upgrading of Korean nuclear regulatory system and safety enhancement. During the second phase of this 2 years study, following research activities were done. Review the technical basis and framework of the new Canadian Regulation System and IAEA. Analysis on the interview of Wolsung operation staffs to identify important safety issues and regulation problems experienced at operation. Providing a plan of CANDU regulation system enhancement program.
2002-03-15
Comments on the NRC safety research program budget for fiscal year 1982
Energy Technology Data Exchange (ETDEWEB)
Recommendations of the Advisory Committee on Reactor Safeguards are presented to the Commissioners for their consideration for FY 82 budget for the NRC safety research program.
1980-07-01
Comments on the NRC safety research program budget for Fiscal Year 1983
Energy Technology Data Exchange (ETDEWEB)
Recommendations of the Advisory Committee on Reactor Safeguards are presented to the Commissioners for their consideration for FY 83 budget for the NRC safety research program.
1981-07-01
Energy Technology Data Exchange (ETDEWEB)
This report is the first of four volumes that identify and assess the environmental, health, and safety issues involved in using sodium-sulfur (Na/S) battery technology as the energy source in electric and hybrid vehicles that may affect the commercialization of Na/S batteries. This and the other reports on recycling, shipping, and vehicle safety are intended to help the Electric and Hybrid Propulsion Division of the Office of Transportation Technologies in the US Department of Energy (DOE/EHP) determine the direction of its research, development, and demonstration (RD&D) program for Na/S battery technology. The reports review the status of Na/S battery RD&D and identify potential hazards and risks that may require additional research or that may affect the design and use of Na/S batteries. This volume covers cell design and engineering as the basis of safety for Na/S ...
1992-09-01
Licensing experiences of safety critical software systems in nuclear applications a case study
Energy Technology Data Exchange (ETDEWEB)
This paper summarizes results of reviews on the safety, critical software performed during the licensing process for the new Wolsung units. Each of these CANDU-type nuclear power plants has two micro-computerized shutdown systems. The SDS No. 1 program is graphically programmed in such a manner that its development process does not essentially differ from the design process of the conventional analog counterpart. This approach is understandable even to a reviewer in the regulatory agency without additional training in software engineering. The confidence in the reliability of this system is strengthened by the reverse verification and increased by extensive testing such as the reliability test. Concerning SDS No. 2, the development process is significantly influenced by the {open_quotes}software cost reduction project{close_quotes} of the U.S. naval research laboratory, and is, as a ...
1997-12-01
Licensing experiences of safety critical software systems in nuclear applications a case study
International Nuclear Information System (INIS)
This paper summarizes results of reviews on the safety, critical software performed during the licensing process for the new Wolsung units. Each of these CANDU-type nuclear power plants has two micro-computerized shutdown systems. The SDS No. 1 program is graphically programmed in such a manner that its development process does not essentially differ from the design process of the conventional analog counterpart. This approach is understandable even to a reviewer in the regulatory agency without additional training in software engineering. The confidence in the reliability of this system is strengthened by the reverse verification and increased by extensive testing such as the reliability test. Concerning SDS No. 2, the development process is significantly influenced by the software cost reduction project of the U.S. naval research laboratory, and is, as a whole, clear and well ...
1997-06-01
Assessment of the PIUS physics and thermal-hydraulic experimental data bases
Energy Technology Data Exchange (ETDEWEB)
The PIUS reactor utilizes simplified, inherent, passive, or other innovative means to accomplish safety functions. Accordingly, the PIUS reactor is subject to the requirements of 10CFR52.47(b)(2)(i)(A). This regulation requires that the applicant adequately demonstrate the performance of each safety feature, interdependent effects among the safety features, and a sufficient data base on the safety features of the design to assess the analytical tools used for safety analysis. Los Alamos has assessed the quality and completeness of the existing and planned data bases used by Asea Brown Boveri to validate its safety analysis codes and other relevant data bases. Only a limited data base of separate effect and integral tests exist at present. This data base is not adequate to fulfill the requirements of 10CFR52.47(b)(2)(i)(A). Asea Brown Boveri has stated that it ...
1993-12-31
Environmental, health, and safety issues of sodium-sulfur batteries for electric and hybrid vehicles
Energy Technology Data Exchange (ETDEWEB)
This report is the first of four volumes that identify and assess the environmental, health, and safety issues involved in using sodium-sulfur (Na/S) battery technology as the energy source in electric and hybrid vehicles that may affect the commercialization of Na/S batteries. This and the other reports on recycling, shipping, and vehicle safety are intended to help the Electric and Hybrid Propulsion Division of the Office of Transportation Technologies in the US Department of Energy (DOE/EHP) determine the direction of its research, development, and demonstration (RD D) program for Na/S battery technology. The reports review the status of Na/S battery RD D and identify potential hazards and risks that may require additional research or that may affect the design and use of Na/S batteries. This volume covers cell design and engineering as the basis of safety for Na/S batteries and ...
1992-09-01
International Nuclear Information System (INIS)
This paper begins with an introduction to Guangdong Daya Bay Nuclear Power Station (GNPS) and gives a simple introduction to the operations and maintenance documentation system at GNPS. It then will review the maintenance program guidelines base and the associated problems prior to the application of reliability centered maintenance (RCM). How RCM was implemented at GNPS, how the results of RCM analysis were used to optimize the maintenance program and test program, and what is the interface between RCM and the existing maintenance program will be shown. Next, it will show the successful implementation of RCM at GNPS resulted in the following changes: A new understanding of equipment failure challenges operations and maintenance beliefs, maintenance concepts undergo a large change, maintenance program and periodic testing program are ...
2003-12-01
Tiger Team assessment of the Brookhaven National Laboratory
Energy Technology Data Exchange (ETDEWEB)
This report documents the results of the Department of Energy's (DOE's) Tiger Team Assessment conducted at Brookhaven National Laboratory (BNL) in Upton, New York, between March 26 and April 27, 1990. The BNL is a multiprogram laboratory operated by the Associated Universities, Inc., (AUI) for DOE. The purpose of the assessment was to provide the status of environment, safety, and health (ES H) programs at the laboratory. The scope of the assessment included a review of management systems and operating procedures and records; observations of facility operations; and interviews at the facilities. Subteams in four areas performed the review: ES H, Occupational Safety and Health, and Management and Organization. The assessment was comprehensive, covering all areas of ES H activities and waste management operations. Compliance with applicable Federal, State, and local ...
1990-06-01
Resolution of key safety-related issues in FFTF regulatory review
International Nuclear Information System (INIS)
The FFTF is an ERDA facility which does not require licensing, but a technical review by NRC is required by ERDA policy. Safety issues which were not fully resolved in the course of the review for construction authorization have been the subject of continuing review since mid-1973. These issues included HCDA energetics, design fallback provisions for additional safety margins, piping integrity, and natural circulation core cooling.
Savannah River Site production reactor safety analysis report. K production reactor
International Nuclear Information System (INIS)
Nuclear facilities of the Department of Energy (DOE) located at the Savannah River Site must comply with DOE orders as implemented at DOE-SR. The DOE orders cover safety criteria, design criteria, environmental protection, occupational health and safety. The program applies to DOE and contractors. In this section, the Nuclear Regulatory Commission (NRC) criteria and industry codes and standards are addressed as well as DOE orders. Specific DOE orders which add additional criteria have also been noted. A program for assessing and implementing contractor applicable DOE orders has been established. This program ensures that compliance is achieved through developing and implementing policies, programs, and procedures. The primary emphasis is placed on safe, efficient reactor restart and operation. DOE has classified orders applicable to restart as Level I, Category ...
PNNL FY2005 DOE Voluntary Protection Program (VPP) Program Evaluation
Energy Technology Data Exchange (ETDEWEB)
This document reports the results of the FY 2005 PNNL VPP Program Evaluation, which is a self-assessment of the operational and programmatic performance of the Laboratory related to worker safety and health. The report was compiled by a team of worker representatives and safety professionals who evaluated the Laboratory's worker safety and health programs on the basis of DOE-VPP criteria. The principle elements of DOE's VPP program are: Management Leadership, Employee Involvement, Worksite Analysis, Hazard Prevention and Control, and Safety and Health Training.
2005-01-31
Energy Technology Data Exchange (ETDEWEB)
The five thermal-hydraulic concepts chosen for advanced PWR have been studied as follows: (1) Critical Heat Flux: Review of previous works, analysis of parametric trends, analysis of transient CHF characteristics, extension of the CHF date bank, survey and assessment of correlations, design of a intermediate-pressure CHF test loop have been performed. (2) Passive Cooling Concepts for Concrete Containment system: Review of condensation phenomena with noncondensable gases, selection of a promising concept (i.e., use of external condensers), design of test loop according to scaling laws have been accomplished. and computer programs based on the control-volume approach, and the conceptual design of test loop have been accomplished. (4) Fluidic Diode Concepts: Review of previous applications of the concept, analysis major parameters affecting the performance, development of a computational code, and ...
1995-08-01
International Nuclear Information System (INIS)
This paper will review code and standard and the safety related features of major components of Monju: Components of the Reactor Coolant Boundary; Components of the Reactor Shurdown Systems; Components of the Decay Heat Removal Systems; Components of the Engineered Safety Features; Other Safety Related Components. Their relationship to the system or plant function is emphasized, in reviewing these components.
1982-07-01
Geothermal progress monitor. Special supplement: proceedings of the geothermal program review
Energy Technology Data Exchange (ETDEWEB)
Separate abstracts were prepared for individual papers. (MHR)
1982-01-01
Strategic principles workshops: Discussion drafts and workshop notes
Energy Technology Data Exchange (ETDEWEB)
The Office of Civilian Radioactive Waste-Management in the Department of Energy (DOE) is responsible for disposing of this nation`s spent fuel and high-level radioactive waste in a manner that protects the health and safety of the public and the quality of the environment. Although embodied in the Federal repository program that began with studies in the late 1950s, this mission was explicitly established by the Nuclear Waste Policy Act of 1982 and reaffirmed by the Nuclear Waste Policy Amendments Act of 1987. To fulfill our mission, we are developing a waste management system consisting of a geologic repository for permanent disposal deep beneath the surface of the earth, a facility for monitored retrievable storage, and a system for transporting the waste. This discussion draft was developed to help involve parties affected by or interested in the waste-management program in the formulation of the basic principles on ...
1991-09-01
UNITED STATES DEPARTMENT OF ENERGY WASTE PROCESSING ANNUAL TECHNOLOGY DEVELOPMENT REPORT 2007
Energy Technology Data Exchange (ETDEWEB)
The Office of Environmental Management's (EM) Roadmap, U.S. Department of Energy--Office of Environmental Management Engineering & Technology Roadmap (Roadmap), defines the Department's intent to reduce the technical risk and uncertainty in its cleanup programs. The unique nature of many of the remaining facilities will require a strong and responsive engineering and technology program to improve worker and public safety, and reduce costs and environmental impacts while completing the cleanup program. The technical risks and uncertainties associated with cleanup program were identified through: (1) project risk assessments, (2) programmatic external technical reviews and technology readiness assessments, and (3) direct site input. In order to address these needs, the technical risks and uncertainties were compiled and divided into the ...
2008-08-12
Labor market trends for nuclear engineers through 2000
Energy Technology Data Exchange (ETDEWEB)
Throughout most of the 1980s, both private organizations and government agencies were concerned about the availability of an adequate supply of qualified nuclear engineers. This concern was primarily the result of a number of nuclear engineering academic programs being eliminated coupled with a continuous decline in graduate and undergraduate enrollments and degrees. By the early 1990s, the number of degrees and available supply had declined to new lows, but cutbacks in funding for the nuclear weapons program and nuclear energy R&D, and in hiring by the electric utility industry, offset in large measure the declining supply. Recently, concerns about environment and waste management and about nuclear safety have again generated questions about the adequacy of supply of qualified personnel for nuclear energy activities. This report briefly examines the nuclear engineering labor market. Trends in employment, new graduates, ...
1995-01-01
A study to develop the domestic functional requirements of the specific safety systems of CANDU
Energy Technology Data Exchange (ETDEWEB)
The present research has been made to develop and review critically the functional requirements of the specific safety systems of CANDU such as SDS-1, SDS2, ECCS, and containment. Based on R documents for this, a systematic study was made to develop the domestic regulation statements. Also, the conventional laws are carefully reviewed to see the compatibility to CANDU. Also, the safety assessment method for CANDU was studied by reviewing C documents and recommendation of IAEA. Through the present works, the vague policy in the CANDU safety regulation is cleaning up in a systematic form and a new frame to measure the objective risk of nuclear power plants was developed.
2003-03-15
A study to develop the domestic functional requirements of the specific safety systems of CANDU
Energy Technology Data Exchange (ETDEWEB)
The present research has been made to develop and review critically the functional requirements of the specific safety systems of CANDU such as SOS-1, SOS-2, ECCS and containment. Based on R documents for this, a systematic study was made to develop the domestic regulation statements. Also, the conventional laws are carefully reviewed to see the compatibility to CANDU. Also, the safety assessment method for CANDU was studied by reviewing C documents and recommendation of IAEA. Through the present works, the vague policy in the CANDU safety regulation is cleaning up in a systematic form and a new frame to measure the objective risk of nuclear power plants was developed.
2001-03-15
Safe ageing management of nuclear power plants: An European synthesis
International Nuclear Information System (INIS)
Ageing of nuclear power plants means evolution of material or equipment properties on one side, and evolution of personnel skill and procedure adequacy on the other side, both of which, after a certain time, may not be compatible with the required safety provisions, or with an economic operation of the plant. Repair or replacement of components, as well as change in service conditions for a better compatibility with component reduced capabilities can be used to mitigate ageing effects. The paper summarises the results of a study conducted in this field with the support of the European Commission. It presents: the synthesis of the work done under international auspices, and in the European context; the comparison of ageing management approaches used in several European countries with international recommendations; the summary of the various potential phenomena and their governing parameters, the methods of in-service ageing identification and possible mitigation ...
2002-11-04
Routine environmental audit of the Y-12 Plant, Oak Ridge, Tennessee
Energy Technology Data Exchange (ETDEWEB)
This report documents the results of the routine environmental audit of the Oak Ridge Y-12 Plant (Y-12 Plant), Anderson County, Tennessee. During this audit, the activities conducted by the audit team included reviews of internal documents and reports from previous audits and assessments; interviews with U.S. Department of Energy (DOE), State of Tennessee regulatory, and contractor personnel; and inspections and observations of selected facilities and operations. The onsite portion of the audit was conducted August 22-September 2, 1994, by the DOE Office of Environmental Audit (EH-24), located within the Office of Environment, Safety and Health (EH). DOE 5482.1 B, {open_quotes}Environment, Safety, and Health Appraisal Program,{close_quotes} establishes the mission of EH-24 to provide comprehensive, independent oversight of DOE environmental programs on behalf of the Secretary of ...
1994-09-01
Review of the Vortec soil remediation demonstration program
Energy Technology Data Exchange (ETDEWEB)
The principal objective of the METC/Vortec program is to develop and demonstrate the effectiveness of the Vortec CMS in remediating soils contaminated with hazardous materials and/or low levels of radionuclides. To convincingly demonstrate the CMS`s capability, a Demonstration Plant will be constructed and operated at a DOE site that has a need for the remediation of contamination soil. The following objectives will be met during the program: (1) establish the glass chemistry requirements to achieve vitrification of contaminated soils found at the selected DOE site; (2) complete the design of a fully integrated soil vitrification demonstration plant with a capacity to process 25 TPD of soil; (3) establish the cost of a fully integrated soil demonstration plant with a capacity to process 25 TPD of soil; (4) construct and operate a fully integrated demonstration plant; (5) analyze all influent and effluent streams to establish the partitioning of ...
1994-12-31
Radioactive waste management in the USSR: A review of unclassified sources. Volume 2
Energy Technology Data Exchange (ETDEWEB)
The Soviet Union does not currently have an overall radioactive waste management program or national laws that define objectives, procedures, and standards, although such a law is being developed, according to the Soviets. Occupational health and safety does not appear to receive major attention as it does in Western nations. In addition, construction practices that would be considered marginal in Western facilities show up in Soviet nuclear power and waste management operations. The issues involved with radioactive waste management and environmental restoration are being investigated at several large Soviet institutes; however, there is little apparent interdisciplinary integration between them, or interaction with the USSR Academy of Sciences. It is expected that a consensus on technical solutions will be achieved, but it may be slow in coming, especially for final disposal of high-level radioactive wastes and environmental restoration of ...
1991-03-01
Radioactive waste management in the USSR: A review of unclassified sources
Energy Technology Data Exchange (ETDEWEB)
The Soviet Union does not currently have an overall radioactive waste management program or national laws that define objectives, procedures, and standards, although such a law is being developed, according to the Soviets. Occupational health and safety does not appear to receive major attention as it does in Western nations. In addition, construction practices that would be considered marginal in Western facilities show up in Soviet nuclear power and waste management operations. The issues involved with radioactive waste management and environmental restoration are being investigated at several large Soviet institutes; however, there is little apparent interdisciplinary integration between them, or interaction with the USSR Academy of Sciences. It is expected that a consensus on technical solutions will be achieved, but it may be slow in coming, especially for final disposal of high-level radioactive wastes and environmental restoration of ...
1991-03-01
Energy Technology Data Exchange (ETDEWEB)
The Seabed Disposal Project (SDP) was evaluating the technical feasibility of high-level nuclear waste disposal in deep ocean sediments. Working standards were needed for risk assessments, evaluation of alternative designs, sensitivity studies, and conceptual design guidelines. This report completes a three part program to develop radiological standards for the feasibility phase of the SDP. The characteristics of subseabed disposal and how they affect the selection of standards are discussed. General radiological protection standards are reviewed, along with some new methods, and a systematic approach to developing standards is presented. The selected interim radiological standards for the SDP and the reasons for their selection are given. These standards have no legal or regulatory status and will be replaced or modified by regulatory agencies if subseabed disposal is implemented. 56 refs., 29 figs., 15 tabs.
1997-06-01
Energy Technology Data Exchange (ETDEWEB)
Under 10CFR50 Appendix B, utilities have a commitment to establish and maintain material control programs to assure the safety and reliability of their power plants. The guidelines in this report discuss methods of establishing, maintaining, and extending the shelf life of limited life items. In addition, these guidelines establish justifiable shelf lives for a sample of 70 items and review the effects of environmental conditions. Moreover, the guidelines are consistent with utility qualification test documentation and provide for evaluation of items with expired shelf lives. These guidelines set precedent by indicating that the shelf life is greater than previously available for many items. This increase in shelf life has been established through natural and accelerated aging tests.
1992-05-01
Class 1E digital systems studies
International Nuclear Information System (INIS)
This document is furnished as part of the effort to develop NRC Class 1E Digital Computer Systems Guidelines which is Task 8 of USAF Rome Laboratories Contract F30602-89-D-0100. The report addresses four major topics, namely, computer programming languages, software design and development, software testing and fault tolerance and fault avoidance. The topics are intended as stepping stones leading to a Draft Regulatory Guide document. As part of this task a small scale survey of software fault avoidance and fault tolerance practices was conducted among vendors of nuclear safety related systems and among agencies that develop software for other applications demanding very high reliability. The findings of the present report are in part based on the survey and in part on review of software literature relating to nuclear and other critical installations, as well as on the authors' experience in these areas.
A compilation of reports of the Advisory Committee on Reactor Safeguards: 1995 annual. Volume 17
Energy Technology Data Exchange (ETDEWEB)
This compilation contains 44 ACRS reports submitted to the Commission, or to the Executive Director for Operations, during calendar year 1995. It also includes a report to the Congress on the NRC Safety Research Program. All reports have been made available to the public through the NRC Public Document Room and the US Library of Congress. The reports are divided into two groups: Part 1: ACRS Reports on Project Reviews, and Part 2: ACRS Reports on Generic Subjects. Part 1 contains ACRS reports by project name and by chronological order within project name. Part 2 categorizes the reports by the most appropriate generic subject area and by chronological order within subject area.
1996-04-01
A compilation of reports of the Advisory Committee on Reactor Safeguards: 1992 Annual. Volume 14
Energy Technology Data Exchange (ETDEWEB)
This compilation contains 50 ACRS reports submitted to the Commission, Executive Director for Operations, or to the Office of Nuclear Regulatory Research, during calendar year 1992. It also includes a report to the Congress on the NRC Safety Research Program. All reports have been made available to the public through the NRC Public Document Room and the US Library of Congress. The reports are divided into two groups: Part 1: ACRS Reports on Project Reviews, and Part 2: ACRS Reports on Generic Subjects. Part I contains ACRS reports alphabetized by project name and by chronological order within project name. Part 2 categorizes the reports by the most appropriate generic subject area and by chronological order within subject area.
1993-04-01
A compilation of reports of the Advisory Committee on Reactor Safeguards: 1992 Annual
Energy Technology Data Exchange (ETDEWEB)
This compilation contains 50 ACRS reports submitted to the Commission, Executive Director for Operations, or to the Office of Nuclear Regulatory Research, during calendar year 1992. It also includes a report to the Congress on the NRC Safety Research Program. All reports have been made available to the public through the NRC Public Document Room and the US Library of Congress. The reports are divided into two groups: Part 1: ACRS Reports on Project Reviews, and Part 2: ACRS Reports on Generic Subjects. Part I contains ACRS reports alphabetized by project name and by chronological order within project name. Part 2 categorizes the reports by the most appropriate generic subject area and by chronological order within subject area.
1993-04-01
A compilation of reports of the Advisory Committee on Reactor Safeguards: 1991 annual. Volume 13
Energy Technology Data Exchange (ETDEWEB)
This compilation contains 41 Advisory Committee on Reactor Safeguards (ACRS) reports submitted to the Commission, Executive Director for Operations, or to the Office of Nuclear Regulatory Research, during calendar year 1991. It also includes a report to the Congress on the NRC Safety Research Program. All reports have been made available to the public through the NRC Public Document Room and the US Library of Congress. The reports are divided into two groups: Part 1: ACRS Reports on Project Reviews, and Part 2: ACRS Reports on Generic Subjects. Part 1 contains ACRS reports alphabetized by project name and by chronological order within project name. Part 2 categorizes the reports by the most appropriate generic subject area and by chronological order within subject area.
1992-04-01
A compilation of reports of the Advisory Committee on Reactor Safeguards: 1991 annual
Energy Technology Data Exchange (ETDEWEB)
This compilation contains 41 Advisory Committee on Reactor Safeguards (ACRS) reports submitted to the Commission, Executive Director for Operations, or to the Office of Nuclear Regulatory Research, during calendar year 1991. It also includes a report to the Congress on the NRC Safety Research Program. All reports have been made available to the public through the NRC Public Document Room and the US Library of Congress. The reports are divided into two groups: Part 1: ACRS Reports on Project Reviews, and Part 2: ACRS Reports on Generic Subjects. Part 1 contains ACRS reports alphabetized by project name and by chronological order within project name. Part 2 categorizes the reports by the most appropriate generic subject area and by chronological order within subject area.
1992-04-01
A compilation of reports of the Advisory Committee on Reactor Safeguards: 1989 annual
Energy Technology Data Exchange (ETDEWEB)
This compilation contains 54 ACRS reports submitted to the Commission or to the Executive Director for Operations during calendar year 1989. It also includes a report to the Congress on the NRC Safety Research Program. All reports have been made available to the public through the NRC Public Document Room and the US Library of Congress. The reports are divided into two groups: Part 1 -- ACRS Reports on Project Reviews, and Part 2 -- ACRS Reports on Generic Subjects. Part 1 contains ACRS reports alphabetized by project name and within project name by chronological order. Part 2 categorizes the reports by the most appropriate generic subject area and within subject area by chronological order.
1990-04-01
A compilation of reports of the Advisory Committee on Reactor Safeguards: 1988 annual
Energy Technology Data Exchange (ETDEWEB)
This compilation contains 47 ACRS reports submitted to the Commission or to the Executive Director for Operations during calendar year 1988. It also includes a report to the Congress on the NRC Safety Research Program. All reports have been made available to the public through the NRC Public Document Room and the US Library of Congress. The reports are divided into two groups: Part 1, ACRS Reports on Project Reviews, and Part 2, ACRS Reports on Generic Subjects. Part 1 contains ACRS reports alphabetized by project name and within project name by chronological order. Part 2 categorizes the reports by the most appropriate generic subject area and within subject area by chronological order. 136 refs., 1 tab.
1989-04-01
A compilation of reports of the Advisory Committee on Reactor Safeguards: 1987 annual
Energy Technology Data Exchange (ETDEWEB)
This compilation contains 47 ACRS reports submitted to the Commission or to the Executive Director for Operations during calendar year 1987. It also includes a report to the Congress on the NRC Safety Research Program for FY 1988. All reports have been made available to the public through the NRC Public Document Room and the US Library of Congress. The reports are divided into two groups: Part 1: ACRS Reports on Project Reviews, and Part 2: ACRS Reports on Generic Subjects. Part 1 contains ACRS reports alphabetized by project name and within project name by chronological order. Part 2 categorizes the reports by the most appropriate generic subject area and within subject area by chronological order.
1988-04-01
A compilation of reports of the Advisory Committee on Reactor Safeguards, 1990 annual
Energy Technology Data Exchange (ETDEWEB)
This compilation contains 31 Advisory Committee on Reactor Safeguards (ACRS) reports submitted to the Commission or to the Executive Director for Operations during calendar year 1990. It also includes a report to the Congress on the NRC Safety Research Program. All reports have been made available to the public through the NRC Public Document Room and the US Library of Congress. The reports are divided into two groups: Part 1: ACRS Reports on Project Reviews, and Part 2: ACRS Reports on Generic Subject. Part 1 contains ACRS reports alphabetized by project name and by chronological order within project name. Part 2 categorizes the reports by the most appropriate generic subject area and by chronological order within subject area.
1991-04-01
Recent Reviews in Carcinogenesis 1981.
Recent Reviews in Carcinogenesis is a service of the International Cancer Research Data Bank (ICRDB) Program of the National Cancer Institute, intended to facilitate and promote the exchange of information between cancer scientists. It contains abstracts ...
1982-01-01
Development of safety function assessment trees for pressurized heavy water reactor LP/SD operations
Energy Technology Data Exchange (ETDEWEB)
The objective of Configuration Risk Management Program(CRMP) is to maintain the safety level by assuring the defense-in-depth of nuclear power plant while the configurations are changed during plant operations, especially for the LP/SD. Such a safety purpose can be achieved by establishing the risk monitoring programs with both quantitative and qualitative features. Generally, the quantitative risk evaluation models, i.e., PRA models are used for the risk evaluation during full power operation, and the qualitative risk evaluation models such as safety function assessment trees are used. Through this study, safety function assessment trees were developed.
2003-10-01
Energy Technology Data Exchange (ETDEWEB)
The paper reviews the US Clean Coal Technology program, discussing some of the projects, before describing the Vision 21 program.
2000-07-01
Health, Safety, and Environment Division: Annual progress report 1987
Energy Technology Data Exchange (ETDEWEB)
The primary responsibility of the Health, Safety, and Environment (HSE) Division at the Los Alamos National Laboratory is to provide comprehensive occupational health and safety programs, waste processing, and environment protection. These activities are designed to protect the worker, the public, and the environment. Many disciplines are required to meet the responsibilities, including radiation protection, industrial hygiene, safety, occupational medicine, environmental science, epidemiology, and waste management. New and challenging health and safety problems arise occasionally from the diverse research and development work of the Laboratory. Research programs in HSE Division often stem from these applied needs. These programs continue but are also extended, as needed to study specific problems for the Department of Energy and to help ...
1988-04-01
Energy Technology Data Exchange (ETDEWEB)
This report for the Swiss Federal Office of Energy (SFOE) presents the overview reports made by SFOE Heads of Program on work done in 2007. Projects reported on in the natural gas-fired fuel cell area include the EU-project REAL-SFOC, the long-term testing of anode-supported SOFC stacks, intermediate-temperature fuel cells based on proton conducting electrolytes, the interdisciplinary ONEBAT project and lifetime-enhancement of SOFC stacks for CHP applications. In the polymer-electrolyte fuel cell (PEFC) area, projects concerning proton-conducting polymer membranes, factors limiting the lifetime of fuel cell membranes, a new highly active oxygen reduction electrode for PEM fuel cell and zinc/air battery applications, the enhancement of PEFC durability and reliability, model-based investigation of PEFC performance, and local gas analysis of PE fuel cells are briefly reported on. Long-term research activities in the hydrogen technology area reported on include those ...
2008-07-01
Development of LMFBR safety testing in FFTF
International Nuclear Information System (INIS)
The Fast Flux Test Facility (FFTF) will provide a prototypic test environment for advanced fuels and materials development within the U. S. LMFBR program. As a fast test reactor, the FFTF also provides a potentially unique capability for conduct of safety experimentation relevant to selected LMFBR safety issues associated with postulated core disruption events. The utility and feasibility of possible extension of FFTF testing into the area of safety research is being investigated. 5 fig.
1976-10-01
Survey of systems safety analysis methods and their application to nuclear waste management systems
Energy Technology Data Exchange (ETDEWEB)
This report reviews system safety analysis methods and examines their application to nuclear waste management systems. The safety analysis methods examined include expert opinion, maximum credible accident approach, design basis accidents approach, hazard indices, preliminary hazards analysis, failure modes and effects analysis, fault trees, event trees, cause-consequence diagrams, G0 methodology, Markov modeling, and a general category of consequence analysis models. Previous and ongoing studies on the safety of waste management systems are discussed along with their limitations and potential improvements. The major safety methods and waste management safety related studies are surveyed. This survey provides information on what safety methods are available, what waste management safety areas have been analyzed, and what ...
1981-11-01
UK PubMed Central (United Kingdom)
Telbivudine is a novel nucleoside drug recently approved for the treatment of patients with chronic hepatitis B. Its nonclinical safety was evaluated in a comprehensive program of studies, including...Full Text Available
2008-07-01
ADVANCED CUTTINGS TRANSPORT STUDY
Energy Technology Data Exchange (ETDEWEB)
This is the third quarterly progress report for Year 3 of the ACTS Project. It includes a review of progress made in: (1) Flow Loop construction and development and (2) research tasks during the period of time between Jan. 1, 2002 and Mar. 31, 2002. This report presents a review of progress on the following specific tasks: (a) Design and development of an Advanced Cuttings Transport Facility (Task 3: Addition of a Cuttings Injection/Separation System), (b) Research project (Task 6): ''Study of Cuttings Transport with Foam Under LPAT Conditions (Joint Project with TUDRP)'', (c) Research project (Task 9b): ''Study of Foam Flow Behavior Under EPET Conditions'', (d) Research project (Task 10): ''Study of Cuttings Transport with Aerated Mud Under Elevated Pressure and Temperature Conditions'', (e) Research on three instrumentation tasks to ...
2002-04-30
Performance Testing Methodology for Safety-Critical Programmable Logic Controller
International Nuclear Information System (INIS)
The Programmable Logic Controller (PLC) for use in Nuclear Power Plant safety-related applications is being developed and tested first time in Korea. This safety-related PLC is being developed with requirements of regulatory guideline and industry standards for safety system. To test that the quality of the developed PLC is sufficient to be used in safety critical system, document review and various product testings were performed over the development documents for S/W, H/W, and V/V. This paper provides the performance testing methodology and its effectiveness for PLC platform conducted by KOPEC
2009-05-01
Regulatory review of reactor physics design aspects of TAPP-3 and 4
International Nuclear Information System (INIS)
Atomic Energy Regulatory Board carries out the regulatory review of the reactor physics design, commissioning and operational aspects through Project Design Safety Committee and Specialist Group of reactor physicists with wide experience in the design, commissioning and operational safety review of NPPs. TAPP-3 and 4 PHWRs, being the first indigenous design of 540 MWe Units, are quite different than the standard 220 MWe PHWRs. The safety review of reactor physics design was quite complex, as majority of the systems were new. The Reactor Physics Specialist Group carried out extensive safety review of 540 MWe PHWR reactor physics design and made significant contributions of design modifications and improvements in the operational procedures. Some salient contributions include: Monitoring the core during bulk addition of ...
2006-11-13
NAVAIRSYSCOM Hazardous Material Safety Program
... C-3 ____ Page 21. NALIC-75189-30 Other Publications (Continued) NAVAIRINST 6260.1 -Chlorinated Solvents Instructions; for use of ...
1975-08-18
CDC - Men's Health A-Z - Workplace Safety and Health (Occupational...
Curriculums The Epilepsy Foundation, in partnership with CDC, is conducting a national education and outreach program to educate and train law enforcement officers, police...
2011-09-03
Suitability of permitted explosives and sheathed explosives for blasting in mines
Energy Technology Data Exchange (ETDEWEB)
This paper discusses use of chemical explosives for blasting in underground coal mines endangered by methane, and reviews safety regulations on blasting in mines endangered by methane in Poland. Results of tests carried out by the Institute for Mine Safety of the Central Mining Institute in Katowice are reviewed. The following types of explosives were tested: the L permitted Barbaryt, the FGH2 permitted Barbaryt, the D6G permitted Metanit, the D5G permitted Metanit, the W2AG permitted Metanit, the CG sheathed permitted Metanit. Test results are given in a table and 2 diagrams. Comparative evaluations show that the CG sheathed permitted Metanit and the W2AG permitted metanit are superior to other explosives. Methods for evaluating safety of explosives for blasting in coal mines endangered by methane are reviewed. Indices characterizing safety ...
1983-11-01
CANDU licensing in Korea : status review and future requirements
International Nuclear Information System (INIS)
The licensing status and procedures, regulatory framework, and current safety issues of CANDU type reactors, Wolsong units 2, 3 and 4 are examined. Licensing difficulties and lessons learned during the safety review of Wolsong 2, 3 and 4 and future requirements are also summarized. The review was conducted, not only to confirm the design adequacy with respect to the domestic atomic laws and regulatory requirements of the vendor country, Canada, but also to reflect into the design the lessons learned from the regulatory experiences of operating Wolsong I to enhance the safety as high as practically possible. Safety issues observed during the licensing review, such as containment integrity, fuel channel integrity, etc., are summarized. Several efforts have been conducted to harmonize the Canadian regulations with the Korean ones by ...
1998-05-03
Hot Cell Facility (HCF) Safety Analysis Report
Energy Technology Data Exchange (ETDEWEB)
This Safety Analysis Report (SAR) is prepared in compliance with the requirements of DOE Order 5480.23, Nuclear Safety Analysis Reports, and has been written to the format and content guide of DOE-STD-3009-94 Preparation Guide for U. S. Department of Energy Nonreactor Nuclear Safety Analysis Reports. The Hot Cell Facility is a Hazard Category 2 nonreactor nuclear facility, and is operated by Sandia National Laboratories for the Department of Energy. This SAR provides a description of the HCF and its operations, an assessment of the hazards and potential accidents which may occur in the facility. The potential consequences and likelihood of these accidents are analyzed and described. Using the process and criteria described in DOE-STD-3009-94, safety-related structures, systems and components are identified, and the important safety functions of each SSC are described. Additionally, ...
2000-11-01
Selection of detailed items for periodic safety review on PWR radwaste management system
International Nuclear Information System (INIS)
Selection of detailed-items for Periodic Safety Review on PWR radwaste management system, the main component could be faithfully clarified according to the purpose of establishment on each system and basic purpose. It is proper to select detailed-items those of radioactivities in the reactor coolant activity levels and the released volume of liquid and gaseous radioactive material on safety performance. It's also proper to select solid radwaste production quantities as detailed-item that it would be predict the next ten years trends after PSR.
2003-10-01
Safety review of conceptual fusion power plants
The potential public safety impacts from accidents in conceptual fusion power plants were investigated. Fusion was found to have some potential for accidents, as does any energy generating system. Functions of fusion power plants were identified that possess sufficient potential for an accidental release of toxic materials to the environment. An assessment was made of the impact of the potential accidents and recommendations are included for R and D that will allow incorporation of safety concerns in fusion power plant design. This work was based on a review of information available in conceptual design documents of fusion reactor systems.
1976-11-01
Safety review of conceptual fusion power plants
International Nuclear Information System (INIS)
The potential public safety impacts from accidents in conceptual fusion power plants were investigated. Fusion was found to have some potential for accidents, as does any energy generating system. Functions of fusion power plants were identified that possess sufficient potential for an accidental release of toxic materials to the environment. An assessment was made of the impact of the potential accidents and recommendations are included for R and D that will allow incorporation of safety concerns in fusion power plant design. This work was based on a review of information available in conceptual design documents of fusion reactor systems.
Plutonium Finishing Plant safety evaluation report
Energy Technology Data Exchange (ETDEWEB)
The Plutonium Finishing Plant (PFP) previously known as the Plutonium Process and Storage Facility, or Z-Plant, was built and put into operation in 1949. Since 1949 PFP has been used for various processing missions, including plutonium purification, oxide production, metal production, parts fabrication, plutonium recovery, and the recovery of americium (Am-241). The PFP has also been used for receipt and large scale storage of plutonium scrap and product materials. The PFP Final Safety Analysis Report (FSAR) was prepared by WHC to document the hazards associated with the facility, present safety analyses of potential accident scenarios, and demonstrate the adequacy of safety class structures, systems, and components (SSCs) and operational safety requirements (OSRs) necessary to eliminate, control, or mitigate the identified hazards. Documented in this Safety Evaluation Report (SER) ...
1995-01-01
Comments on the NRC Safety Research Program Budget for Fiscal Years 1984 and 1985
Energy Technology Data Exchange (ETDEWEB)
The comments are divided into three parts. Section 2 relates generally to programs for which greater effort or emphasis is needed. Section 3 provides specific comments on the proposed programs in each Decision Unit and, in most cases, for individual Subelements within each Decision Unit. Specific recommendations regarding the Research Program Support Budget are given in Section 4.
1982-07-01
Energy Technology Data Exchange (ETDEWEB)
The purpose of the New Mexico Environmental Evaluation Group (EEG) is to conduct an independent technical evaluation of the Waste Isolation Pilot Plant (WIPP) Project to ensure the protection of the public health and safety and the environment. The WIPP Project, located in southeastern New Mexico, is being constructed as a repository for the disposal of transuranic (TRU) radioactive wastes generated by the national defense programs. The EEG was established in 1978 with funds provided by the U.S. Department of Energy (DOE) to the State of New Mexico. Public Law 100-456, the National Defense Authorization Act, Fiscal Year 1989, Section 1433, assigned EEG to the New Mexico Institute of Mining and Technology and continued the original contract DE-AC04-79AL10752 through DOE contract DE-AC04-89AL58309. The National Defense Authorization Act for Fiscal Year 1994, Public Law 103-160, continues the authorization. EEG performs independent technical ...
1996-03-01
Regulatory experience on safety system instrument uncertainty of Wolsong units
International Nuclear Information System (INIS)
This paper presents the regulatory experience gained from Wolsong Units 2,3 and 4 - Special Safety System Instrumentation Uncertainty for Trip Setpoint and Allowable Values. The equipment diversity method for the defense against common mode failure was applied to the transmitters of shutdown system number 2. However the Units experienced an unexpected drift problem with which the performance did not meet the Technical Specification (Tech Spec) Surveillance Requirements (SR). Discussed are the background, status and corrective actions, regulatory positions and issues to be solved for the drift problem. It was an instrument uncertainty methodology that the designer of safety system should have shown when the drift problem occurred. For deeper understanding of the problem, we present the background of Tech Spec SR for setpoints in Korean PWR and in CANDU reactors. The Setpoint Verification Test(SVT) and Calibration Test(CT) shall be achieved by ...
2001-05-01
Pipeline risk assessment and risk management
Energy Technology Data Exchange (ETDEWEB)
The objective of this work group was to identify obstacles to the development of better risk management practices and performance standards in the pipeline industry. An outline of developments in pipeline risk assesment management was presented, including an update of the Risk Based Design and Assessment annex and other CSA Z662 code developments. It was suggested that progress in risk management require that acceptable levels of risk and reliability need to be defined. Environmental and safety consequence analysis was recommended, as well as failure frequency estimation and assessment of distribution systems. Guidelines for Integrity Management Programs (IMPs) were reviewed. It was noted that CSA Z662 will become mandatory for sour gas in 2005 and may become mandatory for all onshore pipelines in 2007. Operating company procedures in relation to hazards with significant consequences were discussed. It was noted that ...
2005-07-01
Gas-cooled fast reactor safety - and overview and status of the U.S. program
International Nuclear Information System (INIS)
In the revised GCFR Safety Program Plan a quantitative risk limit line has been adopted to establish requirements for the safety related functions and systems. The risk limit line is derived from an interpretation of NRC established licensing requirements, including those for LMFBR's. Multiple barriers to the progression of accident sequences are defined in the form of six Lines of Protection (LOPs). LOPs-1 to 3 are dedicated to accident prevention and represent the normal operating systems, the dedicated safety systems and the inherent design features, respectively. LOPs-4 to 6 are dedicated to the mitigation of core melt accident consequences and include in-vessel accident containment, secondary containment integrity and radiological attenuation, respectively. Cumulative frequency limits and consequence limits are established for each LOP. Design features associated with each LOP are described and the ...
1981-01-01
The U.S. Liquid Metal Reactor Development Program
International Nuclear Information System (INIS)
This paper discusses how the U.S. Liquid Metal Reactor Development Program has been restructured to carry out R and D on advanced reactor technology. The program gives particular emphasis to improvements to reactor safety. The new directions are based on the technology of the integral fast reactor (IFR). Much of the basis for superior safety performance using IFR technology has been experimentally verified and aggressive programs continue in EBR-II and TREAT. Progress has been made in demonstrating both the metallic fuel and the new electrochemical processes of the IFR. The FFTF facility is converting to metallic fuel; however, FFTF also maintains a considerable U.S. program in oxide fuels. In addition, generic programs are continuing in steam generator testing, materials development, and with international cooperation, aqueous reprocessing.
1988-05-01
Performance objectives for the Hanford immobilized low-activity waste (ILAW) performance assessment
Energy Technology Data Exchange (ETDEWEB)
Before low-level waste may be disposed of, a performance assessment must be written and then approved by the DOE (DOE 1988a DOE 1999a). The performance assessment is to determine whether ''reasonable assurance'' exists that the performance objectives of the disposal facility will be met. The DOE requirements for waste disposal (DOE 1988a DOE 1999a) require the protection of public health and safety; and the protection of the environment. Although quantitative limits are sometimes stated (for example, the all-pathways exposure limit is 25 mrem/year), usually the requirements are stated in a general nature. Quantitative limits were established by: investigating all potentially applicable regulations as well as interpretations of the review panels which DOE has established to review performance assessments, interacting with program management to establish the additional ...
1999-09-09
Energy Technology Data Exchange (ETDEWEB)
In a previous survey we revealed uncertainty among responders about (a) whether or not to perform hemodialysis in patients with severely reduced renal function who had received contrast medium; and (b) when to perform hemodialysis in patients on regular treatment with hemodialysis or continuous ambulatory dialysis who received contrast medium. Therefore, the Contrast Media Safety Committee of The European Society of Urogenital Radiology decided to review the literature and to issue guidelines. The committee performed a Medline search. Based on this, a report and guidelines were prepared. The report was discussed at the Ninth European Symposium on Urogenital Radiology in Genoa, Italy. Hemodialysis and peritoneal dialysis safely remove both iodinated and gadolinium-based contrast media. The effectiveness of hemodialysis depends on many factors including blood and dialysate flow rate, permeability of dialysis membrane, duration of hemodialysis and ...
2002-12-01
Review of Panel on Reference Nuclear Data surveys and discussions on reference nuclear data needs
Energy Technology Data Exchange (ETDEWEB)
The results of the six meetings in the years 1976 through 1981 of the Panel on Reference Nuclear Data is reviewed, as well as the results of other studies and workshops. A brief review of how current programs are meeting the expressed nuclear data needs of professional groups is also presented. The types of data included in the review are reaction cross sections, isotopic abundances, atomic masses, nuclear structure, radioactive decay, and fission.
1982-10-01
International Nuclear Information System (INIS)
The UK fully supports the objective of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management to achieve and maintain a high level of safety worldwide in spent fuel and radioactive waste management, through the enhancement of national measures and international co-operation, including where appropriate, safety-related co-operation. The UK's Health and Safety Executive, through its Nuclear Safety Directorate (NSD), has been committed to the Convention since the initial negotiations to set up the Convention and provided the president of the first review meeting in 2003. It would be wrong of any nation to believe that they have all the best solutions to managing spent fuel and radioactive waste. The process of compiling reports for the Convention review meetings ...
Direct liquefaction contractors' review meeting
Energy Technology Data Exchange (ETDEWEB)
Research programs, presented at the contractor's review meeting on direct liquefaction, are presented under the following topics: two-stage liquefaction; coprocessing; and advanced research on coal liquefaction. A total of 20 reports are included. Individual projects are processed separately for the data bases. (CBS)
1989-01-01
Paul Scherrer Institute Scientific Report 2000. Volume IV: Nuclear Energy and Safety
Energy Technology Data Exchange (ETDEWEB)
Nuclear energy related research in Switzerland is concentrated at PSI's Nuclear Energy and Safety Research Department (NES). The activities of the department are concentrated on three main domains of: Safety and related problems of operating plants; safety features of future reactor and fuel cycles; waste management. Comprehensive assessments of energy systems are carried out in cooperation with PSI's General Energy Research Department. Many of the programs are part of collaborations with universities, industry, or international organisations. Progress in 2000 in these topical areas is described in this report. A list of scientific publications in 2000 is also provided.
2001-03-01
Project SAFE. Update of the SFR-1 safety assessment. Phase 1. Appendix A1: Inventory
Energy Technology Data Exchange (ETDEWEB)
One of the aims in the safety assessment of SFR-1 is to estimate the release to the environment. In order to make these calculations there is a need to describe the inventory in greater detail. The new computerised database of waste in SFR-1 gives a good possibility to achieve this. The aim for project SAFE is to make both conservative and realistic radionuclide transport calculations. To achieve this goal there must be two inventories. The conservative inventory is the inventory used in the design of the repository, which in most parts is identical with the limits in the licence for SFR-1. There is a great interest to have good estimates of the volumes of the different waste types. A thorough prognosis should be made in 1999, but until then the latest one from 1995 could be used in the calculations. The total (actual) inventory of nuclides is calculated from the measurements of the easy-to-measure nuclides since, in principle, all hard-to-measure nuclides are ...
1998-10-01
Conference Proceedings: 7th Annual Review of Progress in ...
... 2 Page 27. I PROGRESS: DEVELOPMENT OF AN INTERACTIVE (;RAPHliCS PROGRAM FOR -"M CODES I. Pcng. 1. Choi. ...
1991-03-01
Energy Technology Data Exchange (ETDEWEB)
This paper explores the feasibility of integrating energyefficiency program evaluation with the emerging need for the evaluationof programs from different "energy cultures" (demand response, renewableenergy, and climate change). The paper reviews key features andinformation needs of the energy cultures and critically reviews theopportunities and challenges associated with integrating these withenergy efficiency program evaluation. There is a need to integrate thedifferent policy arenas where energy efficiency, demand response, andclimate change programs are developed, and there are positive signs thatthis integration is starting to occur.
2007-05-29
Energy Technology Data Exchange (ETDEWEB)
This report summarizes the Groundwater Monitoring Program conducted by SRS during third quarter 1998. It includes the analytical data, field data, data review, quality control, and other documentation for this program; provides a record of the program's activities; and serves as an official record of the analytical results.
1999-05-10
Energy Technology Data Exchange (ETDEWEB)
This report summarizes the Groundwater Monitoring Program conducted by the Savannah River site during fourth quarter 1999. It includes the analytical data, field data, data review, quality control, and other documentation for this program; provides a record of the program's activities; and serves as an official records of the analytical results.
2000-10-12
Energy Technology Data Exchange (ETDEWEB)
The International Atomic Energy Agency (IAEA) started the Coordinated Research Program entitled ```The Safety Assessment of Near-Surface Radioactive Waste Disposal Facilities.`` The program is aimed at improving the confidence in the modeling results for safety assessments of waste disposal facilities. The program has been given the acronym NSARS (Near-Surface Radioactive Waste Disposal Safety Assessment Reliability Study) for ease of reference. The purpose of this report is to present the ORNL modeling results for the first test case (i.e., Test Case 1) of the IAEA NSARS program. Test Case 1 is based on near-surface disposal of radionuclides that are subsequently leached to a saturated-sand aquifer. Exposure to radionuclides results from use of a well screened in the aquifer and from intrusion into the repository. Two repository concepts ...
1993-07-01
UK PubMed Central (United Kingdom)
Assessments of drinking water safety rely on the assumption that ingestion represents the principal route of exposure. A review of the experimental literature revealed that skin penetration rates for...Full Text Available
1984-05-01
...Agriculture Analysis of food supply chains and linkages in relation to quality and safety assurances Dept of Primary Industries, Australia Impact of food chain quality assurance requirements on farmer adoption and competitiveness UK Research Councils Review of environmental certification through farm assurance followed by industry developmental workshop Agriculture & ...
Safety performance indicators. Topical issues paper no. 5
International Nuclear Information System (INIS)
Since its creation the nuclear industry has been struggling with the question of how safe is safe enough. Safety is a common goal to all involved in the design, operation and regulation of a nuclear installation. As a concept safety is not easy to define. However, there is a general understanding of what attributes a nuclear power plant should have in order to operate safely. The challenge lies in measuring the attributes. The new competitive open electricity market, in many countries throughout the world, is increasing the economic pressure on operators to lower operating costs without jeopardizing safety. Challenges are occurring at a rate that is unprecedented in the nuclear industry: competitiveness; downsizing; ageing; policy changes; reorganization; restructuring; mergers; globalization; and takeovers demand increasing attention to the management of safety. There are various means to measure ...
2001-09-03
Preventing surgical fires: who needs to be educated?
BACKGROUND AND CASE STUDY: Surgical fires are rare but preventable. During facial surgery for a 68-year-old man, a fire broke out, resulting in first- and second-degree burns after a nasal cannula ignited in an oxygen-rich environment because of improper draping and tenting. DISCUSSION: Operating room (OR) fires can be prevented if any component of the "fire triangle"-fuels, ignition sources, and oxidizers-is reduced or eliminated. The use of supplemental oxygen in the OR via nasal cannulae, nebulizers, and oxygen cylinders must always considered a potential source of fire. Deficits in knowledge among the surgical team with respect to the prevention and management of surgical fires were apparent. A plan was put into place to improve fire safety education, entailing an educational program that is included in intern and resident orientation. Surgical fire safety training was also put into place for anesthesia and surgical ...
2005-09-01
Evaluation of the suitability of the WIPP site
Energy Technology Data Exchange (ETDEWEB)
Determination of the suitability of the site for WIPP is only the first major phase in the evaluation of the radiological impact of the repository on the public health and safety. The Environmental Evaluation Group (EEG) will continue to independently review the design of the facility, the operational procedures, the criteria for packaging and shipment of the waste, the plans, procedures and results of the WIPP experiments, emergency preparedness, adherence to EPA and pertinent NRC regulations, and other important features of the project. EEG has concluded from existing evidence that the Los Medanos site for the WIPP project has been characterized in sufficient detail to warrant confidence in the validation of the site for the permanent emplacement of approximately 6 million cubic feet of defense transuranic waste. This conclusion is based on the assumption that the maximum surface dose rate for the unshielded remote-handled transuranic waste ...
1983-05-01
International Nuclear Information System (INIS)
To be able to carry out review functions regulatory authorities must be able to make critical evaluations of proponent's safety cases. In Sweden the Swedish Radiation Safety Authority aims to have in place its own suite of performance assessment tools. This paper looks at the role and application of a regulator's models to important features of current modelling in a proponent's performance assessment. (authors)
Criticality safety review of FFTF interim decay storage tank
The Interim Decay Storage tank (IDS) will be located in a concrete cell in the FFTF reactor building. The tank will have capacity to store 112 driver fuel assemblies and 10 test assemblies in sodium. A criticality safety analysis for the design of the IDS tank was performed. From the analysis, it is concluded that under normal operating conditions and minor abnormal conditions that might shift the fuel, the IDS tank will remain adequately subcritical. (auth)
1975-10-01
Coastal conservation: essays on experiments in governance. [Monograph
Energy Technology Data Exchange (ETDEWEB)
Three book reviews and five essays address the problems of governing coastal regions. The books reviewed and the articles covered the institutions and programs involved in resource management, the balance of local and state interests in coastal conservation and developments, a consensus on coastal planning issues, and a growing trend in state-local collaborative planning. Four of the articles pertain to California, and one focuses on programs in Maine, Rhode Island, and Washington. 135 references. (DCK)
1981-01-01
Draft Regulatory Rule-making for On-line Maintenance of Nuclear Power Plants
International Nuclear Information System (INIS)
Internationally, on-line maintenance (OLM) of nuclear power plants under the operation is prevailed to enhance nuclear safety and economics. In recent years, Korea Hydro and Nuclear Power Co. Ltd. (KHNP) is eager to apply OLM. Ministry of Education, Science and Technology (MEST) has established the related technology development program as an item of 'Overall Planning on Nuclear Safety(2010-2014)' through acceptance to the request of KHNP in 2009. OLM is defined as maintenance that is performed with the main generator connected to the grid. In other words, it means a preventive maintenance to be implemented during the allowable outage time (AOT) with ignoring inoperability of safety-related equipment listed in the technical specifications. The Korea Institute of Nuclear Safety (KINS) is developing the assessment technology of safety concerns for OLM under the ...
2010-10-01
HPOF transmission-system economic-evaluation program. Final report
Energy Technology Data Exchange (ETDEWEB)
This report describes the successful development of a computer program for the analysis of the economic, thermal, and rating characteristics of HPOF underground transmission cables with forced cooling. With this program cable engineers can interactively analyze self-cooled and forced-cooled HPOF cable design alternatives. The program computes cable thermal characteristics and discounted costs so that the impacts of changes in design parameters can be estimated. This report provides a review of the currently available HPOF design options that can be considered. The HPOF economic analysis program is written in FORTRAN IV and was developed for interactive operation.
1983-01-01
Energy Technology Data Exchange (ETDEWEB)
Information is presented concerning GCFR design and limiting faulted events; selection of PC-5 temperature limit; and verification test programs.
1980-02-01
Environmental Restoration Program quality assurance system requirements for the Hanford Site
International Nuclear Information System (INIS)
This document defines the quality assurance program requirements for the US Department of Energy, Richland Field Office, Environmental Restoration program at the Hanford Site. This document integrates quality assurance requirements from US Department of Energy Orders, the Hanford Federal Facility Agreement and Consent Order, and applicable industry standards into a single source document for the development of quality assurance programs applicable to the Environmental Restoration program items and activities. This document has been configured into three parts and fifteen criteria to provide user organizations with a workable document that best facilitates line operations. When developing individual user organization quality assurance programs, the document configuration provides each organization with the Flexibility to incorporate only those parts and criteria that are applicable ...
Facility Safety Plan B360 Complex Biohazardous Operations CMLS-412r0
This Addendum to the Facility Safety Plan (FSP) 360 Complex describes the safety requirements for the safe conduct of all biohazardous research operations in all buildings within the 360 complex program areas. These requirements include all the responsibilities and authorities of building personnel, operational hazards, and environmental concerns and their controls. In addition, this Addendum prescribes facility-specific training requirements and emergency controls, as well as maintenance and quality assurance requirements for ES&H-related building systems.
2007-01-08
Update of the management strategy for Oak Ridge National Laboratory Liquid Low-Level Waste
Energy Technology Data Exchange (ETDEWEB)
The strategy for management of the Oak Ridge National Laboratory`s (ORNL) radioactively contaminated liquid waste was reviewed in 1991. The latest information available through the end of 1990 on waste characterization, regulations, US Department of Energy (DOE) budget guidance, and research and development programs was evaluated to determine how the strategy should be revised. Few changes are needed to update the strategy to reflect new waste characterization, research, and regulatory information. However, recent budget guidance from DOE indicates that minimum funding will not be sufficient to accomplish original objectives to upgrade the liquid low-level waste (LLLW) system to comply with the Federal Facilities Agreement, provide long-term LLLW treatment capability, and minimize environmental, safety, and health risks. Options are presented that might allow the ORNL LLLW system to continue operations temporarily, but they ...
1995-04-01
Status of the ORNL liquid low-level waste management upgrades
Energy Technology Data Exchange (ETDEWEB)
The strategy for management of the Oak Ridge National Laboratory`s (ORNL`s) radioactively contaminated liquid waste was reviewed. The latest information on waste characterization, regulations, US Department of Energy (DOE) budget guidance, and research and development programs was evaluated to determine how the strategy should be revised. Few changes are needed to update the strategy to reflect new waste characterization, research, and regulatory information. However, recent budget guidance from DOE indicates that minimum funding will not be sufficient to accomplish original objectives to upgrade the liquid low-level waste (LLLW) system to be in compliance with the Federal Facilities Agreement compliance, provide long-term LLLW treatment capability, and minimize Environmental Safety & Health risks. Options are presented that might allow the ORNL LLLW system to continue operations temporarily but significantly reduce its ...
1995-08-01
Oak Ridge National Laboratory Waste Management Plan, fiscal year 1994. Revision 3
Energy Technology Data Exchange (ETDEWEB)
US Department of Energy (DOE) Order 5820.2A was promulgated in final form on September 26, 1988. The order requires heads of field organizations to prepare and to submit updates on the waste management plans for all operations under their purview according to the format in Chap. 6, {open_quotes}Waste Management Plan Outline.{close_quotes} These plans are to be submitted by the DOE Oak Ridge Operations Office (DOE-ORO) in December of each year and distributed to the DP-12, ES&H-1, and other appropriate DOE Headquarters (DOE-HQ) organizations for review and comment. This document was prepared in response to this requirement for fiscal year (FY) 1994. The Oak Ridge National Laboratory (ORNL) waste management mission is reduction, collection, storage, treatment, and disposal of DOE wastes, generated primarily in pursuit of ORNL missions, in order to protect human health and safety and the environment. In carrying out this mission, waste ...
1993-12-01
Health and Safety Research Division progress report for the period October 1, 1991--March 31, 1993
International Nuclear Information System (INIS)
This is a progress report from the Health and Safety Research Division of Oak Ridge National Laboratory. Information is presented in the following sections: Assessment Technology, Biological and Radiation Physics, Chemical Physics, Biomedical and Environmental Information Analysis, Risk Analysis, Center for Risk Management, Associate Laboratories for Excellence in Radiation Technology (ALERT), and Contributions to National and Lead Laboratory Programs and Assignments--Environmental Restoration.
1998-06-01
A study on diagnostic techniques of pump operating condition
Energy Technology Data Exchange (ETDEWEB)
The scope and contents investigate and reviewed are as follows : establishment of study plan and references survey, review of related problems and inservice test standards of safety injection pump in use nuclear power plant, review of the study results in laboratory, the theoretical investigation of temperature rise according to mini-flow rate of pump, mini-flow rate working characteristics of high and low pressure injection pumps at nuclear power plants, setup of testing equipment for measuring ampere, discharge pressure and vibration, selection and behaviors analysis of major parameters concerning pump degradation.
1998-03-15
International Nuclear Information System (INIS)
The IAEA Assessment of Safety Significant Events Team (ASSET) report presents the results of an ASSET team's assessment of their investigation of the effectiveness of the plant for prevention of incidents since 1990 at Zaporozhe nuclear power plant. The results, conclusions and suggestions presented herein reflect the views of the ASSET experts. They are provided for consideration by the responsible authorities in Ukraine. The ASSET team's views presented in this report are based on visits to the plant, on review of documentation made available by the operating organization and on discussions with utility personnel. The report is intended to enhance operational safety at Zaporozhe by proposing improvements to the policy for the prevention of incidents at the plant. The report includes, as a usual practice, the official response of the operating organization as well as of the regulatory body to the ASSET recommendations. ...
2003-11-01
Packaging Review Guide for Reviewing Safety Analysis Reports for Packagings
Energy Technology Data Exchange (ETDEWEB)
This Packaging Review Guide (PRG) provides guidance for Department of Energy (DOE) review and approval of packagings to transport fissile and Type B quantities of radioactive material. It fulfills, in part, the requirements of DOE Order 460.1B for the Headquarters Certifying Official to establish standards and to provide guidance for the preparation of Safety Analysis Reports for Packagings (SARPs). This PRG is intended for use by the Headquarters Certifying Official and his or her review staff, DOE Secretarial offices, operations/field offices, and applicants for DOE packaging approval. This PRG is generally organized at the section level in a format similar to that recommended in Regulatory Guide 7.9 (RG 7.9). One notable exception is the addition of Section 9 (Quality Assurance), which is not included as a separate chapter in RG 7.9. Within each section, this PRG addresses the technical and ...
2007-04-12
International Nuclear Information System (INIS)
This plan establishes both the scope of the review and the acceptance criteria to be utilized for the review of Quality Assurance Program Plans (QAPPs) developed in accordance with the requirements of DOE/RL-90-28. DOE/RL-90-28, the Environmental Restoration Remedial Action Quality Assurance Requirements Document (QARD) defines all quality assurance (QA) requirements governing activities that affect the quality of the Environmental Restoration Remedial Action (ERRA) program at the Hanford Site. These requirements are defined in three parts, Part 1 of Quality Management and Administration tasks, Part 2 for Environmental Data Operations, and Part 3 of the Design and Construction of items, systems, and facilities. The purpose of this document is to identify the scope of the review by the DOE Field Office, Richland staff, and establish the acceptance criteria (Parts 1, 2, and 3) that ...
Energy Technology Data Exchange (ETDEWEB)
This report describes the status of nuclear safety and radiation protection in the facilities of the AREVA group and gives information on radiation protection in the service operations, as observed through the inspection programs and analyses carried out by the General Inspectorate in 2007. Having been submitted to the group's Supervisory Board, this report is sent to the bodies representing the personnel. Content: 1 - A look back at 2007 by the AREVA General Inspector: Visible progress in 2007, Implementation of the Nuclear Safety Charter, Notable events; 2 - Status of nuclear safety and radiation protection in the nuclear facilities and service operations: Personnel radiation protection, Event tracking, Service operations, Criticality control, Radioactive waste and effluent management; 3 - Performance improvement actions; 4 - Description of the General Inspectorate; 5 - Glossary.
2007-07-01
Energy Technology Data Exchange (ETDEWEB)
Since August 1984, the MITRE Corporation has been supporting the Naval Sea Systems Command (NAVSEA) and the Naval Medical Command (NAVMEDCOM) in their joint efforts to enhance the Navy Occupational Health Information Management System (NOHIMS). The goal of the enhancement effort was to create a comprehensive occupational health and safety system for Navy industrial facilities by expanding upon the original NOHIMS functions and adding modules for hazard deficiency abatement, hazardous-material control, injury claims and compensation, and safety and health training. To meet this goal, MITRE developed an enhanced industrial subsystem, referred to as the Occupational Safety and Health Record Keeping System (OSHRKS), using a prototyping approach and a public-domain data base-management software package, the Veterans Administration's (VA's) FileManager (FileMan).
1987-06-01
Quality assurance program requirements (operation)
International Nuclear Information System (INIS)
Apppendix B of 10 CFR Part 50 establishes quality assurance requirements for the operation of nuclear power plant safety-related structures, systems and components. This Guide describes an acceptable method for complying with these regulations with regard to overall quality assurance program requirements for the operation phase of nuclear power plants. Input to this Guide has been provided by the Advisory Committee on Reactor Safeguards.
Quality assurance program requirements (design and construction)
International Nuclear Information System (INIS)
Appendix B to 10 CFR Part 50 establishes overall quality assurance requirements for the design, construction and operation of safety-related structures, systems, and components. This guide presents a method acceptable to the Commission for complying with these regulations with regard to overall quality assurance program requirements during design and construction of nuclear power plants. Input to this guide has been provided by the Advisory Committee on Reactor Safeguards.
Energy Technology Data Exchange (ETDEWEB)
This report summarizes activities of the Amarillo National Resource Center for Plutonium during the quarter. The report describes the Electronic Resource Library; DOE support activities; current and future environmental health and safety programs; pollution prevention and pollution avoidance; communication, education, training, and community involvement programs; and nuclear and other material studies, including plutonium storage and disposition studies.
1997-12-31
Technology development, evaluation, and application (TDEA) FY 1997 progress report
Energy Technology Data Exchange (ETDEWEB)
The public expects that the Los Alamos National Laboratory (LANL) will operate in a manner that prevents negative impacts to the environment and protects the safety and health of its employees and the public. To achieve this goal within budget, the Department of Energy (DOE) and LANL must develop new and improved environment, safety, and health (ES and H) technologies and implement innovative, more cost-effective ES and H approaches to operations. In FY95, the Environment, Safety, and Health (ESH) Division initiated a Technology Development, Evaluation, and Application (TDEA) program. The purpose of this unique program is to test and develop technologies that solve LANL ES and H problems and improve the safety of LANL operations. This progress report presents the results of 10 projects funded in FY97 by the TDEA Committee of the Environment, ...
1998-05-01
Characteristics of safety critical organizations . work psychological perspective
International Nuclear Information System (INIS)
This book deals with organizations that operate in high hazard industries, such as the nuclear power, aviation, oil and chemical industry organisations. The society puts a great strain on these organisations to rigorously manage the risks inherent in the technology they use and the products they produce. In this book, an organisational psychology view is taken to analyse what are the typical challenges of daily work in these environments. The analysis is based on a literature review about human and organisational factors in safety critical industries, and on the interviews of Finnish safety experts and safety managers from four different companies. In addition to this, personnel interviews conducted in the Finnish nuclear power plants are utilised. The authors come up with eight themes that seem to be common organizational challenges cross the industries. These include e.g. how does the personnel ...
The crystalline-silicon photovoltaic R&D project at NREL and SNL
Energy Technology Data Exchange (ETDEWEB)
This paper summarizes the U.S. Department of Energy R&D program in crystalline-silicon photovoltaic technology, which is jointly managed by Sandia National Laboratories and National Renewable Energy Laboratory. This program features a balance of basic an d applied R&D, and of university, industry, and national laboratory R&D. The goal of the crystalline-silicon R&D program is to accelerate the commercial growth of crystalline-silicon photovoltaic technology, and four strategic objectives were identified to address this program goal. Technical progress towards meeting these objectives is reviewed.
1996-12-31
Joint Integration Office Independent Review Committee annual report, 1985
Energy Technology Data Exchange (ETDEWEB)
Comprised of seven persons with extensive experience in the issues of nuclear waste, the Independent Review Committee (IRC) provides independent and objective review of Defense Transuranic Waste Program (DTWP) activities managed by the Joint Integration Office (JIO), formerly the Defense Transuranic Waste Lead Organization (TLO). The Committee is ensured a broad, interdisciplinary perspective since its membership includes representatives from the fields of nuclear engineering, nuclear waste transportation, industrial quality control, systems and environmental engineering and state and local government. The scope of IRC activities includes overall review of specific TLO plans, projects and activities, and technical review of particular research and development projects. The Committee makes specific suggestions and recommendations based upon expertise in the field of TRU Waste ...
1986-08-01
Establishment of Database Program for In-service Test Management in Nuclear Power Plants
International Nuclear Information System (INIS)
In-service Test (IST) of the nuclear power plant is very important to maintain the safety of the plants. The safety features of nuclear power plant are based on the operation of pumps and valves. Therefore, it is an essential basis for the safety of nuclear power plant to keep operational readiness of pumps and valves. Because of the importance of the IST, most of nuclear power plants should designate the IST department and personnel. Because the nuclear power plants of Korea have several types and the designs and operations are different from each other, the methods and experiences are various for the management of the IST program. However, there are no medium to communicate with each other and exchange the tips and information about IST program and education and discussion would be required to apply a consistent code. The nature of the IST Standardization Management Data Base ...
2010-10-01
Site Environmental Report for 2007 Volume I
International Nuclear Information System (INIS)
The Site Environmental Report is an integrated report on Berkeley Lab's environmental programs to satisfy the requirements of DOE Order 231.1A, Environment, Safety, and Health Reporting. It summarizes Berkeley Lab's environmental management performance, presents environmental monitoring results, and describes significant programs for calendar year 2007. Volume I is organized into an executive summary followed by six chapters that contain an overview of the Laboratory, a discussion of the Laboratory's environmental management system, the status of environmental programs, and summarized results from surveillance and monitoring activities.
UK PubMed Central (United Kingdom)
This article focuses on results of the systematic review from the Guide for Useful Interventions for Activity in Latin America project related to school-based...Full Text Available
2010-06-01
Energy Technology Data Exchange (ETDEWEB)
Research programs, presented at the contractor's review meeting on indirect liquefaction, are presented on the following topics: oxygenates (methanol) synthesis; Fischer-Tropsch synthesis; product upgrading; and process support engineering evaluations. A total of 18 reports are included. Individual projects are processed separately for the data bases. (CBS)
1989-01-01
Incidence and Determinants of Birth Defects and Enzyme Deficiencies among Live Births in Oman
UK PubMed Central (United Kingdom)
ObjectivesIn 2003, the Omani Ministry of Health Child Health Care Program initiated a national Birth Defects (BD) Register. This paper reviews the magnitude and risk factors of birth...Full Text Available
2010-04-01
Direct liquefaction contractors' review meeting: Proceedings
Energy Technology Data Exchange (ETDEWEB)
Research programs on coal liquefaction are presented. Major topics include: coprocessing, two-stage liquefaction, low severity liquefaction, coal/catalyst and liquefaction chemistry. Individual projects are processed separately for the data bases. (CBS)
1988-01-01
International Nuclear Information System (INIS)
Calculations, drawing principally on developments at AERE Harwell, of the relaxation about lattice defects are reviewed with emphasis on the techniques required for such calculations. The principles of defect modelling are outlined and various programs developed for defect simulations are discussed. Particular calculations for metals, ionic crystals and oxides, are considered. (UK).
1980-03-01
UK PubMed Central (United Kingdom)
ObjectiveThere has been much debate about the value of condoms in HIV/STI programming. This should be informed by evidence about intervention impact on condom use, but there is limited...Full Text Available
2007-12-01
Energy Technology Data Exchange (ETDEWEB)
In March 2005, the United States Coast Guard requested that Sandia National Laboratories provide a technical review and evaluation of the appropriateness and completeness of models, assumptions, analyses, and risk management options presented in the Cabrillo Port LNG Deepwater Port Independent Risk Assessment-Revision 1 (Cabrillo Port IRA). The goal of Sandia's technical evaluation of the Cabrillo Port IRA was to assist the Coast Guard in ensuring that the hazards to the public and property from a potential LNG spill during transfer, storage, and regasification operations were appropriately evaluated and estimated. Sandia was asked to review and evaluate the Cabrillo Port IRA results relative to the risk and safety analysis framework developed in the recent Sandia report, ''Guidance on Risk Analysis and Safety Implications of a Large Liquefied Natural Gas (LNG) Spill over ...
2006-01-01
Co-operation Equipment Qualification for Safety grade I and C Equipment between Russia and Korea
Energy Technology Data Exchange (ETDEWEB)
Equipment Qualification technology for I and C system on nuclear grade have been approved with accurate and safe for verifying and validation. It contributes to acknowledge of reliability and to review of user approval. Also it did not completely satisfied the requirement of Russia, it can be satisfied by bit of modification on design. It is expected to support the export of safety PLC to nuclear power plant. Proven EQ technology is required on the further markets of nuclear. Therefore, comparison test with foreign country is necessary to support the mutual accreditation of EQ for export of domestic products.
2007-06-15
British Library Electronic Table of Contents (United Kingdom)
In this article, several applications of nanomaterials in food packaging and food safety are reviewed, including: polymer/clay nanocomposites as high barrier packaging materials, silver nanoparticles as potent antimicrobial agents, and nanosensors and nanomaterial-based assays for the detection of food-relevant analytes (gasses, small organic molecules and food-borne pathogens). In addition to covering the technical aspects of these topics, the current commercial status and understanding of health implications of these technologies are also discussed. These applications were chosen because they do not involve direct addition of nanoparticles to consumed foods, and thus are more likely to be marketed to the public in the short term.
2011-01-01
In recent years, several groups, including the physician assistant, health information management, ophthalmic medical technician/technologist, and athletic training review committees, have left the Commission on Accreditation of Allied Health Education Programs (CAAHEP) system to form their own, profession-specific accrediting bodies. Their motivation was typically a desire for greater professional visibility and autonomy. Combined, these professions represented one third of the CAAHEP's programs. This article reviews the history of allied health and examines current attempts to bring cohesion and identity to this increasingly fractured segment of the U.S. health care system. PMID:18444439
2008-01-01
Local government`s pollution prevention program
Energy Technology Data Exchange (ETDEWEB)
The pollution prevention program operated by the Health Department of Boulder County is called Business Partners for a Clean Environment (Business Partners). It is a cooperative effort among local businesses, the City of Boulder, Boulder County, and the Boulder Chamber of Commerce. This nonregulatory, incentive-based program provides industry with pollution prevention information and technical assistance necessary to reduce and/or eliminate environmental waste. This paper provides an overview of the program development, creation of partnerships and trust, and some of the results from implementation of the program. Following the first 18 months of the program, 35 businesses were recognized as Business Partners. The Business Partners program has also received an achievement award from the National Association of Counties for promoting {open_quotes}responsible, ...
1996-12-31
FY05-FY06 Advanced Simulation and Computing Implementation Plan, Volume 2
Energy Technology Data Exchange (ETDEWEB)
The Stockpile Stewardship Program (SSP) is a single, highly integrated technical program for maintaining the safety and reliability of the U.S. nuclear stockpile. The SSP uses past nuclear test data along with future non-nuclear test data, computational modeling and simulation, and experimental facilities to advance understanding of nuclear weapons. It includes stockpile surveillance, experimental research, development and engineering programs, and an appropriately scaled production capability to support stockpile requirements. This integrated national program will require the continued use of current facilities and programs along with new experimental facilities and computational enhancements to support these programs. The Advanced Simulation and Computing program (ASC) is a cornerstone of the SSP, providing simulation ...
2004-07-19
Environmental Restoration Remedial Action quality assurance requirements document
International Nuclear Information System (INIS)
This document defines the quality assurance requirements for the US Department of Energy-Richland Operations Office Environmental Restoration Remedial Action program at the Hanford Site. The Environmental Restoration Remedial Action program implements significant commitments made by the US Department of Energy in the Hanford Federal Facility Agreement and Consent Order entered into with the Washington State Department of Ecology and the US Environmental Protection Agency. This document combines quality assurance requirements from various source documents into one set of requirements for use by the US Department of Energy-Richland Operations Office and other Environmental Restoration Remedial Action program participants. This document will serve as the basis for developing Quality Assurance Program Plans and implementing procedures by the participants. The requirements of this document will be applied to ...
British Library Electronic Table of Contents (United Kingdom)
Abstract Evaluation of pharmaceutical agents in children is now conducted earlier in the drug development process. An important consideration for this pediatric use is how to assess and support its safety. This article is a collaborative effort of industry toxicologists to review strategies, challenges, and current practice regarding preclinical safety evaluations supporting pediatric drug development with biopharmaceuticals. Biopharmaceuticals include a diverse group of molecular, cell-based or gene therapeutics derived from biological sources or complex biotechnological processes. The principles of preclinical support of pediatric drug development for biopharmaceuticals are similar to those for small molecule pharmaceuticals and in general follow the same regulatory guidances outlined by...
2011-01-01
Lessons learned from accidents in industrial radiography
International Nuclear Information System (INIS)
Industrial radiography accounts for approximately half of all the reported accidents for the nuclear related industry, in both developed and developing countries. This Safety Report is the result of a review made of a large selection of accidents in industrial radiography reported by regulatory authorities, professional associations and scientific journals. A small, representative selection of 43 accident descriptions has been used to illustrate the primary causes of radiography accidents, and a set of measures provided to prevent the recurrence of such accidents or to mitigate the consequences of those that do occur. These accident descriptions were categorized by primary causes as follows: inadequate regulatory control; failure to follow operational procedures; inadequate training; inadequate maintenance; human error; equipment malfunction or defect; design flaws; and wilful violation. The information in this Safety ...
Survey on Aging Deterioration of Safety Related Equipment in Operating Nuclear Power Plants
International Nuclear Information System (INIS)
As a basic research to consider aging deterioration of the operating nuclear power plant to seismic fragility analysis, aging deteriorations occurring safety related equipment of both Kori unit 1 and Wolsung unit 1, are investigated in this study. First of all, 378 and 152 safety related equipment are selected at Kori unit 1 and Wolsung unit 1 respectively. Seismic review team including seismic capability engineer, is organized and seismic walkdown is carried out using the nondestructive tests. As a results of seismic walkdown, crack is a typical aging deterioration which can reduce the seismic safety of safety related equipment and the other aging deteriorations such as concrete compressive strength, corrosion, and tightness of anchor bolt, have a much smaller influence than crack. In order to manage the aging deterioration data collected through the seismic walkdown in effective ...
1997-04-14
Survey on Aging Deterioration of Safety Related Equipment in Operating Nuclear Power Plants
Energy Technology Data Exchange (ETDEWEB)
As a basic research to consider aging deterioration of the operating nuclear power plant to seismic fragility analysis, aging deteriorations occurring safety related equipment of both Kori unit 1 and Wolsung unit 1, are investigated in this study. First of all, 378 and 152 safety related equipment are selected at Kori unit 1 and Wolsung unit 1 respectively. Seismic review team including seismic capability engineer, is organized and seismic walkdown is carried out using the nondestructive tests. As a results of seismic walkdown, crack is a typical aging deterioration which can reduce the seismic safety of safety related equipment and the other aging deteriorations such as concrete compressive strength, corrosion, and tightness of anchor bolt, have a much smaller influence than crack. In order to manage the aging deterioration data collected through the seismic walkdown in effective ...
2008-02-15
Natural gas pipeline safety in residential areas served by master meters. a handbook
Prepared to make housing project managers, maintenance engineering staff, and designers and architects of HUD - assisted and HUD - insured housing projects and mobile home parks aware of their responsibilities under the Natural Gas Pipeline Safety Act, this handbook provides technical guidance for the reduction of gas leaks and the handling of gas leak incidents in residential areas. The hazards of natural gas, concern over gas safety in residential areas, applicable codes and standards, and sources of information and help are reviewed, along with maintenance and engineering considerations relating to gas pipe failures, the detection of gas leaks, appliance servicing, and pipe installation, repair, and replacement. Housing management considerations are also examined, with attention to recordkeeping and reporting, emergency contingency planning, tenant education, staff qualifications and training, and the development and use ...
1975-04-01
Loss of flow incident - Simulation and measurements in the MPR
International Nuclear Information System (INIS)
As part of the Probabilistic Safety Analysis of the Multi Purpose Reactor, MPR, the list of Postulated Initiating Events was analyzed and one of these PIEs corresponds to the Loss of Coolant Flow. It is well known that during the operation life of a research reactor a LOFA could eventually occur and, once this event takes place, in time detection and automatic actions, thanks to the engineering safety features of the system, will mitigate the incident evolution. The postulated event corresponds to a loss of flow due to a total loss of power supply. The goal of the present work is to provide a general description and the engineering safety features of the MPR, as well as describe the sequence of scenarios during a LOFA. Temporal evolution of main parameters is presented, also. During Stage A of the Commissioning Program measurements of the core cooling system pump coast-down were performed in order to ...
1999-10-26
Regulatory quality assurance requirements for the operation of nuclear R and D facilities in Korea
International Nuclear Information System (INIS)
Full text: Korea Atomic Energy Research Institute (KAERI) has many R and D facilities in operation. including HANARO research reactor, radioactive waste treatment facility (RWTF), post-irradiation examination facility (PIEF) and irradiated material test facility (IMEF). Recently. nation-wide interest is focused on the safety and security of major industrial facilities. Safe operation of nuclear facilities is imperative because of the consequence of public disaster by radiological release/contamination, in case of an accident. Recently, Ministry of Science and Technology (MOST) of the Korean government announced amendments of Atomic Energy laws to enforce requirements of the physical protection and radiological emergency. All provisions on nuclear safety regulation and radiation protection are entrusted to the Atomic Energy Act(AEA). The Act is enacted as the main law concerning the safety regulation of nuclear ...
2006-10-15
Fast breeder reactor safety : a perspective
International Nuclear Information System (INIS)
Taking into consideration India's limited reserves of natural and vast reserves of thorium, the fast reactor route holds a great promise for India's energy supply in future. The fast reactor fueled with "2"3"9Pu/"2"3"8U (unused or depleted) produces (breeds) more fissionable fuel material "2"3"9Pu than it consumes. Calculations show that a fast breeder reactor (FBR) increases energy potential of natural uranium by about 60 times. As the fast reactor can also convert "2"3"2Th into "2"3"3U which is a fissionable material, it can make India's thorium reserves a source of almost inexhaustible energy supply for a long time to come. Significant advantage of FBR plants cooled by sodium and their world-wide operating experience are reviewed. There are two main safety issues of FBR, one nuclear and the other non-nuclear. The nuclear issue concerns core disruptive accident and the non-nuclear one concerns the high chemical energy potential of sodium. ...
A review of Monte Carlo criticality calculations - Convergence, bias, statistics
International Nuclear Information System (INIS)
Monte Carlo criticality calculations have been performed for over 50 years for reactor physics and criticality safety applications. With today's faster computers, these calculations are being carried out to greater precision (smaller uncertainties) in keff, and detailed distributions of power and reaction rates are being computed routinely. This paper provides a review of the fundamental theory of Monte Carlo criticality calculations, with guidance on practical methods for: (1) assuring convergence of both keff and the source distribution, (2) minimizing the bias in keff and reaction rate distributions, and (3) dealing with the under-prediction bias in uncertainties for keff and reaction rate distributions. (authors)
2009-05-03
Reconsidering the site requirements for NPP on Olt River
International Nuclear Information System (INIS)
Site studies for CANDU type NPP began in a careful manner since 1982 as a first part of the Nuclear Power Plant Romanian Program adopted by political and governmental authorities at the time. A team was charged to develop all packages of the necessary main studies. The first Romanian NPP CANDU 6 type reactor gone to erection on Cernavoda site, planned to have 5 units and, like Wolsong NPP, applied the same design for the nuclear island. For the BOP parts the ANSALDO-GE project was applied with a thorough concern about requirements raised by connection to NSP. The first mission of design and research multi-branch team was to adapt the NPP Cernavoda project having an open water cooling circuit 'once-through' to the new parameters of a close recirculation water cooling circuit. Also, the structural design was re-evaluated for the case of soft foundation strata instead of hard rock ones. The close recirculation water cooling circuit system was applied for PWR NPP type ...
2009-10-12
Status of neutron cross sections for reactor dosimetry
International Nuclear Information System (INIS)
The status of neutron activation cross sections for some threshold reactions important for reactor materials dosimetry is reviewed. An attempt is made to understand and explain discrepancies between integral and differential data, using recent available experimental results. The importance of standard and benchmark neutron fields for testing differential data for reactor dosimetry is emphasized and the Interlaboratory Reaction Rate (ILRR) program, as well as a similar program pursued by the IAEA, are briefly described.
1976-07-06
Joining technologies for the plasma facing components of ITER
Energy Technology Data Exchange (ETDEWEB)
An extensive R and D program on the development of the joining technologies between armour (beryllium, tungsten and carbon fibre composites)/copper alloys heat sink and copper alloys/ stainless steel has been carried out by ITER Home Teams. A brief review of this R and D program is presented in this paper. Based on the results, reference technologies for use in ITER have been selected and recommended for further development. (author)
1998-07-01
Energy Technology Data Exchange (ETDEWEB)
Most analyses of the alternative strategies used by utilities to comply with Title IV requirements have focused on factors directly related to controlling sulfur dioxide (SO{sub 2}) emissions. However, utilities must meet a number of additional environmental requirements at the same tune they comply with the acid rain program. To illuminate the potential synergies and conflicts that might exist between the other regulatory mandates and the acid rain program, a thorough examination of all the various programs and their interrelationships must be conducted. This paper reviews the environmental mandates that utilities will have to plan to meet in the next decade concurrently with the acid rain program, and it analyzes the interactions among the various programs to identify potential synergies and conflicts.
1993-11-01
International Nuclear Information System (INIS)
The Structural Aging (SAG) Program is carried out by the Oak Ridge National Laboratory (ORNL) under sponsorship of the United States Nuclear Regulatory Commission (USNRC). The Program has evolved from preliminary studies conducted to evaluate the long-term environmental challenges to light-water reactor safety-related concrete civil structures. An important conclusion of these studies was that a damage methodology, which can provide a quantitative measure of a concrete structure's durability with respect to potential future requirements, needs to be developed. Under the SAG Program, this issue is being addressed through: establishment of a structural materials information center, evaluation of structural component assessment and repair technologies, and development of a quantitative methodology for structural aging determinations. Progress to date of each of these activities is presented as well as ...
1989-08-14
Canadian fuel development program in 1997/98
International Nuclear Information System (INIS)
This paper describes the CANDU fuel development activities in Canada during 1997 through 1998. The activities include those of the Fuel Technology Program sponsored by the CANDU Owners Group. The goal of the Fuel Technology Program is to maintain and improve the reliability, economics and safety of CANDU fuel in operating reactors. These activities, therefore, concentrate on the present designs of 28-element and 37-element fuel bundles. The Canadian fuel development activities also include those of the Advanced Fuel and Fuel Cycle Technology Program at AECL. These activities concentrate on the development of advanced fuel designs and advanced fuel cycles, which among other advantages, can reduce the capital and fuelling costs, maintain operating margins in aging reactors, improve natural-uranium utilization, and reduce the amount of spent fuel. (author)
1997-09-21
Insight conference reports : proceedings of the smart meters forum
Energy Technology Data Exchange (ETDEWEB)
This forum provided insights into Ontario's new smart meter program. Challenges related to implementing the smart meter program were reviewed, and various functional and operational considerations of the meters were considered. The implications and benefits of using real time metering systems were discussed along with issues related to energy conservation and demand management. Various communications technologies were considered in relation to smart metering program implementation. Issues related to pricing and pricing policies were also discussed. The conference featured 11 presentations, of which 2 have been catalogued separately for inclusion in this database. refs., tabs., figs.
2006-07-01
Paul Scherrer Institute Scientific Report 1998. Volume IV: Nuclear Energy and Safety
Energy Technology Data Exchange (ETDEWEB)
Nuclear energy related research in Switzerland is concentrated at PSI`s Nuclear Energy and Safety Research Department (NES). The total effort invested in nuclear energy research in 1998 amounted to about 195 py/a and 4.5 millions CHF of investment and maintenance costs. Approximately half of the salary, investment and maintenance costs are externally funded, primarily by the Swiss Utilities, the national co-operative for the disposal of nuclear waste (NAGRA), the Federal Office of Energy (BFE) through the nuclear safety inspectorate (HSK) and the Federal Office for Science and Education (BBW) in connection with the EC Framework Programmes; an increasing part of external funding is coming from domestic and foreign industry (nuclear component and fuel suppliers). The activities of the department are concentrated on three main domains of: Safety and related problems of operating plants; safety features of ...
1999-09-01
Loss of coolant accident analysis (thermal hydraulic analysis) - Japanese industries experience
International Nuclear Information System (INIS)
An overview of LOCA analysis in Japanese industry is presented. The BASH-M code, developed for large scale LOCA reflooding analysis, is given as an example of verification and improvement of US computer programs are given. The code's application to the operational safety analysis concerns the following main areas: 1D drift flux model base computer program CANAC; CANAC-based advanced training simulator; emergency operating procedures. The author considers also the code application to the following new PWR safety design concepts: use of steam generators for decay heat removal at LOCA conditions; use of horizontal type steam generator for maintaining two-phase natural circulation under the reactor coolant system submerged. 9 figs.
1995-11-07
Health and Safety Research Division progress report for the period April 1, 1987--September 30, 1988
Energy Technology Data Exchange (ETDEWEB)
The mission of the Health and Safety Research Division (HASRD) is to provide a sound scientific basis for the measurement and assessment of human health impacts of radiological and chemical substances. Our approach to fulfilling this mission is to conduct a broad program of experimental, theoretical, and field research based on a strong foundation of fundamental physical studies that blend into well-established programs in life sciences. Topics include biomedical screening techniques, biological and chemical sensors, risk assessment, health hazards, dosimetry, nuclear medicine, environmental pollution monitoring, electron-molecule interactions, interphase physics, surface physics, data base management, environmental mutagens, carcinogens, and tetratogens.
1989-03-01
Geothermal Program Review VI: proceedings. Beyond goals and objectives
Energy Technology Data Exchange (ETDEWEB)
Program Review VI was comprised of six sessions, including an opening session, four technical sessions that addressed each of the major DOE research areas, and a session on special issues. The technical sessions were on Hydrothermal, Hot Dry Rock, Geopressured and Magma resources. Presenters in the technical sessions discussed their R and D activities within the context of specific GTD Programmatic Objectives for that technology, their progress toward achieving those objectives, and the value of those achievements to industry. The ''Special Issues'' presentations addressed several topics such as the interactions between government and industry on geothermal energy R and D; the origin and basis for the programmatic objectives analytical computer model; and international marketing opportunities for US geothermal equipment and services. The unique aspect of Program ...
1988-01-01
222-S Laboratory maintenance implementation plan
Energy Technology Data Exchange (ETDEWEB)
This Maintenance Improvement Plan has been developed for maintenance functions associated with the 222-S Laboratory. This plan is developed from the guidelines presented by Department of Energy (DOE) Order 4330.4B, Maintenance Management Program (DOE 1994), Chapter 11. The objective of this plan is to provide information for establishing and identifying WMH conformance programs and policies applicable to implementation of DOE Order 4330.4B guidelines. In addition, this maintenance plan identifies the actions necessary to develop a cost effective and efficient maintenance program at 222-S Laboratory. Maintenance activities are mainly going to be performed by existing maintenance organizations within Waste Management Federal Services of Hanford (WMH). Most maintenance performed at 222-S Laboratory is performed by the 222-S Laboratory maintenance organization. This 222-S Laboratory Maintenance Implementation Plan provides the ...
1997-08-13
Review of nuclear energy; Ydinenergian tilannekatsaus
Energy Technology Data Exchange (ETDEWEB)
The report is an overview on the production of the nuclear energy all over the world. The amount of production at present and in future, availability of the nuclear fuel, development of nuclear technology, environmental and safety issues, radioactive waste management and commissioning of the plants and also the competitivity of nuclear energy compared with other energy forms are considered. (91 refs.).
1997-05-01
Management and organizational design: an initial look at a new project
International Nuclear Information System (INIS)
This project is designed to establish one basis for empirically linking aspects of management and organizational design to the safe operation of nuclear power plants. Current work is focusing on (a) reviewing existing literature relevant to this linkage, and (b) isolating and incorporating numerous safety relevant indicators. Later stages of this project will involve hypothesis development, data collection and analysis.
1983-01-01
Chemical assessments for international programmes III
Environmental Research Database
DescriptionThis project continues DEFRA's commitment to the International Programme on Chemical Safety, a joint WHO/ILO/UNEP programme. DEFRA's contribution involves preparing Environmental Health Criteira Documents (EHCs), Concise International Chemical Assessments Documents (CICADS) and input to the OECD test Guidelines Programme and gneral risk assessment guidance. Peer reviews of documents prepared through other research in the IPCS network have also been carried out,as well as attending and hosting ta [continued...
2005-01-21
Energy Technology Data Exchange (ETDEWEB)
A review and a number of extracts are given of the statement made by the acting chairman of the CEGB at a press conference on the publication of documents in support of the case for the building of the proposed Sizewell B PWR. The documents comprise the CEGB Statement of Case proper, the Reference Design, the Pre-Construction Safety Report and some 300 supporting reports. Objectors have eight months to study the reports before the public inquiry into the CEGB's proposals due to open in January 1983.
1982-07-01
Safety assessment of South White Rose expansion project
Energy Technology Data Exchange (ETDEWEB)
Husky Oil Operations Ltd (Husky) is considering the development of the South White Rose Expansion (SWRX) area, located approximately 4 km south of the current Southern Glory Hole (SGH) in approximately 120 m of water. Within the new glory hole, one new drill centre will be constructed with wells tied back and into the SGH manifolds. The SWRX drill centre will comprise three horizontal production wells and two horizontal water injection wells with expansion capacity for eight wells. Husky is intending to submit a Development Plan Amendment to the Canada-Newfoundland and Labrador Offshore Petroleum Board (C-NLOPB) as part of the development. This document presented the results of a study that assessed the potential impact of the new development on existing White Rose safety studies. The study reviewed existing safety studies that were developed for the White Rose project to determine the potential impact of the new SWRX ...
2006-10-05
Construction: Masonry. Secondary Schools. Curriculum Guide.
This construction curriculum guide on masonry for secondary students is one of six developed for inservice teachers at Marianas High School in Saipan. The guide provides the rationale, description, goals, and objectives of the program; the program of studies and performance objectives by levels; samples of lesson plans for effective delivery of instruction; and a listing of references. Concepts covered include orientation to masonry construction, safety, tools and equipment, cement, concrete, concrete block masonry, concrete forms, and concrete reinforcement. Appended materials include transparency copies, tests and answer keys, information sheets, and student activities. (CT)
1980-08-01
British Library Electronic Table of Contents (United Kingdom)
Objective: To review data on efficacy and safety of second-generation antipsychotics (SGAs) in children and adolescents with psychotic and bipolar spectrum disorders. Methods: Medline/PubMed/Google Scholar search for studies comparing efficacy and/or tolerability: (i) between two or more SGAs; (ii) between SGAs and placebo; and (iii) between at least one SGA and one first-generation antipsychotic (FGA). The review focused on three major side-effect clusters: 1. body weight, body mass index, and cardiometabolic parameters, 2. prolactin levels, and 3. neuromotor side effects. Results: In total, 34 studies with 2719 children and adolescents were included. Studies lasted between 3weeks and 12months, with most studies (79.4%) lasting 3months or less. Nine studies (n=788) were conducted in patie...
2011-01-01
HAMMER FY 1996 Multi-Year Program Plan: WBS {number_sign}8.2
Energy Technology Data Exchange (ETDEWEB)
The Hazardous Material Management and Emergency Response Training and Education Center -- known simply as HAMMER -- is being developed to assist the US Department of Energy (DOE) and others dedicated to improving worker health, safety and productivity. HAMMER is a training and education program for hazardous material, waste management, and emergency response workers. HAMMER is managed by the DOE Richland Operations Office under Work Breakdown Structure (8.2). The 1996 Multi-Year Program Plan (MYPP) includes the Execution Year data and provides the information for Programmatic Fiscal Year Site Management System Execution Baseline, as well as the detailed work plan for performance evaluation of the authorized work. The MYPP incorporates various planning methodologies to define the program and provides essential program integration, and a fully developed technical, cost, and schedule ...
1995-09-01
Energy Technology Data Exchange (ETDEWEB)
A Lawrence Livermore National Laboratory (LLNL) Management Pre-Start Review (MPR) Team was formed to independently verify the operational readiness of Building 368 (B368) Biosafety Level III (BSL-3) Facility to conduct research with biological pathogens and toxins including those considered Select Agents. Review objectives and criteria were developed from the DOE/NNSA and LLNL requirements. These were provided in the Implementation Plan for the Biosafety Level III (BSL-3) Facility Management Pre-Start Review (BSL-3 MPR) at Lawrence Livermore National Laboratory that was reviewed and approved by DOE/NNSA-LSO. The formal part of the LLNL MPR for the BSL-3 Facility was begun in August of 2005 but work on the MPR was stopped in October of 2005 due to the need for LLNL to reassess organizational and operational controls and respond to Centers for Disease Control and Prevention inquiries related to a shipping ...
2006-07-25
Standardizing regulations on production of mining electrical equipment
Energy Technology Data Exchange (ETDEWEB)
The paper evaluates standardization of regulations on safety of electrical equipment for underground coal mines in the USSR. Factors increasing hazards of electrical failures of equipment in underground coal mines are analyzed: reduced lighting, increased humidity and dusts, damage caused by falling rocks or damage during haulage in underground workings, installation of electrical equipment in places easily accessible to untrained personnel. Standards on safety of electrical equipment for underground coal mining valid in the USSR are reviewed: the PIRNEh regulations on production of electrical equipment for coal mines developed by the VNIIVEh Institute, and the GOST national standards. International cooperation within the COMECON on safety of mining electrical equipment (the Interelectro Committee of the COMECON) is described. Certification of electrical equipment for coal mines is discussed on the ...
1983-02-01
Restart of K-Reactor, Savannah River Site: Safety evaluation report
Energy Technology Data Exchange (ETDEWEB)
This Safety Evaluation Report (SER) focuses on those issues required to support the restart of the K-Reactor at the Savannah River Plant. This SER provides the safety criteria for restart and documents the results of the staff reviews of the DOE and operating contractor activities to meet these criteria. To develop the restart criteria for the issues discussed in this SER, the Savannah River Restart Office and Savannah River Special Projects Office staffs relied, when possible, on commercial industry codes and standards and on NRC requirements and guidelines for the commercial nuclear industry. However, because of the age and uniqueness of the Savannah River reactors, criteria for the commercial plants were not always applicable. In these cases, alternate criteria were developed. The restart criteria applicable to each of the issues are identified in the safety evaluations for each issue. The restart ...
1991-04-01
LERF Assessment on the AOT changes for Kori 3 and 4 / Yonggwang 1 and 2
International Nuclear Information System (INIS)
Allowed outage time (AOT), which is required by the technical specification of nuclear power plants (NPPs), has been determined on the basis of deterministic analysis or engineering judgment. AOT is defined as the time for which safety related components can remain inoperable before a plant state is changed. Recently, plants' operating experiences and probabilistic safety assessment (PSA) results show that the AOT could be optimized. Foreign NPPs licensees have changed their technical specifications including AOT using PSA techniques. In 1998, U.S. NRC issued the regulatory guides on risk informed decision-making and technical specification changes, and these are Reg. Guide 1.174, and 1.177. The US NRC accepted AOT extension proposals including the safety injection tank (SIT) and low pressure safety injection system (LPSI) for the ABB-CE designed plants. This paper discusses interim results of AOT ...
2007-05-10
Organizational model of control of state of technology in the coal industry
Energy Technology Data Exchange (ETDEWEB)
This paper discusses organizational models of planning technology development in coal mining. The following 4 planning systems are analyzed: all-union national system coordinated by the Ministry of Coal Mining of the USSR, all-union associations of coal mine associations (in the Ukrainian SSR the plan is developed by the Ministry of Coal Industry of the Republic), associations of coal mines, coal mines or groups of coal mines. Methods for developing programs for technology development at 4 levels are reviewed. The following planning periods are used: 10 years or more (from 1980 to 1990), a 5 year period and a 1 year period. System for technology development in the Soviet coal industry from 1981 to 1985 is evaluated: research and development programs (20 comprehensive state programs, 36 branch programs). (In Russian)
1984-02-01
Federal Geothermal Research Program Update Fiscal Year 1999
Energy Technology Data Exchange (ETDEWEB)
The Department of Energy (DOE) and its predecessors have conducted research and development (R&D) in geothermal energy since 1971. To develop the technology needed to harness the Nation's vast geothermal resources, DOE's Office of Geothermal and Wind Technologies oversees a network of national laboratories, industrial contractors, universities, and their subcontractors. The following mission and goal statements guide the overall activities of the Office of Geothermal and Wind Technologies. This Federal Geothermal Program Research Update reviews the specific objectives, status, and accomplishments of DOE's Geothermal Program for Federal Fiscal Year (FY) 1999. The information contained in this Research Update illustrates how the mission and goals of the Office of Geothermal and Wind Technologies are reflected in each R&D activity. The Geothermal Program, from its ...
2004-02-01
System 80+trademark Standard Design: CESSAR design certification
International Nuclear Information System (INIS)
This report, entitled Combustion Engineering Standard Safety Analysis Report -- Design Certification (CESSAR-DC), has been prepared in support of the industry effort to standardize nuclear plant designs. These volumes describe the Combustion Engineering, Inc. System 80"+trademark Standard Design. This volume 11 discusses Radiation Protection, Conduct of Operations, and the Initial Test Program.
Summary of Initial Testing of SuperLig 644 at the TFL Ion Exchange Facility
Energy Technology Data Exchange (ETDEWEB)
Research at the Savannah River Technology Center aided development of a technical design basis for a Waste Treatment Plant (WTP) to pre-treat and vitrify Hanford tank waste as part of the River Protection Project (RPP). The research addresses safety concerns, process optimization, and waste form compliance. This program will provide technical data to ensure that the process functions as it was designed and minimizes costs.
2001-04-17
Risk orientated analysis of the SNR 300
International Nuclear Information System (INIS)
To make a quantitative comparison of risks between the SNR 300 and a modern PWR (Biblis B), the consequences of an accident or the extent of damage of a release of radionuclides to the environment due to an accident are estimated by computer programs for accident consequence models. The accident analysis includes an analysis of events for Bethe-Tait accidents with failure of the outer containment. The FGSB release rates are compared with those of the Society for Reactor Safety (GRS). (HP).
Quality assurance requirements for the design of nuclear fuel reprocessing facilities
International Nuclear Information System (INIS)
Requirements and guidance are provided for a quality assurance program for the design of nuclear fuel reprocessing facilities involving structures, systems and components whose satisfactory performance is required to prevent accidents that could cause undue risk to the health and safety of the public, or to mitigate the consequences of such accidents if they were to occur. The standard is to be used in conjunction with ANSI N46.2.
Melter Disposal Strategic Planning Document
Energy Technology Data Exchange (ETDEWEB)
This document describes the proposed strategy for disposal of spent and failed melters from the tank waste treatment plant to be built by the Office of River Protection at the Hanford site in Washington. It describes program management activities, disposal and transportation systems, leachate management, permitting, and safety authorization basis approvals needed to execute the strategy.
2000-09-25
UK PubMed Central (United Kingdom)
BackgroundPaclitaxel-eluting stents decrease angiographic and clinical restenosis following percutaneous coronary intervention compared to bare metal stents. TAXUS Element is a third-generation...Full Text Available
The automatic programming for safety-critical software in nuclear power plants
Energy Technology Data Exchange (ETDEWEB)
We defined the Korean unique safety-critical software development methodology by modifying Dr. Harel`s statechart-based on formal methods in order to digitalized the reactor protection system. It is suggested software requirement specification guideline to specify design specification which is basis for requirement specification and automatic programming by the caused by shutdown parameter logic of the steam generator water level for Wolsung 2/3/4 unit SDS no.1 and simulated it by binding the Graphic User Interface (GUI). We generated the K and R C code automatically by utilizing the Statemate MAGNUM Sharpshooter/C code generator. Auto-generated K and R C code is machine independent code and has high productivity, quality and provability. The following are the summaries of major research and development. - Set up the Korean unique safety-critical software development methodology - Developed software requirement ...
1998-06-01
International Nuclear Information System (INIS)
The Belgian Tihange 2 nuclear power plant went into commercial operation in 1983 producing a thermal power of 2785 MW. Since the commissioning of the plant the steam generators U-tubes have been affected by primary stress corrosion cracking. In order to avoid further degradation of the performance and an increase in repair costs, Electrabel, the owner of the plant, decided in 1997 to replace the 3 steam generators. This decision was supported by the feasibility study performed by Tractebel Energy Engineering which demonstrated that an increase of 10% of the initial power together with a fuel cycle length of 18 months was achieved. Tractebel Energy Engineering was entrusted by Electrabel as the owner's engineer to manage the project. This paper presents the role of Tractebel Energy Engineering in this project and the safety analysis program necessary to justify the new operation point and the fuel cycle extension to 18 months re-analysis of FSAR ...
2002-08-11
Quality assurance requirements for packaging and transportation of radioactive materials
International Nuclear Information System (INIS)
This paper discusses the new quality assurance regulations of the Nuclear Regulatory Commission (NRC) for packaging and transportation of radioactive materials. These regulations became effective on October 18, 1977. Background information concerning these regulations and packaging and transportation history is included. The quality assurance program is described with indications of how it is composed of general (administrative) provisions which must meet the 18 quality assurance criteria and be approved by the NRC; specific provisions which appear in the DOT and NRC regulations and in the individual package design approval; and other specific procedures which are not required by regulations but which are necessary for the proper control of quality. The quality assurance program is to be developed using a graded approach for the application of pertinent criteria and optimizing the required degree of safety and control ...
Energy Technology Data Exchange (ETDEWEB)
Six safety initiatives have been identified for accelerating the resolution of waste tank safety issues and closure of unreviewed safety questions. Safety Initiative 5 is to reduce safety and environmental risk from tank leaks. Item d of Safety Initiative 5 is to complete corrosion studies of single-shell tanks to determine failure mechanisms and corrosion control options to minimize further degradation by June 1994. This report has been prepared to fulfill Safety Initiative 5, Item d. The corrosion mechanisms that apply to Hanford Site single-shell tanks are stress corrosion cracking, pitting/crevice corrosion, uniform corrosion, hydrogen embrittlement, and microbiologically influenced corrosion. The corrosion data relevant to the single-shell tanks dates back three decades, when results were obtained from in-situ corrosion coupons in a few ...
1994-06-01
Quality assurance considerations in nuclear waste management
International Nuclear Information System (INIS)
Proper use of quality assurance will provide the basis for an effective management control system for nuclear waste management programs. Control is essential for achieving successful programs free from costly losses and failures and for assuring the public and regulators that the environment and health and safety are being protected. The essence of quality assurance is the conscientious use of planned and systematic actions, based on selecting and applying appropriate requirements from an established quality assurance standard. Developing a quality assurance program consists of using knowledge of the technical and managerial aspects of a project to identify and evaluate risks of loss and failure and then to select appropriate quality assurance requirements that will minimize the risks. Those requirements are integrated into the project planning documents and are carried out as specific actions during ...
Data report of BWR post-CHF tests. Transient core thermal-hydraulic test program. Contract research
Energy Technology Data Exchange (ETDEWEB)
JAERI has been performing transient core thermal-hydraulic test program. In the program, authors performed BWR/ABWR DBE simulation tests with a test facility, which can simulate BWR/ABWR transients. The test facility has a 4 x 4 bundle core simulator with 15-rod heaters and one non-heated rod. Through the tests, authors quantified the thermal safety margin for core cooling. In order to quantify the thermal safety margin, authors collected experimental data on post-CHF. The data are essential for the evaluation of clad temperature transient when core heat-up occurs during DBEs. In comparison with previous post-CHF tests, present experiments were performed in much wider experimental condition, covering high clad temperature, low to high pressure and low to high mass flux. Further, data at wider elevation (lower to higher elevation of core) were obtained in the present experiments, which make possible to ...
2001-03-01
Energy Technology Data Exchange (ETDEWEB)
In the thermal hydraulics codes developed for fire safety analysis and for containment thermal hydraulic analysis, junctions in the multi-compartment geometries is often modeled as uni-directional junctions. However, ceiling junctions are known to depict unstable/oscillatory bi-directional flow behavior. Detailed investigations have been carried out to understand the unstable flow behaviour of a junction by analyzing an earlier reported experiment and its subsequent two dimensional numerical RANS based study of fire in an enclosure. The authors attempt more realistic and desired three dimensional and inherently transient large eddy simulations using a computer code Fire Dynamics Simulator (FDS). The paper presents the details of the analysis, the results obtained and further studies required to be conducted so that the findings can be applied to the fire/containment thermal hydraulics analysis codes successfully. (orig.)
2011-05-15
Radiation protection. A guide for scientists and physicians
International Nuclear Information System (INIS)
This manual was written for individuals who wish to become qualified in radiation protection as an adjunct to working with sources of ionizing radiation or using radionuclides in the field of medicine. It provides the radiation user with information needed to protect himself and others and to understand and comply with governmental and institutional regulations regarding the use of radionuclides and radiation machines. It is designed for a wide spectrum of users, including physicians, research scientists, engineers, and technicians. It should be useful also to radiation safety officers, members of radiation safety committees, and others who are responsible for the proper use of radiation sources, although they may not be working with the sources directly. The presentation in this manual is designed to obviate the need for reviews of atomic and radiation physics, and the mathematics has been limited to elementary ...
Nuclear cask testing films misleading and misused
Energy Technology Data Exchange (ETDEWEB)
In 1977 and 1978, Sandia National Laboratories, located in Albuquerque, New Mexico, and operated for the US Department of Energy (DOE), filmed a series of crash and fire tests performed on three casks designed to transport irradiated nuclear fuel assemblies. While the tests were performed to assess the applicability of scale and computer modeling techniques to actual accidents, films of them were quickly pressed into service by the DOE and nuclear utilities as ``proof`` to the public of the safety of the casks. In the public debate over the safety of irradiated nuclear fuel transportation, the films have served as the mainstay for the nuclear industry. Although the scripts of all the films were reviewed by USDOE officials before production, they contain numerous misleading concepts and images, and omit significant facts. The shorter versions eliminated qualifying statements contained in the longer version, and created false ...
1991-10-01
Incorporation of organizational failures in PSA
International Nuclear Information System (INIS)
A large portion of the work performed at nuclear power plants follows standardized flow paths. For example, although components on which the maintenance crew works differ from one assignment to the next, all assignments basically follow the same process: requesting, reviewing, planning, scheduling, executing, testing, and documenting the work. In general, the term open-quotes work processclose quotes is used to refer to a standardized sequence of tasks designed within the operational environment of an organization to achieve a specific goal. The predictable nature of work processes suggests that a systematic analysis can be conducted to identify the desirable design of the process and to develop performance measures with respect to the strengths and weaknesses in the process. Furthermore, because of the close relationship of the work process to plant performance and plant safety, it is believed that such an analysis will facilitate the ...
1993-06-20
International Nuclear Information System (INIS)
This study evaluates the degree to which surface impoundments at licensed facilities comply with significant changes in NRC requirements initiated by enactment of EPA's final environmental standards for uranium recovery facilities (40 CFR Part 192). Impoundment liner requirements, ground-water protection standards, ground-water monitoring and corrective action programs, and site closure standards are the most significant regulatory modifications. The compliance status of 30 conventional mills and 31 in-situ mines is determined from a review of Nuclear Regulatory Commission and agreement state docket files through November, 1983. Results of this review show that a majority of conventional uranium mill tailings management systems are deficient with respect to liner requirements for new impoundments or proposed expansions to existing impoundments, as well as with respect to some aspects of ground-water monitoring and ...
DOE/NORA/BNL oil heat research agenda development
Energy Technology Data Exchange (ETDEWEB)
The National Oilheat Research Alliance (NORA) has been formed and is currently working to establish a Congressionally approved oilheat check-off program to provide funding for research, education, training, safety, and marketing to benefit the US oilheat industry. NORA will be presenting this program to the Congress for its consideration and approval in the coming year. It will follow the same path as the National Propane Gas Association which is currently working on obtaining Congressional approval of a propane check off program that has already attracted over 120 cosponsors in the House of representatives. An effort to define the basis of a joint US Department of Energy (DOE) and Oilheat industry (marketers) program for future oilheat equipment research and development will be conducted during FY-1996. At the request of NORA representatives BNL will coordinate the development of a ...
1996-07-01
The Los Alamos National Laboratory Environmental Restoration Program
Energy Technology Data Exchange (ETDEWEB)
The LANL Environmental Restoration (ER) Program Office, established in October 1989, is faced with the challenge of assessing and cleaning up nearly 1,8000 potentially hazardous waste sites according to an aggressive corrective action schedule that the Environmental Protection Agency (EPA) mandated on May 23, 1990, in a Resource, Conservation, and Recovery Act (RCRA) Part B Permit. To maximize program efficiency, the ER Program Office will implement a unique management approach designed to maximize the use of laboratory technical expertise. The Installation Work Plan, which provides a blueprint for the program, has been submitted to EPA for review and approval. A work plan for characterization of Technical Area 21, an early plutonium processing facility, is also nearing completion. The feasibility of an expedited cleanup of the Laboratory's worst hazardous waste release has ...
1990-01-01
Laboratory directed research and development program, FY 1996
Energy Technology Data Exchange (ETDEWEB)
The Ernest Orlando Lawrence Berkeley National Laboratory (Berkeley Lab) Laboratory Directed Research and Development Program FY 1996 report is compiled from annual reports submitted by principal investigators following the close of the fiscal year. This report describes the projects supported and summarizes their accomplishments. It constitutes a part of the Laboratory Directed Research and Development (LDRD) program planning and documentation process that includes an annual planning cycle, projection selection, implementation, and review. The Berkeley Lab LDRD program is a critical tool for directing the Laboratory`s forefront scientific research capabilities toward vital, excellent, and emerging scientific challenges. The program provides the resources for Berkeley Lab scientists to make rapid and significant contributions to critical national science and technology problems. The ...
1997-02-01
NPD Canada's first nuclear power station
Energy Technology Data Exchange (ETDEWEB)
This talk reviews the history of the Canadian nuclear-electric program highlighting Canada's first nuclear power station, the Nuclear Power Demonstration or NPD. NPD was commissioned and delivered electricity to Canadian consumers for the first time on june 4, 1962. The Canadian nuclear-electric program is based on the CANDU-PHW (Canadian Deuterium Uranium - Pressurized Heavy Water) concept which was conceived between 1955 and 1958 at the Chalk River Nuclear Laboratory (CRNL) of AECL, located a few miles from Deep River. This talk covers the history of the Canadian nuclear-electric activities dating back to 1939.
2002-07-01
Irradiation studies of fusion reactor materials utilizing FFTF/MOTA
International Nuclear Information System (INIS)
The most important and difficult part of materials research for fusion reactor is realized to be irradiation studies of fusion reactor materials. Irradiation studies of fusion reactor materials utilizing FFTF/MOTA, as one of Japan/U.S.A. Fusion Collaboration Programs, have important role to establish fundamental understanding of heavy irradiation effects on materials behavior and properties and to develop methods and technologies for advanced irradiation studies under fusion reactor environment. This paper briefly reviews the history, the state of the art, and the future of the FFTF/MOTA program. (author).
GIT Constructions of Moduli Spaces of Stable Curves and Maps
This largely expository paper first gives an introduction to Hilbert stability and its use in Gieseker's GIT construction of $\\overline{M}_g$. Then I review recent work in this area--variants for unpointed curves that arise in Hassett's log minimal model program, starting with Schubert's moduli space of pseudostable curves, and constructions for weighted pointed stable curves and for pointed stable maps due to Swinarski and to Baldwin and Swinarski respectively. The focus is on the steps at which new ideas are needed. Finally, I list open problems in the area, particularly some arising in the log minimal model program that seem inaccessible to current techniques.
2008-01-01
Dynamic programming and graph algorithms in computer vision.
Optimization is a powerful paradigm for expressing and solving problems in a wide range of areas, and has been successfully applied to many vision problems. Discrete optimization techniques are especially interesting since, by carefully exploiting problem structure, they often provide nontrivial guarantees concerning solution quality. In this paper, we review dynamic programming and graph algorithms, and discuss representative examples of how these discrete optimization techniques have been applied to some classical vision problems. We focus on the low-level vision problem of stereo, the mid-level problem of interactive object segmentation, and the high-level problem of model-based recognition. PMID:20660950
2011-04-01
The US Advanced Liquid Metal Reactor and the Fast Flux Test Facility Phase IIA passive safety tests
International Nuclear Information System (INIS)
This report discusses the safety approach of the Advanced Liquid Metal reactor program, sponsored by the US Department of Energy, which relies upon passive reactor responses to off-normal condition to limit power and temperature excursions to levels that allow safety margins. Gas expansion modules (GEM) have included in the design to provide negative reactivity to enhance these margins in the extremely unlikely event that pumping power is lost and the highly reliable scram system fails to operate. The feasibility and beneficial features of these devices were first demonstrated in the core of the Fast Flux Test Facility (FFTF) in 1986. Preapplication safety evaluations by the US Nuclear Regulatory Commission have identified areas that must be addressed if these devices are to be relied on. One of these areas is the response of the reactor when it is critical and the pumps are turned on, resulting in ...
1992-10-25
International Nuclear Information System (INIS)
The safety approach of the Advanced Liquid Metal Reactor program, sponsored by the U.S. Department of Energy, relies upon passive reactor responses to off-normal conditions to limit power and temperature excursions to levels that allow large safety margins. Gas expansion modules (GEM) have been included in the design to provide negative reactivity to enhance these margins in the extremely unlikely event that pumping power is lost and the highly reliable scram system fails to operate. The feasibility and beneficial features of these devices were first demonstrated in the core of the Fast Flux Test Facility (FFTF) in 1986. Pre-application safety evaluations by the U.S. Nuclear Regulatory Commission have identified areas that must be addressed if these devices are to be relied on. One of these areas is the response of the reactor when it is critical and the pumps are turned on, resulting in positive ...
Developments in indirect coal liquefaction in slurry-phase and other reaction systems
This report accounts for Task 3 of DOE Contract No. AC01-81FE-05077. It reviews the developments in indirect coal liquefaction with emphasis on slurry-phase reactors and catalysis. This report also discusses topics related to indirect coal liquefaction research, such as analytical techniques in catalysis. The subjects covered in this report were selected by DOE. This report is the third and final task report of the three major tasks in this contract. The first task, ''Direct Coal Liquefaction Catalyst Development - Program Review and Research Perspectives'', was completed in November 1982. The second task, ''Review of Direct Coal Liquefaction by Slurry-Phase Catalysis'', was completed in September 1983. 47 refs., 66 figs., 50 tabs.
1984-02-01
Physics and quality assurance of low dose rate brachytherapy
International Nuclear Information System (INIS)
Purpose: The purpose of this course is to review the physical principles underlying design, clinical application and execution of interstitial and intracavitary implants in the classical low dose-rate (LDR) range. This year, the course will focus on quality assurance of sources, applicators and treatment planning software. In addition, development of procedures and QA checks designed optimize treatment delivery accuracy and patient safety during each individual procedure will be reviewed. The level of presentation will be designed to accommodate both physicists and physicians. Implementation of recently published AAPM Task Group reports (no. 40, 'Comprehensive Quality Assurance' and No. 43, 'Dosimetry of Interstitial Brachytherapy Sources') will be reviewed. Outline: (A) General Principles (1) QA endpoints: temporal accuracy, positional accuracy, dose delivery accuracy, and safety ...
Review of Regulatory Quality Assurance Requirements for the Operation of Nuclear R and D Facilities
International Nuclear Information System (INIS)
Korea Atomic Energy Research Institute (KAERI) has many R and D facilities in operation, including HANARO research reactor, radioactive waste treatment facility (RWTF), post-irradiation examination facility (PIEF) and irradiated material test facility (IMEF). Recently, nation-wide interest is focused on the safety and security of major industrial facilities. Safe operation of nuclear facilities is imperative because of the consequence of public disaster by radiological release/ contamination, in case of an accident. Recently, Ministry of Science and Technology (MOST) of the Korean government announced amendments of Atomic Energy laws to enforce requirements of the physical protection and radiological emergency. In this paper, the context of amended Atomic Energy laws were reviewed to confirm quality assurance measures and identify additional QA activities, if any, that is required by the amendment
2005-10-27
Operational procedures - industry observations and opportunities for improvement
Energy Technology Data Exchange (ETDEWEB)
The purpose of this paper is to relate some of the commonly encountered problems with operational procedures in the nuclear industry and offer practical suggestions for their elimination. The paper is based on recent consultant experience in assisting industry clients with human performance related design and assessment initiatives. Operational procedures are a key part of an integrated system design. Procedures provide the specified instructions for actions people are to undertake in operating a facility to achieve production and safety goals. While organizations continue to make substantial investments in procedure development and maintenance, problems with procedures continue to occur, as evidenced through operating inefficiencies, errors, and events. The paper reviews the role procedures play in facility operations, comments on current development and maintenance practices, discusses the extent of human performance related problems ...
2003-07-01
Impacts of Imported Liquefied Natural Gas on Residential Appliance Components: Literature Review
Energy Technology Data Exchange (ETDEWEB)
An increasing share of natural gas supplies distributed to residential appliances in the U.S. may come from liquefied natural gas (LNG) imports. The imported gas will be of a higher Wobbe number than domestic gas, and there is concern that it could produce more pollutant emissions at the point of use. This report will review recently undertaken studies, some of which have observed substantial effects on various appliances when operated on different mixtures of imported LNG. While we will summarize findings of major studies, we will not try to characterize broad effects of LNG, but describe how different components of the appliance itself will be affected by imported LNG. This paper considers how the operation of each major component of the gas appliances may be impacted by a switch to LNG, and how this local impact may affect overall safety, performance and pollutant emissions.
2009-12-09
Engineering Properties of Polymeric-Based Antimicrobial Films for Food Packaging: A Review
British Library Electronic Table of Contents (United Kingdom)
The concept of antimicrobial packaging has received great attention because of its potential to enhance food safety. Several studies have explored its applications and effectiveness to suppress pathogenic microorganisms. However, few studies have analyzed the alterations caused in the engineering properties of food-packaging polymers after the incorporation of antimicrobials. Such information is very important to understand the feasibility of producing antimicrobial packaging films on the industrial scale. This review explores the work done so far to evaluate how the incorporation of antimicrobial substances affects the properties of food-packaging systems. This article also emphasizes diffusion studies on antimicrobial substances through packaging films and the analytical solutions used t...
2011-01-01
International Nuclear Information System (INIS)
According to the present concept, the low and intermediate level wastes generated during the Cernavoda NPP operation will be disposed in a near surface repository. The Saligny site, placed in the NPP protected area, has been proposed for their disposal. Geologically, the main components of this site are the quaternary loess, the Precambrian and Pre-quaternary clays, the Eocene and Barremian limestone. Hydrologically, the site can be divided into a vadose zone down to 45-50 m and three distinct aquifers, two of them in the limestone beds and the third in the lenses of sand and limestone existing in the pre-quaternary clay layer. A large research program for site characterization was initiated in 1996. At present, the site characteristics requested for safety analysis have been experimentally measured on soil samples or calculated by different computer programs. Hundreds of experimental values of the density, porosity, ...
2004-09-09
Safety philosophy and concepts for large liquid metal breeder reactor power plants
International Nuclear Information System (INIS)
This paper will adress the unique safety related aspects of the LMFBR concept which are of significance to containment design and structural analyses. Topics to be covered will include: primary boundary integrity assurance; effects of sodium spills on integrity of structures; provisions being considered for containment of melted cores; and fuel handling accidents. Specific reference will be made to the FFTF and the Clinch River Breeder Reactor Project designs and methods of treatment of the above problems. In particular, the part played by tests, such as those carried out on a simulated FFTF model, and the planned structural reliability and related programs will be considered. Where practicable, these topics will be addressed in a manner which places FFTF and CRBR in context with other LMFBR's, and will point to a possible direction for future American LMFBR designs.
1975-09-01
Human reliability analysis in Wolsung 2/3/4 nuclear power plants probabilistic safety assessment
Energy Technology Data Exchange (ETDEWEB)
The Level 1 probabilistic safety assessment (PSA) for Wolsung(WS) 2/3/4 nuclear power plant (NPPs) in design stage is performed using the methodologies being equivalent to PWR PSA. Accident sequence evaluation program (ASEP) human reliability analysis (HRA) procedure and technique for human error rate prediction (THERR) are used in HRA of WS 2/3/4 NPPs PSA. The= purpose of this paper is to introduce the procedure and methodology of HRA in WS 2/3/4 NPPs PSA. Also, this paper describes the interim results of importance analysis for human actions modeled in WS 2/3/4 PSA and the findings and recommendations of administrative control of secondary control area from the view of human factors. (Author) 10 refs., 2 tabs.
1997-05-01
Human reliability analysis in Wolsong 2/3/4 nuclear power plants probabilistic safety assessment
International Nuclear Information System (INIS)
The Level 1 probabilistic safety assessment (PSA) for Wolsong(WS) 2/3/4 nuclear power plant(NPPs) in design stage is performed using the methodologies being equivalent to PWR PSA. Accident sequence evaluation program (ASEF) human reliability analysis (HRA) procedure and technique for human error rate prediction (THERP) are used in HRA of WS 2/3/4 NPPs PSA. The purpose of this paper is to introduce the procedure and methodology of HRA in WS 2/3/4 NPPs PSA. Also, this paper describes the interim results of importance analysis for human actions modeled in WS 2/3/4 PSA and the findings and recommendations of administrative control of secondary control area from the view of human factors.
1997-05-01
Control maintenance training program for special safety systems at Bruce B
Energy Technology Data Exchange (ETDEWEB)
It was recognized from the early days of commissioning of Bruce B that Control Maintenance staff would require a level of expertise to be able to maintain Special Safety Systems in proper running order. In the early 80's this was achieved through hands on experience during the original commissioning, troubleshooting and placing of the various systems in service. Control maintenance procedures were developed and implemented as the new systems came available for commissioning, as were operating manuals,training manuals etc. Under the development of the Maintenance Manager, a Conduct of Maintenance section was organized. One of the responsibilities of this section was to develop a series of Maintenance Administrative Procedures (MAPs) that set the standards for maintenance activities including training.
1997-07-01
Advanced Simulation & Computing FY09-FY10 Implementation Plan Volume 2, Rev. 0
Energy Technology Data Exchange (ETDEWEB)
The Stockpile Stewardship Program (SSP) is a single, highly integrated technical program for maintaining the safety and reliability of the U.S. nuclear stockpile. The SSP uses past nuclear test data along with current and future nonnuclear test data, computational modeling and simulation, and experimental facilities to advance understanding of nuclear weapons. It includes stockpile surveillance, experimental research, development and engineering programs, and an appropriately scaled production capability to support stockpile requirements. This integrated national program requires the continued use of current facilities and programs along with new experimental facilities and computational enhancements to support these programs. The Advanced Simulation and Computing Program (ASC)1 is a cornerstone of the SSP, providing ...
2008-04-30
In the Savannah River Site's (SRS') Solid Waste Management Program, a key to success is the Public Involvement Program. The Solid Waste Division at SRS manages the site's transuranic, low-level, mixed, and hazardous wastes. All decisions associated with management of this waste are of interest to the public and successful program implementation would be impossible without a vigorous public involvement program. The SRS Solid Waste Division (SWD) and its Department of Energy (DOE) customer developed, implemented, and maintain a comprehensive public participation and communications program. It is staffed by public participation and technical specialists to ensure information is presented in a manner that is technically accurate while being tailored for understanding by people without a technical background. The program provides the public ...
2003-02-27
Systems analysis of the CANDU 3 Reactor
International Nuclear Information System (INIS)
This report presents the results of a systems failure analysis study of the CANDU 3 reactor design; the study was performed for the US Nuclear Regulatory Commission. As part of the study a review of the CANDU 3 design documentation was performed, a plant assessment methodology was developed, representative plant initiating events were identified for detailed analysis, and a plant assessment was performed. The results of the plant assessment included classification of the CANDU 3 event sequences that were analyzed, determination of CANDU 3 systems that are ''significant to safety,'' and identification of key operator actions for the analyzed events.
Acute agitation is a frequent reason for emergency psychiatric intervention. It is important to intervene early to avoid escalation of agitation to aggression. Reducing risk by using effective treatments will result in fewer instances of seclusion and restraint, and fewer injuries to staff and patients. This paper will first review the epidemiology of aggressive behavior and mental disorders, followed by a discussion of assessment and diagnostic considerations. The pathophysiology of safety risk is discussed within the context of the model of the "triune brain." Pharmacological treatment strategies for acute episodes of agitated behavior will be discussed in detail. This includes newer formulations of novel antipsychotics such as liquids and rapidly disintegrating tablets, as well as intramuscular preparations. PMID:15335224
2004-01-01
Buried gas pipelines under vehicular crossings
Energy Technology Data Exchange (ETDEWEB)
This paper describes and evaluates the various methods used in the analysis and design of buried pipelines under vehicular crossings extracted from a vast number of literature. It was found that a unified treatment of the subject is currently not available and additional work is required. The study shows that there are sufficient data and technical information that can be integrated to produce sound design. Theoretical as well as empirical formulas are scrutinized and incorporated in their appropriate places. Design examples are presented, complete with the detail calculations. Where applicable nomographs and graphs are adapted as design aids. A brief review of the current safety codes pertaining to natural gas pipeline design is also presented.
1984-03-01
A framework for the establishment of organizational risk indicators
International Nuclear Information System (INIS)
Organizational risk indicators are proposed as a tool for risk control during operation of offshore installations, as a complement to QRA-based indicators. An organizational factor framework is developed based on a review of existing organizational factor frameworks, research on safety performance indicators, and previous work on QRA-based indicators. The results comprise a qualitative organizational model, proposed organizational risk indicators, and a quantification methodology for assessing the impact of the organization on risk. The risk indicators, when validated, will aid in a frequent control of the risk in the periods between the updating of the quantitative risk assessments.
2001-11-01
CANDU 9 - the CANDU product to meet customer and regulator requirements now and in the future
Energy Technology Data Exchange (ETDEWEB)
CANDU reactors developed under Canadian licensing regulations that placed the primary responsibility for safety on the licensee. The Atomic Energy Control Board (AECB), Canada's nuclear regulatory agency, state in their regulations what is expected in terms of safety performance so that designers are free to propose the best means of meeting this performance. This goal-oriented approach, besides encouraging innovation, allowed CANDU to be licensed in other jurisdictions. The latest design - the large, single unit, CANDU 9 - explicitly incorporates licensability in Canada through a formal AECB review of the design; lessons learned from licensing CANDU 6 in Asian countries, particularly with Wolsong 2, 3 and 4 in Korea, and more recently with Qinshan in China; utility requirements for modem evolutionary plants; and emerging international standards for safety, sponsored or issued by the IAEA. By ...
1998-07-01
CANDU 9 - the CANDU product to meet customer and regulator requirements now and in the future
International Nuclear Information System (INIS)
CANDU reactors developed under Canadian licensing regulations that placed the primary responsibility for safety on the licensee. The Atomic Energy Control Board (AECB), Canada's nuclear regulatory agency, state in their regulations what is expected in terms of safety performance so that designers are free to propose the best means of meeting this performance. This goal-oriented approach, besides encouraging innovation, allowed CANDU to be licensed in other jurisdictions. The latest design - the large, single unit, CANDU 9 - explicitly incorporates licensability in Canada through a formal AECB review of the design; lessons learned from licensing CANDU 6 in Asian countries, particularly with Wolsong 2, 3 and 4 in Korea, and more recently with Qinshan in China; utility requirements for modem evolutionary plants; and emerging international standards for safety, sponsored or issued by the IAEA. By combining ...
1998-05-03
A risk based approach to assess the incidence of ice loads on small concrete dams
International Nuclear Information System (INIS)
Some considerations regarding ice load in risk-based dam safety analysis are presented for small concrete dams. The most significant physical mechanisms leading to ice thrust on dams (such as thermal expansion and water level fluctuations) are outlined. Published literature on dam ice loads to examine ice load magnitude-return period relationships, sliding and overstressing failure mechanisms and structural performance criteria to resist ice loads, are also reviewed. Related loading combinations for structural safety evaluations were determined regarding the issue of simultaneity of ice loads with other events such as earthquakes. Parametric analyses were conducted on a small gravity dam section, 3m high, and a taller dam, 17.9 m high, to demonstrate the ultimate ice load carrying capability as a function of dam geometry and shear and tensile strengths of construction joints. Since the failure mechanism of a dam subjected ...
Energy Technology Data Exchange (ETDEWEB)
The Fourth Annual Participants' Information Meeting of the Department of Energy Low-Level Waste Management Program was held in Denver, Colorado, August 31 to September 2, 1982. The purpose of the meeting was to report and evaluate technology development funded by the program and to examine mechanisms for technology transfer. The meeting consisted of an introductory plenary session, followed by two concurrent overview sessions and then six concurrent technical sessions. There were two group meetings to review the findings of the technical sessions. The meeting concluded with a plenary summary session in which the major findings of the meeting were addressed. All papers have been abstracted and indexed for the Energy Data Base.
1982-10-01
Adapting United States training practices to European utilities
International Nuclear Information System (INIS)
The factors which must be considered in the process of adapting United States nuclear utility training programs to the needs of a European utility are discussed. Following a review of the present situation and drawing up of a new training program, the management commitments in terms of personnel and finance must be considered. Short term, medium and long term programs are outlined. The long term objectives should include the establishment of a total training centre. This facility should be capable of providing all the training necessary to operate a power plant safely. This would include specific simulator training, classroom training for operators, technician training, staff training, management training etc. In addition to a simulator, it should include an emergency response facility to train personnel. (U.K.).
International Nuclear Information System (INIS)
The IAEA Code of Practice on Quality Assurance for Safety in Nuclear Power Plants and the corresponding Safety Guides are reviewed and compared with quality assurance (QA) practices in the IAEA Member States. The QA requirements stipulated by the Code place on the nuclear power plant owner the responsibility to establish an overall QA programme for the plant. In selecting the QA programme level for specific activities, the Code allows of a flexible approach but does not specify gradation in programme requirements. The Code is placing the burden of quality-achieving and quality-assuring functions on the task-performing organizations, namely the designers, manufacturers, constructors and plant operators. The plant owner provides for the management of the overall QA programme, surveillance of activities and verifications of the effectiveness of the constituent programmes of all project participants through programme audits and ...
Tropospheric sampling with aircraft
Energy Technology Data Exchange (ETDEWEB)
Aircraft constitute a unique environment which places stringent requirements on the instruments used to measure the concentrations of atmospheric trace gases and aerosols. Some of these requirements such as minimization of size, weight, and power consumption are general; others are specific to individual techniques. This review presents the basic principles and considerations governing the deployment of trace gas and aerosol instrumentation on an aircraft. An overview of common instruments illustrates these points and provides guidelines for designing and using instruments on aircraft-based measurement programs.
1991-03-01
Status of LBL/LLNL FEL (free electron laser) research for two beam accelerator applications
Energy Technology Data Exchange (ETDEWEB)
We review the status of free electron laser (FEL) research being conducted at LBL and LLNL as part of a broader program of research on two beam accelerators (TBAs). Induction accelerator-driven FELs for use as power sources for high-gradient accelerators are discussed, along with preliminary cost estimates for this type of power source. Finally, a promising new version of an FEL/TBA is described. 25 refs., 1 fig., 3 tabs.
1989-03-01
Energy Technology Data Exchange (ETDEWEB)
This document contains eleven papers on various aspects of low-level radioactive waste regulation. Topics include: EPA environmental standards; international exemption principles; the concept of below regulatory concern; envirocare activities in Utah; mixed waste; FUSRAP and the Superfund; and a review of various incentive programs. Individual papers are processed separately for the data base. (TEM)
1988-12-01
New Reactor Neutrino Experiments besides Double-CHOOZ
Several new reactor neutrino experiments are being considered to measure the parameter theta-13. The current plans for Angra, Braidwood, Daya Bay, KASKA and KR2DET are reviewed. A case is made that, together with Double-CHOOZ, a future world program should include at least three such experiments.
2005-01-01
UK PubMed Central (United Kingdom)
Vector-borne infections (VBI) are defined as infectious diseases transmitted by the bite or mechanical transfer of arthropod vectors. They constitute a significant proportion of the global infectious...Full Text Available
InConference : oil and gas sector
International Nuclear Information System (INIS)
This Insight conference was held to review many of the legal aspects, legislation and regulations dealing with abandoned wells within the petroleum and natural gas industry. Remedial actions to rehabilitate the abandoned sites, legal issues in abandonment, obligations of the owner, the industry-sponsored Orphans Wells Program, were some of the topics discussed.
1997-04-21
Highly Pathogenic H5N1 Avian Influenza: Entry Pathways into North America via Bird Migration
UK PubMed Central (United Kingdom)
Given the possibility of highly pathogenic H5N1 avian influenza arriving in North America and monitoring programs that have been established to detect and track it, we review intercontinental movements...Full Text Available
Geothermal progress monitor. Progress report No. 7
Energy Technology Data Exchange (ETDEWEB)
A state-by-state review of major geothermal-development activities during 1982 is presented. It also inlcudes a summary of recent drilling and exploration efforts and the results of the 1982 leasing program. Two complementary sections feature an update of geothermal direct-use applications and a site-by-site summary of US geothermal electric-power development.
1983-04-01
Geothermal program review 16: Proceedings. A strategic plan for geothermal research
Energy Technology Data Exchange (ETDEWEB)
The proceedings contain 21 papers arranged under the following topical sections: Exploration technology (4 papers); Reservoir technology (5 papers); Energy conversion technology (8 papers); Drilling technology (2 papers); and Direct use and geothermal heat pump technology (2 papers). An additional section contains a report on a workshop on dual-use technologies for hydrothermal and advanced geothermal reservoirs.
1998-12-31
Coal liquefaction. Quarterly report, January--March 1976
ERDA's coal liquefaction program is reviewed, especially the progress with several pilot plant operations. Other items involve the possible recovery of organic chemicals from coal liquids, the filtration of coal liquids, some experiments on hydrogenation and carbonization, and renovation of the Cresap materials and equipment test facility. (LTN)
1976-01-01
Overview of reliability test program on primary coolant piping of light water reactors
Energy Technology Data Exchange (ETDEWEB)
Upon request by the Science and Technology Agency of Japanese Government, the Japan Atomic Energy Research Institute has conducted Piping Reliability Test Program to demonstrate the safety and reliability of light water reactor primary pipings. In this report, the results of the program are summarized. In the test program, pipe fatigue tests, Leak-Before-Break (LBB) verification tests and pipe rupture tests were carried out to examine the integrity of pipings, to verify the LBB concept and to demonstrate the effectiveness of the protective measures against jet impingement and pipe whip under pipe rupture event, respectively. In the pipe fatigue tests, a procedure to predict the fatigue crack growth was developed and the integrity of piping during plant service life was demonstrated. In the LBB verification tests, pipe fracture tests and leak rate tests were performed using cracked pipes. Based on the ...
1993-10-01
MODFLOW 2.0: A program for predicting moderator flow patterns
Energy Technology Data Exchange (ETDEWEB)
Sudden changes in the temperature of flowing liquids can result in transient buoyancy forces which strongly impact the flow hydrodynamics via flow stratification. These effects have been studied for the case of potential flow of stratified liquids to line sinks, but not for moderator flow in SRS reactors. Standard codes, such as TRAC and COMMIX, do not have the capability to capture the stratification effect, due to strong numerical diffusion which smears away the hot/cold fluid interface. A related problem with standard codes is the inability to track plumes injected into the liquid flow, again due to numerical diffusion. The combined effects of buoyant stratification and plume dispersion have been identified as being important in operation the Supplementary Safety System which injects neutron-poison ink into SRS reactors to provide safe shutdown in the event of safety rod failure. The MODFLOW code discussed here provides transient moderator ...
1991-07-01
MODFLOW 2. 0: A program for predicting moderator flow patterns
Energy Technology Data Exchange (ETDEWEB)
Sudden changes in the temperature of flowing liquids can result in transient buoyancy forces which strongly impact the flow hydrodynamics via flow stratification. These effects have been studied for the case of potential flow of stratified liquids to line sinks, but not for moderator flow in SRS reactors. Standard codes, such as TRAC and COMMIX, do not have the capability to capture the stratification effect, due to strong numerical diffusion which smears away the hot/cold fluid interface. A related problem with standard codes is the inability to track plumes injected into the liquid flow, again due to numerical diffusion. The combined effects of buoyant stratification and plume dispersion have been identified as being important in operation the Supplementary Safety System which injects neutron-poison ink into SRS reactors to provide safe shutdown in the event of safety rod failure. The MODFLOW code discussed here provides transient moderator ...
1991-07-01
Critical review of studies on atmospheric dispersion in coastal regions
Energy Technology Data Exchange (ETDEWEB)
This study effort was required as a preliminary step prior to initiation of field measurements of atmospheric dispersion in coastal regions. The Nuclear Regulatory Commission (NRC) is in the process of planning an extensive field measurement program to generate data which will serve as improved data bases for licensing decisions, confirmation of regulations, standards, and guides, and for site characterizations. The study being reported here is an effort directed to obtaining as much information as is possible from existing studies that is relevant toward NRC's objectives. For this study, reports covering research and meteorological measurements conducted for industrial purposes, utility needs, military objectives, and academic studies were obtained and critically reviewed in light of NRC's current data needs. This report provides an interpretation of the extent of existing usable information, an indication of the potential ...
1982-09-01
Occupational health priorities for health standards: the current NIOSH approach.
Government agencies responsible for protecting the public from the adverse effects of toxic chemicals must set priorities for research, regulatory action, protocol testing, and monitoring due to the vast number of toxic chemicals and the limited resources available to these agencies. The National Institute for Occupational Safety and Health (NIOSH) must set priorities for research on hazards encountered in the workplace. Priorities are also utilized by NIOSH in preparing criteria for recommended occupational standards which are forwarded to the Occupational Safety and Health Administration (OSHA), U.S. Department of Labor, for possible promulgation. For various reasons, including rapidly changing conditions in the American workplace, NIOSH has instituted a revised priorities program. In the future, NIOSH research and recommended standards activities will focus not only on individual chemicals, but also on industries, ...
1979-05-01
Effectiveness of storage practices in mitigating aging degradation during reactor layup
Energy Technology Data Exchange (ETDEWEB)
One of the issues identified in the US Nuclear Regulatory Commission`s Nuclear Plant Aging Research program plan is the need to understand the state of ``mothballed`` or other out-of-service equipment to ensure subsequent safe operation. Programs for proper storage and preservation of materials and components are required by NRC regulations (10 CFR 50, Appendix B). However, materials and components have been seriously degraded due to improper storage, protection, or layup, at facilities under construction as well as those with operating licenses. Pacific Northwest Laboratory has evaluated management of aging for unstarted or mothballed nuclear power plants. The investigations revealed that no uniform guidance in the industry addresses reactor layup. In each case investigated, layup was not initiated in a timely manner, primarily because of schedule uncertainty. Hence, it is reasonable to assume that this delay resulted in accelerated aging of ...
1995-09-01
SP-100 fuel pin performance: Results from irradiation testing
Energy Technology Data Exchange (ETDEWEB)
A total of 86 experimental fuel pins with various fuel, liner, and cladding candidate materials have been irradiated in the Experimental Breeder Reactor-II (EBR-II) and the Fast Flux Test Facility (FFTF) reactor as part of the SP-100 fuel pin irradiation testing program. Postirradiation examination results from these fuel pin are key in establishing performance correlations and demonstrating the lifetime and safety of the reactor fuel system. This paper provides a brief description of the in-reactor fuel pin tests and presents the most recent irradiation data on the performance of wrought rhenium (Re) liner material and high density UN fuel at goal burnup of 6 atom percent (at. %). It also provides an overview of the significant variety of other fuel/liner/cladding combinations which were irradiated as part of this program and which may be of interest to more advanced efforts.
1993-09-01
Pirfenidone in idiopathic pulmonary fibrosis: the CAPACITY program
British Library Electronic Table of Contents (United Kingdom)
Idiopathic pulmonary fibrosis is the most lethal form of diffuse lung fibrosis, killing approximately half of those affected within 2-3 years of diagnosis. Until recently, no therapies had been shown to have an impact on disease progression. The Clinical Studies Assessing Pirfenidone (Esbriet) in IPF: Research of Efficacy and Safety Outcomes (CAPACITY) program comprised two almost identical double-blind placebo-controlled studies assessing the effects of pirfenidone on change in forced vital capacity, the primary end point, over a 72-week period. One of these studies was positive, matching in magnitude the benefit seen in two previous positive Japanese studies. The other study did not meet its primary end point but positive trends were consistent in this and a number of secondary end point...
2011-01-01
Managing natural resources for sustainable development. Special report
Energy Technology Data Exchange (ETDEWEB)
The report presents an overview of A.I.D. efforts, which encompass a wide range of environmental issues and support environmental training, research, and institutional development. The report's opening section details A.I.D.'s efforts to enlist host-country support for environmental programs, with specific emphasis on improving natural resource management (especially in Africa), encouraging policy change, strengthening the private sector's environmental role, and preparing environmental profiles of host countries and helping them develop conservation strategies. The ensuing sections recount A.I.D. efforts in particular topics of environmental concern (biological diversity and environmental health and safety), critical ecological areas (coastal areas and forests and fragile lands), and specific country programs (reforestation in Haiti). A brief history of the evolution of the Agency's ...
1987-01-01
Liquid metal reactor cover gas purification and analysis in the USA
International Nuclear Information System (INIS)
Two sodium cooled reactors are currently being operated in the United States of America for the US Department of Energy. These are Experimental Breeder Reactor 11, EBR-11, and the Fast Flux Test Facility, FFTF. EBR-11 is located near Idaho Falls, Idaho, and the FFTF is near Richland, Washington. These reactors are currently engaged in a wide range of testing including fuels and materials tests, and plant system performance and safety development. The US DOE program also includes designs of a next generation sodium cooled power reactor. The FFTF and EBR-11 communities are providing input to these designs. This paper discusses the efforts to develop and operate cover gas systems for the sodium cooled nuclear reactor program in the USA.
1986-09-24
A study on the experimental verification for the pipe whip problem in a Nuclear Power Plant
Energy Technology Data Exchange (ETDEWEB)
The purpose of this study is to investigate on the experimental verification analysis for the pipe whip problems and to obtain the quantitative evaluation technologies for the design technique of pipe whip restraints. These will contribute to the advance of nuclear regulatory technologies and enhance nuclear power plant safety. This study presents the experimental and transient analytical results of pipe whip tests using the 4', 6' diameter pipe and U-shaped restraints. In the tests, the effects of the overhang length, clearance, impact height on the pipe whip behavior of the pipe-restraints were investigated. The transient impact analysis of the pipe-restraint system was conducted by the finite element program ABAQUS. The applicability of the ABAQUS program to the pipe whip analysis is made clear through this analysis.
1993-12-15
International Nuclear Information System (INIS)
The slow or stagnant rate of nuclear power generation development in many developed countries over the last two decades has resulted in a significant shortage in the population of mid-career nuclear industry professionals. This shortage is even more pronounced in some specific areas of expertise such as radiological protection, waste management and decommissioning. This situation has occurred at a time when the renaissance of nuclear power and the globalization of the nuclear industry are steadily gaining momentum and when the industry's involvement in international and national debates in these three fields of expertise (and the industry's impact on these debates) is of vital importance. This paper presents the World Nuclear Association (WNA) approach to building and enhancing worldwide industry cooperation in radiological protection, waste management and decommissioning, which is manifested through the activities of the two WNA working groups on radiological protection (RPWG) and on ...
Use of Behaviorally Anchored Rating Scales (BARS) for deep technical knowledge
Energy Technology Data Exchange (ETDEWEB)
The University of California at Los Angeles (UCLA) participated in a U.S. Nuclear Regulatory Commission research program to investigate methods to measure the effect of management and organization on nuclear plant safety. The UCLA research team focused its efforts on understanding {open_quotes}deep technical knowledge,{close_quotes} and its relation to probabilistic risk assessment. As a result, the research team combined deep technical knowledge with a commonly used rating system for understanding the effectiveness of management and organizations.
1993-12-31
Energy Technology Data Exchange (ETDEWEB)
In order to realize improve of reliability and economy by duplicate production, rapid supply of repair parts from standardized storage, such were expected as to have continuous order of standardized plant, to ignore site condition, to avoid expansion of regulatory requirement. Standardization program was planned to limitedly promote standardization of safety-related design concept, major specification and basic system composition of reactor and primary systems. The area of standardization had been tried to expand to BOP such as general arrangement and rad-waste system.
1985-07-01
Radiation safety in industrial applications
International Nuclear Information System (INIS)
Oil and gas industry is the largest user of radioactive materials in Nigeria. They make use of radiation generators, sealed and unsealed radioactive sources.Some of these are potentially dangerous to human health and environment if not properly controlled. here is also the need to maintain control over occupational exposures to radiation, as well as to protect the public and the environment through proper management of wastes that may be radiologically hazardous. To minimize these, effective regulatory infrastructure is being put in place.For a smooth take-off of the nuclear power program, the National Nuclear Regulatory Authority and other stake holders in the nuclear industry need to start to put together licensing procedure for these.
2008-03-17
Ground subsidence determination in mining areas
Energy Technology Data Exchange (ETDEWEB)
Knowledge of ground subsidence behavior provides for better economic planning and execution of a mining exploitation, higher safety and optimum use of the resources without ruining the environment. In addition, when considering subsidence generated by petroleum exploitation, the monitored (measured) subsidence, combined with geological information and a suitable prediction model, can provide data on the expanse of the oil field and thus aid in the estimation of available resources. An integrated survey system for monitoring mining subsidence is described which has been developed as part of a research program in cooperation with the Canada Centre for Mineral and Energy Technology. (JMT)
1982-02-01
Evaluation of aged concrete structures for continued service in nuclear power plants
International Nuclear Information System (INIS)
Results are summarized of a study on concrete component aging and its significance relative to continued service of nuclear power plants (NPPs) beyond the initial period for which they were granted operating licenses. Progress is presented of a second study being conducted to identify and provide acceptance criteria for structural safety issues which the USNRC staff will need to address when applications are submitted for continued service of NPPs. Major activities under this program include: development of a materials property data base, establishment of structural component assessment and repair procedures, and development of a methodology for determination of structural reliability. 19 refs., 5 figs., 3 tabs.
1988-10-24
Energy Technology Data Exchange (ETDEWEB)
Results obtained on induced current and voltage caused by a high voltage transmission lines running parallel at a trolley bus contact lines, are presented. A computer program in Basic language, was developed to calculate the electric induction, problems of safety, a theoretical development and mathematical model of the electric factors between two lines (inductor and induced) are also discussed. 11 figs., 1 tab., 8 refs.
1991-12-31
A compilation of reports of the Advisory Committee on reactor safeguards. 1996 Annual report
Energy Technology Data Exchange (ETDEWEB)
This compilation contains 47 ACRS reports submitted to the Commission, or to the Executive Director for Operations, during calendar year 1996. It also includes a report to the Congress on the NRC Safety Research Program. All reports have been made available to the public through the NRC Public Document Room, the U.S. Library of Congress, and the Internet at http://www.nrc.gov/ACRSACNW. The reports are divided into two groups: Part 1 contains ACRS reports by project name and by chronological order within project name. Part 2 categorizes the reports by the most appropriate generic subject area and by chronological order within subject area.
1997-04-01
Development of next-generation light water reactor in Japan
International Nuclear Information System (INIS)
In Japan, the development of next-generation Light Water Reactor has been launched since April 2008. The development program will be completed in 2015. The purpose of development is to cope with the replacement for existing nuclear power plants after 2030 in Japan and the expanding demand for nuclear power in the world; 'Nuclear Renaissance.' The reactor also aims to be global standard at around 2030. The requirements for global standard and domestic users have been investigated through the feasibility study of past 2 years, 2006-2007, and six innovative features or 'Core-Concepts' were established as follows. A) Reactor core system with uranium enrichment above 5% for significant decrease of spent fuel discharge and prominent higher availability B) Long-life materials and innovative water chemistry technologies for 80 years plant lifetime and significant reduction of occupational dose C) Seismic isolation technologies to standardize plant design independent from ...
2009-10-27
Review of fires and fire control methods for nuclear air cleaning systems
International Nuclear Information System (INIS)
The nuclear power industry has experienced four carbon based adsorbent fires in its history, one was of the Monticello Standby Gas Treatment System and other three were in various off-gas delay beds. Although, some of the latter may not be classified as a full fledged fires. There were a number of experiments performed relating to igniting carbon beds and experiments relating to attempts at extinguishing set fires reported in the literature. Review of these experiments indicates that fire resulting from decay heat of adsorbed radioactive iodine is not justified even under the somewhat unrealistic source terms still in effect. At the same time the non-nuclear chemical industry application of carbon base adsorbents for solvent recovery has resulted in numerous fires and significant property losses. Fire control systems installed in nuclear air cleaning systems in the US consists of water deluge. Accidental initiation of these systems has occurred in excess of one ...
1987-05-01
A study of passive and inherent safety design concepts for advanced light= water reactors
Energy Technology Data Exchange (ETDEWEB)
The five thermal-hydraulic concepts chosen for conceptual study of advanced PWR systems have been studied as follows: (1) Critical Heat Flux in passive PWR Conditions: review of previous works (various of correlations, analysis of parametric trends) on CHF, assessment and improvement of CHF prediction models for round tubes, development of the prediction model on bundle CHF with considering the correction factor calculated from the tube data base, design and construction of the intermediate-pressure CHF experimental loop, extension of CHF data base by performing the experiments at low-flow, and low-quality conditions (2) Passive Cooling Concepts for Concrete Containment Systems: Selection of the external condenser by comparing and reviewing between passive cooling concepts for concrete containment system concepts, survey and review of previous studies (theoretical mechanism of condensation heat transfer and effect of ...
1997-07-01
General-purpose heat source development: Extended series test program SRB fragment/fuselage tests
Energy Technology Data Exchange (ETDEWEB)
General-Purpose Heat Source radioisotope thermoelectric generators (GPHS-RTGs) will provide electrical power for the NASA Galileo and European Space Agency (ESA) Ulysses missions. Each GPHS-RTG comprises two major components: GPHS modules, which provide thermal energy, and a thermoelectric converter, which converts the thermal energy into electrical power. Each of the 18 GPHS modules in a GPHS-RTG contains four /sup 238/PuO/sub 2/-fueled capsules. LANL conducted a series of safety verification tests on the GPHS-RTG before the scheduled May 1986 launch of the Galileo spacecraft to assess the ability of the GPHS modules to contain plutonia in potential accident environments. As a result of the Challenger 51-L accident in January 1986, NASA postponed the launch of Galileo; the spacecraft launch vehicle was reconfigured and the spacecraft trajectory modified. These actions prompted NASA to reevaluate potential mission accidents and the extended series ...
1989-06-01
International Nuclear Information System (INIS)
Full text: The transmutation of nuclear waste to reduce the burden on a geological repository is a relevant topic within the Program of Nuclear Safety Research of the Research Centre Karlsruhe. Several studies have confirmed that a high efficiency of transmutation of actinides is reached in fast neutron spectrum reactor system. Therefore, an important effort is dedicated to the study of transmutation strategies with different fast reactors and their associated technologies. Moreover, in international contexts as Generation IV International Forum (GIF) and Sustainable Nuclear Energy Technology Platform (SNETP), fast reactors are considered in the frame of sustainable development of nuclear energy and reduction of waste. The systems that are currently under investigation, in the frame of the different fuel cycle scenarios, are liquid metal cooled and gas cooled fast reactors as well as Accelerator Driven Sub-critical Transmutation devices (ADS). ...
2009-10-05
National NIF Diagnostic Program Fiscal Year 2002 Second Quarter Report
Energy Technology Data Exchange (ETDEWEB)
Since October 2001 the development of the facility diagnostics for NIF has been funded by the NIF Director through the National NIF Diagnostic Program (NNDP). The current emphasis of the NNDP is on diagnostics for the early NIF quad scheduled to be available for experiment commissioning in FY03. During the past six months the NNDP has set in place processes for funding diagnostics, developing requirements for diagnostics, design reviews and monthly status reporting. Those processes are described in an interim management plan for diagnostics (''National NIF Diagnostic Program Interim Plan'', NIF-0081315, April 2002) and a draft Program Execution Plan (''Program Execution Plan for the National NlF Diagnostic Program'', NIF-0072083, October 2001) and documents cited therein. Work has been ...
2002-04-01
Operational safety experience and passive safety testing at the FFTF
International Nuclear Information System (INIS)
The FFTF is a 400-MWt sodium-cooled fast neutron flux test reactor located on the US government-owned Hanford Site in southeastern Washington state. The reactor is operated for the US Department of Energy by the Westinghouse Hanford Company. Since FFTF started routine operation in 1982, the commercially fabricated driver fuel has performed flawlessly to well beyond the design goal peak burnup of 80 MWd/kgM. The core average discharge exposure is now some 60% beyond the original design expectations and attests to the ruggedness and reliability of the mixed oxide fuel system. In Cycle 9 sixteen long-life assemblies were installed to begin the irradiation of mixed oxides in the advanced low-swelling alloy HT-9 as the Core Demonstration Experiment (CDE). Operation of the plant from initial startup testing to ten cycles of operation has confirmed that the nuclear characteristics are well within the design predictions, and all parameters have remained inside the operating envelope defined by ...
1987-10-21
WIPS: computer code for whip and impact analysis of piping systems. Summary report
Energy Technology Data Exchange (ETDEWEB)
WIPS (Whip and Impact of Piping Systems) is a special purpose computer code for the structural analysis of pipe whip dynamic effects following a postulated pipe rupture. WIPS has been developed primarily to provide support for the pipe whip analysis procedures described in Section 3.6.2 of the US Nuclear Regulatory Commission Standard Review Plan. This report summarizes the purpose and scope of the WIPS development effort, identifying those clauses in the Standard Review Plan which refer to pipe whip analysis, and indicating how the WIPS code can be used to provide supporting data. Detailed information on use of the code is contained in accompanying reports which cover: (1) user instructions; (2) theory; (3) programming procedures; and (4) verification examples.
1984-06-01
Proceedings of the Pacific Knowledge Acquisition Workshop 2004
Artificial intelligence (AI) research has evolved over the last few decades and knowledge acquisition research is at the core of AI research. PKAW-04 is one of three international knowledge acquisition workshops held in the Pacific-Rim, Canada and Europe over the last two decades. PKAW-04 has a strong emphasis on incremental knowledge acquisition, machine learning, neural nets and active mining. The proceedings contain 19 papers that were selected by the program committee among 24 submitted papers. All papers were peer reviewed by at least two reviewers. The papers in these proceedings cover the methods and tools as well as the applications related to develop expert systems or knowledge based systems.
2005-01-01
Whole-body counting in the Marshall Islands
Energy Technology Data Exchange (ETDEWEB)
In 1978 the Marshall Islands Radiological Safety Program was organized to perform radiation measurements and assess radiation doses for the people of the Bikini, Enewetak, Rongelap and Utirik Atolls. One of the major field components of this program is whole- body counting (WBC). WBC is used to monitor the quantity of gamma- emitting radionuclides present in individuals. A primary objective of the program was to establish {sup 137}Cesium body contents among the Enewetak, Rongelap and Utirik populations. {sup 137}Cs was the only gamma-emitting fission radionuclide detected in the 1,967 persons monitored. {sup 137}Cs body burdens tended to increase with age for both sexes, and were higher in males. The average {sup 137}Cs dose Annual Effective Dose for the three populations was as follows: For Enewetak, the dose was 22{+-}4 {mu}Sv. For Utirik, the dose was 33{+-} 3 {mu}Sv. Since 1985 the Rongelap people ...
1991-01-01
Tiger Team assessment of the Lawrence Berkeley Laboratory, Washington, DC
Energy Technology Data Exchange (ETDEWEB)
This report documents the results of the Department of Energy's (DOE's) Tiger Team Assessment of the Lawrence Berkeley Laboratory (LBL) conducted from January 14 through February 15, 1991. The purpose of the assessment was to provide the Secretary of Energy with the status of environment, safety, and health (ES H) programs at LBL. The Tiger Team concluded that curtailment of cessation of any operations at LBL is not warranted. However, the number and breadth of findings and concerns from this assessment reflect a serious condition at this site. In spite of its late start, LBL has recently made progress in increasing ES H awareness at all staff levels and in identifying ES H deficiencies. Corrective action plans are inadequate, however, many compensatory actions are underway. Also, LBL does not have the technical expertise or training programs nor the tracking and followup to effectively direct and control ...
1991-02-01
Results of reliability test program on light water reactor piping
Energy Technology Data Exchange (ETDEWEB)
The Japan Atomic Energy Research Institute has conducted a piping reliability test program to demonstrate the safety and reliability of light water reactor primary piping. In this program, pipe fatigue test, leak-before-break (LBB) verification test and pipe rupture test were carried out to examine the integrity of piping, to verify the LBB and to demonstrate the effectiveness of protective measures against jet impingement and pipe whip loads under a pipe rupture event.In the pipe fatigue test, a procedure to predict the fatigue crack growth was developed, and the integrity of piping during the plant service life was evaluated. In the LBB verification test, the pipe fracture test and the leak rate test were performed to verify the LBB in the primary piping.In the pipe rupture test, the influence of jet impingement on the target disk and the deformation behavior of whipping pipe and restraint were investigated. Using the ...
1994-12-01
Advanced Simulation and Computing FY10-FY11 Implementation Plan Volume 2, Rev. 0.5
Energy Technology Data Exchange (ETDEWEB)
The Stockpile Stewardship Program (SSP) is a single, highly integrated technical program for maintaining the surety and reliability of the U.S. nuclear stockpile. The SSP uses past nuclear test data along with current and future non-nuclear test data, computational modeling and simulation, and experimental facilities to advance understanding of nuclear weapons. It includes stockpile surveillance, experimental research, development and engineering (D&E) programs, and an appropriately scaled production capability to support stockpile requirements. This integrated national program requires the continued use of current facilities and programs along with new experimental facilities and computational enhancements to support these programs. The Advanced Simulation and Computing Program (ASC) is a cornerstone of the SSP, providing simulation ...
2009-09-08
Quality assurance requirements for high-level waste form production
International Nuclear Information System (INIS)
The Department of Energy has issued a Quality Assurance (QA) specification for organizations involved in making a canistered high-level waste form product that is acceptable for storage in a deep geologic federal repository. The logic for the waste form acceptance process is described. In addition to NQA-1 requirements, fourteen supplemental QA requirements have been drafted to fit the waste form production process. A review plan for assuring complicance with the QA specification is provided. Guidelines for preparation of a waste form producer QA program are also presented. It is expected that the QA program description that result will be influential in supporting the acceptybility of the product to OCRWM and for ultimate disposal of the high-level waste in a deep geologic repository. (author) 3 figs., 4 refs.
Production of radioisotopes in the ORNL 86-inch cyclotron
Energy Technology Data Exchange (ETDEWEB)
The radioisotope production facilities and programs of the 86-Inch Cyclotron are reviewed in this presentation. The 86-Inch Cyclotron is designed to accelerate protons to a maximum energy of 22 MeV for internal targets. These protons are used to bombard metals that are electroplated, potted or soldered to water-cooled plates. Additionally, metals and inorganic compounds are bombarded in water-cooled tube targets. High radioisotope production rates are obtained by beam currents as large as 3 mA. Production rates for /sup 11/C, /sup 57/Co, /sup 67/Ga, /sup 68/Ge, /sup 109/Cd, and other isotopes are presented. The production of /sup 11/C for the carboxyl labeling of amino acids in cooperation with Oak Ridge Associated Universities is discussed. The 86-Inch Cyclotron is used for those programs requiring a larger beam current than is available from commercial cyclotrons.
1981-04-01
Energy Technology Data Exchange (ETDEWEB)
With the issuance of the Decommissioning Rule (July 27, 1988), nuclear power plant licensees are required to submit to the US Regulatory Commission (NRC) for review, decommissioning plans and cost estimates. This user`s manual and the accompanying Cost Estimating Computer Program (CECP) software provide a cost-calculating methodology to the NRC staff that will assist them in assessing the adequacy of the licensee submittals. The CECP, designed to be used on a personnel computer, provides estimates for the cost of decommissioning PWR plant stations to the point of license termination. Such cost estimates include component, piping, and equipment removal costs; packaging costs; decontamination costs; transportation costs; burial costs; and manpower costs. In addition to costs, the CECP also calculates burial volumes, person-hours, crew-hours, and exposure person-hours associated with decommissioning.
1993-10-01
A study of the Teachers` Academy for Mathematics and Science
Energy Technology Data Exchange (ETDEWEB)
The Teachers` Academy for Mathematics and Science in Chicago (TAMS) is a freestanding institution founded in 1989 by scientists and a variety of other stakeholders, to advance the systemic reform of mathematics and science education in Chicago`s public schools. It focuses on the ``re-tooling`` of its elementary level teachers. The TAMS program, which has been funded in part by the DOE, contributes to strategic goals two through five of the Office of University and Science Education (OUSE). This evaluation of TAMS by the National Center for Improving Science Education is primarily a qualitative study that summarizes the history and current status of the organization and its programs. Data was obtained through extensive interviews, observations, and document review, using a framework of templates to guide data collection and analyses. The findings are organized around a series of lessons learned from the first three years of ...
1994-09-15
Sandia National Laboratories/California site environmental report for 1997
Energy Technology Data Exchange (ETDEWEB)
Sandia National Laboratories (SNL) is committed to conducting its operations in an environmentally safe and sound manner. It is mandatory that activities at SNL/California comply with all applicable environmental statutes, regulations, and standards. Moreover, SNL/California continuously strives to reduce risks to employees, the public, and the environment to the lowest levels reasonably possible. To help verify effective protection of public safety and preservation of the environment, SNL/California maintains an extensive, ongoing environmental monitoring program. This program monitors all significant effluents and the environment at the SNL/California site perimeter. Lawrence Livermore National Laboratory (LLNL) performs off-site external radiation monitoring for both sites. These monitoring efforts ensure that emission controls are effective in preventing contamination of the environment. As part of SNL/California`s ...
1998-06-01
This report summarizes the results of an expert-opinion elicitation activity designed to qualitatively assess the status and capabilities of currently available computer codes and models for accident analysis and reactor safety calculations of advanced sodium fast reactors, and identify important gaps. The twelve-member panel consisted of representatives from five U.S. National Laboratories (SNL, ANL, INL, ORNL, and BNL), the University of Wisconsin, the KAERI, the JAEA, and the CEA. The major portion of this elicitation activity occurred during a two-day meeting held on Aug. 10-11, 2010 at Argonne National Laboratory. There were two primary objectives of this work: (1) Identify computer codes currently available for SFR accident analysis and reactor safety calculations; and (2) Assess the status and capability of current US computer codes to adequately model the required accident scenarios and associated phenomena, and identify important gaps. ...
2011-06-01
Concepts in radiation protection
International Nuclear Information System (INIS)
This monograph provides basic notions and principles in dosimetry and radiation protection in compliance with two fundamental works: IAEA Safety Series No.115 - International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources - and Publication no. 60 of International Commission on Radiological Protection. After the review of quantities and units necessary in radiation protection, the book presents the new values of dose limits as well as the values of 'radiation weighting factor', 'tissue weighting factor' and 'conversion factor intake-dose' (committed effective dose per unit intake) by ingestion and inhalation for 30 most important radionuclides. The new values of dose limits, lower than the old values, are a challenge for the radiation protection, especially of the 'public' where the dose limit diminished by a factor of five relative to the earlier ...
1996-01-01
Fifty years of federal radioactive waste management: Policies and practices
Energy Technology Data Exchange (ETDEWEB)
This report provides a chronological history of policies and practices relating to the management of radioactive waste for which the US Atomic Energy Commission and its successor agencies, the Energy Research and Development Administration and the Department of Energy, have been responsible since the enactment of the Atomic Energy Act in 1946. The defense programs and capabilities that the Commission inherited in 1947 are briefly described. The Commission undertook a dramatic expansion nationwide of its physical facilities and program capabilities over the five years beginning in 1947. While the nuclear defense activities continued to be a major portion of the Atomic Energy Commission`s program, there was added in 1955 the Atoms for Peace program that spawned a multiplicity of peaceful use applications for nuclear energy, e.g., the civilian nuclear power program and its associated ...
1997-04-01
Verification of safety critical software
Energy Technology Data Exchange (ETDEWEB)
To assure quality of safety critical software, software should be developed in accordance with software development procedures and rigorous software verification and validation should be performed. Software verification is the formal act of reviewing, testing of checking, and documenting whether software components comply with the specified requirements for a particular stage of the development phase[1]. New software verification methodology was developed and was applied to the Shutdown System No. 1 and 2 (SDS1,2) for Wolsung 2,3 and 4 nuclear power plants by Korea Atomic Energy Research Institute(KAERI) and Atomic Energy of Canada Limited(AECL) in order to satisfy new regulation requirements of Atomic Energy Control Boars(AECB). Software verification methodology applied to SDS1 for Wolsung 2,3 and 4 project will be described in this paper. Some errors were found by this methodology during the software development for SDS1 and were corrected by ...
1996-12-01
Verification of safety critical software
International Nuclear Information System (INIS)
To assure quality of safety critical software, software should be developed in accordance with software development procedures and rigorous software verification and validation should be performed. Software verification is the formal act of reviewing, testing of checking, and documenting whether software components comply with the specified requirements for a particular stage of the development phase[1]. New software verification methodology was developed and was applied to the Shutdown System No. 1 and 2 (SDS1,2) for Wolsung 2,3 and 4 nuclear power plants by Korea Atomic Energy Research Institute(KAERI) and Atomic Energy of Canada Limited(AECL) in order to satisfy new regulation requirements of Atomic Energy Control Boars(AECB). Software verification methodology applied to SDS1 for Wolsung 2,3 and 4 project will be described in this paper. Some errors were found by this methodology during the software development for SDS1 and were corrected by ...
1996-01-01
Status of non-electric nuclear heat applications: Technology and safety
International Nuclear Information System (INIS)
Nuclear energy plays an important role in electricity generation, producing 16% of the world's electricity at the beginning of 1999. It has proven to be safe, reliable, economical and has only a minimal impact on the environment. Most of the world's energy consumption, however, is in the form of heat. The market potential for nuclear heat was recognized early. Some of the first reactors were used for heat supply, e.g. Calder Hall (United Kingdom), Obninsk (Russian Federation), and Agesta (Sweden). Now, over 60 reactors are supplying heat for district heating, industrial processes and seawater desalination. But the nuclear option could be better deployed if it would provide a larger share of the heat market. In particular, seawater desalination using nuclear heat is of increasing interest to some IAEA Member States. In consideration of the growing experience being accumulated, the IAEA periodically reviews the progress and new developments in the field of nuclear ...
Risks and safety aspects related to PET/MR examinations
International Nuclear Information System (INIS)
The introduction of positron emission tomography (PET)/magnetic resonance (MR) systems into medical practice in the foreseeable future may not only lead to a gain in clinical diagnosis compared to PET/computed tomography (CT) imaging due to the superior soft-tissue contrast of the MR technology but can also substantially reduce exposure of patients to ionizing radiation. On the other hand, there are also risks and health effects associated with the use of diagnostic MR devices that have to be considered carefully. This review article summarizes biophysical and biological aspects, which are of relevance for the assessment of health effects related to the exposure of patients to both ionizing radiation in PET and magnetic and electromagnetic fields in MR. On this basis, some considerations concerning the justification and optimization of PET/MR examinations are presented - as far as this is possible at this very early stage. Current safety ...
2009-03-01
Response of a Spent Fuel Transportation Cask to a Tunnel Fire Event
Energy Technology Data Exchange (ETDEWEB)
The staff of the Spent Fuel Project Office at the U.S. Nuclear Regulatory Commission undertook the investigation and thermal analysis of the Baltimore tunnel fire event. This event occurred in the Howard Street tunnel, in Baltimore, Maryland, on July 18, 2001. The staff was tasked with assessing the consequences of this event on the transportation of spent nuclear fuel. This paper describes the staff's coordination with the following government and laboratory organizations: the National Transportation Safety Board (NTSB), to determine the details of the train derailment and fire; the National Institute of Standards and Technology (NIST), to quantify the thermal conditions within the tunnel; the Center for Nuclear Waste Regulatory Analysis (CNWRA), to validate the NIST evaluations, and the Pacific Northwest National Laboratory (PNNL), to assist in the thermal analysis. The results of the staff's review and analysis efforts are ...
2003-02-25
Nuclear cask testing films misleading and misused
Energy Technology Data Exchange (ETDEWEB)
In 1977 and 1978, Sandia National Laboratories, located in Albuquerque, New Mexico, and operated for the US Department of Energy (DOE), filmed a series of crash and fire tests performed on three casks designed to transport irradiated nuclear fuel assemblies. While the tests were performed to assess the applicability of scale and computer modeling techniques to actual accidents, films of them were quickly pressed into service by the DOE and nuclear utilities as proof'' to the public of the safety of the casks. In the public debate over the safety of irradiated nuclear fuel transportation, the films have served as the mainstay for the nuclear industry. Although the scripts of all the films were reviewed by USDOE officials before production, they contain numerous misleading concepts and images, and omit significant facts. The shorter versions eliminated qualifying statements contained in the longer version, ...
1991-10-01
Natural resource valuation: A primer on concepts and techniques
Energy Technology Data Exchange (ETDEWEB)
Natural resource valuation has always had a fundamental role in the practice of cost-benefit analysis of health, safety, and environmental issues. Today, this role is becoming all the more apparent in the conduct of natural resource damage assessments (NRDA) and cost-benefit analyses of environmental restoration (ER) and waste management (WM) activities. As such, environmental professionals are more interested in how natural resource values are affected by ER and WM activities. This professional interest extends to the use of NRDA values as measures of liability and legal causes of action under such environmental status as the Clean Water Act (CWA); the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA, as amended); and the Oil Pollution Act (OPA) of 1990. Also, environmental professionals are paying closer attention to NRDA values in cost-benefit analyses of risk and pollution-abatement standards, and in meeting environmental ...
1997-07-01
Mine stability evaluation of panel 1 during waste emplacement operations at WIPP
Energy Technology Data Exchange (ETDEWEB)
The specific objectives of the work were defined by the Environmental Evaluation Group (EEG) as follows: (1) assess the stability of panel 1 during the proposed operation of waste emplacement; (2) estimate the amount of time before room closure would be expected to transfer rock loads to the waste packages. The work consisted of (1) an analysis of geotechnical data and a review of the Department of Energy`s (DOE) plans for waste emplacement in panel 1, (2) an evaluation of ground conditions based on data analysis and observations of changes in ground conditions since the first evaluation in 1993 (USBM 1993), and (3) preparation of a report and presentation of the results to EEG staff. Excluded from this study are radiological safety issues and policies. The study is based on data provided by DOE and Westinghouse Electric Corporation (operator of the site) and conversations with DOE and Westinghouse personnel. MTI cannot independently verify the ...
1998-07-01
Development of the Regulation Concept for a Fusion Reactor
International Nuclear Information System (INIS)
Fusion energy has been studied in many countries such as U.S., France, Japan, Korea etc. Because it would provide much more energy for a given weight of fuel than any technology currently in use, and the fuel itself (primarily deuterium) exists abundantly in the Earth's ocean. Nuclear fusion reactor uses tritium and deuterium as fuel while nuclear fission reactor uses uranium and plutonium as fuel. Besides, inherent design characteristics and driving condition of nuclear fusion reactor is different from those of nuclear fission reactor. Therefore, we cannot apply the regulation rules of nuclear fission reactor to nuclear fusion reactor without change and thus it is needed to development of the safety regulation concept which reflects the characteristics of nuclear fusion reactor. Safety regulation of nuclear fusion reactor employs deterministic approach until sufficient data are secured. However, regulation methodology of nuclear fusion reactor ...
2010-10-01
International Nuclear Information System (INIS)
The DOE is conducting a comprehensive technical analysis of a flexible-fuel transportation system in the United States -- that is, a system that could easily switch between petroleum and another fuel, depending on price and availability. The DOE Alternative Fuels Assessment is aimed directly at questions of energy security and fuel availability, but covers a wide range of issues. This report examines environmental, health, and safety concerns associated with a switch to alternative- and flexible-fuel vehicles. Three potential alternatives to oil-based fuels in the transportation sector are considered: methanol, compressed natural gas (CNG), and electricity. The objective is to describe and discuss qualitatively potential environmental, health, and safety issues that would accompany widespread use of these three fuels. This report presents the results of exhaustive literature reviews; discussions with specialists in the ...
2004-06-07
Application of LBB to high energy pipings of PWR in Korea
Energy Technology Data Exchange (ETDEWEB)
The application of the LBB technology to the newly constructed PWRs has been approved in Korea for several high energy systems that can meet rigorous acceptance criteria. The LBB evaluation had been initiated for Yong-Gwang 3 and 4 units (YGN 3 and 4) which are in service, and subsequently performed for Ul-Chin 3 and 4 units (UCN 3 and 4) which are in construction. The LBB application in Korea is based on the USNRC requirements. The LBB evaluation for YGN 3 and 4 is to eliminate the dynamic effects associated with the postulated DEGB from design basis loads as well as to eliminate pipe whip restraints and jet impingement barriers. There were several issues on the application of LBB to the primary coolant loop and the pressurizer surge line. Of concern were material properties of carbon steel for the primary coolant loop, estimation of crack opening area at the pipe-to-nozzle interface considering the asymmetry, and the leakage crack size which barely meets the required margin of 2 in ...
1996-12-31
Energy Technology Data Exchange (ETDEWEB)
Critics of higher fuel economy standards for vehicles have long argued that improving vehicle fuel economy will require reducing vehicle weight, and that would result in an increase in the number of fatalities from vehicle crashes. Several researchers have estimated that an across-the-board reduction of vehicle weight would reduce passenger safety (Evans 1991; Kahane 1997; U.S. GAO 1994). However, little research has been done on the relationship of vehicle size and fatality rates, independent of weight (see, however, Joksch, Massie, and Pichler 1998). In this report we review previous analyses of the relationship of vehicle weight and safety. We do this to study the opportunities to improve fuel economy in a more sophisticated way than across-the-board mass reduction. The aim is to explore improvements in traffic safety by making selected vehicle groups lighter, and retaining or enlarging selected ...
2001-07-01
Up in smoke: regulatory immortality for 'grandfathered' power plants under the NSR rule changes
Energy Technology Data Exchange (ETDEWEB)
The US New Source Review (NSR) program requires power plant owners to install modern pollution control whenever they upgrade their plants in a way that will cause more pollution. The Clean Air Task Force and other environmental organizations and dozens of states and municipalities have challenged changes to the NSR rule change exempting grandfathered power plants under certain conditions. The author discussed this legislation and whether the Clear Skies Act will be effective. 9 refs.
2004-01-01
Alternative sources of fuel, especially for transport, continue to be of interest, as the availability of petroleum is likely to decline in the foreseeable future. Coal is a perfect alternative since it is abundant and can readily be refined to products similar to petroleum fuels. This work details the continuing research program undertaken by the European Commission, bringing together results of studies by international experts in the field. The editors have synthesized vast amounts of recent literature to produce a state-of-the-art review covering synthetic processes, single and two-stage hydrogenation processes, processing of coal with heavy oil and catalysis.
1988-01-01
Energy Technology Data Exchange (ETDEWEB)
This report is published in the framework of the 1991 French law for the nuclear waste management. The state of the art reported here concerns the long term evolution of spent fuel in the various environmental conditions corresponding to dry storage and geological disposal: closed system, air and water saturated medium. This review is based on the results of the french PRECCI project (Research Program on Long term Evolution of Spent Nuclear Fuel) and on literature data. (authors)
2005-03-15
Review of the Vortec soil remediation demonstration program
Energy Technology Data Exchange (ETDEWEB)
The DOE`s clean-up of its nuclear complex require the development of innovative technologies to convert soils contaminated by hazardous and/or radioactive wastes to forms which can be readily disposed in accordance with current waste disposal methods. The unique features of Votec CMS technology should make it particularly cost-effective process for the vitrification of soils, sediments, sludges, and mill tailings containing organic metallic and/or radioactive contaminants. This article describes the technology (Votec`s combustion and melting system), the results of testing, the demonstration plant system, and summarizes the future schedule and the equipment needed. 3 figs., 3 tabs.
1994-11-01
The Beyond the Standard Model Working Group discussed a variety of topics relating to exotic searches at current and future colliders, and the phenomenology of current models beyond the Standard Model. For example, various supersymmetric (SUSY) and extra dimensions search possibilities and constraints are presented. Fine-tuning implications of SUSY searches are derived. The implications of Higgs (non)-discovery are discussed, as well as the program HDECAY. The individual contributions are included seperately. Much of the enclosed work is original, although some is reviewed.
2000-01-01
Progress and Plans for R&D and the Conceptual Design of the ILC Main Linacs
The International Linear Collider Main Linacs are based on superconducting accelerator structures operating at 1.3 GHz. The basis for this design has been developed and tested at DESY and R&D is progressing at many laboratories around the world including DESY, Orsay, KEK, FNAL, SLAC, Cornell, and JLAB. The status of the TESLA-style cavities and rf system will be reviewed and parameters for the ILC linac will be described. The role of the different linac test facilities will discussed and the critical items and R&D program to support a Conceptual Design and Technical Design will be outlined.
2005-01-01
Opportunities for coal liquefaction research in British Columbia
Energy Technology Data Exchange (ETDEWEB)
This paper presents the results of a study commissioned by the British Columbia Science Council to identify opportunities for liquefaction of B.C. coals and to recommend effective approaches to the development of a research program on coal conversion. Contains reviews of British Columbia coal resources to identify prospective candidates for conversion to liquid fuels; of the state of the art in the various processes for the conversion of coal to liquid fuels with particular emphasis on those processes most relevant to British Columbia applications; and of research opportunities in British Columbia for the development of coal liquefaction technology. (16 refs.)
1980-05-01
This bulletin traces development of high-pressure, coal and tar hydrogenation technology, based on an intensive review of pertinent literature. The bulletin written as part of the Bureau of Mines research program on synthetic liquid fuels covers the history and economics of the process; chemical aspects of hydrogenation of coal, tar, and middle oil; engineering aspects of converting coal and tar to liquid fuels, principally gasoline; and equipment for the process. The literature covered includes documents of United States and British governments, journals, and other publications. Bureau results in the hydrogenation field are also incorporated.
1968-01-01
Feasibility study on the management of the disposal of Bangkok municipal waste. Final report
Energy Technology Data Exchange (ETDEWEB)
In January, 1985, the Government of Thailand sought assistance from the United States Trade and Development Program (USTDP) to undertake a feasibility study to review and update the solid waste management master plan, with particular emphasis to be placed on waste disposal methods. In April, 1985, the USTDP engaged the firm of Engineering and Economic Research, Inc. to carry out a definitional/prefeasibility study to assess the potential of a project for solid waste management and energy production using municipal solid waste as fuel.
1989-09-01
Explosives synthesis at Los Alamos
Energy Technology Data Exchange (ETDEWEB)
During the past two decades, the explosives synthetic effort at Los Alamos has been directed toward energetic heterocylic compounds and has produced some useful thermally stable explosives. The recent evolution of crystal-density predictive methods is guiding our current efforts toward ultrahigh performance explosives. Much of our effort is now on the development of new methods for preparing unique nitro compounds that are inaccessible by conventional techniques. This paper reviews the Los Alamos synthetic program with emphasis on the development of novel thermally stable explosives, and current efforts to synthesize high-density/performance explosives will be discussed.
1986-03-01
Energy Technology Data Exchange (ETDEWEB)
The state of the laboratory address by LLNL Director Roger Batzel is summarized, and a breakdown of the laboratory funding is given. The Livermore defense-related committment is described, including the design and development of advanced nuclear weapons as well as research in inertial confinement fusion, nonnuclear ordnance, and particle beam technology. LLNL is also applying its scientific and engineering resources to the dual challenge of meeting future energy needs without degrading the quality of the biosphere. Some representative examples are given of the supporting groups vital for providing the specialized expertise and new technologies required by the laboratory's major research programs. (GHT)
1982-07-01
Development of the EE-1 small community solar thermal power system
The development status of the EE-1 Small Community Solar Thermal Power Experiment (SCSE Program) is presented. Current activities on the Phase II single module development effort are presented, together with plans for a Phase III 1 MW/sub e/ demonstration plant. A description of the various subsystems and components is given with a brief review of their development background. Latest performance figures are given for a 1 MW/sub e/ plant, based on 56 power modules, each consisting of a 12m parabolic dish concentrator, a cavity receiver, an organic Rankine power conversion subsystem and a ground-mounted solid-state rectifier.
1981-01-01
Subcritical Noise Analysis Measurements with Fresh and Spent Research Reactor Fuels Elements
Energy Technology Data Exchange (ETDEWEB)
The verification of the subcriticality is of utmost importance for the safe transportation and storage of nuclear reactor fuels. Transportation containers and storage facilities are designed such that nuclear fuels remain in a subcritical state. Such designs often involve excess conservatism because of the lack of relevant experimental data to verify the accuracy of Monte Carlo codes used in nuclear criticality safety analyses. A joint experimental research program between Oak Ridge National Laboratory, Westinghouse Safety Management Solutions, Inc., and the University of Missouri was initiated to obtain measured quantities that could be directly related to the subcriticality of simple arrays of Missouri University Research Reactor (MURR) fuel elements. A series of measurement were performed to assess the reactivity of materials such as BORAL, stainless steel, aluminum, and lead that are typically used in the construction ...
1999-02-01
British Library Electronic Table of Contents (United Kingdom)
This review describes how a mismatch between the knowledge produced by scientists and the evidence demanded by regulators has emerged, and how society has struggled to find definitive answers to questions of safety, for an important flame retardant chemical in current use ? Deca-BDE. This has involved two key disciplines: analytical chemistry and toxicology. Within the chemistry, a lack of standardized methodologies among scientists has resulted in a persistent yet largely undeclared failure to replicate results within the discipline. Within the toxicology, the quest for innovative, curiosity-driven research by university scientists in preference to using validated standard protocols, designed to promote consistency within the risk assessment process, has prompted questions about the credi...
2011-01-01
Single Setting Bilateral Laparoscopic Orchiopexy for Bilateral Intra-Abdominal Testicles
British Library Electronic Table of Contents (United Kingdom)
Purpose The laparoscopic surgical approach to unilateral intra-abdominal testis has replaced the open approach at several large centers. There is considerable literature on experience with unilateral intra-abdominal testes but little on the management of bilateral intra-abdominal testes. We assessed the feasibility and safety of performing single setting bilateral laparoscopic orchiopexy in boys with bilateral intra-abdominal testes. Materials and Methods A single surgeon experience was reviewed. The surgical technique was similar in all cases and on each side, including infra-umbilical access, diagnostic evaluation, peritoneal mobilization lateral to the spermatic vessels and inferior to the vas deferens, gubernacular transection, and a decision for or against a Fowler-Stephens procedure ...
2008-01-01
British Library Electronic Table of Contents (United Kingdom)
In children and adolescents the Second Generation Antipsychotics (SGAs) represent the class of psychotropic drugs whose use has grown more significantly in recent years: they are primarily used for treatment of patients with disruptive behavior disorders, mood disorders and pervasive developmental disorders or mental retardation. In order to compare the efficacy and tolerability of antipsychotics against placebo or each other, a systematic Medline/PubMed search for randomized, double blind studies on SGA in patients younger than 18years of age at enrolment, was conducted. Papers on schizophrenia, discussed in another article of this specific issue, were excluded by the efficacy analysis. A set of standard efficacy and safety indices, such as treatment effect sizes (ES), the Numbers Needed ...
2011-01-01
Science and Technology Review March 2001
Energy Technology Data Exchange (ETDEWEB)
This issue contains the following articles: (1) ''Safety and Security Are Enhanced by Understanding Plutonium''. (2) ''Inside the Superblock'' This area of Lawrence Livermore is home to one of just two US plutonium research and development facilities for defense. (3) ''Exploring the Fundamental Limits of Simulations'' Some of the nation's leading computer simulation experts gathered at Lawrence Livermore to discuss the common barriers facing their craft. (4) ''Plutonium Up Close...Way Close'' An examination of stockpile plutonium at the atomic level indicates so far, so good. (5) ''Shocked and Stressed, Metals Get Stronger'' Laser peening yields stronger, corrosion-resistant metals.
2001-03-01
Regulations on health/functional foods in Korea
International Nuclear Information System (INIS)
The term 'health/functional food' (HFF) refers to food supplements containing nutrients or other substances (in a concentrated form) that have a nutritional or physiological effect whose purpose is to supplement the normal diet. The Korean Health/Functional Food Act that came into effect in 2004 requires these products to be marketed in measured doses, such as in pills, tablets, capsules, and liquids. HFFs are of two types: generic and product-specific. There are 37 ingredients listed in the act for generic HFFs, and if an HFF contains a new active ingredient that is not included in the generic 37 products, it is considered a product-specific HFF. The standardization, safety, and efficacy of a new active ingredient are reviewed by the Korean Food and Drug Administration in order to receive approval as a product-specific HFF. Conforming with international standards and protecting public health requires constant upgrading of the Health/Functional ...
2006-04-03
Regulation of naturally occurring radioactive materials in Australia
British Library Electronic Table of Contents (United Kingdom)
In order to promote uniformity between jurisdictions, the Australian Radiation Protection and Nuclear Safety Agency (ARPANSA) has developed the National Directory for Radiation Protection, which is a regulatory framework that all Australian governments have agreed to adopt. There is a large and diverse range of industries involved in mining or mineral processing, and the production of fossil fuels in Australia. Enhanced levels of naturally occurring radionuclides can be associated with mineral extraction and processing, other industries (e.g. metal recycling) and some products (e.g. plasterboard). ARPANSA, in conjunction with industry and State regulators, has undertaken a review and assessment of naturally occurring radioactive material (NORM) management in Australian industries. This rev...
2011-01-01
Natural convection cooling of liquid metal systems
International Nuclear Information System (INIS)
The recognition that natural convection offers the prospect of an important inherent safety feature for liquid metal cooled reactor systems has provided the impetus for a world-wide research effort over the past decade. Whilst this research has been based on experiment, both plant experiments and out-of-pile experiments, the enormous advances in the development of computing power in recent years have enabled complementary programmes of mathematical modelling through numerical simulation of the transport equations in three spatial dimensions. These not only offer considerable promise for the designer in projecting the behaviour from experiments and prototype plant to full scale plant, they have also proved to be of considerable value in helping us to interpret and understand the results of the experiments themselves. This paper attempts to review the progress made with the emphasis on decay heat removal by natural convection in the pool-type ...
Energy Technology Data Exchange (ETDEWEB)
A review of analytical design methods used for predicting reactor core flow and temperature distributions is presented with emphasis on LMFBR's. The paper also briefly describes and contrasts the methods used for LWR's. These methods are global analysis, subchannel analysis, distributed parameter, and hybrid analysis. The evolution of the local and subchannel analysis methods is presented. Data used for code validation are also presented. Current research and development needs are identified and discussed. Areas identified for future research and development include methods and expermental data for analysis of distorted bundles and natural convection. Methods that have been developed for predicting the safety performance of LMFBR's and LWR's are not within the scope of this paper.
1981-04-01
Investigating the Ultraviolet Properties of Gravity with a Wilsonian Renormalization Group Equation
We review and extend in several directions recent results on the asymptotic safety approach to quantum gravity. The central issue in this approach is the search of a Fixed Point having suitable properties, and the tool that is used is a type of Wilsonian renormalization group equation. We begin by discussing various cutoff schemes, i.e. ways of implementing the Wilsonian cutoff procedure. We compare the beta functions of the gravitational couplings obtained with different schemes, studying first the contribution of matter fields and then the so-called Einstein-Hilbert truncation, where only the cosmological constant and Newton's constant are retained. In this context we make connection with old results, in particular we reproduce the results of the epsilon expansion and the perturbative one loop divergences. We then apply the Renormalization Group to higher derivative gravity. In the case of a general action quadratic in curvature we recover, ...
2008-01-01
British Library Electronic Table of Contents (United Kingdom)
PurposeAlthough the safety and feasibility of partial adrenalectomy in patients with von Hippel-Lindau syndrome have been established, long-term outcomes have not been examined. In this study we evaluate the recurrence and functional outcomes in a von Hippel-Lindau syndrome cohort treated for pheochromocytoma with partial adrenalectomy with a followup of at least 5 years. Materials and MethodsWe reviewed the records of patients with von Hippel-Lindau syndrome treated with partial adrenalectomy for pheochromocytoma at the National Cancer Institute. Demographic, germline mutation status, surgical indication, oncologic and functional outcome data were collected. Local recurrence was defined as radiographic evidence of recurrent tumor on the ipsilateral side of partial adrenalectomy. Patients ...
2010-01-01
Energy Technology Data Exchange (ETDEWEB)
This report presents the preliminary findings of the first phase of the Environmental Survey of the US Department of Energy's (DOE) National Institute for Petroleum and Energy Research (NIPER), conducted February 29 through March 4, 1988. The Survey is being conducted by an interdisciplinary team of environmental specialists, led and managed by the Office of Environment, Safety and Health's Office of Environmental Audit. Team members are being provided by private contractors. The objective of the Survey is to identify environmental problems and areas of environmental risk associated with NIPER. The Survey covers all environmental media and all areas of environmental regulation. It is being performed in accordance with the DOE Environmental Survey Manual. The on-site phase of the Survey involves the review of existing site environmental data, observations of the operations carried on at NIPER and interviews with site personnel. ...
1989-01-01
Endoscopic management of congenital esophageal stenosis
British Library Electronic Table of Contents (United Kingdom)
Background/Purpose: Congenital esophageal stenosis (CES) is a rare malformation. Endoscopic dilations represent a therapeutic option. This study retrospectively evaluated the efficacy and safety of a conservative treatment of CES. Patients and Methods: Patients diagnosed with CES since 1980 by a barium study or endoscopy were reviewed. Endoscopic ultrasonography (Olympus UM-3R-20-MHz radial miniprobe, Olympus Corporation, Tokyo, Japan), available from 2001, allowed for the differential diagnosis of tracheobronchial remnants (TBR) and fibromuscular hypertrophy (FMH) CES. All children underwent conservative treatment by endoscopic dilations (hydrostatic and Savary). Results: Forty-seven patients (20 men) had CES. Fifteen were associated with esophageal atresia; and 8, with Down syndrome. Mea...
2011-01-01
Energy Technology Data Exchange (ETDEWEB)
Onshore pipelines have traditionally been designed with a deterministic stress based methodology. The changing operating environment has however imposed many challenges to the pipeline industry, including heightened public awareness of risk, more challenging natural hazards and increased economic competitiveness. To meet the societal expectation of pipeline safety and enhance the competitiveness of the pipeline industry, significant efforts have been spent for the development of reliability-based design and assessment (RBDA) methodology. This paper will briefly review the technology development in the RBDA area and the focus will be on the progresses in the past years in standard development within the American Society of Mechanical Engineers (ASME) and the Canadian Standard Association (CSA) organizations. (author)
2005-07-01
Consuming for production - Procurement for power production at Cernavoda NPP - Nuclear Sector
International Nuclear Information System (INIS)
The paper presents some aspects relating to the importance of a good communication and cooperation between all factors involved in procurement process at Societatea Nationala 'Nuclearelectrica', SNN. In order to comply with the internal and international rules related to safety in nuclear field and public procurement requirements and for maintaining a high standard of operational performance of Cernavoda NPP, adequate procurement systems were developed by SNN SA. The importance of human factor and the training activities for all personnel from this chain of procurement process is the main key issue to maintain high quality of their activities considering that procurement documents are reviewed and approved before to be issued by all departments involved in procurement process. The specialized department for public acquisition is supervising that the procurement processes initiated at the level of branches, in accordance with their needs and ...
2009-10-12
Adoptive immunotherapy with virus-specific T cells
British Library Electronic Table of Contents (United Kingdom)
Viral infections are still common causes of morbidity and mortality in immunosuppressed patients after allogeneic hematopoietic stem cell transplantation. Infections caused by virus such as cytomegalovirus, adenovirus and Epstein-Barr virus are well-known. In addition, several other viruses such as polyomavirus and human herpesvirus 6 have been recently reported to be causes of significant complications. As the delay in recovery of virus-specific cellular immune response after transplant is associated with viral reactivation and viral disease, adoptive immunotherapy to restore virus-specific cellular immunity is an attractive option. Recent clinical trials showed the safety and effectiveness of adoptive immunotherapy against viral diseases. In this review, we summarize the current status o...
2011-01-01
A vibration amplification device for the seismic margins test of NPP equipment
International Nuclear Information System (INIS)
This paper describes new test methodologies to obtain data used to evaluate the ultimate seismic strength of Nuclear Power Plant (NPP) equipment related to nuclear safety. The paper first reviews existing equipment seismic test data from the viewpoint of the evaluation of their ultimate seismic strength and/or seismic design margins, and extracts the issues in the existing data with regard to their applicability to the evaluation. Then, the paper proposes new test methodologies for the equipment to evaluate their ultimate seismic strength. The test methodology of the equipment employs a vibration amplification system to a shaking table and enhances its applicable maximum acceleration up to 6g. The test methodology herein is cost effective for obtaining test data that is indispensable for evaluating proper seismic margins of NPPs. (author)
2003-09-15
Gas Storage Technology Consortium
Energy Technology Data Exchange (ETDEWEB)
The EMS Energy Institute at The Pennsylvania State University (Penn State) has managed the Gas Storage Technology Consortium (GSTC) since its inception in 2003. The GSTC infrastructure provided a means to accomplish industry-driven research and development designed to enhance the operational flexibility and deliverability of the nation's gas storage system, and provide a cost-effective, safe, and reliable supply of natural gas to meet domestic demand. The GSTC received base funding from the U.S. Department of Energy's (DOE) National Energy Technology Laboratory (NETL) Oil & Natural Gas Supply Program. The GSTC base funds were highly leveraged with industry funding for individual projects. Since its inception, the GSTC has engaged 67 members. The GSTC membership base was diverse, coming from 19 states, the District of Columbia, and Canada. The membership was comprised of natural gas storage field operators, service companies, industry ...
2010-09-30
Natural circulation in FFTF, a loop type LMFBR
International Nuclear Information System (INIS)
The authors present a state-of-the-art review of natural circulation heat transfer in loop type reactor plants. Most of the examples are taken from Fast Flux Test Facility (FFTF) design experience, drawing on the authors' familiarity and a developing base of available documentation. On-going studies related to the Clinch River Breeder Reactor (CRBR) and some foreign experience are also noted where available in the literature. The emphasis is on the role of natural circulation in decay heat removal; however, free convection during either operation at power or normal shutdown does influence some aspects of the design and these are reviewed. In treating decay heat removal the topics discussed include steady state loop performance and transient dynamics for conditions immediately after scram and for the longer term which involves different considerations. The review summarizes complex dynamics, specific to the FFTF design ...
Energy Technology Data Exchange (ETDEWEB)
Ontario's Countdown Acid Rain program was formulated in 1985 and placed an annual SO{sub 2} emissions cap of 885 kilotonnes over the province from 1994. Caps were placed on emissions from the Inco nickel/copper smelter in Sudbury, the Falconbridge nickel/copper smelter in Sudbury, the Algoma iron ore sintering plant in Wawa, and Ontario Hydro fossil-fuel plants province-wide. Semi-annual reports are required of the companies, with the 6th report outlining the final planning phase and the 7th and later reports outlining implementation progress. This document summarizes the contents of the 7th set of reports and the responses of the government review team to each company's efforts. All companies have begun implementing abatement plans outlined in the final planning phase reports of December 1988 at a rapid pace and are generally on track in controlling emissions. However, all 4 company reports lack the necessary detail for a ...
1990-01-01
The influence of salt aerosol on alpha radiation detection by WIPP continuous air monitors
Energy Technology Data Exchange (ETDEWEB)
Alpha continuous air monitors (CAMs) will be used at the Waste Isolation Pilot Plant (WIPP) to measure airborne transuranic radioactivity that might be present in air exhaust or in work-place areas. WIPP CAMs are important to health and safety because they are used to alert workers to airborne radioactivity, to actuate air-effluent filtration systems, and to detect airborne radioactivity so that the radioactivity can be confined in a limited area. In 1993, the Environmental Evaluation Group (EEG) reported that CAM operational performance was affected by salt aerosol, and subsequently, the WIPP CAM design and usage were modified. In this report, operational data and current theories on aerosol collection were reviewed to determine CAM quantitative performance limitations. Since 1993, the overall CAM performance appears to have improved, but anomalous alpha spectra are present when sampling-filter salt deposits are at normal to high levels. This ...
1996-01-01
Development of QA/QC technology in Korea
International Nuclear Information System (INIS)
KAERI (Korea Advanced Energy Research Institute) has performed research to develop the fabrication technology of CANDU nuclear fuel since 1981. Based on the satisfactory results of in-pile and out-of-pile tests of prototype nuclear fuel and the outstanding performance of 48 KAERI-made nuclear fuels in Wolsung(CANDU) power reactor, Korean government decided KAERI to supply all the nuclear fuels for Wolsung from 1988. In order to guarantee the safety and performance of nuclear fuel manufactured in mass production scale, well-organized quality assurance system and appropriate quality control techniques should be established. To establish the QA system, KAERI reviewed various QA standards and decided to establish QA system based on the 10 CFR 50 Appendix B. Quality control techniques was also revised to fit the mass production even though quality inspection techniques have already been developed during research period. By applying statistical ...
1986-10-06
Mitigating aging in CANDU plants
Energy Technology Data Exchange (ETDEWEB)
Aging degradation is a phenomenon we all experience throughout life, both on a personal basis and in business. Many industries have been successful in postponing the inevitable impact on their related systems and components through programs to maintain long-term reliability, maintainability and safety. However, this has not always been the case for nuclear power. While all power plants are experiencing the world trend of increasing operating costs with age, few (if any) have been able to fully define the parameters that solve the aging equation, particularly in relation to major components. Inspection and preventive maintenance have not been effective in predicting life-limiting degradation and failure. In CANDU nuclear plants, utilities are taking a comprehensive approach in dealing with the aging problem. Programs have been established to identify the current condition and degradation mechanisms of critical components, ...
1995-07-01
Emplacement technology for the direct disposal of spent fuel into deep vertical boreholes
International Nuclear Information System (INIS)
In the early sixties it was decided to investigate salt formations on its suitability to host heat generating radioactive waste in Germany. In the reference repository concept consequently the emplacement of vitrified waste canisters in deep vertical boreholes inside a salt mine was considered whereas spent fuel should be disposed of in self shielding casks (type POLLUX) in horizontal drifts. The POLLUX casks, 65 t heavy carbon steel casks, will be laid down on the floor of a horizontal drift in one of the disposal zones to be constructed in the salt dome at the 870 m level. The space between casks and drift walls will be backfilled with crushed salt. The transport, the handling und the emplacement of POLLUX casks were subject of successfully performed demonstration and in situ tests in the nineties and resulted in an adjustment of the atomic law. The borehole disposal concept comprises the emplacement of unshielded canisters with vitrified HLW in boreholes with a diameter of 60 cm and ...
2008-09-01
The year 2000 embedded systems problem to maintain the safety of nuclear installations
International Nuclear Information System (INIS)
The Y2K problem may impact on nuclear installations in a number of ways because embedded systems are used in nuclear routine operation, monitoring and control system. The very simplest embedded systems are capable of performing only a single function or set of functions to meet a single predetermined purpose. In more complex systems the functioning of the embedded system is determined by an application program that enables the embedded system to be used for a particular purpose in a specific application. The simplest devices consist of a single microprocessor which may itself be packaged with other chips in a hybrid system or Application Specific Integrated Circuit (ASIC). Its input comes from a detector or sensor and its output goes to a switch or activator which may start or stop the operation of a positioning motors or, by operating a valve, may control the flow of cooling system to reactor core. Embedded systems in our organization are also be found in Batan ...
1999-02-01
The advanced CANDU reactor: The next step in safety and economics
International Nuclear Information System (INIS)
The Advanced CANDU Reactor (ACR"T"M) is the 'Next Generation' CANDU"R reactor, aimed at safe, reliable power production at a capital cost significantly less than that of current reactors such as the very successful CANDU 6 reactors (e.g., Wolsong 1-4). The Wolsong 1-4 units are being joined by the Qinshan Phase 3 units in China as the current successful examples of CANDU technology. The ACR design builds on this knowledge base, adding a selected group of innovations to obtain substantial cost reduction while retaining a proven design basis. The ACR maximizes the use of components and equipment applications that are well proven through CANDU and other nuclear experience. Joint development of equipment designs and specifications with manufactures has been emphasized. Similarly, the ACR design emphasizes constructability, and takes advantage of inherent CANDU features to enable short project and construction schedules. Overall, the ACR design represents a balance of proven design basis ...
2003-04-01
Energy Technology Data Exchange (ETDEWEB)
Test Area North (TAN) was a site of the Aircraft Nuclear Propulsion (ANP) Project of the U.S. Air Force and the Atomic Energy Commission. Its Cold War mission was to develop a turbojet bomber propelled by nuclear power. The project was part of an arms race. Test activities took place in five areas at TAN. The Assembly & Maintenance area was a shop and hot cell complex. Nuclear tests ran at the Initial Engine Test area. Low-power test reactors operated at a third cluster. The fourth area was for Administration. A Flight Engine Test facility (hangar) was built to house the anticipated nuclear-powered aircraft. Experiments between 1955-1961 proved that a nuclear reactor could power a jet engine, but President John F. Kennedy canceled the project in March 1961. ANP facilities were adapted for new reactor projects, the most important of which were Loss of Fluid Tests (LOFT), part of an international safety program for commercial power reactors. ...
2005-02-01
Energy Technology Data Exchange (ETDEWEB)
This paper described the Geographic Response Information Network (GRIN) project which was launched to address some of the logistical challenges that often complicate oil spill and emergency response operations. The objective of the project was to develop a computer-based tool for incident logistics to organize maps and data related to oil spills, safety, public relations and basic community resources. In addition to its use for oil spill response planning, the data available can be useful for all-hazards emergency response planning. Early prototypes of the GRIN used PowerPoint slides to organize basic information about coastal communities in Alaska. With time, hyper text markup language (html) was used as the programming format because it can be more readily hyper-linked. Currently, GRIN is organized as a web page with the following 5 categories of information: general, liaison, public information, logistics and safety. ...
2006-07-01
Assessment of RELAP5 model for the University of Massachusetts Lowell research reactor
International Nuclear Information System (INIS)
RELAP5 (Reactor Excursion and Leak Analysis Program) is a system code developed at the Idaho National Environmental and Engineering Laboratory for thermal hydraulic analysis of nuclear reactors. The code RELAP5 is widely used for safety analysis studies of commercial nuclear power plants. However, recent released version of RELAP5/3.2 and over present significant capabilities for analysis of nuclear reactor research systems. As a contribution to the assessment of RELAP5/3.3 for research reactor safety analysis, experimental data from the University of Massachusetts Lowell Research Reactor UMLRR are used. The UMLRR is a 1 MW, light water moderated and cooled, graphite-reflected, open-pool type research reactor. This paper presents the development and the validation of a UMLRR-RELAP model using experimental data. For this purpose, a series of experiments were performed for benchmarking RELAP5 calculations for research reactor ...
Application and experience of low alloy steel main coolant lines in PWRs
Energy Technology Data Exchange (ETDEWEB)
The significant technical and industrial aspects which have led to main coolant line (MCL) materials selection are addressed from a long term experience and operational practice point of view. They are based on the Siemens/KWU developed basic material concept for its nuclear power plants. It considers the choice of appropriate materials, the evaluation and qualification of the materials and the materials manufacturer, the use of appropriate semi-finished products, the tailoring of material and semi-finished products to the specific requirements of the various systems, the application of adequate manufacturing processes and the proof of the requirements by specifying proper tests and examinations. The main systems are assigned to safety classes in accordance with their safety relevance. Summarizing the operation time of nuclear power plants with ferritic MCL equipped by Siemens/KWU, more than 200 years of operation experience exist and no ...
1996-08-01
Energy Technology Data Exchange (ETDEWEB)
This report describes the work performed during FY 1995 by Pacific Northwest Laboratory in developing and optimizing analysis techniques for identifying organics present in Hanford waste tanks. The main focus was to provide a means for rapidly obtaining the most useful information concerning the organics present in tank waste, with minimal sample handling and with minimal waste generation. One major focus has been to optimize analytical methods for organic speciation. Select methods, such as atmospheric pressure chemical ionization mass spectrometry and matrix-assisted laser desorption/ionization mass spectrometry, were developed to increase the speciation capabilities, while minimizing sample handling. A capillary electrophoresis method was developed to improve separation capabilities while minimizing additional waste generation. In addition, considerable emphasis has been placed on developing a rapid screening tool, based on Raman and infrared spectroscopy, for determining organic ...
1995-09-01
Nuclear safety culture star-class assessment system based BP neural network
International Nuclear Information System (INIS)
In order to build the safety culture for nuclear power industry, it is important to evaluate the safety culture scientifically. Considering the traits of safety culture in the nuclear power industry, 24 safety culture assessment indexes are established from 4 aspects such as Safety consciousness, Safety attitude, Safety action and Safety actuality by using the SMART criteria. Safety culture star-class assessment criterion is presented and safety culture star-class assessment system is developed by using Visual Basic 6.0 and BP neural network. The system has a better generalization ability, and it can show exactly which phase the safety culture is in. Experimental results show that safety culture star-class assessment is practical and easy ...
2007-02-01
Terra Nova Environmental effects monitoring program
Energy Technology Data Exchange (ETDEWEB)
Elements of the environmental effects monitoring program in the Terra Nova oil field, about 350 km east-southeast of St. John's, Newfoundland, are described. This oilfield is being developed using a floating production storage and offloading (FPSO) facility. A total of 24 wells are expected to be drilled through seven subsea templates located in four glory holes to protect them from icebergs. Subsea installations will be linked to the FPSO by trenched flowlines connected to flexible risers. The FPSO will offload to shuttle tankers. First oil is expected in 2001. The environmental effects monitoring program will be conducted annually for the first two years beginning in 2000. Subsequent scheduling will be determined after a review of monitoring data collected during the first three years. Input to the design of the monitoring program was provided by all stakeholders, i. e. owners, local public, ...
2000-07-01
Telecommunications Network Plan
International Nuclear Information System (INIS)
The Office of Civilian Radioactive Waste Management (OCRWM) must, among other things, be equipped to readily produce, file, store, access, retrieve, and transfer a wide variety of technical and institutional data and information. The data and information regularly produced by members of the OCRWM Program supports, and will continue to support, a wide range of program activities. Some of the more important of these information communication-related activities include: supporting the preparation, submittal, and review of a license application to the Nuclear Regulatory Commission (NRC) to authorize the construction of a geologic repository; responding to requests for information from parties affected by and/or interested in the program; and providing evidence of compliance with all relevant Federal, State, local, and Indian Tribe regulations, statutes, and/or treaties. The OCRWM Telecommunications Network ...
1997-10-07
Relevance of mixed layer scaling for daytime dispersion based on RAPS and other field programs
Energy Technology Data Exchange (ETDEWEB)
A brief review and assessment of field measurement programs that provide data for mixed layer diffusion research is presented. The majority of programs emphasize either the meteorological aspects of the mixed layer or plume characterization. Few programs are available that provide the complimentary blend of plume and appropriate meteorological measurements needed to adequately validate mixed layer diffusion theory. Three major U.S. EPA (Environmental Protection Agency) field programs that provide data bases for model development and validation of mixed layer diffusion processes are described and discussed in more detail. The Regional Air Pollution Study (RAPS) focused on measurements of surface and mixed layer turbulent transport processes in the urban environment. The Tennessee Plume Study (TPS) obtained a database with coincident measurement of boundary layer turbulent structure ...
1983-01-01
The review of radioactive waste management in the world
International Nuclear Information System (INIS)
Radioactive waste is generally classified on the basis of how much radiation and the type of radiation it emits as well as the length of time over which it will continue to emit radiation. Many activities dealing with radioactive materials produce nuclear wastes, including civilian nuclear power programs (nuclear Power plant operations and nuclear fuel-cycle activities), defense nuclear programs (nuclear weapons production, naval nuclear reactor programs, and related R and D), and industrial and institutional activities (scientific research, medical operations, and other industrial uses of Radioisotopic sources or Radio chemicals). To minimize the potential adverse health and environment impacts to people and other systems including of animals, plant and etc, during the entire lifetime of the radionuclides involved, nuclear waste must be carefully and properly managed. The scope of nuclear - waste management encompasses ...
Analysis of lagoon sludge characteristics for choice of treatment process
Energy Technology Data Exchange (ETDEWEB)
The Korea Atomic Energy Research Institute has launched a decommissioning program of uranium conversion plant. One of the important tasks in the decommissioning program is the treatment of the sludge, which was generated during operation and stored in the two ponds of the lagoon. The treatment requires the volume reduction of lagoon sludges for the low cost of the program and the conversion of the chemical forms, including uranium, for the acceptance at the final disposal site. The physical properties, such as densities, were measured and chemical compositions and radiological properties were analyzed. The denitration was a candidate process which would satisfy the requirements for sludge treatment, and the characteristics of thermal decomposition and dissolution with water were analyzed. The main compounds of the sludge were ammonium and sodium nitrate from conversion plant and calcium nitrate, calcium carbonate from Ca ...
2002-04-01
University of Michigan workscope for 1991 DOE University program in robotics for advanced reactors
International Nuclear Information System (INIS)
The University of Michigan (UM) is a member of a team of researchers, including the universities of Florida, Texas, and Tennessee, along with Oak Ridge National Laboratory, developing robotic for hazardous environments. The goal of this research is to develop the intelligent and capable robots which can perform useful functions in the new generation of nuclear reactors currently under development. By augmenting human capabilities through remote robotics, increased safety, functionality, and reliability can be achieved. In accordance with the established lines of research responsibilities, our primary efforts during 1991 will continue to focus on the following areas: radiation imaging; mobile robot navigation; three-dimensional vision capabilities for navigation; and machine-intelligence. This report discuss work that has been and will be done in these areas.
Transuranic material recovery in the Integral Fast Reactor fuel cycle demonstration
Energy Technology Data Exchange (ETDEWEB)
The Integral Fast Reactor is an innovative liquid metal reactor concept that is being developed by Argonne National Laboratory. It takes advantage of the properties of metallic fuel and liquid metal cooling to offer significant improvements in reactor safety, operation, fuel cycle economics, environmental protection, and safeguards. The plans for demonstrating the IFR fuel cycle, including its waste processing options, by processing irradiated fuel from the Experimental Breeder Reactor-II fuel in its associated Fuel Cycle Facility have been developed for the first refining series. This series has been designed to provide the data needed for the further development of the IFR program. An important piece of the data needed is the recovery of TRU material during the reprocessing and waste operations.
1993-01-01
Transuranic material recovery in the Integral Fast Reactor fuel cycle demonstration
Energy Technology Data Exchange (ETDEWEB)
The Integral Fast Reactor is an innovative liquid metal reactor concept that is being developed by Argonne National Laboratory. It takes advantage of the properties of metallic fuel and liquid metal cooling to offer significant improvements in reactor safety, operation, fuel cycle economics, environmental protection, and safeguards. The plans for demonstrating the IFR fuel cycle, including its waste processing options, by processing irradiated fuel from the Experimental Breeder Reactor-II fuel in its associated Fuel Cycle Facility have been developed for the first refining series. This series has been designed to provide the data needed for the further development of the IFR program. An important piece of the data needed is the recovery of TRU material during the reprocessing and waste operations.
1993-03-01
The BCNT treatment planning for the Brookhaven trials on human gliomas
International Nuclear Information System (INIS)
Boron neutron capture therapy (BNCT) trials for human glioma (glioblastoma multiform) were initiated September 1994 at the Brookhaven National Laboratory (BNL). Patients are given p-boronophenylalanine-fructose (BPA-F) intravenously as the boron carrier followed by exposure to the epithermal-neutron beam at the Brookhaven Medical Research Reactor (BMRR). The initial phase of the study is to determine safety and toxicity of the drug and irradiation procedure. The epithermal-neutron beam was developed in a joint effort by BNL and Idaho National Engineering Laboratory (INEL) researchers. For the human trials, treatment planning and radiation dose estimation is performed using the BNCT-Rtpe and the rtt-MC computer codes developed by the INEL BNCT program. This paper discusses our initial experience using these treatment planning codes for human subjects. The basic principles of BNCT have been previously documented.
Technical input to NAECA rulemaking for gas-fired ranges. Topical report, January-July 1994
Energy Technology Data Exchange (ETDEWEB)
The report presents the results of a Gas Research Institute (GRI) program to evaluate the technical and economic aspects of design options proposed by the U.S. Department of Energy (DOE) for reducing the energy consumption of residential ranges and ovens as mandated by the National Appliance Energy Conservation Act (NAECA) of 1987. The study shows that none of the proposed DOE design options are justified except electric ignition for stand-alone cooktops, based on life-cycle costs, loss of consumer utility, safety, technical considerations, or food quality considerations. An individual range uses so little gas during the year (approximately $14/year for a self-cleaning range) that it is difficult to justify any design modification, since the cost of even a simple modification could not be recovered on the basis of gas saved.
1994-07-01
Safety philosophy and concepts for large liquid metal breeder reactor power plants
International Nuclear Information System (INIS)
This paper addresses the unique related aspects of the LMFBR concept which are of significance to containment design and structural analysis. Topics covered include: Primary boundary integrity assurance; Effects of sodium spills on integrity of structures; Provisions being considered for containment of melted cores; Fuel handling accidents. Specific reference is made to the FFTF and the Clinch River Breeder Reactor Project designs and methods of treatment of the above problems. In particular, the part played by tests, such as those carried out on a simulated FFTF model, and the planned structural reliability and related programs are considered. Where practicable, these topics are addressed in a manner which places FFTF and CRBR in context with other LMFBR's and point to a possible direction for future American LMFBR designs. (Auth.).
Safety analysis of FFTF loss of flow without scram tests
International Nuclear Information System (INIS)
A program of tests were conducted in July 1986 at the Fast Flux Test Facility (FFTF) to demonstrate that the reactor could withstand a prototypic loss of flow (LOF) without scram without sustaining fuel damage. The reactor was taken to powers up to 50%, and the main primary coolant pump motors were tripped without scramming the control rods. This paper summarizes the analyses performed to demonstrate the maintenance of redundant protection for all design events as well as potential new events introduced by the test. The analyses focused on the following consequences: (1) unexpected test behavior; (2) transient overpower event during the test; and (3) LOF event during the test.
1987-06-07
Energy Technology Data Exchange (ETDEWEB)
To make a quantitative comparison of risks between the SNR-300 and a modern PWR (Biblis B), the consequences of an accident or the extent of damage of a release of radionuclides to the environment due to an accident are estimated by computer programs for accident consequence models. The accident analysis includes an analysis of events for Bethe-Tait accidents with failure of the outer containment. The FGSB release rates are compared with those of the Society for Reactor Safety (GRS).
1982-01-01
British Library Electronic Table of Contents (United Kingdom)
Summary This third paper, in a three-part CE series on the preventions of infection in patients with chronic kidney disease, focuses on surveillance and auditing of healthcare-associated infections within the renal care environment. The last decade has seen an increased awareness of the threat to patient safety from healthcare-associated infection (HCAI) and the emergence of multi-drug resistance organisms. Effective HCAI prevention strategies include adequate governance structures, access to expert advice, adherence to standard and transmission-based precautions, minimising the use of invasive medical devices, and surveillance. Surveillance data can be collected using outcome (e.g. infection) and/or process (e.g. hand hygiene compliance audit) measures. Establishing a surveillance program...
2011-01-01
Methods for probabilistic design of wind turbines
Energy Technology Data Exchange (ETDEWEB)
This report gives a brief introduction to the project `Probabilistic Design Tool for Wind Turbines` - PRODETO - which was carried out during the years 1996-98 with partial funding from the European Commission under the Non-Nuclear Energy Programme JOULE III. The report gives an overview of the objectives and motivation for the project, and the methodology used. In this context, an example of reliability-based wind turbine design against fatigue failure is outlined with emphasis on the various important steps herein, which include probabilistic load and resistance modelling, calculation of failure probability, and calibration of partial safety factors for use with a deterministic design code format. The results of the project are presented with emphasis on a developed computer program and its capabilities, and the various elements of an executed case study are outlined. A list of project reports concludes the report. (au)
1998-12-01
Human factors assessments of innovative technologies: Robotics sector
International Nuclear Information System (INIS)
The U.S. Department of Energy (DOE) has funded major environmental technology developments over the past several years. One area that received significant attention is robotics, which has resulted in the development of a wide range of unique robotic systems tailored to the many tasks unique to the DOE complex. These systems are often used in highly hazardous environments, which reduces or eliminates worker exposures. The DOE, concurrent with the technology development initiative, also established and funded a 5-yr cooperative agreement intended to interface with the technology development community-with specific attention to the occupational safety and health aspects associated with individual technologies through human factors and hazard assessments. This program is now in its third year.
1997-11-16
Five years operating experience at the Fast Flux Test Facility
Energy Technology Data Exchange (ETDEWEB)
The Fast Flux Test Facility (FFTF) is a 400 Mw(t), loop-type, sodium-cooled, fast neutron reactor. It is operated by the Westinghouse Hanford Company for the United States Department of Energy at Richland, Washington. The FFTF is a multipurpose test reactor used to irradiate fuels and materials for programs such as Liquid Metal Reactor (LMR) research, fusion research, space power systems, isotope production and international research. FFTF is also used for testing concepts to be used in Advanced Reactors which will be designed to maximize passive safety features and not require complex shutdown systems to assure safe shutdown and heat removal. The FFTF also provides experience in the operation and maintenance of a reactor having prototypic components and systems typical of large LMR (LMFBR) power plants. The 5 year operational performance of the FFTF reactor is discussed in this report. 6 refs., 10 figs., 2 tabs.
1987-04-01
Five years operating experience at the Fast Flux Test Facility
International Nuclear Information System (INIS)
The Fast Flux Test Facility (FFTF) is a 400 Mw(t), loop-type, sodium-cooled, fast neutron reactor. It is operated by the Westinghouse Hanford Company for the United States Department of Energy at Richland, Washington. The FFTF is a multipurpose test reactor used to irradiate fuels and materials for programs such as Liquid Metal Reactor (LMR) research, fusion research, space power systems, isotope production and international research. FFTF is also used for testing concepts to be used in Advanced Reactors which will be designed to maximize passive safety features and not require complex shutdown systems to assure safe shutdown and heat removal. The FFTF also provides experience in the operation and maintenance of a reactor having prototypic components and systems typical of large LMR (LMFBR) power plants. The 5 year operational performance of the FFTF reactor is discussed in this report. 6 refs., 10 figs., 2 tabs.
1987-09-13
FY2000 Annual Self-Evaluation Report for the Pacific Northwest National Laboratory
Energy Technology Data Exchange (ETDEWEB)
This self-evaluation report offers a summary of results from FY2000 actions to achieve Pacific Northwest National Laboratory's strategy and provides an analysis of the state of their self-assessment process. The result of their integrated planning and assessment process identifies Laboratory strengths and opportunities for improvement. Critical elements of that process are included in this report; namely, a high-level summary of external oversight activities, progress against Operations Improvement Initiatives, and a summary of Laboratory strengths and areas for improvement developed by management from across the laboratory. Some key areas targeted for improvement in FY2001 are: systems approach to resource management; information protection; integrated safety management flow-down to the benchtop; cost management; integrated assessment; Price Anderson Amendments Act (PAAA) Program; and travel risk mitigation.
2000-11-15
FFTF operating experience, 1982-1984
International Nuclear Information System (INIS)
The Fast Flux Test Facility (FFTF) is a 400 Mwt sodium-cooled fast reactor operating at the Hanford Engineering Development Laboratory, Richland, Washington, to conduct fuels and materials testing in support of the US Liquid Metal Fast Breeder Reactor (LMFBR) program. Startup and initial power testing included a comprehensive series of nonnuclear and nuclear tests to verify the thermal, hydraulic, and neutronic characteristics of the plant. A specially designed series of natural circulation tests were then performed to demonstrate the inherent safety features of the plant. Early in 1982, the FFTF began its first 100-day irradiation cycle. Since that time the plant has operated very well, achieving a cycle capacity factor of 94% in the most recent irradiation cycle. Seventy-five specific test assemblies and 25,000 individual fuel pins have been irradiated, some in excess of 80 MWd/Kg.
1984-04-09
Accelerated aging speeds test of instrument reliability
International Nuclear Information System (INIS)
This paper shows how molecular theory paves the way for accelerated aging tests of safety-related equipment in nuclear power plants, as required by NRC qualification programs. Arrhenius' model, based on an equation, provides useful information regarding the extent of molecular change as a function of time and temperature. Critical to determining the aging characteristics and qualified life of organic materials is the activation energy concept, which is derived from information gathered when the molecular reaction of the material is documented over the entire life cycle. In accelerated-aging applications, the importance of the model lies in characterizing the chemical related reactions of materials. The problem with the Arrhenius approach is that, in generating a testing period of reasonable duration, a rather high test temperature must be selected which may lead to an added and unrelated environmental effect.
1982-01-01
The overarching goals of the 'Kootenai River Floodplain Ecosystem Operational Loss Assessment, Protection, Mitigation and Rehabilitation' Project (BPA Project No.2002-011-00) are to: (1) assess abiotic and biotic factors (i.e., geomorphologic, hydrological, aquatic and riparian/floodplain communities) in determining a definitive composition of ecological integrity, (2) develop strategies to assess and mitigate losses of ecosystem functions, and (3) produce a regional operational loss assessment framework. To produce a scientifically defensible, repeatable, and complete assessment tool, KTOI assembled a team of top scientists in the fields of hydrology, hydraulics, ornithology, entomology, statistics, and river ecology, among other expertise. This advisory team is known as the Research Design and Review Team (RDRT). The RDRT scientists drive the review, selection, and adaptive management of the research designs to evaluate the ...
2009-02-18
Energy Technology Data Exchange (ETDEWEB)
Program activities and achievements in 1982 of the geodynamic program are summarized. The significant results presented are summarized.
1983-05-01
Energy Technology Data Exchange (ETDEWEB)
Safety in general and harmonization of International Maritime Organization rules on mobile offshore drilling rig operation in particular are discussed. The improvement of the industry's safety record is also discussed.
1985-02-01
International Nuclear Information System (INIS)
For more than thirty years, the IAEA has published a set of documents aimed at the limitation of the radiation exposure of the population from various nuclear activities. In particular, in 1994 the IAEA published Technical Reports Series No. 364, Handbook of Parameter Values for the Prediction of Radionuclide Transfer in Temperate Environments. Over the years, it has proved to be a valuable reference for radioecologists, modellers and authorities in Member States, and has been quoted in numerous impact assessments. Technical Reports Series No. 364 was based on a review of available data up to the end of 1992. However, a number of high quality critical reviews have been produced in recent years for some of the transfer parameter values which merit consideration. Thus, it was assumed that there is sufficient new information available to warrant reconsideration of a significant proportion of the values given in Technical Reports Series No. 364 and ...
1993-04-05
Validation of WIMS-AECL reactivity device calculations for CANDU reactor
Energy Technology Data Exchange (ETDEWEB)
An important component of the overall program to validate WIMS-AECL for use with RFSP in the analysis of CANDU-6 reactors for design and safety analysis calculations is the validation of calculations of incremental cross sections used to represent reactivity devices. A method has been developed for the calculation of the three-dimensional neutron flux distribution in and around CANDU reactor fuel channels and reactivity control devices. The methods is based on one- and two dimensional transport calculations with the WIMS-AECL lattice cell code, SPH homogenization, and three-dimensional flux calculations with finite-difference diffusion theory using the MULTICELL code. Simulations of Wolsung 1 Phase-B commissioning measurements and Point Lepreau restart tests have been performed, as a part of the program to validate WIMS-AECL lattice cell calculations for application to CANDU reactor simulations in RFSP. The incremental ...
1997-06-01
The experience of obsolete item identification and solution in CANDU NPPs
International Nuclear Information System (INIS)
Design and procurement of equipment for nuclear power plant took place in late 1970's. A large number of originally installed equipment is obsolete. The manufacturer's do not support their products or have discontinued their production due to technological evolutions or lack of product demand. Lack of spares affects the performance of obsolete equipment and has a negative impact on plant safety and plant production. A proactive approach to address obsolescence is necessary to ensure critical spares are always available when needed. This is an ongoing effort and requires a program to be in place to resolve immediate and longterm issues. A cross-functional team with adequate external exposure is needed to administer the obsolescence program. CANDU utilities and CANDU Owners Group(COG) has taken initiatives to identify lack of equipment spares in the members' plant. The equipment replacement information collected from each ...
2010-10-01
Energy Technology Data Exchange (ETDEWEB)
The purpose and need for DOE to undertake the actions described in this document are to improve the efficiency of the Alternating Gradient Synchrotron (AGS) complex. Benefits would include optimization of the AGS scientific program, increased high-energy and nuclear physics experimentation, improved health and safety conditions for workers and users, reduced impact on the environment and the general public, energy conservation, decreased generation of hazardous and radioactive wastes, and completion of actions required to permit the AGS to be the injector to the Relativistic Heavy Ion Collider (RHIC)., Improved efficiency is defined as increasing the AGS`s capabilities to capture and accelerate the proton intensity transferred to the AGS from the AGS booster. Improved capture of beam intensity would reduce the beam losses which equate to lost scientific opportunity for study and increased potential for radiation doses to workers and the general ...
1994-03-01
Heavy water reactor facility large-scale containment cooling test program
The Heavy Water Reactor Facility (HWRF), as part of the defense-in-depth philosophy to mitigate the effect of design-basis and severe accidents, is equipped with a passive containment cooling system (PCCS). The function of the PCCS is to provide a safety-grade path to the ultimate heat sink for the removal of the reactor coolant system sensible heat and core decay heat. Ambient air enters an annular space between the steel containment shell and the surrounding concrete shield building through inlets in the shield building wall, is heated via natural convection, rises, and exits the building through a chimney located above the containment dome. A test program is in place to access parameters important to the effective operation of the PCCS. This paper focuses on the large-scale tests (LSTs). The objectives of these tests are as follows: (1) demonstrate natural circulation cooling with more prototypic cylinder and dome surface area ratios than ...
1992-01-01
Heavy water reactor facility large-scale containment cooling test program
International Nuclear Information System (INIS)
The Heavy Water Reactor Facility (HWRF), as part of the defense-in-depth philosophy to mitigate the effect of design-basis and severe accidents, is equipped with a passive containment cooling system (PCCS). The function of the PCCS is to provide a safety-grade path to the ultimate heat sink for the removal of the reactor coolant system sensible heat and core decay heat. Ambient air enters an annular space between the steel containment shell and the surrounding concrete shield building through inlets in the shield building wall, is heated via natural convection, rises, and exits the building through a chimney located above the containment dome. A test program is in place to access parameters important to the effective operation of the PCCS. This paper focuses on the large-scale tests (LSTs). The objectives of these tests are as follows: (1) demonstrate natural circulation cooling with more prototypic cylinder and dome surface area ratios than ...
1992-11-15
Graphite Technology Development Plan
Energy Technology Data Exchange (ETDEWEB)
This technology development plan is designed to provide a clear understanding of the research and development direction necessary for the qualification of nuclear grade graphite for use within the Next Generation Nuclear Plant (NGNP) reactor. The NGNP will be a helium gas cooled Very High Temperature Reactor (VHTR) with a large graphite core. Graphite physically contains the fuel and comprises the majority of the core volume. Considerable effort will be required to ensure that the graphite performance is not compromised during operation. Based upon the perceived requirements the major data needs are outlined and justified from the perspective of reactor design, reatcor performance, or the reactor safety case. The path forward for technology development can then be easily determined for each data need. How the data will be obtained and the inter-relationships between the experimental and modeling activities will define the technology development for graphite ...
2007-09-01
Evaluation of light-water-moderated, mixed-oxide, hexagonal pitch lattices
International Nuclear Information System (INIS)
The use of previously measured mixed-oxide (MOX) fuel systems as benchmarks can be valuable tool in computational analysis and quality assurance efforts. The Fissile Materials Disposition Program (FMDP) has identified these experiments as potential benchmarks, or standards, for VVER's employing MOX fuel. Standards for the analysis of these benchmark experiments were based on those used in the recent compilation International Handbook of Evaluated Criticality Safety Benchmark Experiments begun in 1992 by the U.S. Department of Energy. The Los Alamos National Laboratory's archives were explored for log-book records of these experiments without success. These experiments were the first to use MOX fuel in light water. Three approach-to-critical experiments were performed using fuel rods at various pitches and different plutonium-oxide concentrations. A parallel program verified the prediction of critical condition as similar ...
1997-11-16
Energy Technology Data Exchange (ETDEWEB)
A program is currently in progress at Argonne National Laboratory to evaluate and develop evaporator technology for concentrating radioactive waste streams. By concentrating radioactive waste streams, disposal costs can be significantly reduced. To effectively reduce the volume of waste, the evaporator must achieve high decontamination factors so that the distillate is sufficiently free of radioactive material. One technology that shows a great deal of potential for this application is being developed by LICON, Inc. In this program, Argonne plans to apply LICON`s evaporator designs to the processing of radioactive solutions. Concepts that need to be incorporated into the design of the evaporator include, criticality safety, remote operation and maintenance, and materials of construction. To design an effective process for concentrating waste streams, both solubility and vapor-liquid equilibrium data are needed. The key ...
1993-10-01
Energy Technology Data Exchange (ETDEWEB)
This report describes the 5 tasks to be covered under this project and compiles budget information. Task 1 is to establish a Plutonium Information Resource, which has been established in Amarillo, Texas. Task 2, Advisory Functions, coordinates studies and activities relating to the disposition of excess weapons-grade plutonium. Task 3, Environmental, Public Health, and Safety, supports soil remediation activities. Task 4, Education and Outreach, is supporting four programs: K--12 education improvement in science and math courses; Academic intervention to identify and encourage high ability high school and middle school students with potential to become scientists and engineers; Graduate education evaluation; and Public outreach programs. Task 5, Plutonium and other Materials Studies, is currently funding two projects for the disposition of high explosives: a feasibility study of burning a mixture of high explosives and ...
1995-06-29
Advanced evaporator technology progress report FY 1992
Energy Technology Data Exchange (ETDEWEB)
This report summarizes the work that was completed in FY 1992 on the program {open_quotes}Technology Development for Concentrating Process Streams.{close_quotes} The purpose of this program is to evaluate and develop evaporator technology for concentrating radioactive waste and product streams such as those generated by the TRUEX process. Concentrating these streams and minimizing the volume of waste generated can significantly reduce disposal costs; however, equipment to concentrate the streams and recycle the decontaminated condensates must be installed. LICON, Inc., is developing an evaporator that shows a great deal of potential for this application. In this report, concepts that need to be incorporated into the design of an evaporator operated in a radioactive environment are discussed. These concepts include criticality safety, remote operation and maintenance, and materials of construction. Both solubility and ...
1995-01-01
Facing the challenges of the nuclear renaissance
Energy Technology Data Exchange (ETDEWEB)
The Nuclear Renaissance is stumbling at the very same time it should speed up in order to help control the climate change and meet a fast growing energy need in a large part of the world. Rising costs of projects, uncertainties about their completion, rocketing safety requirements, and financial constraints are key factors which slow down the Nuclear Renaissance. Furthermore, the legal infrastructure required from any country to enter a commercial nuclear programme (safety authorities, fuel cycle, and waste disposal) is a major hurdle s which impedes consideration for small to mid size reactors, well suited for many countries. The paper prepared and presented by Alain Bugat (Chairman of NucAdvisor and former Head of the French Atomic Energy Commission), Dominique Vignon (CEO of NucAdvisor and former President and CEO of AREVA NP) and Michel Lecomte (Co-founder NucAdvisor) reviews the present status of the Nuclear ...
2010-07-01
Geothermal materials program: strategy. Final report
Energy Technology Data Exchange (ETDEWEB)
The following topics are discussed: program goal and objectives, program organization, and program status. Current program projects are described. (MHR)
1980-10-01
Proceedings of the second annual oil shale contractors meeting
Energy Technology Data Exchange (ETDEWEB)
This proceedings includes the papers presented at the US Department of Energy's Second Annual Oil Shale Contractors Meeting. The meeting was sponsored and hosted by the US Department of Energy's Morgantown Energy Technology Center and was held August 12-13, 1986, at the Ramada Inn in Morgantown, West Virginia. This year's meeting was attended by some 100 individuals from private industry, academia, research institutes, national laboratories, state and Federal Government agencies, and other domestic and foreign businesses. The purposes of this meeting were (1) to review and evaluate the current research in the Oil Shale Program, (2) to establish a forum for interchange of information and ideas related to oil shale, and (3) to assist the Department in planning future work. Utilization of the United States oil shale resources will not occur without the investment, involvement, and cooperation of both Government and ...
1986-08-01
Recent environment, energy and resources cases and issues in Alberta
Energy Technology Data Exchange (ETDEWEB)
Significant environmental issues and regulatory proceedings in Alberta were discussed. The Mackenzie Valley Pipeline Project was reviewed in relation to the Deh Cho First Nation's advanced actions in the federal court to enjoin the review panel from proceeding with the review process. The Deh Cho First Nation is seeking a declaration that the plan violates their rights under the Canadian Charter of Rights and Freedoms and the Constitution Act. Various regulatory and government agencies have now developed a plan to coordinate their different regulatory processes and approvals in the Cooperation Plan for the Environmental Impact Assessment and Regulatory Review of the Northern Gas Pipeline project. The Deh Cho allege that they were not afforded the opportunity to participate in the development and implementation of the plan. A review panel plans to proceed once the ...
2005-07-01
International Nuclear Information System (INIS)
The COSA II (computer codes for salt) benchmark problem has been pursued with the ADINA (Automatic Dynamic Incremental Nonlinear Analysis) program code. With the use of this, the code should be validated by means of experimental data and the ability to reproduce real-life calculation results of the KfK (Kernforschungszentrum Karlsruhe/Nuclear Research Center in Karlsruhe) should be proven. A successful validation of the code then forms the foundation stone for the ability to use different calculation problems in the final (ultimate) storage. This also accompanies the consequent reaction of replacing the STEALTH (Solids and Thermal Hydraulics Code for EPRI Adapted from LAGRANGE TOODY and HEMP) program which has a number of program-specific weaknesses compared to the ADINA computer code. In order to reproduce the approximate values from the KfK, the same values have been used. Differences were evident in the discretion and ...
One of the biggest fears and challenges a parent of a child with special needs faces is navigating the post-22 landscape. When a child hits the age of 22, the Department of Elementary and Secondary Education (DESE) is no longer required to provide daily services and support. Whatever the abilities, or disabilities, of a child, every parent has the same concerns about how their child will productively fill their days and live as independently as possible without the safety net of the DESE. One of the transition paths most frequented is entering the workforce. Public and private schools alike work to teach their students the basic skills they need to work. In fact, the national Individuals with Disabilities Education Act (IDEA) states that students must have a transition plan in formulation by the age of 16. This article describes the vocational program developed by the League School of Greater Boston which specifically addresses the challenges ...
2010-10-01
Safety culture development at Daya Bay NPP
International Nuclear Information System (INIS)
From view on Organization Behavior theory, the concept, development and affecting factors of safety culture are introduced. The focuses are on the establishment, development and management practice for safety culture at Daya Bay NPP. A strong safety culture, also demonstrated, has contributed greatly to improving performance at Daya Bay
2001-12-01
NHTSA Contact Information | National Highway Traffic Safety Administra...
Skip to Main Content Skip to Main Navigation National Highway Traffic Safety Administration Accessible menu--Sitemap Driving Safety Aggressive Driving Bicycles Child Safety...
2011-09-24
Risk-based inspection in ASME Section XI
International Nuclear Information System (INIS)
By 1970 the first edition of the ASME Code Section XI, Inservice Inspection of Nuclear Reactor Coolant Systems was published. From its inception, the Section XI inservice inspection scope was based on a fundamental risk-based selection process. In other words the inservice inspection scope included components where the consequences of a pressure boundary failure were high. Once the consequence significant system boundaries were established, inspections would then be performed at locations believed to be most susceptible service induced failure. Current Section XI requirements require that inspection locations be selected on the basis of peak stress and fatigue usage values contained in the Design Reports. These original stress calculations were designed to qualify a design and assure that the plant would provide reliable service throughout its design life. For the most part, the fatigue usage values in these reports do not provide an accurate measure of service life. As service history ...
1996-07-21
Energy Technology Data Exchange (ETDEWEB)
As part of the work scope set in the French law on high level long lived waste R&D passed in 1991, CEA is conducting a research program to establish the scientific basis and assess the feasibility of long term storage as an option for the safe management of nuclear waste for periods as long as centuries. This goal is a significant departure from the current industrial practice where storage facilities are usually built to last only a few decades. From a technical viewpoint such an extension in time seems feasible provided care and maintenance is exercised. Considering such long periods of time, the risk for Society of loosing oversight and control of such a facility is real, which triggers the question of whether and how long term storage safety can be actually achieved. Therefore CEA commissioned a study (1) in which MUTADIS Consultants (2) and CEPN (3) were both involved. The case study looks into several past and actual human ...
2003-02-24
Code requirements document: MODFLOW 2.1: A program for predicting moderator flow patterns
Energy Technology Data Exchange (ETDEWEB)
Sudden changes in the temperature of flowing liquids can result in transient buoyancy forces which strongly impact the flow hydrodynamics via flow stratification. These effects have been studied for the case of potential flow of stratified liquids to line sinks, but not for moderator flow in SRS reactors. Standard codes, such as TRAC and COMMIX, do not have the capability to capture the stratification effect, due to strong numerical diffusion which smears away the hot/cold fluid interface. A related problem with standard codes is the inability to track plumes injected into the liquid flow, again due to numerical diffusion. The combined effects of buoyant stratification and plume dispersion have been identified as being important in operation of the Supplementary Safety System which injects neutron-poison ink into SRS reactors to provide safe shutdown in the event of safety rod failure. The MODFLOW code discussed here provides transient ...
1992-03-01
Code requirements document: MODFLOW 2. 1: A program for predicting moderator flow patterns
Energy Technology Data Exchange (ETDEWEB)
Sudden changes in the temperature of flowing liquids can result in transient buoyancy forces which strongly impact the flow hydrodynamics via flow stratification. These effects have been studied for the case of potential flow of stratified liquids to line sinks, but not for moderator flow in SRS reactors. Standard codes, such as TRAC and COMMIX, do not have the capability to capture the stratification effect, due to strong numerical diffusion which smears away the hot/cold fluid interface. A related problem with standard codes is the inability to track plumes injected into the liquid flow, again due to numerical diffusion. The combined effects of buoyant stratification and plume dispersion have been identified as being important in operation of the Supplementary Safety System which injects neutron-poison ink into SRS reactors to provide safe shutdown in the event of safety rod failure. The MODFLOW code discussed here provides transient ...
1992-03-01
State-of-the-art review of computational fluid dynamics modeling for fluid-solids systems
Energy Technology Data Exchange (ETDEWEB)
As the result of 15 years of research (50 staff years of effort) Argonne National Laboratory (ANL), through its involvement in fluidized-bed combustion, magnetohydrodynamics, and a variety of environmental programs, has produced extensive computational fluid dynamics (CFD) software and models to predict the multiphase hydrodynamic and reactive behavior of fluid-solids motions and interactions in complex fluidized-bed reactors (FBRS) and slurry systems. This has resulted in the FLUFIX, IRF, and SLUFIX computer programs. These programs are based on fluid-solids hydrodynamic models and can predict information important to the designer of atmospheric or pressurized bubbling and circulating FBR, fluid catalytic cracking (FCC) and slurry units to guarantee optimum efficiency with minimum release of pollutants into the environment. This latter issue will become of paramount importance with the enactment of the Clean Air Act ...
1994-05-12
Hydrogen systems analysis, education, and outreach. Annual report, August 1996--September 1997
Energy Technology Data Exchange (ETDEWEB)
The set of activities performed by SENTECH, Inc. addressed the specific recommendations provided to the Department of Energy (DOE) by its advisors, including the Hydrogen Technical Advisory Panel and the review panel members of the DOE Annual Hydrogen Program Review. SENTECH`s efforts were conducted under five tasks: Task 1: Technology and Process Analysis; Task 2: Hydrogen Information Development and Transfer; Task 3: Educational Products; Task 4: Systems Analysis; and Task 5: Life Cycle Costs. SENTECH activities were executed in two broad areas--analysis and technology transfer. The analytical tasks undertaken in FY97 were focused on two types of analysis--systems analysis and technical/economic assessments. These analytical activities benefit DOE by providing data that allow it to define the strategic goals of the hydrogen R and D program. By collecting analysis of the energy efficiency, ...
1997-11-01
International Nuclear Information System (INIS)
Naturally occurring radionuclides are present in most material. The most common naturally occurring radionuclides in material are those of the uranium and thorium series and potassium-40. This material is commonly referred to as Naturally Occurring Radioactive Material (NORM). In some material the levels of naturally occurring radionuclides are significantly higher, to the extent that regulatory control may be required for radiation protection purposes. Regulation of NORM presents a range of new challenges for both regulators and operators. Unlike more traditional industries dealing with radionuclides, NORM industries have generally not had any radiological oversight and, for example, are not equipped for radiological monitoring. Some consumer goods containing NORM, which have not traditionally been considered as a radiological problem (such as some fertilizers), may require regulation and this may have social and economic consequences. The transport and disposal of NORM are also a ...
2002-09-23
International Nuclear Information System (INIS)
CORAL-I was an experimental, zero-power, fast-spectrum, high-enriched metal uranium reactor that operated from 1968 until 1988 at the former Junta de Energia Nuclear (JEN), CIEMAT at present. The critical measurements performed at the startup of the reactor are being evaluated as part of the International Critical Safety Benchmark Evaluation Program (ICSBEP) and proposed to be included in its 2001 edition. Additionally, the measurement of the mass reactivity coefficient is compared with MCNP4B calculations. This measurement allows one to perform the approach to critical without the need of a previous control rod calibration, thus enhancing the safety of such an approach. This technique can also be applied to other reactor types. CORAL-I (Ref. 1) is a 90% enriched metal uranium reactor domestically designed and manufactured in the experimental facilities of JEN, now CIEMAT, in Madrid, Spain. The enriched uranium was supplied ...
2001-06-17
International Nuclear Information System (INIS)
The Joint Convention on the Safety of Spent Fuel management and on the Safety of Radioactive Waste Management is the first legal instrument to directly address the safety of spent fuel and radioactive waste management on a global scale. The Joint Convention entered into force in 2001. This paper describes its process and its main achievements to date. The perspectives to establish of a Global Waste Safety Regime based on the Joint Convention are also discussed. (authors)
White Rose development plan amendment production volume increase
Energy Technology Data Exchange (ETDEWEB)
In January 2001, Husky Oil Operations Limited (Husky), in joint-venture with Petro-Canada, submitted a Benefits Plan for the White Rose Development to the Canada- Newfoundland and Labrador Offshore Petroleum Board (C-NLOPB). This revised document provided the case for requesting an increase in the facility maximum daily production rate and the average annual production rate for the White Rose field from 100,000 barrels per day (bpd) as stated in the approved White Rose Development Plan to 140,000 bpd. In order to determine the potential for increasing oil production through the Floating Production, Storage and Offloading (FPSO) vessel, two things were considered, namely the proper reservoir management of the White Rose field to ensure optimum resource recovery, and the capacity of the FPSO topsides processing system and supporting utilities to accommodate increased production. This document presented a detailed review of all the implications of increased production ...
2006-09-15
Screening Criteria for Loss of Room Cooling Failure
Energy Technology Data Exchange (ETDEWEB)
In this report, we estimated the temperature of the pump rooms and reviewed the operability of the components under the loss of the HVAC (Heating, Ventilation, and Air Condition) system. The issues relevant to the HVAC system in the PSA (Probabilistic Safety Assessment) FT (Fault Tree) model are as follows: (1) Does the loss of the HVAC system bring about a function failure of other components? (2) Can the operator take action to reduce the temperature of the room in case of a HVAC function failure? At present, we do not know whether a component will lose its function or not under the loss of the HVAC. ASME Standard describes that a recovery action can be credited if the related recovery action is included in the procedure or there are similar recovery experiences in the plant. However, there is no description about the recovery action of the HVAC in the EOP (Emergency Operation Procedure) of the UCN3, 4 under the situation of a loss of the ...
2007-01-15
A Preliminary Study for the Analysis of PSA Success Criteria for Kori Units 3 and 4
Energy Technology Data Exchange (ETDEWEB)
This paper identifies the event sequences that require thermal-hydraulic analyses for the success criteria of probabilistic safety analysis (PSA). The selection of the sequences is performed based on the review of the NEI Peer Review Process Guidance and ASME PRA Standard. Success criteria are the important element of PSA quality. Success criteria decide the success or failure of the key function in the PSA event tree. It is defined as a minimum set of components/trains of system required to mitigate an accident. Thermal-hydraulic codes are generally used to derive time-related criteria in the PSA, such as operator action time used in human reliability analysis (HRA), event timing, and time to recover the component or the power. This paper suggests the use of the MARS code for the T-H analysis to obtain the success criteria and sequence timing, and operator action time. In the Kori Units 3 and 4 PSA report, the T-H analyses ...
2009-10-15
A Preliminary Study for the Analysis of PSA Success Criteria for Kori Units 3 and 4
International Nuclear Information System (INIS)
This paper identifies the event sequences that require thermal-hydraulic analyses for the success criteria of probabilistic safety analysis (PSA). The selection of the sequences is performed based on the review of the NEI Peer Review Process Guidance and ASME PRA Standard. Success criteria are the important element of PSA quality. Success criteria decide the success or failure of the key function in the PSA event tree. It is defined as a minimum set of components/trains of system required to mitigate an accident. Thermal-hydraulic codes are generally used to derive time-related criteria in the PSA, such as operator action time used in human reliability analysis (HRA), event timing, and time to recover the component or the power. This paper suggests the use of the MARS code for the T-H analysis to obtain the success criteria and sequence timing, and operator action time. In the Kori Units 3 and 4 PSA report, the T-H analyses ...
2009-10-01
Energy Technology Data Exchange (ETDEWEB)
With the aid of a DOE grant (No. DE-FC26-01NT41050), Stolar Research Corporation (Stolar) developed the Horizon Sensor (HS) to distinguish between the different layers of a coal seam. Mounted on mining machine cutter drums, HS units can detect or sense the horizon between the coal seam and the roof and floor rock, providing the opportunity to accurately mine the section of the seam most desired. HS also enables accurate cutting of minimum height if that is the operator's objective. Often when cutting is done out-of-seam, the head-positioning function facilitates a fixed mining height to minimize dilution. With this technology, miners can still be at a remote location, yet cut only the clean coal, resulting in a much more efficient overall process. The objectives of this project were to demonstrate the feasibility of horizon sensing on mining machines and demonstrate that Horizon Sensing can allow coal to be cut cleaner and more efficiently. Stolar's primary goal was ...
2003-03-18
Different aspects of safety in Nuclear Fuel Plant at Pitesti, Romania
International Nuclear Information System (INIS)
Nuclear Fuel Plant (FCN) is a facility that produces fuel bundles of CANDU-6 type for the CANDU nuclear power plant. Only natural and depleted uranium in bulk and itemized form are present as nuclear materials in this facility. Uranium and wastes from the plant are handled, processed, treated and stored throughout the entire facility. The nuclear materials with natural and depleted uranium are entirely under nuclear safeguards. The amount of uranium present in the plant in different forms and activities together with zircaloy, beryllium and other hazardous substances, wastes, explosive materials at high temperatures, etc. lead to special measures undertaken by Nuclear Safety Department (DNS) to ensure nuclear safety. Different aspects of safety are continuously monitored in the plant: operational safety, industrial safety, radiological safety, labour ...
2009-10-12
Evolutionary developments advancing the floating production, storage, and offloading concept
Energy Technology Data Exchange (ETDEWEB)
Tanker-based floating production, storage, and offloading (FPSO) systems have been in operation since Aug. 1977, when a single-well FPSO facility was put into production by Shell Espana in the Mediterranean. The overall operational experience with this system at this field is reviewed, with special attention to the wireline workover facilities, which have proved very satisfactory. A subsequent evolutionary step, a FPSO system accommodating multiple wells, necessitated development of a multibore fluid swivel. A design program for this swivel was initiated in 1978; a prototype was built and full-scale testing finalized in 1980. A summary of the test results is presented. Simultaneously with the multibore swivel development, detailed engineering for an eight-well FPSO unit was begun. This system includes gas-lift and water injection capabilities. Provisions for through-flowline (TFL) well workover can be incorporated. The detailed design is ...
1983-04-01
GAO's review of the H-Coal and Exxon projects showed inadequacies in DOE's contracting practices and a failure by DOE to properly plan, manage, and monitor, especially the H-Coal project. The initial Government-industry H-Coal agreements regarding the level of investment by private sponsors and the ceilings imposed on sharing in cost growth were imbalanced. Larger investments by private sponsors and sharing of cost growth provides an incentive to private sponsors to control costs and helps to assure that each party is fully committed to the success of the project. DOE started the H-Coal project prematurely before sufficiently detailed designs were available and without adequate project planning for functions such as construction scheduling, materials handling, inventory systems, and quality control. DOE staffing was inadequate at both projects to effectively monitor progress and contribute to timely decisions. Its contracts for the H-Coal plants ...
1981-02-04
Blast designs to improve dragline stripping rates. Final report: Phase I
International Nuclear Information System (INIS)
This report is in accordance with Phase I of the United States Department of Energy and Bureau of Mines Contract No. USDOE DE-AC01-77QQ90147. A thorough literature search was conducted and the current mining practice at nine coal stripping operations reviewed in detail. A review of the state of the art of blast design using current theory and practice is presented. Based upon this information, a series of recommendations are presented and a detailed test program is outlined for three operations. The recommendations to increase dragline productivity by improved blast design are directed at filling the bucket more quickly, with greater consistency and with a better fill factor: (a) overburden fragmentation, (b) muckpile displacements, and (c) blasting reliability. Recommended blast design concepts and operating procedures to provide the desired blast performance include: (1) Increase energy input per BCY by 40 to 100 percent ...
In the past few decades the need for improved nuclear reactor safety analyses has led to a rapid development of advanced methods for multidimensional thermal-hydraulic analyses. These methods have become progressively more complex in order to account for the many physical phenomena anticipated during steady state and transient Light Water Reactor (LWR) conditions. The advanced thermal-hydraulic subchannel code COBRA-TF (Thurgood, M. J. et al., 1983) is used worldwide for best-estimate evaluations of the nuclear reactor safety margins. In the framework of a joint research project between the Pennsylvania State University (PSU) and AREVA NP GmbH, the theoretical models and numerics of COBRA-TF have been improved. Under the name F-COBRA-TF, the code has been subjected to an extensive verification and validation program and has been applied to variety of LWR steady state and transient simulations. To enable F-COBRA-TF for ...
2007-01-01
Waste reduction at the Savannah River Site
Energy Technology Data Exchange (ETDEWEB)
The Savannah River Site (SRS) is a key installation for the production and research of nuclear materials for national defense and peace time applications and has been operating a full nuclear fuel cycle since the early 1950s. Wastes generated include high level radioactive, transuranic, low level radioactive, hazardous, mixed, sanitary, and aqueous wastes. Much progress has been made during the last several years to reduce these wastes including management systems, characterization, and technology programs. The reduction of wastes generated and the proper handling of the wastes have always been a part of the Site's operation. This paper summarizes the current status and future plans with respect to waste reduction to waste reduction and reviews some specific examples of successful activities.
1990-01-01
Waste reduction at the Savannah River Site
Energy Technology Data Exchange (ETDEWEB)
The Savannah River Site (SRS) is a key installation for the production and research of nuclear materials for national defense and peace time applications and has been operating a full nuclear fuel cycle since the early 1950s. Wastes generated include high level radioactive, transuranic, low level radioactive, hazardous, mixed, sanitary, and aqueous wastes. Much progress has been made during the last several years to reduce these wastes including management systems, characterization, and technology programs. The reduction of wastes generated and the proper handling of the wastes have always been a part of the Site`s operation. This paper summarizes the current status and future plans with respect to waste reduction to waste reduction and reviews some specific examples of successful activities.
1990-12-31
Energy Technology Data Exchange (ETDEWEB)
A historical review on insulated cables for power transmission, is presented, beginning with impregnated paper insulation, oil filled cables and natural rubber cables. High density and chemically reticulated polyethylene were then used for high voltage and very high voltage cables; the advantages of polyethylene compared to impregnated paper cables are discussed, which led to research programs at EDF on various themes concerning the optimization of polyethylene cables: dielectric properties and reliability, thermomechanical behaviour, thermal ageing of materials, testing methods (acceptance dielectric test and long duration temperature test); utilization of low- and high-density and chemically reticulated polyethylene for 225 kV cables is discussed
1997-06-01
Transuranic waste form characterization and data base. Executive summary
Energy Technology Data Exchange (ETDEWEB)
The Transuranic Waste Form Characterization and Data Base (Volume 1) provides a wide range of information from which a comprehensive data base can be established and from which standards and criteria can be developed for the present NRC waste management program. Supplementary information on each of the areas discussed in Volume 1 is presented in Appendices A through K (Volumes 2 and 3). The structure of the study (Volume 1) is outlined and appendices of Volumes 2 and 3 correlate with each main section of the report. The Executive Summary reviews the sources, quantities, characteristics and treatment of transuranic wastes in the United States. Due to the variety of potential treatment processes for transuranic wastes, the end products for long-term storage may have corresponding variations in quantities and characteristics.
1980-09-30
Energy Technology Data Exchange (ETDEWEB)
Coal can be converted to liquid fuels via three generically defined technologies: pyrolysis, direct hydroliquefaction, and indirect liquefaction. This paper presents a general overview of the indirect liquefaction technology and a discussion of processes tht are commercially available as well as those in the development stage. Finally, the objective of the DOE research and development program in conversion of synthesis gas derived from coal to transportation fuels is summarized. The current outlook for indirect liquefaction is encouraging. New facilities are being built in South Africe and New Zealand, and commercial plants could be designed and built for operation in the United States using proven technology. At the same time, developments in gasification as well as liquefaction catalysts and reactor technology promise significant improvements in indirect liquefaction processes in the years to come.
1982-01-01
Seismic evaluation and upgrading of critical tower pile foundations in liquefiable soils
Energy Technology Data Exchange (ETDEWEB)
An overview of BC Hydro`s review of its overhead transmission system to withstand earthquakes and its program of seismic upgrading, including the upgrading of tower pile foundations in liquefiable soils, was presented. BC Hydro`s system, geologic environment, seismic design criteria, investigations and analysis, treatment and alternatives and a case history of a seismic upgrade of a tall river crossing tower at the Pitt River in the Lower Mainland of B.C. were summarized. It was concluded that the inherent strength of towers, conductors, fittings and insulators was sufficient to withstand earthquakes. The towers most susceptible to slope and soil failure due to seismic activity were tall river crossing towers. It was suggested that soils investigations, seismicity, ground response, liquefaction and stability analyses be carried out at each site. The results of these tests would help to establish system seismic design criteria at each location. ...
1995-12-31
British Library Electronic Table of Contents (United Kingdom)
This study emphasizes the need for a systematic and in-depth connection between the progress in quantum theory of energetic ion collisions and applications to hadron therapy. Scattering theory for fast ion beams has reached its stage of development where accurate and robustly applicable methodologies can advantageously be exported to applied fields such as space research, fusion energy program, medicine, etc. In particular, distorted wave collision theories at high energies readily provide total, partial and fully differential cross sections for inelastic collisions of ionic projectiles with any target system. By numerous and thorough testings, such theoretical cross sections were found to exhibit excellent agreement with experimental data on atomic targets. Adequate extensions of these me...
2010-01-01
Recommended changes in meteorological measurement and prediction methods for coastal sites
Energy Technology Data Exchange (ETDEWEB)
A study was performed to examine currently recommended meteorological measurement programs and atmospheric transport and diffusion prediction models for nuclear power plants to determine their adequacy for plants located in coastal zones where meteorological conditions are normally more complex than at inland sites and to make recommendations for changes to improve current procedures. Recommendations were based on an extensive literature review and on studies of coastal meteorology and diffusion. The study was focused on the following areas: coastal internal boundary layers; tower location; instrument heights; atmospheric stability classification; plume meander; and diffusion calculations. Each of the areas is discussed with appropriate recommendations which were made with respect to either the scientific or the regulation aspects of current procedures or both. Other potential problem areas are also pointed out.
1980-01-01
Energy Technology Data Exchange (ETDEWEB)
The Savannah River Site disposes of low-level radioactive waste within on-site engineered disposal facilities. The Savannah River Site must demonstrate that these disposals meet the requirements of DOE Order 435 . 1 through a process known as performance assessment (PA). The objective of this document is to provide the radionuclide -specific data needed for the PA calculations . This work is part of an on-going program to periodically review and update existing PA work as new data becomes available. Revision of the E -Area Low-Level Waste Facility PA is currently underway. The number of radionuclides selected to undergo detailed analysis in the PA is determined by a screening process. The basis of this process is described. Radionuclide-specific data for half-lives, decay modes, daughters, dose conversion factors and groundwater concentration limits are presented with source references and methodologies.
2007-03-20
Meteorological measurement methods and diffusion models for use at coastal nuclear reactor sites
Energy Technology Data Exchange (ETDEWEB)
A study, based on a literature review was made to examine currently recommended meteorological measurement programs and diffusion prediction methods for nuclear power plants to determine their adequacy for plants located in coastal zones. Although procedures for handling the near-worst case (stable, light-wind situation) were judged adequately conservative, deficiencies in guidelines and procedures were found with respect to the following: failure to consider the role of coastal internal boundary layers; specifications for tower locations and instrument heights; methods of classifying atmospheric stability; methods of allowing credit for plume meander, and models specified for diffusion calculations. Recommendations were made for changes in the guidelines applicable to these topics. Areas in which additional research is needed were identified.
1980-11-01
Measurement of Lake Roosevelt biota in relation to reservoir operations. Appendices 1991
International Nuclear Information System (INIS)
This report consists of appendices A-F containing the biological data which were collected from Lake Roosevelt, Washington. The data are to be used in the design of a computer model that would predict biological responses of reservoir operations as part of the System Operation Review program. Major components of the model included: Quantification of impacts to phytoplankton, zooplanktons, benthic invertebrates, and fish caused by reservoir drawdowns and low water retention times; quantification of number, distribution, and use of fish food organisms in the reservoir by season; determination of seasonal growth of fish species as related to reservoir operations, prey abundance and utilization; and quantification of entrainment levels of zooplankton and fish as related to reservoir operations and water retention times.
1995-11-05
Gas Appliance Technology Center: Annual report, January-December 1986
Energy Technology Data Exchange (ETDEWEB)
The report reviews the activity during the fourth year of Gas Research Institute's Gas Appliance Technology Center program. Work on gas appliances involved a conceptual table-top multi-function oven, development of an indirect-fired conveyor oven, and performance comparisons of smooth cooktops. Performance-evaluation methods for commercial ovens were evaluated. Design improvements were made to a direct-fired conveyor oven and a pulse-combustion deep-fat fryer. Performance of common vents were studied, and a device was designed to allow incorporation of appliances with positive vent pressures into such systems. Standards-related work included draft-hood capacities, flexible corrugated-connector corrosion, and sediment trap efficiencies. Heating-related work comprised conceptual design of a vented baseboard heater and a centralized heat-transfer fluid system.
1987-08-01
Evolutionary developments advancing the floating production, storage, and offloading concept
Energy Technology Data Exchange (ETDEWEB)
Tanker-based floating production, storage and offloading (FPSO) systems have been in operation since Aug. 1977, when a single-well FPSO was put into production by Shell Espana in the Mediterranean. The overall operational experience with this system at this field is reviewed. Special attention is directed to the wireline workover facilities which have proven to be satisfactory. A subsequent evolutionary step, a FPSO accommodating multiple wells, necessitated development of a multiple-bore product swivel. A design program for this swivel was initiated in 1978, a prototype was built and fullscale testing finalized in 1980. A summary of the test results is presented. Simultaneous with the multiple-bore swivel development, detailed engineering for an 8-well FPSO was begun. This sytem includes gas lift a
1982-01-01
Emissions trading and green power : profitability for buyers and sellers
Energy Technology Data Exchange (ETDEWEB)
Proposed features of the competitive electricity market in Ontario were reviewed. The speaker predicted that demand for renewable energy in Ontario`s competitive electricity market will be affected by green power, emissions trading, labelling, and renewables portfolio standard. Under current regulations retailers can charge customers a premium for purchasing electricity generated by `green` sources. The existing limits on emissions of sulphur dioxide, nitrogen oxides and carbon dioxides will remain in place, but an emissions cap and trading program for all Ontario-based generation is an option to consider. Ontario`s Market Design Committee (MDC) has recommended the implementation of emissions trading for electricity-related air pollutants for all generators located in Ontario. The complex mechanics of emission trading are explained. The MDC recommendation of the use of standard labels to disclose the mix of energy sources used by sellers of ...
1998-12-31
Emergency medicine in Oman: current status and future challenges
British Library Electronic Table of Contents (United Kingdom)
The Sultanate of Oman has a relatively young national health care system that could demonstrate its high performance at an international level. Emergency medicine as a specialty has developed rapidly in the country over the last decade. This has involved the parallel development of local emergency residency training, prehospital emergency care, and emergency nursing programs. This article reviews the progress of emergency care practice in this country from a general primary care system toward becoming an established specialty in hospital, prehospital, and private emergency care settings. It also describes aspects of undergraduate, postgraduate, and continuous emergency medicine education in the country. Further, a glimpse into academic emergency medicine and emergency nursing is provided. ...
2009-01-01
International Nuclear Information System (INIS)
Manitoba Hydro's Ice Storm Management Program to reduce ice damage to overhead power lines in the voltage range of 8 kV to 115 kV is described. Overhead power lines are de-iced either by AC ice melting, which involves placing a three-phase short at a calculated point, or ice rolling, which is a process of mechanically stripping ice from conductors. Direct current heating and underground distribution systems are also accepted prevention measures. Advantages and disadvantages of each of these methods of de-icing are reviewed. Material for this paper has been extracted from a workshop manual prepared for the 1993 and 1998 Ice Storm Management workshops organized by Manitoba Hydro through the Canadian Electrical Association. 1 ref.
1999-03-29
Continuous emission monitoring and quality assurance requirements for new power plants
International Nuclear Information System (INIS)
Electric utility plants, for which construction commenced after September 18, 1978, must install and operate continuous emission monitoring (CEM) systems to demonstrate compliance with SO_2 and NO_x emission standards. Furthermore, effective December 4, 1987, each plant must develop and implement a CEM quality assurance (QA) program. This paper reviews the CEM and QA requirements set forth by new source performance standards (NSPS) promulgated by the Environmental Protection Agency. The paper summarizes operating characteristics of the 32 power plants currently subject to NSPS and describes the types of CEM systems used by these plants. Also, to the extent available, the paper presents the results of initial (i.e., first quarter 1988) QA activities (e.g., audits and calibration drift assessments) conducted by these plants.
1988-09-25
Special education researchers have made noteworthy progress toward conceptualizing literacy research questions, designing quality studies, and disseminating the results of their research. These advancements have been made through the establishment and refinement of quality research indicators. Unfortunately, this progress has mostly eluded the arena of juvenile justice special education research. The purpose of this article is to review juvenile justice literacy studies and provide juvenile justice personnel and researchers with methodological and practical considerations for improving the quality of juvenile justice literacy research. The focus is on advancing group designs. Practical concerns are based on the first-year experiences of researchers who implemented an Institute of Education Sciences Goal 3 study with the aim of determining the efficacy of literacy instructional programs in a juvenile justice setting.
2010-11-01
We present in this article a detailed quantitative discussion of the measurement of the leptonic mixing angle theta_13 through currently scheduled reactor neutrino oscillation experiments. We thus focus on Double Chooz (Phase I & II), Daya Bay (Phase I & II) and RENO experiments. We perform a unified analysis, including systematics, backgrounds and accurate experimental setup in each case. Each identified systematic error and background impact has been assessed on experimental setups following published data when available and extrapolating from Double Chooz acquired knowledge otherwise. After reviewing the experiments, we present a new analysis of their sensitivities to sin^2(2 theta_13) and study the impact of the different systematics based on the pulls approach. Through this generic statistical analysis we discuss the advantages and drawbacks of each experimental setup.
2007-01-01
Energy Technology Data Exchange (ETDEWEB)
The International Atomic Energy Agency (IAEA) plans to use the Common Criteria, as the tool for developing graded and measurable evaluation criteria for information technology (IT) in safeguards systems in facilities subject to IAEA inspection. In their draft paper [ITSECSES] the IAEA defines a three-tiered Vulnerability Assessment Level (VAL) scheme. Each increased VAL level (1-3) defines additional and more stringent security and security-related requirements for the system developer, the system evaluator (assessor or authenticator), and for the IAEA. When all parties meet all requirements for a particular VAL level, IAEA has a measurable degree of confidence in the secure and proper operation of an IT system.
2001-12-06
Nuclear new-build - Status and Outlook from a German utility perspective
International Nuclear Information System (INIS)
Full text: As one of the Top 5 utilities in Europe, Rheinisch-Westfaelisches Elektrizitaetswerk AG, FWB: RW, RWE, operates a diversified generating capacity of about 45 GW; RWE Power alone generates over 30 GW. Besides a share of approximately 20% nuclear power, a large proportion of the generating base is in lignite and hard coal. RWE has an ambitious, Euro10 bn newbuild program of about 10 GW modern fossil fired plants and further expansion plans across Europe. By 2012, RWE intends to invest between Euro 15 and 20 bn outside Germany.The European Union has a challenging policy to increase the share of renewables, improve energy efficiency, and reduce greenhouse gases by 2020. At the same time, ageing power plants need to be replaced. This requires an enormous investment program across Europe. Nuclear power therefore, as a proven technology with low lifecycle carbon emissions and reasonable lifecycle cost, is a crucial contributor to achieve ...
2009-10-12
A technical review is presented of experiment activities and state of knowledge on air-borne, radiation source terms resulting from explosive sabotage attacks on spent reactor fuel subassemblies in shielded casks. Current assumptions about the behavior of irradiated fuel are largely based on a limited number of experimental results involving unirradiated, depleted uranium dioxide ''surrogate'' fuel. The behavior of irradiated nuclear fuel subjected to explosive conditions could be different from the behavior of the surrogate fuel, depending on the assumptions made by the evaluator. Available data indicate that these potential differences could result in errors, and possible orders-of-magnitude overestimates of aerosol dispersion and potential health effects from sabotage attacks. Furthermore, it is suggested that the current assumptions used in arriving at existing regulations for the transportation and storage of spent fuel in ...
2002-04-01
Survey of agents and techniques applicable to the solidification of low-level radioactive wastes
Energy Technology Data Exchange (ETDEWEB)
A review of the various solidification agents and techniques that are currently available or potentially applicable for the solidification of low-level radioactive wastes is presented. An overview of the types and quantities of low-level wastes produced is presented. Descriptions of waste form matrix materials, the wastes types for which they have been or may be applied and available information concerning relevant waste form properties and characteristics follow. Also included are descriptions of the processing techniques themselves with an emphasis on those operating parameters which impact upon waste form properties. The solidification agents considered in this survey include: hydraulic cements, thermoplastic materials, thermosetting polymers, glasses, synthetic minerals and composite materials. This survey is part of a program supported by the United States Department of Energy's Low-Level Waste Management ...
1981-12-01
Study on quality assurance for high-level radioactive waste disposal project
International Nuclear Information System (INIS)
The U.S. Department of Energy (DOE) has developed comparatively detailed quality assurance requirements for the high-level radioactive waste disposal systems. Quality assurance is recognized as a key issue for confidence building and smooth implementation of the HLW program in Japan, and Japan is at an initial phase of repository development. Then the quality assurance requirements at site research and site selection, site characterization, and site suitability analysis used in the Yucca Mountain project were examined in detail and comprehensive descriptions were developed using flow charts. Additionally, the applicability to the Japan high-level radioactive waste disposal project was studied. The examination and study were performed for the following QA requirements: The requirements that have the relative importance at site research and site selection, site characterization, and site suitability analysis (such as planning and performing scientific investigations, ...
2005-03-01
Spray Forming Aluminum - Final Report (Phase II)
Energy Technology Data Exchange (ETDEWEB)
The U.S. Department of Energy - Office of Industrial Technology (DOE) has an objective to increase energy efficient and enhance competitiveness of American metals industries. To support this objective, ALCOA Inc. entered into a cooperative program to develop spray forming technology for aluminum. This Phase II of the DOE Spray Forming Program would translate bench scale spray forming technology into a cost effective world class process for commercialization. Developments under DOE Cooperative Agreement No. DE-FC07-94ID13238 occurred during two time periods due to budgetary constraints; April 1994 through September 1996 and October 1997 and December 1998. During these periods, ALCOA Inc developed a linear spray forming nozzle and specific support processes capable of scale-up for commercial production of aluminum sheet alloy products. Emphasis was given to alloys 3003 and 6111, both being commercially significant alloys used in the automotive ...
1999-07-08
Salt repository project closeout status report
Energy Technology Data Exchange (ETDEWEB)
This report provides an overview of the scope and status of the US Department of Energy (DOE`s) Salt Repository Project (SRP) at the time when the project was terminated by the Nuclear Waste Policy Amendments Act of 1987. The report reviews the 10-year program of siting a geologic repository for high-level nuclear waste in rock salt formations. Its purpose is to aid persons interested in the information developed during the course of this effort. Each area is briefly described and the major items of information are noted. This report, the three salt Environmental Assessments, and the Site Characterization Plan are the suggested starting points for any search of the literature and information developed by the program participants. Prior to termination, DOE was preparing to characterize three candidate sites for the first mined geologic repository for the permanent disposal of high-level nuclear waste. The sites were in ...
1988-06-01
Energy Technology Data Exchange (ETDEWEB)
SYVAC3 (Systems Variability Analysis Code, generation 3) is a computer program that implements a method called systems variability analysis to analyze the behaviour of a system in the presence of uncertainty. This method is based on simulating the system many times to determine the variation in behaviour it can exhibit. SYVAC3 specializes in systems representing the transport of contaminants, and has several features to simplify the modelling of such systems. It provides a general tool for estimating environmental impacts from the dispersal of contaminants. This report describes the use and structure of SYVAC3. It is intended for modellers, programmers, operators and reviewers who deal with simulation codes based on SYVAC3. From this manual they can learn how to link a model with SYVAC3, how to set up an input file, and how to extract results from output files. The manual lists the subroutines of SYVAC3 that are available for use by models, and ...
2000-07-01
Energy Technology Data Exchange (ETDEWEB)
The objective of this research was to determine the extent of damage that occurs when two pipes experience an impact event due to one whipping against the other. The research was conducted through experimental and analytical approaches. The former required the development of a specialized impact machine that could accelerate a whipping pipe with sufficient energy to cause failure of a target pipe that was heated and pressurized to Pressurized Water Reactor (PWR) conditions. Damage was measured in terms of crushing, bending, and failure. The results of the tests permitted the correlation between pipes of a certain size and the damage they could cause when impacting with a certain amount of known energy. These results were used to evaluate the pipe whip criteria in the Standard Review Plan 3.6.2-4. It was established that the criteria conditions did not fully represent the results obtained experimentally. An analysis procedure to model the pipe whip event was ...
1987-05-01
Leak-Before-Break: Further developments in regulatory policies and supporting research
Energy Technology Data Exchange (ETDEWEB)
The fourth in a series of international Leak-Before-Break (LBB) Seminars supported in part by the US Nuclear Regulatory Commission was held at the National Central Library in Taipei, Taiwan on May 11 and 12, 1989. The seminar updated the international polices and supporting research on LBB. Attendees included representatives from regulatory agencies, electric utilities, nuclear power plant fabricators, research organizations, and academic institutions. Regulatory policy was the subject of presentations by Mr. G. Arlotto (US NRC, USA) Dr. B. Jarman (AECB, Canada), Dr.P. Milella (ENEA-DISP, Italy), Dr. C. Faidy (EDF/Septen, France ), and Dr. K. Takumi (NUPEC, Japan). A paper by Mr. K. Wichman and Mr. A. Lee of the US NRC Office of Nuclear Reactor Regulation is included as background material to these proceedings; it discusses the history and status of LBB applications in US nuclear power plants. In addition, several papers on the supporting research programs ...
1990-02-01
Haiti: energy efficiency in the sugar and manufacturing industries
Energy Technology Data Exchange (ETDEWEB)
A review of energy use in Haiti, aimed at identifying possible projects to complement current A.I.D. support for institution building and energy planning within the Ministry of Mines and Energy Resources (MMRE), is presented. Key findings are that: (1) the sugar and manufacturing industries rely heavily on biomass fuels - wood, charcoal, and bagasse (sugar cane residue); and (2) demand for commercial energy and for electricity is growing rapidly despite supply constraints. The report calls for A.I.D. to: initiate a program to reduce biomass consumption (which is causing severe soil erosion and deforestation), especially in the small distilleries called guildives; collaborate with MMRE and the World Bank to develop a detailed workplan to promote energy efficiency in the guildives, focusing on technology development; help MMRE and the private sector to project Haiti's industrial energy and electricity needs through the year 2000; and ...
1985-03-28
Designed primarily for Missouri vocational agricultural instructors participating in the Farm Business Management Analysis Program, this instructor's guide, consisting of 10 lessons, deals with adjusting a farm business to increase profits. The following topics are covered in the individual lessons: law and the farm family, planning income tax management, closing the record book and planning cash flow, evaluating family living expenses, determining the most profitable livestock enterprise, determining the most profitable cropping system, planning the farm marketing program, adjusting capital investments to increase net profit, planning for efficient labor use, and controlling costs. Included in each section are suggestions for a review of previous materials covered, an objective, motivational techniques, key points to be addressed in the lesson, information to be introduced during the lesson, guidelines for holding a group ...
1982-06-01
On November 2, 1974, Skelly and Loy submitted recommendations to the United States Environmental Protection Agency concerning establishment of effluent limitations for the Coal Mining Point Source Category, culminating an exhaustive study of water treatment technology within the coal industry. Members of the National Coal Association alleged that the efficiency of acid mine drainage treatment plants and settling basins is seriously reduced during winter and spring seasons. The original study was conducted during the summer months, and review of historical seasonal effluent data indicated there may be validity to this claim. To validate and confirm the conclusions and proposed effluent limitations established in part from this historical data, a further sampling program was conducted during the winter and spring of 1975. This report presents the findings of that sampling program, and correlates previously collected sample ...
1975-06-24
Assessing the ACGME Competencies in Psychiatry Training programs.
In 2000, the Accreditation Council of Graduate Medical Education (ACGME) laid out a definition of competence that included six specific areas of focus: patient care (including clinical reasoning), medical knowledge, practice-based learning and improvement, interpersonal and communication skills, professionalism, and systems-based practice. The ACGME's intention was to mandate increasingly reliable and valid assessment measures to be used by all training programs over the next decade, with the goal of providing "more credible, accurate, reliable and useful educational outcome data." In this article, the authors will review definitions of competency according to the new ACGME standards and examine the assessment tools currently available, including global evaluations, 360-degree evaluations, checklists, standardized examinations and direct observations. The authors will provide an overview of critical considerations in different assessment ...
Restructured site characterization program at Yucca Mountain
International Nuclear Information System (INIS)
During 1994 and the early part of 1995, the US Department of Energy's Yucca Mountain Site Characterization Office (YMSCO) and its parent organization, the Office of Civilian Radioactive Waste Management (OCRWM) underwent a significant restructuring. Senior Department officials provided the leadership to reorient the management, technical, programmatic, and public interaction approach to the US High Level Radioactive Waste Disposal Program. The restructuring involved reorganizing the federal staff, conducting meaningful strategic planning, improving the management system, rationalizing contractor responsibilities, focusing upon major products, and increasing stakeholder involvement. The restructured program has prioritized technical and scientific activities toward meeting major regulatory milestones in a timely and cost-effective manner. This approach has raised concern among elements of technical, scientific, and oversight bodies that ...
1995-09-03
Energy Technology Data Exchange (ETDEWEB)
The Coastal Zone Sector of the Canadian Climate Impact and Adaptation Research Network (C-CIARN) was established to address concerns regarding climate change in coastal areas. Coastal zones are sensitive to increases in air, sea and ground temperatures as well as to variations in sea level, precipitation, ice thickness, and storm intensity. This report presents the results of a workshop which focused on how coastal communities will be affected by climate induced water level changes, particularly sea-level rise on ocean coasts and decreasing lake levels in the Great Lakes. The workshop addressed issues such as the effects of changing water levels on coastal infrastructure, utilities, community development, and the implications of changing water levels to human safety, cultural resources, tourism, and insurance. The workshop reviewed the current state of understanding on water level fluctuations resulting from climate change. It also identified ...
2004-07-01
The comparison of radioactives source term(ANSI N18.1) and 2900MW NPP's reactor coolant activity
International Nuclear Information System (INIS)
There are several radioactive source terms in nuclear power plant's design and construction. The radioactivity source in systems and components is derived from the reactor coolant activity and provide the parameters used to determine secondary system equilibrium activities and annually releasing amounts to environment. The reactor coolant activity standard(ANSI-Nl8.l) had been periodically revised. In Korea, the utility should do the PSR for NPP's. The objective of PSR is to determine by means of a comprehensive assessment of an existing nuclear power plant to what extent the plant meets current internationally accepted safety standards and practices. So, Kori 3 NPP's reactor coolant activity is reviewing with the anticipated source terms. The comparative results of RCS average activity is lower one fifth (1/5) #approx# one tenth(1/10) than ANSI/ANS N18.1-1999.
2003-10-01
Energy Technology Data Exchange (ETDEWEB)
This paper presents the technical and economic studies performed by CEMIG, Companhia Energetica de Minas Gerais, Brazil, concerning the use of closing resistor in its extra-high voltage (EHV) breakers. The analysis emphasizes the advantages which could be achieved with the elimination of the resistor as far as costs and reliability are concerned. This evaluation was motivated by two 500 kV breaker failures resulting from the breakdown of the closing resistor operation mechanism. These occurrences resulted in operative restriction for CEMIG EHV system. The analysis demanded a review of the capability criteria of silicon carbide (Si C) gap arresters, which are still greatly used in CEMIG EHV System, and of the procedures to be applied when carrying out the transient studies. The investigation resulted in the prompt removal of closing resistors from circuit breakers in CEMIG extra-high voltage system generating an economy of approximately U$ 840,00 and an improvement ...
1994-12-31
International Nuclear Information System (INIS)
This conference and trade show provided a forum to present new, emerging and existing technologies that will play a key role in ensuring that hydrocarbon exploitation occurs in a sustainable manner, where costs and resource recovery are optimized while minimizing environmental impacts. The challenge of developing maturing basins, frontier lands and unconventional resources was discussed. In particular, the application of thermal recovery methods such as steam assisted gravity drainage (SAGD) for the in-situ recovery of heavy oils and bitumens was reviewed and compared with the performance of alternative enhanced energy recovery technologies such as vapor extraction (VAPEX). The conference was attended by local and international participants in the petroleum sector, including managers, engineers, technologists, geologists, and other petroleum industry specialists. The conference featured 132 presentations addressing topics such as improved recovery of conventional ...
2007-06-12
Energy Technology Data Exchange (ETDEWEB)
Dye-sensitized nanocrystalline TiO{sub 2} solar cells are currently under development. Since these cells contain an electrolyte solution we reviewed the health and safety aspects in view of indoor applications, where personal contact cannot be excluded. Only small amounts of chemicals are present in each cell and so there is no danger of acute toxicity. However, long-term effects often can be caused by incidental contact with minute amounts. For this reason we have tested cis-di(thiocyanato)-bis(4,4'-dicarboxy-2,2'-bipyridine)Ru(II), the sensitizer dye in the Ames test. The dye was not mutagenic in the Salmonella typhimurium reverse mutation assay and in the Escherichia coli reverse mutation assay.
2000-01-01
Improving PSA quality of KSNP PSA model
Energy Technology Data Exchange (ETDEWEB)
In the RIR (Risk-informed Regulation), PSA (Probabilistic Safety Assessment) plays a major role because it provides overall risk insights for the regulatory body and utility. Therefore, the scope, the level of details and the technical adequacy of PSA, i.e. the quality of PSA is to be ensured for the successful RIR. To improve the quality of Korean PSA, we evaluate the quality of the KSNP (Korean Standard Nuclear Power Plant) internal full-power PSA model based on the 'ASME PRA Standard' and the 'NEI PRA Peer Review Process Guidance.' As a working group, PSA experts of the regulatory body and industry also participated in the evaluation process. It is finally judged that the overall quality of the KSNP PSA is between the ASME Standard Capability Category I and II. We also derive some items to be improved for upgrading the quality of the PSA up to the ASME Standard Capability Category II. In this paper, we ...
2004-07-01
Environmental Survey preliminary report, Los Alamos National Laboratory, Los Alamos, New Mexico
Energy Technology Data Exchange (ETDEWEB)
This report presents the preliminary findings from the first phase of the Environmental Survey of the United States Department of Energy's (DOE) Los Alamos National Laboratory (LANL), conducted March 29, 1987 through April 17, 1987. The Survey is being conducted by an interdisciplinary team of environmental specialists, led and managed by the Office of Environment, Safety and Health's Office of Environmental Audit. Individual team components are outside experts being supplied by a private contractor. The objective of the Survey is to identify environmental problems and areas of environmental risk associated with the LANL. The Survey covers all environmental media and all areas of environmental regulation. It is being performed in accordance with the DOE Environmental Survey Manual. The on-site phase of the Survey involves the review of existing site environmental data, observations of the operations carried on at the LANL, and ...
1988-01-01
Energy Technology Data Exchange (ETDEWEB)
Chapter 1 reviews the current and projected air pollution abatement measures of the Federal Government. Chapter 2 describes the development, status, and projected measures in industrial plant safety. Chapter 3 lists the points of emphasis of noise abatement; it presents the legal fundamentals and the resulting measures of the Federal Government. Each chapters starts by summarizing the present situation and then gives an outlook on tasks to cope with in the future. (orig.). [Deutsch] Kapitel 1 befasst sich mit dem Bereich der Luftreinhaltung und beschreibt die Massnahmen der Bundesregierung, die sie im Rahmen ihrer Umweltvorsorgepolitik bisher getroffen hat und fuer die Zukunft noch geplant sind. Kapitel 2 beschreibt die Entwicklung, den derzeitigen Stand und die kuenftigen Massnahmen im Bereich der Sicherheit industrieller Anlagen. Kapitel 3 nennt die Schwerpunkte der Laermbekaempfung und stellt die gesetzlichen Grundlagen sowie die daraus ...
1990-03-01
International Nuclear Information System (INIS)
Different concrete waste packages have been designed by Electricite de France (EDF) for the long-term storage of radioactive Low Level Waste (LLW). Their main function is to confine radionuclides from the biosphere for three hundred years in a near-surface disposal. According to the transport regulations, a Type-B package is needed for some waste like water filters. The water filters from EDF nuclear power plants are encapsulated in mortar and placed in a concrete container. Transport regulations for these containers have required the development of a methodology for safety assessment. The reference scenario of container degradation during transport considers a 9 m drop and a 800"oC fire for 30 min. First, the different chemical and physical processes involved in the containment of radionuclides are analysed. In particular, the radionuclide transport mechanisms in cement-based materials have been reviewed. Secondly, the effects of a container ...
Design modifications in 540 MWe and its impact on the dose rates
International Nuclear Information System (INIS)
Exposure control at the operating Nuclear Power Station is a major concern. TAPS Unit-4 is the first Pressurized Heavy Water Reactor of 540 MWe electrical capacity. This unit was made critical on March 6, 2005. In-depth review of radiation safety was done to identify the impact of design modification on dose rates at various locations and on the equipment's. Problems encountered in controlling the dose rates in 220 MWe electrical are eliminated by appropriate design modifications. Due to higher capacity of the unit there are design changes in major systems such as reactor core, primer heat transport system, moderator system, reactor regulation and protection systems. Reactor operations and maintenance activities during shut down contributes to exposure of the employees. Based on the experience gained in the operation of 220 MWe, design modifications incorporated in TAPS unit-4 and dose rate measurements carried out at 90 % full power, through ...
2005-11-23
Behavioral Economics and Regulatory Analysis.
Behavioral economics has captured the interest of scholars and the general public by demonstrating ways in which individuals make decisions that appear irrational. While increasing attention is being focused on the implications of this research for the design of risk-reducing policies, less attention has been paid to how it affects the economic valuation of policy consequences. This article considers the latter issue, reviewing the behavioral economics literature and discussing its implications for the conduct of benefit-cost analysis, particularly in the context of environmental, health, and safety regulations. We explore three concerns: using estimates of willingness to pay or willingness to accept compensation for valuation, considering the psychological aspects of risk when valuing mortality-risk reductions, and discounting future consequences. In each case, we take the perspective that analysts should avoid making judgments about whether ...
2011-08-13
Energy Technology Data Exchange (ETDEWEB)
The goal of this study is to estimate the relevance and Influence of the Existing Regulation and the RI-PBR to the institutionalization of the regulatory system. This study reviews the current regulatory system and the status of the RI-PBR implementation of the US NRC and Korea based upon SECY Papers, Risk Informed Regulation Implementation Plan (RIRIP) of the US NRC and other domestic studies. In order to investigate the perceptions, knowledge level, ground for the regulatory change, a survey was performed to Korean nuclear utilities, researchers and regulators on the perception on the RIR. The questionnaire was composed of 50 questions regarding personal details on work experience, level of education and specific field of work ; level of knowledge on the risk informed performance based regulation (RI-PBR); the perception of the current regulation, the effectiveness, level of procedure, flexibility, dependency on the regulator and personal view, and the perception ...
2003-02-15
A study of Two-Phase Flow Regime Maps in Vertical and Horizontal Pipes
Energy Technology Data Exchange (ETDEWEB)
A safety analysis code to design a pressurized water reactor and to obtain the licences including entire proprietary rights is under development in domestic research and development project. The purpose and scope of this report is to develop the flow regimes related models for inter-phase friction, wall frictions, wall heat transfer, and inter-phase heat and mass transfer in two-phase three-field equations. In order to choose choose the flow regime criteria, we have investigated various exiting best-estimate T/H codes in this chapter 2. They are the RELAP5-3D, TRAC-M, CATHARE, MARS codes. Around 500 references used in these codes have been collected and reviewed. Also we have investigated eleven papers in detail. In chapter 3, based on the selected flow regimes, the flow regime maps for a gas-liquid flow in horizontal and vertical tubes have decided including the mechanisms of flow regime transition regions. Conclusively, the process will be ...
2007-10-15
DARPA Program Composition for Embedded Systems (PCES) ...
... Title : DARPA Program Composition for Embedded Systems (PCES) Program Capstone Demonstration Video (Postprint) (CD-ROM). ...
2005-09-01
Geothermal Technologies Program: News
and Renewable Energy EERE Home | Programs & Offices | Consumer Information Geothermal Technologies Program Search Search Help Geothermal Technologies Program HOME ABOUT...
2011-08-21
EERE: Geothermal Technologies Program Home Page
and Renewable Energy EERE Home | Programs & Offices | Consumer Information Geothermal Technologies Program Search Search Help Geothermal Technologies Program HOME ABOUT...
2011-08-21
Energy Technology Data Exchange (ETDEWEB)
Laser safety standards and eye protection (filters) are designed to limit ocular exposures to prevent retinal lesions, yet eyesafe laser exposures can disrupt vision by causing glare and flashblindness. Protective filters can have opposing effects on vision function. They reduce laser exposures but also reduce task luminance and contrast. Filters alone may interfere with vision and consequently reduce work safety and performance. It is therefore important to be able to predict the effects of both laser exposures and protective filters to assess trade-offs between protection and visual function. This paper briefly reviews the methods, concepts, and experimental database used in our laboratory to predict laser, filter, and laser-plus-filter effects on tasks involving visual detection. The modeling approach uses estimates of the spatial distribution of light in the retinal image of the laser source to predict glare, ...
1990-01-01
Energy Technology Data Exchange (ETDEWEB)
This study examines various aspects of natural radioactive materials in the atmosphere over Perth in order to characterise the behaviour of these radionuclides. Data for this study was provided by the surface air sampling program (SASP) of the U.S. Department of Energy, which focuses on the lowest 2 metre layer of air; sampling being at 1.6 metres above the surface. The study particularly aimed to interpret correlation between existing radionuclide concentration data and meteorological data; which has been achieved in a qualitative sense. A general conclusion drawn form the observed results is that long-term averages of radionuclide concentrations have the highest correlation with climatic data; correlations between sample readings and contemporaneous weather data have the lowest correlation coefficients. Limitations in both the radionuclide and meteorological data were realised early in the project. The focus of the project accordingly changed from one of data ...
1995-12-31
Energy Technology Data Exchange (ETDEWEB)
The Clean Air Act establishes New Source Review (NSR) programs that apply to the construction or modification of major stationary emissions sources. In 2002 and 2003, the U.S. Environmental Protection Agency revised its rules to narrow the applicability of NSR to facility renovations. Congress then mandated a National Research Council study of the effects of the rules. An electricity-sector model - the Integrated Planning Model (IPM) - was used to explore the possible effects of the equipment replacement provision (ERP), the principal NSR change that was to affect the power-generation industry. The studies focused in particular on coal-fired electricity generating units, EGUs, for two reasons. First, coal-fired EGUs are important contributors of these pollutants, accounting for approximately 70 and 20% of nations SO{sub 2} and NOx emissions in 2004, respectively. Second, the shares of total capacity of large coal-fired EGUs that lack flue-gas ...
2007-03-15
Summary of Information and Resources Related to Energy Use in Healthcare Facilities - Version 1
Energy Technology Data Exchange (ETDEWEB)
This document presents the results of a review of publicly available information on energy use in health care facilities. The information contained in this document and in the sources cited herein provides the background and context for efforts to reduce energy use and costs in health care. Recognizing the breadth and diversity of relevant information, the author acknowledges that the report is likely not comprehensive. It is intended only to present a broad picture of what is currently known about health care energy use. This review was conducted as part of a 'High Performance Health Care Buildings' research study funded by the California Energy Commission. The study was motivated by the recognition that health care facilities collectively account for a substantial fraction of total commercial building energy use, due in large part to the very high energy intensity of hospitals and other inpatient care facilities. The goal of ...
2009-09-08
Oleoresin Capsicum toxicology evaluation and hazard review
Energy Technology Data Exchange (ETDEWEB)
Oleoresin Capsicum (OC) is an extract of the pepper plant used for centuries as a culinary spice (hot peppers). This material has been identified as a safe and effective Less-Than- Lethal weapon for use by Law enforcement and security professionals against assault. The National Institute of Justice (NIJ) is currently also evaluating its use in conjunction with other Less-Than-Lethal agents such as aqueous foam for use in corrections applications. Therefore, a comprehensive toxicological review of the literature was performed for the National Institute of Justice Less-Than-Lethal Force program to review and update the information available on the toxicity and adverse health effects associated with OC exposure. The results of this evaluation indicate that exposure to OC can result in dermatitis, as well as adverse nasal, pulmonary, and gastrointestinal effects in humans. The primary effects of OC exposure include pain and ...
1995-10-01
Energy Technology Data Exchange (ETDEWEB)
An initial review was conducted of the current treatment operations for remediation of groundwater contaminated with trichloroethene (TCE) at the Fort lewis Logistics Center. Results from this review indicate the two pump-and-treat systems are effectively containing the TCE plume within the upper unconfined aquifer (Vashon Drift). However, mass balance calculations show the existing treatment systems alone will not accomplish the remedial action objective of cleaning up the aquifer to drinking water standards within 30 years as specified in the Record of Decision (ROD). This conclusion is based on the estimated mass of TCE at the source term (51,000 kg), the calculated mass of TCE in the aquifer (4,900 kg), and the removal rate of the pump-and-treat systems that currently ranges from 324 to 667 kg of TCe per year. Four areas within the TCE plume have been identified where enhancements could be made to the existing treatment operations. These ...
1998-07-01
Energy Technology Data Exchange (ETDEWEB)
The advanced detector development project at the University of Michigan has completed the first full year of its current funding. Our general goals are the development of radiation detectors and spectrometers that are capable of portable room temperature operation. Over the past 12 months, we have worked primarily in the development of semiconductor spectrometers with {open_quotes}single carrier{close_quotes} response that offer the promise of room temperature operation and good energy resolution in gamma ray spectroscopy. We have also begun a small scale effort at investigating the properties of a small non-spectroscopic detector system with directional characteristics that will allow identification of the approximate direction in which gamma rays are incident. These activities have made use of the extensive clean room facilities at the University of Michigan for semiconductor device fabrication, and also the radiation measurement capabilities provided in our laboratory in the Phoenix ...
1995-11-01
Proceedings of CanWEA's 2006 conference and trade show
International Nuclear Information System (INIS)
The Canadian wind energy industry is experiencing rapid and unprecedented growth. The year 2006 saw the installation of 534 MW of wind energy across Canada, representing approximately $1 billion in new investment. It is anticipated that the wind energy industry will help to create jobs and training opportunities for many Canadians, as well as provide ongoing economic benefits to local communities through municipal tax and land lease payments. However, many challenges remain if Canada is to meet, or exceed, its objective of a total of 10,000 MW in installed wind energy by 2015. This conference provided a forum for wind industry member, academics and representatives of both governmental and non-governmental agencies to discuss issues related to wind energy development. The conference was divided into 3 streams. The policy stream examined issues related to the Canadian Wind Power Production Incentive (WPPI) program, as well as various federal policies regarding ...
2006-10-22
WHO wants more use of irradiated food, calls for education programs
International Nuclear Information System (INIS)
Short note. The World Health Organization (WHO) has taken aim at critics of irradiated food, claiming that the process has the potential to reduce the incidence of foodborne diseases such as salmonellosis, to cut postharvest food losses and to provide a wider variety of foods for consumers. 'The unwarranted rejection of this process, often based on lack of understanding of what food irradiation entails, may hamper its use in those countries which may benefit most', Dr. Jean-Paul Jardel, WHO's assistant director-general, argued following a recent international conference on the subject. Critics, including Canadians, has opposed food irradiation for years, claiming that more needs to be known about its effects. WHO said the 'vast majority' of the 54 national delegations at the conference supported use of the technology on foods ranging from grain and potatoes to poultry, tropical fruit and strawberries. WHO wants governments to educate the public on the benefits and ...
1989-02-01
The cascad spent fuel dry storage facility
International Nuclear Information System (INIS)
France has a wide variety of experimental spent fuels different from LWR spent fuel discharged from commercial reactors. Reprocessing such fuels would thus require the development and construction of special facilities. The French Atomic Energy Commission (CEA) has consequently opted for long-term interim storage of these spent fuels over a period of 50 years. Comparative studies of different storage concepts have been conducted on the basis of safety (mainly containment barriers and cooling), economic, modular design and operating flexibility criteria. These studies have shown that dry storage in a concrete vault cooled by natural convection is the best solution. A research and development program including theoretical investigations and mock-up tests confirmed the feasibility of cooling by natural convection and the validity of design rules applied for fuel storage. A facility called CASCAD was built at the CEA's Cadarache Nuclear Research ...
1991-04-14
Slide Rule for Rapid Response Estimation of Radiological Dose from Criticality Accidents
Energy Technology Data Exchange (ETDEWEB)
This paper describes a functional slide rule that provides a readily usable ?in-hand? method for estimating nuclear criticality accident information from sliding graphs, thereby permitting (1) the rapid estimation of pertinent criticality accident information without laborious or sophisticated calculations in a nuclear criticality emergency situation, (2) the appraisal of potential fission yields and external personnel radiation exposures for facility safety analyses, and (3) a technical basis for emergency preparedness and training programs at nonreactor nuclear facilities. The slide rule permits the estimation of neutron and gamma dose rates and integrated doses based upon estimated fission yields, distance from the fission source, and time-after criticality accidents for five different critical systems. Another sliding graph permits the estimation of critical solution fission yields based upon fissile material concentration, critical vessel ...
1999-09-20
Energy Technology Data Exchange (ETDEWEB)
In order to design roof bolting systems safely and economically, it is essential to understand the flexural behaviour of the immediate roof. Based on the strata sequence, the strata in the immediate roof are divided into three types. The flexural behaviour of the three strata types are investigated in terms of the following effects: roof span, horizontal stress, thickness and Young's modulus of the lowest strata. The suspension reinforcement mechanism is analysed using beam-column theory. The equations for the maximum bending stress, deflection and transferred bolt load for the bolted strata are derived. In the analysis, the bolt load is assumed to be a point load and a horizontal stress is uniformly applied to each stratum. The friction reinforcement mechanism is also investigated. The major function of roof bolting in this case is to create frictional resistance by tensioning the roof bolts so that the individual layers are combined into one single thick layer. A computer ...
1985-05-01
Energy Technology Data Exchange (ETDEWEB)
Purpose: calculation of conversion coefficients for the reconstruction of organ doses from entrance doses for abdomen radiographs of 0, 1, 5, 10, 15, and 30-year-old patients in conventional pediatric radiology for the radiographic settings recommended by the German and European guidelines for quality management in diagnostic radiology. Materials und method: using the commercially available personal computer program PCXMC developed by the Finnish Center for Radiation and Nuclear Safety (Saeteilyturvakeskus STUK), conversion coefficients for conventional abdomen radiographs were calculated performing Monte Carlo simulations in mathematical hermaphrodite phantom models describing patients of different ages. The possible clinical variation of beam collimation was taken into consideration by defining optimal and suboptimal radiation fields on the phantoms' surfaces. Results: conversion coefficients for the reconstruction of organ does in ...
2009-10-15
Epigenomic disruption: the effects of early developmental exposures.
Through DNA methylation, histone modifications, and small regulatory RNAs the epigenome systematically controls gene expression during development, both in utero and throughout life. The epigenome is also a very reactive system; its labile nature allows it to sense and respond to environmental perturbations to ensure survival during fetal growth. This pliability can lead to aberrant epigenetic modifications that persist into later life and induce numerous disease states. Endocrine-disrupting compounds (EDCs) are ubiquitous chemicals that interfere with growth and development. Several EDCs also interfere with epigenetic programming. The investigation of the epigenotoxic effects of bisphenol A (BPA), an EDC used in the production of plastics and resins, has further raised concern over the impact of EDCs on the epigenome. Using the Agouti viable yellow (A(vy)) mouse model, dietary BPA exposure was shown to hypomethylate both the A(vy) and the Cabp(IAP) metastable ...
2010-10-01
Energy Technology Data Exchange (ETDEWEB)
The mission of the Emerging Technologies thrust area at Lawrence Livermore National Laboratory is to help individuals establish technology areas that have national and commercial impact, and are outside the scope of the existing thrust areas. We continue to encourage innovative ideas that bring quality results to existing programs. We also take as our mission the encouragement of investment in new technology areas that are important to the economic competitiveness of this nation. In fiscal year 1992, we have focused on nine projects, summarized in this report: (1) Tire, Accident, Handling, and Roadway Safety; (2) EXTRANSYT: An Expert System for Advanced Traffic Management; (3) Odin: A High-Power, Underwater, Acoustic Transmitter for Surveillance Applications; (4) Passive Seismic Reservoir Monitoring: Signal Processing Innovations; (5) Paste Extrudable Explosive Aft Charge for Multi-Stage Munitions; (6) A Continuum Model for Reinforced Concrete ...
1993-03-01
Development of a Simple Scheme for Prediction of Flame Acceleration and DDT
International Nuclear Information System (INIS)
Hydrogen combustion phenomenology during severe accidents in nuclear power plants has been a safety issue. Especially, flame acceleration (FA) and Deflagration-to-Detonation Transition (DDT) are important because of their possible destructive impact on the containment or plant systems in it. Accordingly, it is the design goal to avoid FA and DDT for the hydrogen mitigation system. As a result from extensive effort dedicated to resolve the hydrogen issue, compiled information on the FA and DDT has been provided by the NEA. The FA criterion was suggested in terms of the mixture expansion ratio ? , and the criterion for onset of DDT was based on the greatness of the geometrical size of the reactive system compared with the detonation cell width ? of the average mixture composition. The DDT onset criterion reflects the current state of knowledge based on the experimental database; however, the criterion is not sufficient but a necessary condition. Therefore, it should ...
2010-10-01
CASCAD dry storage concept for spent fuel
International Nuclear Information System (INIS)
Further to a cost-benefit analysis of the various medium-term and long-term and H.L.W. storage possibilities, C.E.A. (French Atomic Energy Commission) and S.G.N. decided to develop an original dry storage process with natural convection cooling that offers many advantages: cut in the total investment and operating costs; high operating safety; natural convection cooling; existence of two containment barriers irrespective of the assumed clad conditions; flexible, modular and compact design. The process was first implemented in the so-called CASCAD Cadarache Facility (vault-type facility) constructed in Cadarache mainly to store fuel from Brennilis heavy water reactor. For the purpose, a large program was set up to develop and validate computer codes, in particular with the use of mockups. On the request of many clients, and owing to the outstanding operating results of the CASCAD Cadarache Facility, SGN was brought to adapt the process to the ...
1994-08-01
Indicators of safety culture - selection and utilization of leading safety performance indicators
International Nuclear Information System (INIS)
Safety indicators play a role in providing information on organizational performance, motivating people to work on safety and increasing organizational potential for safety. The aim of this report is to provide an overview on leading safety indicators in the domain of nuclear safety. The report explains the distinction between lead and lag indicators and proposes a framework of three types of safety performance indicators - feedback, monitor and drive indicators. Finally the report provides guidance for nuclear energy organizations for selecting and interpreting safety indicators. It proposes the use of safety culture as a leading safety performance indicator and offers an example list of potential indicators in all three categories. The report concludes that monitor and drive indicators are so ...
2010-05-01
FFTF operational results: startup to 100 MWd/kg
International Nuclear Information System (INIS)
The Fast Flux Test Facility (FFTF) is a 400-MW(t) sodium-cooled fast reactor operating at the Hanford Engineering Development Laboratory in Richland, Washington, to conduct fuels and materials testing in support of the US liquid-metal fast breeder reactor program. Startup and initial power testing included a comprehensive series of nuclear and nonnuclear tests to verify the thermal and neutronic characteristics of the plant and to demonstrate its inherent safety features. Extensive reactor core characterization measurements were completed to provide the neutron and gamma spectra, fission rates, and other physics data needed to design and evaluate tests irradiated in the FFTF. A specially designed series of natural-circulation tests was performed to demonstrate the inherent safety features of the plant. Early in 1982 the FFTF began its first 100-d irradiation cycle. Since that time the plant has operated beyond expectations; ...
Computerised, remote monitoring systems for underground coal mines
Energy Technology Data Exchange (ETDEWEB)
This report presents a study on the use of computerised, continuous remote monitoring systems for fire and explosive atmosphere safety in underground coal mines. The effects of these systems on the safety level in mines are investigated, and the relationship between mine safety regulations and computerised, continuous, remote monitoring is analysed.
1983-03-01
International Nuclear Information System (INIS)
National Nuclear Safety Department is authorized by Infra (Iranian Nuclear Regulatory Authority) for issuing rules and regulation and conducting the licensing and supervisory process for nuclear facilities. The main responsibilities of the NNSD are conducted via five main division are, nuclear codes and standards, Nuclear Safety assessment, Authorization, Inspection and Enforcement and Technical Support. In this paper, the functions and responsibilities of TSD in enhancing nuclear safety are described. Examples of main tasks to support the Nuclear Safety assessment division regarding to technical calculations and research of safety issues in licensing documents are provided. (author)
2007-08-01
Energy Technology Data Exchange (ETDEWEB)
United Solar completed its Phase 1 report and its proposal for Phase 2 of the PVBONUS Two program at the end of March 1998. At the same time, it also completed and submitted a proposal to the California Energy Commission PIER program for additional funding to cost-share development and testing of a pre-production model of the PVT-14. It was unsuccessful in both of these proposed efforts. While waiting for the proposal decisions, work continued in April and May to analyze the system design and component decisions described below. This document is a final summation report on the Phase 1 effort of the PVBONUS Two program that describes the key technical issues that United Solar and its subcontractor, Industrial Solar Technology Corporation, worked on in preparation of a Phase 2 award. The decisions described were ones that will guide the design and fabrication of a pre-production prototype of a 1500:1 mirrored concentrator ...
1998-12-31
Energy Technology Data Exchange (ETDEWEB)
Economics may one day dictate that it makes sense to replace oil or natural gas with coal in boilers that were originally designed to burn oil or gas. In recognition of this future possibility, Pittsburgh Energy Technical Center (PETC) has supported a program led by ABB Power Plant Laboratories in cooperation with the Energy and Fuels Research Center of Penn State University to develop the High Efficiency Advanced Coal Combustor (HEACC). The objective of the program is to demonstrate the technical and economic feasibility of retrofitting a gas/oil designed boiler to burn micronized coal. In support of the overall objective the following specific areas were targeted: a coal handling/preparation system that can meet the technical requirements for retrofitting microfine coal on a boiler designed for burning oil or natural gas; maintaining boiler thermal performance in accordance with specifications when burning oil or natural gas; maintaining NOx ...
1995-07-01
Coal liquefaction in Canada: the CANMET program
Energy Technology Data Exchange (ETDEWEB)
In Canada, the federal government, through CANMET, is actively supporting coal liquefaction research and development in a number of areas. A review of the basic principles and some of the processes in the production of liquid fuels from coal is presented with reference to the characteristics of the Canadian coal resource base. An overview of the CANMET coal liquefaction contract program is presented and specific results from the batch autoclave studies carried out with Saskatchewan lignite and Nova Scotia high-volatile bituminous coals are discussed. The development of a laboratory-scale continuous-flow coal liquefaction unit at the Energy Research Laboratories of CANMET to investigate the co-processing of coal and bitumen/heavy oil is also described. In principle, there are only two routes to the production of liquid fuels from coal - a degradation route and a synthesis route. The degradation route partially breaks the complex coal structure ...
1981-02-01
Energy Technology Data Exchange (ETDEWEB)
The use of standard cementitious material creates pulses of pH in the magnitude of 12-13 in the leachates and release alkalis. Such a high pH is detrimental and also unnecessarily complicates the safety analysis of the repository. As no reliable pH-plume models exist, the use of products giving a pH below 11 in the leachates facilitates the safety analysis. Also, according to current understanding, the use of low-pH cement (pH = 11) will not disturb the functioning of the bentonite, although limiting the amount of low-pH cement is recommended. A result of the project is that there are both low-pH cementitious material for grouting larger fractures (= 100 {mu}m) and non-cementitious material for grouting smaller fractures (< 100 {mu}m) that will, after further optimisation work, be recommended for grouting of deep repositories. This project concentrated on the technical development of properties for the low pH grouts. Long-term ...
2005-06-01
Environmental Sciences Division annual progress report for period ending September 30, 1981
Energy Technology Data Exchange (ETDEWEB)
Research programs from the following sections and programs are summarized: aquatic ecology, environmental resources, earth sciences, terrestrial ecology, advanced fossil energy program, toxic substances program, environmental impacts program, biomass, low-level waste research and development program, US DOE low-level waste management program, and waste isolation program.
1982-04-01
International Nuclear Information System (INIS)
... reactor intake canals intake structures nuclear power plants safety seismic
2011-01-01
Fire Safety Concerns in Space Operations - NASA Technical Reports ...
familiarity fire triangle (i.e., fuel, oxidant, and ignition source) are excluded. It Is obvious that for the baseline safety goal for spacecraft this ...
Explosives - hazard management
Energy Technology Data Exchange (ETDEWEB)
The management of risks of explosives are described. Administrative and procedural controls are considered. The safety management plan involves hazard identification, risk analysis, assessment and control. The current position of explosives safety is considered. 4 tabs.
1998-12-31
A bibliography of AECL publications on reactor safety
International Nuclear Information System (INIS)
AECL Publications on Reactor Safety in CANDU Reactors are listed in this bibliography. The listing is chronological and the accompanying index is by subject. The bibliography will be brought up to date annually. (auth).
1995-05-08
Coal Liquefaction Program: Fiscal year 1989, Summary program plan
Energy Technology Data Exchange (ETDEWEB)
Program plans of the Office of Coal Technology in coal liquefaction are presented. Technology description, status, market applications, program strategy and program management descriptions are included. 2 figs. (CBS)
1989-01-01
The safety issues of medical robotics
International Nuclear Information System (INIS)
In this paper, we put forward a systematic method to analyze, control and evaluate the safety issues of medical robotics. We created a safety model that consists of three axes to analyze safety factors. Software and hardware are the two material axes. The third axis is the policy that controls all phases of design, production, testing and application of the robot system. The policy was defined as hazard identification and safety insurance control (HISIC) that includes seven principles: definitions and requirements, hazard identification, safety insurance control, safety critical limits, monitoring and control, verification and validation, system log and documentation. HISIC was implemented in the development of a robot for urological applications that was known as URObot. The URObot is a universal robot with different modules adaptable for 3D ultrasound ...
2001-08-01
Resolving conflicting safety cultures
International Nuclear Information System (INIS)
Several nuclear power plant sites have been wounded in the crossfire between two distinct corporate cultures. The traditional utility culture lies on one side and that of the nuclear navy on the other. The two corporate cultures lead to different perceptions of open-quotes safety culture.close quotes This clash of safety cultures obscures a very important point about nuclear plant operations: Safety depends on organizational learning. Organizational learning provides the foundation for a perception of safety culture that transcends the conflict between utility and nuclear navy cultures. Corporate culture may be defined as the knowledge, attitudes, and beliefs shared by employees of a given company. Safety culture is the part of corporate culture concerning shared attitudes and beliefs affecting individual or public safety. If the safety ...
1993-06-20
Uranium-233 waste definition: Disposal options, safeguards, criticality control, and arms control
Energy Technology Data Exchange (ETDEWEB)
The US investigated the use of {sup 233}U for weapons, reactors, and other purposes from the 1950s into the 1970s. Based on the results of these investigations, it was decided not to use {sup 233}U on a large scale. Most of the {sup 233}U-containing materials were placed in long-term storage. At the end of the cold war, the US initiated, as part of its arms control policies, a disposition program for excess fissile materials. Other programs were accelerated for disposal of radioactive wastes placed in storage during the cold war. Last, potential safety issues were identified related to the storage of some {sup 233}U-containing materials. Because of these changes, significant activities associated with {sup 233}U-containing materials are expected. This report is one of a series of reports to provide the technical bases for future decisions on how to manage this material. A basis for defining when {sup 233}U-containing ...
1998-07-07
Terra Nova tow-out poised as next East Coast event
Energy Technology Data Exchange (ETDEWEB)
This spring, Newfoundland will send off a floating production, storage and offloading (FPSO) vessel to the offshore Terra Nova field. The Terra Nova will proceed southeast through Bull Arm, then northeast out of Trinity Bay, then heads southeast to the Jeanne d'Arc Basin on the Grand Banks. The Terra Nova is expected to produce 115,000 barrels of oil per day for six years, when it reaches full capacity. The consortium, headed by Petro-Canada as senior ownership partner and operator, built an environment protection program into every aspect of the project. Some of the features of the environment protection program include glory holes excavated on the ocean floor for the protection of production equipment from icebergs, to a flare stack on the platform, which has four legs to provide stability in rough seas. The FPSO was designed to withstand sea ice, icebergs, and severe winter storms. Flow lines are also protected, and in the event ...
2001-01-15
RAAN Conference. Support of Nuclear Power. Opening talk
International Nuclear Information System (INIS)
Nuclear power in Romania was initiated on the basis of CANDU reactor type technology, an option found to fulfill the requirements for a sustainable economic development, to support the electric energy demand of the country and to ensure the population and environment protection. The construction of the Cernavoda NPP was heavily based on the Romanian industry participation and basic and applied nuclear research national resources. The experience acquired from Cernavoda NPP Unit 1 will be fructified in the construction of Units 2-5 to be built. The Romanian Ministry of Education and Research implemented a nuclear national program for research and development taking into account the European Union requirements and recommendations, the cooperation with the IAEA - Vienna and the Romanian government policy on short and medium terms in the nuclear field. The research-development program targeted: the reactor physics and nuclear fuel management; the ...
2002-09-06
International Nuclear Information System (INIS)
After five years of implantation of a program for classification and signalling of restricted areas in the IPEN-CNEN-SP, we noticed that the applied measures of radio protection contributed for the improvement of the system of occupational radiological protection, promoting an improvement in the security of the workers, towards the planning in the execution of the activities involving the use of sources of ionizing radiation. Later, during the implantation of this program, the service of occupational radiological protection, there was great difficulty to conciliate its necessities in terms of security signalling, face the absence of existing standardisation in the country for the minimum disposals on the subject in question. Nowadays there are different interpretations of the specific criteria and many effective normative documents that exist in the country. This work presents as proposal the elaboration of a technical guide whose objective is ...
Low-activity waste envelope definitions for the TWRS Privatization Phase I Request For Proposal
Energy Technology Data Exchange (ETDEWEB)
Radioactive waste has been stored in large underground storage tanks at the Hanford Site since 1944. Approximately 212 million liters of waste containing approximately 240,000 metric tons of processed chemicals and 177 mega-curies of radionuclides are now stored in 177 tanks. These caustic wastes are in the form of liquids, slurries, saltcakes, and sludge. In 1991, the Tank Waste Remediation System (TWRS) Program was established to manage, retrieve, treat, immobilize, and dispose of these wastes in a safe, environmentally sound, and cost-effective manner. The Department of Energy (DOE) has believes that it is feasible to privatize portions of the TWRS Program. Under the privatization strategy embodied in the Request for Proposal (RFP), DOE will purchase services from a contractor-owned, contractor-operated facility under a fixed-price contract. Phase I of the TWRS privatization strategy is a proof-of-concept/commercial demonstration-scale ...
1996-11-01
Dose reduction by chemical decontamination
International Nuclear Information System (INIS)
At the Borssele Nuclear Power Station, which has been in operation since 1973, a comprehensive program of modifications, one of the most extensive of its kind worldwide, was conducted in 1997 within the framework of an integral safety evaluation carried out at ten-year intervals, especially in the nuclear section. The collective dose associated with this activity was greatly reduced by Alara measures, one of which was chemical decontamination of part of the emergency and residual heat removal systems. An average decontamination factor (DF) of 17 was achieved by using the Siemens Cord UV process. Two decontamination cycles were required. The decontamination program took three days to be completed. The planned collective dose was reduced from 1029 mSv (without decontamination) to 335 mSv (on the basis of a DF of 8). Based on the DF of 17 achieved, the planned dose was corrected downward to 270 mSv. The dose finally achieved ...
1998-10-01
Developing effective professional bus driver health programs: An investigation of self-rated health.
The health of professional bus drivers is a critical factor in their driving performance; any impairment may lead to undesired consequences. In an attempt to develop and prioritize health and wellness programs, this study investigates the factors significantly affecting the health conditions of professional bus drivers, as well as the strength of these factors. This study uses self-rated health as the examination measurement. This simple assessment is an inclusive measure of health status for judging health trajectory, and is highly associated with changes in functional ability, including perceived control over driving. This study evaluates driver responses of self-rated health with ordered response models that consider factors such as the driver reported health problems, physical and psychological conditions, demographic factors, driving experience, and working environment. Analysis of a sample of 785 drivers shows that age, body mass index, depression, daily ...
2011-06-24
Energy Technology Data Exchange (ETDEWEB)
This groundwater quality report (GWQR) contains an evaluation of the groundwater quality data obtained during the 1993 calendar year (CY) at several hazardous and non-hazardous waste management facilities associated with the US DOE Y-12 Plant located on the DOE Oak Ridge Reservation (ORR) southeast of Oak Ridge, Tennessee. The groundwater quality data are presented in Part 1 of the GWQR submitted by Martin Marietta Energy Systems, Inc. to the Tennessee Department of Environment and Conservation (TDEC) in February 1994. Groundwater quality data evaluated in this report were obtained at several hazardous and non-hazardous waste management sites located within the Chestnut Ridge Hydrogeologic Regime (Chestnut Ridge Regime). The Chestnut Ridge Regime encompasses a section of Chestnut Ridge south of the Y-12 Plant and is one of three hydrogeologic regimes defined for the purposes of groundwater quality monitoring at the plant. The Environmental Management Department of the Y-12 Plant ...
1994-09-01
A.C.R.O. activity report 2001; A.C.R.O. rapport d'activite 2001
Energy Technology Data Exchange (ETDEWEB)
As regards the environmental protection, the A.C.R.O. maintained in 2001 its programs of surveillance around the main western nuclear installations of France. The radioecological surveillance of the site of Cogema La-Hague for the dismantling of the former pipe of release in sea was one of the key points of this action environmental surveillance. The two accidents of atmospheric release in may and october 2001 at Cogema La Hague have shown the interest of an association as A.C.R.O.. It is thank to the measure, by our laboratory, of repercussions on environment of these incidents that it has been possible to bring to light a dysfunction of the measurement system of the gaseous effluents released by the facility operator. To improve the public information, A.C.R.O. concerns its main efforts on the development of the consumer technical information available on-line via its web site and in its regular publication 'the nuclear chronicle'. Besides, the ...
2001-07-01
OFFICE OF NEW DRUGS OFFICE OF PHARMACOEPIDEMIOLOGY AND STATISTICAL ...
... The pharmacologist/toxicologist and the statistician will jointly determine if a statistical review is needed and when the review should be done. ...
Energy Technology Data Exchange (ETDEWEB)
The U.S. Department of Energy (DOE)-Carlsbad Field Office (CBFO) has developed draft documentation to present the proposed Waste Isolation Pilot Plant (WIPP) remote-handled (RH-) transuranic (TRU) waste characterization program to its regulators, the U.S. Environmental Protection Agency and the New Mexico Environment Department. Compliance with Title 40, Code of Federal Regulations, Parts 191 and 194; the WIPP Land Withdrawal Act (PL 102-579); and the WIPP Hazardous Waste Facility Permit, as well as the Certificates of Compliance for the 72-B and 10-160B Casks, requires that specific waste parameter limits be imposed on DOE sites disposing of TRU waste at WIPP. The DOE-CBFO must control the sites' compliance with the limits by specifying allowable characterization methods. As with the established WIPP contact handled TRU waste characterization program, the DOE-CBFO has proposed a Remote-Handled TRU Waste Acceptance Criteria (RH-WAC) ...
2002-02-26
Energy Technology Data Exchange (ETDEWEB)
The U.S. Department of Energy (DOE) and the U.S. Council for Automotive Research (composed of automakers Ford, General Motors, and Chrysler) announced in January 2002 a new cooperative research effort. Known as 'FreedomCAR' (derived from 'Freedom' and 'Cooperative Automotive Research'), it represents DOE's commitment to developing public/private partnerships to fund high-risk, high-payoff research into advanced automotive technologies. Efficient fuel cell technology, which uses hydrogen to power automobiles without air pollution, is a very promising pathway to achieving the ultimate vision. The new partnership replaces and builds upon the Partnership for a New Generation of Vehicles initiative that ran from 1993 through 2001. The Advanced Power Electronics and Electric Machines (APEEM) subprogram within the FreedomCAR and Vehicle Technologies Program provides support and guidance for many cutting-edge ...
2007-10-01
Energy Technology Data Exchange (ETDEWEB)
Information is presented concerning new trends in licensing; seismic considerations and system structural behavior; TMI-2 risk assessment and thermal hydraulics; statistical assessment of potential accidents and verification of computational methods; issues with respect to improved safety; human factors in nuclear power plant operation; diagnostics and activities in support of recovery; LOCA transient analysis; unresolved safety issues and other safety considerations; and fission product transport.
1980-06-01
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