WorldWideScience
1

Monitoring processes and measuring the effectiveness of the management system  

International Nuclear Information System (INIS)

This document presents the way which the 8th principle of the quality management system 'Process approach' is applied, the principle that is identified and used by international standard ISO 9000. In order to understand the evolution of the management system requirements, as used today in different activities namely, industry, services, and nuclear activities, the authors present an evolution of the quality concept and its traceability to different standards, applicable in time. There are described the requirements of ISO 9001 standard, that represents the most widely spread model for modern organization management and the IAEA concerns related to integration of the above standard requirements into the most recent safety IAEA standard 'The Management System for facilities and activities'. The IAEA ...

2009-10-12

2

The Importance of Building and Enhancing Worldwide Industry Cooperation in the Areas of Radiological Protection, Waste Management and Decommissioning  

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 ...

3

Grading of quality assurance requirements  

International Nuclear Information System (INIS)

The present Manual provides guidance and illustrative examples for applying a method by which graded quality assurance requirements may be determined and adapted to the items and services of a nuclear power plant in conformance with the requirements of the IAEA Nuclear Safety Standards (NUSS) Code and Safety Guides on quality assurance. The Manual replaces the previous publication IAEA-TECDOC-303 on the same subject. Various methods of grading quality assurance are available in a number of Member States. During the development of the present Manual it was not considered practical to attempt to resolve the differences between those methods and it was preferred to identify and benefit from the good practices available in all the methods. The method presented in this Manual deals with the aspects of management, documentation, control, verification and administration which affect ...

4

Sequential chemical treatment of radium species in TENORM waste sludge produced from oil and natural gas production  

British Library Electronic Table of Contents (United Kingdom)

This paper is dedicated to the treatment of sludge occurring in frame of the Egyptian produced from oil and gas production. The activity levels of three radium isotopes: Ra-226 (of U-series), Ra-228 and Ra-224 (of Th-series) in the solid TENORM waste (sludge) were first evaluated and followed by a sequential treatment for all radium species (fractions) presented in TENORM. The sequential treatment was carried out based on two approaches `A' and `B' using different chemical solutions. The results obtained indicate that the activity levels of all radium isotopes (Ra-226, Ra-228 and Ra-224) of the environmental interest in the TENORM waste sludge were elevated with regard to exemption levels established by IAEA [International Atomic Energy Agency (IAEA), International basic safety standards f...

2009-01-01

5

The Joint Convention on the Safety of Spent fuel Management and on the safety of Radioactive Waste Management: A UK Regulator's Perspective  

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 provides a structured process through which every ...

6

Legal Analysis of the Korea Radioactive Waste Management Act in the aspect of IAEA Principles  

International Nuclear Information System (INIS)

According to the Principles of Radioactive Waste Management, the IAEA SAFETY SERIES NO-111-F, IAEA declared 9 doctrines. The IAEA advised a country that operates nuclear power plant to adopt the principles. As a member of the IAEA, Korea has also discussed about a unified policy and enacting law for radioactive waste management to follow the doctrines. This study analyzed the recently enacted Korea Radioactive Waste Management Act and verified whether the Act successfully follows the doctrine or not

2009-05-01

7

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 establishing domestic regulatory positions and guidelines. For example, ...

1998-05-03

8

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 ...

1998-07-01

9

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 ...

1998-05-03

10

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 ...

1996-01-01

11

Sequential chemical treatment of radium species in TENORM waste sludge produced from oil and natural gas production.  

Science.gov (United States)

This paper is dedicated to the treatment of sludge occurring in frame of the Egyptian produced from oil and gas production. The activity levels of three radium isotopes: Ra-226 (of U-series), Ra-228 and Ra-224 (of Th-series) in the solid TENORM waste (sludge) were first evaluated and followed by a sequential treatment for all radium species (fractions) presented in TENORM. The sequential treatment was carried out based on two approaches 'A' and 'B' using different chemical solutions. The results obtained indicate that the activity levels of all radium isotopes (Ra-226, Ra-228 and Ra-224) of the environmental interest in the TENORM waste sludge were elevated with regard to exemption levels established by IAEA [International Atomic Energy Agency (IAEA), International basic safety standards for the protection against ionizing radiation and for the safety of radiation sources. ...

2008-04-18

12

Sequential chemical treatment of radium species in TENORM waste sludge produced from oil and natural gas production  

Energy Technology Data Exchange (ETDEWEB)

This paper is dedicated to the treatment of sludge occurring in frame of the Egyptian produced from oil and gas production. The activity levels of three radium isotopes: Ra-226 (of U-series), Ra-228 and Ra-224 (of Th-series) in the solid TENORM waste (sludge) were first evaluated and followed by a sequential treatment for all radium species (fractions) presented in TENORM. The sequential treatment was carried out based on two approaches 'A' and 'B' using different chemical solutions. The results obtained indicate that the activity levels of all radium isotopes (Ra-226, Ra-228 and Ra-224) of the environmental interest in the TENORM waste sludge were elevated with regard to exemption levels established by IAEA [International Atomic Energy Agency (IAEA), International basic safety standards for the protection against ionizing radiation and for the ...

2009-01-30

13

Roles of the operator and the safety services in nuclear power plant quality assurance  

International Nuclear Information System (INIS)

With regard to the operation of nuclear power plants, Electricite de France formally recognized in 1973 that it was necessary for safety reasons and economically acceptable to adopt organizational principles of quality assurance that would be applicable both to its own activities and to those of its suppliers. Generally speaking, the form and spirit of the quality assurance programme chosen is based largely on the Code of Practice No. 50-C-QA. In particular, the programme focuses on the flexible character of quality assurance requirements and stresses that in the final analysis product quality depends above all on those to whom the project has been assigned, because it is they who are responsible for meeting the quality objectives set. Ten years of experience with the suppliers of Electricite de France has shown that these suppliers, after some initial difficulty, have been able to adapt the application of quality assurance so as to achieve satisfactory quality as ...

14

Treatment for dismantled radioactive solid waste from the TRIGA Mark-2 and 3  

Energy Technology Data Exchange (ETDEWEB)

Radioactive wastes are generally classified into 3 type depending on their physical property: liquid, solid and gaseous type. State-of -the art concerning liquid waste treatment has already been published; KAERI/TR-1315/99. Solid wastes classification package and treatment method will be studied to effectively manage them during the practical decommissioning work. All of the spent fuel produced during the operation of the TRIGA Mark-2 and 3 have been transported to the US last year, 1998, according to the spent fuel management strategy set-up by the US government for the non-proliferation of nuclear energy. Solid wastes are mainly all equipment existing inside of the reactors, activated concrete among the bio-shielded concrete, pipes, pimps, resin filter and it's housings, heat-exchangers, liquid waste storage tanks, to radioactive waste storage treatment facilities and so on. Solid wastes are generally low-level. They are classified according to the national regulation and ...

1999-06-01

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 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

16

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

17

Quality assurance requirements in various codes and standards  

International Nuclear Information System (INIS)

The quality assurance requirements in various countries and according to various international codes and standards are presented, compared and critically discussed. Cases of developing countries are also discussed, and the use of IAEA code of practice and other codes for quality assurance in these countries is reviewed. Recommendations are made regarding the quality assurance system to be applied for Egypt's nuclear power plants.

18

Nuclear forensics support. Reference manual  

International Nuclear Information System (INIS)

Illicit trafficking of nuclear and other radioactive material has been an issue of concern since the first seizures in the early 1990s. By the end of 2004 Member States had confirmed 540 cases, while about another 500 remain unconfirmed. Most of the confirmed cases have a criminal dimension, even if they were not for known terrorist purposes. The attacks of September 2001 in the USA dramatically emphasized the requirement for the enhanced control and security of nuclear and other radioactive material. In response to a resolution by the IAEA General Conference in September 2002 the IAEA has adopted an integrated approach to protection against nuclear terrorism. This brings together IAEA activities concerned with the physical protection of nuclear material and nuclear installations, nuclear material accountancy, detection and response to illicit nuclear trafficking, the security and safety of radioactive ...

19

ORNL results for Test Case 1 of the International Atomic Energy Agency`s research program on the safety assessment of Near-Surface Radioactive Waste Disposal Facilities  

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 were defined in Test Case 1: a simple earth ...

1993-07-01

20

Quantification of radionuclide transfer in terrestrial and freshwater environments for radiological assessments  

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

21

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

22

Report of the ASSET (Assessment of Safety Significant Events Team) mission to the Zaporozhe nuclear power plant in Ukraine 13-24 June 1994 Division of Nuclear Safety. Root cause analysis of operational events with a view to enhancing the prevention of incidents  

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

23

Non-standard natural circulation in primary circuit of VVR-440, behavior of horizontal steam generator in this regime  

Energy Technology Data Exchange (ETDEWEB)

Analyzing various SBLOCA with high pressure safety injection (HPSI) at VVER-440/213, we met a surprising phenomenon - a 'natural' circulation post SG heat transfer reversal. This is not usual, because normal natural circulation (NC) in primary circuit is connected with positive heat transfer at SG. If there is reverse heat transfer at SG (as soon as the break enthalpy outflow is sufficient for removal of reactor decay heat), it should obstruct any natural circulation. The question was, what is the driving force of this 'non-standard natural circulation'. After all we revealed that force - it is the density difference between the colder water in reactor downcomer (cold water from HPSI) and warmer water in inner reactor (lower plenum, core, upper plenum). This phenomenon could be confusing for operating personal, because there would be an opposite temperature difference at the loop than by normal natural ...

2001-07-01

24

Non-standard natural circulation in primary circuit of VVR-440, behavior of horizontal steam generator in this regime  

International Nuclear Information System (INIS)

Analyzing various SBLOCA with high pressure safety injection (HPSI) at VVER-440/213, we met a surprising phenomenon - a 'natural' circulation post SG heat transfer reversal. This is not usual, because normal natural circulation (NC) in primary circuit is connected with positive heat transfer at SG. If there is reverse heat transfer at SG (as soon as the break enthalpy outflow is sufficient for removal of reactor decay heat), it should obstruct any natural circulation. The question was, what is the driving force of this 'non-standard natural circulation'. After all we revealed that force - it is the density difference between the colder water in reactor downcomer (cold water from HPSI) and warmer water in inner reactor (lower plenum, core, upper plenum). This phenomenon could be confusing for operating personal, because there would be an opposite temperature difference at the loop than by normal natural circulation (under ...

2001-03-20

25

Plutonium Finishing Plant (PFP) Standards/Requirements Identification Document (S/RID)  

International Nuclear Information System (INIS)

This Standards/Requirements Identification Document (S/RID) sets forth the Environmental Safety and Health (ESH) standards/requirements for the Plutonium Finishing Plant (PFP). This S/RID is applicable to the appropriate life cycle phases of design, construction, operation, and preparation for decommissioning. These standards/requirements are adequate to ensure the protection of the health and safety of workers, the public, and the environment.

1998-06-01

26

The computerized management for individual monitoring data in Daya Bay Nuclear Power Station  

International Nuclear Information System (INIS)

The authors report the individual monitoring data management system (IDOSE) at Daya Bay Nuclear Power Station. The components of the individual monitoring system, the design requirements of IDOSE, the characteristics and application of this computerized management system are mainly presented. Its application shows that IDOSE meets the requirements of the concerning occupational standards of the state and matches with the requirements of IAEA/ISOE.

27

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

28

International Symposium on Nuclear Energy SIEN 2009. Nuclear Power - A New Challenge  

International Nuclear Information System (INIS)

The SIEN 2009 symposium organized by Romanian Nuclear Energy Association, AREN, in co-operation with Romanian Atomic Forum, ROMATOM, was primarily targeting the expert community involved in developing new nuclear power projects and implementing the National Nuclear Program. The symposium was also open as a discussion and information forum for scientists, engineers, technicians and students interested in scientific and technologic topics of Nuclear Power. It was structured in the following 6 sections: - Nuclear new builds and developments; - Operation, inspection and maintenance; - Increasing nuclear safety features; - Fuel cycle and decommissioning; - Public perception and confidence strengthening; - Environmental management. The symposium began with three plenary lectures dealing with: - Sustainable Nuclear Energy European Technology Platform; - Nuclear new-build; - Current issues of nuclear equipment standardization in Romania. A poster ...

2009-10-12

29

Status and trends of nuclear technologies - Report of the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO). Additional information (Companion CD-ROM)  

International Nuclear Information System (INIS)

The International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO) was launched in the year 2000, based on a resolution by the IAEA General Conference (GC(44)/RES/21). INPRO intends to help to ensure that nuclear energy is available in the 21st century in a sustainable manner, and seeks to bring together all interested Member States, both technology holders and technology users, to consider, jointly, actions to achieve desired innovations. INPRO is taking care of the specific needs of developing countries. This IAEA publication is part of Phase 1 of INPRO. It intends to provide an overview on history, present situation and future perspectives of nuclear fuel cycle technologies. While this overview focuses on technical issues, nevertheless, the aspects of economics, environment, and safety and proliferation resistance are important background issues for this study. After a brief description about the INPRO ...

1991-01-01

30

6. Sample preparation for determining pollutants in components of the environment  

International Nuclear Information System (INIS)

Examples are given of reference materials for radionuclide X-ray fluorescence analysis (RXFA) of the environment processed by the National Bureau of Standards and the IAEA. Methods are described used for preparing standard materials for RXFA. For determining air pollutants the sample is prepared by dry or wet mineralization. Water samples have to be preserved prior to analysis. Insoluble components are separated by filtration or centrifugation. Biological materials must be dehydrated and homogenized. Samples of soil, sludges, sediments and solid wastes will sometimes have to be converted into a solution in some cases a leachate will have to be obtained. (ES).

1983-12-01

31

Training guidelines in non-destructive testing techniques. 2002 edition  

International Nuclear Information System (INIS)

Non-destructive testing (NDT) is a dynamic technology and progresses with time. Since the issuance of IAEA-TECDOC-628 in 1991, the technology has experienced numerous changes. Advancements in knowledge about the behaviour of materials have led to changes in the applicable NDT codes, standards and specifications. In addition, over the last ten years, as a result of extensive research and development activities worldwide, new NDT techniques and equipment have been developed which are accepted by engineering community. To accommodate the latest developments, modifications are required to training materials. The present publication is an updated version of IAEA-TECDOC-628. The modifications were made during an Advisory Group Meeting, held in Vienna from 25-29 June 2001. The content of the first edition of IAEA-TECDOC-628 has been revised based on the experience of the experts, as well as comments of the ...

1986-09-21

32

SSAC at Your Service: Promoting Co-operation Between IAEA and Finnish SSAC for Safeguards Implementation (Within the EU)  

International Nuclear Information System (INIS)

As the nuclear world is changing, the non-proliferation and safeguard systems have to change along the global development. Nuclear security as well as safety must be involved in all phases. Thus, modernization of thinking is a must. State system of accounting for and control of nuclear material (SSAC) is a basis, but now it is time to move ahead. Safeguards is not any more only to verify the declared nuclear materials but it is to inform the international safeguards society transparently but confidentially about the nuclear fuel cycle related activities and trade, and to confirm that there are no undeclared activities related to the nuclear fuel cycle in the states. Only strong SSAC with enhanced capabilities, activities and rights can meet the demand. The proliferation of nuclear weapons is a threat that also urges cooperation at all levels. International, regional and state systems must work closely together, and there is need and space for everyone. State ...

2010-11-01

33

Integrated Safeguards proposal for Finland. Final report on Task FIN C 1264 of the Finnish Support Programme to IAEA Safeguards  

Energy Technology Data Exchange (ETDEWEB)

The IAEA has requested several member states to present their proposal of the application of the Integrated Safeguards (IS) system in their nuclear facilities. This report contains a IS proposal for Finland prepared under the Task FIN C 1264 of The Finnish Support Programme to IAEA Safeguards. The comprehensive safeguards system of the International Atomic Energy Agency (IAEA) has been one of the main tools in the fight against nuclear proliferation since the entry-into-force of the Nuclear Non-proliferation Treaty three decades ago. In the 1990s some of the inherent weaknesses of this so-called traditional safeguards system were revealed first in Iraq and then in North Korea. Therefore, the member states of the LAEA decided to give the Agency additional legal authority in order to make its control system more effective as well as more efficient than before. This was accomplished by the approval of the so-called Model ...

2000-08-01

34

Role and responsibilities of Technical Support Division (TSD) of National Nuclear Safety Department (NNSD) in licensing process  

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

35

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 ...

36

Design, fabrication, qualification and reliability of the major components of ''MONJU'' from a safety point of view  

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

37

The IAEA Code of Practice on quality assurance, and quality assurance requirements and practices in Member States  

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 ...

38

Future needs and requirements for AMS "1"4C standards and reference materials  

International Nuclear Information System (INIS)

"1"4C measurement uses a number of standards and reference materials with different properties. Historically the absolute calibration of "1"4C measurement was tied to 1890 wood, through the 'primary' standard of NBS-OxI (produced by the National Bureau of Standards, now NIST - National Institute of Standards and technology) subsequently replaced by NBS-OxII. These are both internationally calibrated and certified materials, whose "1"4C activities are known absolutely. A second tier of materials, often called secondary standards or reference materials, and including internationally recognised materials such as ANU-sucrose (now also IAEA-C6), Chinese - sucrose and the IAEA C1-C6 series, augmented by additional oxalic acid samples are also used routinely. The activity of these materials has been estimated from large numbers of measurements made ...

2004-08-01

39

Second international symposium on nuclear power plant life management. Book of extended synopses  

International Nuclear Information System (INIS)

The world's fleet of nuclear power plants is, on average, more than 20 years old. Even though the design life of a nuclear power plant is typically 30-40 years, it is quite feasible that many plants will be able to operate in excess of their design lives, provided that nuclear power plant engineers demonstrate by analysis, trending, equipment and system upgrades, increased vigilance, testing and ageing management that the plant will operate safely. In the operation of nuclear power plants, safety should be always the prime consideration. Plant operators and regulators must always ensure that plant safety is maintained, and where possible enhanced, during a plant's operating lifetime. Nuclear power plant life management (PLiM) has gained increased attention over the past decade, and effective ageing management of systems, structures and components (SSCs) is a key element in PLiM for the safe and reliable long term operation of nuclear power ...

2007-10-15

40

Formulation and practice of standards for radiation protection of #gamma#-ray industrial computed tomography  

International Nuclear Information System (INIS)

There are many differences between industrial CT and industrial radiography, such as imaging principle, inspection time, radiation dose and the requirements for operators etc. The national standards for radiation protection of industrial detection are not applicable to the requirements of protection and safety for #gamma#-ray industrial CT to some extent now. In order to standardize the production and use for #gamma#-ray industrial CT, protect the safety of operators and the public, and to promote the popularization and application of #gamma#-ray industrial CT, it is significant to establish the national standards for radiation protection of #gamma#-ray industrial CT as soon as possible. The purpose of this paper is to introduce the contents of this standard, and specify some important terms. Then there is a brief discussion on the existing problems during ...

2009-03-01

41

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

42

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 like in French or ...

2009-10-12

43

System 80+{trademark} Standard Design: CESSAR design certification. Volume 9: Amendment I  

Energy Technology Data Exchange (ETDEWEB)

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{sup +}{trademark} Standard Design. This volume 9 discusses Electric Power and Auxiliary Systems.

1990-12-21

44

System 80+{trademark} Standard Design: CESSAR design certification. Volume 8: Amendment I  

Energy Technology Data Exchange (ETDEWEB)

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{sup +}{trademark} Standard Design. This volume 8 provides a description of instrumentation and controls.

1990-12-21

45

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.

46

Standardization/improvement and technical development of light water reactor power station in Japan(BWR)  

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

47

Technical Standards for Wolsong Unit 1 Nuclear Power Plant  

International Nuclear Information System (INIS)

More than twenty years after commencing commercial operation in 1983, Wolsong Unit 1(W1- NPP), the first CANDU Pressurized Heavy Water Reactor (PHWR) in Korea, has been undergoing refurbishment. Safety analyses were required to evaluate the safety of W1-NPP because significant amount of equipment has been refurbished. To evaluate the effectiveness of W1-NPP after these upgrades, new safety analyses were performed using the same technical standards of Wolsong Units 2, 3, 4 (W234-NPP) for Design Basis Accidents (DBA). The refurbished W1- NPP is expected to be licensed for full power operation based on the verified safety analysis results that are obtained by using the upgraded computer codes and newly adopted technical standards of W234-NPP

2010-10-01

48

XML schema for atomic and molecular data. Summary report of consultants' meeting  

International Nuclear Information System (INIS)

Advanced developments in computer technologies offer exciting opportunities for new distribution tools and applications in various fields of physics. The convenient and reliable exchange of data is clearly an important component of such applications. Therefore, in 2003, the A+M Data Unit initiated within the collaborative efforts of the DCN (Data Centre Network) a new standard for atomic, molecular and particle surface interaction data exchange (AM'PSI) based on XML (eXtensible Markup Language). A working group composed of staff from the IAEA, NIST, ORNL and Observatoire Paris-Meudon meets biannually to discuss progress made on the XML schema, and to foresee new developments and actions to be taken to promote this standard for AM/PSI data exchange. (author)

2007-12-06

49

Proceedings of a specialist meeting on regulatory approaches for the control of environmental residues containing naturally occurring radioactive material. Working material  

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

50

Interim radiological safety standards and evaluation procedures for subseabed high-level waste disposal  

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 ...

1997-06-01

51

Elemental investigation of Syrian medicinal plants using PIXE analysis  

Energy Technology Data Exchange (ETDEWEB)

Particle induced X-ray emission (PIXE) technique has been employed to perform elemental analysis of K, Ca, Mn, Fe, Cu, Zn, Br and Sr for Syrian medicinal plants used traditionally to enhance the body immunity. Plant samples were prepared in a simple dried base. The results were verified by comparing with those obtained from both IAEA-359 and IAEA-V10 reference materials. Relative standard deviations are mostly within {+-}5-10% suggest good precision. A correlation between the elemental content in each medicinal plant with its traditional remedial usage has been proposed. Both K and Ca are found to be the major elements in the samples. Fe, Mn and Zn have been detected in good levels in most of these plants clarifying their possible contribution to keep the body immune system in good condition. The contribution of the elements in these plants to the dietary recommended intakes (DRI) has been evaluated. Advantages and ...

2010-09-15

52

Break Nodalization Influence to IAEA-SPE-4 Test Simulation  

International Nuclear Information System (INIS)

A small break LOCA event simulation with no high pressure injection system available, known as International Atomic Energy Agency Standard Problem Exercise no. 4 (IAEA-SPE-4), was performed on the PMK-2 integral test facility in Budapest in 1993. This paper analyses the response of the PMK-2 facility, a model of VVER-440 nuclear power plant, using the latest released version MOD3.2.1.2 of the RELAP5 thermal-hydraulic code. After several years of the SPE-4 experiment analyses, many problems have emerged and been studied. Main goal of the present analyses was to study the main influencing parameters for adequate modelling of the hexagonal core channel with 19-rod bundle and phenomena during the core uncovery. Some influencing parameters have been identified, mostly on the primary side, but some also on the secondary side. This is exact simulation of main coolant pump coast down, hydro-accumulators water temperature and connections to the primary ...

1998-06-15

53

American National Standard: design basis for protection of light water nuclear power plants against effects of postulated pipe rupture  

Energy Technology Data Exchange (ETDEWEB)

This standard addresses the design bases for light water reactor, nuclear power plant structures and components essential for the protection of public health and safety from the potential adverse effects of pipe whip, jet impingement, pressurization of compartments outside containment, environmental conditions and flooding associated with a postulated pipe rupture. The design bases for missile protection and the design bases for containment pressurization are not within this standard.

1980-12-31

54

Report of the technical committee meeting 1997 annual workshop on ASSET experience and feedback  

International Nuclear Information System (INIS)

Papers and presentations were made by all participating countries and provided a wide range of perspectives on the use of the ASSET methodology. Generally, the views expressed were positive, however, there were comments on areas were the service could be improved or enhanced. The workshop was divided into three task groups to analyze the self-assessments conducted at Krsko NPP, Slovenia; Dukovany NPP, Czech Republic; and Balakovo NPP, Russian Federation. In addition, they were asked to comment on the recommendations on the ASSET service made by the Consultants' Meeting of 26-30 August 1996 on ''Performance of the IAEA programme on Operational Safety Services''. A presentation was made by Mr. B. Thomas to remind delegates of the ASSET methodologies, and Mr. V. Sivokon demonstrated the latest developments of computer software available for assisting in the plant Self-Assessment process. Refs, figs, tabs.

1997-06-24

55

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 ...

1983-02-01

56

OSHA Hazardous-Chemical Occupational Exposure Standard for laboratories: A new management regulation to ensure employee health. Final report  

Energy Technology Data Exchange (ETDEWEB)

The OSHA's chemical occupational exposure standard for laboratories is an outgrowth of the previously issued Hazard Communication Standard. The standard relieves laboratories from complying with general industry standards but does not require compliance with specific guidelines. The heart of the standard is the creation of a Chemical Hygiene Plan (CHP) in every laboratory. The CHP addresses major issues such as safety equipment and procedures, work practices and training, the designation of a chemical hygiene officer, and the provision of medical consultation and examination for affected employees. This new standard, in effect as of 31 January, 1991, presents yet another regulatory challenge to laboratory managers but also will ensure a safer work environment for laboratory workers.

1991-04-01

57

American National Standard ANSI/ANS-8.15-1983: Nuclear criticality control of special actinide elements  

Energy Technology Data Exchange (ETDEWEB)

The American National Standard, `Nuclear Criticality Safety in Operations with Fissionable Materials Outside Reactors` ANSI/ANS-8.1- 1983 provides guidance for the nuclides [sup 233]U, [sup 235]U, and [sup 239]Pu These three nuclides are of primary interest in out-of-reactor criticality safety since they are the most commonly encountered in the vast majority of operations. However, some operations can involve nuclides other than `U, `U, and `Pu in sufficient quantities that their effect on criticality safety could be of concern. The American National Standard, `Nuclear Criticality Control of Special Actinide Elements` ANSI/ANS-8.`15-1983 (Ref 2), provides guidance for fifteen such nuclides.

1996-12-31

59

The CAMAC Standard  

CERN Document Server

The CAMAC Standard

1972-01-01

60

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

61

Safety and efficacy of botox injection in alleviating post-operative pain and improving quality of life in lower extremity limb lengthening and deformity correction  

UK PubMed Central (United Kingdom)

BackgroundDistraction osteogenesis is the standard treatment for the management of lower limb length discrepancy of more than 3 cm and bone loss secondary to congenital anomalies,...Full Text Available

62

Medical Examinations for Public Safety*  

UK PubMed Central (United Kingdom)

Driving buses in London is an occupation in which the standards of fitness have been defined and in which the frequency of, and clinical reason for, exclusion from the occupation have been recorded.The...Full Text Available

1959-04-01

63

Efficacy and Safety of Low-Molecular-Weight Heparins As An Adjunct to Thrombolysis in Acute ST-Elevation Myocardial Infarction  

UK PubMed Central (United Kingdom)

A 48-hour course of intravenous unfractionated heparin (UFH) is the standard of treatment in conjunction with fibrin-specific thrombolysis in ST-elevation myocardial infarction (STEMI). In recent trials,...Full Text Available

2008-02-01

64

Safety design guide for pipe rupture protection for CANDU 9  

Energy Technology Data Exchange (ETDEWEB)

This safety design guide for pipe rupture protection identifies high-energy systems in which pipe ruptures must be postulated to occur, as well as systems that must be protected from the dynamic effects of such ruptures. Dynamic effects considered in this SDG consist of pipe whip (including missiles generated by pipe ruptures, if any) and jet impingement, Requirements for protection against the dynamic effects of a postulated pipe rupture and method of protection of essential structures, systems and components are specified for these effects. The change status for the regulatory requirements, code and standards should be traced and this safety design guide shall be updated accordingly. 2 tabs., 5 refs. (Author) .new.

1996-03-01

65

American National Standard ANSI/ANS-8.6: Safety in conducting subcritical neutron-multiplication measurements {open_quote}In Situ{close_quote}  

Energy Technology Data Exchange (ETDEWEB)

Safe and economical operations with fissile materials require knowledge of the subcriticality of configurations that arise in material processing, storage, and transportation. Data from critical experiments have been a principal source of information with which to establish safety margins. However, the lower cost and the expediency of performing confirmatory subcritical measurements on the process floor or in the storage vault resulted in much of the early criticality safety guidance being based on subcritical in situ experiments.

1996-10-01

66

International Atomic Energy Agency publications. Publications catalogue 2006 including full details of publications published in 2004-2005 and forthcoming in 2006 and a stocklist of publications published in 2002-2003  

International Nuclear Information System (INIS)

This Publications Catalogue lists all sales publications of the IAEA published in 2004, 2005 and forthcoming in 2006. Most IAEA publications are issued in English, some are also available in Arabic, Chinese, French, Russian or Spanish. This is indicated at the bottom of the book entry. A complete listing of all IAEA priced publications is available on the IAEA's web site: http://www.iaea.org/books

67

Design basis for protection of light water nuclear power plants against effects of postulated pipe rupture  

Energy Technology Data Exchange (ETDEWEB)

This standard addresses the design bases for light water reactor, nuclear power plant structures and components essential for the protection of public health and safety from the potential adverse effects of pipe whip, jet impingement, pressurization of compartments outside containment, environmental conditions and flooding associated with a postulated pipe rupture. The design bases for missile protection and the design bases for containment pressurization are not within this standard.

1981-01-01

68

Safety considerations in the application of tension leg platforms and spar based systems  

Energy Technology Data Exchange (ETDEWEB)

This paper is focused on TLP and Spar technology as applied to floating production applications. In particular, safety considerations as related to classification and certification requirements are addressed. This covers hull structures, marine systems, production facilities and the relevant mooring systems for each platform type from design approval on through construction, installation and ultimately the ongoing maintenance of the platform to acceptable standards throughout its operating life. The experience of the American Bureau of Shipping with these platforms will be utilized in supporting the practical application of classification and regulatory standards to ensure safe operations and concluding that use of such standards in conjunction with an experienced classification society provides a substantial benefit to companies utilizing these technologies. (author)

1998-07-01

69

A structured approach to the assessment of the quality culture in nuclear installation  

International Nuclear Information System (INIS)

INSAG has emphasized that safety culture has two general components: the organizational framework and the attitude of the staff. To develop a structured approach to the assessment of safety culture, we propose that the highly formalized nature of nuclear power plant organizations be exploited. The prime coordinating mechanism of NPP organizations is the standardization of work processes, where a work process is defined as a standardized sequence of tasks designed to achieve a specific goal (an example is the maintenance work process). The predictable nature of work processes is exploited by the Work Process Analysis Model (WPAM) to conduct a systematic analysis that identifies the desirable characteristics of work processes and develops performance measures for their strengths and weaknesses. These can provide a set of tangible characteristics of a good safety culture. It is argued ...

1995-04-01

70

An analysis strategy for safeguards use of optical satellite imagery  

International Nuclear Information System (INIS)

This paper outlines conceptual framework for safeguards remote sensing, and suggests a strategy for overcoming the challenges to full exploitation of all types of optical satellite imagery. Since the introduction of commercial open-source high-resolution satellite imagery in 1999, it has become an important tool for verification of declarations, baseline mapping, detection and monitoring of changes and investigation of undeclared activities. Its use is still relatively restricted, but there is a growing demand for wider satellite reconnaissance support, and the Satellite Image Analysis Unit (SIAU) has recently been expanded in response. For a number of reasons, IAEA safeguards use of satellite imagery is largely based on visual interpretation by experienced image analysts of high-resolution monochromatic imagery to monitor and characterize buildings and structures on safeguards sites. The very wide range of remote sensing capabilities could be more fully exploited. ...

2006-10-16

71

Crux of our work  

Energy Technology Data Exchange (ETDEWEB)

Depicts procedures employed to improve work safety at a mine of the Antratsit association in the Ukrainian SSR, where 1K-101 and 2K-52 cutter loaders are used to extract coal at a depth of 750 m. Some 15-20% of accidents is caused by carelessness or clumsiness. To increase awareness among miners, illuminated signs with slogans relating to work safety have been installed at 15 m intervals in roadways leading to workplaces. A satirical wall newspaper lampoons those who infringe safety regulations. Mining teams with good safety records pass on their experience to others. Public inspectors and public inspections (competitions) also play an important part in ensuring that conditions remain up to standard.

1986-04-01

72

Development of quality assurance requirements as part of the regulatory framework in the United Kingdom  

International Nuclear Information System (INIS)

Within the United Kingdom, the regulatory body having responsibility for the licensing of nuclear installations is the Health and Safety Executive (HSE). The Nuclear Installations Inspectorate (NII) is that part of HSE which administers this function. Discussions on the applicability of quality assurance (QA) to licensed sites began in 1974, and an internal report was published in 1975. In parallel with work going on at the International Atomic Energy Agency (IAEA) to prepare Quality Assurance for Safety in Nuclear Power Plants: A Code of Practice, Safety Series No. 50-C-QA, NII published a second report in 1978 entitled A Guide to the Quality Assurance Programme for Nuclear Power Plants. In 1980, the construction of advanced gas cooled reactors at Heysham 2 and at Torness was licensed, and a condition was attached to the licences requiring the licensees to submit their QA arrangements to the NII for ...

1988-11-07

73

Management of long term radiological liabilities: Stewardship challenges  

International Nuclear Information System (INIS)

The IAEA attaches great importance to the dissemination of information that can assist Member States with the development, implementation, maintenance and continuous improvement of systems, programmes and activities that support the nuclear fuel cycle and nuclear applications, including management of the legacy of past practices and accidents. In this connection, the IAEA has initiated a comprehensive programme of work covering all aspects of environmental remediation: - Technical and non-technical factors, including costs, that influence environmental remediation strategies and pertinent decision making; - Site characterization techniques and strategies; - Assessment of remediation technologies; - Techniques and strategies for post-remediation compliance monitoring; - Special issues such as the remediation of sites with dispersed radioactive contamination or mixed contamination by hazardous and radioactive substances. Experience in Member ...

2006-01-01

74

A Review of the IAEA Vulnerability Assessment Level Scheme: Applicabiliy to DTRA and DOE Programs in the FSU  

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

75

International symposium on nuclear security. Book of extended synopses  

International Nuclear Information System (INIS)

The International Symposium on Nuclear Security took place within a context of international acknowledgement that the threat of nuclear terrorism required dedicated action by the international community, States, industry and others. The Symposium dealt with those issues involved in protecting nuclear and other radioactive material from criminals. It also took place against a backdrop of renewed interest in nuclear technology: increased use of nuclear power, and increased use of radioactive isotopes in medicine and in industry. These are welcome developments, since nuclear energy and technology can indeed contribute to the technological and economic welfare of many countries, without compromising public health or the environment. In this context, security measures should not impede State programmes for peaceful use of nuclear technology. The symposium dealt with (1) the threat of nuclear terrorism and of other nuclear-related criminal acts; (2) international response and cooperation; ...

2003-11-05

76

AIDE: internal dosimetry software.  

Science.gov (United States)

AIDE (Activity and Internal Dose Estimates) is a software for calculating activities in compartments and committed doses due to occupational exposures, and for performing intake and dose estimates using bioassay data. It has been continuously developed and tested for more than 20 years. Its calculation core has been applied in several situations, like performing all dose estimates due to (137)Cs intakes, which occurred during the Goiania accident in 1987; performing quality assurance of the ICRP Task Group on Dose Calculations regarding calculations of activities in compartments and generation of dose coefficients for adults due to intakes by inhalation, ingestion and injection of several radionuclides; and producing the tables of activities in compartments and dose coefficients using the NCRP Wound Model for the NCRP report. It provides several capabilities like performing calculations using modified Human Respiratory Tract Model parameters for the mechanical transport, blood ...

2008-03-12

77

The role of the United States Food Safety and Inspection Service after the Chernobyl accident  

International Nuclear Information System (INIS)

The Food Safety and Inspection Service (FSIS) of the United States Department of Agriculture (USDA) inspects domestic and imported meat and poultry food products to assure the public that they are safe, wholesome, not economically adulterated and properly labeled. The Service also monitors the activities of meat and poultry plants and related activities in allied industries, and establishes standards and approves labels for meat and poultry products. As part of its responsibility, shortly after the Chernobyl accident occurred, FSIS developed a plan to assess this accident's impact on domestically produced and imported meat and poultry

1989-09-01

78

Reflections on a future international convention on safety in radioactive waste management - September 1994  

Energy Technology Data Exchange (ETDEWEB)

This probably is a suitable moment for work to begin on an international Convention in this area, although it is a difficult task. Generally speaking, the RADWASS (Radioactive Waste Safety Standards) Programme has achieved sufficient consensus, and might serve as an important basis for work in relation to the Convention. The Convention should not go into highly technical details since consensus at this level is more difficult at the present moment, although this will undoubtedly be achieved in the medium term. An important element of the Convention should be the regulation of movements of radioactive wastes at international level. (orig./HP)

1995-12-31

79

Regulation of red mud from the alumina industry in Australia  

International Nuclear Information System (INIS)

English 2005 p. 52-59 International Atomic Energy Agency (IAEA) Collier,

2002-09-23

80

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 ...

1993-06-20

81

Hardware standardization for embedded systems  

International Nuclear Information System (INIS)

Reactor Control Division (RCnD) has been one of the main designers of safety and safety related systems for power reactors. These systems have been built using in-house developed hardware. Since the present set of hardware was designed long ago, a need was felt to design a new family of hardware boards. A Working Group on Electronics Hardware Standardization (WG-EHS) was formed with an objective to develop a family of boards, which is general purpose enough to meet the requirements of the system designers/end users. RCnD undertook the responsibility of design, fabrication and testing of boards for embedded systems. VME and a proprietary I/O bus were selected as the two system buses. The boards have been designed based on present day technology and components. The intelligence of these boards has been implemented on FPGA/CPLD using VHDL. This paper outlines the various boards that have been developed with a brief ...

2010-02-01

82

FENDL multigroup libraries  

International Nuclear Information System (INIS)

Selected neutron reaction nuclear data libraries and photon-atomic interaction cross section libraries for elements of interest to the IAEA's program on Fusion Evaluated Nuclear Data Library (FENDL) have been processed into MATXSR format using the NJOY system on the VAX4000 computer of the IAEA. This document lists the resulting multigroup data libraries. All the multigroup data generated are available cost-free upon request from the IAEA Nuclear Data Section. (author). 9 refs.

83

Use plan for demonstration radioactive-waste incinerator  

Energy Technology Data Exchange (ETDEWEB)

The University of Maryland at Baltimore was awarded a grant from the Department of Energy to test a specially modified incinerator to burn biomedical radioactive waste. In preparation for the incinerator, the Radiation Safety Office devised a comprehensive plan for its safe and effective use. The incinerator plan includes a discussion of regulations regarding on-site incineration of radioactive waste, plans for optimum use in burning four principal waste forms, controlled air incineration technology, and standard health physics safety practices; a use plan, including waste categorization and segregation, processing, and ash disposition; safety procedures, including personnel and area monitoring; and methods to evaluate the incinerator's effectiveness by estimating its volume reduction factors, mass and activity balances, and by determining the cost effectiveness of incineration versus ...

1982-04-01

84

3D modelling as a support to thermal-hydraulic safety analyses with standard codes  

Energy Technology Data Exchange (ETDEWEB)

A three-dimensional (3D) thermal-hydraulic model and a numerical procedure for the simulation and analysis of a steady-state, as well as transient operation of nuclear power plant components are presented. A two-fluid approach is applied to modelling of two-phase flow. Thermal-hydraulics of a horizontal steam generator in the WWER 1000 nuclear power plant has been simulated at the full load, steady-state operation. A comparison of the numerical results with data measured at the NPP Novovoronjezh shows good agreement. 3D numerical results can be used in plant design or retrofitting, in nuclear power plant operation and safety analysis and as improvement of existing one-dimensional thermal-hydraulics models of the horizontal steam generator which are assessed by system codes used for the nuclear power plant safety analyses. (author)

1999-07-01

85

3D modelling as a support to thermal-hydraulic safety analyses with standard codes  

International Nuclear Information System (INIS)

A three-dimensional (3D) thermal-hydraulic model and a numerical procedure for the simulation and analysis of a steady-state, as well as transient operation of nuclear power plant components are presented. A two-fluid approach is applied to modelling of two-phase flow. Thermal-hydraulics of a horizontal steam generator in the WWER 1000 nuclear power plant has been simulated at the full load, steady-state operation. A comparison of the numerical results with data measured at the NPP Novovoronjezh shows good agreement. 3D numerical results can be used in plant design or retrofitting, in nuclear power plant operation and safety analysis and as improvement of existing one-dimensional thermal-hydraulics models of the horizontal steam generator which are assessed by system codes used for the nuclear power plant safety analyses. (author)

1999-04-19

86

The KSNPP risk-effect analysis of the digital safety-critical systems  

Energy Technology Data Exchange (ETDEWEB)

The study was performed for evaluating the risk effect of digital systems on the total plant. Based on risk monitor, a fault tree model for the Korean Standard Nuclear Power Plants (KSNPP), we integrate the fault-tree models for Digital Plant Protection System (DPPS) and Digital Engineered SaFety Actuation System (DESFAS) which are the most important safety-critical I and C systems in the KSNPP. In this study, however, three important factors (the probabilities of manual actuation failure, the software failure probability, and the watchdog timer fault coverage) are treated as the variables of the sensitivity study because quantification methodologies for these factors are not developed yet. Not only the unavailability of digital safety-critical system itself, but also the risk effect of digital systems on the total plant should be assessed to prove the safety of digital systems. The ...

2004-02-01

87

Report of study group 4.3 ''pipeline integrity management and safety''  

Energy Technology Data Exchange (ETDEWEB)

This report highlights the Pipeline integrity Management methods being implemented by gas companies. These aim at maintaining the current high safety level, prevent major hazards, ensure the integrity of the pipeline and protect people and environment in the vicinity of the pipeline in the most cost effective way. It should be noticed that Pipeline Integrity Management aspects, technical and organisational, are included in the more general framework of the Safety Management System. Currently, more and more gas companies implement such a system on the basis of standards like ISO 9000 and so on. In this way, the report shows how practices of Pipeline Integrity Management are continually developing in order to adapt to their environment, and to improve performance. Past experience and imminent developments show that Pipeline Integrity Management is a flexible and efficient approach to improve safety in the ...

2000-07-01

88

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 moderator without the availability of shutdown systems. Logics ...

2006-11-13

89

Natural gas pipeline safety in residential areas served by master meters. a handbook  

Science.gov (United States)

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

90

Development of regulatory techniques for operational performance evaluation of nuclear power plants  

Energy Technology Data Exchange (ETDEWEB)

In this study, the state-of-the art for estimating LERF is considered for the regulatory risk-informed decisions. The consideration is mainly focused on (1) the relationship between Level 2 PSA and LERF evaluation methodology, (2) the standard requirements in terms of modeling preparation and the acceptance criteria based on the application capability II of ASME PRA standard, and (3) some pending issues for developing and proposing a simplified LERF model. This study is preliminarily presented and will be updated for establishing detailed evaluation scheme of extended MPAS (multi-purpose probabilistic analysis of safety) model and preparing the technical basis.

2006-01-15

91

Analysis of Elements in The Baltic Sea Sediment by Using Gamma Spectrometry  

International Nuclear Information System (INIS)

We have done analysis of elements in the Baltic sea sediment by using gamma spectrometry in neutron activation analysis Goal of the analysis is to determine the rate of morsel elements which is contained in the Baltic sea sediment. Sample of the Baltic sea Sediment (IAEA-SED-1), Standard of Reference Material (SRM) 1646 Estuarine Sediment and Standard Ce, Fe, Sc, and Co are put into vial of capsule rabbit, then irradiated together for 30 minutes in rabbit facility Multi Purpose Reactor at power of 25 MW and then cooled for one week. Next sample, standard, and SRM which have irradiated, each is cut for 30 minutes using gamma spectrometer. Result of analysis of rate of elements Ce, Fe, Sc and Co in the baltic sea sediment successively equal to 141.20 ppm, 5.91 %, 14.88 ppm, and 19.59 ppm. Result of analysis in SRM Estuarine sediment successively equal to 96.60 ppm, 3.21 %, 10.25 ppm, and 9.63 ppm. Result ...

2007-04-01

92

Development of reliability-based design and assessment standards for onshore gas transmission pipelines  

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

93

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.

94

Development of technical information basis of aging management for nuclear power plants  

International Nuclear Information System (INIS)

In order to implement effective safety regulations on aging management for reactor facilities etc., the information on important technology issues, the latest technical knowledge including evaluation technology, test and research outcomes, related codes and standards, regulation information, operation experiences such as accidents and trouble, etc. with respect to aging-induced deterioration in and outside Japan and in other industries, were collected, organized and evaluated. (author)

2007-08-01

95

CRC handbook of biological effects of electromagnetic fields  

Energy Technology Data Exchange (ETDEWEB)

This book presents the current knowledge about the effects of electromagnetic fields on living matter. The three-part format covers dielectric permittivity and electrical conductivity of biological materials; effects of direct current and low frequency fields; and effects of radio frequency (including microwave) fields. The parts are designed to be consulted independently or in sequence, depending upon the needs of the reader. Useful appendixes on measurement units and safety standards are also included.

1986-01-01

96

Annual report on heavy water reactor fuel fabrication  

Energy Technology Data Exchange (ETDEWEB)

The CANDU-type nuclear fuel localization project started in 1981, and mass-production system completed in 1987 through the pilot scale demonstration of fuel manufacturing. Since the completion of the mass-production system, about 24,000 fuel bundles (450 ton-U) had been delivered to Wolsung Nuclear Power Plant by the end of 1992, according to the fuel supply contracts with KEPCO. The superiority of KAERI-made nuclear fuel has been demonstrated by having achieved the highest utilization factor in the world in 1992. In 1993, as contracted, 4,824 fuel bundles well fabricated and delivered to Wolsung Nuclear Power Plant. The process improvement, quality control, safety management, safeguards of nuclear materials and various kinds of audits have also been performed in the course for fuel manufacturing. Especially in 1993, the difficulties of the reduction of participating work-force were overcome by improving the manufacturing techniques, and raising the efficiency of ...

1994-03-01

97

Accident analysis in research reactors  

International Nuclear Information System (INIS)

Full text: Full text: The incomplete understanding of the complex mechanisms connected with the interaction between thermal-hydraulic and neutron kinetics still challenges the design and the operation of nuclear reactors and imposes the adoption of conservatism in the evaluation of safety limits. The recent availability of powerful computer and computational techniques together with the continuing increase in operational experience suggests the revisiting of those areas and the identification of design/operation requirements that can be relaxed. So far, almost all of the safety analyses of research reactors have been performed using conservative computational tools such as channel codes but, nowadays, the application of Best-Estimate (BE) methods constitutes a real necessity. The global aim of the current work is an attempt to apply the best-estimate system thermal-hydraulic code Relap5. For this purpose, the generic IAEA ...

2006-10-15

98

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 ...

1991-07-01

99

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 ...

1991-07-01

100

Occupational health priorities for health standards: the current NIOSH approach.  

Science.gov (United States)

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 ...

1979-05-01

101

The Efforts to Utilize High-Temperature Melting Technologies for ILLW and the Development of Guidelines for their Technical Assessment  

Energy Technology Data Exchange (ETDEWEB)

A couple of domestic institutions have been investigating the application of vitrification technology to treat low- and intermediate-level radioactive wastes in Korea. In the case that such investigations prove to be successful, it is expected that commercial vitrification plants will be constructed. The safety insuring on vitrification plants could not be compatible with criterion on radioactive waste management because the facilities are at high temperature and contain a variety of accommodations for the exhaust gases and residual products. Therefore, it is necessary to suggest a new strategy or modifications of criterion of radioactive waste management on considerations related with the vitrification technology. In order to ensure the safety of vitrification plants, a technical guideline or standard for design and operation of vitrification plants must be established too. A study on the safety ...

2003-02-25

102

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

103

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

104

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 ...

2009-10-27

105

The Experience of Cooperation with IAEA new approach for Spent Fuel Transfer Campaign at CANDU Reactors  

Energy Technology Data Exchange (ETDEWEB)

It was agreed that both of the Republic Of Korea (ROK) and the International Atomic Energy Agency (IAEA) cooperate with the new approach using the Unattended Monitoring Systems (UMS), the mailbox declaration and the short notice inspections, which can decrease the agency inspection efforts and operator' s burden. As a result of the positive cooperation of ROK for applying new approach, the IAEA could accomplish a successful implementation of new safeguards approach during last transfer campaigns at Wolsung site. As of the end of Feb. 2007, the IAEA installed the UMS at Wolsung units 2, 3 and 4. The transfer campaigns at Wolsung units 2 and 4 are performing from April, 2007. The IAEA will install the UMS at Wolsung unit 1 by the end of 2007. Then agency will inspect all of transfer campaign at Wolsung units by using new approach with UMS, mailbox declaration and SNI. It is based on the SSAC full ...

2007-07-01

106

The Experience of Cooperation with IAEA new approach for Spent Fuel Transfer Campaign at CANDU Reactors  

International Nuclear Information System (INIS)

It was agreed that both of the Republic Of Korea (ROK) and the International Atomic Energy Agency (IAEA) cooperate with the new approach using the Unattended Monitoring Systems (UMS), the mailbox declaration and the short notice inspections, which can decrease the agency inspection efforts and operator' s burden. As a result of the positive cooperation of ROK for applying new approach, the IAEA could accomplish a successful implementation of new safeguards approach during last transfer campaigns at Wolsung site. As of the end of Feb. 2007, the IAEA installed the UMS at Wolsung units 2, 3 and 4. The transfer campaigns at Wolsung units 2 and 4 are performing from April, 2007. The IAEA will install the UMS at Wolsung unit 1 by the end of 2007. Then agency will inspect all of transfer campaign at Wolsung units by using new approach with UMS, mailbox declaration and SNI. It is based on the SSAC full ...

2007-05-10

107

The U.S. Support Program to IAEA Safeguards - How It Works  

Energy Technology Data Exchange (ETDEWEB)

The U.S. Support Program to International Atomic Energy Agency (IAEA) Safeguards (USSP) was established in 1977 to transfer US technology and expertise to assist the IAEA Department of Safeguards because its limited budget and scope would not allow for R&D activities and the procurement of specialized or customized equipment. Over the years, the USSP and the Department of Safeguards have worked together continuously to develop and improve processes for requesting, selecting, and managing projects that support the Safeguards verification mission. This paper will discuss the main USSP processes for accepting and processing Safeguards requests, and managing and reporting task progress.

2008-07-13

108

Perception of anesthesia safety and postoperative symptoms of surgery patients in Ho Chi Minh City, Vietnam: a pioneering trial of postoperative care assessment in a developing nation  

British Library Electronic Table of Contents (United Kingdom)

Objectives Vietnamese patients? views on healthcare are changing as surgical interventions become more commonplace, but their views on perioperative care have remained largely unstudied during this period of rapid change. This study assesses Vietnamese patients? impression of anesthesia safety and postoperative pain in relation to clinical outcomes with the aim of improving patient-centered perioperative care. Methods The study cohort consisted of 180 hospitalized patients who were followed for 24?h following abdominal surgery. The assessments of these patients on the use of anesthesia and postoperative pain were measured by means of a 5-point Likert scale survey. Perioperative events were recorded on standardized forms by medical staff. The relationship between relevant factors affecting ...

2010-01-01

109

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

110

An estimation of an operators action time by using the MARS code in a small break LOCA without a HPSI for a PWR  

British Library Electronic Table of Contents (United Kingdom)

To estimate the success criteria of an operators action time for a probabilistic safety/risk assessment (PSA/PRA) of a nuclear power plant, the information from a safety analysis report (SAR) and/or that by using a simplified simulation code such as the MAAP code has been used in a conventional PSA. However, the information from these is often too conservative to perform a realistic PSA for a risk-informed application. To reduce the undue conservatism, the use of a best-estimate thermal hydraulic code has become an essential issue in the latest PSA and it is now recognized as a suitable tool. In the same context, the `ASME PRA standard' also recommends the use of a best-estimate code to improve the quality of a PSA. In Korea, a platform to use a best-estimate thermal hydraulic code called ...

2007-01-01

111

The Status of Korea-IAEA Enhanced Cooperation on the Spent Fuel Transfer to Dry Storage in CANDU Reactors  

Energy Technology Data Exchange (ETDEWEB)

Based on the enhanced cooperation between Republic of Korea (ROK) and International Atomic Energy Agency (IAEA), IAEA installed new safeguards equipment (Unattended Monitoring System, UMS) at Wolsung unit 2 on January, 2005. The UMS was utilized in parallel with traditional human surveillance during the transfer campaign of Wolsung unit 2 (7 March - 22 July). Installation of UMS at all Wolsung units will be decided on the basis of the result of this test. The transfer campaign with UMS at Wolsung units 2 and 4 was started from September 1, 2006 at the same time. Implementation of UMS to the transfer campaign in Wolsung site will be considerably reduced the IAEA's inspection effort and burden of operator.

2006-07-01

112

The Status of Korea-IAEA Enhanced Cooperation on the Spent Fuel Transfer to Dry Storage in CANDU Reactors  

International Nuclear Information System (INIS)

Based on the enhanced cooperation between Republic of Korea (ROK) and International Atomic Energy Agency (IAEA), IAEA installed new safeguards equipment (Unattended Monitoring System, UMS) at Wolsung unit 2 on January, 2005. The UMS was utilized in parallel with traditional human surveillance during the transfer campaign of Wolsung unit 2 (7 March - 22 July). Installation of UMS at all Wolsung units will be decided on the basis of the result of this test. The transfer campaign with UMS at Wolsung units 2 and 4 was started from September 1, 2006 at the same time. Implementation of UMS to the transfer campaign in Wolsung site will be considerably reduced the IAEA's inspection effort and burden of operator.

2006-11-02

114

Nuclear Power Reactors in the World. 2009 Ed  

International Nuclear Information System (INIS)

This is the twenty-ninth edition of Reference Data Series No. 2, Nuclear Power Reactors in the World, which is published once per year, and presents the most recent reactor data available to the IAEA. It contains the following summarized information: - General information as of the end of 2008 on power reactors operating or under construction, and shut down; - Performance data on reactors operating in the Agency's Member States, as reported to the IAEA. The IAEA's Power Reactor Information System (PRIS) is a comprehensive data source on nuclear power reactors in the world. It includes specification and performance history data of operating reactors as well as reactors under construction or reactors being decommissioned. PRIS data are collected by the IAEA through the designated national correspondents of Member States

115

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 ...

2004-07-01

116

Understanding the mismatch between the demands of risk assessment and practice of scientists ? The case of Deca-BDE  

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

117

Supplementary quality assurance requirements for installation, inspection and testing of mechanical equipment and systems for the construction phase of nuclear power plants - reaffirmed 1980  

International Nuclear Information System (INIS)

This standard provides requirements and guidelines for installation, inspection and testing activities that assure the quality of important mechanical parts of a nuclear power plant not covered by the ASME Boiler and Pressure Vessel Code, Section III, during construction. These parts include those mechanical systems and components whose satisfactory performance is required: for the plant to operate reliably; 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 requirements of this standard deal with the protection and control necessary to assure that the requisite quality of those important parts of the plant are preserved from the time items are removed from storage or receiving until they are incorporated into the plant up to but not including fuel loading for PWR plants and the completion of cold functional ...

118

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 ...

2006-04-03

119

Radiation: how safe is safe?  

International Nuclear Information System (INIS)

Recent research findings of epidemiologist Alice Stewart suggest that nuclear workers may be at risk of contracting cancer even though their measured occupational doses fall within current safety standards. It is argued that these standards are inappropriate as they are based on extrapolations of studies on survivors of the Hiroshima and Nagasaki explosions. These individuals received single doses of radiation, whereas today's nuclear industry personnel are exposed to low-level ionizing radiation over the length of their working lives. Stewart's team linked low dose occupational exposure to ionizing radiation with an increased risk of cancer in respiratory, digestive and blood-forming tissues. The nuclear industry and United States government agencies hotly contest these assertion with their potentially damaging political and economic consequences. (UK).

1993-05-01

120

Radiation: how safe is safe  

Energy Technology Data Exchange (ETDEWEB)

Recent research findings of epidemiologist Alice Stewart suggest that nuclear workers may be at risk of contracting cancer even though their measured occupational doses fall within current safety standards. It is argued that these standards are inappropriate as they are based on extrapolations of studies on survivors of the Hiroshima and Nagasaki explosions. These individuals received single doses of radiation, whereas today's nuclear industry personnel are exposed to low-level ionizing radiation over the length of their working lives. Stewart's team linked low dose occupational exposure to ionizing radiation with an increased risk of cancer in respiratory, digestive and blood-forming tissues. The nuclear industry and United States government agencies hotly contest these assertion with their potentially damaging political and economic consequences. (UK).

1993-05-15

121

Ideal MHD stability properties of pressure-driven modes in low shear tokamaks  

Energy Technology Data Exchange (ETDEWEB)

The role of shear in determining the ideal MHD stability properties of tokamaks is discussed. In particular, we assess the effects of low shear within the plasma upon pressure-driven modes. The standard ballooning theory is shown to break down, as the shear is reduced and the growth rate is shown to be an oscillatory function of n, the toroidal mode number, treated as a continuous parameter. The oscillations are shown to depend on both the pressure and safety-factor profiles. When the shear is sufficiently weak, the oscillations can result in bands of unstable n values which are present even when the standard ballooning theory predicts complete stability. These instabilities are named ''infernal modes.'' The occurrence of these instabilities at integer n is shown to be a sensitive function of q-axis, raising the possibility of a sharp onset as plasma parameters evolve. 20 refs., 31 figs.

1987-03-01

122

From Circle of Poison to Circle of Virtue: Pesticides, Export Standards and Kenya's Green Bean Farmers  

British Library Electronic Table of Contents (United Kingdom)

Abstract In response to growing consumer concerns, developed-country governments have reduced permissible pesticide residue levels in food. Many food retailers have developed even more stringent private food safety protocols relating to pesticide use, storage and disposal and passed them on to their suppliers. Exporters in developing countries enforce these developed-country pesticide standards (DC-PS) by subjecting farmers to close monitoring. This study explores the effects of enforcing compliance with DC-PS on smallholder farmers' pesticide-related health costs. Results suggest that enforcing DC-PS encourages farmers to use protection that lowers pesticide-induced morbidity, hence reducing farmers' health costs from pesticide exposure. The study concludes that there are health benefits ...

2010-01-01

123

A comparative study of standard versus laparoendoscopic single-site surgery (LESS) totally extraperitoneal (TEP) inguinal hernia repair  

British Library Electronic Table of Contents (United Kingdom)

Background Laparoscopic inguinal hernia repair has been around since the 1990s. A novel surgical approach known as laparoendoscopic single-site surgery (LESS) has been developed to reduce the port-related morbidities and improve the cosmetic outcomes of laparoscopic surgery, including totally extraperitoneal (TEP) inguinal hernia repair. The aim of the present study was to evaluate the safety and feasibility of the LESS TEP technique for inguinal hernia repair and compare the outcomes with the standard TEP approach. Methods Between January and May 2009, 54 consecutive healthy patients (48 men and 6 women) underwent LESS TEP inguinal hernia repair at our institute. All procedures were performed using our homemade single port for simultaneous passage of the laparoscope and instruments. The p...

2011-01-01

124

Storage of hazardous substances in bonded warehouses  

International Nuclear Information System (INIS)

A variety of special regulations exist in Costa Rica for registration and transport of hazardous substances; these set the requirements for entry into the country and the security of transport units. However, the regulations mentioned no specific rules for storing hazardous substances. Tax deposits have been the initial place where are stored the substances that enter the country.The creation of basic rules that would be regulating the storage of hazardous substances has taken place through the analysis of regulations and national and international laws governing hazardous substances. The regulatory domain that currently exists will be established with a field research in fiscal deposits in the metropolitan area. The storage and security measures that have been used by the personnel handling the substances will be identified to be putting the reality with that the hazardous substances have been handled in tax deposits. A rule base for the storage of hazardous substances in tax deposits ...

125

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 ...

1997-07-01

126

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 operation ...

2002-09-06

127

Implementation strategies and tools for condition based monitoring at nuclear power plants  

International Nuclear Information System (INIS)

There is now an acute need to optimize maintenance to improve both reliability and competitiveness of nuclear power plant operation. There is an increasing tendency to move from the preventive (time based) maintenance concept to one dependent on plant and component conditions. In this context, various on-line and off-line condition monitoring and diagnostics, nondestructive inspection techniques and surveillance are used. Component selection for condition based maintenance, parameter selection for monitoring condition, evaluation of condition monitoring results are issues influencing the effectiveness of condition based maintenance. All these selections of components and parameters to be monitored, monitoring and diagnostics techniques to be used, acceptance criteria and trending for condition evaluation, and the economic aspect of predictive maintenance and condition monitoring should be incorporated into an integrated, effective condition based maintenance programme, which is part of ...

2009-01-01

128

Criticality calculations of the fixed bed nuclear reactor  

Energy Technology Data Exchange (ETDEWEB)

The Fixed Bed Nuclear Reactor (FBNR) is a small 40 MWe reactor based on the Pressurized Water Reactor (PWR) technology. FBNR is an integrated primary circuit and simple in design. It has the characteristics of being small, modular, proliferation resistant, inherently safe and passively cooled reactor with reduced adverse environmental impact. It utilizes the fuel designed for high temperature reactors operating in a relatively low temperature of PWR environment The 15 mm diameter spherical fuel elements are made of TRISO type microspheres embedded in graphite and cladded by SiC. The coolant flow transfers them from the fuel chamber into the core and become fixed forming a suspended core. Any accident signal will cut off the power to the coolant pump causing a stop in the flow. This results in making the fuel elements fall out of the reactor core by the force of gravity and return into the fuel chamber where they are passively cooled under subcritical condition. Therefore, the ...

2007-07-01

129

Low Power and Shutdown Risk Assessment Benchmarking Study  

Science.gov (United States)

(B204)Probabilistic risk assessment (PRA) insights are now used by the United States Nuclear Regulatory Commission (USNRC) to confirm the level of safety for plant operations and to justify changes in nuclear power plant operating requirements, both on an exception basis and as changeds to a plant's licensing basis. This report examines qualitative and quantitative risk assessments during shutdown plant states, providing feedback to utilities in the use of qualitative models for outage risk management, and also providing input to the development of the American Nuclear Society (ANS) Low Power and Shutdown PRA Standard.

2002-12-15

130

Low Power and Shutdown Risk Assessment Benchmarking Study  

Energy Technology Data Exchange (ETDEWEB)

(B204)Probabilistic risk assessment (PRA) insights are now used by the United States Nuclear Regulatory Commission (USNRC) to confirm the level of safety for plant operations and to justify changes in nuclear power plant operating requirements, both on an exception basis and as changeds to a plant's licensing basis. This report examines qualitative and quantitative risk assessments during shutdown plant states, providing feedback to utilities in the use of qualitative models for outage risk management, and also providing input to the development of the American Nuclear Society (ANS) Low Power and Shutdown PRA Standard.

2002-12-15

131

High Exposure Facility Technical Description  

Energy Technology Data Exchange (ETDEWEB)

The High Exposure Facility is a collimated high-level gamma irradiator that is located in the basement of the 318 building. It was custom developed by PNNL back in 1982 to meet the needs for high range radiological instrument calibrations and dosimeter irradiations. At the time no commercially available product existed that could create exposure rates up to 20,000 R/h. This document is intended to pass on the design criteria that was employed to create this unique facility, while maintaining compliance with ANSI N543-1974, "General Safety Standard for Installations Using Non-Medical X-Ray and Sealed Gamma-Ray Sources, Energies up to 10 MeV."

2008-02-12

132

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

133

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 (SMDB) is to exchange ...

2010-10-01

134

An analysis of PZR and related system design features for KNGR  

Energy Technology Data Exchange (ETDEWEB)

The development of KNGR (Korean Next Generation Reactor) is now in progress. KAERI is developing KNGR which is a advanced active PWR (pressurized water reactor) and 1350 MW electric capacities and is by based on UCN(Ulchin) 3 and 4 nuclear power plant which is a Korean standard PWR. In this report, the PZR (pressurizer) and Related System Design Features for KNGR which include PZR volume, PPCS (pressurizer safety valve)were analyzed. First, the Design Parameters between KNGR compared to UCH 3 and 4 were compared, and second, advanced design features of KNGR compared to UCN 3 and 4 were analyzed. After the present analysis, it has been concluded that the safety margins for the PZR level and pressure of KNGR were more increased by the larger PZR volume than those of UCN 3 and 4, for PZR minimum water level at reactor/turbine trip and PZR maximum pressure at LOCV(loss of condenser vacuum) of KNGR were higher and lower, ...

1995-12-01

135

The operating experience for Wolsung Unit 3 commissioning  

International Nuclear Information System (INIS)

This is a slide-based oral presentation given to the COG/IAEA: Fifth technical committee meeting on 'Exchange of operating experience of pressurized heavy water reactors' held in Mangalia, Romania on 7-10 September 1998. Since energization of Wolsung Unit 3 station service transformer on July 12, 1996 a line of initial test program was conducted as follows: 1. ILRT/SIT; 2. Pre-operational and Hot Functional testing with a Light Water and without Fuel in Systems; 3. Load D_2O in Moderator System; 4. Initial fuel loading; 5. Load D_2O in PHT System; 6. Hot Functional Testing with Heavy Water and Fuel in Systems; 7. Criticality and Low Power Physics Testing; 8. Power Ascension Test and, then finally, phase-D test; the plant acceptance test was accomplished after having a Mini-Overhaul to prepare for Commercial Operation. These documents contain not only both overall introduction of commissioning and the first TBN rolling and Synchronization test performed in Hot ...

1998-09-07

136

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 companies should assess ...

2005-07-01

137

Secure data communication for safeguards implementation  

International Nuclear Information System (INIS)

Full text: Secure, reliable and cost-effective communications are becoming an increasingly important tool for safeguards verification. This trend began with the initiation of remote monitoring implementation, where secure and cost effective data communications were required both to satisfy the confidentiality requirements of Member States and in order to meet the rigorous data authenticity requirements which allow the International Atomic Energy Agency (IAEA) to draw credible and independent conclusions. In addition, the implementation of additional protocols and integrated safeguards increases the importance of information (obtained in the course of an inspection, visit, complementary access or design information verification) being analyzed and corroborated with other information sources stored at IAEA Headquarters or Regional Offices, often while the inspector is still on-site. This requires the capability of enabling the inspector, wherever ...

2006-10-16

138

Overview of IAEA year 2000 activities in the Department of Safeguards  

International Nuclear Information System (INIS)

The IAEA Department of Safeguards established a project in 1996 for the year 2000 (Y2K) conversion activities. This project covered assessment, conversion and testing of the software applications, instrument evaluation software, embedded systems and Personal Computer (PC) hardware attached to various equipment. Significant progress has been made in converting the applications and instruments to be year 2000 compliant. At the same time Member states have made an effort as well in converting the systems used jointly at the facilities

1999-02-01

139

Korea-IAEA Unattended Safeguards Approach on the Spent Fuel Transfer to Dry Storage in Wolsung NPP  

Energy Technology Data Exchange (ETDEWEB)

The field trial of an unattended monitoring system for SF transfer verification ended in June 2005. The system is aiming to improve the safeguards measures applied during SF transfers and reduce inspection effort currently required by the Operator, NNCA and the IAEA. They were reviewed based on its technical performance and other issues in this paper.

2006-07-01

140

Korea-IAEA Unattended Safeguards Approach on the Spent Fuel Transfer to Dry Storage in Wolsung NPP  

International Nuclear Information System (INIS)

The field trial of an unattended monitoring system for SF transfer verification ended in June 2005. The system is aiming to improve the safeguards measures applied during SF transfers and reduce inspection effort currently required by the Operator, NNCA and the IAEA. They were reviewed based on its technical performance and other issues in this paper.

2006-05-25

141

IAEA Nuclear Security Programme Combating Nuclear Terrorism  

International Nuclear Information System (INIS)

IAEA Plans of activities include, General Conference in September 2001 which reviewed activities relevant to preventing nuclear terrorism and proposed master plan. The Board of Governors approved new Nuclear Security Plan for the next four years. Three activity areas are; - needs assessment, analysis and coordination, prevention and detection and response.

2010-05-10

142

Hungarian experience in using the IAEA planning methodologies  

International Nuclear Information System (INIS)

The Hungarian Power Companies Ltd. has been using the IAEA planning methodologies since 1985 when it acquired the WASP model. Since then this model has been applied on a regular basis to determine the least cost expansion plan of the power generating system of the country. This report describes this experience as well as the application of the WASP model for other types of studies. (author).

1997-09-01

143

NWIS MEASUREMENTS FOR URANIUM METAL ANNULAR CASTINGS  

Energy Technology Data Exchange (ETDEWEB)

This report describes measurements performed with annular uranium metal castings of different enrichments to investigate the use of {sup 252}Cf-source-driven noise analysis measurements as a means to quantify the amount of special nuclear material (SNM) in the casting. This work in FY 97 was sponsored by the Oak Ridge Y-12 Plant and the DOE Office of Technology Development Programs. Previous measurements and calculational studies have shown that many of the signatures obtained from the source-driven measurement are very sensitive to fissile mass. Measurements were performed to assess the applicability of this method to standard annular uranium metal castings at the Oak Ridge Y-12 plant under verification by the International Atomic Energy Agency (IAEA) using the Nuclear Weapons Identification System (NWIS) processor. Before the measurements with different enrichments, a limited study of source-detector-casting moderator configurations was ...

1998-03-13

144

Dosimetry audit on the accuracy of 192Ir brachytherapy source strength determinations in Sweden  

Energy Technology Data Exchange (ETDEWEB)

The absorbed dose delivered to the patient in brachytherapy is directly proportional to the source strength in terms of the reference air-kerma rate (RAKR). Verification of this quantity by the hospitals is widely recognized as an important part of a quality assurance program. An external audit was performed on behalf of the Secondary Standard Dosimetry Laboratory at the Swedish Radiation Protection Authority (SSI). The aim was to investigate how accurately the source-strength in 192Ir brachytherapy is determined at Swedish hospitals. The SSI reference well-type ion chamber and calibrated equipment were used to measure the RAKR of an 192Ir source in each of the 14 Swedish afterloading units. Comparisons with values determined by vendors and hospitals were made. Agreement in values of RAKR as determined by SSI, hospitals and vendors were in all cases within the +-3% uncertainty (at a coverage factor of k=2), typically guaranteed by the vendors. The good agreement ...

2007-11-15

145

Development of an irradiation system for a small size continuous run multipurpose gamma irradiator  

International Nuclear Information System (INIS)

The Radiation Technology Center from IPEN-CNEN/SP, Brazil, developed a revolutionary design and national technology, a small-sized continuous run and multipurpose industrial gamma irradiator, to be used as a demonstration facility for manufacturers and contract service companies, which need economical and logistical in-house irradiation system alternatives. Also, to be useful for supporting the local scientific community on development of products and process using gamma radiation, assisting the traditional and potential users on process validation, training and qualification of operators and radioprotection officers. The developed technology for this facility consists of a continuous tote box transport system, comprising a single concrete vault, where the automated transport system of products inside and outside of the irradiator utilizes a rotating door, integrated with the shielding, avoiding the traditional maze configuration. Covering 76 m"2 of floor area, the irradiator design is ...

146

Development of quality assurance requirements - an international comparison  

International Nuclear Information System (INIS)

Total quality management strategy and the worldwide introduction of the DIN/ISO 9000 (EN 29 000) series of standards have given new impetus to traditional quality assurance. The most important change must surely be seen in the holistic approach of total quality management and its strict orientation towards customer requirements and satisfaction. International codes and standards for the nuclear industry will also have to be brought into line as part of the process of harmonizing quality assurance system standards. One possible approach is simply to specify a supplementary 'delta' of nuclear-specific requirements to be appended to the broad range of conventional requirements. It is a particular feature of quality-assured procedures in Germany that product and/or component related quality requirements and quality verifications are defined in the specifications of the architect engineer so that full implementation of the ...

147

Study of the inorganic constituents in different species of Casearia medicinal plant collected in distinct regions of the Atlantic Forest, SP State, Brazil; Estudo sobre os constituintes inorganicos presentes em diferentes especies da planta medicinal do genero Casearia coletadas em regioes distintas da Mata Atlantica, SP  

Energy Technology Data Exchange (ETDEWEB)

The use of medicinal plants in the treatment of diseases has increased significantly in the last years, as has research concerning chemical characterization of these plants. In this study, inorganic constituents were determined in leaves and in extracts from three medicinal plant species of the Casearia genus (C. sylvestris, C. decandra and C. obliqua) collected in distinct regions of the Atlantic Forest, SP. The elemental compositions of the soils in which these plants were grown were also determined. Traditionally, these plants are used due to their antiinflammatory, antiacid, antiseptic and cicatrizing properties. The antiulcer and the antitumor activities of the Casearia genus and its capacity to neutralize snake and bee venoms, have also been scientifically confirmed. The analytical methodology used was neutron activation analysis. Long and short irradiation periods of the samples and the standards were carried out at IPEN's IEA-R1 nuclear research ...

2006-07-01

148
149

Annual book of ASTM standards  

CERN Document Server

Annual book of ASTM standards

1976-01-01

150

XML  

Indian Academy of Sciences (India)

designed to work with companion standards ...

151

IAEA and nuclear forensics  

International Nuclear Information System (INIS)

Nuclear forensics can provide information about the history, intended use and potentially the origin of nuclear or radioactive material. For these reasons, it is an important tool for improving nuclear security and combating illicit trafficking of nuclear and other radioactive materials. The IAEA is currently working on enhancing knowledge, techniques, procedures and cooperation in the field of nuclear forensics. Some of the work currently being undertaken by the IAEA includes the development of a five day training workshop on basic methods for radiological crime scene activities, to ensure adequate control of evidence, including for nuclear forensics purposes, a coordinated research project on the application of nuclear forensics in illicit trafficking, and a proposal for international cooperation with nuclear forensics databases and the development of guidelines for establishing databases. Nuclear forensics will continue to be an important ...

152

Safety evaluation of Propionibacterium freudenreichii ET-3 culture.  

Science.gov (United States)

Propionibacterium freudenreichii ET-3 culture, a cell-free product of whey fermentation using P. freudenreichii ET-3 (7025), has been shown to promote the growth of Bifidobacteria through the action of 1,4-dihydroxy-2-naphthoic acid (DHNA), and therefore, has potential use in the food and supplement industries. Although currently used as a food ingredient in Japan, the safety of this novel ingredient has not been previously evaluated through traditional toxicity testing. Therefore, here we report the results of standard toxicological testing performed on P. freudenreichii ET-3 culture. In a 4-week oral toxicity study, administration of 6000mg/kg body weight/day P. freudenreichii ET-3 culture was without compound-related adverse effects on clinical signs, body weights, food consumption, ophthalmology, hematology, clinical chemistry, urinalysis, organ weights, and gross and microscopic findings in male and female Sprague-Dawley rats. Furthermore, ...

2011-03-22

153

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 ...

1992-03-01

154

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 ...

1992-03-01

155

An estimation of an operator's action time by using the MARS code in a small break LOCA without a HPSI for a PWR  

International Nuclear Information System (INIS)

To estimate the success criteria of an operator's action time for a probabilistic safety/risk assessment (PSA/PRA) of a nuclear power plant, the information from a safety analysis report (SAR) and/or that by using a simplified simulation code such as the MAAP code has been used in a conventional PSA. However, the information from these is often too conservative to perform a realistic PSA for a risk-informed application. To reduce the undue conservatism, the use of a best-estimate thermal hydraulic code has become an essential issue in the latest PSA and it is now recognized as a suitable tool. In the same context, the 'ASME PRA standard' also recommends the use of a best-estimate code to improve the quality of a PSA. In Korea, a platform to use a best-estimate thermal hydraulic code called the MARS code has been developed for the PSA of the Korea standard nuclear power plant (KSNP). This study has ...

2007-04-01

156

An estimation of an operator's action time by using the MARS code in a small break LOCA without a HPSI for a PWR  

Energy Technology Data Exchange (ETDEWEB)

To estimate the success criteria of an operator's action time for a probabilistic safety/risk assessment (PSA/PRA) of a nuclear power plant, the information from a safety analysis report (SAR) and/or that by using a simplified simulation code such as the MAAP code has been used in a conventional PSA. However, the information from these is often too conservative to perform a realistic PSA for a risk-informed application. To reduce the undue conservatism, the use of a best-estimate thermal hydraulic code has become an essential issue in the latest PSA and it is now recognized as a suitable tool. In the same context, the 'ASME PRA standard' also recommends the use of a best-estimate code to improve the quality of a PSA. In Korea, a platform to use a best-estimate thermal hydraulic code called the MARS code has been developed for the PSA of the Korea standard nuclear power plant ...

2007-04-15

157

Progress report within the series of GRS-F progress reports on reactor safety, sponsored by the Federal Ministry of Economics and Labour. Period: 1 July - 31 December 2002; Berichte ueber vom Bundesministerium fuer Wirtschaft und Arbeit gefoerderte Forschungsvorhaben auf dem Gebiet der Reaktorsicherheit. Berichtszeitraum: 01. Juli - 31. Dezember 2002  

Energy Technology Data Exchange (ETDEWEB)

Within its competence for energy research, the Bundesministerium fuer Wirtschaft und Arbeit (BMWA) (Federal Ministry of Economics and Technology) sponsors investigations into the safety of nuclear power plants. The objective of these investigations is to provide fundamental knowledge, procedures and methods to contribute to realistic safety assessments of nuclear installations, to the further development of safety technology and to make use of the potential of innovative safety-related approaches. The Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) mbH, by order to the BMWi, continuously issues information on the status of such investigations by publishing semi-annual and annual progress reports within the series of GRS-F-Fortschrittsberichte (GRS-F-Progress Reports). Each progress report represents a compilation of individual reports about the objectives, work performed, results achieved, next ...

2002-07-01

158

Proposal of procedures to prevent errors in radiotherapy based in learned lessons of accidental expositions; Proposta de procedimentos para evitar erros em radioterapia baseados em licoes aprendidas de exposicoes acidentais  

Energy Technology Data Exchange (ETDEWEB)

In order to consider some procedures to prevent errors in radiotherapy based in learned lessons of accidental expositions and in accordance with information contained in international reports elaborated by International Atomic Energy Agency (IAEA) and of the data base availability by the European group Radiation Oncology Safety Information System (ROSIS) on the events, a research of the occurred errors was performed. For the evaluation of the incidents a data base based in the ROSIS and added plus a parameter was created 'type of error'. All the stored data make possible the evaluation of the 839 incidents in terms of frequency of the type of error, the process of detention, the number of reached patients and the degree of severity. Of the 50 types of found errors, the type of error more frequently was 'incorrect treatment coordinate', confirmed with the data of literature and representing 28,96 por cent of ...

2007-07-01

159

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 I while those applicable to post-restart are classified as ...

160

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

161

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

162

Good practice and successful experience of cooperation at Daya Bay and Ling Ao  

International Nuclear Information System (INIS)

Electricite de France, (EDF) in the late sixties and China through 10. 5-year Plan adopted the same approach of standardized NPPs to benefit from the series effect and to increase and speed up self reliance and localization. This approach also allows to continuously gather the feedback from design, construction and operation and to use it to constantly improve future and present nuclear power plants, by optimizing design features, construction phase and generation performances for safety, quality, cost and schedule aspects. Daya Bay NPP put into commercial operation in 1994 is posting high level safety and operation results. At Ling Ao NPP Chinese engineers of LANPC, with the contribution of the Chinese industry, have efficiency and successfully managed engineering, construction and operation preparation. GNPJVC / LANPC and EDF are developing permanent and mutual experience feedback exchanges in all areas of engineering, ...

163

Behavioral effects of exposure to the TEMPO high-power microwave system. Interim report, January-June 1987  

Energy Technology Data Exchange (ETDEWEB)

Safety standards for exposure to radiofrequency radiation must be based upon biologic consequences of exposure to such environments. Behavioral-based measures are considered to be the most-sensitive indices of biological effects. Current safety guidelines are based upon average power density and may not be relevant to the high-peak-power, short pulse width microwave radiation produced by newly developed high peak power microwave sources. The effects of exposure to high-peak-power radiation on reflexive responding and motor function in Fischer 344/N rats were assessed by measuring startle and general activity, and disruption of on-going performance of a rotarod task, respectively. The emitter used was the TEMPO repeat pulse axially extracted vircator. Exposure to single pulses resulted in significant startle responses. Exposure to 1 pps for 10 s produced significant alterations in baseline activity and marked disruption of ...

1988-03-01

164

Nuclear raw materials: Developing resources through technical co-operation  

International Nuclear Information System (INIS)

This article presents an overview of the IAEA's technical co-operation activities in the field of nuclear raw materials, particularly looking at recent developments and trends influencing future directions

1993-09-01

165

IAEA RESEARCH CONTRACTS. THIRD ANNUAL REPORT. Technical Reports Series No. 16  

Science.gov (United States)

Brief summaries of all final reports relating to contracts that were completed during 1962 are presented. 20 summaries are included. (P.C.H.)

1963-01-01

166

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 regulatory bases for the review, the manner in ...

2007-04-12

167

End user needs for enhanced IAEA Safeguards Information Management Capabilities  

International Nuclear Information System (INIS)

The International Atomic Energy Agency is undertaking a program for strengthening its safeguards on the recognition that safeguards must give assurance not only of the non-diversion of declared material or that declared facilities are not being misused, but also of the absence of any undeclared nuclear activities in States which have signed comprehensive safeguards agreements with the Agency. The IAEA has determined that the detection of undeclared nuclear activities and the creation of confidence in the continuing peaceful use of declared material and facilities is largely dependent on more information being made available to the Agency and on the capability of the Agency to make more effective use of this additional information, as well as existing information.

168

UK regulations for NORM [naturally occurring radioactive material  

International Nuclear Information System (INIS)

The primary UK legislation relating to the use of radioactive materials are the Radioactive Substances Act 1993 (RSA, 1993) and the Ionising Radiations Regulations 1999 (IRR, 1999). These implement the European Union's Basic Safety Standards Directive (EUBSS) (EC, 1996). The Radioactive Substances Act 1993 (RSA93) regulates the accumulation, storage and disposal of radioactive waste, principally to control potential doses to members of the public. The Ionising Radiations Regulations 1999 (IRR, 1999) deal primarily with regulating the doses that people receive at work. Both of these pieces of legislation apply to the use of materials containing naturally occurring radionuclides. Historically UK regulations relating to radioactive materials have covered both artificial and natural radionuclides

2002-09-23

169

The work of the CONRAD task group 5.2: research studies on biokinetic models.  

Science.gov (United States)

The objective of this Task Group is the coordination of research studies on biokinetic models and the evaluation of the implications of new biokinetic models on dose assessment and safety standards. For this the new ICRP models, which will be used for a revision of ICRP Publications 30, 54, 68 and 78, are implemented into six different computer codes in five European countries and quality assured by intercomparison procedures. The work has started with the implementation of the new ICRP Alimentary Tract Model. New systemic models and the new NCRP wound model will follow. The work also includes the evaluation of experimental results in terms of formulation by the new model structures and a quality assurance of model formulation. PMID:17556343

2007-06-07

170

Second generation antipsychotics (SGAs) for non-psychotic disorders in children and adolescents: A review of the randomized controlled studies  

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

171

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

172

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

173

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 the life of the project.

174

PREVENTION OF INFECTION IN PATIENTS WITH CHRONIC KIDNEY DISEASE PART III: SURVEILLANCE AND AUDITING IN A RENAL CARE ENVIRONMENT  

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

175

Measurements of x-ray radiation dose levels during radiological examination in Jos university teaching hospital and Plateau state specialist hospital  

International Nuclear Information System (INIS)

In this project, measurement of x-ray radiation dose level during radiological examination in Jos university teaching hospital and Plateau State specialist hospital at different locations within the department were carried out using radiation survey meter. The results were converted from micro sievert per hour (#mu#Sv/hr) to milisievert per year (mSv/yr). The radiation levels from the two hospitals visited ranged from 1.3m Sv/yr to 8.4m Sv/yr. This implies that all the radiology departments visited are still operating within the safety limit having less than 20 mSv/yr which is the standard permissible radiation level recommended per year.

2008-10-15

176

Lighting in indoor environments: Visual and non-visual effects of light sources with different spectral power distributions  

British Library Electronic Table of Contents (United Kingdom)

Since the end of the 1990s, good quality lighting was that which balanced the needs of humans, economic and environmental issues, and architectural design. Recent studies aimed to find a correlation between environmental lighting and human performance and health, with positive results. What is known, is that insufficient or inappropriate light exposure can disrupt standard human rhythms which may result in adverse consequences for performance, safety, health. By studying the relationship between human physiology and light, research in photobiology has advanced to the point where some attempts to foresee what the lighting practice will be in future. The question is if lighting practice and lighting practitioners are ready for changes. This paper has the aim of introducing the recent discove...

2011-01-01

177

Fire and explosion assessment on oil and gas floating production storage offloading (FPSO): An effective screening and comparison tool  

British Library Electronic Table of Contents (United Kingdom)

Fires and explosions have been identified as major potential hazards for Oil and Gas Floating Production Storage Offloading (FPSO) installations and pose risk to personnel, assets, and the environment. Current fire and explosion assessment (FEA) tools require physical effect modeling software and follows standards from API, ISO, and engineering practices. However, the tools are not specific to any particular system such as an FPSO, and do not provide comprehensive guidance for safety engineers to perform FEA. This paper discusses the development of a screening and comparison tool for FEA on FPSOs and the incorporation of an expert system into the tool. The results are computerized using MS Excel/VBA to provide a structured and comprehensive assessment on each equipment and module handling ...

2009-01-01

178

Dynamic construction of outage lists for safety analysis of power transmission lines. Dynamische Erstellung von Ausfallisten fuer die Sicherheitsanalyse elektrischer Energieuebertragungssysteme  

Energy Technology Data Exchange (ETDEWEB)

An adaptive contingency selection process is set up which produces outage lists in order to guarantee on-line network security control. The quality index system used so far did not detect and reveal all critical variables due to observation problems in the mapping of two functions. The new process uses the results of the outage simulation computing of the system status just past for the drawing up of an up-to-date outage list. A linear correcting function transform the G{sub 2}-values of the standard quality index method - which still incorporate the observation problem effect - into improved values G. Studies which use data from realstic high-voltage networks prove that the detection of critical variables is far superior to ordinary methods. (orig.).

1990-04-23

179

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

180

Development of radioimmunometric assays and kits for non-clinical applications. Proceedings of a final research coordination meeting  

International Nuclear Information System (INIS)

Immunoassays are versatile analytical techniques that had a leading role in various clinical applications, during the last four decades. The studies carried out by Rosalyn Yalow, Solomon Berson and Roger Ekins in the 1960s gave a breakthrough in the development of this novel analytical method. Sensitivity up to femtomolar concentrations, high specificity and universal application to different classes of molecular species made immunoassay a very useful tool in analytical investigation. The expertise acquired by immunochemists in producing antibodies against any antigen and the ability of radiochemists in labeling the antigens with "1"2"5I without affecting the active site are the two main factors responsible for the above development. There are concerns about the safety and health of humans due to the high-level contamination of environment by pesticides, industrial compounds and metals, anabolic steroids in milk and meat products, and presence of mycotoxins in food ...

2004-12-06

181

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

182

Radiation exposure of children in pediatric radiology. Pt. 6. Conversion factors for reconstruction of organ dose in abdominal radiography; Zur Strahlenexposition von Kindern in der paediatrischen Radiologie. T. 6. Konversionsfaktoren zur Rekonstruktion von Organdosen bei Abdomenaufnahmen  

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 about 40 organs and ...

2009-10-15

183

Improving the PSA quality in the human reliability analysis of pre-accident human errors  

Energy Technology Data Exchange (ETDEWEB)

This paper describes the activities for improving the Probabilistic Safety Assessment (PSA) quality in the human reliability analysis (HRA) of the pre-accident human errors for the Korea Standard Nuclear Power Plant (KSNP). We evaluate the HRA results of the PSA for the KSNP and identify the items to be improved using the ASME PRA Standard. Evaluation results show that the ratio of items to be improved for pre-accident human errors is relatively high when compared with the ratio of those for post-accident human errors. They also show that more than 50% of the items to be improved for pre-accident human errors are related to the identification and screening analysis for them. In this paper, we develop the modeling guidelines for pre-accident human errors and apply them to the auxiliary feedwater system of the KSNP. Application results show that more than 50% of the items to be improved for the pre-accident human errors of ...

2004-07-01

184

Improving the PSA quality in the human reliability analysis of pre-accident human errors  

International Nuclear Information System (INIS)

This paper describes the activities for improving the Probabilistic Safety Assessment (PSA) quality in the human reliability analysis (HRA) of the pre-accident human errors for the Korea Standard Nuclear Power Plant (KSNP). We evaluate the HRA results of the PSA for the KSNP and identify the items to be improved using the ASME PRA Standard. Evaluation results show that the ratio of items to be improved for pre-accident human errors is relatively high when compared with the ratio of those for post-accident human errors. They also show that more than 50% of the items to be improved for pre-accident human errors are related to the identification and screening analysis for them. In this paper, we develop the modeling guidelines for pre-accident human errors and apply them to the auxiliary feedwater system of the KSNP. Application results show that more than 50% of the items to be improved for the pre-accident human errors of ...

2004-06-06

185

Highlights of design and construction of Sendai Nuclear Power Station Unit No.2  

International Nuclear Information System (INIS)

As for No.2 plant in Sendai Nuclear Power Station, which is the fourth nuclear power generation facilities in Kyushu Electric Power Co., Inc., all works have been completed, and at present, the final trial operation is under way. In No.2 plant, many new techniques for raising the reliability and safety, improving the maintainability and reducing radiation exposure were introduced on the basis of the operation experience of PWRs obtained so far, similarly to No.1 plant. In this paper, the main items of the new techniques related to the design and construction of the plant are reported. No. 2 plant is a first improved and standardized plant having the thermal output of 2660 MW for standard three-loop PWRs, and the rated power output was set at 890 MW. As for the turbine, TC6F-40 in was adopted. As the improved design, a large reactor containment vessel, 17 x 17 type 9-grid fuel, improved steam generators, a reactor vessel ...

1985-01-01

186

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

187

Electric power system design: The NEC and the IEC approach  

Energy Technology Data Exchange (ETDEWEB)

The purpose of this paper is to compare the techniques and results obtained when a general industrial or commercial building power electrical system is prepared using the US National Electrical Code{copyright} (NEC) and the International Electrotechnical Commission (IEC) Standards. The final design offer the reader the possibility of making an initial comparison and analyzation of the two methods based of their overall effectiveness (sizing, protection, co-ordination of protective devices with components etc.), safety and cost. In order to make such a comparison a specific example was developed and limited in detail to avoid complexity in this study. The power source selected will be a delta-wye utility supplied transformer feeding various load groups such as lighting and motor circuits (possibly through associated transformers). Relevant NE Code references, IEC standards, and appropriate justifications will be made at ...

1995-12-31

188

Collection efficiency and decontamination factor of HEPA filter  

International Nuclear Information System (INIS)

It is very important in a nuclear air cleaning system that HEPA (High Efficiency Particulate Air) filter is for reduction of releasing amounts of airborne radioactive particles. HEPA filter, by definition, has a minimum collection efficiency of 99.97 % for 0.3 #mu#m particles. However, DF (Decontamination Factor), which is necessary for safety management, can not be directly derived from the efficiency. And the current standard defined for 0.3 #mu#m particles has no scientific justification, because it has been found that the most penetrating particle size through HEPA filter is not always 0.3 #mu#m. In the present paper, a numerical experiment was made in order to estimate a relationship between DF and the efficiency. And new standard, in which the minimum DF is able to be easily obtained, was proposed. In the multistage filtration system, it was found that lower values of DF was possible to be experimentally indicated in ...

189

Application of the CFAST zone model to the Fire PSA  

Energy Technology Data Exchange (ETDEWEB)

The integrity of the cables located in the target room is very important in the Fire PSA, because the CDF and CCDP are changed according to the results of a cable integrity that depends on the surrounding gas temperature. The conservative assumptions used in the Fire PSA typically specify that all of the equipment and cables of a room would fail when a fire happens in the room. But the realistic assessment of a fire risk by using a fire simulation tool has become necessary in the Fire PSA as described in the ANS Fire PRA Standard. This paper evaluates the cable integrity of eight pump rooms in the nuclear power plant by using the CFAST zone fire model. The upper layer gas temperature of each room is estimated, and an analysis based on the results of model simulations is used to judge the cable integrity. According to the analysis results, the integrity of the cable located in the upper layer in the pump rooms is maintained without any thermal damage, and the CCDP ...

2010-10-15

190

Ageing assessments with application of PSA Models  

International Nuclear Information System (INIS)

One of the main applications of PSA studies is related to identification of the major key issues related to plant safety. In standard PSA one assumes a constant value for component failure rates by considering that the component doesn't experience any degradation that could affect its performance. Used in this manner, standard PSA tools do not adequately address important ageing issues, and this fact could have a significant impact on the conclusions drawn from PSA studies and applications, in conditions of operation of ageing plants. To obtain realistic results, it is necessary to consider in the PSA model the ageing effects, and to do that it is necessary to take into consideration the change in component failure rate as a function of component age. In case of ageing phenomena, this dependence causes the failure rate of a component (or a set of components) to increase in time as the component age increase. The paper ...

2009-10-12

191

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

192

Management of fire and industrial safety - challenges during commissioning of a NPP  

International Nuclear Information System (INIS)

Construction and commissioning period of NPP are reduced world over drastically by stringent schedule for financial and economic reasons. For meeting the schedule, commissioning of components and systems are started immediate after installation, while construction activities are continued in parallel at the same place. Parallel activities' and 'Time Constraint' have brought new challenges to 'Management of Fire and Industrial Safely' during commissioning. An innovative approach was used during such phase of commissioning of TAPP-3 and 4. This paper outlines challenges encountered during this phase and special approach and measures used to meet those challenges. This paper also outlines problems encountered during implementation of these measures and subsequent change in approach to ensure smooth and safe execution of activities. Primarily, challenges were conflicting requirements by various agencies to carryout commissioning in parallel with construction activities concurrently. Main ...

2006-11-13

193

Insights from Guideline for Performance of Internal Flooding Probabilistic Risk Assessment (IFPRA)  

Energy Technology Data Exchange (ETDEWEB)

An internal flooding (IF) risk assessment refers to the quantitative probabilistic safety assessment (PSA) treatment of flooding as a result of pipe and tank breaks inside the plants, as well as from other recognized flood sources. The industry consensus standard for Internal Events Probabilistic Risk Assessment (ASME-RA-Sb-2005) includes high-level and supporting technical requirements for developing internal flooding probabilistic risk assessment (IFPRA). This industry standard is endorsed in Regulatory Guide 1.200, Revision 1 as an acceptable approach for addressing the risk contribution from IF events for risk informed applications that require U.S. Nuclear Regulatory commission (NRC) approval. In 2006, EPRI published a draft report for IFPRA that addresses the requirements of the ASME PRA consensus standard and have made efforts to refine and update the final EPRI IFPRA guideline. Westinghouse has ...

2009-10-15

194

A Human Reliability Analysis of Pre-Accident Human Errors in the Low Power and Shutdown PSA of the KSNP  

International Nuclear Information System (INIS)

Korea Atomic Energy Research Institute, using the ANS Low Power /Shutdown (LPSD)PRA Standard, evaluated the LPSD PSA model of the KSNP, Younggwang (YGN) Units 5 and 6, and identified the items to be improved. The evaluation results of human reliability analysis (HRA) of the pre-accident human errors in the LPSD PSA model of the KSNP showed that 13 items among 15 items of supporting requirements for those in the ANS PRA Standard were identified as them to be improved. Thus, we newly carried out a HRA for pre-accident human errors in the LPSD PSA model for the KSNP to improve its quality. We considered potential pre-accident human errors for all manual valves and control/instrumentation equipment of the systems modeled in the KSNP LPSD PSA model except reactor protection system/ engineering safety features actuation system. We reviewed 160 manual valves and 56 control/instrumentation equipment. The number of newly identified ...

2003-04-20

195

Traces of evidence. Nuclear forensics and illicit trafficking  

International Nuclear Information System (INIS)

An IAEA databank lists a number of reported cases of illicitly trafficked nuclear or other radioactive materials. Apart from the traditional concern with nuclear proliferation, the post September 11th public is now wary of a possible attack by terrorists with a nuclear or radiation dispersion device (RDD). Until now, the seized quantities have not been sufficient to manufacture a nuclear explosive device, but they might be enough to construct an RDD. Recognizing the latent global challenge to public health and safety, the G8 States (Japan, USA, Germany, France, UK, Italy, Canada, and Russia) have called for 'joint international efforts to identify and suppress illicit supply' of, and demand for, nuclear material and to deter potential traffickers. One measure gaining in significance is to identify seized material and trace it back to its origin the objective of an emerging science known as nuclear forensics. Repeatedly nuclear or other ...

2003-06-01

196

Safety in the forefront  

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

197

Review of the WIPP draft application to show compliance with EPA transuranic waste disposal standards  

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 analyses of the ...

1996-03-01

198

Current status of siting a new near surface repository in Romania  

International Nuclear Information System (INIS)

Full text: The site selection process for a near surface repository dedicated for the radioactive waste resulted from the Cernavoda NPP operation and decommissioning started early in 90's. Each site selection stage included the collection of data from specific field and laboratory works as well as the appropriate safety performance evaluation. In order to assess/confirm the performance of the natural barrier of the Saligny site, the radionuclide concentration in the disposal system compartments has been evaluated, as complementary safety indicator of repository. The siting process was made in accordance with national and international regulations and standards and using a conceptual design similar to those used at L'Aube (France), ElCabril (Spain) or Mohovce (Slovak Republic). ANDRAD, the Romanian waste management organization that has continued the siting process in the last three years applied and obtained a partial ...

2009-05-27

199

Contributions of pesticide residue chemistry to improving food and environmental safety: past and present accomplishments and future challenges.  

Science.gov (United States)

The principles of modern pesticide residue chemistry were articulated in the 1950s. Early authors pointed out the advantages of systematizing and standardizing analytical methods for pesticides so that they could be widely practiced and the results could be reproduced from one laboratory to the next. The availability of improved methods has led to a much more complete understanding of pesticide behavior and fate in foods and the environment. Using methods based largely upon gas chromatography (GC) and high-performance liquid chromatography (HPLC) coupled increasingly with mass spectrometry (MS) and MS(n) as the detection tool, residues can be measured at parts per billion levels and below in a variety of food and environmental matrices. Development of efficient extraction and cleanup methods, techniques such as ELISA, efficient sample preparation techniques such as QuEChERS, and automated laboratory and field instrumentation has also contributed to the tools ...

2011-04-07

200

Losing weight to save lives: A review of the role of automobile weight and size in traffic fatalities  

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

202

Implementation of integrated safeguards in Nuclear Fuel Plant at Pitesti, Romania  

International Nuclear Information System (INIS)

The nuclear activity was conducted for many years in Romania under Traditional Safeguards (TS) and has developed in good conditions the specific nuclear safeguards. Now there is a good opportunity to improve the performance and quality of the safeguards activity and at the same time to increase the accountancy and control of nuclear materials by passing to Integrated Safeguards (IS) implementation. The legal framework is the Law 100/2000 for ratification of the Protocol between Romania and International Atomic Energy Agency (IAEA), additional completion to the Agreement between the Socialist Republic of Romania Government and IAEA relating to safeguards. It is part of the Treaty on the non-proliferation of nuclear weapons published in the Official Gazette no. 3/31 January 1970, and the Additional Protocol published in the Official Gazette no. 295/ 29.06.2000. The first discussion about Integrated Safeguards (IS) between the Nuclear Fuel Plant ...

2009-10-12

205

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

208

NHTSA Contact Information | National Highway Traffic Safety Administra...  

Science.gov (United States)

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

210

Survey of light-water-reactor designs to be offered in the United States  

Energy Technology Data Exchange (ETDEWEB)

ORNL has conducted a Nuclear Power Options Viability Study for the Department of Energy. That study is primarily concerned with new technology which could be developed for initial operation in the 2000 to 2010 time frame. Such technology would have to compete not only with coal options but with incrementally improved commercial light-water-reactors. This survey reported here was undertaken to gain an understanding of the nuclear commercial technology likely to be offered in the late 1980s and perhaps beyond. The three US vendors actively marketing NSSSs are each developing a product for the future which they expect to be more reliable, more maintainable, more economical, and safer than the present plants. These are all essentially 3800-MW(t) designs, although all are studying smaller plants. They apparently will be off offered as standard prelicensed designs with much larger scope than earlier NSSS offerings, with the possibility of firm prices. Westinghouse with ...

1986-03-01

211

Achievements and Perspectives of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management  

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)

212

The upgrade of nuclear material accounting system at KAERI  

International Nuclear Information System (INIS)

The agreement between the government of Republic Of Korea (ROK) and the IAEA for the application of safeguards was signed and entered into force in 1975. The Additional Protocol (AP) to the Safeguards Agreement between the ROK and the IAEA was signed in 1999 and entered into force on 19 February 2004. Also, Implementation of Integrated Safeguards (IS) was started on 1 July, 2008 after a draw of the broader conclusion. The IAEA provides 2 hours notification for Random Interim Inspection (RII) under IS. For RII, the facility has to prepare the inspection documents in a short time. Therefore, KAERI (Korea Atomic Energy Research Institute) developed a new computerized nuclear material accounting system named KASIS (KAERI Safeguards Information treatment System) to treat the data by on-line for RII. For the efficient IS implementation, KAERI has a plan to upgrade the system to reflect the accounting approaches or reporting ...

2010-10-01

213

Spent Fuel Transfer to Dry Storage Using Unattended Monitoring System  

Energy Technology Data Exchange (ETDEWEB)

There are 4 CANDU reactors at Wolsung site together with a spent fuel dry storage associated with unit 1. These CANDU reactors, classified as On-Load Reactor (OLR) for Safeguards application, change 16- 24 fuel bundles with fresh fuel in everyday. Especially, the spent fuel bundles are transferred from spent fuel bays to dry storage throughout a year because of the insufficient capacity of spent fuel pond. Safeguards inspectors verify the spent fuel transfer to meet safeguards purposes according to the safeguards criteria by means of inspector's presence during the transfer campaign. For the verification, 60-80 person-days of inspection (PDIs) are needed during approximately 3 months for each unit. In order to reduce the inspection effort and operators' burden, an Unattended Monitoring System (UMS) was designed and developed by the IAEA for the verification of spent fuel bundles transfers from wet storage to dry storage. Based on the enhanced ...

2009-05-15

214

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

215

The development of thyroid dose assessment software for nuclear or radiological emergency  

International Nuclear Information System (INIS)

Objective: To develop software for assessment of dose to thyroid gland in emergencies resulting in the release of radioiodine. Methods: Based on procedures for thyroid monitoring and dose assessment introduced in IAEA publications (IAEA-TECDOC-1092 and EPR-MEDICAL-2005), a software was developed with Visual Basic 6.0 program to computerized the methods of thyroid dose estimation. Results: The intake of radioiodine and committed equivalent dose to thyroid could be estimated rapidly and accurately with the present software. Conclusion: The present software provide a practical and rapid tool for estimating thyroid doses received in emergencies resulting in the release of radioiodine by emergency workers and members of public, which is necessary for recommendation of further actions. (authors)

2006-12-01

216

The assessment of soil conservation technologies for sustainable agricultural production. Report of the FAO/IAEA consultants meeting. Working material  

International Nuclear Information System (INIS)

A Consultants' Meeting on 'The assessment of soil conservation technologies for sustainable agricultural production' was held in Vienna at the IAEA Headquarters from May 28-30, 2001. The consultants' presentations reviewed recent advances in the use of fallout radionuclides to measure soil erosion as well as approaches and technologies applied for soil conservation worldwide. Also, activities and experiences of FAO and UNEP in the field of land degradation, soil conservation and related issues were presented. Based on the information provided by the Scientific Secretary, a full project proposal was prepared during the second part of the Consultants' Meeting. The consultants also provided recommendations on the formulation and implementation of a future CRP on the subject.

2001-05-28

217

Packing for food irradiation  

International Nuclear Information System (INIS)

Joint FAO/IAEA/WHO Expert Committee approved the use of radiation treatment of foods. Nowadays food packaging are mostly made of plastics, natural or synthetic, therefore effect of irradiation on these materials is crucial for packing engineering for food irradiation technology. By selecting the right polymer materials for food packaging it can be ensured that the critical elements of material and product performance are not compromised. When packaging materials are in contact with food at the time of irradiation that regulatory approvals sometimes apply. The review of the R-and-D and technical papers regarding material selection, testing and approval is presented in the report. The most information come from the USA where this subject is well elaborated, the International Atomic Energy Agency (IAEA) reports are reviewed as well. The report can be useful for scientists and food irradiation plants operators. (author)

218

Introduction of Member State Support Program (MSSP) of Korea  

International Nuclear Information System (INIS)

The demand of nuclear energy is sharply increasing to solve the energy and environment problems all over the world. The interest and support on the field of nuclear energy in Korea are enlarging as the acceptance of ordering nuclear power plant of UAE. The attention of safeguards is needed to maintain peaceful use of nuclear material and the nuclear nonproliferation as the increasing demand of nuclear energy. The International Atomic Energy Agency (IAEA) invests more in research and development to achieve the effective and efficient implementation of safeguards. Research and development (R and D) in safeguards approaches, procedures and techniques is essential to meeting the safeguards challenges of the future. The IAEA has conducted the R and D program through member state support program (MSSP) since 1977. The objective of this paper is to introduce the MSSP and policy of Korea on MSSP

2010-10-01

219

Energy and nuclear power planning study for Thailand  

International Nuclear Information System (INIS)

The present report describes the study conducted in co-operation with several agencies and organizations from Thailand and covers the energy and electricity requirements and the optimal expansion plans for the power generating system for this country up to year 2011. It is emphasized that the study was carried out by a team of experts from the Electricity Generating Authority of Thailand (EGAT), the National Economic and Social Development Board (NESDB), the National Energy Administration (NEA) and the Office of Atomic Energy for Peace (OAEP), who were fully responsible for all phases of the study, including the production of the present report. The IAEA's responsibility was to provide overall co-ordination and general guidance during the conduct of the study, as well as training and assistance in the implementation and use of the IAEA's computerized planning methodologies on the computer facilities of Thailand. Refs, figs and tabs.

2002-06-16

220

A computer program for rapid calculation of internal committed effective dose through inhalation and ingestion pathways under radiological emergency  

International Nuclear Information System (INIS)

Objective: To establish a computer program for rapid calculation of internal committed effective close through inhalation and ingestion pathways under radiological emergency. Methods: Visual Basic 6.0 is used to compile the generic procedures of internal committed effective dose by inhalation and ingestion in IAEA-TECDOC-1162, Generic Procedures for Assessment and Response during a Radiological Emergency. Results: The assessment methodology of internal committed effective dose by inhalation and ingestion under radiological emergency in the report IAEA-TECDOC-1162 can be coded into a computer program. Conclusions: This research provides a rapid method of assessment for internal committed effective dose by inhalation and ingestion under radiological emergency, and it may provide needed dosimetry data for treatment under emergency response. (authors)

2008-08-01

221

An Introduction to the Standard Theory of Electroweak Interactions (4/4)  

CERN Document Server

An Introduction to the Standard Theory of Electroweak Interactions (4/4)

2011-01-01

222

An Introduction to the Standard Theory of Electroweak Interactions (3/4)  

CERN Document Server

An Introduction to the Standard Theory of Electroweak Interactions (3/4)

2011-01-01

223

An Introduction to the Standard Theory of Electroweak Interactions (2/4)  

CERN Document Server

An Introduction to the Standard Theory of Electroweak Interactions (2/4)

2011-01-01

224

Validation and verification of the ORNL Monte Carlo codes for nuclear safety analysis  

International Nuclear Information System (INIS)

The process of ensuring the quality of computer codes can be very time consuming and expensive. The Oak Ridge National Laboratory (ORNL) Monte Carlo codes all predate the existence of quality assurance (QA) standards and configuration control. The number of person-years and the amount of money spent on code development make it impossible to adhere strictly to all the current requirements. At ORNL, the Nuclear Engineering Applications Section of the Computing Applications Division is responsible for the development, maintenance, and application of the Monte Carlo codes MORSE and KENO. The KENO code is used for doing criticality analyses; the MORSE code, which has two official versions, CGA and SGC, is used for radiation transport analyses. Because KENO and MORSE were very thoroughly checked out over the many years of extensive use both in the United States and in the international community, the existing codes were open-quotes baselined.close quotes This means that ...

1993-11-14

225

The Performance of Spent Fuel Casks in Severe Tunnel Fires  

International Nuclear Information System (INIS)

The Nuclear Regulatory Commission (NRC), working with the National Institute of Standards and Technology (NIST), Pacific Northwest National Laboratory (PNNL), and the National Transportation Safety Board (NTSB), performed analyses to predict the response of various spent fuel transportation cask designs when exposed to a fire similar to that which occurred in the Howard Street railroad tunnel in downtown Baltimore, Maryland on July 18, 2001. The thermal performance of three different spent fuel cask designs (HOLTEC HI-STAR 100, TransNuclear TN-68, and NAC-LWT) was evaluated with the ANSYSR and COBRA-SFS analysis codes, utilizing boundary conditions for the tunnel fire obtained using NIST's Fire Dynamics Simulator (FDS) code. NRC Staff evaluated the potential for a release of radioactive material from each of the three transportation casks analyzed for the Baltimore tunnel fire scenario. The results of these analyses are described in detail in ...

2005-11-01

226

Re-evaluation of floor response spectra of reactor building for Daya Bay NPP  

International Nuclear Information System (INIS)

The seismic analysis of nuclear island of Daya Bay Nuclear Power Plant (NPP) was just in accordance with the approaches in RCC-G standard for the model M310 in France, in which the simplified impedance matrix method was employed for the consideration of soil's function. In this paper the more sophisticated 3D half-space continuum impedance method based on the Green functions is used to analyze the function of soil. In addition, multi-group of input time histories was used in the seismic response analysis in the existing design and their average of responses for each group was taken as the design basis. The same multi-group of input time histories was used in the seismic response analysis in this study, but the average and enveloped value of responses for each case are calculated respectively to account for the uncertainty of input motions. Focused on the above two issues, the seismic responses of the reactor building are calculated and the floor response spectra ...

2006-03-01

227

Overview of hazardous-waste regulation at federal facilities  

Energy Technology Data Exchange (ETDEWEB)

This report is organized in a fashion that is intended to explain the legal duties imposed on officials responsible for hazardous waste at each stage of its existence. Section 2 describes federal hazardous waste laws, explaining the legal meaning of hazardous waste and the protective measures that are required to be taken by its generators, transporters, and storers. In addition, penalties for violation of the standards are summarized, and a special discussion is presented of so-called imminent hazard provisions for handling hazardous waste that immediately threatens public health and safety. Although the focus of Sec. 2 is on RCRA, which is the principal federal law regulating hazardous waste, other federal statutes are discussed as appropriate. Section 3 covers state regulation of hazardous waste. First, Sec. 3 explains the system of state enforcement of the federal RCRA requirements on hazardous waste within their borders. Second, Sec. 3 ...

1982-05-01

228

Organic farming in the Nordic countries--animal health and production.  

Science.gov (United States)

Organic farming (or ecological agriculture) is of growing importance in the agricultural sector worldwide. In the Nordic countries, 1-10% of the arable land was in organic production in 1999. Organic farming can be seen as an approach to agriculture where the aim is to create integrated, humane, environmentally and economically sustainable agricultural production systems. Principles like nutrient recycling, prevention rather than treatment and the precautionary principle are included in aims and standards. Animal welfare is another hallmark of organic livestock production but despite this, several studies have indicated severe health problems e.g. in organic poultry production in Denmark. Also the quality of animal food products in relation to human health, particularly the risk of zoonotic infections, has been debated. For these reasons there is a need for improvement of production methods and animal health status. Vets play an important role in this development ...

2001-01-01

229

Increase in the number of distributed power generation installations in electricity distribution grids - Project findings; Zunahme der dezentralen Energieerzeugungsanlagen in elektrischen Verteilnetzen: Erkenntnisse aus dem Projekt  

Energy Technology Data Exchange (ETDEWEB)

This is the eighth part of a ten-part final report for the Swiss Federal Office of Energy (SFOE) on a project that looked into potential problems relating to the Swiss electricity distribution grid with respect to the increasing number of distributed power generation facilities being put into service. The identification of special conditions for the grid's operation and future development that take increasing decentralised power production into account are discussed. The results of the project activities encompass the analysis and evaluation of various problem areas associated with planning and management of the grid during normal operation and periods of malfunction, as well as required modifications to safety systems and grid configurations. This seventh appendix to the main report summarises and discusses the knowledge gained during the project and attempts to provide answers to various questions posed by the use of distributed power generation in ...

2003-07-01

230

Fuzzy reliability analysis of structures by using the method of fuzzy optimization  

Energy Technology Data Exchange (ETDEWEB)

There are two kinds of uncertainties in safety assessment of engineering structures. One is of the nature of randomness, and the other fuzziness. Fuzzy uncertainties exist in defining certain structural performances, conditions, parameters, and their interrelationships. The theory of fuzzy sets should be employed to cope with the fuzzy uncertainties. In this paper, a general definition for structural failure considering the fuzzy uncertainties is introduced firstly. Failure of the structure is modelled by a fuzzy event, and described by the membership function. The limit state surface is then replaced by a fuzzy limit state zone, in which every point represents a state belonging to the failure with a certain degree of membership. Then a fuzzy optimization problem for solving the reliability index is formulated. In classical structural reliability theory, the reliability index is defined by the minimum distance from the limit state surface to the origin of the ...

1996-12-31

231

Four-fermion production at {gamma}{gamma} colliders: 2. Radiative corrections in double-pole approximation  

Energy Technology Data Exchange (ETDEWEB)

The O({alpha}) electroweak radiative corrections to {gamma}{gamma}{yields}WW{yields}4f within the electroweak standard model are calculated in double-pole approximation (DPA). Virtual corrections are treated in DPA, leading to a classification into factorizable and non-factorizable contributions, and real-photonic corrections are based on complete lowest-order matrix elements for {gamma}{gamma}{yields}4f+{gamma}. Soft and collinear singularities appearing in the virtual and real corrections are combined alternatively in two different ways, namely by using the dipole subtraction method or by applying phase-space slicing. The radiative corrections are implemented in a Monte Carlo generator called Coffer {gamma}{gamma} - the computer code can be obtained from the authors upon request - which optionally includes anomalous triple and quartic gauge-boson couplings in addition and performs a convolution over realistic spectra of the photon beams. A detailed survey of ...

2005-09-01

232

Four-fermion production at #gamma##gamma# colliders: 2. Radiative corrections in double-pole approximation  

International Nuclear Information System (INIS)

The O(#alpha#) electroweak radiative corrections to #gamma##gamma##->#WW#->#4f within the electroweak standard model are calculated in double-pole approximation (DPA). Virtual corrections are treated in DPA, leading to a classification into factorizable and non-factorizable contributions, and real-photonic corrections are based on complete lowest-order matrix elements for #gamma##gamma##->#4f+#gamma#. Soft and collinear singularities appearing in the virtual and real corrections are combined alternatively in two different ways, namely by using the dipole subtraction method or by applying phase-space slicing. The radiative corrections are implemented in a Monte Carlo generator called Coffer #gamma##gamma# - the computer code can be obtained from the authors upon request - which optionally includes anomalous triple and quartic gauge-boson couplings in addition and performs a convolution over realistic spectra of the photon beams. A detailed survey of ...

2005-09-01

233

Fluid mixing in reactor containment  

Energy Technology Data Exchange (ETDEWEB)

Full text of publication follows: Hydrogen release and distribution in nuclear power plant containment is an important safety issue. Selection of a proper turbulence model is important for accurate estimation of the mixing process. The selection of turbulence model is dictated by the best compromise between accuracy and computational efforts. For this, three different turbulence models, viz. Standard k-{epsilon}, RNG k-{epsilon} and Reynolds Stress Model, based on Reynolds averaged Navier Stokes equations (RANS) approach, were used. The computations were done using the CFD code FLUENT, which is based on the control volume methodology. The computational results were compared with the experimental results of HYMIS test facility, where helium was used to simulate hydrogen. The processes of helium plume rise, multiple plume merging, distribution and mixing were studied. Based on these computations, a simple analytical/empirical zone based model was ...

2005-07-01

234

Fluid mixing in reactor containment  

International Nuclear Information System (INIS)

Full text of publication follows: Hydrogen release and distribution in nuclear power plant containment is an important safety issue. Selection of a proper turbulence model is important for accurate estimation of the mixing process. The selection of turbulence model is dictated by the best compromise between accuracy and computational efforts. For this, three different turbulence models, viz. Standard k-#epsilon#, RNG k-#epsilon# and Reynolds Stress Model, based on Reynolds averaged Navier Stokes equations (RANS) approach, were used. The computations were done using the CFD code FLUENT, which is based on the control volume methodology. The computational results were compared with the experimental results of HYMIS test facility, where helium was used to simulate hydrogen. The processes of helium plume rise, multiple plume merging, distribution and mixing were studied. Based on these computations, a simple analytical/empirical zone based model was ...

2005-10-02

235

Failure modes, reliability and integrity of floating storage unit (FPSO, FSU) turret and swivel systems  

Energy Technology Data Exchange (ETDEWEB)

This report provides an assessment of the designs of turret and swivel systems for floating production, storage and offloading (FPSO) vessels and floating storage Units (FSU) which are either purpose built or converted from tankers. Use of FPSO and FSO in the North Sea with the move to subsea and deepwater production is discussed, and the background to FPSO and FSU turret systems is traced. Details are given of general issues relating to ship structure, systems affecting the turret, swivel systems, mooring systems, turret loading, scaffolding and support structure, on-board personnel, and construction standards. Turret system components and types are described, and failure modes, operation and safety relevant components are examined. Inspection and maintenance, examples of good and poor practice, and applicable regulations are considered. Annexes list UK installations and present information on individual turret design, fluid transfer systems, ...

2002-07-01

236

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 to their individual scope of work as it is associated with the Environmental ...

237

Development of Risk Management Technology/Development of Risk-Informed Application Technology  

Energy Technology Data Exchange (ETDEWEB)

This project aims at developing risk-informed application technologies to enhance the safety and economy of nuclear power plant altogether. For this, the Integrated Level 1 and 2 PSA model is developed. In addition, the fire and internal flooding PSA models are improved according to the PSA standard of U.S.A. To solve the issues of domestic PSA model, the best-estimate thermal hydraulic analyses are preformed for the ATWS and LSSB. In order to reduce the uncertainty of PSA, several new PSA technologies are developed: (1) more exact quantification of large fault tree, (2) importance measure including the effects of external PSA. As feasibility studies of Option 2 and 3, the class of 6 systems' SSC are re-classified based on the risk information and the sensitivity analyses is performed for the EDG starting time, respectively. It is also improved that the methodology to identify the vital area of NPP. The research results of this project ...

2007-06-15

238

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

239

BMFT. The 'biotechnology 2000' project. Annual report 1991. BMFT. Programm Biotechnologie 2000. Jahresbericht 1991  

Energy Technology Data Exchange (ETDEWEB)

The ''biotechnology 2000'' project is supervised by the project sponsor ''biology, energy, ecology'' at Forschungszentrum Juelich on behalf of the Federal Ministry for Research and Technology. The project activities cover the development of techniques and methods, cell biology, gene structure and gene regulation, photosynthetic production processes, biological hydrogen production, synthetic biology, protein design, neurobiological research, biosystems, plant breeding, phytomedicine and plant protection, the biology of waste disposal methods, research into methods which replace animal experiments, biological safety research, technology risk assessment, and ethical aspects. A general survey introduces the promoted projects, and standardized data sheets briefly introduce the individual activities. The appendix gives the project indices, the indices of joint projects, a list of ...

1992-01-01

240

Application of pharmacological techniques to the study of the biological effects of microwaves during low level exposures  

Energy Technology Data Exchange (ETDEWEB)

The influence of low-level microwaves (2.45 GHz, CW, 2 and 5 mW.cm/sup -2/) was studied on various models of previsional animal psychopharmacology involving tests of motor activity, stereotypy, convulsions and hypothermia after a standard 30 min irradiation. The results obtained on 933 rodents allow to conclude that: (1) there is no interaction between microwaves and the studied convulsants and stimulants; (2) there is a possibility of potentialization of the behavioral effects of a tranquilizer; (3) there is a thermogenic effect of microwaves; (4) there is no change of the blood-brain barrier permeability. The demonstration of a thermal effect of microwaves during radiations lower than 10 mW.cm/sup -2/ the safety threshold admitted presently (a value below which the exposure duration comes under regulation) could explain the energetic nature of certain effects of microwaves up-to-now described as non-thermal.

1982-01-01

241

Application of automatic inspection system to nondestructive test of heat transfer tubes of primary pressurized water cooler in the high temperature engineering test reactor. Joint research  

International Nuclear Information System (INIS)

Heat transfer tubes of a primary pressurized water cooled (PPWC) in the high temperature engineering test reactor (HTTR) form the reactor pressure boundary of the primary coolant, therefore are important from the viewpoint of safety. To establish inspection techniques for the heat transfer tubes of the PPWC, an automatic inspection system was developed. The system employs a bobbin coil probe, a rotating probe for eddy current testing (ECT) and a rotating probe for ultrasonic testing (UT). Nondestructive test of a half of the heat transfer tubes of the PPWC was carried out by the automatic inspection system during reactor shutdown period of the HTTR (about 55% in the maximum reactor power in this paper). The nondestructive test results showed that the maximum signal-to-noise ratio was 1.8 in ECT. Pattern and phase of Lissajous wave, which were obtained for the heat transfer tube of the PPWC, were different from those obtained for the artificially defected tube. In ...

242

Analysis and evaluation of seismic response of reactor building for Daya Bay Nuclear Power Plant  

International Nuclear Information System (INIS)

Daya Bay NPP has been operating safely and stably over 10 years since 1994, and its' seismic analysis of nuclear island was in accordance with the approaches in RCC-G standard for the model M310, in which the Simplified Impedance Matrix Method (SIMM) was employed for the consideration of SSI. Thanks to the rapid progress being made in upgrading the evaluation technology and the capability of data processing systems, methods and software tools for the SSI analysis have experienced significant development all over the world. Focused on the model of reactor building of the Daya Bay NPP, in his paper the more sophisticated 3D half-space continuum impedance method based on the Green functions is used to analyze the functions of the soil, and then the seismic responses of the coupled SSI system are calculated and compared with the corresponding design values. It demonstrates that the design method provides a set of conservatively safe results. The conclusions from the ...

2005-12-01

243

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 Energy. The ultimate goal of EH-24 is enhancement of environmental ...

1994-09-01

244

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 of the patient, personnel, and the institution (2) QA procedure ...

245

Model for predicting the effects of laser exposures and eye protection on vision. Interim report, January 1989-January 1990  

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

246

Improving radiotherapy quality and safety: a common objective of A.S.N. and the Ile de France Regional Hospital Agency. Thoughts on successful cooperation in Ile de France; Ameliorer la qualite et la securite de la radiotherapie: un objectif conjoint de l'A.S.N. et de l'Agence regionale de l'hospitalisation Ile de France. Reflexions sur une cooperation feconde en Ile de France  

Energy Technology Data Exchange (ETDEWEB)

Radiotherapy recent development in cancer treatment needs strong procedures and quality assessment to improve safety both for patients and professionals. In Ile de France territory, a coordinated action between ASN inspectors and medical doctors specialized in public health (MISP), working as civil servants in health administration, was initiated at the end of 2007. An inspection guideline was implemented in a workshop between ASN and Regional Hospital Agency (ARH). The MISP as health administrator has to verify if care organisation responds to treatment cancer regulatory framework: as a doctor he is authorized to access to patient records to know which treatment was chosen. He has to assure if the therapeutic guidelines are respected. His comprehensive approach is essentially patient-oriented. The MISP inspection coordinated with ASN inspectors is a very pertinent pluri-disciplinary approach, undeniably necessary in such a medical technic. The effectiveness of the ...

2009-02-15

247

Improving radiotherapy quality and safety: a common objective of A.S.N. and the Ile de France Regional Hospital Agency. Thoughts on successful cooperation in Ile de France  

International Nuclear Information System (INIS)

Radiotherapy recent development in cancer treatment needs strong procedures and quality assessment to improve safety both for patients and professionals. In Ile de France territory, a coordinated action between ASN inspectors and medical doctors specialized in public health (MISP), working as civil servants in health administration, was initiated at the end of 2007. An inspection guideline was implemented in a workshop between ASN and Regional Hospital Agency (ARH). The MISP as health administrator has to verify if care organisation responds to treatment cancer regulatory framework: as a doctor he is authorized to access to patient records to know which treatment was chosen. He has to assure if the therapeutic guidelines are respected. His comprehensive approach is essentially patient-oriented. The MISP inspection coordinated with ASN inspectors is a very pertinent pluri-disciplinary approach, undeniably necessary in such a medical technic. The effectiveness of the ...

2009-02-01

248

HT technology -- All-metal sealing answers safety and environmental concerns  

Energy Technology Data Exchange (ETDEWEB)

This paper discusses the evolution of the horizontal subsea tree and its utilization in increasingly demanding applications. Initially, the Horizontal Tree was seen as a solution for wells requiring high well maintenance, such as those using electrical downhole pumps. Today, the horizontal tree is being applied to natural drive wells because of attractive whole life economics. This raises concern in a number of areas. Tubing hanger seals are permanently exposed to well fluids, and must provide high integrity sealing. This required the development of a new type of radially energized, all metal sealing system, specifically for horizontal tree applications, suitable for oil or gas service at working pressures to 15,000 psi. In addition, horizontal tree pressure integrity depends on the master valve stem, gate and bonnet seals. The need for high seal integrity also dictates that the first master valves should be integral to the main body of the tree, to maximize dropped object protection. ...

1995-12-31

249

IAEA advisory group meeting on basic and applied problems of nuclear level densities  

International Nuclear Information System (INIS)

Separate entries were made in the data base for 17 of the 19 papers included. Two papers were previously included in the data base. Workshop reports are included on (1) nuclear level density theories and nuclear model reaction cross-section calculations and (2) extraction of nuclear level density information from experimental data.

1983-04-11

250

IAEA advisory group meeting on basic and applied problems of nuclear level densities  

Energy Technology Data Exchange (ETDEWEB)

Separate entries were made in the data base for 17 of the 19 papers included. Two papers were previously included in the data base. Workshop reports are included on (1) nuclear level density theories and nuclear model reaction cross-section calculations and (2) extraction of nuclear level density information from experimental data. (WHK)

1983-06-01

251

IAEA Co-ordinated Research Program (CRP)  

International Nuclear Information System (INIS)

The Coordinated Research Project is a topical collection of research agreements and contracts. The research contracts are awarded with financial support of about 10-20% of the total contract cost. Among the activities of the project is the organization of consultant group meetings and workshops involving several international experts and representatives of users and developers of border radiation monitoring equipment. The project also supports in coordinating the development of equipment and techniques for up-to-date border monitoring and in establishing of a process for providing nuclear forensics support to member states

2010-05-19

252

Additional protocol between France, EURATOM and IAEA. 2001-2002 ordinary session. Project of law authorizing the ratification of the additional protocol to the agreement between France, the European Atomic Energy Community and the International Atomic Energy Agency relative to the application of warranties in France; Protocole additionnel entre la France, Euratom et l'AIEA. Session ordinaire de 2001-2002. Projet de loi autorisant la ratification du protocole additionnel a l'accord entre la France, la Communaute europeenne de l'energie atomique et l'Agence internationale de l'energie atomique relatif a l'application de garanties en France  

Energy Technology Data Exchange (ETDEWEB)

This additional protocol to the agreement between France, EURATOM and the IAEA aims at reinforcing the nuclear weapons non-proliferation regime. This protocol widens the field of competences of the IAEA with the supply of new information relative to: the civil nuclear cooperation between France and countries having no nuclear weapons in the domain of fuel cycle; the regular inspection of French nuclear facilities; the trade (import and export) of medium- or high-level radioactive wastes containing plutonium, highly enriched uranium or {sup 233}U, and the trade of some non-nuclear equipments or materials with countries having no nuclear weapons. The protocol defines also some practical dispositions relative to the delays and periodicity of controls, to the transmission of data, to the appointment of IAEA inspectors and their access to the facilities and sites considered. The list of the activities and equipments covered by ...

2002-07-01

253

Standards and guidances for limiting ionizing radiation exposure  

Energy Technology Data Exchange (ETDEWEB)

This chapter is concerned with standards and guidances for limiting radiation exposures. It is divided into three sections, each of which has several parts. Section 1: Ionizing Radiation -- Standards and Guidances Applicable to the Public: Part A, Radiation Protection Standards; Part B, Environmental Radiation Standards; Part C, Exempt Levels of Radioactivity; Part D, Protective Action Guides for Accidents. Section 2: Ionizing Radiation -- Standards Applicable to the Workplace. Section 3: Medical and Other Standards.

1992-12-31

254

On new methods for standardization of samples in activation analysis of biological materials  

International Nuclear Information System (INIS)

New standardization techniques of samples in multielement instrumental neutron-activation analysis (INAA) of biological materials (BM) are considered. New methodical developments of sample preparation techniques, BM tableting, creation of comparison standards and standardization of packing material are suggested. Correlated data on concentration of different elements in standard specimens-comparison standards are presented for mass INAA, that is: for phenol-formaldehyde resin-base and human blood-base synthetic standards. 7 refs.; 3 tabs.

1988-06-26

255

Sandia National Laboratories support of the Iraq Nuclear Facility Dismantlement and Disposal Program.  

Energy Technology Data Exchange (ETDEWEB)

Because of past military operations, lack of upkeep and looting there are now enormous radioactive waste problems in Iraq. These waste problems include destroyed nuclear facilities, uncharacterized radioactive wastes, liquid radioactive waste in underground tanks, wastes related to the production of yellow cake, sealed radioactive sources, activated metals and contaminated metals that must be constantly guarded. Iraq currently lacks the trained personnel, regulatory and physical infrastructure to safely and securely manage these facilities and wastes. In 2005 the International Atomic Energy Agency (IAEA) agreed to organize an international cooperative program to assist Iraq with these issues. Soon after, the Iraq Nuclear Facility Dismantlement and Disposal Program (the NDs Program) was initiated by the U.S. Department of State (DOS) to support the IAEA and assist the Government of Iraq (GOI) in eliminating the threats from poorly controlled ...

2009-03-01

256

Development of a dedicated ethanol ultra-low emission vehicle (ULEV) system design  

Energy Technology Data Exchange (ETDEWEB)

The objective of this 3.5 year project is to develop a commercially competitive vehicle powered by ethanol (or ethanol blend) that can meet California`s ultra-low emission vehicle (ULEV) standards and equivalent corporate average fuel economy (CAFE) energy efficiency for a light-duty passenger car application. The definition of commercially competitive is independent of fuel cost, but does include technical requirements for competitive power, performance, refueling times, vehicle range, driveability, fuel handling safety, and overall emissions performance. This report summarizes a system design study completed after six months of effort on this project. The design study resulted in recommendations for ethanol-fuel blends that shall be tested for engine low-temperature cold-start performance and other criteria. The study also describes three changes to the engine, and two other changes to the vehicle to improve low-temperature starting, ...

1995-02-01

257

The stability of biological standards  

UK PubMed Central (United Kingdom)

The authors emphasize the importance of stability in biological standards and discuss the steps taken to ensure the stability of International Standards and the theoretical basis of the various stability...Full Text Available

1956-01-01

258

Standardization of Ajmodadi churna, a polyherbal formulation  

UK PubMed Central (United Kingdom)

Standardization of herbal formulations is essential in order to assess the quality of drugs, based on the concentration of their active principles. This article reports on standardization of Ajmodadi...Full Text Available

2010-03-01

259

Ada Compiler Validation Summary Report: Certificate Number ...  

Science.gov (United States)

... Standards Validation Group National Computer Systems Laboratory National Institute of Standards and Technology ... STANDARD. ... (See test Ci )i3A. ...

1989-08-18

260

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

261

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

262

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 are potential areas ...

1981-11-01

264

Fire Safety Concerns in Space Operations - NASA Technical Reports ...  

Science.gov (United States)

familiarity fire triangle (i.e., fuel, oxidant, and ignition source) are excluded. It Is obvious that for the baseline safety goal for spacecraft this ...

265

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

266

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

267

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

268

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

270

Standardization of rules for manufacturing normal electrical equipment for mining  

Energy Technology Data Exchange (ETDEWEB)

Information is provided about standardization and unification of rules for manufacturing normal electrical equipment designed for operating in underground shafts when there is no danger of explosion of gas, dust or steam. An analysis is made of the requirements included in the CEMA standard and in the state standard.

1983-01-01

271

PRA QUALITY IN REGULATORY DECISIONS  

Science.gov (United States)

ASME PRA STANDARD FOR PRA. FOR NPP APPLICATION. " Provides a Standard for performing and using a. PRA. Definitions. Risk assessment ...

273

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

274

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

276

Thermal reactor safety  

International Nuclear Information System (INIS)

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.

1990-09-01

277

Thermal reactor safety  

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

278

Table of Contents  

British Library Electronic Table of Contents (United Kingdom)

Abstract Overall Numbers Small, But Study Finds SSRI Exposure, Autism Link Additional Drug Safety, Efficacy Data Needed for Pediatric Bipolar Disorder SGA Safety and Efficacy in Children and Adolescents Aripiprazole Safety and Tolerability for Irritability in Autism No Lisdexamfetamine Effect on Sleep Disturbances in Children With ADHD Sickle Cell Disease With Comorbid Depression Homeopathy in Psychiatry Manic Symptoms Induced by Marijuana in a Healthy Adolescent New Warnings Safety Labeling Changes

2011-01-01

280

Optimization of the availability-safety pair for propulsion boilers; Optimisation du couple, disponibilite - surete pour les chaufferies de propulsion  

Energy Technology Data Exchange (ETDEWEB)

The relations between nuclear energy availability and nuclear plant safety are analyzed in the particular cases of naval propulsion nuclear boilers (aircraft carriers, submarines): safety objectives, present and potential risk analysis, optimization of the availability-safety couple, at the design stage and during operation (procedural rules related to the boiler state, real time decisions). 6 fig., 1 tab.

1994-12-31

283

Integrated Safety Management System Phase I Verification for the Plutonium Finishing Plant (PFP) [VOL 1 & 2  

Energy Technology Data Exchange (ETDEWEB)

U.S. Department of Energy (DOE) Policy 450.4, Safety Management System Policy commits to institutionalizing an Integrated Safety Management System (ISMS) throughout the DOE complex as a means of accomplishing its missions safely. DOE Acquisition Regulation 970.5204-2 requires that contractors manage and perform work in accordance with a documented safety management system.

2000-01-10

285

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

286

Cold Vacuum Drying (CVD) Facility Technical Safety Requirements  

Energy Technology Data Exchange (ETDEWEB)

The Technical Safety Requirements (TSRs) for the Cold Vacuum Drying Facility define acceptable conditions, safe boundaries, bases thereof, and management or administrative controls required to ensure safe operation. Controls required for public safety, significant defense-in-depth, significant worker safety, and for maintaining radiological and toxicological consequences below risk evaluation guidelines are included.

1999-12-16

287

The Waste Management Plan integration into Decommissioning Plan of the WWR-S research reactor from Romania  

International Nuclear Information System (INIS)

The paper presents the progress of the Radioactive Waste Management Plan which accompanies the Decommissioning Plan for research reactor WWR-S located in Magurele, Ilfov, near Bucharest, Romania. The new variant of the Decommissioning Plan was elaborated taking into account the IAEA recommendation concerning radioactive waste management. A new feasibility study for WWR-S decommissioning was also developed. The preferred safe management strategy for radioactive wastes produced by reactor decommissioning is outlined. The strategy must account for reactor decommissioning, as well as rehabilitation of the existing Radioactive Waste Treatment Plant and the upgrade of the Radioactive Waste Disposal Facility at Baita-Bihor. Furthermore, the final rehabilitation of the laboratories and reusing of cleaned reactor building is envisaged. An inventory of each type of radioactive waste is presented. The proposed waste management strategy is selected in accordance with the ...

2008-05-28

288

Status of IAEA CRP on Study of Process-Losses in Separation Processes in Partitioning and Transmutation Systems in View of Minimizing Long-Term Environmental Impacts  

Science.gov (United States)

Coordinated Research Project (CRP) was initiated in 2002 by IAEA to enable Member States in developing methodologies for reducing radio-toxic discharge to the environment from nuclear fuel cycle activities and in paving the way for sustainability of nuclear energy. In the past three Research Coordination Meetings (RCM), the following areas of research were examined upon: (1)Basic studies to compare dry partitioning process with aqueous partitioning process; (2)Defining proliferation resistance attributes of partitioning processes; (3) Advanced characterization methods for actinides for measuring the possible material holdup;( 4)Minimization of actinides losses in the waste fraction from the partitioning process;(5)Establishment of separation criteria of partitioning process to minimize environmental impact; and (6)Defining environmental impact associated with partitioning processes. The final TECDOC is currently being prepared to summarize the activities of this ...

2007-07-01

289

Pollution in the Gulf: Monitoring the marine environment  

International Nuclear Information System (INIS)

More than 2 years after the Gulf conflict, scientists are continuing to keep a close watch on marine pollution stemming from the war. Following the conflict in early 1991, major concern was raised worldwide when an estimated four to eight million barrels of crude oil were directly released into the Persian Gulf from the Sea Island terminal in Kuwait. Such amounts clearly made it the largest oil spill in history. The catastrophe was exacerbated when Kuwaiti oil fields were ignited. The magnitude of the pollution, and the types of toxic contaminants involved, led to a worldwide response through the United Nations system. An inter-agency plan of action was developed quickly. As one of its steps, the co-ordinating agency - the United Nations Environment Programme (UNEP) - asked the IAEA's Marine Environment Laboratory (MEL) in Monaco to help make a preliminary assessment of the situation. The Laboratory's main goal in initial surveys was to map the extent and general ...

290

Physical aspects of quality assurance in radiotherapy: A protocol for quality control  

International Nuclear Information System (INIS)

In consistency with the increasing requests from Member States for establishing radiotherapy programmes, an IAEA Technical Co-operation project was initiated in Latin America aimed at improving the physical aspects (as a complement to the clinical issues) of quality assurance in radiotherapy; this ARCAL XXX project (RLA/6/032) was classified as a Model Project of the IAEA. Among the important outcomes of the project were (i) the training of a considerable number of medical physicists in hospitals of the region, (ii) the development of a protocol for quality control procedures, and (iii) the organization of quality audit site visits (to the participant countries) where the implementation in hospitals of the developed quality control procedures is verified. The present publication is the protocol for quality control of the physical aspects of radiotherapy. It contains detailed procedures on what should be measured by a medical physicist in a ...

2009-06-21

291

Challenges in validating the sterilisation dose for processed human amniotic membranes  

Energy Technology Data Exchange (ETDEWEB)

Most of the tissue banks in the Asia Pacific region have been using ionising radiation at 25 kGy to sterilise human tissues for save clinical usage. Under tissue banking quality system, any dose employed for sterilisation has to be validated and the validation exercise has to be a part of quality document. Tissue grafts, unlike medical items, are not produced in large number per each processing batch and tissues relatively have a different microbial population. A Code of Practice established by the International Atomic Energy Agency (IAEA) in 2004 offers several validation methods using smaller number of samples compared to ISO 11137 (1995), which is meant for medical products. The methods emphasise on bioburden determination, followed by sterility test on samples after they were exposed to verification dose for attaining of sterility assurance level (SAL) of 10{sup -1}. This paper describes our experience in using the IAEA Code of Practice in ...

2007-11-15

292

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 designers seeking to optimize inherent ...

1985-07-01

293

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 designers seeking to optimize inherent ...

1985-04-21

294

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

295

Development of Reliability Data Management System (RDMS) for safety systems of PHWR type plants  

International Nuclear Information System (INIS)

The Reliability Data Management System (RDMS) for safety systems of PHWR type plants has been developed and utilized in the reliability analysis of the special safety systems of Wolsong Unit 1 with plant overhaul period lengthened. The RDMS is developed for the periodic efficient reliability analysis of the safety systems of Wolsong Unit 1. In addition, this system provides the function of analyzing the effects on safety system unavailability if the test period of a test procedure changes as well as the function of optimizing the test periods of safety-related test procedures. The RDMS can be utilized in handling the requests of the regulatory institute actively with regard to the reliability validation of safety systems.

1999-10-01

296

Development and application of technology-neutral safety requirements for the regulation of new nuclear power reactors  

International Nuclear Information System (INIS)

This paper explores the current trends in development of technology-neutral safety requirements to be used in the regulation of future nuclear power reactors and the role of the quantitative safety goals in the design of reactor safety systems. Establishing the requirements concerning the reliability of safety functions rather than on particular systems employed to achieve the functions, as well as the use of the recommendations of the International Commission on Radiological Protection (ICRP) on protection against potential exposure could form the basis of a technology-neutral framework for safety requirements on new reactor designs. Also it could contribute to international harmonisation of nuclear safety assessment practices as part of the licensing processes for future nuclear power plants. (author)

2009-10-12

297

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 Europe's 2020 goals. Accordingly, most ...

2009-10-12

298

MANAGEMENT PRE-START REVIEW FINAL REPORT FOR THE BIOSAFETY LEVEL 3 (BSL-3) FACILITY (B368) LAWRENCE LIVERMORE NATIONAL LABORATORY  

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 incident involving select agents. The MPR was restarted in mid-June of 2006. ...

2006-07-25

299

Use of stable isotopes in developing countries: safe markers for nutrition regime study  

International Nuclear Information System (INIS)

Possible use of stable radioisotopes in studies on nutrition and medicine problems that may be used in investigations of babies, children, pregnant women is shown. Attention is paid to behaviour of limited number of elements: hydrogen, carbon, nitrogen, oxygen. The IAEA plans implementation of a new coordinated research program on use of stable isotopes for studying nutrition problems and related diseases. The program emphasis will be placed on protein metabolism measurements and estimation of energy consumption in control population groups in developing countries.

300

Self-consistent electric field effect on electron transport of ECH plasmas  

Energy Technology Data Exchange (ETDEWEB)

An algorithm is proposed which treats the ECH generated potential in a self-consistent way, by extending the Monte-Carlo Fokker-Planck method used by Murakami [S. Murakami et al., Proc. 17th IAEA Fusion Energy Conference, Yokohama, 1998 (International Atomic Energy Agency, Vienna, in press), paper CN-69/TH2/1]. The additional physics is expected to influence the transport of both thermal and suprathermal electrons in a helical toroidal system. (author)

1999-02-01

301

Production of "9"9Tc"m radiopharmaceuticals for brain, heart and kidney imaging. Final report of a co-ordinated research programme 1991-1994  

International Nuclear Information System (INIS)

The report contains highlights of the achievements of the IAEA Co-ordinated Research programme on Evaluation on the Use of Bulk Reagents for the Production of "9"9Tc_m Radiopharmaceutical and Kits, the participants' summary reports (Argentina, Chile, Greece, India, Indonesia, Japan, Malaysia, Portugal, Russian Federation, Thailand, Uruguay, United States of America), recommended product protocols for five compounds and the participants' recommendations regarding continued support and further directions of co-ordinated research work. Refs, 6 figs, 8 tabs, 6 schemes.

1990-06-24

302

Potential vulnerabilities of nuclear fuel cycle facilities to the year 2000 (Y2K) issue and measures to address them  

International Nuclear Information System (INIS)

The exchange of information and experience among Member Sates is an essential component of the IAEA action plan for addressing the Year 2000 problem. The objective is to enable Member States to identify any gaps in their own conversion programmes, benefit form the experience of others in developing remedial actions and establish the basis for future action to solve remaining problems. Experts in Year 2000 issues particularly those related to digital equipment prepared this report dealing with nuclear fuel cycle facilities

1993-04-18

303

IAEA Coordinated Research Project: Updated decay data library for actinides  

Energy Technology Data Exchange (ETDEWEB)

Recommended nuclear decay data for specific actinides are important in fuel-cycle studies for thermal and fast reactors and inventory studies for safeguards. Therefore, a programme of work was initiated in 2005 to improve the actinide decay data library of the International Atomic Energy Agency through the efforts of a Coordinated Research Project (CRP). The proposed contents of the new database are described, including the agreement to include additional actinides and a significant number of natural decay chain radionuclides. This work is on-going, and is estimated for completion in 2009/10.

2008-06-15

304

Human dietary intakes of trace elements: A global literature survey mainly for the period 1970-1991: 1. Data listings and sources of information  

International Nuclear Information System (INIS)

A database has been compiled on human dietary intakes of trace elements by populations groups living in various countries. The main sources of information used were (1) publications in the open scientific literature, and (2) data submitted to the IAEA in response to a questionnaire. The database contains 1,758 intake values covering 35 elements and 47 countries. In this report the data are listed in various ways to facilitate identification of intake values for any specified country, element and population group. 4 refs, 5 tabs.

305

NRC safety research in support of regulation--FY 1989  

Energy Technology Data Exchange (ETDEWEB)

This report, the fifth in a series of annual reports, was prepared in response to congressional inquiries concerning how nuclear regulatory research is used. It summarizes the accomplishments of the Office of Nuclear Regulatory Research during FY 1989. The goal of this office is to ensure that safety-related research provides the technical bases for rulemaking and for related decisions in support of NRC licensing and inspection activities. This research is necessary to make certain that the regulations that are imposed on licensees provide an adequate margin of safety so as to protect the health and safety of the public. This report describes both the direct contributions to scientific and technical knowledge with regard to nuclear safety and their regulatory applications.

1990-04-01

306

NRC safety research in support of regulation, FY 1991. Volume 6  

Energy Technology Data Exchange (ETDEWEB)

This report, the seventh in a series of annual reports, was prepared in response to congressional inquiries concerning how nuclear regulatory research is used. It summarizes the accomplishments of the Office of Nuclear Regulatory Research during FY 1991. The goal of this office is to ensure that safety-related research provides the technical bases for rulemaking and for related decisions in support of NRC licensing and inspection activities. This research is necessary to make certain that the regulations that are imposed on licensees provide an adequate margin of safety so as to protect the health and safety of the public. This report describes both the direct contributions to scientific and technical knowledge with regard to nuclear safety and their regulatory applications.

1992-04-01

307

NRC safety research in support of regulation, FY 1991  

Energy Technology Data Exchange (ETDEWEB)

This report, the seventh in a series of annual reports, was prepared in response to congressional inquiries concerning how nuclear regulatory research is used. It summarizes the accomplishments of the Office of Nuclear Regulatory Research during FY 1991. The goal of this office is to ensure that safety-related research provides the technical bases for rulemaking and for related decisions in support of NRC licensing and inspection activities. This research is necessary to make certain that the regulations that are imposed on licensees provide an adequate margin of safety so as to protect the health and safety of the public. This report describes both the direct contributions to scientific and technical knowledge with regard to nuclear safety and their regulatory applications.

1992-04-01

308

NRC safety research in support of regulation, FY 1990  

Energy Technology Data Exchange (ETDEWEB)

This report, the sixth in a series of annual reports, was prepared in response to congressional inquiries concerning how nuclear regulatory research is used. It summarizes the accomplishments of the Office of Nuclear Regulatory Research during FY 1990. The goal of this office is to ensure that safety-related research provides the technical bases for rulemaking and for related decisions in support of NRC licensing and inspection activities. This research is necessary to make certain that the regulations that are imposed on licensees provide an adequate margin of safety so as to protect the health and safety of the public. This report describes both the direct contributions to scientific and technical knowledge with regard to nuclear safety and their regulatory applications.

1991-04-01

309

NRC safety research in support of regulation, 1988  

Energy Technology Data Exchange (ETDEWEB)

This report, the fourth in a series of annual reports, was prepared in response to Congressional inquiries concerning how nuclear regulatory research is used. It summarizes the accomplishments of the Office of Nuclear Regulatory Research during 1988. The goal of this office is to ensure that safety-related research provides the technical bases for rulemaking and for related decisions in support of NRC licensing and inspection activities. This research is necessary to make certain that the regulations that are imposed on licensees provide an adequate margin of safety so as to protect the health and safety of the public. This report describes both the direct contributions to scientific and technical knowledge with regard to nuclear safety and their regulatory applications.

1989-05-01

310

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

311

The Waste Isolation Pilot Plant: A Success Story with International Cooperation  

Energy Technology Data Exchange (ETDEWEB)

The U.S. Department of Energy (DOE) Carlsbad Field Office (CBFO) administers and operates the Waste Isolation Pilot Plant (WIPP) site, which hosts a deep geologic repository for safe disposal of U.S. defense-related TRU waste and is located 42 kilometers (km) east of Carlsbad, New Mexico. CBFO also manages the National Transuranic Waste Program (NTP), which oversees TRU waste management from generation to disposal. The WIPP began receiving waste in March 1999. In some areas of broad international interest, the CBFO has developed a leading expertise through its 25-year WIPP repository and TRU waste characterization activities. In addition to participating in relevant and beneficial experiments, the CBFO will provide the international community convenient access to this information by sponsoring and hosting symposia and workshops on relevant topics and by participation in international waste management organizations and topical meetings. In recognition of the successes at WIPP, the Inter ...

2002-02-26

312

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

313

Low-pH injection grout for deep repositories. Summary report from a co-operation project between NUMO (Japan), Posiva (Finland) and SKB (Sweden)  

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. ...

2005-06-01

314

The EPA (Environmental Protection Agency) low-level waste standard-a status report  

Energy Technology Data Exchange (ETDEWEB)

The Environmental Protection Agency (EPA) is developing generally applicable environmental standards for land disposal of Atomic Energy Act (AEA) low-level radioactive wastes (LLW) and certain naturally occurring and accelerator-produced radioactive material (NARM) wastes. It is EPA's intention that the LLW standards will protect public health and the environment. The LLW standards would cover disposal of all AEA materials not controlled by other EPA standards and some natural radioactive materials. Coverage of federal waste is significant, because the federal government generates and disposes of >40% of all LLW nationwide, and a uniform standard for all LLW disposal is both a desirable and an achievable goal. Publication of a proposed LLW standard is planned in 1988, and a final standard a year later. This ...

1988-01-01

315

Safety significance of ATR passive safety response attributes  

International Nuclear Information System (INIS)

The Advanced Test Reactor (ATR) at the Idaho National Engineering Laboratory was designed with some passive safety response attributes which contribute to the safety of the facility. The three passive safety attributes being evaluated in the paper are: 1) In-core and in-vessel natural convection cooling, 2) a passive heat sink capability of the ATR primary coolant system (PCS) for the transfer of decay power from the uninsulated piping to the confinement, and 3) gravity feed of emergency coolant makeup. The safety significance of the ATR passive safety response attributes is that the reactor can passively respond to most transients, given a reactor scram, to provide adequate decay power removal and a significant time for operator action should the normal active heat removal systems and their backup systems both fail. The ATR Interim Level 1 Probabilistic Risk Assessment (PRA) models ...

1990-03-01

316

The WHO patient safety curriculum guide for medical schools.  

Science.gov (United States)

BACKGROUND: The urgent need for patient safety education for healthcare students has been recognised by many accreditation bodies, but to date there has been sporadic attention to undergraduate/graduate medical programmes. Medical students themselves have identified quality and safety of care as an important area of instruction; as future doctors and healthcare leaders, they must be prepared to practise safe healthcare. Medical education has yet to fully embrace patient safety concepts and principles into existing medical curricula. Universities are continuing to produce graduate doctors lacking in the patient safety knowledge, skills and behaviours thought necessary to deliver safe care. A significant challenge is that patient safety is still a relatively new concept and area of study; thus, many medical educators are unfamiliar with the literature and unsure how to integrate ...

2010-12-01

317

Republished paper: The WHO patient safety curriculum guide for medical schools.  

Science.gov (United States)

BACKGROUND: The urgent need for patient safety education for healthcare students has been recognised by many accreditation bodies, but to date there has been sporadic attention to undergraduate/graduate medical programmes. Medical students themselves have identified quality and safety of care as an important area of instruction; as future doctors and healthcare leaders, they must be prepared to practise safe healthcare. Medical education has yet to fully embrace patient safety concepts and principles into existing medical curricula. Universities are continuing to produce graduate doctors lacking in the patient safety knowledge, skills and behaviours thought necessary to deliver safe care. A significant challenge is that patient safety is still a relatively new concept and area of study; thus, many medical educators are unfamiliar with the literature and unsure how to integrate ...

2011-04-01

318

Uranium hexafluoride production plant decommissioning; Descomissionamento de uma usina de producao de hexafluoreto de uranio  

Energy Technology Data Exchange (ETDEWEB)

The Institute of Energetic and Nuclear Research - IPEN is a research and development institution, located in a densely populated area, in the city of Sao Paulo. The nuclear fuel cycle was developed from the Yellow Cake to the enrichment and reconversion at IPEN. After this phase, all the technology was transferred to private enterprises and to the Brazilian Navy (CTM/SP). Some plants of the fuel cycle were at semi-industrial level, with a production over 20 kg/h. As a research institute, IPEN accomplished its function of the fuel cycle, developing and transferring technology. With the necessity of space for the implementation of new projects, the uranium hexafluoride (UF{sub 6}) production plant was chosen, since it had been idle for many years and presented potential leaking risks, which could cause environmental aggression and serious accidents. This plant decommission required accurate planning, as this work had not been carried out in Brazil before, for this type of facility, and ...

2008-07-01

319

The thematic plant life assessment network (PLAN)  

Energy Technology Data Exchange (ETDEWEB)

The Plant Life Assessment Network (PLAN) is a Brite Euram Type II Thematic Network, initiated by the European Commission to facilitate structured co-operation between all cost shared action projects already funded by the Commission which fall under this common technical theme. The projects involved address a multiplicity of problems associated with plant life assessment and are drawn from Brite-Euram, Standards, Measurement and Testing, Nuclear Fission Safety and Esprit EC programmes. The main aim of the Network is to initiate, maintain and monitor a fruitful co-operation process between completed, ongoing and future EC R and D projects, thereby promoting improved cross fertilization and enhanced industrial exploitation of R and D results. As the project is in its infancy, this presentation covers the background to the initiative in some detail. In particular two key aspects are highlighted, namely, the requirement of the EC to launch such a ...

1998-12-31

320

TRIGA reactor spent fuel pool under severe earthquake conditions  

International Nuclear Information System (INIS)

Supplemental criticality safety analysis of a pool type storage for TRIGA spent fuel at 'Jozef Stefan' Institute in Ljubljana, Slovenia, is presented. Previous results (Ravnik, M, Glumac, B., 1996) have shown that subcriticality is not guaranteed for some postulated accidents. To mitigate this deficiency, a study was made about replacing a certain number of fuel elements in the rack with absorber rods (Glumac, B., Ravnik, M., Logar, M., 1997) to lower the supercriticality probability, when the pitch is decreased to contact (as a consequence of a severe earthquake) in a square arrangement. The criticality analysis for the hexagonal contact pitch is presented in this paper, following the same scenario as outlined above. The Monte Carlo computer code MCNP4B with ENDF-B/VI library and detailed three dimensional geometry was used. First, the analysis about the influence of the number of triangular fuel piles on the bottom that could appear, if the fuel rack, made of ...

1998-07-01

321

Spent fuel transportation cask response to a tunnel fire scenario  

Energy Technology Data Exchange (ETDEWEB)

On July 18, 2001, a freight train carrying hazardous (non-nuclear) materials derailed and caught fire while passing through the Howard Street railroad tunnel in downtown Baltimore, Maryland. The United States Nuclear Regulatory Commission (USNRC), one of the agencies responsible for ensuring the safe transportation of radioactive materials in the United States, undertook an investigation of the train derailment and fire to determine the possible regulatory implications of this particular event for the transportation of spent nuclear fuel by railroad. Shortly after the accident occurred, the USNRC met with the National Transportation Safety Board (NTSB), the U.S. agency responsible for determining the cause of transportation accidents, to discuss the details of the accident and the ensuing fire. Following these discussions, the USNRC assembled a team of experts from the National Institute of Standards and Technology (NIST), the Center for ...

2004-07-01

322

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

323

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 Environmental Monitoring ...

1998-06-01

324

Municipal solid waste management in Africa: Strategies and livelihoods in Yaounde, Cameroon  

International Nuclear Information System (INIS)

This paper provides an overview of the state of municipal solid waste (MSW) management in the capital of Cameroon, Yaounde, and suggests some possible solutions for its improvement. The institutional, financial, and physical aspects of MSW management, as well as the livelihoods of the population, were analyzed. Our study revealed that distances and lack of infrastructure have a major impact on waste collection. Garbage bins are systematically mentioned as the primary infrastructure needed by the population in all quarters, whether it be a high or low standard community. The construction of transfer stations and the installation of garbage bins are suggested as a solution to reduce distances between households and garbage bins, thus improving waste collection vehicle accessibility. Transfer stations and garbage bins would enable the official waste collection company to expand its range of services and significantly improve waste collection rates. Several transfer ...

2009-02-01

325

Multi-rotor-stations, a new concept for large-scale wind power stations; Multi-Rotor-Konstruktionen. Ein neues Konzept fuer grosse Windkraftanlagen  

Energy Technology Data Exchange (ETDEWEB)

As an alternative to the usual way of installing wind machines in extended windfarms new concepts are being developed. Several wind turbines are affixed to one support structure and can be aligned together. Drafts of steel constructions developed by students in three diploma theses are presented. The attempt to transform existing design standards requires extensive discussion of possible influence scenarios. Several concepts regarding structure and safety elements are described and evaluated. The design of the support structure is to be seen as a first step to the practicability of the whole concept. A preliminary mass calculation and a specification of further cost factors facilitates the comparison to conventional wind power stations. (orig.) [Deutsch] Als Alternative zur ueblichen Praxis, Windenergieanlagen in Form grossflaechiger Windparks zu bauen, werden Konzepte entwickelt, bei denen mehrere Konverter an einem Tragwerk angeordnet und ...

1996-06-01

326

MOX in reactors: present and future  

International Nuclear Information System (INIS)

In Europe, MOX fuel has been supplied by AREVA for more than 30 years, to 36 reactors: 21 in France, 10 in Germany, 3 in Switzerland, 2 in Belgium. For the present and future, recycling is compulsory in the frame of sustainable development of nuclear energy. By 2030 the overall volume of used fuel will reach about 400 000 t worldwide. Their plutonium and uranium content represents a huge resource of energy to recycle. That is the reason why, the European Utilities issued an EUR (European Utilities Requirement) demanding new builds reactors to be able of using MOX Fuel Assemblies in up to 50 % of the core. AREVA GEN3+ reactors, like EPR"T"M or ATMEA"T"M designed with MHI partnership, are designed to answer any utility need of MOX recycling. The example of the EPR"T"M reactor operated with 100 % MOX core optimized for MOX recycling will be presented. A standard EPR"T"M can be operated with 100 % MOX core using an advanced homogeneous MOX (single Pu content) with ...

327

Inherent safe heat removal in advanced medium-sized high-temperature reactors  

International Nuclear Information System (INIS)

One of the main points for the inherent safety of a pebble bed high temperature reactor (HTR) is to guarantee the safe removal of the after-heat in case of a break-down of all active cooling systems like heat-exchangers or liner-cooling. This will be necessary because it is well known today that graphite pebble bed fuel elements stay intact, if the accident temperature is below 1600 deg. C. Therefore the heat must be taken out of the reactor system by passive, natural law heat-transfer mechanism so that the maximum fuel temperature stays below the specified limit. Today medium-sized HTRs with a power of 750 MW_t_h and more (TGTR-300, HTR 500) reach temperatures of more than 2400 deg. C in small parts of the core in such hypothetical accidents. A possible way to realize the inherent safe heat removal in advanced medium-sized HTRs is to change the form of the core. Instead of employing the standard cylindrical geometry a plate shaped core should ...

1990-04-01

328

Highly enriched isotope samples of uranium and transuranium elements for scientific investigation  

International Nuclear Information System (INIS)

The paper describes the production of highly enriched isotopes of uranium, plutonium, americium and curium by electromagnetic separation for scientific and applied researches in physics, chemistry, geology, medicine, biology and other fields. Using the equipment described, the isotopes are produced in quantities sufficient to set up nuclear physical experiments, to produce nuclear reference materials and standard sources for calibration of radiometrical and mass spectrometrical equipment, in radionuclide metrology, etc. For the following isotopes the indicated degrees of isotopic enrichment were achieved: "2"3"3U-99.97%; "2"3"5U-99.97%; "2"3"6U-98.0%; "2"3"8U-99.997%; "2"3"8Pu-99.6%; "2"3"9Pu-99.9977%; "2"4"0Pu-99.9-100%; "2"4"1Pu-96.998%; "2"4"2Pu-97.8-99.96%; "2"4"4Pu-96.7%; "2"4"1Am-99.6%; "2"4"2"mAm-73.6%; "2"4"3Am-99.2-99.94%; "2"4"3Cm-99.99%; "2"4"5Cm-99.998%; "2"4"6Cm-99.8%; "2"4"7Cm-90%, "2"4"8Cm-97%. Methods for preparing layers of highly enriched isotopes ...

329

HEXTRAN-SMABRE calculation of the 6th AER Benchmark, main steam line break in a WWER-440 NPP  

International Nuclear Information System (INIS)

The sixth AER benchmark is the second AER benchmark for couplings of the thermal hydraulic codes and three dimensional neutron kinetic core models. It concerns a double end break of one main steam line in a WWER-440 plant. The core is at the end of its first cycle in full power conditions. In VTT HEXTRAN2.9 is used for the core kinetics and dynamics and SMABRE4.8 as a thermal hydraulic model for the primary and secondary loop. The plant model for SMABRE consists mainly of two input models, Loviisa model and a standard WWER-440/213 plant model. The primary loop includes six separate loops, the pressure vessel is divided into six parallel channels in SMABRE and the whole core calculation is performed in the core with HEXTRAN. The horizontal steam generators are modelled with heat transfer tubes in five levels and vertically with two parts, riser and downcomer. With this kind of detailed modelling of steam generators there occurs strong flashing after break opening. ...

2003-11-01

330

GE's advanced nuclear reactor designs  

International Nuclear Information System (INIS)

The excess of US electrical generating capacity which has existed for the past 15 years is coming to an end as we enter the 1990s. Environmental and energy security issues associated with fossil fuels are kindling renewed interest in the nuclear option. The importance of these issues are underscored by the National Energy Strategy (NES) which calls for actions which open-quotes are designed to ensure that the nuclear power option is available to utilities.close quotes Utilities, utility associations, and nuclear suppliers, under the leadership of the Nuclear Power Oversight Committee (NPOC), have jointly developed a 14-point strategic plan aimed at establishing a predictable regulatory environment, standardized and pre-licensed Advanced Light Water Reactor (ALWR) nuclear plants, resolving the long-term waste management issue, and other open-quotes enabling conditions.close quotes GE is participating in this national effort and GE's family of advanced nuclear power ...

1993-07-01

331

Emissions, activity data, and emission factors of fluorinated greenhouse gases (F-Gases) in Germany 1995-2002  

Energy Technology Data Exchange (ETDEWEB)

Before the 1997 Kyoto Protocol on Climate Protection, the fluorinated greenhouse gases HFCs, PFCs, and SF6 (F-gases) aroused little public attention. Since then, the standards on surveying and reporting on national emissions have been rising constantly. Amongst others, the annual reporting to the UNFCCC secretariat makes detailed declarations on use and emissions of F-gases necessary, which have to be filled in specified formats for submission (Common Reporting Format = CRF). The scientific basis has been set out by the UNFCCC guidelines on reporting, in accordance with the instructions laid down in IPCC good practice guidance. Additionally, in Germany the Centralised System of Emissions (ZSE) shall provide a suitable tool to satisfy any quality needs of both activity data and emission factors. From 1995 onwards, activity data and emissions of each individual application sector shall be presented in a comprehensible and transparent way. Therefore, the way of data ...

2005-06-15

332

Disposal of old heads for Daya Bay NPP  

International Nuclear Information System (INIS)

The paper introduces the disposal procedures of the old reactor pressure vessel head. Reactor pressure vessel (RPV) heads were replaced successfully in Daya Bay Nuclear Power Plant. The on-site treatment and disposal of replaced heads was thereafter implemented. This is the first time in China for large size radioactive article disposal. To guarantee the safety of old head treatment, issues of radiation protection have to be taken into account. Dose rate distribution of the old head surface and radioactivity were initially calculated according to the operation history and the neutron flux rate of the reactor. Shielding calculation and package design was thereafter worked out based on the data obtained from the old head, e.g. neutron flux, sorts of nuclides, radioactivity and dose rates. Shielding package was afterwards manufactured in special factories and transported to Daya Bay NPP site by truck and ship. The shielding package was designed relatively simple, ...

333

Basic aspects of the concept of reactor compartment (including damaged compartments) management during utilization of nuclear powered submarines -- High priority R and D  

International Nuclear Information System (INIS)

Large-scale decommissioning of Russian nuclear-powered submarines (NPS) and their utilization prospects gave rise to numerous complicated scientific and technical, as well as economic, problems. Problems of handling of radioactive equipment from the reactor compartments (RC) are among the vital ones, arousing a growing concern with the public. Without solution of the problems the processes of NPS utilization can not be considered completed. It involves potential hazard, for the environment both from NPS being paid up (temporal on-float storage) with unloaded spent nuclear fuel (SNF), and RC, cut from submarine hull, containing highly radioactive equipment and materials but no SNF. Diverse variations of the concept of reactor compartment handling of NPS subject to, utilization are possible, but, in principle, there are essentially two variants: (1) RC utilization directly in the course of NPS utilization, envisaging removal of radioactive equipment from the reactor compartment and its ...

1996-03-10

334

BMBF. The biotechnology 2000 project. Annual report 1994; BMBF. Programm Biotechnologie 2000. Jahresbericht 1994  

Energy Technology Data Exchange (ETDEWEB)

The `biotechnology 2000` project is supervised by the project sponsor `biology, energy, ecology` at Forschungszentrum Juelich on behalf of the Federal Ministry for Research and Technology. The project activities cover the development of techniques and methods, cell biology, gene structure and gene regulation, photosynthetic production processes, biological hydrogen production, synthetic biology, protein design, neurobiological research, biosystems, plant breeding, phytomedicine and plant protection, the biology of waste disposal methods, research into methods which replace animal experiments, biological safety research, technology risk assessment, and ethical aspects. A general survey introduces the promoted projects, and standardized data sheets briefly introduce the individual activities. The appendix gives the project indices, the indices of joint projects, a list of the supported companies and institutions, and the project sponsor ...

1995-11-01

335

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 for those criteria ...

2009-10-15

336

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 for those criteria ...

2009-10-01

337

Research and development on next generation reactor (phase I)  

Energy Technology Data Exchange (ETDEWEB)

The objective of the study is to improve the volume of nuclear power plant which adopts passive safety system concept. The passive safety system reactor is characterized by excellent safety and reliability. But the volume of NSSS (Nuclear Steam Supply System) of the passive safety system reactor is so small that it should be upgraded for commercial operation. For volume upgrade, detailed analyses are performed as follows; core design, hydraulics, design and mechnical structures, and safety analysis. In addition to above analysis, some investigations must be supplied as follows: power density vs. DNB margin decrease, outlet temperature vs. EPRI-URD, additional tests for upgraded reactor, dynamic analysis of mechanical vibration according to expanded reactor vessel and expanded in-core structures, and Merit loss of passive safety system reactor according to design ...

1994-10-01

338

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 develop better occupational health and safety ...

1988-04-01

339

Decree of the Czechoslovak Atomic Energy Commission No. 436/1990 on quality assurance of selected facilities with respect to nuclear safety of nuclear facilities  

International Nuclear Information System (INIS)

The Decree specifies basic quality assurance requirements applicable to machines, their parts and materials, civil engineering structures, means for automated control of technological processes including hardware and software, and electricity supply systems related to nuclear safety of nuclear facilities, and stipulates binding procedures for the implementation of technical and organizational provisions associated with the quality of selected equipment to ensure nuclear safety of nuclear facilities. Safety classes are defined for selected equipment. Requirements laid on safety assurance documentation are specified, and requirements placed on safety assurance programmes, their preparation, finalization and approval are defined. Quality assurance requirements are also specified with respect to the designing, manufacture, construction, operation, repair, modification and ...

1995-02-01

340

DOE explosives safety manual  

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 reflect the ...

1991-10-01

341

Vector Boson Scattering in the Standard Model an Overview of Formulae  

CERN Document Server

Tree-level scattering amplitudes of longitudinally polarized electroweak vector bosons in the Standard Model are calculated using Mathematica package Feyncalc. The modifications of low-energy theorems for longitudinally polarized W and Z in the Standard Model are discussed.

1997-01-01

342

System 80+{trademark} standard design: CESSAR design certification. Volume 15: Amendment I  

Energy Technology Data Exchange (ETDEWEB)

This report has been prepared in support of the industry effort to standardize nuclear plant designs. These documents describe the Combustion Engineering, Inc. System 80+{trademark} Standard Design.

1990-12-21

343

System 80+trademark standard design: CESSAR design certification  

International Nuclear Information System (INIS)

This report has been prepared in support of the industry effort to standardize nuclear plant designs. These documents describe the Combustion Engineering, Inc. System 80+trademark Standard Design.

344

Clinical pathology accreditation: standards for the medical laboratory  

UK PubMed Central (United Kingdom)

This article describes a new set of revised standards for the medical laboratory, which have been produced by Clinical Pathology Accreditation (UK) Ltd (CPA). The original standards have been in use...Full Text Available

2002-10-01

345

Benzene Enabling Document for Standards on Benzene Transfer and Waste Operations.  

Science.gov (United States)

On February 27, 1990, standards for Benzene were promulgated for benzene transfer and benzene waste operations. The benzene enabling document summarizes these standards. The basic purpose of the document is to assist the EPA regional enforcement personnel...

1990-01-01

346

Abnormalities in the microsomal oxidases of the WHO standard reference strain of Musca domestica*  

UK PubMed Central (United Kingdom)

Observations made during biochemical and toxicological studies of the housefly, in which the WHO standard reference (SR) strain was used as a standard, indicated that this strain differs from other...Full Text Available

1975-01-01

347

45 CFR 170.210 - Standards for health information technology to protect electronic health information created...  

Science.gov (United States)

...2010-10-01 false Standards for health information technology to protect electronic health information...DEPARTMENT OF HEALTH AND HUMAN SERVICES HEALTH INFORMATION TECHNOLOGY HEALTH INFORMATION TECHNOLOGY STANDARDS, IMPLEMENTATION...

2010-10-01

348

Use of gold and silver standards based on phenol-formalde-hyde resin in assay-activation analysis of geological samples  

International Nuclear Information System (INIS)

Using standards on phenol-formaldehyde resin base for assaying-activation analysis of geological specimens for gold and silver has bee the advantage of uniformly distributing Au and Ag in spesimens and possible preparing tablets of practically any form or size. The validity and accuracy of these standards have been studied for the cases of short irradiation. Conventional point standards were used as reference standards. The experiments carried out have shown that tablet resol standards are suitable for a mass assaying-activation analysis for gold and silver at practically any concentrations.

349

Development of an analysis rule of diagnosis error for standard method of human reliability analysis  

International Nuclear Information System (INIS)

This paper presents the status of development of Korea standard method for Human Reliability Analysis (HRA), and proposed a standard procedure and rules for the evaluation of diagnosis error probability. The quality of KSNP HRA was evaluated using the requirement of ASME PRA standard guideline, and the design requirement for the standard HRA method was defined. Analysis procedure and rules, developed so far, to analyze diagnosis error probability was suggested as a part of the standard method. And also a study of comprehensive application was performed to evaluate the suitability of the proposed rules.

2003-10-01

350

The Effects of Long Term Storage on Special Purpose Lead ...  

Science.gov (United States)

... Special Purpse Lead Azide Lot #I3A-4-62 ... Standard X-ray techniques are not sufficiently sensitive ... the National Bureau of Standards, and examined ...

1972-10-01

351

The Economic Strategy for German Unification  

Science.gov (United States)

... PERSONAL AUTHOR(S) ROY A. BROOKS, LTC i3a. ... gave the impression of an immediate increase in the standard ... high rate by German standards. ...

1993-02-19

352

The Development of a Dental Diagnostic Terminology  

UK PubMed Central (United Kingdom)

There is no commonly accepted standardized terminology for oral diagnoses. The purpose of this article is to report the development of a standardized dental diagnostic terminology by a work...Full Text Available

2011-01-01

353

STUDY OF METEOR WIND MEASUREMENT TECHNIQUES. ...  

Science.gov (United States)

... of a secondary standard (VCO) locally available. ... phase of the local secondary standards to the 10-min average of the phase of ... I3a - - \\.-e-~--. ...

1970-02-01

354

Impacts of Renewable Fuel and Electricity Standards on State Economies (Poster)  

Energy Technology Data Exchange (ETDEWEB)

This poster, submitted for the CU Energy Initiative/NREL Symposium on October 3, discusses the impacts of renewable fuel and electricity standards on state economies.

2006-10-03

355

Development of standard solutions for the Minergie standard; Standardloesungen - Entwicklung von Standardloesungen fuer den Minergie-Standard  

Energy Technology Data Exchange (ETDEWEB)

This final report for the Swiss Federal Office of Energy (SFOE) examines a project that aimed to define standard solutions for use in buildings built to meet Minergie low energy consumption standards. These standard solutions are to provide a way of meeting Minergie standards in an easy way and thus further the use of the standard and also assure quality at the same time. The report describes how the solutions were developed on the basis of a selection of existing Minergie buildings. For various combinations of heating systems - wood, wood/solar, heat pumps (brine-water and air-water), gas/solar and oil/solar - the appropriate U-values for various building elements are listed. The resulting Minergie forms and guides are listed.

2003-07-01

356

An Evaluation of a Technique for Using the Combat Training ...  

Science.gov (United States)

... proficiency, most Army personnel must shoot to the same standards required of ... Wild- flecken was to provide this standard range, but its scores ... I3a I] ...

1979-05-01

357

A PC-Based Imaging System for the Naval Postgraduate ...  

Science.gov (United States)

... 1 I3a TYPE OF REPORT 1 3b TIME COVERED ... Measured by this standard the system provides good results; it ... did not fully meet all the standards or ...

1989-09-01

358

50 (Fifty) Years of Research on Man in Flight  

Science.gov (United States)

... i3a. ... This pioneering research established the new Air Force standard for future ... Echols ,.stablished new standards for high- altitude long-range flight ...

1985-06-01

359

Safety of pull-type and introducer percutaneous endoscopic gastrostomy tubes in oncology patients: a retrospective analysis  

UK PubMed Central (United Kingdom)

BackgroundPercutaneous endoscopic gastrostomy (PEG) allows long-term tube feeding. Safety of pull-type and introducer PEG placement in oncology patients with head/neck or oesophageal...Full Text Available

360

Safety during the monitoring of diabetic patients: trial teaching course on health professionals and diabetics - SEGUDIAB study  

UK PubMed Central (United Kingdom)

BackgroundSafety for diabetic patients means providing the most suitable treatment for each type of diabetic in order to improve monitoring and to prevent the adverse effects of...Full Text Available

361

Relationship of pharmacokinetics and drug distribution in tissue to increased safety of amphotericin B colloidal dispersion in dogs.  

UK PubMed Central (United Kingdom)

The safety, pharmacokinetics, and distribution in tissue of an amphotericin B (AmB)-cholesteryl sulfate colloidal dispersion (ABCD) were compared with those of micellar amphotericin B-deoxycholate (m-AmB)....Full Text Available

1992-02-01

362

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

363

Performance Assessment of Wolsung Unit 2 Safety Grade Pumps using In-Service Test  

Energy Technology Data Exchange (ETDEWEB)

Nuclear power plant has several safety features and each safety feature is 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 by In-Service Test (IST). According to Ministry of Education, Science and Technology (MEST) Bulletin 2008-14, the safety functioned pumps and valves of all nuclear power plants of Korea Hydro and Nuclear Power Co. Ltd.(KHNP) have been tested to verify their performance of safety function. Each safety grade pump has own design requirement and should be tested to identify whether it could meet the requirement. Design requirements and test references of all safety grade pumps of Wolsung Nuclear Power Plant Unit 2 (Wolsung Unit 2) were examined in this study. And the results of the performance test of the ...

2008-10-15

364

Performance Assessment of Wolsung Unit 2 Safety Grade Pumps using In-Service Test  

International Nuclear Information System (INIS)

Nuclear power plant has several safety features and each safety feature is 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 by In-Service Test (IST). According to Ministry of Education, Science and Technology (MEST) Bulletin 2008-14, the safety functioned pumps and valves of all nuclear power plants of Korea Hydro and Nuclear Power Co. Ltd.(KHNP) have been tested to verify their performance of safety function. Each safety grade pump has own design requirement and should be tested to identify whether it could meet the requirement. Design requirements and test references of all safety grade pumps of Wolsung Nuclear Power Plant Unit 2 (Wolsung Unit 2) were examined in this study. And the results of the performance test of the ...

2008-10-01

365

OPERATION CASTLE. Radiological Safety. Volume 2.  

Science.gov (United States)

This report is designed to cover the overall Operation Castle radiological safety matters from the viewpoint of those issues of direct concern to Headquarters, Joint Task Force Seven. It was written for the express purpose of assisting in the development ...

1985-01-01

366

OPERATION CASTLE. Radiological Safety. Volume 1.  

Science.gov (United States)

This report is designed to cover the overall Operation Castle radiological safety matters from the viewpoint of those issues of direct concern to Headquarters, Joint Task Force Seven. It was written for the express purpose of assisting in the development ...

1985-01-01

367

Nuclear Regulatory Commission issuances, June 1984. Volume 19, No. 6  

Energy Technology Data Exchange (ETDEWEB)

This report includes the issuances received during the specified period from the Commission, the Atomic Safety and Licensing Appeal Boards, the Atomic Safety and Licensing Boards, the Administrative Law Judge, the Directors' Decisions, and the Denials of Petitions for Rulemaking.

1984-06-01

368

Nuclear Regulatory Commission issuances  

Energy Technology Data Exchange (ETDEWEB)

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM).

1982-02-01

369

Nuclear Regulatory Commission Issuances  

Energy Technology Data Exchange (ETDEWEB)

This report includes the issuances received during the specified period from the Commission (CLl), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), The Directors' Decisions (DD), and the Denials of Petitions For Rulemaking (DPRM).

1982-06-01

370

Nonclinical Safety Profile of Telbivudine, a Novel Potent Antiviral Agent for Treatment of Hepatitis B?  

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

371

Investigation of the radiological safety concerns and medical history of the late Joseph T. Harding, former employee of the Paducah Gaseous Diffusion Plant  

Energy Technology Data Exchange (ETDEWEB)

An ex-employee's claims that inadequate enforcement of radiation safety regulations allowed excess radiation exposure thereby causing his deteriorating health was not substantiated by a thorough investigation.

1981-03-01

372

Introduction and summary of the 13th meeting of the Scientific Group on Methodologies for the Safety Evaluation of Chemicals (SGOMSEC): alternative testing methodologies.  

UK PubMed Central (United Kingdom)

A workshop on alternative toxicological testing methodologies was convened by the Scientific Group on Methodologies for the Safety Evaluation of Chemicals (SGOMSEC) 26-31 January 1997 in Ispra, Italy,...Full Text Available

1998-04-01

373

FEMA Media Library: Fire Safety  

Science.gov (United States)

Install. Inspect. Protect. Smoke Alarm Campaign Video 10/28/2009 | 04:09 Cooking_4 Cooking Fire Safety: Watch What You Heat 10/26/2007 | 01:40 Cooking_3 Cooking Fire...

2011-08-20

374

Evaluation of the Sida Support to the Global Safety Partnership.  

Science.gov (United States)

The Global Road Safety Partnership (GRSP) is a global partnership of business, civil society and government working for sustained reduction of road accidents in developing and transition countries. GRSP, which started operations in 1999, has a global secr...

2004-01-01

375

Efficacy and safety of vigabatrin in the long-term treatment of refractory epilepsy  

UK PubMed Central (United Kingdom)

1 The long term safety and efficacy of vigabatrin has been studied in 254 patients with refractory epilepsy (82% with partial seizures) in 23 different clinics in eight European countries....Full Text Available

1989-01-01

376

Efficacy and safety of livwin (polyherbal formulation) in patients with acute viral hepatitis: A randomized double-blind placebo-controlled clinical trial  

UK PubMed Central (United Kingdom)

Objectives:The study was planned to evaluate the efficacy and safety of Livwin (polyherbal formulation) in acute viral hepatitis.Materials...Full Text Available

2010-10-01

377

Efficacy and safety of Ayurvedic medicines: Recommending equivalence trial design and proposing safety index  

UK PubMed Central (United Kingdom)

Ayurvedic drugs have begun to be evaluated in controlled clinical trials. The trials, often placebo controlled, are usually designed to demonstrate superiority. Though the results have been usually...Full Text Available

2010-07-01

378

Concomitant use of ibuprofen and paracetamol and the risk of major clinical safety outcomes  

UK PubMed Central (United Kingdom)

AIMSTo evaluate and compare the risk of specific safety outcomes in patients prescribed ibuprofen and paracetamol concomitantly with those in patients prescribed ibuprofen or paracetamol...Full Text Available

2010-09-01

379

Cardiovascular Safety of Degarelix: Results From a 12-Month, Comparative, Randomized, Open Label, Parallel Group Phase III Trial in Patients With Prostate Cancer  

UK PubMed Central (United Kingdom)

PurposeWe assessed the cardiovascular safety profile of degarelix, a new gonadotropin-releasing hormone antagonist.Materials...Full Text Available

2010-12-01

380

Thermodynamic Stable Metal Compositions  

International Science & Technology Center (ISTC)

Thermodynamic Stable Metal Compositions for Improvement of an Operational Safety of Constructional Materials under Conditions of Multifactor Loadings of an Aggressive Environment

381

Thermal-hydraulic testing on a Mitsubishi simplified PWR  

Energy Technology Data Exchange (ETDEWEB)

Mitsubishi is now developing a new Pressurized water reactor (PWR), the Mitsubishi simplified PWR (MS-PWR), which has the innovative features of hybrid safety systems (an optimum combination of passive and active systems) and cooling by horizontal steam generators. In order to confirm the feasibility of the Mitsubishi hybrid safety system, various kinds of safety analyses are performed for loss-of-coolant accident events. In parallel to these safety analysis efforts, the following thermal-hydraulic tests are to be performed: (1) thermal-hydraulic test of a horizontal steam generator; (2) integrated thermal-hydraulic test using a simulation loop for the innovative MS-PWR (SLIM).

1993-01-01

383

Safety analysis and justification for modification of auxiliary feed-water system in Daya Bay Nuclear Power Plant  

International Nuclear Information System (INIS)

The major feed-water line break accident is re-analyzed, which is based on Guangdong Daya Bay nuclear power station final safety analysis report, to justify the impacts of the decreasing of auxiliary feed-water flow rate on the safety margin in Daya Bay. The results showed that the accident analysis can meet the demands of acceptance criteria with the auxiliary feed-water flowrate decreasing from 45 m"3/h to 41.8 m"3/h, and enough safety margin is still retained

2002-06-01

384

Podcast: Viruses and Cooking  

Science.gov (United States)

The Podcast: Viruses and Cooking is a segment of the Web Seminar: Teaching Science with Food Safety , April 27 2010. The podcast is 14 minutes 11

1900-01-01

385

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

386

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

387

Man-made disasters: A cross-national analysis  

British Library Electronic Table of Contents (United Kingdom)

This research investigates the impact of national culture and several institutional factors on the safety performance of society and establishes statistically significant relationships between those variables. As expected, the research results reveal that some cultural variables such as uncertainty avoidance, gender orientation and institutional variables such as the degree of law avoidance can directly influence the safety performance of the society. The findings also support the inverted u-curve (Safety Kuznet curve) hypothesis indicating even if we expect a negative trend at the beginning stage of industrialization, we can expect a positive trend in safety performance as their income level continues to improve beyond a certain point.

2011-01-01

388

Ecologically clean prophylactic food addition from eatable mushroom  

International Nuclear Information System (INIS)

... Safety Institute, GRS, Cologne (Germany) INIS-UA--089 456 p. APPLIED LIFE

2001-04-18

389

Aviation Maintenance Safety Articles, January/February 1990  

Science.gov (United States)

... These are abnormal and an indication of NAVAIRINST 13340.3 identifies these laboratories a possible breakdown in the fuel-handling equip- ...

1990-02-01

390

An overview of FFTF [Fast Flux Test Facility] contributions to Liquid Metal Reactor Safety  

International Nuclear Information System (INIS)

The Fast Flux Test Facility has provided a very useful framework for testing the advances in Liquid Metal Reactor Safety Technology. During the licensing phase, the switch from a nonmechanistic bounding technique to the mechanistic approach was developed and implemented. During the operational phase, the consideration of new tests and core configurations led to use of the anticipated-transients-without-scram approach for beyond design basis events and the move towards passive safety. The future role of the Fast Flux Test Facility may involve additional passive safety and waste transmutation tests. 26 refs.

1990-11-11

391

Comparison of the Standards applied to Instrumentation and Control Systems for Nuclear Power Stations in Korea and Russia  

Energy Technology Data Exchange (ETDEWEB)

This report describes a comparison result of technical standards applied to instrumentation and control systems for nuclear power plants between in Korea and in Russia. Russia also has a state-run organization authorized to conduct approval, cancellation, and audit in use of nuclear facility or equipment. The Russian standards for nuclear instrumentation and control equipment are analogous with the Korean ones in the aspect of basic concepts and principles. However, there are some differences in document structure, design requirements, qualification test items, depth of contents between two standard systems. The biggest deviation exists in the standard documents for seismic qualification and electromagnetic interference qualification. Korean seismic qualification standard utilizing US approach, defines testing and qualification methods specifically and clearly. Russian ...

2005-04-15

392

Safety analysis and license of rod drop time issue at Daya Bay Nuclear Power Plant  

International Nuclear Information System (INIS)

The rod drop time event of the Daya Bay Nuclear Power Plant is caused by the malfunction of the guide tube developed by Framatome. Three temporary solutions were implemented successively and the long term solution was found in the process of searching for the root cause. The different solutions and the root cause are introduced. The safety analysis and license of the solutions are mainly discussed. Experiences and lessons are drawn by summarizing the important items related to nuclear safety.

393

Review and evaluation of the Nuclear Regulatory Commission safety research program for Fiscal Year 1983. Report to the Congress  

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

394

Review and evaluation of the Nuclear Regulatory Commission safety research program for Fiscal Year 1982. Report to the Congress  

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

395

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.

396

Reload safety analysis checklist of Daya Bay Nuclear Power Plant  

International Nuclear Information System (INIS)

The safety analysis checklist scope and the criteria of key parameters needed to be checked for Daya bay reload cycles are introduced. The INCORE code package was used for the safety evaluation of Daya bay unit 2 cycle 2. The method and the contents can not only be applicable for Daya Bay reload cycles but also for Qinshan 600 MW and Qinshan 300 MW reload cycles.

397

Quality assurance requirements for the computer software and safety analyses  

International Nuclear Information System (INIS)

The requirements are given as placed on the development, procurement, maintenance, and application of software for the creation or processing of data during the design, construction, operation, repair, maintenance and safety-related upgrading of nuclear power plants. The verification and validation processes are highlighted, and the requirements put on the software documentation are outlined. The general quality assurance principles applied to safety analyses are characterized. (J.B.). 1 ref.

398

Operation Castle. Radiological Safety. Volume 2. Final report  

Science.gov (United States)

This report is designed to cover the overall Operation Castle radiological safety matters from the viewpoint of those issues of direct concern to Headquarters, Joint Task Force Seven. It was written for the express purpose of assisting in the development of future radiological safety plans by presenting detailed discussion of the problems and solutions arising during Operation Castle.

1985-09-01

399

Operation Castle. Radiological Safety. Volume 1. Final report  

Science.gov (United States)

This report is designed to cover the overall Operation Castle radiological safety matters from the viewpoint of those issues of direct concern to Headquarters, Joint Task Force Seven. It was written for the express purpose of assisting in the development of future radiological safety plans by presenting detailed discussion of the problems and solutions arising during Operation Castle. Included is a discussion of fallout forecasting techniques.

1985-09-01

400

Health physics, safety and medical services report for 1989  

Energy Technology Data Exchange (ETDEWEB)

The Health Physics, Safety and Medical Services Report for Harwell Laboratory for 1989 includes data on the monitoring of the working environment, personnel monitoring, radiological incidents, disposal of radioactive waste and protection of the public. Work on emergency planning, non-radiological health and safety, occupational hygiene, operations support is also discussed. Finally the medical services available and the medical examinations performed are described. (UK).

1990-09-01

401

200 Area Interim Storage Area Technical Safety Requirements  

Energy Technology Data Exchange (ETDEWEB)

The 200 Area Interim Storage Area Technical Safety Requirements define administrative controls and design features required to ensure safe operation during receipt and storage of canisters containing spent nuclear fuel. This document is based on the 200 Area Interim Storage Area, Annex D, Final Safety Analysis Report which contains information specific to the 200 Area Interim Storage Area.

2000-03-15

402

Radiation technology, radiation technics and technological dosimetry in the Institute of Isotopes of the Hungarian Academy of Sciences. 1966-1981  

Energy Technology Data Exchange (ETDEWEB)

Pilot-plant irradiation began in Hungary in 1969 with the construction of a high-activity multi-purpose /sup 60/Co facility. Technologies for radiation sterilization, food handling, plastics irradiation as well as chemical dosimetry, semiconductor instrumental dosimetry, computer-based construction and control methods have been developed. Our chlorobenzene dose-meter system is used in Hungary and abroad; as a result of an IAEA-organized dosimetric intercomparison the system was adopted as a reference system. The institute has developed into a basic institute for the reconstruction and re-load of old ..gamma..-facilities as well as it serves for the planning, construction and launching of new ones in Hungary.

1982-01-01

403

Nuclear forensics  

International Nuclear Information System (INIS)

Increasing threat by terrorists for a possible nuclear attack is particularly alarming in recent years. The likelihood of such an event is highly uncertain but cannot be ruled out. The consequence of such an event would be highly disastrous and the implications could be far-reaching both socially and politically. It is feared that significant amount of nuclear weapons materials may be kept under poor security. Therefore, there is a greater demand with utmost priority to curb nuclear terrorism by adapting proper security measures. One of the most important measures is to stop illicit trafficking of nuclear materials which are the source of building nuclear explosive devices. According to the IAEA illicit trafficking database (ITDB) report, a total number of 252 incidents were reported in 2006, of which 150 occurred in 2006 and the remaining 102 had taken place prior to that year, mainly in 2005

2010-11-15

404

Nuclear forensic investigations with a focus on plutonium  

International Nuclear Information System (INIS)

Since the beginning of the 1990s when the first seizures of nuclear material were reported, the IAEA has recorded over 200 cases of illicit trafficking of nuclear materials. Despite the decreasing frequency of nuclear material seizures, particularly the ones involving weapons-grade material, the issue continues to attract public attention and is a reason for concern due to the hazard associated with such materials. Once illicitly trafficked nuclear material has been intercepted, the questions of its intended use and origin are to be addressed. Especially the origin is of prime importance in order to close the gaps and improve the physical protection at the sites where the theft or diversion occurred. To answer these questions, a dedicated nuclear forensics methodology has been developed. In this paper an overview is given on the methodologies used, on the past and on-going developments and on the experience gathered. Some selected examples shall illustrate the ...

2007-10-11

405

IAEA RESEARCH CONTRACTS FIRST ANNUAL REPORT. Technical reports Series No. 4  

Science.gov (United States)

Summaries are included of research contracts which expired prior to Dec. 31, 1960. The contracts were concerned with investigations of: electrophysiological responses of biological systems in nerve cells to irradiation with small doses of ionizing radiations; the mode of the protective action of certain sulfhydryl compounds against radiation effects on the synthesis of deoxyribonucleic acid, using tritium-labeled thymidine; development of a bubble chamber method of monitoring and dosimetry for Low fast neutron fluxes; effects of incorporated radioisotopes on the stability of genetic materials; interrelation of root and leaf absorption of radioisotopes in herbaceous plants; uptake of radioactive wastes by lowland rice from soils contaminated by irrigation water, and decontamination of the rice; and comparison between mutation rates induced by acute and chronic gamma irradiations. (B.O.G.)

1961-01-01

406

Guidebook on design, construction and operation of pilot plants for uranium ore processing  

International Nuclear Information System (INIS)

The design, construction and operation of a pilot plant are often important stages in the development of a project for the production of uranium concentrates. Since building and operating a pilot plant is very costly and may not always be required, it is important that such a plant be built only after several prerequisites have been met. The main purpose of this guidebook is to discuss the objectives of a pilot plant and its proper role in the overall project. Given the wide range of conditions under which a pilot plant may be designed and operated, it is not possible to provide specific details. Instead, this book discusses the rationale for a pilot plant and provides guidelines with suggested solutions for a variety of problems that may be encountered. This guidebook is part of a series of Technical Reports on uranium ore processing being prepared by the IAEA's Division of Nuclear Fuel Cycle and Waste Management. 42 refs, 7 figs, 3 tabs.

407

Exclusion, exemption and clearance in the mining and minerals industry - A review of the concepts from a South African perspective  

International Nuclear Information System (INIS)

The risks from mining and processing of ores is reviewed on a generic basis with particular reference to some of the confusions which can arise due to lack of consistency or common logic in the use of exclusion, exemption and clearance. The difference in exclusion and exemption are challenged by comparing doses received in high background radiation areas and the doses received from a mining practice. The common principle of risk to the human species is not applied consistently. The differences between IAEA recommendations and local regulatory conditions are compared, and the use of exemption levels as clearance levels is considered. A case study on management of mine tailings is presented with special focus on the use of clearance levels. In all areas of review the interpretation of regulation is subject to confusion resulting from inconsistencies which can distort free market economics. (author).

1997-05-06

408

Co-ordinated research programme on isotope-aided studies of the bioavailability of iron and zinc from human diets. Report of the second research co-ordination meeting, Hyderabad, India, 16-20 November 1992  

International Nuclear Information System (INIS)

The Co-ordinated Research Programme (CRP) on ''Isotope-Aided Studies on the Bioavailability of Iron and Zinc from Human Diets'' was initiated by the IAEA in 1990, and presently encompasses participating institutes in 11 countries. A summary of the discussions that took place during thr second Research Co-ordination Meeting held in Hyderabad, India, between 16-20 November 1992, is given in this report together with 12 working papers (progress reports) presented by individual participants. A separate abstract was prepared for each of these papers. Refs, figs and tabs.

1992-11-16

409

Calculation model testing for the case of rcs hot collector rupture inside the horizontal steam generator of VVER-440 NPP  

Energy Technology Data Exchange (ETDEWEB)

The calculations presented are based on RELAP5/MOD2-3 input for VVER 440/213 Bohunice NPP, developed within the framework of IAEA TC Project by an international team of specialists from CSFR, Hungary, Bulgaria and Poland. Project activities were condentrated on input data refinement and testing. Several cases were calculated using the latest version of RELAP5/MOD2 provided by RMA, Albuquerque to investigate some modelling assumptions, such as break location, geometrical representation of secondary circuit piping as well as the effect of deactivation of the signal controlling the SG isolation valves. (2 refs., 21 figs., 2 tabs.).

1993-12-31

410

Calculation model testing for the case of rcs hot collector rupture inside the horizontal steam generator of VVER-440 NPP  

International Nuclear Information System (INIS)

The calculations presented are based on RELAP5/MOD2-3 input for VVER 440/213 Bohunice NPP, developed within the framework of IAEA TC Project by an international team of specialists from CSFR, Hungary, Bulgaria and Poland. Project activities were condentrated on input data refinement and testing. Several cases were calculated using the latest version of RELAP5/MOD2 provided by RMA, Albuquerque to investigate some modelling assumptions, such as break location, geometrical representation of secondary circuit piping as well as the effect of deactivation of the signal controlling the SG isolation valves. (2 refs., 21 figs., 2 tabs.).

1992-09-29

411

An MS-DOS-based program for analyzing plutonium gamma-ray spectra  

Energy Technology Data Exchange (ETDEWEB)

A plutonium gamma-ray analysis system that operates on MS-DOS-based computers has been developed for the International Atomic Energy Agency (IAEA) to perform in-field analysis of plutonium gamma-ray spectra for plutonium isotopics. The program titled IAEAPU consists of three separate applications: a data-transfer application for transferring spectral data from a CICERO multichannel analyzer to a binary data file, a data-analysis application to analyze plutonium gamma-ray spectra, for plutonium isotopic ratios and weight percents of total plutonium, and a data-quality assurance application to check spectral data for proper data-acquisition setup and performance. Volume 3 contains the software listings for these applications.

1989-09-07

412

Survey of state water quality standards for wetlands  

Energy Technology Data Exchange (ETDEWEB)

This document summarizes the degree to which State water quality standards include wetlands in their definitions of State waters. The detailed review of other elements of standards, such as uses, criteria and antidegradation, is beyond the scope of this review. The purpose of this review is to provide a baseline of information for the development of EPA guidance and policies related to water quality standards for wetlands.

1989-08-17

414

Reference standard for carbonaceous impurity measurements in carbon nanotubes  

Science.gov (United States)

Near-infrared spectroscopy is a convenient tool for measuring nanotube / carbonaceous impurities

2004-01-01

417

Industrial experience with an intelligent AC/DC standard  

Energy Technology Data Exchange (ETDEWEB)

AC/DC voltage standards based entirely on solid-state references used as secondary, working, or transfer standards is widespread, although metrological performance is typically defined only via comparison with a higher level standard. The present report shows the improvements of the output metrological characteristics of an ac/dc calibrator by establishing three internal hierarchical levels of dc voltage references and by constant calibration of ac measuring circuits.

1989-04-01

418

Estimation of half-life values of actinide radionuclides  

International Nuclear Information System (INIS)

... actinides americium 241 americium 242 americium 243 calibration standards

1986-04-15

421

Development of a Standard Data Base and Computer ...  

Science.gov (United States)

... (Author). Descriptors : (*TERMINAL FLIGHT FACILITIES ... PROGRAMMING, HANDLING), QUEUEING THEORY, STOCHASTIC PROCESSES ...

1973-01-01

422

Development document for proposed effluent limitations guidelines, new source performance standards, and pretreatment standards for the steam electric point source category. Interim report  

Science.gov (United States)

This document provides a technical basis for the revision of chemical effluent limitations guidelines for the Steam Electric Power Industry reflecting the Best Available Technology Economically Achievable (BATEA) for existing sources, New Source Performance Standards (NSPS) and Pretreatment Standards. The analysis of pollutants and the technologies applicable to their control has been based on specific waste streams of concern.

1980-09-01

423

Development Document for Proposed Effluent Limitations Guidelines, New Source Performance Standards, and Pretreatment Standards for the Ink Formulating Point Source Category.  

Science.gov (United States)

This document presents the findings of a study of the Ink Manufacturing Industry for the purpose of developing effluent limitations and standards, and pretreatment standards for existing and new sources to implement Sections 301, 304, 306, 307 and 501 of ...

1979-01-01

425

The Nuclear Safety Convention and French law  

Energy Technology Data Exchange (ETDEWEB)

French law should not be very affected when the NSC enters into force in France. This results from the fact that French law has already achieved most of the `work` to be done in the field of safety of nuclear installations as it integrated the concept of `safety culture` (i.e. high level of safety for nuclear installations) which is, actually, the main objective of this convention. The elaboration of this convention on safety of nuclear power plants took approximately 3 years. The success (i.e. adoption of the draft text by the Diplomatic Conference) was made possible because of the large technical consensus existing among experts in that field. This means that if we intend to do the same in the field of radioactive waste management, we have to get first a similar consensus on fundamental adequate principles. (orig./HP)

1995-12-31

426

Positive safety features of US nuclear reactors: technical lessons confirmed at Chernobyl. Hearing before the Subcommittee on Energy Research and Production of the Committee on Science and Technology, US House of Representatives, Ninety-Ninth Congress, Second Session, May 14, 1986, No. 138  

Science.gov (United States)

Dr. Rudolf Schulten of West Germany and expert witnesses from national laboratories, utilities, and the nuclear industry testified on reactor safety issues as they relate to the Chernobyl accident and public concern that modern technology has not paid enough attention to public safety. Each of the witnesses contributed safety-related information based on what has been learned from the Soviet incident. Particular focus went to similarities and differences between the Chernobyl and US reactors in safety design and engineering and to the environmental effects of the accident. The N reactor near Richland and a commercial reactor at Fort St. Vrain, Colorado are the only two operating graphite reactors, but neither is a boiling water reactor.

1986-01-01

427

Positive safety features of US nuclear reactors: technical lessons confirmed at Chernobyl. Hearing before the Subcommittee on Energy Research and Production of the Committee on Science and Technology, US House of Representatives, Ninety-Ninth Congress, Second Session, May 14, 1986, No. 138  

International Nuclear Information System (INIS)

Dr. Rudolf Schulten of West Germany and expert witnesses from national laboratories, utilities, and the nuclear industry testified on reactor safety issues as they relate to the Chernobyl accident and public concern that modern technology has not paid enough attention to public safety. Each of the witnesses contributed safety-related information based on what has been learned from the Soviet incident. Particular focus went to similarities and differences between the Chernobyl and US reactors in safety design and engineering and to the environmental effects of the accident. The N reactor near Richland and a commercial reactor at Fort St. Vrain, Colorado are the only two operating graphite reactors, but neither is a boiling water reactor.

428

Implementing 10 CFR Part 830 Subpart B at WIPP  

Energy Technology Data Exchange (ETDEWEB)

Implementation of Title 10 Code of Federal Regulations Part 830, Subpart B Nuclear Safety Management (1) was accomplished at the Waste Isolation Pilot Plant (WIPP) in a timely and efficient manner. The primary reason the transition went smoothly was that the existing safety analysis was relatively new, initially developed in 1995, and written in accordance with the safe harbor document DOE-STD-3009 (2). The WIPP Safety Analysis Report (SAR) (3) is kept up-to-date with the unreviewed safety question (USQ) process and thorough oversight and input provided by DOE-Carlsbad Field Office (CBFO) documented in the annual safety evaluation report (SER) process.

2002-02-26

429

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 results of ...

1981-01-01

430

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 auspices of MEST. Draft ...

2010-10-01

431

ISO - ISO Standards - TC 156 - Corrosion of metals and alloys  

Wastenet

...ISO - ISO Standards - TC 156 - Corrosion of metals and alloys go to main navigation go to content area go to search International Standards for Business,...ISO Members FAQs Fr ISO Store Products ISO Standards By TC TC 156 Corrosion of metals and alloys ISO Store ISO Standards By ICS By ...aerospace standards Publications and e-products ISO Concept Database (ISO/CDB) Copyright TC 156 - Corrosion of metals and alloys Items to be displayed: Published ...responsibility of TC 156 Secretariat Standard and/or project Stage ICS 3ISO/WD 7441 Corrosion of metals and alloys Determination of bimetallic corrosion in outdoor ...

432

Extensions to the VME hardware and software standards for the physics community  

Energy Technology Data Exchange (ETDEWEB)

With the ubiquitous availability of commercial VME modules and interface chips many experiments in all branches of Experimental Physics are turning to VME as the module packaging and backplane protocol of choice for application specific modules. The current VME backplane, electrical, and mechanical standards are clearly lacking when it comes to implementing the analogue and digital front end modules that Physics experiments rely on to provide the needed high speed and intelligent solutions to their data collection requirements. To address these needs the European ESONE and American VME-P committees are collaborating with the ANSII and ISO standards committees, and the VME VITA/VSO manufacturers associations, to define standard extensions to the VME protocols for such HEP needs as ``sparse data scans``, standard uses and implementations of previously user defined pins and connectors, ...

1995-10-01

433

Summary of the report of the Senior Committee on Environmental, Safety, and Economic Aspects of Magnetic Fusion Energy  

Energy Technology Data Exchange (ETDEWEB)

The Senior Committee on Environmental, Safety, and Economic Aspects of Magnetic Fusion Energy (ESECOM) has assessed magnetic fusion energy's prospects for providing energy with economic, environmental, and safety characteristics that would be attractive compared with other energy sources (mainly fission) available in the year 2015 and beyond. ESECOM gives particular attention to the interaction of environmental, safety, and economic characteristics of a variety of magnetic fusion reactors, and compares them with a variety of fission cases. Eight fusion cases, two fusion-fission hybrid cases, and four fission cases are examined, using consistent economic and safety models. These models permit exploration of the environmental, safety, and economic potential of fusion concepts using a wide range of possible materials choices, power densities, power conversion schemes, and fuel ...

1987-09-10

434

Safety analysis practices for the dense storage of RBMK spent fuel and improved technology for the long term storage of spent fuel in water pools  

International Nuclear Information System (INIS)

The paper discusses the safety problems connected with the conversion to dense storage of RBMK-1000 spent fuel in reactor cooling pools and independent storage facilities. Recourse to dense storage has been made for a number of reasons, among which are the absence of spent fuel shipments from the nuclear power plant site, prolongation of storage time and a partial change in storage conditions. Increasing the storage density per unit volume of the storage facility and turning to new technical procedures (as against the basic design) call for further investigation of safety problems. The safety assessment of the dense storage mode includes: (1) Selecting a list of initiating events for design basis and unforeseeable accidents; (2) Assessing dense storage safety under normal as well as design basis accident conditions; (3) Safety analysis and development of measures to compensate for ...

1995-08-01

435

DOE explosives safety manual  

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 the state-of-the-art ...

1990-05-01

436

Deployment Support Leading to Implementation  

Energy Technology Data Exchange (ETDEWEB)

The following paragraphs summarize the progress of each research project funded under the WVU Cooperative Agreement during the third quarter of 1997 (July - September 1997). The projects are arranged according to their 1997 WVU task number. WVU Focus Area 1.0: Subsurface Contaminants, Containment and Remediation Task No. 1.1: Project discontinued. Task No. 1.2: Development of Standard Test Protocols and Barrier Design Models for Desiccation Barriers (K. Amininan & S. Ameri): A number of experiments were preformed this period to evaluate the ability of the dried sand-packs to act as a barrier to liquids. Water infiltration tests were done with a constant head, dispersing 80 ml of water, and by adding water in small increments. Results indicate that when the water is spilled over the sand-pack, it has the tendency to channel through the sand-pack, significantly reducing the capacity of the dried zone to retain liquid contaminants. This appears to be largely ...

1997-10-01

437

Spent Fuel Transportation Package Response to the Baltimore Tunnel Fire Scenario  

International Nuclear Information System (INIS)

On July 18, 2001, a freight train carrying hazardous (non-nuclear) materials derailed and caught fire while passing through the Howard Street railroad tunnel in downtown Baltimore, Maryland. The United States Nuclear Regulatory Commission (USNRC), one of the agencies responsible for ensuring the safe transportation of radioactive materials in the United States, undertook an investigation of the train derailment and fire to determine the possible regulatory implications of this particular event for the transportation of spent nuclear fuel by railroad. Shortly after the accident occurred, the USNRC met with the National Transportation Safety Board (NTSB, the U.S. agency responsible for determining the cause of transportation accidents), to discuss the details of the accident and the ensuing fire. Following these discussions, the USNRC assembled a team of experts from the National Institute of Standards and Technology (NIST), the Center for ...

2006-11-01

438

FLUTAN 2.0. Input specifications  

Energy Technology Data Exchange (ETDEWEB)

FLUTAN is a highly vectorized computer code for 3D fluiddynamic and thermal-hydraulic analyses in Cartesian or cylinder coordinates. It is related to the family of COMMIX codes originally developed at Argonne National Laboratory, USA, and particularly to COMMIX-1A and COMMIX-1B, which were made available to FZK in the frame of cooperation contracts within the fast reactor safety field. FLUTAN 2.0 is an improved version of the FLUTAN code released in 1992. It offers some additional innovations, e.g. the QUICK-LECUSSO-FRAM techniques for reducing numerical diffusion in the k-{epsilon} turbulence model equations; a higher sophisticated wall model for specifying a mass flow outside the surface walls together with its flow path and its associated inlet and outlet flow temperatures; and a revised and upgraded pressure boundary condition to fully include the outlet cells in the solution process of the conservation equations. Last but not least, a so-called visualization ...

1996-05-01

439

Development of Guide System for a Reactor Head Maintenance Robot  

Energy Technology Data Exchange (ETDEWEB)

The Control Rod Drive(CRD) nozzles for PWR nuclear power plants(NPP) house the control rod drives. The number of nozzle penetrations range from the mid-30's to over 100 in each reactor head. The integrity of CRD nozzles is very important, because the primary pressure boundary is established with the J-groove weld joining the nozzle to the head clad surface. The Alloy 600 PWSC CRD nozzle leaks discovered in the fall of 2000 and spring of 2001 in several US plants. Therefore the NRC has recommended a more proactive effort by US utilities to inspect similarly susceptible nozzles in all US plants. The primary safety concern is circumferential cracks that can permit the nozzles to separate from the head at high velocity and produce a large-break leak in the reactor vessel. A secondary concern is head leakage from any through-wall cracks in the nozzle or J-groove weld area. Numerous inspection and repair tools have been developed to address CRD nozzle inspection ...

2005-07-01

440

The role of networking for nuclear education  

International Nuclear Information System (INIS)

Nuclear knowledge is the basis for almost all nuclear activities, and education and training are the most fundamental means to transfer knowledge from one generation to the next. Understanding means and trends in knowledge transfer through education and training thus deserves a closer examination. In the past years, a number of trends and questions in nuclear knowledge, education and training have emerged. With declining student enrolment numbers and a general stagnation of the use of nuclear power in some of the IAEA's Member States, the issue of a slow erosion of the knowledge base and the possibility of loosing knowledge has become increasingly important, in particular if seen against the background of a possible renaissance of nuclear power in the future. In other Member States, an expansion of nuclear power is expected, with a corresponding need for human resources. As a result, in many Member States education and training of the next generation and succession ...

2004-10-01

441

Global residential appliance standards  

Energy Technology Data Exchange (ETDEWEB)

In most countries, residential electricity consumption typically ranges from 20% to 40% of total electricity consumption. This energy is used for heating, cooling, refrigeration and other end-uses. Significant energy savings are possible if new appliance purchases are for models with higher efficiency than that of existing models. There are several ways to ensure or encourage such an outcome, for example, appliance rebates, innovative procurement, and minimum efficiency standards. This paper focuses on the latter approach. At the present time, the US is the only country with comprehensive appliance energy efficiency standards. However, many other countries, such as Australia, Canada, the European Community (EC), Japan and Korea, are considering enacting standards. The greatest potential impact of minimum efficiency standards for appliances is in the developing countries (e.g., China and India), where ...

1993-03-01

442

PSA methodology including new design, operational and safety factors, 'Level of recognition of phenomena with a presumed dominant influence upon operational safety' (failures of conventional as well as non-conventional passive components, dependent failures, influence of operator, fires and external threats, digital control, organizational factors)  

International Nuclear Information System (INIS)

The document represents a specific type of discussion of existing methodologies for the creation and application of probabilistic safety assessment (PSA) in light of the EUR document summarizing requirements placed by Western European NPP operators on the future design of nuclear power plants. A partial goal of this discussion consists in mapping, from the PSA point of view, those selected design, operational and/or safety factors of future NPPs that may be entirely new or, at least, newly addressed. Therefore, the terms of reference for this stage were formulated as follows: Assess current level of knowledge and procedures in the analysis of factors and phenomena with a dominant influence upon operational safety of new generation reactors, especially in the following areas: (1) Phenomenology of failure types and mechanisms and reliability of conventional passive safety system components; (2) ...

443

Status of the ANS low power and shutdown PRA standard  

Energy Technology Data Exchange (ETDEWEB)

The Low Power and Shutdown (LPSD) PRA (Probabilistic Risk Assessment) Standard (ANS-58.22) is currently being drafted by a Writing Group under the auspices of the Risk Informed Standards Committee of the American Nuclear Society (ANS). The Writing Group includes representatives from nuclear utilities, US Nuclear Regulatory Commission (NRC), national laboratories, universities, and consultants with substantial experience producing LPSD PRAs. This draft standard is scheduled to be released for public comment in the second quarter of 2004, with publication by the end of 2004. The LPSD PRA Standard is based on a mature technology that shares many requirements with full power PRAs. It will provide specific methods and criteria whereby PRAs of appropriate quality and scope can be used in the conduct of plant decision-making and other activities, including addressing NRC requirements. This paper presents the ...

2004-07-01

444

IEEE standard quality assurance program requirements for the design and manufacture of class 1E instrumentation and electric equipment for nuclear power generating station  

International Nuclear Information System (INIS)

The Institute of Electrical and Electronic Engineers (IEEE) standards for the quality assurance requirements for the design and manufacture of Class 1E instrumentation and electric equipment for a nuclear power generating station are presented. This standard establishes Quality Assurance Program requirements for electrical manufacturers. This standard, used in conjunction with ANSI N45.2-1977 and the supplemental standards to the extent referenced in this standard, is intended to meet the requirements of 10CFR50, Appendix B. These requirements are intended to assure that Class 1E instrumentation and electric equipment are responsibly engineered and manufactured from proper materials, that the manufacturing processes and practices are controlled, and that the manufacturing process produces a product of the required quality for Class 1E application.

445

IEEE [Institute of Electrical and Electronics Engineers] standards and nuclear software quality engineering  

International Nuclear Information System (INIS)

Significant new nuclear-specific software standards have recently been adopted under the sponsorship of the American Nuclear Society and the American Society of Mechanical Engineers. The interest of the US Nuclear Regulatory Commission has also been expressed through their issuance of NUREG/CR-4640. These efforts all indicate a growing awareness of the need for thorough, referenceable expressions of the way to build in and evaluate quality in nuclear software. A broader professional perspective can be seen in the growing number of software engineering standards sponsored by the Institute of Electrical and Electronics Engineers (IEEE) Computer Society. This family of standards represents a systematic effort to capture professional consensus on quality practices throughout the software development life cycle. The only omission-the implementation phase-is treated by accepted American National Standards ...

1988-06-12

446

Regulatory view of the close-out of the uranium ore mine Zirovski Vrh  

International Nuclear Information System (INIS)

The production of the uranium mine Zirovski Vrh ceased in 1990. The main remaining problem of the remadiation are mine and mill tailings. The uranium mine Zirovski Vrh has one mill tailings site Borst and one waste pile Jazbec. According to the Act on protection against ionising radiation and nuclear safety which was adopted by the Parliament in 2002, they are classified as radiation facilities. Slovenian Nuclear Safety Administration (SNSA) is authorised for issuing a mandatory consent to mining work. The SNSA prepared the initial proposal of content of the safety report for the mine waste pile Jazbec. In 2005, according to the detailed content of this document, the public company Zirovski Vrh Ltd prepared the safety report which was examined by an authorised expert for radiation and nuclear safety. After a careful revision of the safety evaluation report, the ...

2005-09-05

447

Regulatory requirements for design of safety related computer based control Systems in Indian PHWRs: case study of DPHS-PCS for TAPP-3 and 4  

International Nuclear Information System (INIS)

Computer based control systems for safety related applications in nuclear power plants have to meet not only the functional, performance and interface requirements, they in addition, have to meet regulatory requirements like enhanced reliability, safety and security and should provide fault tolerance, diagnostics and self-supervision. The control system architecture, hardware design and software design should meet requirements as specified in design code and guides of AERB. The Dual Processor Hot Standby Process Control System (DPHS-PCS) for TAPP-3 and 4 is a safety related (Class- IB) system. DPHS-PCS regulates PHT pressure, Pressuriser pressure, Pressuriser level, Bleed condenser pressure, Bleed condenser level and Steam generator pressure. The performance, reliability and safety requirements of this control system are met by employing a fault tolerant computer configuration developed for this purpose ...

2005-03-01

448

Optimal inspection and replacement periods of the safety system in Wolsung Nuclear Power Plant Unit 1 with an optimized cost perspective  

Energy Technology Data Exchange (ETDEWEB)

In this work, a model for determining the optimal inspection and replacement periods of the safety system in Wolsung Nuclear Power Plant Unit 1 is developed, which is to minimize economic loss caused by inadvertent trip and the system failure. This model uses cost benefit analysis method and the part for optimal inspection period considers the human error. The model is based on three factors as follows: (i) The cumulative failure distribution function of the safety system, (ii) The probability that the safety system does not operate due to failure of the system or human error when the safety system is needed at an emergency condition and (iii) The average probability that the reactor is tripped due to the failure of system components or human error. The model then is applied to evaluate the safety system in Wolsung Nuclear Power Plant Unit 1. The optimal replacement periods which ...

1996-01-01

449

Improving safety and quality: how can education help?  

Science.gov (United States)

National efforts to improve the quality and safety of health care present challenges for medical education and training. Today's doctors need to be skilled communicators who know how to identify, prevent and manage adverse events and near misses, how to use evidence and information, how to work safely in a team, how to practise ethically, and how to be workplace teachers and learners. These competencies (knowledge, skills and attitudes) are set out in the National Patient Safety Education Framework (NPSF) of the Australian Council for Safety and Quality in Health Care. The NPSF is designed to help medical schools, vocational colleges, health organisations and private practitioners develop curricula to enable health professionals to work safely. The NPSF describes what doctors (depending on their level of knowledge and experience) can do to demonstrate competencies in a range of quality and safety ...

2006-05-15

450

Foundations  

Energy Technology Data Exchange (ETDEWEB)

This Health and Safety (HSE) document offers technical information on the design of foundations for supports in offshore installations, and relates particularly to the North Sea. It is based largely on guidance offered earlier in Section 20 of the Fourth Edition of the Health and Safety Executive's 'Offshore Installations; Guidance on Design, Construction and Certification', which was withdrawn in 1998. The document contains a general section on foundations and the rest of the document comprises sections on: (a) piled foundations (planning, problems, pile make-up, steel stresses, design of pile foundations, axial pile capacity, factors of safety for piled foundations, load-deflection of piles, and piles for tethered buoyant structures); (b) foundations for gravity structures (foundation types, loads and reactions during installation, operating loads and reactions, foundation problems, cyclic load ...

2002-07-01

451

Definition and means of maintaining the criticality detectors and alarms portion of the PFP safety envelope  

Energy Technology Data Exchange (ETDEWEB)

The purpose of this document is to provide the definition and means of maintaining the Safety Envelope (SE) related to the Criticality Alarm System (CAS). This document provides amplification of the Limiting Condition for Operation (LCO) described in the Plutonium Finishing Plant (PFP) Operational Safety Requirements (OSR), WHC-SD-CP-OSR-010, Rev. 0, 1994, Section 3.1.2, Criticality Detectors and Alarms. This document, with its appendices, provides the following: (1) System functional requirements for determining system operability (Section 3); (2) A list of annotated system block diagrams which indicate the safety envelope boundaries (Appendix C); (3) A list of the Safety Class 1 and 2 Safety Envelope (SC-1/2 SE) equipment for input into the Master Component Index (Appendix B); (4) Functional requirements for individual SC-1/2 SE components, including appropriate setpoints and ...

1997-05-13

452

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 understand the risks and ...

453

VDMA contribution to functional safety of turbo-machines - A necessary risk reduction by means of safety function for steam turbines; VDMA-Beitrag zur Funktionalen Sicherheit von Turbomaschinen. Notwendige Risikoreduktion durch Schutzfunktionen fuer Dampfturbinen  

Energy Technology Data Exchange (ETDEWEB)

In the last two years, the VDMA work group 'Functional security' compiled a qualitative and quantitative procedure for the determination and evaluation of turbo-machine specific risks. With the calibrated risk graph for turbo-machines the requirements (Safety Integrity Level SIL) to the protective functions for turbo-machines (steam turbines, gas turbines, generators and compressors) were determined. With consideration of the legislation, the work group compiled a recommendation for the renewal and/or reconstruction of protective functions with old facilities.

2010-07-01

454

The SPOOM-EDM method for assessing organizational factors  

International Nuclear Information System (INIS)

Organization factors have been known as an important contributor to plant safety. Previous studies associated with assessing organisation factors mainly deals with the aspect of safety of an organization. For an organization, however, efficiency or an aspect of economy related with work activities is also important. This paper introduces a conceptual model, SPOOM-EDM (Self Poly-Oriented Organizational Model - Evaluation Diamond Model), for evaluating an organization with respect to both safety and economy. It also shows how the proposed model can be applied for the evaluation of an organization through the analysis of real events. (author)

2003-04-20

455

Stochastic aspects of dam safety analysis  

Energy Technology Data Exchange (ETDEWEB)

A stochastic analysis is presented of the probability of overtopping of a dam. The discussion is based on the case of a dam for a small water storage reservoir which has recently been constructed in the Saar district in the FRG. The problem is first solved by means of a simulation method. However, it is possible to describe the result of the sumulation method by means of a much simpler model which is based on a solution of the failure integral of Freudenthal for uncorrelated resistances and loads. It is shown that the actual safety of this dam against overtopping is extremely sensitive to both the operation rule for the reservoir, and the freeboard allowance. Some general conclusions are derived from this study for assisting in the ongoing discussion of dam safety. (6 figs, 1 tab, 7 refs)

1988-05-15

456

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

457

Safety review of conceptual fusion power plants  

Science.gov (United States)

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

458

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.

459

Nuclear design analysis of wolsung-1 CANDU-PHW nuclear generating station  

International Nuclear Information System (INIS)

A combination of computer codes such as LATREP, HWRAXAV and CITATION is utilized in an attempt to analyze the nuclear design characteristics of the CAXDU-PHWR of the Wolsung Unit 1. The major nuclear properties to be computed are the lattice properties of CANDU fuel channel and the core channel power distribution. The computed results are compared with the preliminary safety reports documentation for the Wolsung reactor. The observed discrepancies between our computations and the preliminary safety reports values are discussed in terms of incomplete information on the description of the core configuration in the preliminary safety reports and the different calculation methods. (author).

1978-01-01

460

H/sub 2/S safety aboard an offshore production facility handling crude oil and associated sour natural gas  

Energy Technology Data Exchange (ETDEWEB)

This paper describes the safety system and training for personnel on board the floating production storage and offloading (FPSO II) currently working in the Cadlao Field, offshore Palawan in the Philippine Islands. (See Figure 1). The crude oil being produced has wellstream hydrogen sulfide concentrations up to 6000 PPM. Concentrations of hydrogen sulfide at 700 PPM or higher can be immediately dangerous to life and every effort must be made to ensure personnel safety.

1984-02-01

461

Facility Safety Plan B360 Complex Biohazardous Operations CMLS-412r0  

Science.gov (United States)

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

462

Department of Nuclear Safety Research and Nuclear Facilities annual report 1995  

Energy Technology Data Exchange (ETDEWEB)

The report presents a summary of the work of the Department of Nuclear Safety Research and Nuclear Facilities in 1995. The department`s research and development activities are organized in three research programmes: Radiation Protection, Reactor Safety, and Radioanalytical Chemistry. The nuclear facilities operated by the department include the Research Reactor DR3, the Isotope Laboratory, the Waste Treatment Plant, and the Educational Reactor DR1. Lists of staff and publications are included together with a summary of the staff`s participation in national and international committees. (au) 5 tabs., 21 ills.

1996-03-01

463

Application of probabilistic safety assessment models to risk-based inspection of piping  

International Nuclear Information System (INIS)

From the beginning, one of the most useful applications of Probabilistic Safety Assessment (PSA) is its use in evaluating the risk importance of changes to plant design, operations, or other plant conditions. Risk importance measures the impact of a change on the risk. Risk is defined as a combination of the likelihood of failure and consequence of the failure. The consequence can be safety system unavailability, core melt frequency, early release, or various other consequence measures. The goal in this PSA application is to evaluate the risk importance of an ISI process, as applied to plant piping systems. Two approaches can be taken in this evaluation: Current PSA Approach or the Blended Approach. Both are discussed here.

1996-07-21

464

Thermal-hydraulic analysis following a safety flapper valve's fault for a pool-type research reactor  

International Nuclear Information System (INIS)

One of the characteristic safety features of a pool type research reactor is a safety flapper valve. The valve enables natural convection cooling mechanism in one of the following events. (a) Opening flapper valve promote decay heat removal following reactor's shutdown. (b) Also the valve is gravity driven. There is a possibility that the valve fails to open when it is required to do so. In the present paper the cooling characteristics of the core are analyzed for this event. A steady state study was performed for 5 MW power and 18 FE following a reactor shutdown. It is shown that enough margin exists to assure adequate reactor core cooling should the safety flapper valve fails to open. (authors)

465

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 of chemical explosives are evaluated. (3 refs.) (In Polish)

1983-11-01

466

Status of safety at Areva group facilities. 2007 annual report; Areva, etat de surete des installations nucleaires. Rapport annuel 2007  

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

467

Seismic qualification method of equipment for nuclear power plant  

Energy Technology Data Exchange (ETDEWEB)

Safety related equipment installed in Korean Nuclear Power Plants are required to perform a safety function during and after a seismic event. To accomplish this safety function, they must be seismically qualified in accordance with the intent and requirements of the USNRC Reg. Guide 1.100 Rev. 02 and IEEE Std. 344-1987. This paper defines and summarizes acceptable criteria and procedures, based on the Korean experience, for seismic qualification of purchased equipment to be installed in a nuclear power plant. As such the paper is intended to be a concise reference by equipment designers, architectural engineering company and plant owners in uniform implementation of commitments to nuclear regulatory agencies such as the USNRC or Korea Institute of Nuclear Safety (KINS) relating to adequacy of seismic Category 1 equipment. Thus, the paper provides the methodologies which can be used for qualifying ...

1995-12-31

468

Safety of using montelukast during pregnancy  

UK PubMed Central (United Kingdom)

ABSTRACTQUESTION Montelukast is used more and more by my patients with asthma. Is it safe to use during pregnancy?ANSWER Cumulative data, including a...Full Text Available

2010-09-01

469

Safety measures for prevention of PCB accidents.  

UK PubMed Central (United Kingdom)

This paper attempts to clarify the most common measures available for the fire and electrical engineer in the prevention of polychlorinated biphenyl (PCB) hazards. It points out the risks and the potential...Full Text Available

1985-05-01

470

Safety calculation for an underground repository for radioactive waste: the first objective of the alliances calculation software platform  

International Nuclear Information System (INIS)

The aim of the safety calculation is to quantify through numerical modelling the radiological impact (molar flow, human dose) of a potential repository for radioactive waste on the Meuse/Haute Marne site at Bure. A selection process is underway for safety scenarios and their phenomenological and numerical conceptual models upstream from the safety calculation. This involves defining and quantifying the geometric and dimensional representations of the repository for each scenario plus the physical, mathematical and numerical models that reflect its behaviour and the uncertainties associated with all the parameters required to quantify the impact. A summary will be given of these various aspects. The numerical simulations are then performed on the Alliances platform which integrates the various computer codes required for the physical representation of the system. (authors)

2005-03-14

471

SAFETY--Water Resources Division National Pollutant Discharge...  

Science.gov (United States)

Provisions (a) NPDES field personnel shall be currently trained and certified in CPR and basic first-aid procedures. (b) NPDES field personnel shall be aware of the...

2011-09-24

473

Projective goals - concepts and pragmatic aspects based on the terminology and methodology of safety science  

International Nuclear Information System (INIS)

Protective goals set the line of orientation of tasks and activities in the field of accident prevention. They have to be based on safety-science methods in order to develop from the conceptual idea to the practically feasible solution, while using the scientific methods to take into account the facts and the capabilities of a situation and, proceeding from them, finding an efficient and rational, optimal pragmatic approach by way of various strategies or tactics. In this process, the activities of defining, informing, thinking and developing need the proper terminology. Safety is absence of danger, protection is limitation of danger and prevention of damage. So it is protection what is needed with danger being given, and risks have to be minimized. Riskology is a novel method of safety science, combining risk analysis and risk control into a systematic concept which is practice-oriented. Applying this to the field of ...

474

Navy Occupational Health Information Management System (NOHIMS). Hazardous Materials Control Module. Users' manual  

Energy Technology Data Exchange (ETDEWEB)

The Hazardous Materials Control Module (HMC) is one module of four for the Industrial Health component. The HMC module was designed to inform employees of health and safety hazards in the workplace and to track the movement of hazardous materials through the facility. The module performs these functions by maintaining health and safety data on hazardous materials used in the facility, and by tracking who requests information about any hazardous materials. The HMC module gets its information from two sources. The first one is the Hazardous Materials Information System (HMIS), this is a national system that is used by the Department of Defense. It is loaded on to the system via tapes that contain all safety, health and transportation information about a particular product. The second is Material Safety Data Sheets (MSDS) that are procured by a particular site. This information is manually entered into ...

1987-01-16

475

Naval Sea Systems Command occupational safety and health record-keeping system. Hazardous Materials Control Module. Program maintenance manual  

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

476

Nail-Gun Injuries to the Hand  

UK PubMed Central (United Kingdom)

Background: The nail gun is a commonly utilized tool in carpentry and construction. When used properly with appropriate safety precautions, it can facilitate production and boost efficiency;...Full Text Available

477

NAVAIRSYSCOM Hazardous Material Safety Program  

Science.gov (United States)

... C-3 ____ Page 21. NALIC-75189-30 Other Publications (Continued) NAVAIRINST 6260.1 -Chlorinated Solvents Instructions; for use of ...

1975-08-18

478

Minutes of the Third Explosives Safety Seminar on High ...  

Science.gov (United States)

... for. Now there already exists under the SPIA aegis a document which is called the JANAP mailing list. This is the joint Army ...

1961-12-01

479

Marines Pictures  

Science.gov (United States)

Team 6 Regimental Combat Team 8 Retired Activities Office Safety Division School of Infantry - East School of Infantry - West Second Low Altitude Air Defense Battalion Security...

2011-09-24

481

How safe are the biologicals in treating asthma and rhinitis?  

UK PubMed Central (United Kingdom)

A number of biological agents are available or being investigated for the treatment of asthma and rhinitis. The safety profiles of these biologic agents, which may modify allergic and immunological...Full Text Available

482

Health and safety risks in production agriculture.  

UK PubMed Central (United Kingdom)

Production agriculture is associated with a variety of occupational illnesses and injuries. Agricultural workers are at higher risk of death or disabling injury than most other workers. Traumatic injury...Full Text Available

1998-10-01

483

Food additives: an ethical evaluation.  

Science.gov (United States)

Background Food additives are an integral part of the modern food system, but opinion polls showing most Europeans have worries about them imply an urgent need for ethical analysis of their use. Sources of data The existing literature on food ethics, safety assessment and animal testing. Areas of agreement Food additives provide certain advantages in terms of many people's lifestyles. Areas of controversy There are disagreements about the appropriate application of the precautionary principle and of the value and ethical validity of animal tests in assessing human safety. Growing points Most consumers have a poor understanding of the relative benefits and risks of additives, but concerns over food safety and animal testing remain high. Areas timely for developing research Examining the impacts of food additives on consumer sovereignty, consumer health and on animals used in safety testing should allow a ...

2011-07-01

484

Fire Safety in Extraterrestrial Environments - NASA Technical ...  

Science.gov (United States)

of the familiar fire triangle, namely, fuel, ignition, and oxygen. Fuel is minimized ... The third element of the fire triangle, oxygen, is obviously ...

485

Environmental, health, and safety issues of sodium-sulfur batteries for electric and hybrid vehicles. Volume 1, Cell and battery safety  

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 describes and assesses the ...

1992-09-01

486

Electrical installations in locations with explosion hazards  

Energy Technology Data Exchange (ETDEWEB)

The optimization of the safety characteristics of electrical installations in industrial plants with explosion or fire hazards can be obtained only through a careful interdisciplinary study and analysis carried out at the onset of the plant project design phase. The least complex and costly and safest solutions are those which are born from plant designs which take into account the typology of the industrial process or technology, or which incorporate pollution abatement measures and adequate safety measures for the electrical installations. This paper provides examples to illustrate how the global plant economy is fundamentally dependant upon a multi-disciplinary initial effort in design analyses. Comments are made relevant to the adequacy of the safety requirements established by existing and planned Italian norms in dealing with safety and fire protection for high-tech industrial plant electrical ...

1987-11-01

488

Efficacy and Safety of a New Vaginal Contraceptive Antimicrobial Formulation Containing High Molecular Weight ...  

Science.gov (United States)

... commercial material manufactured utilizing chlorinated hydrocarbons for the sulfonation of a long chain polystyrene to produce high ... ...

489

DYNAMIC ANALYSIS OF DARRIEUS VERTICAL AXIS WIND ...  

Science.gov (United States)

The dynamic response characteristics of the VAWT rotor are important factors governing the safety and fatique life of VAWT systems. The principal problems are ...

490

Cold vacuum drying facility design requirements; FINAL  

International Nuclear Information System (INIS)

This document provides the detailed design requirements for the Spent Nuclear Fuel Project Cold Vacuum Drying Facility. Process, safety, and quality assurance requirements and interfaces are specified.

491

Chapter 9 - Columbia Accident Investigation Board - NASA  

Science.gov (United States)

our exploration of space, in a manner with improved safety. ... a new Space Transportation System. ... Columbia launches as STS-107 on January 16, 2003. ...

492

CRC manual of nuclear medicine: Procedures. Fourth Edition  

Energy Technology Data Exchange (ETDEWEB)

This book discusses the procedures applied for the clinical nuclear medicine laboratory. The procedures are presented as proven guidelines. The chapters are included on quality assurance, radionuclide handling, and radiation safety.

1983-01-01

493

CDC - Men's Health A-Z - Workplace Safety and Health (Occupational...  

Science.gov (United States)

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

494

Application of Risk Management for Control and Monitoring Systems  

CERN Document Server

This paper presents an application of the state of the art and new trends for risk management of safety-related control and monitoring systems, currently applied in the industry. These techniques not only enable to manage safety and reliability issues but they also help in the control of quality and economic factors affected by the availability and maintenance of the system. The method includes an unambiguous definition of the system in terms of functions and a systematic analysis of hazardous situations, undesired events and possible malfunctions. It also includes the identification and quantification of the risk associated to the system. The required risk reduction is specified in terms of safety integrity levels. The safety integrity level results in requirements, preventive measures, possible improvements and recommendations to assure the satisfactory management of the risk.

2001-01-01

495

Advice about the safety of graphite storage silos of Saint Laurent des Eaux facility; Avis sur la surete des silos de stockage de graphite de Saint Laurent des Eaux  

Energy Technology Data Exchange (ETDEWEB)

This document is the safety analysis made by the national association of the local commissions of information about nuclear activities (ANCLI), about the safety of graphite storage silos of Saint Laurent des Eaux nuclear facility. The analysis covers: the operation safety and the accident hypothesis, the monitoring of indoor and outdoor contamination in routine situation, the geotechnical characteristics of the site environment, the isotopic inventory and the estimation of radioactivity in routine and accidental situation, the estimation of doses received by the population in accidental situation and the internal emergency plan. After examination of these different points, the scientific committee of the ANCLI considers that a new global evaluation of risks, which integrates more recent exposure data, has to be carried out. (J.S.)

2005-07-01

496

A motor-driven hoisting winch with a safety-braking device  

International Nuclear Information System (INIS)

... brakes reactor charging machines reactors machine parts Int. Cl. B66d5/00;