Study of system safety evaluation on LTO of national project. NISA safety research project on system safety of nuclear power plants

International Nuclear Information System (INIS)

Takizawa, Masayuki; Sekimura, Naoto; Miyano, Hiroshi; Aoyama, Katsunobu

2012-01-01

Japanese safety regulatory body, that is, Nuclear and Industrial Safety Agency (NISA) started a 5-year national safety research project as 'the first stage' from 2006 FY to 2010 FY whose objective is 'Improve the technical information basis in order to utilize knowledge as well as information related to ageing management and maintenance of NPPs. Fukushima disaster happened in March 2011, and the priority of research needs for ageing management dramatically changed in Japan. The second-stage national project started in October 2011 with the concept of 'system safety' of NNPs where not only ageing management on degradation phenomena of important components but also safety management on total plant systems are paid attention to. The second-stage project is so called 'Japanese Ageing Management Program for System Safety (JAMPSS)'. (author)

Guidance and Control Software Project Data - Volume 2: Development Documents

Science.gov (United States)

Hayhurst, Kelly J. (Editor)

2008-01-01

The Guidance and Control Software (GCS) project was the last in a series of software reliability studies conducted at Langley Research Center between 1977 and 1994. The technical results of the GCS project were recorded after the experiment was completed. Some of the support documentation produced as part of the experiment, however, is serving an unexpected role far beyond its original project context. Some of the software used as part of the GCS project was developed to conform to the RTCA/DO-178B software standard, "Software Considerations in Airborne Systems and Equipment Certification," used in the civil aviation industry. That standard requires extensive documentation throughout the software development life cycle, including plans, software requirements, design and source code, verification cases and results, and configuration management and quality control data. The project documentation that includes this information is open for public scrutiny without the legal or safety implications associated with comparable data from an avionics manufacturer. This public availability has afforded an opportunity to use the GCS project documents for DO-178B training. This report provides a brief overview of the GCS project, describes the 4-volume set of documents and the role they are playing in training, and includes the development documents from the GCS project. Volume 2 contains three appendices: A. Guidance and Control Software Development Specification; B. Design Description for the Pluto Implementation of the Guidance and Control Software; and C. Source Code for the Pluto Implementation of the Guidance and Control Software

National Ignition Facility Project Site Safety Program

International Nuclear Information System (INIS)

Dun, C

2003-01-01

This Safety Program for the National Ignition Facility (NIF) presents safety protocols and requirements that management and workers shall follow to assure a safe and healthful work environment during activities performed on the NIF Project site. The NIF Project Site Safety Program (NPSSP) requires that activities at the NIF Project site be performed in accordance with the ''LLNL ES and H Manual'' and the augmented set of controls and processes described in this NIF Project Site Safety Program. Specifically, this document: (1) Defines the fundamental NIF site safety philosophy. (2) Defines the areas covered by this safety program (see Appendix B). (3) Identifies management roles and responsibilities. (4) Defines core safety management processes. (5) Identifies NIF site-specific safety requirements. This NPSSP sets forth the responsibilities, requirements, rules, policies, and regulations for workers involved in work activities performed on the NIF Project site. Workers are required to implement measures to create a universal awareness that promotes safe practice at the work site and will achieve NIF management objectives in preventing accidents and illnesses. ES and H requirements are consistent with the ''LLNL ES and H Manual''. This NPSSP and implementing procedures (e.g., Management Walkabout, special work procedures, etc.,) are a comprehensive safety program that applies to NIF workers on the NIF Project site. The NIF Project site includes the B581/B681 site and support areas shown in Appendix B

Guidance and Control Software Project Data - Volume 1: Planning Documents

Science.gov (United States)

Hayhurst, Kelly J. (Editor)

2008-01-01

The Guidance and Control Software (GCS) project was the last in a series of software reliability studies conducted at Langley Research Center between 1977 and 1994. The technical results of the GCS project were recorded after the experiment was completed. Some of the support documentation produced as part of the experiment, however, is serving an unexpected role far beyond its original project context. Some of the software used as part of the GCS project was developed to conform to the RTCA/DO-178B software standard, "Software Considerations in Airborne Systems and Equipment Certification," used in the civil aviation industry. That standard requires extensive documentation throughout the software development life cycle, including plans, software requirements, design and source code, verification cases and results, and configuration management and quality control data. The project documentation that includes this information is open for public scrutiny without the legal or safety implications associated with comparable data from an avionics manufacturer. This public availability has afforded an opportunity to use the GCS project documents for DO-178B training. This report provides a brief overview of the GCS project, describes the 4-volume set of documents and the role they are playing in training, and includes the planning documents from the GCS project. Volume 1 contains five appendices: A. Plan for Software Aspects of Certification for the Guidance and Control Software Project; B. Software Development Standards for the Guidance and Control Software Project; C. Software Verification Plan for the Guidance and Control Software Project; D. Software Configuration Management Plan for the Guidance and Control Software Project; and E. Software Quality Assurance Activities.

Enhancing Safety Culture in Complex Nuclear Industry Projects

International Nuclear Information System (INIS)

Gotcheva, N.

2016-01-01

This paper presents an on-going research project “Management principles and safety culture in complex projects” (MAPS), supported by the Finnish Research Programme on Nuclear Power Plant Safety 2015-2018. The project aims at enhancing safety culture and nuclear safety by supporting high quality execution of complex projects in the nuclear industry. Safety-critical industries are facing new challenges, related to increased outsourcing and complexity in technology, work tasks and organizational structures (Milch and Laumann, 2016). In the nuclear industry, new build projects, as well as modernisation projects are temporary undertakings often carried out by networks of companies. Some companies may have little experience in the nuclear industry practices or consideration of specific national regulatory requirements. In large multinational subcontractor networks, the challenge for assuring nuclear safety arises partly from the need to ensure that safety and quality requirements are adequately understood and fulfilled by each partner. Deficient project management practices and unsatisfactory nuclear safety culture in project networks have been recognised as contributing factors to these challenges (INPO, 2010). Prior evidence indicated that many recent major projects have experienced schedule, quality and financial challenges both in the nuclear industry (STUK, 2011) and in the non-nuclear domain (Ahola et al., 2014; Brady and Davies, 2010). Since project delays and quality issues have been perceived mainly as economic problems, project management issues remain largely understudied in safety research. However, safety cannot be separated from other performance aspects if a systemic view is applied. Schedule and quality challenges may reflect deficiencies in coordination, knowledge and competence, distribution of roles and responsibilities or attitudes among the project participants. It is increasingly understood that the performance of the project network in all

Nuclear Safety Project

International Nuclear Information System (INIS)

1978-11-01

The 13th semi-annual report 1/78 is a description of work within the Nuclear Safety Project performed in the first six months of 1978 in the nuclear safety field by KFK institutes and departments and by external institutions on behalf of KfK. It includes for each individual research activity short summaries on - work completed, - essential results, - plans for the near future. (orig./RW) [de

Nuclear Safety Project

International Nuclear Information System (INIS)

1983-12-01

The semiannual progress report 1983/1 is a description of work within the Nuclear Safety Project performed in the first six month of 1983 in the nuclear safety field by KfK institutes and departments and by external institutions on behalf of KfK. The chosen kind of this report is that of short summaries, containing the topics work performed, results obtained and plans for future work. (orig./RW) [de

Nuclear safety project

International Nuclear Information System (INIS)

Anon.

1980-11-01

The 17th semi-annual report 1980/1 is a description of work within the Nuclear Safety Project performed in the first six months of 1980 in the nuclear safety field by KfK institutes and departments and by external institutions on behalf of KfK. The chosen kind of this report is that of short summaries, containing the topics - work performed, results obtained, plans for future work. (orig.) [de

Safety Specialist Manpower, Manpower Resources. Volumes II and III.

Science.gov (United States)

Booz Allen and Hamilton, Inc., Washington, DC.

These second and third volumes of a four-volume study of manpower in state highway safety programs over the next decade estimate manpower resources by state and in national aggregate and describe present and planned training programs for safety specialists. For each educational level, both total manpower and manpower actually available for…

Guidance and Control Software Project Data - Volume 3: Verification Documents

Science.gov (United States)

Hayhurst, Kelly J. (Editor)

2008-01-01

The Guidance and Control Software (GCS) project was the last in a series of software reliability studies conducted at Langley Research Center between 1977 and 1994. The technical results of the GCS project were recorded after the experiment was completed. Some of the support documentation produced as part of the experiment, however, is serving an unexpected role far beyond its original project context. Some of the software used as part of the GCS project was developed to conform to the RTCA/DO-178B software standard, "Software Considerations in Airborne Systems and Equipment Certification," used in the civil aviation industry. That standard requires extensive documentation throughout the software development life cycle, including plans, software requirements, design and source code, verification cases and results, and configuration management and quality control data. The project documentation that includes this information is open for public scrutiny without the legal or safety implications associated with comparable data from an avionics manufacturer. This public availability has afforded an opportunity to use the GCS project documents for DO-178B training. This report provides a brief overview of the GCS project, describes the 4-volume set of documents and the role they are playing in training, and includes the verification documents from the GCS project. Volume 3 contains four appendices: A. Software Verification Cases and Procedures for the Guidance and Control Software Project; B. Software Verification Results for the Pluto Implementation of the Guidance and Control Software; C. Review Records for the Pluto Implementation of the Guidance and Control Software; and D. Test Results Logs for the Pluto Implementation of the Guidance and Control Software.

Chemical Safety Vulnerability Working Group report. Volume 2

International Nuclear Information System (INIS)

1994-09-01

The Chemical Safety Vulnerability (CSV) Working Group was established to identify adverse conditions involving hazardous chemicals at DOE facilities that might result in fires or explosions, release of hazardous chemicals to the environment, or exposure of workers or the public to chemicals. A CSV Review was conducted in 148 facilities at 29 sites. Eight generic vulnerabilities were documented related to: abandoned chemicals and chemical residuals; past chemical spills and ground releases; characterization of legacy chemicals and wastes; disposition of legacy chemicals; storage facilities and conditions; condition of facilities and support systems; unanalyzed and unaddressed hazards; and inventory control and tracking. Weaknesses in five programmatic areas were also identified related to: management commitment and planning; chemical safety management programs; aging facilities that continue to operate; nonoperating facilities awaiting deactivation; and resource allocations. Volume 2 consists of seven appendices containing the following: Tasking memorandums; Project plan for the CSV Review; Field verification guide for the CSV Review; Field verification report, Lawrence Livermore National Lab.; Field verification report, Oak Ridge Reservation; Field verification report, Savannah River Site; and the Field verification report, Hanford Site

Chemical Safety Vulnerability Working Group report. Volume 2

Energy Technology Data Exchange (ETDEWEB)

1994-09-01

The Chemical Safety Vulnerability (CSV) Working Group was established to identify adverse conditions involving hazardous chemicals at DOE facilities that might result in fires or explosions, release of hazardous chemicals to the environment, or exposure of workers or the public to chemicals. A CSV Review was conducted in 148 facilities at 29 sites. Eight generic vulnerabilities were documented related to: abandoned chemicals and chemical residuals; past chemical spills and ground releases; characterization of legacy chemicals and wastes; disposition of legacy chemicals; storage facilities and conditions; condition of facilities and support systems; unanalyzed and unaddressed hazards; and inventory control and tracking. Weaknesses in five programmatic areas were also identified related to: management commitment and planning; chemical safety management programs; aging facilities that continue to operate; nonoperating facilities awaiting deactivation; and resource allocations. Volume 2 consists of seven appendices containing the following: Tasking memorandums; Project plan for the CSV Review; Field verification guide for the CSV Review; Field verification report, Lawrence Livermore National Lab.; Field verification report, Oak Ridge Reservation; Field verification report, Savannah River Site; and the Field verification report, Hanford Site.

Project safety studies - nuclear waste management (PSE)

International Nuclear Information System (INIS)

1981-10-01

The project 'Safety Studies-Nuclear Waste Management' (PSE) is a research project performed by order of the Federal Minister for Research and Technology, the general purpose of which is to deepen and ensure the understanding of the safety aspects of the nuclear waste management and to prepare a risk analysis which will have to be established in the future. Owing to this the project is part of a series of projects which serve the further development of the concept of nuclear waste management and its safety, and which are set up in such a way as to accompany the realization of that concept. This report contains the results of the first stage of the project from 1978 to mid-1981. (orig./RW) [de

Proceedings of the twenty-fourth water reactor safety information meeting. Volume 2: Reactor pressure vessel embrittlement and thermal annealing; Reactor vessel lower head integrity; Evaluation and projection of steam generator tube condition and integrity

Energy Technology Data Exchange (ETDEWEB)

Monteleone, S. [comp.] [Brookhaven National Lab., Upton, NY (United States)

1997-02-01

This three-volume report contains papers presented at the Twenty-Fourth Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, October 21--23, 1996. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from Czech Republic, Finland, France, Japan, Norway, Russia and United Kingdom. This volume is divided into the following sections: reactor pressure vessel embrittlement and thermal annealing; reactor vessel lower head integrity; and evaluation and projection of steam generator tube condition and integrity. Selected papers are indexed separately for inclusion in the Energy Science and Technology Database.

Proceedings of the twenty-fourth water reactor safety information meeting. Volume 2: Reactor pressure vessel embrittlement and thermal annealing; Reactor vessel lower head integrity; Evaluation and projection of steam generator tube condition and integrity

International Nuclear Information System (INIS)

Monteleone, S.

1997-02-01

This three-volume report contains papers presented at the Twenty-Fourth Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, October 21--23, 1996. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from Czech Republic, Finland, France, Japan, Norway, Russia and United Kingdom. This volume is divided into the following sections: reactor pressure vessel embrittlement and thermal annealing; reactor vessel lower head integrity; and evaluation and projection of steam generator tube condition and integrity. Selected papers are indexed separately for inclusion in the Energy Science and Technology Database

ELECTRICAL SAFETY IMPROVEMENT PROJECT A COMPLEX WIDE TEAMING INITIATIVE

Energy Technology Data Exchange (ETDEWEB)

GRAY BJ

2007-11-26

This paper describes the results of a year-long project, sponsored by the Energy Facility Contractors Group (EFCOG) and designed to improve overall electrical safety performance throughout Department of Energy (DOE)-owned sites and laboratories. As evidenced by focused metrics, the Project was successful primarily due to the joint commitment of contractor and DOE electrical safety experts, as well as significant support from DOE and contractor senior management. The effort was managed by an assigned project manager, using classical project-management principles that included execution of key deliverables and regular status reports to the Project sponsor. At the conclusion of the Project, the DOE not only realized measurable improvement in the safety of their workers, but also had access to valuable resources that will enable them to do the following: evaluate and improve electrical safety programs; analyze and trend electrical safety events; increase electrical safety awareness for both electrical and non-electrical workers; and participate in ongoing processes dedicated to continued improvement.

Impact of Construction Health & Safety Regulations on Project ...

African Journals Online (AJOL)

Impact of Construction Health & Safety Regulations on Project Parameters in Nigeria: Consultants and Contractors View. ... The study recommends that better attention is given to health and safety should as a project parameter and that related practice notes and guidelines should be evolved for all project stakeholders.

Nuclear Safety Project. Annual report 1983

International Nuclear Information System (INIS)

1984-06-01

The annual report 1983 is a detailed description (in German language) of work within the Nuclear Safety Project performed in 1983 in the nuclear safety field by KfK institutes and departments and by external institutes on behalf of KfK. It includes for each individual research activity short summaries in English language on work performed, results obtained and plans for future work. This report was compiled by the project management. (orig.) [de

Nuclear safety project. Annual report 1985

International Nuclear Information System (INIS)

1986-07-01

The annual report 1985 is a detailed description (in German language) of work within the nuclear safety project performed in 1985 in the nuclear safety field by KfK institutes and departments and by external institutes on behalf of KfK. It includes for each individual research activity short summaries in English language on work performed, results obtained and plans for future work. This report was compiled by the project management. (orig./HP) [de

Cesium legacy safety project management work plan

International Nuclear Information System (INIS)

Durham, J.S.

1998-01-01

This Management Work Plan (MWP) describes the process flow, quality assurance controls, and the Environment, Safety, and Health requirements of the Cesium Legacy Safety Project. This MWP provides an overview of the project goals and methods for repackaging the non-conforming Type W overpacks and packaging the CsCl powder and pellets. This MWP is not intended to apply to other activities associated with the CsCl Legacy Safety Program (i.e., clean out of South Cell)

NASA's Aviation Safety and Modeling Project

Science.gov (United States)

Chidester, Thomas R.; Statler, Irving C.

2006-01-01

The Aviation Safety Monitoring and Modeling (ASMM) Project of NASA's Aviation Safety program is cultivating sources of data and developing automated computer hardware and software to facilitate efficient, comprehensive, and accurate analyses of the data collected from large, heterogeneous databases throughout the national aviation system. The ASMM addresses the need to provide means for increasing safety by enabling the identification and correcting of predisposing conditions that could lead to accidents or to incidents that pose aviation risks. A major component of the ASMM Project is the Aviation Performance Measuring System (APMS), which is developing the next generation of software tools for analyzing and interpreting flight data.

Use of safety management practices for improving project performance.

Science.gov (United States)

Cheng, Eddie W L; Kelly, Stephen; Ryan, Neal

2015-01-01

Although site safety has long been a key research topic in the construction field, there is a lack of literature studying safety management practices (SMPs). The current research, therefore, aims to test the effect of SMPs on project performance. An empirical study was conducted in Hong Kong and the data collected were analysed with multiple regression analysis. Results suggest that 3 of the 15 SMPs, which were 'safety committee at project/site level', 'written safety policy', and 'safety training scheme' explained the variance in project performance significantly. Discussion about the impact of these three SMPs on construction was provided. Assuring safe construction should be an integral part of a construction project plan.

Nuclear carrier business volume projections, 1980-2000

International Nuclear Information System (INIS)

Lebo, R.G.; McKeown, M.S.; Rhyne, W.R.

1980-05-01

The expected number of shipments of commodities in the nuclear fuel cycle are projected for the years 1980 thru 2000. Projections are made for: yellowcake (U 3 O 8 ); natural, enriched and reprocessed uranium hexafluoride (UF 6 ); uranium dioxide powder (UO 2 ); plutonium dioxide powder (PuO 2 ); fresh UO 2 and mixed oxide (MOX) fuel; spent UO 2 fuel; low-level waste (LLW); transuranic (TRU) waste; high-activity TRU waste; high-level waste (HLW), and cladding hulls. Projections are also made for non-fuel cycle commodities such as defense TRU wastes and institutional wastes, since they also are shipped by the commercial transportation industry. Projections of waste shipments from LWRs are based on the continuation of current volume reduction and solidification techniques now used by the utility industry. Projections are also made based on a 5% per year reduction in LWR waste volume shipped which is assumed to occur as a result of increased implementation of currently available volume reduction systems. This assumption results in a net 64% decrease in the total waste shipped by the year 2000. LWR waste shipment projections, and essentially all other projections for fuel cycle commodities covered in this report, are normalized to BWR and PWR generating capacity projections set forth by the Department of Energy (DOE) in their low-growth projection of April, 1979. Therefore these commodity shipment projections may be altered to comply with future changes in generating capacity projections. Projected shipments of waste from the reprocessing of spent UO 2 fuel are based on waste generation rates proposed by Nuclear Fuels Services, Allied-General Nuclear Services, Exxon Nuclear, and the DOE. Reprocessing is assumed to begin again in 1990, with mixed oxide fresh fuel available for shipment by 1991

Real options and volume uncertainty by field development projects

International Nuclear Information System (INIS)

Ekern, S.; Stensland, G.

1993-12-01

The report concerns a study on the use of option methodology in field development projects. The report shows how the value of flexibility in the different decision processes is to be found by means of real option methodology. Particular attention is laid on the uncertainty concerning the volume of reserves and production capacity. The results from the study were based on the research project dubbed ''Use of real options in field development projects''. The project is partially connected to another project dubbed ''Decisive behaviour and alternative action under uncertainty in the petroleum sector''. Main topics cover as follow: Example with volume uncertainty; real options and volume uncertainty; gradual disclosure of uncertainty in the production; value of flexible production equipment. 33 refs., 19 figs., 17 tabs

Outline of criticality safety research project

International Nuclear Information System (INIS)

Kobayashi, Iwao; Tachimori, Shoichi; Suzaki, Takenori; Takeshita, Isao; Miyoshi, Yoshinori; Nakajima, Ken; Sakurai, Satoshi; Yanagisawa, Hiroshi

1987-01-01

As the power generation capacity of LWRs in Japan increased, the establishment and development of nuclear fuel cycle have become the important subject. Conforming to the safety research project of the nation, the Japan Atomic Energy Research Institute has advanced the project of constructing a new research facility, that is, Nuclear Fuel Cycle Engineering Research Facility (NUCEF). In this facility, it is planned to carry out the research on criticality safety, upgraded reprocessing techniques, and the treatment and disposal of transuranium element wastes. In this paper, the subjects of criticality safety research and the research carried out with a criticality safety experiment facility which is expected to be installed in the NUCEF are briefly reported. The experimental data obtained from the criticality safety handbooks and published literatures in foreign countries are short of the data on the mixture of low enriched uranium and plutonium which is treated in the reprocessing of spent fuel from LWRs. The acquisition of the criticality data for various forms of fuel, the elucidation of the scenario of criticality accidents, and the soundness of the confinement system for gaseous fission products and plutonium are the main subjects. The Static Criticality Safety Facility, Transient Criticality Safety Facility and pulse column system are the main facilities. (Kako, I.)

UMTRA Project environmental, health, and safety plan

International Nuclear Information System (INIS)

1989-02-01

The basic health and safety requirements established in this plan are designed to provide guidelines to be applied at all Uranium Mill Tailings Remedial Action (UMTRA) Project sites. Specific restrictions are given where necessary. However, an attempt has been made to provide guidelines which are generic in nature, and will allow for evaluation of site-specific conditions. Health and safety personnel are expected to exercise professional judgment when interpreting these guidelines to ensure the health and safety of project personnel and the general population. This UMTRA Project Environmental, Health, and Safety (EH ampersand S) Plan specifies the basic Federal health and safety standards and special DOE requirements applicable to this program. In addition, responsibilities in carrying out this plan are delineated. Some guidance on program requirements and radiation control and monitoring is also included. An Environmental, Health, and Safety Plan shall be developed as part of the remedial action plan for each mill site and associated disposal site. Special conditions at the site which may present potential health hazards will be described, and special areas that should should be addressed by the Remedial Action Contractor (RAC) will be indicated. Site-specific EH ampersand S concerns will be addressed by special contract conditions in RAC subcontracts. 2 tabs

Understanding lean & safety projects: analysis of case studies

Directory of Open Access Journals (Sweden)

Maria Crema

2017-12-01

Full Text Available Facing the current socio-economic contingency while guaranteeing a high level of care quality is particularly challenging in the field of healthcare. Through an integrated adoption of emerging managerial solutions, projects that allow organizations to achieve both efficiency and patient safety improvements could be implemented, thereby transposing policy directives towards a safer and more sustainable healthcare system. Therefore, the purpose of this paper is to investigate the features of Lean & Safety (L&S projects. Three Health Lean Management (HLM projects that had unexpected patient safety results were selected from the same region. Differences and similarities among the cases have been highlighted and interesting points of evidence have been noted. Despite the fact that the projects were pursuing similar objectives and benefiting from comparable support, the obtained changes had direct impact on patient safety enhancement in the cases that involved the front-office processes, and an indirect impact on patient safely for the L&S project that focused on back-office activities. The implementation processes and the Information and Communication Technologies (ICT adoption of the cases are also different.

Index to Nuclear Safety: a technical progress review by chronology, permuted title, and author, Volume 18 (1) through Volume 22 (6)

International Nuclear Information System (INIS)

Cottrell, W.B.; Passiakos, M.

1982-06-01

This index to Nuclear Safety covers articles published in Nuclear Safety, Volume 18, Number 1 (January-February 1977) through Volume 22, Number 6 (November-December 1981). The index is divided into three section: a chronological list of articles (including abstracts), a permuted-title (KWIC) index, and an author index. Nuclear Safety, a bimonthly technical progress review prepared by the Nuclear Safety Information Center, covers all safety aspects of nuclear power reactors and associated facilities. Over 300 technical articles published in Nuclear Safety in the last 5 years are listed in this index

Index to Nuclear Safety: a technical progress review by chronology, permuted title, and author, Volume 18 (1) through Volume 22 (6)

Energy Technology Data Exchange (ETDEWEB)

Cottrell, W.B.; Passiakos, M.

1982-06-01

This index to Nuclear Safety covers articles published in Nuclear Safety, Volume 18, Number 1 (January-February 1977) through Volume 22, Number 6 (November-December 1981). The index is divided into three section: a chronological list of articles (including abstracts), a permuted-title (KWIC) index, and an author index. Nuclear Safety, a bimonthly technical progress review prepared by the Nuclear Safety Information Center, covers all safety aspects of nuclear power reactors and associated facilities. Over 300 technical articles published in Nuclear Safety in the last 5 years are listed in this index.

Spent nuclear fuel project technical databook

Energy Technology Data Exchange (ETDEWEB)

Reilly, M.A.

1998-07-22

The Spent Nuclear Fuel (SNF) project technical databook provides project-approved summary tables of selected parameters and derived physical quantities, with nominal design and safety basis values. It contains the parameters necessary for a complete documentation basis of the SNF Project technical and safety baseline. The databook is presented in two volumes. Volume 1 presents K Basins SNF related information. Volume 2 (not yet available) will present selected sludge and water information, as it relates to the sludge and water removal projects. The values, within this databook, shall be used as the foundation for analyses, modeling, assumptions, or other input to SNF project safety analyses or design. All analysis and modeling using a parameter available in this databook are required to use and cite the appropriate associated value, and document any changes to those values (i.e., analysis assumptions, equipment conditions, etc). Characterization and analysis efforts are ongoing to validate, or update these values.

Spent nuclear fuel project technical databook

International Nuclear Information System (INIS)

Reilly, M.A.

1998-01-01

The Spent Nuclear Fuel (SNF) project technical databook provides project-approved summary tables of selected parameters and derived physical quantities, with nominal design and safety basis values. It contains the parameters necessary for a complete documentation basis of the SNF Project technical and safety baseline. The databook is presented in two volumes. Volume 1 presents K Basins SNF related information. Volume 2 (not yet available) will present selected sludge and water information, as it relates to the sludge and water removal projects. The values, within this databook, shall be used as the foundation for analyses, modeling, assumptions, or other input to SNF project safety analyses or design. All analysis and modeling using a parameter available in this databook are required to use and cite the appropriate associated value, and document any changes to those values (i.e., analysis assumptions, equipment conditions, etc). Characterization and analysis efforts are ongoing to validate, or update these values

Spent Nuclear Fuel Project Safety Management Plan

International Nuclear Information System (INIS)

Garvin, L.J.

1996-02-01

The Spent Nuclear Fuel Project Safety Management Plan describes the new nuclear facility regulatory requirements basis for the Spemt Nuclear Fuel (SNF) Project and establishes the plan to achieve compliance with this basis at the new SNF Project facilities

Index to Nuclear Safety: a technical progress review by chrology, permuted title, and author, Volume 11(1) through Volume 20(6)

Energy Technology Data Exchange (ETDEWEB)

Cottrell, W B; Passiakos, M

1980-06-01

This index to Nuclear Safety, a bimonthly technical progress review, covers articles published in Nuclear Safety, Volume II, No. 1 (January-February 1970), through Volume 20, No. 6 (November-December 1979). It is divided into three sections: a chronological list of articles (including abstracts) followed by a permuted-title (KWIC) index and an author index. Nuclear Safety, a bimonthly technical progress review prepared by the Nuclear Safety Information Center (NSIC), covers all safety aspects of nuclear power reactors and associated facilities. Over 600 technical articles published in Nuclear Safety in the last ten years are listed in this index.

MATHEMATICAL APPARATUS FOR KNOWLEDGE BASE PROJECT MANAGEMENT OF OCCUPATIONAL SAFETY

Directory of Open Access Journals (Sweden)

Валентина Николаевна ПУРИЧ

2015-05-01

Full Text Available The occupational safety project (OSP management is aimed onto a rational choice implementation. With respect to the subjectivity of management goals the project selection is considered as a minimum formalization level information process, The proposed project selection model relies upon the enterprise’s occupational and industrial safety assessment using fuzzy logic and linguistic variables based on occupational safety knowledge base.

Criticality safety benchmark evaluation project: Recovering the past

Energy Technology Data Exchange (ETDEWEB)

Trumble, E.F.

1997-06-01

A very brief summary of the Criticality Safety Benchmark Evaluation Project of the Westinghouse Savannah River Company is provided in this paper. The purpose of the project is to provide a source of evaluated criticality safety experiments in an easily usable format. Another project goal is to search for any experiments that may have been lost or contain discrepancies, and to determine if they can be used. Results of evaluated experiments are being published as US DOE handbooks.

Joint nuclear safety research projects between the US and Russian Federation International Nuclear Safety Centers

International Nuclear Information System (INIS)

Bougaenko, S.E.; Kraev, A.E.; Hill, D.L.; Braun, J.C.; Klickman, A.E.

1998-01-01

The Russian Federation Ministry for Atomic Energy (MINATOM) and the US Department of Energy (USDOE) formed international Nuclear Safety Centers in October 1995 and July 1996, respectively, to collaborate on nuclear safety research. Since January 1997, the two centers have initiated the following nine joint research projects: (1) INSC web servers and databases; (2) Material properties measurement and assessment; (3) Coupled codes: Neutronic, thermal-hydraulic, mechanical and other; (4) Severe accident management for Soviet-designed reactors; (5) Transient management and advanced control; (6) Survey of relevant nuclear safety research facilities in the Russian Federation; (8) Advanced structural analysis; and (9) Development of a nuclear safety research and development plan for MINATOM. The joint projects were selected on the basis of recommendations from two groups of experts convened by NEA and from evaluations of safety impact, cost, and deployment potential. The paper summarizes the projects, including the long-term goals, the implementing strategy and some recent accomplishments for each project

Guidance and Control Software Project Data - Volume 4: Configuration Management and Quality Assurance Documents

Science.gov (United States)

Hayhurst, Kelly J. (Editor)

2008-01-01

The Guidance and Control Software (GCS) project was the last in a series of software reliability studies conducted at Langley Research Center between 1977 and 1994. The technical results of the GCS project were recorded after the experiment was completed. Some of the support documentation produced as part of the experiment, however, is serving an unexpected role far beyond its original project context. Some of the software used as part of the GCS project was developed to conform to the RTCA/DO-178B software standard, "Software Considerations in Airborne Systems and Equipment Certification," used in the civil aviation industry. That standard requires extensive documentation throughout the software development life cycle, including plans, software requirements, design and source code, verification cases and results, and configuration management and quality control data. The project documentation that includes this information is open for public scrutiny without the legal or safety implications associated with comparable data from an avionics manufacturer. This public availability has afforded an opportunity to use the GCS project documents for DO-178B training. This report provides a brief overview of the GCS project, describes the 4-volume set of documents and the role they are playing in training, and includes configuration management and quality assurance documents from the GCS project. Volume 4 contains six appendices: A. Software Accomplishment Summary for the Guidance and Control Software Project; B. Software Configuration Index for the Guidance and Control Software Project; C. Configuration Management Records for the Guidance and Control Software Project; D. Software Quality Assurance Records for the Guidance and Control Software Project; E. Problem Report for the Pluto Implementation of the Guidance and Control Software Project; and F. Support Documentation Change Reports for the Guidance and Control Software Project.

Relational approach in managing construction project safety: a social capital perspective.

Science.gov (United States)

Koh, Tas Yong; Rowlinson, Steve

2012-09-01

Existing initiatives in the management of construction project safety are largely based on normative compliance and error prevention, a risk management approach. Although advantageous, these approaches are not wholly successful in further lowering accident rates. A major limitation lies with the approaches' lack of emphasis on the social and team processes inherent in construction project settings. We advance the enquiry by invoking the concept of social capital and project organisational processes, and their impacts on project safety performance. Because social capital is a primordial concept and affects project participants' interactions, its impact on project safety performance is hypothesised to be indirect, i.e. the impact of social capital on safety performance is mediated by organisational processes in adaptation and cooperation. A questionnaire survey was conducted within Hong Kong construction industry to test the hypotheses. 376 usable responses were received and used for analyses. The results reveal that, while the structural dimension is not significant, the mediational thesis is generally supported with the cognitive and relational dimensions affecting project participants' adaptation and cooperation, and the latter two processes affect safety performance. However, the cognitive dimension also directly affects safety performance. The implications of these results for project safety management are discussed. Copyright © 2011 Elsevier Ltd. All rights reserved.

Low-level radioactive waste in the northeast: revised waste volume projections

International Nuclear Information System (INIS)

1984-06-01

The volume of low-level radioactive waste generated in the eleven Northeast states has undergone significant change since the inital 1982 analysis and projection. These revised projections incorporate improved data reporting and evidence of sharp declines in certain categories of waste. Volumes in the 1982-1983 period reflect waste shipped for disposal as reported by disposal site operators. Projected waste volumes represent waste intended for disposal. The recent dramatic changes in source reduction and waste management practices underscore the need for annual review of waste volume projections. The volume of waste shipped for off-site disposal has declined approximately 12% in two years, from an average 1,092,500 ft 3 annually in 1979 to 1981 to an average annual 956,500 ft 3 in 1982 to 1983; reactor waste disposal volumes declined by about 39,000 ft 3 or 7% during this period. Non-reactor waste volumes shipped for disposal declined by over 70,000 ft 3 or 15% during this period. The data suggest that generators increased their use of such management practices as source reduction, compaction, or, for carbon-14 and tritium, temporary storage followed by disposal as non-radioactive waste under the NRC de minimus standard effective March 1981. Using the Technical Subcommittee projection methodology, the volume of low-level waste produced annually in the eleven states, individually and collectively, is expected to increase through the year 2000, but at a significantly lower rate of increase than initially projected. By the year 2000, the Northeast is projected to generate 1,137,600 ft 3 of waste annually, an increase of about 20% over 1982 to 1983 average volume

Assessment of Contributions to Patient Safety Knowledge by the Agency for Healthcare Research and Quality-Funded Patient Safety Projects

Science.gov (United States)

Sorbero, Melony E S; Ricci, Karen A; Lovejoy, Susan; Haviland, Amelia M; Smith, Linda; Bradley, Lily A; Hiatt, Liisa; Farley, Donna O

2009-01-01

Objective To characterize the activities of projects funded in Agency for Healthcare Research and Quality (AHRQ)' patient safety portfolio and assess their aggregate potential to contribute to knowledge development. Data Sources Information abstracted from proposals for projects funded in AHRQ' patient safety portfolio, information on safety practices from the AHRQ Evidence Report on Patient Safety Practices, and products produced by the projects. Study Design This represented one part of the process evaluation conducted as part of a longitudinal evaluation based on the Context–Input–Process–Product model. Principal Findings The 234 projects funded through AHRQ' patient safety portfolio examined a wide variety of patient safety issues and extended their work beyond the hospital setting to less studied parts of the health care system. Many of the projects implemented and tested practices for which the patient safety evidence report identified a need for additional evidence. The funded projects also generated a substantial body of new patient safety knowledge through a growing number of journal articles and other products. Conclusions The projects funded in AHRQ' patient safety portfolio have the potential to make substantial contributions to the knowledge base on patient safety. The full value of this new knowledge remains to be confirmed through the synthesis of results. PMID:21456108

19th JANNAF Safety and Environmental Protection Subcommittee Meeting. Volume 1

Science.gov (United States)

Cocchiaro, J. E. (Editor); Becker, D. L. (Editor)

2002-01-01

This volume, the first of two volumes, is a compilation of 22 unclassified/unlimited technical papers presented at the 19th Joint Army-Navy-NASA-Air Force (JANNAF) Safety & Environmental Protection Subcommittee Meeting. The meeting was held 18-21 March 2002 at the Sheraton Colorado Springs Hotel, Colorado Springs, Colorado. Topics covered include green energetic materials and life cycle pollution prevention; space launch range safety; propellant/munitions demilitarization, recycling, and reuse: and environmental and occupational health aspects of propellants and energetic materials.

Between demarcation and discretion: The medical-administrative boundary as a locus of safety in high-volume organisational routines.

Science.gov (United States)

Grant, Suzanne; Guthrie, Bruce

2018-04-01

Patient safety is an increasing concern for health systems internationally. The majority of administrative work in UK general practice takes place in the context of organisational routines such as repeat prescribing and test results handling, where high workloads and increased clinician dependency on administrative staff have been identified as an emerging safety issue. Despite this trend, most research to date has focused on the redistribution of the clinical workload between doctors, nurses and allied health professionals within individual care settings. Drawing on Strauss's negotiated order perspective, we examine ethnographically the achievement of safety across the medical-administrative boundary in key high-volume routines in UK general practice. We focus on two main issues. First, GPs engaged in strategies of demarcation by defining receptionist work as routine, unspecialised and dependent upon GP clinical knowledge and oversight as the safety net to deal with complexity and risk. Receptionists consented to this 'social closure' when describing their role, thus reinforcing the underlying inter-occupational relationship of medical domination. Second, in everyday practice, GPs and receptionists engaged in informal boundary-blurring to safely accommodate the complexity of everyday high-volume routine work. This comprised additional informal discretionary spaces for receptionist decision-making and action that went beyond the routine safety work formally assigned to them. New restratified intra-occupational hierarchies were also being created between receptionists based on the complexity of the safety work that they were authorised to do at practice level, with specialised roles constituting a new form of administrative 'professional project'. The article advances negotiated order theory by providing an in-depth examination of the ways in which medical-administrative boundary-making and boundary-blurring constitute distinct modes of safety in high-volume

Safety report concerning the reactor Pegase - volume 1 - Description of the installation - volume 2 - Safety of the installations

International Nuclear Information System (INIS)

Lacour, J.

1964-01-01

In the first volume: This report is a description of the reactor Pegase, given with a view to examine the safety of the installations. The Cadarache site at which they are situated is briefly described, in particular because of the consequences on the techniques employed for building Pegase. A description is also given of the original aspects of the reactor. The independent loops which are designed for full-scale testing of fuel elements used in natural uranium-gas-graphite reactor systems are described in this report, together with their operational and control equipment. In the second volume: In the present report are examined the accidents which could cause damage to the Pegase reactor installation. Among possible causes of accidents considered are the seismicity of the region, an excessive power excursion of the reactor and a fracture in the sealing of an independent loop. Although all possible precautions have been taken to offset the effects of such accidents, their ultimate consequences are considered here. The importance is stressed of the security action and regulations which, added to the precautions taken for the construction, ensure the safety of the installations. (authors) [fr

Multivariate volume visualization through dynamic projections

Energy Technology Data Exchange (ETDEWEB)

Liu, Shusen [Univ. of Utah, Salt Lake City, UT (United States); Wang, Bei [Univ. of Utah, Salt Lake City, UT (United States); Thiagarajan, Jayaraman J. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Bremer, Peer -Timo [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Pascucci, Valerio [Univ. of Utah, Salt Lake City, UT (United States)

2014-11-01

We propose a multivariate volume visualization framework that tightly couples dynamic projections with a high-dimensional transfer function design for interactive volume visualization. We assume that the complex, high-dimensional data in the attribute space can be well-represented through a collection of low-dimensional linear subspaces, and embed the data points in a variety of 2D views created as projections onto these subspaces. Through dynamic projections, we present animated transitions between different views to help the user navigate and explore the attribute space for effective transfer function design. Our framework not only provides a more intuitive understanding of the attribute space but also allows the design of the transfer function under multiple dynamic views, which is more flexible than being restricted to a single static view of the data. For large volumetric datasets, we maintain interactivity during the transfer function design via intelligent sampling and scalable clustering. As a result, using examples in combustion and climate simulations, we demonstrate how our framework can be used to visualize interesting structures in the volumetric space.

Developing a stochastic traffic volume prediction model for public-private partnership projects

Science.gov (United States)

Phong, Nguyen Thanh; Likhitruangsilp, Veerasak; Onishi, Masamitsu

2017-11-01

Transportation projects require an enormous amount of capital investment resulting from their tremendous size, complexity, and risk. Due to the limitation of public finances, the private sector is invited to participate in transportation project development. The private sector can entirely or partially invest in transportation projects in the form of Public-Private Partnership (PPP) scheme, which has been an attractive option for several developing countries, including Vietnam. There are many factors affecting the success of PPP projects. The accurate prediction of traffic volume is considered one of the key success factors of PPP transportation projects. However, only few research works investigated how to predict traffic volume over a long period of time. Moreover, conventional traffic volume forecasting methods are usually based on deterministic models which predict a single value of traffic volume but do not consider risk and uncertainty. This knowledge gap makes it difficult for concessionaires to estimate PPP transportation project revenues accurately. The objective of this paper is to develop a probabilistic traffic volume prediction model. First, traffic volumes were estimated following the Geometric Brownian Motion (GBM) process. Monte Carlo technique is then applied to simulate different scenarios. The results show that this stochastic approach can systematically analyze variations in the traffic volume and yield more reliable estimates for PPP projects.

Thirteenth water reactor safety research information meeting: proceedings Volume 1

International Nuclear Information System (INIS)

Weiss, A.J.

1986-02-01

This six-volume report contains 151 papers out of the 178 that were presented at the Thirteenth Water Reactor Safety Research Information Meeting held at the National Bureau of Standards, Gaithersburg, Maryland, during the week of October 22-25, 1985. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included thirty-one different papers presented by researchers from Japan, Canada and eight European countries. The title of the papers and the names of the authors have been updated and may differ from those that appeared in the final program of the meeting. This volume presents information on: risk analysis PRA application; severe accident sequence analysis; risk analysis/dependent failure analysis; and industry safety research

Organizational analysis and safety for utilities with nuclear power plants: perspectives for organizational assessment. Volume 2

International Nuclear Information System (INIS)

Osborn, R.N.; Olson, J.; Sommers, P.E.

1983-08-01

This two-volume report presents the results of initial research on the feasibility of applying organizational factors in nuclear power plant (NPP) safety assessment. Volume 1 of this report contains an overview of the literature, a discussion of available safety indicators, and a series of recommendations for more systematically incorporating organizational analysis into investigations of nuclear power plant safety. The six chapters of this volume discuss the major elements in our general approach to safety in the nuclear industry. The chapters include information on organizational design and safety; organizational governance; utility environment and safety related outcomes; assessments by selected federal agencies; review of data sources in the nuclear power industry; and existing safety indicators

Safety culture and subcontractor network governance in a complex safety critical project

International Nuclear Information System (INIS)

Oedewald, Pia; Gotcheva, Nadezhda

2015-01-01

In safety critical industries many activities are currently carried out by subcontractor networks. Nevertheless, there are few studies where the core dimensions of resilience would have been studied in safety critical network activities. This paper claims that engineering resilience into a system is largely about steering the development of culture of the system towards better ability to anticipate, monitor, respond and learn. Thus, safety culture literature has relevance in resilience engineering field. This paper analyzes practical and theoretical challenges in applying the concept of safety culture in a complex, dynamic network of subcontractors involved in the construction of a new nuclear power plant in Finland, Olkiluoto 3. The concept of safety culture is in focus since it is widely used in nuclear industry and bridges the scientific and practical interests. This paper approaches subcontractor networks as complex systems. However, the management model of the Olkiluoto 3 project is to a large degree a traditional top-down hierarchy, which creates a mismatch between the management approach and the characteristics of the system to be managed. New insights were drawn from network governance studies. - Highlights: • We studied a relevant topical subject safety culture in nuclear new build project. • We integrated safety science challenges and network governance studies. • We produced practicable insights in managing safety of subcontractor networks

Cigeo storage project - Examination of the Safety options file. Meeting of the Experts Permanent Groups for wastes and for laboratories and plants on the 18-19 May 2017

International Nuclear Information System (INIS)

2017-01-01

This document contains a report in two volumes and several appendices with documents issues by other bodies than the IRSN (notably the ASN). The two volumes report a study made on the request of the ASN regarding safety options for the Cigeo project of deep geological storage of nuclear wastes. The first volume proposes a description of the Cigeo project (site, storage architecture, parcels, Cigeo timescale, storage closure, processes implemented within the installations, Cigeo adaptability to inventory evolution, safety functions), addresses the waste parcel inventory (parcel inventory, reference radiological and chemical inventories, storage planning, reserve wastes, spent fuels), presents elements related to the site itself (geological context, natural resources, geo-dynamic characterisation, host rock, hydro-geology of aquifer layers), discusses the evolution of storage components (parcel behaviour after storage closure, evolution of steels, of concretes and of clayey materials). The second volume proposes a detailed overview of the safety approach for the different phases (exploitation, and after closure), proposes an assessment of safety during the exploitation phase (internal risks from nuclear origin, internal aggressions like fire, flooding or explosion, or related to parcel transport and handling, external aggressions like earthquakes, external flooding, and issues related to exploitation effluents and wastes), and proposes a safety assessment after closure (risk analysis for underground installations, and assessment of the global confinement capacity)

Nuclear Safety Project - annual report 1980

International Nuclear Information System (INIS)

1981-08-01

The Annual Report 1980 is a detailed description (in German language) of work within the Nuclear Safety Project performed in 1980 in the nuclear safety field by KfK institutes and departments and by external institutes on behalf of KfK. It includes for each individual research activity short summaries in English language on work completed, essential results, plans for the near future. (orig./RW) [de

Sensitivity and uncertainty analyses applied to criticality safety validation. Volume 2

International Nuclear Information System (INIS)

Broadhead, B.L.; Hopper, C.M.; Parks, C.V.

1999-01-01

This report presents the application of sensitivity and uncertainty (S/U) analysis methodologies developed in Volume 1 to the code/data validation tasks of a criticality safety computational study. Sensitivity and uncertainty analysis methods were first developed for application to fast reactor studies in the 1970s. This work has revitalized and updated the existing S/U computational capabilities such that they can be used as prototypic modules of the SCALE code system, which contains criticality analysis tools currently in use by criticality safety practitioners. After complete development, simplified tools are expected to be released for general use. The methods for application of S/U and generalized linear-least-square methodology (GLLSM) tools to the criticality safety validation procedures were described in Volume 1 of this report. Volume 2 of this report presents the application of these procedures to the validation of criticality safety analyses supporting uranium operations where enrichments are greater than 5 wt %. Specifically, the traditional k eff trending analyses are compared with newly developed k eff trending procedures, utilizing the D and c k coefficients described in Volume 1. These newly developed procedures are applied to a family of postulated systems involving U(11)O 2 fuel, with H/X values ranging from 0--1,000. These analyses produced a series of guidance and recommendations for the general usage of these various techniques. Recommendations for future work are also detailed

DOE standard: Integration of environment, safety, and health into facility disposition activities. Volume 2: Appendices

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-05-01

This volume contains the appendices that provide additional environment, safety, and health (ES and H) information to complement Volume 1 of this Standard. Appendix A provides a set of candidate DOE ES and H directives and external regulations, organized by hazard types that may be used to identify potentially applicable directives to a specific facility disposition activity. Appendix B offers examples and lessons learned that illustrate implementation of ES and H approaches discussed in Section 3 of Volume 1. Appendix C contains ISMS performance expectations to guide a project team in developing and implementing an effective ISMS and in developing specific performance criteria for use in facility disposition. Appendix D provides guidance for identifying potential Applicable or Relevant and Appropriate Requirements (ARARs) when decommissioning facilities fall under the Comprehensive Environmental Response, Compensation, Liability Act (CERCLA) process. Appendix E discusses ES and H considerations for dispositioning facilities by privatization. Appendix F is an overview of the WSS process. Appendix G provides a copy of two DOE Office of Nuclear Safety Policy and Standards memoranda that form the bases for some of the guidance discussed within the Standard. Appendix H gives information on available hazard analysis techniques and references. Appendix I provides a supplemental discussion to Sections 3.3.4, Hazard Baseline Documentation, and 3.3.6, Environmental Permits. Appendix J presents a sample readiness evaluation checklist.

DOE standard: Integration of environment, safety, and health into facility disposition activities. Volume 2: Appendices

International Nuclear Information System (INIS)

1998-05-01

This volume contains the appendices that provide additional environment, safety, and health (ES and H) information to complement Volume 1 of this Standard. Appendix A provides a set of candidate DOE ES and H directives and external regulations, organized by hazard types that may be used to identify potentially applicable directives to a specific facility disposition activity. Appendix B offers examples and lessons learned that illustrate implementation of ES and H approaches discussed in Section 3 of Volume 1. Appendix C contains ISMS performance expectations to guide a project team in developing and implementing an effective ISMS and in developing specific performance criteria for use in facility disposition. Appendix D provides guidance for identifying potential Applicable or Relevant and Appropriate Requirements (ARARs) when decommissioning facilities fall under the Comprehensive Environmental Response, Compensation, Liability Act (CERCLA) process. Appendix E discusses ES and H considerations for dispositioning facilities by privatization. Appendix F is an overview of the WSS process. Appendix G provides a copy of two DOE Office of Nuclear Safety Policy and Standards memoranda that form the bases for some of the guidance discussed within the Standard. Appendix H gives information on available hazard analysis techniques and references. Appendix I provides a supplemental discussion to Sections 3.3.4, Hazard Baseline Documentation, and 3.3.6, Environmental Permits. Appendix J presents a sample readiness evaluation checklist

Krsko periodic safety review project prioritization process

International Nuclear Information System (INIS)

Basic, I.; Vrbanic, I.; Spiler, J.; Lambright, J.

2004-01-01

Definition of a Krsko Periodic Safety Review (PSR) project is a comprehensive safety review of a plant after last ten years of operation. The objective is a verification by means of a comprehensive review using current methods that Krsko NPP remains safety when judged against current safety objectives and practices and that adequate arrangements are in place to maintain plant safety. This objective encompasses the three main criteria or goals: confirmation that the plant is as safe as originally intended, determination if there are any structures, systems or components that could limit the life of the plant in the foreseeable future, and comparison the plant against modern safety standards and to identify where improvements would be beneficial at justifiable cost. Krsko PSR project is structured in the three phases: Phase 1: Preparation of Detailed 10-years PSR Program, Phase 2: Performing of 10-years PSR Program and preparing of associated documents (2001-2003), and Phase 3: Implementation of the prioritized compensatory measures and modifications (development of associated EEAR, DMP, etc.) after agreement with the SNSA on the design, procedures and time-scales (2004-2008). This paper presents the NEK PSR results of work performed under Phase 2 focused on the ranking of safety issues and prioritization of corrective measures needed for establishing an efficient action plan. Safety issues were identified in Phase 2 during the following review processes: Periodic Safety Review (PSR) task; Krsko NPP Regulatory Compliance Program (RCP) review; Westinghouse Owner Group (WOG) catalog items screening/review; SNSA recommendations (including IAEA RAMP mission suggestions/recommendations).(author)

Project safety as a sustainable competitive advantage.

Science.gov (United States)

Rechenthin, David

2004-01-01

To be consistently profitable, a construction company must complete projects in scope, on schedule, and on budget. At the same time, the nature of the often high-risk work performed by construction companies can result in high accident rates. Clients and other stakeholders are placing increasing pressure on companies to decrease those accident rates. Clients routinely demand copies of safety plans and evidence of past results at the "pre-qualification" or "request for proposal" stages of the procurement process. Are high accident rates and the associated costs just a part of business? Companies that deliver on scope, schedule, and budget have a competitive advantage. Is it possible for projects with low accident rates to use it as a competitive advantage? Is the value added by safety just a temporary or parity issue, or does a successful safety program offer significant advantage to the company and the client? This article concludes that in the case of a high-risk industry, such as the construction industry, an organization with a successful safety program can promote safety performance as a sustainable competitive advantage. It is a choice the company can make.

SAFETY IMPROVES DRAMATICALLY IN FLUOR HANFORD SOIL AND GROUNDWATER REMEDIATION PROJECT

International Nuclear Information System (INIS)

GERBER MS

2007-01-01

This paper describes dramatic improvements in the safety record of the Soil and Groundwater Remediation Project (SGRP) at the Hanford Site in southeast Washington state over the past four years. During a period of enormous growth in project work and scope, contractor Fluor Hanford reduced injuries, accidents, and other safety-related incidents and enhanced a safety culture that earned the SGRP Star Status in the Department of Energy's (DOE's) Voluntary Protection Program (VPP) in 2007. This paper outlines the complex and multi-faceted work of Fluor Hanford's SGRP and details the steps taken by the project's Field Operations and Safety organizations to improve safety. Holding field safety meetings and walkdowns, broadening safety inspections, organizing employee safety councils, intensively flowing down safety requirements to subcontractors, and adopting other methods to achieve remarkable improvement in safety are discussed. The roles of management, labor and subcontractors are detailed. Finally, SGRP's safety improvements are discussed within the context of overall safety enhancements made by Fluor Hanford in the company's 11 years of managing nuclear waste cleanup at the Hanford Site

2009 transparency and nuclear safety report. CEA Cadarache. Volumes 1 + 2

International Nuclear Information System (INIS)

2009-01-01

After a general presentation of the Cadarache site and of its nuclear installations, the first volume of this report describes the various measures concerning the site safety (safety organisation, general measures, measures related to various risks, inspections, control of emergency situations, audits and second level control, measures in basic nuclear installations) and radioprotection (organisation, significant facts, dosimeter results). It describes significant events which occurred in relationship with nuclear safety and radioprotection, presents results of measurements of releases and of their impact on the environment (chemical and radiological assessment). Then after a description of measures to limit the volume of stored radioactive wastes and their impact on health and on the environment, tables indicate the nature and quantities of wastes which are stored in the different basic nuclear installations of Cadarache. The second volume proposes the same information for two specific nuclear installations belonging to Areva and located in Cadarache, the INB 32 and 54 (INB stands for basic nuclear installation) for which a significant event occurred on the 6 October 2009. For these installations, release measurements concern gaseous and liquid releases

Proceedings of the 1984 DOE nuclear reactor and facility safety conference. Volume II

Energy Technology Data Exchange (ETDEWEB)

1984-01-01

This report is a collection of papers on reactor safety. The report takes the form of proceedings from the 1984 DOE Nuclear Reactor and Facility Safety Conference, Volume II of two. These proceedings cover Safety, Accidents, Training, Task/Job Analysis, Robotics and the Engineering Aspects of Man/Safety interfaces.

Proceedings of the 1984 DOE nuclear reactor and facility safety conference. Volume II

International Nuclear Information System (INIS)

1984-01-01

This report is a collection of papers on reactor safety. The report takes the form of proceedings from the 1984 DOE Nuclear Reactor and Facility Safety Conference, Volume II of two. These proceedings cover Safety, Accidents, Training, Task/Job Analysis, Robotics and the Engineering Aspects of Man/Safety interfaces

Light water reactor safety research project

International Nuclear Information System (INIS)

Markoczy, G.; Aksan, S.N.; Behringer, K.; Prodan, M.; Stierli, F.; Ullrich, G.

1980-07-01

The research and development activities for the safety of Light Water Power Reactors carried out 1979 at the Swiss Federal Institute for Reactor Research are described. Considerations concerning the necessity, objectives and size of the Safety Research Project are presented, followed by a detailed discussion of the activities in the five tasks of the program, covering fracture mechanics and nondestructive testing, thermal-hydraulics, reactor noise analysis and pressure vessel steel surveillance. (Auth.)

Practice and innovation on safety management of Haiyang Nuclear Power Project

International Nuclear Information System (INIS)

Wei Guohu

2011-01-01

From the perspective of owner, this article has introduced the safety management model and practice of Haiyang Nuclear Power Project, one of AP1000 Self-reliance Program supporting projects of China. And the article has summarized characteristics of the safety management of Haiyang Project for reference and communication with nuclear or other projects. (author)

Overview of DOE/ONS criticality safety projects

International Nuclear Information System (INIS)

Barber, R.W.; Brown, B.P.; Hopper, C.M.

1985-01-01

The evolution of Federal involvement with nuclear criticality safety has traversed through the 1940's and early 1950's with the Manhattan Engineering District, the 1950's and 1960's with the Atomic Energy Commission, the early 1970's with the Energy Research and Development Administration, and the late 1970's to date with the US Department of Energy. The importance of nuclear criticality safety has been maintained throughout these periods; however, criticality safety has received shifting emphases in research/applications, promulgations of regulations/standards, origins of fiscal support and organization. In June 1981 the Office of Nuclear Safety was established in response to a Department of Energy study of the impact of the March 1979 Three Mile Island accident. The organizational structure of the ONS, its program for establishing and maintaining a progressive nuclear criticality safety program, and associated projects, and current history of ONS's fiscal support of program projects is presented. With the establishment of the ONS came concomitant missions to develop and maintain nuclear safety policy and requirements, to provide independent assurance that nuclear operations are performed safely, to provide resources and management for DOE responses to nuclear accidents, and to provide technical support. In the past four years, ONS has developed and initiated a continuing Department Nuclear Criticality Safety Program in such areas as communications and information, physics of criticality, knowledge of factors affecting criticality, and computational capability

Low-level radioactive waste in the northeast: disposal volume projections

International Nuclear Information System (INIS)

1982-10-01

The northeastern states, with support of the Coalition of Northeastern Governors (CONEG), are developing compact(s) for the disposal and management of low-level radioactive waste (LLRW) generated in the eleven northeastern states (Connecticut, Delaware, Maine, Maryland, Massachusetts, New Hampshire, New Jersey, New York, Pennsylvania, Rhode Island, and Vermont). The Technical Subcommittee has made a projection of future low-level radioactive waste to the year 2000 based on existing waste volume data and anticipated growth in the Northeast states. Aware of the difficulties involved with any long range projection - unforeseen events can drastically change projections based on current assumptions - the Technical Subcommittee believes that waste volume projections should be reviewed annually as updated information becomes available. The Technical Subcommittee made the following findings based upon a conservative projection methodology: volumes of low-level waste produced annually in the eleven states individually and collectively are expected to grow continually through the year 2000 with the rate of increase varying by state; by the year 2000, the Northeast is projected to generate 58,000 m 3 of low-level waste annually, about 1.9 times the current average; and based on current estimates, 47% of the total projected waste volume in the year 2000 will be produced by nuclear power plants, compared to the current average of 54%. Non-reactor wastes will equal 53% of the total in the year 2000 compared to the current 46%

SAFETY IMPROVES DRAMATICALLY IN FLUOR HANFORD SOIL AND GROUNDWATER REMEDIATION PROJECT

Energy Technology Data Exchange (ETDEWEB)

GERBER MS

2007-12-05

This paper describes dramatic improvements in the safety record of the Soil and Groundwater Remediation Project (SGRP) at the Hanford Site in southeast Washington state over the past four years. During a period of enormous growth in project work and scope, contractor Fluor Hanford reduced injuries, accidents, and other safety-related incidents and enhanced a safety culture that earned the SGRP Star Status in the Department of Energy's (DOE's) Voluntary Protection Program (VPP) in 2007. This paper outlines the complex and multi-faceted work of Fluor Hanford's SGRP and details the steps taken by the project's Field Operations and Safety organizations to improve safety. Holding field safety meetings and walkdowns, broadening safety inspections, organizing employee safety councils, intensively flowing down safety requirements to subcontractors, and adopting other methods to achieve remarkable improvement in safety are discussed. The roles of management, labor and subcontractors are detailed. Finally, SGRP's safety improvements are discussed within the context of overall safety enhancements made by Fluor Hanford in the company's 11 years of managing nuclear waste cleanup at the Hanford Site.

Safety Culture Enhancement Project. Final Report. A Field Study on Approaches to Enhancement of Safety Culture

Energy Technology Data Exchange (ETDEWEB)

Lowe, Andrew; Hayward, Brent (Dedale Asia Pacific, Albert Park VIC 3206 (Australia))

2006-08-15

This report documents a study with the objective of enhancing safety culture in the Swedish nuclear power industry. A primary objective of this study was to ensure that the latest thinking on human factors principles was being recognised and applied by nuclear power operators as a means of ensuring optimal safety performance. The initial phase of the project was conducted as a pilot study, involving the senior management group at one Swedish nuclear power-producing site. The pilot study enabled the project methodology to be validated after which it was repeated at other Swedish nuclear power industry sites, providing a broad-ranging analysis of opportunities across the industry to enhance safety culture. The introduction to this report contains an overview of safety culture, explains the background to the project and sets out the project rationale and objectives. The methodology used for understanding and analysing the important safety culture issues at each nuclear power site is then described. This section begins with a summary of the processes used in the information gathering and data analysis stage. The six components of the Management Workshops conducted at each site are then described. These workshops used a series of presentations, interactive events and group exercises to: (a) provide feedback to site managers on the safety culture and safety leadership issues identified at their site, and (b) stimulate further safety thinking and provide 'take-away' information and leadership strategies that could be applied to promote safety culture improvements. Section 3, project Findings, contains the main observations and output from the project. These include: - a brief overview of aspects of the local industry operating context that impinge on safety culture; - a summary of strengths or positive attributes observed within the safety culture of the Swedish nuclear industry; - a set of identified opportunities for further improvement; - the aggregated

Nuclear power. Volume 2: nuclear power project management

International Nuclear Information System (INIS)

Anon.

1980-01-01

The following topics are discussed: review of nuclear power plants; licensing procedures; safety analysis; project professional services; quality assurance and project organization; construction, scheduling and operation; construction, scheduling and operation; nuclear fuel handling and fuel management; and plant cost management. 116 references, 115 figures, 33 tables

Proceedings of the international topical meeting on advanced reactors safety: Volume 2

International Nuclear Information System (INIS)

1997-01-01

In this volume, 89 papers are grouped under the following headings: advances in research/test reactor safety; advanced reactor accident management and emergency actions; advanced reactors instrumentation/controls/human factors; probabilistic risk/safety and reliability assessments; steam explosion research and issues; advanced reactor severe accident issues and research (analysis and assessments); advanced reactor thermal hydraulics; accelerator-driven source safety; liquid-metal reactor safety; structural assessments and issues; late papers

Technical Assistance in Evaluating Career Education Projects. Final Report. Volume I: Summary Volume.

Science.gov (United States)

Stenner, A. Jackson; And Others

This document contains the first of five volumes reporting the activities and results of a career education evaluation project conducted to accomplish the following two objectives: (1) to improve the quality of evaluations by career education projects funded by the United States Office of Career Education (OCE) through the provision of technical…

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)

Ohi, J M

1992-09-01

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 potential chemical, electrical, and thermal hazards and risks of Na/S cells and batteries as well as the RD&D performed, under way, or to address these hazards and risks. The report is based on a review of the literature and on discussions with experts at DOE, national laboratories and agencies, universities, and private industry. Subsequent volumes will address environmental, health, and safety issues involved in shipping cells and batteries, using batteries to propel electric vehicles, and recycling and disposing of spent batteries. The remainder of this volume is divided into two major sections on safety at the cell and battery levels. The section on Na/S cells describes major component and potential failure modes, design, life testing and failure testing, thermal cycling, and the safety status of Na/S cells. The section on batteries describes battery design, testing, and safety status. Additional EH&S information on Na/S batteries is provided in the appendices.

Safety Culture in New Build Projects

International Nuclear Information System (INIS)

Reiman, T.

2016-01-01

The concept of culture emphasises the social factors that have an effect on the way hazards are perceived, risks are evaluated, risk management is conducted, the current safety level is interpreted, and what is considered normal and what abnormal. It also contributes to defining the correct ways to behave in situations and correct ways to talk about safety, risks or uncertainty. Culture is something the company has created for itself that then has an effect on the company. This effect is not necessarily perceived by the company itself, since the members of the organization consider all things that happen according to their cultural taken-for-granted assumptions (“business as usual”). Thus, safety culture can either hinder or advance nuclear safety. This depends on what the shared values and assumptions are, and how they are in line with, and influence, the organizational structures, practices, personnel and technology. Safety culture requires constant and systematic development, monitoring and review during the entire life-cycle of a nuclear facility. The pre-operational phase sets many unique requirements for nuclear safety culture. For example, some of the organizations and individuals involved in the project may have no insight on how safety culture relates to nuclear power plants. Companies that work in the conventional industry typically associate safety with occupational safety issues, not with nuclear safety. Further, it may be unclear how the construction phase affects nuclear safety of an operating plant. When workers are asked to perform their work differently than previously (e.g., in conventional construction sites), explanation has to be given. For example, structures, systems and components may have different functions during emergency that exceed or differ from their quality requirements during normal operation. The strict quality requirements and use of certain methods and procedures, documentation requirements, etc., may seem unimportant if

Organizational analysis and safety for utilities with nuclear power plants: an organizational overview. Volume 1

International Nuclear Information System (INIS)

Osborn, R.N.; Olson, J.; Sommers, P.E.; McLaughlin, S.D.; Jackson, M.S.; Scott, W.G.; Connor, P.E.

1983-08-01

This two-volume report presents the results of initial research on the feasibility of applying organizational factors in nuclear power plant (NPP) safety assessment. A model is introduced for the purposes of organizing the literature review and showing key relationships among identified organizational factors and nuclear power plant safety. Volume I of this report contains an overview of the literature, a discussion of available safety indicators, and a series of recommendations for more systematically incorporating organizational analysis into investigations of nuclear power plant safety

The Fukushima Daiichi Accident. Technical Volume 2/5. Safety Assessment

International Nuclear Information System (INIS)

2015-08-01

Technical Volume 1 of this report has described what happened during the accident at the Fukushima Daiichi nuclear power plant (NPP). This volume begins (Section 2.1) with a review of how the design basis of the site for external events was assessed initially and then reassessed over the life of the NPP. The section also describes the physical changes that were made to the units as a result. The remainder of the volume describes the treatment of beyond design basis events in the safety assessment of the site, the accident management provisions, the effectiveness of regulatory programmes, human and organizational factors and the safety culture, and the role of operating experience. Further background information is contained in three annexes included on the CD-ROM of this Technical Volume which describe analytical investigations of the accident along with information on topics such as system performance, defence in depth and severe accident phenomena. Section 2.2 provides an assessment of the systems that failed, resulting in a failure to maintain the fundamental safety functions in Units 1–3, which were in operation at the time of the tsunami and in which the reactor pressure vessels (RPV) and containment vessels failed. The section also describes Units 4-6, which were shut down at the time of the tsunami, and the site’s central spent fuel storage facility. Section 2.3 discusses the probabilistic and deterministic safety assessments of beyond design basis accidents (BDBAs) that had been performed for the plant and the insights from these assessments that had led to changes in the plant’s design. The section pays particular attention to the assessment of extreme natural hazards, such as the one which led to the total loss of AC power supply on the site. The additional loss of DC power supply in Units 1 and 2 played a key role in the progression of the accident because it impeded the diagnosis of plant conditions and made the operators unaware of the status of

SNF fuel retrieval sub project safety analysis document

International Nuclear Information System (INIS)

BERGMANN, D.W.

1999-01-01

This safety analysis is for the SNF Fuel Retrieval (FRS) Sub Project. The FRS equipment will be added to K West and K East Basins to facilitate retrieval, cleaning and repackaging the spent nuclear fuel into Multi-Canister Overpack baskets. The document includes a hazard evaluation, identifies bounding accidents, documents analyses of the accidents and establishes safety class or safety significant equipment to mitigate accidents as needed

SNF fuel retrieval sub project safety analysis document

Energy Technology Data Exchange (ETDEWEB)

BERGMANN, D.W.

1999-02-24

This safety analysis is for the SNF Fuel Retrieval (FRS) Sub Project. The FRS equipment will be added to K West and K East Basins to facilitate retrieval, cleaning and repackaging the spent nuclear fuel into Multi-Canister Overpack baskets. The document includes a hazard evaluation, identifies bounding accidents, documents analyses of the accidents and establishes safety class or safety significant equipment to mitigate accidents as needed.

Safety equipment list for the 241-SY-101 RAPID mitigation project

Energy Technology Data Exchange (ETDEWEB)

MORRIS, K.L.

1999-06-29

This document provides the safety classification for the safety (safety class and safety RAPID Mitigation Project. This document is being issued as the project SEL until the supporting authorization basis documentation, this document will be superseded by the TWRS SEL (LMHC 1999), documentation istlralized. Upon implementation of the authorization basis significant) structures, systems, and components (SSCS) associated with the 241-SY-1O1 which will be updated to include the information contained herein.

Safety equipment list for the 241-SY-101 RAPID mitigation project

International Nuclear Information System (INIS)

Morris, K.L.

1999-01-01

This document provides the safety classification for the safety (safety class and safety RAPID Mitigation Project. This document is being issued as the project SEL until the supporting authorization basis documentation, this document will be superseded by the TWRS SEL (LMHC 1999), documentation istlralized. Upon implementation of the authorization basis significant) structures, systems, and components (SSCS) associated with the 241-SY-1O1 which will be updated to include the information contained herein

Status of safety issues at licensed power plants: TMI action plan requirements, unresolved safety issues, generic safety issues

International Nuclear Information System (INIS)

1991-12-01

As part of ongoing US Nuclear Regulatory Commission (NRC) efforts to ensure the quality and accountability of safety issue information, a program was established whereby an annual NUREG report would be published on the status of licensee implementation and NRC verification of safety issues in major NRC requirements areas. This information was compiled and reported in three NUREG volumes. Volume 1, published in March 1991, addressed the status of of Three Mile Island (TMI) Action Plan Requirements. Volume 2, published in May 1991, addressed the status of unresolved safety issues (USIs). Volume 3, published in June 1991, addressed the implementation and verification status of generic safety issues (GSIs). This annual NUREG report combines these volumes into a single report and provides updated information as of September 30, 1991. The data contained in these NUREG reports are a product of the NRC's Safety Issues Management System (SIMS) database, which is maintained by the Project Management Staff in the Office of Nuclear Reactor Regulation and by NRC regional personnel. This report is to provide a comprehensive description of the implementation and verification status of TMI Action Plan Requirements, safety issues designated as USIs, and GSIs that have been resolved and involve implementation of an action or actions by licensees. This report makes the information available to other interested parties, including the public. An additional purpose of this NUREG report is to serve as a follow-on to NUREG-0933, ''A Prioritization of Generic Safety Issues,'' which tracks safety issues up until requirements are approved for imposition at licensed plants or until the NRC issues a request for action by licensees

Safety Culture Enhancement Project. Final Report. A Field Study on Approaches to Enhancement of Safety Culture

International Nuclear Information System (INIS)

Lowe, Andrew; Hayward, Brent

2006-08-01

This report documents a study with the objective of enhancing safety culture in the Swedish nuclear power industry. A primary objective of this study was to ensure that the latest thinking on human factors principles was being recognised and applied by nuclear power operators as a means of ensuring optimal safety performance. The initial phase of the project was conducted as a pilot study, involving the senior management group at one Swedish nuclear power-producing site. The pilot study enabled the project methodology to be validated after which it was repeated at other Swedish nuclear power industry sites, providing a broad-ranging analysis of opportunities across the industry to enhance safety culture. The introduction to this report contains an overview of safety culture, explains the background to the project and sets out the project rationale and objectives. The methodology used for understanding and analysing the important safety culture issues at each nuclear power site is then described. This section begins with a summary of the processes used in the information gathering and data analysis stage. The six components of the Management Workshops conducted at each site are then described. These workshops used a series of presentations, interactive events and group exercises to: (a) provide feedback to site managers on the safety culture and safety leadership issues identified at their site, and (b) stimulate further safety thinking and provide 'take-away' information and leadership strategies that could be applied to promote safety culture improvements. Section 3, project Findings, contains the main observations and output from the project. These include: - a brief overview of aspects of the local industry operating context that impinge on safety culture; - a summary of strengths or positive attributes observed within the safety culture of the Swedish nuclear industry; - a set of identified opportunities for further improvement; - the aggregated results of the

Safety of magnetic fusion facilities: Volume 2, Guidance

International Nuclear Information System (INIS)

1995-01-01

This document provides guidance for the implementation of the requirements identified in Vol. 1 of this Standard. This guidance is intended for the managers, designers, operators, and other personnel with safety responsibilities for facilities designated as magnetic fusion facilities. While Vol. 1 is generally applicable in that requirements there apply to a wide range of fusion facilities, this volume is concerned mainly with large facilities such as the International Thermonuclear Experimental Reactor (ITER). Using a risk-based prioritization, the concepts presented here may also be applied to other magnetic fusion facilities. This volume is oriented toward regulation in the Department of Energy (DOE) environment

Nuclear Safety Project. Annual report 1986

International Nuclear Information System (INIS)

1987-09-01

The annual report 1986 is a detailed description of work within the Nuclear Safety Project performed in 1986 in the nuclear safety field by KfK institutes and departments and by external institutes on behalf of KfK. It includes individual research activities on dynamic loads and strains of reactor components under accident conditions, fuel behaviour under accident conditions, investigation and control of LWR core-meltdown accidents, improvement of fission product retention and reduction of radiation exposure, and on behaviour, impact and removal of released pollutants. (DG)

PETRO-SAFE '94 conference papers: Book 2. Volume 5: Emergency response ampersand spill control; Volume 6: Remediation; Volume 7: Health ampersand safety issues

International Nuclear Information System (INIS)

Anon.

1994-01-01

The Fifth Annual Environmental, Safety and Health Conference and Exhibition for the oil, gas and petrochemical industries was held January 25--27, 1994 in Houston, Texas. The objective of this conference was to provide a multidisciplinary forum dealing with state-of-the-art environmental and safety issues. This volume focuses on the following: emergency response and spill control; remediation; and health and safety issues. Individual papers have been processed separately for inclusion in the appropriate data bases

Organizational analysis and safety for utilities with nuclear power plants: perspectives for organizational assessment. Volume 2. [PWR; BWR

Energy Technology Data Exchange (ETDEWEB)

Osborn, R.N.; Olson, J.; Sommers, P.E.; McLaughlin, S.D.; Jackson, M.S.; Nadel, M.V.; Scott, W.G.; Connor, P.E.; Kerwin, N.; Kennedy, J.K. Jr.

1983-08-01

This two-volume report presents the results of initial research on the feasibility of applying organizational factors in nuclear power plant (NPP) safety assessment. Volume 1 of this report contains an overview of the literature, a discussion of available safety indicators, and a series of recommendations for more systematically incorporating organizational analysis into investigations of nuclear power plant safety. The six chapters of this volume discuss the major elements in our general approach to safety in the nuclear industry. The chapters include information on organizational design and safety; organizational governance; utility environment and safety related outcomes; assessments by selected federal agencies; review of data sources in the nuclear power industry; and existing safety indicators.

Implementing Patient Safety Initiatives in Rural Hospitals

Science.gov (United States)

Klingner, Jill; Moscovice, Ira; Tupper, Judith; Coburn, Andrew; Wakefield, Mary

2009-01-01

Implementation of patient safety initiatives can be costly in time and energy. Because of small volumes and limited resources, rural hospitals often are not included in nationally driven patient safety initiatives. This article describes the Tennessee Rural Hospital Patient Safety Demonstration project, whose goal was to strengthen capacity for…

25 CFR 170.144 - What are eligible highway safety projects?

Science.gov (United States)

2010-04-01

... RESERVATION ROADS PROGRAM Indian Reservation Roads Program Policy and Eligibility Highway Safety Functions... management system; (g) Education and outreach highway safety programs, such as use of child safety seats... 25 Indians 1 2010-04-01 2010-04-01 false What are eligible highway safety projects? 170.144...

Annual colloquium 1976 of the project nuclear safety

International Nuclear Information System (INIS)

1976-11-01

The present report gives the full text of the nine papers read during the annual colloquium 1976 of the Project Nuclear Safety at Karlsruhe Nuclear Research Centre, in which the main activities and findings of the project in 1976 are contained. (RW) [de

Case study: the Argentina Road Safety Project: lessons learned for the decade of action for road safety, 2011-2020.

Science.gov (United States)

Raffo, Veronica; Bliss, Tony; Shotten, Marc; Sleet, David; Blanchard, Claire

2013-12-01

This case study of the Argentina Road Safety Project demonstrates how the application of World Bank road safety project guidelines focused on institution building can accelerate knowledge transfer, scale up investment and improve the focus on results. The case study highlights road safety as a development priority and outlines World Bank initiatives addressing the implementation of the World Report on Road Traffic Injury's recommendations and the subsequent launch of the Decade of Action for Road Safety, from 2011-2020. The case study emphasizes the vital role played by the lead agency in ensuring sustainable road safety improvements and promoting the shift to a 'Safe System' approach, which necessitated the strengthening of all elements of the road safety management system. It summarizes road safety performance and institutional initiatives in Argentina leading up to the preparation and implementation of the project. We describe the project's development objectives, financing arrangements, specific components and investment staging. Finally, we discuss its innovative features and lessons learned, and present a set of supplementary guidelines, both to assist multilateral development banks and their clients with future road safety initiatives, and to encourage better linkages between the health and transportation sectors supporting them.

Expediting Clinician Adoption of Safety Practices: The UCSF Venous Access Patient Safety Interdisciplinary Education Project

National Research Council Canada - National Science Library

Donaldson, Nancy E; Plank, Rosemary K; Williamson, Ann; Pearl, Jeffrey; Kellogg, Jerry; Ryder, Marcia

2005-01-01

...) Venous Access Device (VAD) Patient Safety Interdisciplinary Education Project was to develop a 30-hour/one clinical academic unit VAD patient safety course with the aim of expediting clinician adoption of critical concepts...

Software qualification for digital safety system in KNICS project

International Nuclear Information System (INIS)

Kwon, Kee-Choon; Lee, Dong-Young; Choi, Jong-Gyun

2012-01-01

In order to achieve technical self-reliance in the area of nuclear instrumentation and control, the Korea Nuclear Instrumentation and Control System (KNICS) project had been running for seven years from 2001. The safety-grade Programmable Logic Controller (PLC) and the digital safety system were developed by KNICS project. All the software of the PLC and digital safety system were developed and verified following the software development life cycle Verification and Validation (V and V) procedure. The main activities of the V and V process are preparation of software planning documentations, verification of the Software Requirement Specification (SRS), Software Design Specification (SDS) and codes, and a testing of the software components, the integrated software, and the integrated system. In addition, a software safety analysis and a software configuration management are included in the activities. For the software safety analysis at the SRS and SDS phases, the software Hazard Operability (HAZOP) was performed and then the software fault tree analysis was applied. The software fault tree analysis was applied to a part of software module with some critical defects identified by the software HAZOP in SDS phase. The software configuration management was performed using the in-house tool developed in the KNICS project. (author)

A series of student design projects for improving and modernizing safety helmets

NARCIS (Netherlands)

Beurden, van K.M.M. (Karin); Boer, de J. (Johannes); Stilma, M. (Margot); Teeuw, W.B. (Wouter)

2014-01-01

The Saxion Research Centre for Design and Technology employs many students during research projects. This paper discusses a series of student design projects on safety helmets in the Safety@Work project. At construction sites workers are required to wear personal protective equipment during their

Nuclear criticality safety experiments, calculations, and analyses: 1958 to 1982. Volume 1. Lookup tables

International Nuclear Information System (INIS)

Koponen, B.L.; Hampel, V.E.

1982-01-01

This compilation contains 688 complete summaries of papers on nuclear criticality safety as presented at meetings of the American Nuclear Society (ANS). The selected papers contain criticality parameters for fissile materials derived from experiments and calculations, as well as criticality safety analyses for fissile material processing, transport, and storage. The compilation was developed as a component of the Nuclear Criticality Information System (NCIS) now under development at the Lawrence Livermore National Laboratory. The compilation is presented in two volumes: Volume 1 contains a directory to the ANS Transaction volume and page number where each summary was originally published, the author concordance, and the subject concordance derived from the keyphrases in titles. Volume 2 contains - in chronological order - the full-text summaries, reproduced here by permission of the American Nuclear Society from their Transactions, volumes 1-41

Fast reactor safety: proceedings of the international topical meeting. Volume 1

Energy Technology Data Exchange (ETDEWEB)

1985-07-01

The emphasis of this meeting was on the safety-related aspects of fast reactor design, analysis, licensing, construction, and operation. Relative to past meetings, there was less emphasis on the scientific and technological basis for accident assessment. Because of its broad scope, the meeting attracted 217 attendees from a wide cross section of the design, safety analysis, and safety technology communities. Eight countries and two international organizations were represented. A total of 126 papers were presented, with contributions from the United States, France, Japan, the United Kingdom, Germany, and Italy. Sessions covered in Volume 1 include: impact of safety and licensing considerations on fast reactor design; safety aspects of innovative designs; intra-subassembly behavior; operational safety; design accommodation of seismic and other external events; natural circulation; safety design concepts; safety implications derived from operational plant data; decay heat removal; and assessment of HCDA consequences.

Fast reactor safety: proceedings of the international topical meeting. Volume 1

International Nuclear Information System (INIS)

1985-07-01

The emphasis of this meeting was on the safety-related aspects of fast reactor design, analysis, licensing, construction, and operation. Relative to past meetings, there was less emphasis on the scientific and technological basis for accident assessment. Because of its broad scope, the meeting attracted 217 attendees from a wide cross section of the design, safety analysis, and safety technology communities. Eight countries and two international organizations were represented. A total of 126 papers were presented, with contributions from the United States, France, Japan, the United Kingdom, Germany, and Italy. Sessions covered in Volume 1 include: impact of safety and licensing considerations on fast reactor design; safety aspects of innovative designs; intra-subassembly behavior; operational safety; design accommodation of seismic and other external events; natural circulation; safety design concepts; safety implications derived from operational plant data; decay heat removal; and assessment of HCDA consequences

Nuclear safety research project. Annual report 1995

International Nuclear Information System (INIS)

Hueper, R.

1996-08-01

The reactor safety R and D work of the Karlsruhe Research Centre (FZK) has been part of the Nuclear Safety Research Project (PSF) since 1990. The present annual report 1995 summarizes the R and D results. The research tasks are coordinated in agreement with internal and external working groups. The contributions to this report correspond to the status of early 1996. An abstract in English precedes each of them, whenever the respective article is written in German. (orig.) [de

Baseline Projection Data Book: GRI baseline projection of U.S. Energy Supply and Demand to 2010. 1992 Edition. Volume 1 and Volume 2

International Nuclear Information System (INIS)

Holtberg, P.D.; Woods, T.J.; Lihn, M.L.; Koklauner, A.K.

1992-01-01

The 1992 Baseline Projection Data Book provides backup data in tabular form for the 1992 GRI Baseline Projection of U.S. Energy Supply and Demand to 2010. Summary tables and data for the residential, commercial, industrial, electric utility, and transportation sectors are presented in the volume

2007 transparency and nuclear safety report. CEA Cadarache. Volumes 1 + 2

International Nuclear Information System (INIS)

2007-01-01

After a general presentation of the Cadarache site and of its nuclear installations, the first volume of this report describes the various measures concerning the site safety: safety organisation, general measures, measures related to various risks, control of emergency situations, inspections, audits and second level control, measures in basic nuclear installations. It describes the measures concerning the radioprotection on this site: organisation, significant facts, and dose measurement results. It describes significant events which occurred in relationship with nuclear safety and radioprotection, presents results of release measurements and of radiological and chemical assessments of the impact these releases on the environment. The report then describes measures implemented to limit the volume of stored radioactive wastes and also their impact on health and on the environment. It provides a series of tables indicating the nature and quantities of wastes which are stored in the different basic nuclear installations of Cadarache. It reports the recommendations expressed by the CHSCT (committee on hygiene, security and working conditions) after the 2006 report. The second volume proposes the same information for two specific nuclear installations belonging to Areva and located in Cadarache, the INB 32 and 54 (INB stands for basic nuclear installation), for which the significant events occurred on the 13. of March and on the 25. of May 2007. For these installations, release measurements concern gaseous and liquid releases

Vandellos 1 decommissioning project. Safety before, during and after

International Nuclear Information System (INIS)

Rodriguez, A.

2002-01-01

The Nuclear Power Plant of Vandellos 1, a gas-graphite reactor (GCR), started operation in the 70's after 17 years running the decommissioning process began in 1998, and is expected to finish at the end of 2002 with the level 2 of decommissioning with a practically total scope reached, except the concrete reactor vessel and its internals that will remain for another 25 years in surveillance state (dormancy) until their total dismantling. During the last four years the activities related to decontamination and disassembly of the power plant system as well as the management of all this material have been carried out. One of the last phases of the project that will be performed this year, without doubt, one of the most representative of the operative difficulty of the task is the disassembly of some buildings which are more than 80 meters high and with some structures weighing more than 3.000 t, an operation, which is spectacular in terms of volume and mass involved. However one has to keep in mind that it has been preceded by the of clearance process of all these structures to be disassembled this summer. Hundred of thousands of radiological measures will confirm with guarantee that the destination of the dismantled materials is the correct one, assuring the protection of people and the environment. This is a process which has to integrate the principles of radiological safety and industrial safety. First, it has to be guaranteed that structures and components are below the values authorised by authorities for their free release, and, secondly, that the planned sequence of the process and manoeuvres in the disassembly of these colossal structures assures safety. (author)

Radiation safety at the West Valley Demonstration Project

International Nuclear Information System (INIS)

Hoffman, R.L.

1997-01-01

This is a report on the Radiation Safety Program at the West Valley Demonstration Project (WVDP). This Program covers a number of activities that support high-level waste solidification, stabilization of facilities, and decontamination and decommissioning activities at the Project. The conduct of the Program provides confidence that all occupational radiation exposures received during operational tasks at the Project are within limits, standards, and program requirements, and are as low as reasonably achievable

System Safety Program Plan for Project W-314, tank farm restoration and safe operations

International Nuclear Information System (INIS)

Boos, K.A.

1996-01-01

This System Safety Program Plan (SSPP) outlines the safety analysis strategy for project W-314, ''Tank Farm Restoration and Safe Operations.'' Project W-314 will provide capital improvements to Hanford's existing Tank Farm facilities, with particular emphasis on infrastructure systems supporting safe operation of the double-shell activities related to the project's conceptual Design Phase, but is planned to be updated and maintained as a ''living document'' throughout the life of the project to reflect the current safety analysis planning for the Tank Farm Restoration and Safe Operations upgrades. This approved W-314 SSPP provides the basis for preparation/approval of all safety analysis documentation needed to support the project

Main benefits from 30 years of joint projects in nuclear safety

International Nuclear Information System (INIS)

Thadani, Ashok; Teschendorff, Victor; Vitanza, Carlo; Hrehor, Miroslav

2012-01-01

One of the major achievements of the OECD Nuclear Energy Agency (NEA) is the knowledge it has helped to generate through the organisation of joint international research projects. Such projects, primarily in the areas of nuclear safety and radioactive waste management, enable interested countries, on a cost-sharing basis, to pursue research or the sharing of data with respect to particular areas or issues. Over the years, more than 30 joint projects have been conducted with wide participation of member countries. The purpose of this report is to describe the achievements of the OECD/NEA joint projects on nuclear safety research that have been carried out over the past three decades, with a particular focus on thermal-hydraulics, fuel behaviour and severe accidents. It shows that the resolution of specific safety issues in these areas has greatly benefited from the joint projects' activities and results. It also highlights the added value of international co-operation for maintaining unique experimental infrastructure, preserving skills and generating new knowledge

Time series trends of the safety effects of pavement resurfacing.

Science.gov (United States)

Park, Juneyoung; Abdel-Aty, Mohamed; Wang, Jung-Han

2017-04-01

This study evaluated the safety performance of pavement resurfacing projects on urban arterials in Florida using the observational before and after approaches. The safety effects of pavement resurfacing were quantified in the crash modification factors (CMFs) and estimated based on different ranges of heavy vehicle traffic volume and time changes for different severity levels. In order to evaluate the variation of CMFs over time, crash modification functions (CMFunctions) were developed using nonlinear regression and time series models. The results showed that pavement resurfacing projects decrease crash frequency and are found to be more safety effective to reduce severe crashes in general. Moreover, the results of the general relationship between the safety effects and time changes indicated that the CMFs increase over time after the resurfacing treatment. It was also found that pavement resurfacing projects for the urban roadways with higher heavy vehicle volume rate are more safety effective than the roadways with lower heavy vehicle volume rate. Based on the exploration and comparison of the developed CMFucntions, the seasonal autoregressive integrated moving average (SARIMA) and exponential functional form of the nonlinear regression models can be utilized to identify the trend of CMFs over time. Copyright © 2017 Elsevier Ltd. All rights reserved.

Radiation safety for decommissioning projects

International Nuclear Information System (INIS)

Ross, A.C.

1999-01-01

Decommissioning of redundant nuclear facilities is a growth area in the UK at the present time. NUKEM Nuclear Limited is a leading-edge nuclear decommissioning and waste management contractor (with its own in-house health physics and safety department), working for a variety of clients throughout the UK nuclear industry. NUKEM Nuclear is part of the prestigious, international NUKEM group, a world-class organization specializing in nuclear engineering and utilities technologies. NUKEM Nuclear is involved in a number of large, complex decommissioning projects, both in its own right and as part of consortia. This paper explores the challenges presented by such projects and the interfaces of contractor, client and subcontractors from the point of view of a radiation protection adviser. (author)

A root cause analysis project in a medication safety course.

Science.gov (United States)

Schafer, Jason J

2012-08-10

To develop, implement, and evaluate team-based root cause analysis projects as part of a required medication safety course for second-year pharmacy students. Lectures, in-class activities, and out-of-class reading assignments were used to develop students' medication safety skills and introduce them to the culture of medication safety. Students applied these skills within teams by evaluating cases of medication errors using root cause analyses. Teams also developed error prevention strategies and formally presented their findings. Student performance was assessed using a medication errors evaluation rubric. Of the 211 students who completed the course, the majority performed well on root cause analysis assignments and rated them favorably on course evaluations. Medication error evaluation and prevention was successfully introduced in a medication safety course using team-based root cause analysis projects.

Organizational analysis and safety for utilities with nuclear power plants: an organizational overview. Volume 1. [PWR; BWR

Energy Technology Data Exchange (ETDEWEB)

Osborn, R.N.; Olson, J.; Sommers, P.E.; McLaughlin, S.D.; Jackson, M.S.; Scott, W.G.; Connor, P.E.

1983-08-01

This two-volume report presents the results of initial research on the feasibility of applying organizational factors in nuclear power plant (NPP) safety assessment. A model is introduced for the purposes of organizing the literature review and showing key relationships among identified organizational factors and nuclear power plant safety. Volume I of this report contains an overview of the literature, a discussion of available safety indicators, and a series of recommendations for more systematically incorporating organizational analysis into investigations of nuclear power plant safety.

Developing an action-based health and safety training project in southern China.

Science.gov (United States)

Szudy, Betty; O'Rourke, Dara; Brown, Garrett D

2003-01-01

A project brought together international footwear manufacturers, labor rights groups, local contract factories, and occupational health professionals to strengthen factory health and safety programs in southern China. Steps involved in the two-year project, including needs assessment, interviews and focus groups with workers and supervisors; design and development of a participatory workshop; development of plant-wide health and safety committees in three footwear factories; and evaluation project impact, are discussed. The project significantly increased occupational safety and health knowledge, and hazards in the factories were identified and corrected. Successes and challenges faced by three functioning worker-management health and safety committees are discussed. Key elements to create effective programs with meaningful participation by workers include: 1) developing clear guidelines that enable multi-stakeholder groups to collaborate; 2) obtaining top-level management support; 3) building workers' knowledge and capacity to fully participate; 4) involving local labor rights groups and occupational professionals in support and technical assistance; and 5) connecting project goals to larger issues within a country and the global economy.

Steam Pressure-Reducing Station Safety and Energy Efficiency Improvement Project

Energy Technology Data Exchange (ETDEWEB)

Lower, Mark D [ORNL; Christopher, Timothy W [ORNL; Oland, C Barry [ORNL

2011-06-01

The Facilities and Operations (F&O) Directorate is sponsoring a continuous process improvement (CPI) program. Its purpose is to stimulate, promote, and sustain a culture of improvement throughout all levels of the organization. The CPI program ensures that a scientific and repeatable process exists for improving the delivery of F&O products and services in support of Oak Ridge National Laboratory (ORNL) Management Systems. Strategic objectives of the CPI program include achieving excellence in laboratory operations in the areas of safety, health, and the environment. Identifying and promoting opportunities for achieving the following critical outcomes are important business goals of the CPI program: improved safety performance; process focused on consumer needs; modern and secure campus; flexibility to respond to changing laboratory needs; bench strength for the future; and elimination of legacy issues. The Steam Pressure-Reducing Station (SPRS) Safety and Energy Efficiency Improvement Project, which is under the CPI program, focuses on maintaining and upgrading SPRSs that are part of the ORNL steam distribution network. This steam pipe network transports steam produced at the ORNL steam plant to many buildings in the main campus site. The SPRS Safety and Energy Efficiency Improvement Project promotes excellence in laboratory operations by (1) improving personnel safety, (2) decreasing fuel consumption through improved steam system energy efficiency, and (3) achieving compliance with applicable worker health and safety requirements. The SPRS Safety and Energy Efficiency Improvement Project being performed by F&O is helping ORNL improve both energy efficiency and worker safety by modifying, maintaining, and repairing SPRSs. Since work began in 2006, numerous energy-wasting steam leaks have been eliminated, heat losses from uninsulated steam pipe surfaces have been reduced, and deficient pressure retaining components have been replaced. These improvements helped ORNL

Gas reactor in-pile safety test project (GRIST-2)

International Nuclear Information System (INIS)

Kelley, A.P. Jr.; Arbtin, E.; St Pierre, R.

1979-01-01

Although out-of-pile tests may be expected to confirm individual phenomena models in core disruptive accident analysis codes, only in-pile tests are capable of verifying the extremely complex integrated model effects within the appropriate time phase for these accidents. For this reason, the GRIST-2 project, the purpose of which is to design and construct an in-pile helium loop capable of transient safety testing in the TREAT facility in Idaho, forms a cornerstone of the US GCFR safety program. The project organization, experiment program, facility, helium system design, and schedule which have been selected to meet the objectives are described

Fast reactor safety: proceedings of the international topical meeting. Volume 2

International Nuclear Information System (INIS)

1985-07-01

The emphasis of this meeting was on the safety-related aspects of fast reactor design, analysis, licensing, construction, and operation. Relative to past meetings, there was less emphasis on the scientific and technological basis for accident assessment. Because of its broad scope, the meeting attracted 217 attendees from a wide cross section of the design, safety analysis, and safety technology communities. Eight countries and two international organizations were represented. A total of 126 papers were presented, with contributions from the United States, France, Japan, the United Kingdom, Germany, and Italy. Sessions covered in Volume 2 include: safety design concepts; operational transient experiments; analysis of seismic and external events; HCDA-related codes, analysis, and experiments; sodium fires; instrumentation and control/PPS design; whole-core accident analysis codes; and impact of safety design considerations on future LMFBR developments

Chemical Safety Vulnerability Working Group report. Volume 3

Energy Technology Data Exchange (ETDEWEB)

1994-09-01

The Chemical Safety Vulnerability (CSV) Working Group was established to identify adverse conditions involving hazardous chemicals at DOE facilities that might result in fires or explosions, release of hazardous chemicals to the environment, or exposure of workers or the public to chemicals. A CSV Review was conducted in 148 facilities at 29 sites. Eight generic vulnerabilities were documented related to: abandoned chemicals and chemical residuals; past chemical spills and ground releases; characterization of legacy chemicals and wastes; disposition of legacy chemicals; storage facilities and conditions; condition of facilities and support systems; unanalyzed and unaddressed hazards; and inventory control and tracking. Weaknesses in five programmatic areas were also identified related to: management commitment and planning; chemical safety management programs; aging facilities that continue to operate; nonoperating facilities awaiting deactivation; and resource allocations. Volume 3 consists of eleven appendices containing the following: Field verification reports for Idaho National Engineering Lab., Rocky Flats Plant, Brookhaven National Lab., Los Alamos National Lab., and Sandia National Laboratories (NM); Mini-visits to small DOE sites; Working Group meeting, June 7--8, 1994; Commendable practices; Related chemical safety initiatives at DOE; Regulatory framework and industry initiatives related to chemical safety; and Chemical inventory data from field self-evaluation reports.

Chemical Safety Vulnerability Working Group report. Volume 3

International Nuclear Information System (INIS)

1994-09-01

The Chemical Safety Vulnerability (CSV) Working Group was established to identify adverse conditions involving hazardous chemicals at DOE facilities that might result in fires or explosions, release of hazardous chemicals to the environment, or exposure of workers or the public to chemicals. A CSV Review was conducted in 148 facilities at 29 sites. Eight generic vulnerabilities were documented related to: abandoned chemicals and chemical residuals; past chemical spills and ground releases; characterization of legacy chemicals and wastes; disposition of legacy chemicals; storage facilities and conditions; condition of facilities and support systems; unanalyzed and unaddressed hazards; and inventory control and tracking. Weaknesses in five programmatic areas were also identified related to: management commitment and planning; chemical safety management programs; aging facilities that continue to operate; nonoperating facilities awaiting deactivation; and resource allocations. Volume 3 consists of eleven appendices containing the following: Field verification reports for Idaho National Engineering Lab., Rocky Flats Plant, Brookhaven National Lab., Los Alamos National Lab., and Sandia National Laboratories (NM); Mini-visits to small DOE sites; Working Group meeting, June 7--8, 1994; Commendable practices; Related chemical safety initiatives at DOE; Regulatory framework and industry initiatives related to chemical safety; and Chemical inventory data from field self-evaluation reports

Safety cases for the co-ordinated research project on improvement of safety assessment methodologies for near surface radioactive waste disposal facilities (ISAM)

International Nuclear Information System (INIS)

Kozak, M.W.; Torres-Vidal, C.; Kelly, E.; Guskov, A.; Blerk, J. van

2002-01-01

A Co-ordinated Research Project (CRP) has recently been completed on the Improvement of Safety Assessment Methodologies for Near-Surface Radioactive Waste Disposal Facilities (ISAM). A major aspect of the project was the use of safety cases for the practical application of safety assessment. An overview of the ISAM safety cases is given in this paper. (author)

Implementing national nuclear safety plan at the preliminary stage of nuclear power project development

International Nuclear Information System (INIS)

Xue Yabin; Cui Shaozhang; Pan Fengguo; Zhang Lizhen; Shi Yonggang

2014-01-01

This study discusses the importance of nuclear power project design and engineering methods at the preliminary stage of its development on nuclear power plant's operational safety from the professional view. Specifically, we share our understanding of national nuclear safety plan's requirement on new reactor accident probability, technology, site selection, as well as building and improving nuclear safety culture and strengthening public participation, with a focus on plan's implications on preliminary stage of nuclear power project development. Last, we introduce China Huaneng Group's work on nuclear power project preliminary development and the experience accumulated during the process. By analyzing the siting philosophy of nuclear power plant and the necessity of building nuclear safety culture at the preliminary stage of nuclear power project development, this study explicates how to fully implement the nuclear safety plan's requirements at the preliminary stage of nuclear power project development. (authors)

Safety Design Strategy for the Advanced Test Reactor Emergency Firewater Injection System Replacement Project

International Nuclear Information System (INIS)

Duckwitz, Noel

2011-01-01

In accordance with the requirements of U.S. Department of Energy (DOE) Order 413.3B, 'Program and Project Management for the Acquisition of Capital Assets,' safety must be integrated into the design process for new or major modifications to DOE Hazard Category 1, 2, and 3 nuclear facilities. The intended purpose of this requirement involves the handling of hazardous materials, both radiological and chemical, in a way that provides adequate protection to the public, workers, and the environment. Requirements provided in DOE Order 413.3B and DOE Order 420.1B, 'Facility Safety,' and the expectations of DOE-STD-1189-2008, 'Integration of Safety into the Design Process,' provide for identification of hazards early in the project and use of an integrated team approach to design safety into the facility. This safety design strategy provides the basic safety-in-design principles and concepts that will be used for the Advanced Test Reactor Reliability Sustainment Project. While this project does not introduce new hazards to the ATR, it has the potential for significant impacts to safety-related systems, structures, and components that are credited in the ATR safety basis and are being replaced. Thus the project has been determined to meet the definition of a major modification and is being managed accordingly.

Fuel Rod Consolidation Project: Phase 2, Final report: Volume 2, Appendices

International Nuclear Information System (INIS)

1987-01-01

This document, Volume 2, provides the appendices to Volume 1 of the Fuel Rod Consolidation Project. It provides information on the following: References; Trade-off Studies; Instrument List; RAM Data; Fabrication Specifications; Software Specifications; and Design Requirements

Computing the maximum volume inscribed ellipsoid of a polytopic projection

NARCIS (Netherlands)

Zhen, Jianzhe; den Hertog, Dick

We introduce a novel scheme based on a blending of Fourier-Motzkin elimination (FME) and adjustable robust optimization techniques to compute the maximum volume inscribed ellipsoid (MVE) in a polytopic projection. It is well-known that deriving an explicit description of a projected polytope is

Computing the Maximum Volume Inscribed Ellipsoid of a Polytopic Projection

NARCIS (Netherlands)

Zhen, J.; den Hertog, D.

2015-01-01

We introduce a novel scheme based on a blending of Fourier-Motzkin elimination (FME) and adjustable robust optimization techniques to compute the maximum volume inscribed ellipsoid (MVE) in a polytopic projection. It is well-known that deriving an explicit description of a projected polytope is

Cloud/Fog Computing System Architecture and Key Technologies for South-North Water Transfer Project Safety

Directory of Open Access Journals (Sweden)

Yaoling Fan

2018-01-01

Full Text Available In view of the real-time and distributed features of Internet of Things (IoT safety system in water conservancy engineering, this study proposed a new safety system architecture for water conservancy engineering based on cloud/fog computing and put forward a method of data reliability detection for the false alarm caused by false abnormal data from the bottom sensors. Designed for the South-North Water Transfer Project (SNWTP, the architecture integrated project safety, water quality safety, and human safety. Using IoT devices, fog computing layer was constructed between cloud server and safety detection devices in water conservancy projects. Technologies such as real-time sensing, intelligent processing, and information interconnection were developed. Therefore, accurate forecasting, accurate positioning, and efficient management were implemented as required by safety prevention of the SNWTP, and safety protection of water conservancy projects was effectively improved, and intelligential water conservancy engineering was developed.

Integrated Environment and Safety and Health Management System (ISMS) Implementation Project Plan

Energy Technology Data Exchange (ETDEWEB)

MITCHELL, R.L.

2000-01-10

The Integrated Environment, Safety and Health Management System (ISMS) Implementation Project Plan serves as the project document to guide the Fluor Hanford, Inc (FHI) and Major Subcontractor (MSC) participants through the steps necessary to complete the integration of environment, safety, and health into management and work practices at all levels.

Integrated Environment and Safety and Health Management System (ISMS) Implementation Project Plan

International Nuclear Information System (INIS)

MITCHELL, R.L.

2000-01-01

The Integrated Environment, Safety and Health Management System (ISMS) Implementation Project Plan serves as the project document to guide the Fluor Hanford, Inc (FHI) and Major Subcontractor (MSC) participants through the steps necessary to complete the integration of environment, safety, and health into management and work practices at all levels

Safety assessment and regulatory strategy for NPP I and C modernization projects

International Nuclear Information System (INIS)

Manners, S.; Blocquel, Ch.

1999-10-01

IPSN is the technical support for the French nuclear safety authority (DSIN), but also acts independently. Through our participation at this IAEA meeting we wish to further our appreciation of the industry position for I and C modernization projects. We will present some of the concerns of the safety assessor and safety authority for such projects. We hope to share our experiences and views concerning current strategies for I and C modernization and licensing from. In our experience with NPP I and C programmes, the need for modification is most often not directly linked to safety. For our safety assessment we have to identify clearly and, as far as possible, categorize the safety relevance of the specified modifications and all safety impact in its implementation. Modernization can be simply for reasons of replacement of obsolete existing equipment or it can be linked to functional evolutions; safety functions may be directly or indirectly affected. The state of the art I and C solutions proposed by today's modernization programs have many benefits, but also pose a certain number of difficulties for the safety demonstration. On the implementation side, the safety assessment for a modernization project has to take into consideration specific issues compared with that for new plant. These include interface and compatibility with the existing installation, issues relating to 'on line' installation and commissioning, as well as operational issues concerning the changeover and trail periods. A further subject for discussion concerns how our regulatory requirements apply to modernization. We must as a minima comply with the requirements of the period. To what measure must we apply current or future (under development or for future reactor designs) standards? How can we tie in with requirements and legislation for new projects? Do we make a special case for back-fits? (authors)

Safety assessment and regulatory strategy for NPP I and C modernization projects

Energy Technology Data Exchange (ETDEWEB)

Manners, S.; Blocquel, Ch

1999-10-01

IPSN is the technical support for the French nuclear safety authority (DSIN), but also acts independently. Through our participation at this IAEA meeting we wish to further our appreciation of the industry position for I and C modernization projects. We will present some of the concerns of the safety assessor and safety authority for such projects. We hope to share our experiences and views concerning current strategies for I and C modernization and licensing from. In our experience with NPP I and C programmes, the need for modification is most often not directly linked to safety. For our safety assessment we have to identify clearly and, as far as possible, categorize the safety relevance of the specified modifications and all safety impact in its implementation. Modernization can be simply for reasons of replacement of obsolete existing equipment or it can be linked to functional evolutions; safety functions may be directly or indirectly affected. The state of the art I and C solutions proposed by today's modernization programs have many benefits, but also pose a certain number of difficulties for the safety demonstration. On the implementation side, the safety assessment for a modernization project has to take into consideration specific issues compared with that for new plant. These include interface and compatibility with the existing installation, issues relating to 'on line' installation and commissioning, as well as operational issues concerning the changeover and trail periods. A further subject for discussion concerns how our regulatory requirements apply to modernization. We must as a minima comply with the requirements of the period. To what measure must we apply current or future (under development or for future reactor designs) standards? How can we tie in with requirements and legislation for new projects? Do we make a special case for back-fits? (authors)

Report on the behalf of the special commission for the examination of the bill project, after activation of the accelerated procedure, related to energy transition for a green growth (nr 2188) - Nr 2230. Volume I, Volume II - comparative table, Volume III - hearings, impact study

International Nuclear Information System (INIS)

Bareigts, Ericka; Battistel, Marie-Noelle; Buis, Sabine; Baupin, Denis; Plisson, Philippe

2014-01-01

The first volume of this huge report reports the general discussion and the detailed examination, discussion and modifications of the French bill project on energy transition. The addressed topics are: the definition of common objectives for a successful energy transition, for a strengthening of France energy independence and for the struggle against global warming; a better renovation of buildings to save energy, to reduce prices and to create jobs; the development of clean transports to improve air quality and to protect health; the struggle against wastage and the promotion of circular economy from product design to product recycling; the promotion of renewable energies to diversify our energies and valorise territorial resources; the strengthening of nuclear safety and citizen information; the simplification and clarification of procedures for efficiency and competitiveness gains; the empowerment of citizen, enterprises, territories and State to act together. The second volume proposes a table which gives a comparative overview between the bill project text and the text modified and adopted by the commission. The third volume reports hearings of the minister and of several representatives of professional, public, and consumer organisations and bodies. It also contains the report of an impact study performed on all the different arrangements and measures contained by the bill project

Safety work organization in nuclear power plant. A9. Volume 2

International Nuclear Information System (INIS)

1985-01-01

The second volume provides the laws, directives, major standards, principles, lists of selected workplaces where woman work is prohibited, instructions for new personnel, general principles of workplace safety, reports and provisions by commissions for reporting accidents and injuries, recourses, etc. (J.P.)

Safety risk assessment using analytic hierarchy process (AHP) during planning and budgeting of construction projects.

Science.gov (United States)

Aminbakhsh, Saman; Gunduz, Murat; Sonmez, Rifat

2013-09-01

The inherent and unique risks on construction projects quite often present key challenges to contractors. Health and safety risks are among the most significant risks in construction projects since the construction industry is characterized by a relatively high injury and death rate compared to other industries. In construction project management, safety risk assessment is an important step toward identifying potential hazards and evaluating the risks associated with the hazards. Adequate prioritization of safety risks during risk assessment is crucial for planning, budgeting, and management of safety related risks. In this paper, a safety risk assessment framework is presented based on the theory of cost of safety (COS) model and the analytic hierarchy process (AHP). The main contribution of the proposed framework is that it presents a robust method for prioritization of safety risks in construction projects to create a rational budget and to set realistic goals without compromising safety. The framework provides a decision tool for the decision makers to determine the adequate accident/injury prevention investments while considering the funding limits. The proposed safety risk framework is illustrated using a real-life construction project and the advantages and limitations of the framework are discussed. Copyright © 2013 National Safety Council and Elsevier Ltd. All rights reserved.

Environmental Restoration Disposal Facility (Project W-296) Safety Assessment

International Nuclear Information System (INIS)

Armstrong, D.L.

1994-08-01

This Safety Assessment is based on information derived from the Conceptual Design Report for the Environmental Restoration Disposal Facility (DOE/RL 1994) and ancillary documentation developed during the conceptual design phase of Project W-296. The Safety Assessment has been prepared to support the Solid Waste Burial Ground Interim Safety Basis document. The purpose of the Safety Assessment is to provide an evaluation of the design to determine if the process, as proposed, will comply with US Department of Energy (DOE) Limits for radioactive and hazardous material exposures and be acceptable from an overall health and safety standpoint. The evaluation considered affects on the worker, onsite personnel, the public, and the environment

Environmental Restoration Disposal Facility (Project W-296) Safety Assessment

Energy Technology Data Exchange (ETDEWEB)

Armstrong, D.L.

1994-08-01

This Safety Assessment is based on information derived from the Conceptual Design Report for the Environmental Restoration Disposal Facility (DOE/RL 1994) and ancillary documentation developed during the conceptual design phase of Project W-296. The Safety Assessment has been prepared to support the Solid Waste Burial Ground Interim Safety Basis document. The purpose of the Safety Assessment is to provide an evaluation of the design to determine if the process, as proposed, will comply with US Department of Energy (DOE) Limits for radioactive and hazardous material exposures and be acceptable from an overall health and safety standpoint. The evaluation considered affects on the worker, onsite personnel, the public, and the environment.

Nordic projects in the field of nuclear safety

International Nuclear Information System (INIS)

Soerensen, H.C.

1989-07-01

This report describes the work in 1988 within the Nordic program concerning nuclear safety 1985-1989. The report has the form of a handbook meant for those in Scandinavia who are involeved in nuclear safety, and it is based on statements from the constituent subject fields of the program. The first chapter is a short summary of the work and results over the year. In the next chapter an account is given of the ongoing projects within each of the subject fields. An economic survey of the entire program and a list of the reports and articles published in 1988 is included in the publicaltion as well. Chapter 5 is a complete list of adresses comprising participants, project managers, program coordinators and members of the advirosy group. (SH)

Nordic projects in the field of nuclear safety

International Nuclear Information System (INIS)

Soerensen, H.C.

1988-05-01

This report deseribes the work in 1987 within the Nordic program concerning nuclear safety 1985-1989. The report has the form of a handbook meant for those in Scandinavia who are involved in nuclear safety, and it is based on statements from the constituent subject fields of the program. The first chapter is a short summary of the work and results over the year. In the next chapter an account is given of the ongoing projects within each of the subject fields. An economic survey of the entire program and a list of the reports and articles published in 1987 is included in the publication as well. Chapter 5 is a complete list of adresses comprising participants, project managers, program coordinators and members of the advisory group. (SH) 74 refs

Aviation Safety Program: Weather Accident Prevention (WxAP) Project Overview and Status

Science.gov (United States)

Nadell, Shari-Beth

2003-01-01

This paper presents a project overview and status for the Weather Accident Prevention (WxAP) aviation safety program. The topics include: 1) Weather Accident Prevention Project Background/History; 2) Project Modifications; 3) Project Accomplishments; and 4) Project's Next Steps.

Description of data-sources used in SafetyCube, Deliverable 3.1 of the H2020 project SafetyCube (Safety CaUsation, Benefits and Efficiency).

NARCIS (Netherlands)

Hagström, L. Thomson, R. Hermitte, T. Weijermars, W. Bos, N. Talbot, R. Thomas, P. Dupont, E. Martensen, H. Bauer, R. Hours, M. Høye, E. Jänsch, M. Murkovic, A. Niewöhner, W. Papadimitriou, E. Pérez, C. Phan, V. Usami, D. & Vázquez-de-Prada, J.

2017-01-01

Safety CaUsation, Benefits and Efficiency (SafetyCube) is a European Commission supported Horizon 2020 project with the objective of developing an innovative road safety Decision Support System (DSS) that will enable policy-makers and stakeholders to select and implement the most appropriate

Nuclear safety research project (PSF). 1999 annual report

International Nuclear Information System (INIS)

Muehl, B.

2000-08-01

The reactor safety R and D work of the Karlsruhe Research Centre (FZK) has been part of the Nuclear Safety Research Project (PSF) since 1990. The present annual report summarizes the R and D results of PSF during 1999. The research tasks cover three main topics: Light Water Reactor safety, innovative systems, and studies related to the transmutation of actinides. The importance of the Light Water Reactor safety, however, has decreased during the last year in favour of the transmutation of actinides. Numerous institutes of the research centre contribute to the PSF programme, as well as several external partners. The tasks are coordinated in agreement with internal and external working groups. The contributions to this report, which are either written in German or in English, correspond to the status of early/mid 2000. (orig.) [de

Transport fire safety engineering in the European Union - project TRANSFEU

Directory of Open Access Journals (Sweden)

Jolanta Maria RADZISZEWSKA-WOLIŃSKA

2011-01-01

Full Text Available Article presents European Research project (of FP7-SST-2008-RTD-1 for Surface transportation TRANSFEU. Projects undertakes to deliver both a reliable toxicity measurement methodology and a holistic fire safety approach for all kind of surface transport. It bases on a harmonized Fire Safety Engineering methodology which link passive fire security with active fire security mode. This all embracing system is the key to attain optimum design solutions in respect to fire safety objectives as an alternative to the prescriptive approach. It will help in the development of innovative solutions (design and products used for the building of the surface transport which will better respect the environment.In order to reach these objectives new toxicity measurement methodology and related classification of materials, new numerical fire simulation tools, fire test methodology (laboratory and full scale and a decisive tool to optimize or explore new design in accordance to the fire safety requirements will be developed.

UMTRA project office federal employee occupational safety and health program plan

International Nuclear Information System (INIS)

1994-06-01

This document establishes the Federal Employee Occupational Safety and Health (FEOSH) Program for the US Department of Energy (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project Office. This program will ensure compliance with applicable requirements of DOE Order 3790.1B and DOE Albuquerque Operations Office (AL) Order 3790.lA. FEOSH Program responsibilities delegated by the DOE-AL to the UMTRA Project Office by AL Order 3790.1A also are assigned. The UMTRA Project Office has developed the UMTRA Project Environmental, Safety, and Health (ES ampersand H) Plan (DOE, 1992), which establishes the basic programmatic ES ampersand H requirements for all participants on the UMTRA Project. The ES ampersand H plan is designed primarily to cover remedial action activities at UMTRA sites and defines the ES ampersand H responsibilities of both the UMTRA Project Office and its contractors. The UMTRA FEOSH Program described herein is a subset of the overall UMTRA ES ampersand H program and covers only federal employees working on the UMTRA Project

The action of the project coordinator with respect to reactor safety

International Nuclear Information System (INIS)

Leclercq, Jacques

1981-01-01

Before describing the various actions of the project coordinator (EDF) entrusted with the building of nuclear power stations, with respect to reactor safety in France, the definition of reactor safety and the various participants are mentioned first. These participants are: the Government Departments and the Experts involved (the Department of Nuclear Safety of the 'Institut de Protection et de Surete Nucleaire' forming the first technical support) and the applicant, namely the EDF. The reactor safety actions of the project coordinator are defined as from the following components: 1 - The targets laid down with respect to safety, the final objective being the protection of workers and the public against the potential dangers of the installations, principally against radiation. 2 - The safety methodology at the design stage of the power station: 'barrier' method, defence method in depth at three levels, lines of assurance method, and probabilistic method. 3 - Safety actions at the construction stage within the context of an assurance of quality programe. 4 - Safety at the trials, commissioning and operating stage, with the backing of the 'Groupe Operationnel de Demarrage (G.O.D.)' and the 'Commission d'Essais sur Site (C.E.S.)'. An initial balance sheet of the reactor safety actions for the PWR units built by the EDF is presented [fr

User's operating procedures. Volume 3: Projects directorate information programs

Science.gov (United States)

Haris, C. G.; Harris, D. K.

1985-01-01

A review of the user's operating procedures for the scout project automatic data system, called SPADS is presented. SPADS is the results of the past seven years of software development on a prime mini-computer. SPADS was developed as a single entry, multiple cross-reference data management and information retrieval system for the automation of Project office tasks, including engineering, financial, managerial, and clerical support. This volume, three of three, provides the instructions to operate the projects directorate information programs in data retrieval and file maintenance via the user friendly menu drivers.

Annual report on reactor safety research projects. Reporting period 2011. Progress report

International Nuclear Information System (INIS)

2011-01-01

Within its competence for energy research the Federal Ministry of Economics and Technology (BMWi) sponsors research projects on the safety of nuclear power plants currently in operation. The objective of these projects 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 of the BMWi, continuously issues information on the status of such research projects by publishing semi-annual and annual progress reports within the series of GRSF- Fortschrittsberichte (GRS-F-Progress Reports). Each progress report represents a compilation of individual reports about the objectives, work performed, results achieved, next steps of the work etc. The individual reports are prepared in a standard form by the research organisations themselves as documentation of their progress in work. The progress reports are published by the Project Management Agency/Authority Support Division of GRS. The reports as of the year 2000 are available in the Internet-based information system on results and data of reactor safety research (http://www.grs-fbw.de). The compilation of the reports is classified according to the classification system ''Joint Safety Research Index (JSRI)''. The reports are arranged in sequence of their project numbers. It has to be pointed out that the authors of the reports are responsible for the contents of this compilation. The BMWi does not take any responsibility for the correctness, exactness and completeness of the information nor for the observance of private claims of third parties. (orig.)

Annual report on reactor safety research projects. Reporting period 2014. Progress report

Energy Technology Data Exchange (ETDEWEB)

NONE

2014-07-01

Within its competence for energy research the Federal Ministry for Economic Affairs and Energy (BMWi) sponsors research projects on the safety of nuclear power plants currently in operation. The objective of these projects 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) gGmbH, by order of the BMWi, continuously issues information on the status of such research projects 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 steps of the work etc. The individual reports are prepared in a standard form by the research organisations themselves as documentation of their progress in work. The progress reports are published by the Project Management Agency/Authority Support Division of GRS. The reports as of the year 2000 are available in the lnternet-based information system on results and data of reactor safety research (http://www.grs-fbw.de). The compilation of the reports is classified according to the classification system ''Joint Safety Research Index (JSRI)''. The reports are arranged in sequence of their project numbers. lt has to be pointed out that the authors of the reports are responsible for the contents of this compilation. The BMWi does not take any responsibility for the correctness, exactness and completeness of the information nor for the observance of private claims of third parties.

Annual report on reactor safety research projects. Reporting period 2013. Progress report

International Nuclear Information System (INIS)

2013-01-01

Within its competence for energy research the Federal Ministry of Economics and Technology (BMWi) sponsors research projects on the safety of nuclear power plants currently in operation. The objective of these projects 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 of the BMWi, continuously issues information on the status of such research projects by publishing semi-annual and annual progress reports within the series of GRSF- Fortschrittsberichte (GRS-F-Progress Reports). Each progress report represents a compilation of individual reports about the objectives, work performed, results achieved, next steps of the work etc. The individual reports are prepared in a standard form by the research organisations themselves as documentation of their progress in work. The progress reports are published by the Project Management Agency/Authority Support Division of GRS. The reports as of the year 2000 are available in the Internet-based information system on results and data of reactor safety research (http://www.grs-fbw.de). The compilation of the reports is classified according to the classification system ''Joint Safety Research Index (JSRI)''. The reports are arranged in sequence of their project numbers. It has to be pointed out that the authors of the reports are responsible for the contents of this compilation. The BMWi does not take any responsibility for the correctness, exactness and completeness of the information nor for the observance of private claims of third parties. (orig.)

Annual report on reactor safety research projects. Reporting period 2015. Progress report

International Nuclear Information System (INIS)

2015-01-01

Within its competence for energy research the Federal Ministry for Economic Affairs and Energy (BMWi) sponsors research projects on the safety of nuclear power plants currently in operation. The objective of these projects 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 tor Anlagen- und Reaktorsicherheit (GRS) gGmbH, by order of the BMWi, continuously issues information on the status of such research projects 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 steps of the work etc. The individual reports are ·' prepared in a standard form by the research organisations themselves as documentation of their progress in work. The progress reports are published by the Project Management Agency/Authority Support Division of GRS. The reports as of the year 2000 are available in the lnternet-based information system on results and data of reactor safety research (http://www.grs-fbw.de). The compilation of the reports is classified according to the classification system ''Joint Safety Research Index (JSRI)''. The reports are arranged in sequence of their project numbers. it has to be pointed out that the authors of the reports are responsible for the contents of this compilation. The BMWi does not take any responsibility for the correctness, exactness and completeness of the information nor for the observance of private claims of third parties.

UMTRA Project: Environment, Safety, and Health Plan

International Nuclear Information System (INIS)

1995-02-01

The US Department of Energy has prepared this UMTRA Project Environment, Safety, and Health (ES and H) Plan to establish the policy, implementing requirements, and guidance for the UMTRA Project. The requirements and guidance identified in this plan are designed to provide technical direction to UMTRA Project contractors to assist in the development and implementation of their ES and H plans and programs for UMTRA Project work activities. Specific requirements set forth in this UMTRA Project ES and H Plan are intended to provide uniformity to the UMTRA Project's ES and H programs for processing sites, disposal sites, and vicinity properties. In all cases, this UMTRA Project ES and H Plan is intended to be consistent with applicable standards and regulations and to provide guidance that is generic in nature and will allow for contractors' evaluation of site or contract-specific ES and H conditions. This plan specifies the basic ES and H requirements applicable to UMTRA Project ES and H programs and delineates responsibilities for carrying out this plan. DOE and contractor ES and H personnel are expected to exercise professional judgment and apply a graded approach when interpreting these guidelines, based on the risk of operations

Spent Nuclear Fuel (SNF) Project Safety Basis Implementation Strategy

International Nuclear Information System (INIS)

TRAWINSKI, B.J.

2000-01-01

The objective of the Safety Basis Implementation is to ensure that implementation of activities is accomplished in order to support readiness to move spent fuel from K West Basin. Activities may be performed directly by the Safety Basis Implementation Team or they may be performed by other organizations and tracked by the Team. This strategy will focus on five key elements, (1) Administration of Safety Basis Implementation (general items), (2) Implementing documents, (3) Implementing equipment (including verification of operability), (4) Training, (5) SNF Project Technical Requirements (STRS) database system

The use of living PSA in safety management, a procedure developed in the nordic project ''safety evaluation, NKS/SIK-1''

International Nuclear Information System (INIS)

Johanson, G.; Holmberg, J.

1994-01-01

The essential objective with the development of a living PSA concept is to bring the use of the plant specific PSA model out to the daily safety work to allow operational risk experience feedback and to increase the risk awareness of the intended users. This paper will present results of the Nordic project ''Safety Evaluation, NKS/SIK-1''. The SIK-1 project has defined and demonstrated the practical use of living PSA for safety evaluation and for identification of possible improvements in operational safety. Subjects discussed in this paper are dealing with the practical implementation and use of PSA to make proper safety related decisions and evaluation. (author). 24 refs, 1 fig., 1 tab

Dissemination material template, Deliverable 2.2 of the H2020 project SafetyCube (Safety CaUsation, Benefits and Efficiency).

NARCIS (Netherlands)

Tros, M. & Houtenbos, M.

2016-01-01

Safety CaUsation, Benefits and Efficiency (SafetyCube) is a European Commission supported Horizon 2020 project with the objective of developing an innovative road safety Decision Support System (DSS) that will enable policy-makers and stakeholders to select and implement the most appropriate

Project W-030 safety class upgrade summary report

International Nuclear Information System (INIS)

Kriskovich, J.R.

1998-01-01

This document presents a summary of safety class criteria for the 241-AY/AZ Tank Farm primary ventilation system upgrade under Project W-030, and recommends acceptance of the system as constructed, based on a review of supporting documentation

The spin project: safety and performance indicators in different time frames

International Nuclear Information System (INIS)

Storck, R.; Becker, D.A.

2002-01-01

Safety and performance indicators have been under discussion for many years in several countries and international organisations. If those indicators refer to the long term safety of the total disposal system, they are often called safety indicators. If they refer to the performance of subsystems or the total system from a more technical point of view, they are sometimes called performance indicators. The need for indicators other than dose rates derives e.g. from the long time frames involved in safety assessments of waste disposal systems and the increasing uncertainty in dose rate calculations over time due to uncertainty in evolution of the surface environment and of behaviour of man. Before introducing additional indicators into a safety case of a potential repository site, the applicability and usefulness of different indicators have to be investigated and evaluated. The systematic analysis and testing of safety and performance indicators for use in different time horizons after closure of the disposal facility is the task of the SPIN project. This is done by re-calculating four recent studies concerning repository projects in granite formations. (authors)

Assessment and management of ageing of major nuclear power plant components important to safety: In-containment instrumentation and control cables. Volume I

International Nuclear Information System (INIS)

2000-12-01

and technical support organizations dealing with specific plant components addressed in the reports. The component addressed in the present report is the in-containment instrumentation and control (I and C) cables. The report presents, in two volumes, results of a Co-ordinated Research Project (CRP) on the Management of Ageing of In-containment Instrumentation and Control cables. Part I, Volume 1 presents information on current methods for assessing and managing ageing degradation of Instrumentation and Control cables in real NPP environments prepared by the CRP team. An important complement of this information is user perspectives on the application of these methods which are presented in Part II, Volume 1. Volume 2 contains annexes supporting the guidance of Volume 1 with more detailed information and examples provided by individual CRP participants. For a quick overview, readers should see Section 8 of Part I, Volume 1, which describes a systematic ageing management programme for Instrumentation and Control cables utilizing methods presented in the report; Section 9 of Part I, Volume 1, which presents CRP conclusions and recommendations; and Part II providing the application guidance from the user's perspective

Assessment and management of ageing of major nuclear power plant components important to safety: In-containment instrumentation and control cables. Volume II

International Nuclear Information System (INIS)

2000-12-01

and technical support organizations dealing with specific plant components addressed in the reports. The component addressed in the present report is the in-containment instrumentation and control (I and C) cables. The report presents, in two volumes, results of a Co-ordinated Research Project (CRP) on the Management of Ageing of In-containment Instrumentation and Control cables. Part I, Volume 1 presents information on current methods for assessing and managing ageing degradation of Instrumentation and Control cables in real NPP environments prepared by the CRP team. An important complement of this information is user perspectives on the application of these methods which are presented in Part II, Volume 1. Volume 2 contains annexes supporting the guidance of Volume 1 with more detailed information and examples provided by individual CRP participants. For a quick overview, readers should see Section 8 of Part I, Volume 1, which describes a systematic ageing management programme for Instrumentation and Control cables utilizing methods presented in the report; Section 9 of Part I, Volume 1, which presents CRP conclusions and recommendations; and Part II providing the application guidance from the user's perspective

Proceedings of the nuclear criticality technology safety project

Energy Technology Data Exchange (ETDEWEB)

Sanchez, R.G. [comp.

1997-06-01

This document contains summaries of the most of the papers presented at the 1994 Nuclear Criticality Technology Safety Project (NCTSP) meeting, which was held May 10 and 11 at Williamsburg, Va. The meeting was broken up into seven sessions, which covered the following topics: (1) Validation and Application of Calculations; (2) Relevant Experiments for Criticality Safety; (3) Experimental Facilities and Capabilities; (4) Rad-Waste and Weapons Disassembly; (5) Criticality Safety Software and Development; (6) Criticality Safety Studies at Universities; and (7) Training. The minutes and list of participants of the Critical Experiment Needs Identification Workgroup meeting, which was held on May 9 at the same venue, has been included as an appendix. A second appendix contains the names and addresses of all NCTSP meeting participants. Separate abstracts have been indexed to the database for contributions to this proceedings.

Proceedings of the nuclear criticality technology safety project

International Nuclear Information System (INIS)

Sanchez, R.G.

1997-06-01

This document contains summaries of the most of the papers presented at the 1994 Nuclear Criticality Technology Safety Project (NCTSP) meeting, which was held May 10 and 11 at Williamsburg, Va. The meeting was broken up into seven sessions, which covered the following topics: (1) Validation and Application of Calculations; (2) Relevant Experiments for Criticality Safety; (3) Experimental Facilities and Capabilities; (4) Rad-Waste and Weapons Disassembly; (5) Criticality Safety Software and Development; (6) Criticality Safety Studies at Universities; and (7) Training. The minutes and list of participants of the Critical Experiment Needs Identification Workgroup meeting, which was held on May 9 at the same venue, has been included as an appendix. A second appendix contains the names and addresses of all NCTSP meeting participants. Separate abstracts have been indexed to the database for contributions to this proceedings

Fast reactor safety: proceedings of the international topical meeting. Volume 2. [R

Energy Technology Data Exchange (ETDEWEB)

1985-07-01

The emphasis of this meeting was on the safety-related aspects of fast reactor design, analysis, licensing, construction, and operation. Relative to past meetings, there was less emphasis on the scientific and technological basis for accident assessment. Because of its broad scope, the meeting attracted 217 attendees from a wide cross section of the design, safety analysis, and safety technology communities. Eight countries and two international organizations were represented. A total of 126 papers were presented, with contributions from the United States, France, Japan, the United Kingdom, Germany, and Italy. Sessions covered in Volume 2 include: safety design concepts; operational transient experiments; analysis of seismic and external events; HCDA-related codes, analysis, and experiments; sodium fires; instrumentation and control/PPS design; whole-core accident analysis codes; and impact of safety design considerations on future LMFBR developments.

The modification of main steam safety valves in Qinshan phase Ⅱ expansion project

International Nuclear Information System (INIS)

Chen Haiqiao

2012-01-01

The main steam safety valves of NPP steam system are second- class nuclear safety component. It used to limit the pressure of SG secondary side and main steam system via emitting steam into the environment. At present, the main steam safety valves have mechanical valves and assisted power valves. According to the experience of power plants at home and abroad, including Qinshan Phase Ⅱ unit 1/2 experience feedback, Qinshan Phase Ⅱ expansion project made modification on valve type, setting value and valve body. This paper introduce the characteristics of different safety valve types, the modification of main steam safety valves and the modification analysis on safety issues.security and impact on the other systems in Qinshan Phase Ⅱ expansion project. (author)

Project Guarantee 1985. Final repository for high-level radioactive wastes: The system of safety barriers

International Nuclear Information System (INIS)

Anon.

1985-01-01

Final disposal of radioactive waste involves preventing the waste from returning from the repository location into the biosphere by means of successively arranged containment measures known as safety barriers. In the present volume NGB 85-04 of the series of reports for Project 'Guarantee' 1985, the safety barrier system for the type C repository for high-level waste is described. The barrier parameters which are relevant for safety analysis are quantified and associated error limits and data scatter are given. The aim of the report is to give a summary documentation of the safety analysis input data and their scientific background. For secure containment of radioactive waste safety barriers are used which effectively limit the release of radioactive material from the repository (release barriers) and effectively retard the entry of the original radioactive material into the biosphere (time barriers). Safety barriers take the form of both technically constructed containment measures and the siting of the repository in suitable geological formations. The technical safety barrier system in the case of high-level waste comprises: the waste solidification matrix (borosilicate glass), massive steel canisters, encasement of the waste canisters, encasement of the waste canisters in highly compacted bentonite, sealing of vacant storage space and access routes on repository closure. The natural geological safety barriers - the host rock and overlying formations provide sufficiently long deep groundwater flow times from the repository location to the earth's surface and for additional lengthening of radionuclide migration times by means of various chemical and physical retardation mechanisms. The stability of the geological formations is so great that hydrogeological system is protected for a sufficient length of time from deterioration caused, in particular, by erosion. Observations in the final section of the report indicate that input data for the type C repository safety

KfK Nuclear Safety Project. First semiannual report 1985

International Nuclear Information System (INIS)

1985-11-01

The semiannual progress report 1985/1 is a description of work within the Nuclear Safety Project performed in the first six month of 1985 in the nuclear safety field by KfK institutes and departements and by external institutions on behalf of KfK. The chosen kind of this report is that of short summaries, containing the topics: work performed, results obtained and plans for future work. (orig./HP) [de

Chemical Safety Vulnerability Working Group report. Volume 1

Energy Technology Data Exchange (ETDEWEB)

1994-09-01

The Chemical Safety Vulnerability (CSV) Working Group was established to identify adverse conditions involving hazardous chemicals at DOE facilities that might result in fires or explosions, release of hazardous chemicals to the environment, or exposure of workers or the public to chemicals. A CSV Review was conducted in 148 facilities at 29 sites. Eight generic vulnerabilities were documented related to: abandoned chemicals and chemical residuals; past chemical spills and ground releases; characterization of legacy chemicals and wastes; disposition of legacy chemicals; storage facilities and conditions; condition of facilities and support systems; unanalyzed and unaddressed hazards; and inventory control and tracking. Weaknesses in five programmatic areas were also identified related to: management commitment and planning; chemical safety management programs; aging facilities that continue to operate; nonoperating facilities awaiting deactivation; and resource allocations. Volume 1 contains the Executive summary; Introduction; Summary of vulnerabilities; Management systems weaknesses; Commendable practices; Summary of management response plan; Conclusions; and a Glossary of chemical terms.

Chemical Safety Vulnerability Working Group report. Volume 1

International Nuclear Information System (INIS)

1994-09-01

The Chemical Safety Vulnerability (CSV) Working Group was established to identify adverse conditions involving hazardous chemicals at DOE facilities that might result in fires or explosions, release of hazardous chemicals to the environment, or exposure of workers or the public to chemicals. A CSV Review was conducted in 148 facilities at 29 sites. Eight generic vulnerabilities were documented related to: abandoned chemicals and chemical residuals; past chemical spills and ground releases; characterization of legacy chemicals and wastes; disposition of legacy chemicals; storage facilities and conditions; condition of facilities and support systems; unanalyzed and unaddressed hazards; and inventory control and tracking. Weaknesses in five programmatic areas were also identified related to: management commitment and planning; chemical safety management programs; aging facilities that continue to operate; nonoperating facilities awaiting deactivation; and resource allocations. Volume 1 contains the Executive summary; Introduction; Summary of vulnerabilities; Management systems weaknesses; Commendable practices; Summary of management response plan; Conclusions; and a Glossary of chemical terms

Incorporation of occupational health and safety in cleaner production projects in South Africa

DEFF Research Database (Denmark)

Hedlund, Frank Huess

2002-01-01

The purpose of this research is to reveal ways in which occupational health and safety can be integrated in environmental cleaner production projects. Of particular interest are those cleaner production projects that are run by the Danish government's environmental assistance agency, Danced......, in South Africa.The study explores two main avenues of integration. First, integrating through better planning, focussing at the tools and procedures in use by Danced for project management -- integrating occupational health and safety into the project specification, so to speak.Second, integrating...... occupational health and safety into the environmental activities that take place at company level. Two ways of doing so are explored, the main distinction being company size. For large companies, integration of management systems may be attractive. For small companies, integration into a less formal network...

Inventory of Federal energy-related environment and safety research for FY 1977. Volume IV. Indices

Energy Technology Data Exchange (ETDEWEB)

1978-07-01

This volume contains indexes useful for accessing projects contained in the FY 1977 Federal Inventory. The indexing has been greatly broadened this year to provide hard copy users with greater flexibility in locating projects. The Inventory projects are printed sequentially by log number. An inventory log number is a unique number assigned to each project from a block of numbers set aside for each agency. The association of agencies with blocks of log numbers is found in the table of contents of the Index (Volume III).

Ice volume distribution and implications on runoff projections in a glacierized catchment

Directory of Open Access Journals (Sweden)

J. Gabbi

2012-12-01

Full Text Available A dense network of helicopter-based ground-penetrating radar (GPR measurements was used to determine the ice-thickness distribution in the Mauvoisin region. The comprehensive set of ice-thickness measurements was combined with an ice-thickness estimation approach for an accurate determination of the bedrock. A total ice volume of 3.69 ± 0.31 km³ and a maximum ice thickness of 290 m were found. The ice-thickness values were then employed as input for a combined glacio-hydrological model forced by most recent regional climate scenarios. This model provided glacier evolution and runoff projections for the period 2010–2100. Runoff projections of the measured initial ice volume distribution show an increase in annual runoff of 4% in the next two decades, followed by a persistent runoff decrease until 2100. Finally, we checked the influence of the ice-thickness distribution on runoff projections. Our analyses revealed that reliable estimates of the ice volume are essential for modelling future glacier and runoff evolution. Wrong estimations of the total ice volume might even lead to deviations of the predicted general runoff trend.

JRC/IE support activities to PHARE nuclear safety programmes. Dissemination of PHARE project results

International Nuclear Information System (INIS)

Ranguelova, V.; Pla, P.; Rieg, C.; Bieth, M.

2005-01-01

Nuclear safety in Europe is one of European Union's primary concerns, therefore the European Union decided to take a prominent role to help the New Independent States and countries of Central and Eastern Europe to ensure the safety of their nuclear reactors. The European Union TACIS and PHARE programmes in nuclear safety have been undertaken since 1990. The European Commission's Directorate General External Relations (EC DG RELEX) and, Directorate General Europe Aid Co-operation Office (EC DG AIDCO), are responsible for programming and management of implementation of TACIS projects. Directorate General Enlargement (EC DG ELARG) is responsible for programming PHARE programmes, but implementation of most projects has been decentralised since 1999 budget year to the Beneficiary countries. DG ELARG acts as backstopping for the relevant EC Delegations. In these activities, the TSSTP Unit at the JRC/IE in Petten, The Netherlands, is a technical and scientific adviser of DG RELEX and DG AIDCO and provides support to DG ELARG for very specific technical issues. Several PHARE projects aiming at improving nuclear safety have been successfully implemented for a number of plants from Central and Eastern Europe. In some cases major safety issues have been addressed by means of multi-country projects and results have been disseminated to the rest of the nuclear community. Although a lot of information has been exchanged at a bilateral level, further effort is needed to collect the project results in a systematic way and make them available by means of the internet. At present the TSSTP Unit is implementing two projects for dissemination of PHARE project results. This activity will take a better advantage of today's communication technologies and ensure the management of the acquired knowledge through preservation and user-friendly access and retrieval of the project results. The paper provides an outline of the TSSTP Unit relevant knowledge preservation initiative, a description

Status of safety issues at licensed power plants

International Nuclear Information System (INIS)

1991-06-01

As part of ongoing US Nuclear Regulatory Commission (NRC) efforts to ensure the quality and accountability of safety issue information, a program has been established whereby an annual NUREG report will be published on the status of licensee implementation and NRC verification of safety issues in major NRC requirement areas. This report, the third volume of a three-volume series, addresses the status of generic safety issues (GSIs) at licensed plants. Volume 1 addressed the status of Three Mile Island Action Plan requirements and was published in March 1991. Volume 2 addressed the status of implementation and verification of unresolved safety issues and was published in May 1991. The annual NUREG report will combine these three areas in a single volume to be published in late 1991. The data contained in these NUREG reports are a product of the NRC's Safety Issues Management System (SIMS) database, which is maintained by the Project Management Staff in the Office of Nuclear Reactor Regulation and by NRC regional personnel. The purpose of this report is to provide a comprehensive description of the status of implementation and verification of the 34 GSIs and sub-issues that have been resolved by the NRC and involve implementation of an action or actions by licensees. This NUREG report also serves as a follow-on to NUREG-0933, ''A Prioritization of Generic Safety Issues,'' which tracks safety issues up until a request for action by licensees is issued by NRC. 3 figs., 6 tabs

MODELS AND METHODS OF SAFETY-ORIENTED PROJECT MANAGEMENT OF DEVELOPMENT OF COMPLEX SYSTEMS: METHODOLOGICAL APPROACH

Directory of Open Access Journals (Sweden)

Олег Богданович ЗАЧКО

2016-03-01

Full Text Available The methods and models of safety-oriented project management of the development of complex systems are proposed resulting from the convergence of existing approaches in project management in contrast to the mechanism of value-oriented management. A cognitive model of safety oriented project management of the development of complex systems is developed, which provides a synergistic effect that is to move the system from the original (pre condition in an optimal one from the viewpoint of life safety - post-project state. The approach of assessment the project complexity is proposed, which consists in taking into account the seasonal component of a time characteristic of life cycles of complex organizational and technical systems with occupancy. This enabled to take into account the seasonal component in simulation models of life cycle of the product operation in complex organizational and technical system, modeling the critical points of operation of systems with occupancy, which forms a new methodology for safety-oriented management of projects, programs and portfolios of projects with the formalization of the elements of complexity.

Finnish research programmes on nuclear power plant safety

International Nuclear Information System (INIS)

Puska, E. K.

2010-01-01

The current Finnish national research programme on nuclear power plant safety SAFIR2010 for the years 2007-2010 as well as the coming SAFIR2014 programme for the years 2011-2014 are based on the chapter 7a, 'Ensuring expertise', of the Finnish Nuclear Energy Act. The objective of this chapter is realised in the research work and education of experts in the projects of these research programmes. SAFIR2010 research programme is divided in eight research areas that are Organisation and human, Automation and control room, Fuel and reactor physics, Thermal hydraulics, Severe accidents, Structural safety of reactor circuit, Construction safety, and Probabilistic Safety Analysis (PSA). All the research areas include both projects in their own area and interdisciplinary co-operational projects. Research projects of the programme are chosen on the basis of annual call for proposals. In 2010 research is carried out in 33 projects in SAFIR2010. VTT is the responsible research organisation in 26 of these projects and VTT is also the coordination unit of SAFIR2010 and SAFIR2014. In 2007-2009 SAFIR2010 produced 497 Specified research results (Deliverables), 618 Publications, and 33 Academic degrees. SAFIR2010 programme covers approximately half of the reactor safety research volume in Finland currently. In 2010 the programme volume is EUR 7.1 million and 47 person years. The major funding partners are VYR with EUR 2.96 million, VTT with EUR 2.66 million, Fortum with EUR 0.28 million, TVO with EUR 0.19 million, NKS with EUR 0.15 million, EU with only EUR 0.03 million and other partners with EUR 0.85 million. The new decisions-in-principle on Olkiluoto unit 4 for Teollisuuden Voima and new nuclear power plant for Fennovoima ratified by the Finnish Parliament on 1 July 2010 increase the annual funding collected according to the Finnish Nuclear Energy Act from Fennovoima, Fortum and Teollisuuden Voima for the SAFIR2014 programme to EUR 5.2 million from the current level of EUR 3

Implementing an interprofessional patient safety learning initiative: insights from participants, project leads and steering committee members.

Science.gov (United States)

Jeffs, Lianne; Abramovich, Ilona Alex; Hayes, Chris; Smith, Orla; Tregunno, Deborah; Chan, Wai-Hin; Reeves, Scott

2013-11-01

Effective teamwork and interprofessional collaboration are vital for healthcare quality and safety; however, challenges persist in creating interprofessional teamwork and resilient professional teams. A study was undertaken to delineate perceptions of individuals involved with the implementation of an interprofessional patient safety competency-based intervention and intervention participants. The study employed a qualitative study design that triangulated data from interviews with six steering committee members and five members of the project team who developed and monitored the intervention and six focus groups with clinical team members who participated in the intervention and implemented local patient safety projects within a large teaching hospital in Canada. Our study findings reveal that healthcare professionals and support staff acquired patient safety competencies in an interprofessional context that can result in improved patient and work flow processes. However, key challenges exist including managing projects amidst competing priorities, lacking physician engagement and sustaining projects. Our findings point to leaders to provide opportunities for healthcare teams to engage in interprofessional teamwork and patient safety projects to improve quality of patient care. Further research efforts should examine the sustainability of interprofessional safety projects and how leaders can more fully engage the participation of all professions, specifically physicians.

How to communicate safety? Some reflections from European project studies

International Nuclear Information System (INIS)

Richardson, Philip; Galson, Daniel

2009-12-01

Attempts to site geological disposal facilities for radioactive waste - and associated public reactions - indicate that communicating safety and demonstrating safety are very different things. The three different approaches to stakeholder engagement undertaken in the context of the PAMINA, ARGONA and CIP projects have provided valuable insights into how risk communication processes and tools can be improved. The approaches used in these projects all involve the participation of interested stakeholders in identifying concerns and issues, which are then examined in a co-operative fashion between stakeholders and developers acting in partnership. Such approaches offer avenues for dialogue and confidence building where such channels were previously not well developed, Full results from the projects will be available in late 2009 for PAMINA and ARGONA and in early 2010 for CIP. The comments and interim insights outlined here will be developed further and incorporated in the overall project outputs, and help inform developing European policy in this area. It is already clear, however, that the approaches used in these projects offer great promise in helping to develop the trust in the institutions and organisations involved that is essential in gaining support and acceptance for the waste management activities now underway across Europe

Safety Design Strategy for the Advanced Test Reactor Diesel Bus (E-3) and Switchgear Replacement Project

International Nuclear Information System (INIS)

Duckwitz, Noel

2011-01-01

In accordance with the requirements of U.S. Department of Energy (DOE) Order 413.3B, 'Program and Project Management for the Acquisition of Capital Assets,' safety must be integrated into the design process for new or major modifications to DOE Hazard Category 1, 2, and 3 nuclear facilities. The intended purpose of this requirement involves the handling of hazardous materials, both radiological and chemical, in a way that provides adequate protection to the public, workers, and the environment. Requirements provided in DOE Order 413.3B and DOE Order 420.1B, 'Facility Safety,' and the expectations of DOE-STD-1189-2008, 'Integration of Safety into the Design Process,' provide for identification of hazards early in the project and use of an integrated team approach to design safety into the facility. This safety design strategy provides the basic safety-in-design principles and concepts that will be used for the Advanced Test Reactor Reliability Sustainment Project. While this project does not introduce new hazards to the ATR, it has the potential for significant impacts to safety-related systems, structures, and components that are credited in the ATR safety basis and are being replaced. Thus the project has been determined to meet the definition of a major modification and is being managed accordingly.

Ferrocyanide safety project ferrocyanide aging studies. Final report

International Nuclear Information System (INIS)

Lilga, M.A.; Hallen, R.T.; Alderson, E.V.

1996-06-01

This final report gives the results of the work conducted by Pacific Northwest National Laboratory (PNNL) from FY 1992 to FY 1996 on the Ferrocyanide Aging Studies, part of the Ferrocyanide Safety Project. The Ferrocyanide Safety Project was initiated as a result of concern raised about the safe storage of ferrocyanide waste intermixed with oxidants, such as nitrate and nitrite salts, in Hanford Site single-shell tanks (SSTs). In the laboratory, such mixtures can be made to undergo uncontrolled or explosive reactions by heating dry reagents to over 200 degrees C. In 1987, an Environmental Impact Statement (EIS), published by the U.S. Department of Energy (DOE), Final Environmental Impact Statement, Disposal of Hanford Defense High-Level Transuranic and Tank Waste, Hanford Site, Richland, Washington, included an environmental impact analysis of potential explosions involving ferrocyanide-nitrate mixtures. The EIS postulated that an explosion could occur during mechanical retrieval of saltcake or sludge from a ferrocyanide waste tank, and concluded that this worst-case accident could create enough energy to release radioactive material to the atmosphere through ventilation openings, exposing persons offsite to a short-term radiation dose of approximately 200 mrem. Later, in a separate study (1990), the General Accounting Office postulated a worst-case accident of one to two orders of magnitude greater than that postulated in the DOE EIS. The uncertainties regarding the safety envelope of the Hanford Site ferrocyanide waste tanks led to the declaration of the Ferrocyanide Unreviewed Safety Question (USQ) in October 1990

Preliminary safety evaluation for 241-C-106 waste retrieval, project W-320

International Nuclear Information System (INIS)

Conner, J.C.

1994-01-01

This document presents the Preliminary Safety Evaluation for Project W-320, Tank 241-C-106 Waste Retrieval Sluicing System (WRSS). The US DOE has been mandated to develop plans for response to safety issues associated with the waste storage tanks at the Hanford Site, and to report the progress of implementing those plans to Congress. The objectives of Project W-230 are to design, fabricate, develop, test, and operate a new retrieval system capable of removing a minimum of about 75% of the high-heat waste contained in C-106. It is anticipated that sluicing operations can remove enough waste to reduce the remaining radiogenic heat load to levels low enough to resolve the high-heat safety issue as well as allow closure of the tank safety issue

Project Guarantee 1985. Final repository for low- and intermediate level radioactive wastes: Safety report

International Nuclear Information System (INIS)

Anon.

1985-01-01

Storage of radioactive waste must delay the return of radionuclides to the biosphere for a long period of time and must maintain the release rates at a sufficiently low level for all time. This is achieved with the aid of a series of safety barriers which consist, on the one hand, of technical barriers in the repository and, on the other hand , of natural geological barriers as they occur at the repository location. In order to assess the efficiency of the barriers, the working methods of the technical barriers and the host rock must be understood. This understanding is transferred into quantitative models in order to calculate the safety of the repository. The individual barriers and the methods used to modelling their functions were described in volume NGB 85-07 of the Project Guarantee 1985 report series and the data necessary for modelling were given. The models and data are used in the safety analysis, the results of which are contained in the present report. Safety considerations show that models are available in Switzerland which allow, in principle, an assessment of the long-term behaviour of a repository for low- and intermediate-level waste. The evaluation of earlier studies and experimental work, suitable laboratory measurements and results from field research enable compilation of a representative data-set so that the requirements for quantitative statements on safety of final disposal are met from this side also. The safety calculations show that the radiation doses calculated for a base case scenario with realistic/conservative parameter values are negligibly low. Also, radiation doses which are clearly under the protection standard of 10 mrem per year result for conservative values and the cumulation of several conservative assumptions. Even assuming exposure of the repository by erosion, a radiotoxicity of the soil formed results which is under natural values

Overview of the NKS/RAK-1 project 'Strategies for reactor safety' and linkages to piping reliability studies

International Nuclear Information System (INIS)

Andersson, Kjell

1997-01-01

The NKS/RAK-1 project forms part of a four-year research program (1994-97) in the Nordic countries. The general objective of NKS/RAK-1 project is to explore strategies for reactor safety: to investigate and evaluate the safety work, to increase realism and reliability of safety analysis; and to increase the safety of nuclear installations in selected areas. The project has done extensive interview work at utilities and authorities, and analysed a number of case studies. Brief highlights and overviews of the sub-projects are presented in this paper

Legacy sample disposition project. Volume 2: Final report

International Nuclear Information System (INIS)

Gurley, R.N.; Shifty, K.L.

1998-02-01

This report describes the legacy sample disposition project at the Idaho Engineering and Environmental Laboratory (INEEL), which assessed Site-wide facilities/areas to locate legacy samples and owner organizations and then characterized and dispositioned these samples. This project resulted from an Idaho Department of Environmental Quality inspection of selected areas of the INEEL in January 1996, which identified some samples at the Test Reactor Area and Idaho Chemical Processing Plant that had not been characterized and dispositioned according to Resource Conservation and Recovery Act (RCRA) requirements. The objective of the project was to manage legacy samples in accordance with all applicable environmental and safety requirements. A systems engineering approach was used throughout the project, which included collecting the legacy sample information and developing a system for amending and retrieving the information. All legacy samples were dispositioned by the end of 1997. Closure of the legacy sample issue was achieved through these actions

User's operating procedures. Volume 2: Scout project financial analysis program

Science.gov (United States)

Harris, C. G.; Haris, D. K.

1985-01-01

A review is presented of the user's operating procedures for the Scout Project Automatic Data system, called SPADS. SPADS is the result of the past seven years of software development on a Prime mini-computer located at the Scout Project Office, NASA Langley Research Center, Hampton, Virginia. SPADS was developed as a single entry, multiple cross-reference data management and information retrieval system for the automation of Project office tasks, including engineering, financial, managerial, and clerical support. This volume, two (2) of three (3), provides the instructions to operate the Scout Project Financial Analysis program in data retrieval and file maintenance via the user friendly menu drivers.

No 2943. Project of law relative to nuclear transparency and safety

International Nuclear Information System (INIS)

2006-03-01

This project of law comprises 5 titles dealing with: 1 - general dispositions: definition and scope of nuclear safety, security, radiation protection, operators liability, facilities in concern; 2 - the high nuclear safety authority: role and duties; 3 - public information in the domain of nuclear safety and radiation protection: information right of the public, local information commissions, high committee for nuclear safety transparency and information; 4 - basic nuclear facilities and transport of radioactive materials: applicable rules, police controls and measures, penal dispositions (investigations, sanctions); 5 - miscellaneous dispositions: changes made with respect to previous legislative texts. (J.S.)

Environmental, health, and safety issues of sodium-sulfur batteries for electric and hybrid vehicles. Volume 4, In-vehicle safety

Energy Technology Data Exchange (ETDEWEB)

Mark, J.

1992-11-01

This report is the last of four volumes that identify and assess the environmental, health, and safety issues that may affect the commercial-scale use of sodium-sulfur (Na/S) battery technology as the energy source in electric and hybrid vehicles. The reports 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 the in-vehicle safety issues of electric vehicles powered by Na/S batteries. The report is based on a review of the literature and on discussions with experts at DOE, national laboratories and agencies, and private industry. It has three major goals: (1) to identify the unique hazards associated with electric vehicle (EV) use; (2) to describe the existing standards, regulations, and guidelines that are or could be applicable to these hazards; and (3) to discuss the adequacy of the existing requirements in addressing the safety concerns of EVs.

Safety Assessment Methodologies and Their Application in Development of Near Surface Waste Disposal Facilities--ASAM Project

International Nuclear Information System (INIS)

Batandjieva, B.; Metcalf, P.

2003-01-01

Safety of near surface disposal facilities is a primary focus and objective of stakeholders involved in radioactive waste management of low and intermediate level waste and safety assessment is an important tool contributing to the evaluation and demonstration of the overall safety of these facilities. It plays significant role in different stages of development of these facilities (site characterization, design, operation, closure) and especially for those facilities for which safety assessment has not been performed or safety has not been demonstrated yet and the future has not been decided. Safety assessments also create the basis for the safety arguments presented to nuclear regulators, public and other interested parties in respect of the safety of existing facilities, the measures to upgrade existing facilities and development of new facilities. The International Atomic Energy Agency (IAEA) has initiated a number of research coordinated projects in the field of development and improvement of approaches to safety assessment and methodologies for safety assessment of near surface disposal facilities, such as NSARS (Near Surface Radioactive Waste Disposal Safety Assessment Reliability Study) and ISAM (Improvement of Safety Assessment Methodologies for Near Surface Disposal Facilities) projects. These projects were very successful and showed that there is a need to promote the consistent application of the safety assessment methodologies and to explore approaches to regulatory review of safety assessments and safety cases in order to make safety related decisions. These objectives have been the basis of the IAEA follow up coordinated research project--ASAM (Application of Safety Assessment Methodologies for Near Surface Disposal Facilities), which will commence in November 2002 and continue for a period of three years

Safety in Academic Chemistry Laboratories: Volume 2. Accident Prevention for Faculty and Administrators, 7th Edition.

Science.gov (United States)

American Chemical Society, Washington, DC.

This book contains volume 2 of 2 and describes safety guidelines for academic chemistry laboratories to prevent accidents for college and university students. Contents include: (1) "Organizing for Accident Prevention"; (2) "Personal Protective Equipment"; (3) "Labeling"; (4) "Material Safety Data Sheets (MSDSs)"; (5) "Preparing for Medical…

Project SAFE. Update of the SFR-1 safety assessment. Phase 1

International Nuclear Information System (INIS)

Andersson, Johan; Riggare, P.; Skagius, K.

1998-10-01

SFR-1 is a facility for disposal of low-level radioactive operational waste from the nuclear power plants in Sweden. Low-level radioactive waste from industry, medicine, and research is also disposed in SFR-1. The facility is situated in bedrock beneath the Baltic Sea, 1 km off the coast near the Forsmark nuclear power plant. SFR-1 was built between the years 1983 and 1988. An assessment of the long-term performance of the facility was included in the vast documentation that was a part of the application for an operational license. The assessment was presented in the form of a final safety report. In the operational licence for SFR-1 it is stated that renewed safety assessments should be carried out at least each ten years. In order to meet this demand SKB has launched a special project, SAFE (Safety Assessment of Final Disposal of Operational Radioactive Waste). The aim of the project is to update the safety analysis and to prepare a safety report that will be presented to the Swedish authorities not later than year 2000. Project SAFE is divided into three phases. The first phase is a prestudy, and the results of the prestudy are given in this report. The aim of the prestudy is to identify issues where additional studies would improve the basis for the updated safety analysis as well as to suggest how these studies should be carried out. The work has been divided into six different topics, namely the inventory, the near field, the far field, the biosphere, radionuclide transport calculations and scenarios. For each topic the former safety reports and regulatory reviews are scrutinised and needs for additional work is identified. The evaluations are given in appendices covering the respective topics. The main report is a summary of the appendices with a more stringent description of the repository system and the processes that are of interest and therefore should be addressed in an updated safety assessment. However, it should be pointed out that one of the

Use of OECD/NEA Data Project Products in Probabilistic Safety Assessment

International Nuclear Information System (INIS)

Cherkas, G.; Raducu, Gheorghe; Riznic, J.; Yalaoui, S.; Huang, Hui-Wen; Holy, Jaroslav; Holmberg, Jan-Erik; Sandberg, Jorma; Balmain, Michel; Bonnevialle, Anne-Marie; Curnier, Florence; Georgescu, Gabriel; Lanore, Jeanne-Marie; Lindner, Arndt; Fujimoto, Haruo; Ahn, Kwang-Il; Hwang, Taesuk; Jang, Seung-Cheol; Husarcek, Jan; Kovacs, Zoltan; Vazquez, Teresa; Johanson, Gunnar; Liwaang, Bo; Nyman, Ralph; Dang, Vinh; Schoen, Gerhard; Brook, Kevin; Hamblen, David; Siu, Nathan; Sturzebecher, Karl; Tobin, Margaret; Wood, Jeff; Amri, Abdallah; Breest, Axel

2014-01-01

The Nuclear Energy Agency (NEA)/Committee for the Safety of Nuclear Installations' (CSNI) Working Group on Risk Assessment (WGRISK) is tasked with supporting the improved use of Probabilistic Safety Assessment (PSA) in risk informed regulation and safety management through the analysis of results and the development of perspectives regarding potentially important risk contributors and associated risk reduction strategies. The task consists of the following major activities: Development, distribution, and completion of survey questionnaires; Analysis of survey questionnaire results at a task workshop; Preparation of the final task report. The main objectives of this task, as proposed by WGRISK and approved by CSNI, are the following: - Identification and characterization of the current uses of OECD data project products and data in support of PSA. In this context, the term 'products' refers to data analysis results, technical reports, and other project outputs. - Identification and characterization of technical and programmatic characteristics that either support or impede use of data project products in PSA. This includes an assessment of which PSA parameters could be potentially estimated from the various data project products and gaps between available product information and PSA data needs. - Identification of recommendations for enhancing the usefulness of data project products and the coordination between WGRISK and the data projects. This task report consists of the following sections: - Chapter 1 Provides a general overview of motivation and approach used for this task. - Chapter 2 Describes scope and objectives of the task. - Chapter 3 Provides an overview of the ICDE, FIRE, OPDE/CODAP, and COMPSIS data projects. For each project, the project objectives, project history, data collection methodology and quality assurance, project status, example PSA Applications, and information related to project participation is provided. - Chapter 4 Describes the

Probabilistic safety analysis procedures guide, Sections 8-12. Volume 2, Rev. 1

International Nuclear Information System (INIS)

McCann, M.; Reed, J.; Ruger, C.; Shiu, K.; Teichmann, T.; Unione, A.; Youngblood, R.

1985-08-01

A procedures guide for the performance of probabilistic safety assessment has been prepared for interim use in the Nuclear Regulatory Commission programs. It will be revised as comments are received, and as experience is gained from its use. The probabilistic safety assessment studies performed are intended to produce probabilistic predictive models that can be used and extended by the utilities and by NRC to sharpen the focus of inquiries into a range of issues affecting reactor safety. The first volume of the guide describes the determination of the probability (per year) of core damage resulting from accident initiators internal to the plant (i.e., intrinsic to plant operation) and from loss of off-site electric power. The scope includes human reliability analysis, a determination of the importance of various core damage accident sequences, and an explicit treatment and display of uncertainties for key accident sequences. This second volume deals with the treatment of the so-called external events including seismic disturbances, fires, floods, etc. Ultimately, the guide will be augmented to include the plant-specific analysis of in-plant processes (i.e., containment performance). This guide provides the structure of a probabilistic safety study to be performed, and indicates what products of the study are valuable for regulatory decision making. For internal events, methodology is treated in the guide only to the extent necessary to indicate the range of methods which is acceptable; ample reference is given to alternative methodologies which may be utilized in the performance of the study. For external events, more explicit guidance is given

Hanford spent nuclear fuel project recommended path forward, volume III: Alternatives and path forward evaluation supporting documentation

International Nuclear Information System (INIS)

Fulton, J.C.

1994-10-01

Volume I of the Hanford Spent Nuclear Fuel Project - Recommended Path Forward constitutes an aggressive series of projects to construct and operate systems and facilities to safely retrieve, package, transport, process, and store K Basins fuel and sludge. Volume II provided a comparative evaluation of four Alternatives for the Path Forward and an evaluation for the Recommended Path Forward. Although Volume II contained extensive appendices, six supporting documents have been compiled in Volume III to provide additional background for Volume II

Legacy data sharing to improve drug safety assessment: the eTOX project

DEFF Research Database (Denmark)

Sanz, Ferran; Pognan, François; Steger-Hartmann, Thomas

2017-01-01

The sharing of legacy preclinical safety data among pharmaceutical companies and its integration with other information sources offers unprecedented opportunities to improve the early assessment of drug safety. Here, we discuss the experience of the eTOX project, which was established through...

The SISIFO project: Seismic Safety at High Schools

Science.gov (United States)

Peruzza, Laura; Barnaba, Carla; Bragato, Pier Luigi; Dusi, Alberto; Grimaz, Stefano; Malisan, Petra; Saraò, Angela; Mucciarelli, Marco

2014-05-01

For many years, the Italian scientific community has faced the problem of the reduction of earthquake risk using innovative educational techniques. Recent earthquakes in Italy and around the world have clearly demonstrated that seismic codes alone are not able to guarantee an effective mitigation of risk. After the tragic events of San Giuliano di Puglia (2002), where an earthquake killed 26 school children, special attention was paid in Italy to the seismic safety of schools, but mainly with respect to structural aspects. Little attention has been devoted to the possible and even significant damage to non-structural elements (collapse of ceilings, tipping of cabinets and shelving, obstruction of escape routes, etc..). Students and teachers trained on these aspects may lead to a very effective preventive vigilance. Since 2002, the project EDURISK (www.edurisk.it) proposed educational tools and training programs for schools, at primary and middle levels. More recently, a nationwide campaign aimed to adults (www.iononrischio.it) was launched with the extensive support of civil protection volounteers. There was a gap for high schools, and Project SISIFO was designed to fill this void and in particular for those schools with technical/scientific curricula. SISIFO (https://sites.google.com/site/ogssisifo/) is a multidisciplinary initiative, aimed at the diffusion of scientific culture for achieving seismic safety in schools, replicable and can be structured in training the next several years. The students, helped by their teachers and by experts from scientific institutions, followed a course on specialized training on earthquake safety. The trial began in North-East Italy, with a combination of hands-on activities for the measurement of earthquakes with low-cost instruments and lectures with experts in various disciplines, accompanied by specifically designed teaching materials, both on paper and digital format. We intend to raise teachers and students knowledge of the

Alligator rivers analogue project. Final report; volume 1; summary of findings

International Nuclear Information System (INIS)

Duerden, P.; Lever, D.A.; Sverjensky, D.A.; Townley, L.R.

1992-01-01

The Koongarra uranium ore deposit is located in the Alligator Rivers Region of the Northern Territory of Australia. Many of the processes that have controlled the development of this natural system are relevant to the performance assessment of radioactive waste repositories. An agreement was reached in 1987 by a number of agencies concerned with radioactive waste disposal to set up the International Alligator Rivers Analogue Project (ARAP) to study relevant aspects of the hydrological and geochemical evolution of the site. The Project ran for five years. The aims of the study were: to contribute to the production of reliable and realistic models for radionuclide migration within geological environments relevant to the assessment of the safety of radioactive waste repositories; to develop methods of validation of models using a combination of laboratory and field data associated with the Koongarra uranium deposit; and to encourage maximum interaction between modellers and experimentalists in achieving these objectives. It was anticipated that the substantial databases generated in the field and laboratory studies would then be used to develop and test geochemical and radionuclide transport models. The findings from the technical studies are discussed in the context of assessments of the long-term performance of geological repositories for radioactive wastes, which are being undertaken in many countries. They are also considered in an integrated 'Scenario Development' approach, aimed to understand the formation of the ore deposit. Despite their inherent uncertainties, the findings provide a basis for assessing the way in which radionuclides will migrate in environments with a variety of geologic settings and over a range of different geologic timescales. This summary report, which highlights the work and findings of the Alligator Rivers Analogue Project is one of a series of 16 volumes

Patterns of patient safety culture: a complexity and arts-informed project of knowledge translation.

Science.gov (United States)

Mitchell, Gail J; Tregunno, Deborah; Gray, Julia; Ginsberg, Liane

2011-01-01

The purpose of this paper is to describe patterns of patient safety culture that emerged from an innovative collaboration among health services researchers and fine arts colleagues. The group engaged in an arts-informed knowledge translation project to produce a dramatic expression of patient safety culture research for inclusion in a symposium. Scholars have called for a deeper understanding of the complex interrelationships among structure, process and outcomes relating to patient safety. Four patterns of patient safety culture--blinding familiarity, unyielding determination, illusion of control and dismissive urgency--are described with respect to how they informed creation of an arts-informed project for knowledge translation.

Specifications of the International Atomic Energy Agency's international project on safety assessment driven radioactive waste management solutions

International Nuclear Information System (INIS)

Ghannadi, M.; Asgharizadeh, F.; Assadi, M. R.

2008-01-01

Radioactive waste is produced in the generation of nuclear power and the production and use of radioactive materials in the industry, research, and medicine. The nuclear waste management facilities need to perform a safety assessment in order to ensure the safety of a facility. Nuclear safety assessment is a structured and systematic way of examining a proposed facility, process, operation and activity. In nuclear waste management point of view, safety assessment is a process which is used to evaluate the safety of radioactive waste management and disposal facilities. In this regard the International Atomic Energy Agency is planed to implement an international project with cooperation of some member states. The Safety Assessment Driving Radioactive Waste Management Solutions Project is an international programme of work to examine international approaches to safety assessment in aspects of p redisposal r adioactive waste management, including waste conditioning and storage. This study is described the rationale, common aspects, scope, objectives, work plan and anticipated outcomes of the project with refer to International Atomic Energy Agency's documents, such as International Atomic Energy Agency's Safety Standards, as well as the Safety Assessment Driving Radioactive Waste Management Solutions project reports

The International Criticality Safety Benchmark Evaluation Project (ICSBEP)

International Nuclear Information System (INIS)

Briggs, J.B.

2003-01-01

The International Criticality Safety Benchmark Evaluation Project (ICSBEP) was initiated in 1992 by the United States Department of Energy. The ICSBEP became an official activity of the Organisation for Economic Cooperation and Development (OECD) - Nuclear Energy Agency (NEA) in 1995. Representatives from the United States, United Kingdom, France, Japan, the Russian Federation, Hungary, Republic of Korea, Slovenia, Yugoslavia, Kazakhstan, Israel, Spain, and Brazil are now participating. The purpose of the ICSBEP is to identify, evaluate, verify, and formally document a comprehensive and internationally peer-reviewed set of criticality safety benchmark data. The work of the ICSBEP is published as an OECD handbook entitled 'International Handbook of Evaluated Criticality Safety Benchmark Experiments.' The 2003 Edition of the Handbook contains benchmark model specifications for 3070 critical or subcritical configurations that are intended for validating computer codes that calculate effective neutron multiplication and for testing basic nuclear data. (author)

The Nordic nuclear safety program 1994-1997. Project handbook

International Nuclear Information System (INIS)

1997-06-01

This is a new revision of the handbook for administrators of the Nordic reactor safety program NKS. The most important administrative functions in project management are described, which should secure a uniform management approach in all the projects. The description of the organizational scheme of the NKS and distribution of responsibilities is followed by examples of various administrative routines and document forms. In the annex the names and addresses of the staff involved in administration of the NKS program are listed. (EG)

Uranium Mill Tailings Remedial Action Project Safety Advancement Field Effort (SAFE) Program

Energy Technology Data Exchange (ETDEWEB)

1994-02-01

In 1992, the Uranium Mill Tailings Remedial Action (UMTRA) Project experienced several health and safety related incidents at active remediation project sites. As a result, the U.S. Department of Energy (DOE) directed the Technical Assistance Contractor (TAC) to establish a program increasing the DOE`s overall presence at operational remediation sites to identify and minimize risks in operations to the fullest extent possible (Attachments A and B). In response, the TAC, in cooperation with the DOE and the Remedial Action Contractor (RAC), developed the Safety Advancement Field Effort (SAFE) Program.

Uranium Mill Tailings Remedial Action Project Safety Advancement Field Effort (SAFE) Program

International Nuclear Information System (INIS)

1994-02-01

In 1992, the Uranium Mill Tailings Remedial Action (UMTRA) Project experienced several health and safety related incidents at active remediation project sites. As a result, the U.S. Department of Energy (DOE) directed the Technical Assistance Contractor (TAC) to establish a program increasing the DOE's overall presence at operational remediation sites to identify and minimize risks in operations to the fullest extent possible (Attachments A and B). In response, the TAC, in cooperation with the DOE and the Remedial Action Contractor (RAC), developed the Safety Advancement Field Effort (SAFE) Program

INTEGRAL BENCHMARKS AVAILABLE THROUGH THE INTERNATIONAL REACTOR PHYSICS EXPERIMENT EVALUATION PROJECT AND THE INTERNATIONAL CRITICALITY SAFETY BENCHMARK EVALUATION PROJECT

Energy Technology Data Exchange (ETDEWEB)

J. Blair Briggs; Lori Scott; Enrico Sartori; Yolanda Rugama

2008-09-01

Interest in high-quality integral benchmark data is increasing as efforts to quantify and reduce calculational uncertainties accelerate to meet the demands of next generation reactor and advanced fuel cycle concepts. The International Reactor Physics Experiment Evaluation Project (IRPhEP) and the International Criticality Safety Benchmark Evaluation Project (ICSBEP) continue to expand their efforts and broaden their scope to identify, evaluate, and provide integral benchmark data for method and data validation. Benchmark model specifications provided by these two projects are used heavily by the international reactor physics, nuclear data, and criticality safety communities. Thus far, 14 countries have contributed to the IRPhEP, and 20 have contributed to the ICSBEP. The status of the IRPhEP and ICSBEP is discussed in this paper, and the future of the two projects is outlined and discussed. Selected benchmarks that have been added to the IRPhEP and ICSBEP handbooks since PHYSOR’06 are highlighted, and the future of the two projects is discussed.

INTEGRAL BENCHMARKS AVAILABLE THROUGH THE INTERNATIONAL REACTOR PHYSICS EXPERIMENT EVALUATION PROJECT AND THE INTERNATIONAL CRITICALITY SAFETY BENCHMARK EVALUATION PROJECT

International Nuclear Information System (INIS)

J. Blair Briggs; Lori Scott; Enrico Sartori; Yolanda Rugama

2008-01-01

Interest in high-quality integral benchmark data is increasing as efforts to quantify and reduce calculational uncertainties accelerate to meet the demands of next generation reactor and advanced fuel cycle concepts. The International Reactor Physics Experiment Evaluation Project (IRPhEP) and the International Criticality Safety Benchmark Evaluation Project (ICSBEP) continue to expand their efforts and broaden their scope to identify, evaluate, and provide integral benchmark data for method and data validation. Benchmark model specifications provided by these two projects are used heavily by the international reactor physics, nuclear data, and criticality safety communities. Thus far, 14 countries have contributed to the IRPhEP, and 20 have contributed to the ICSBEP. The status of the IRPhEP and ICSBEP is discussed in this paper, and the future of the two projects is outlined and discussed. Selected benchmarks that have been added to the IRPhEP and ICSBEP handbooks since PHYSOR-06 are highlighted, and the future of the two projects is discussed

Overview criteria for the environmental, safety and health evaluation of remedial action project planning

International Nuclear Information System (INIS)

Stenner, R.D.; Denham, D.H.

1984-10-01

Overview criteria (i.e., subject areas requiring review) for evaluating remedial action project plans with respect to environmental, safety and health issues were developed as part of a Department of Energy, Office of Operational Safety, technical support project. Nineteen elements were identified as criteria that should be addressed during the planning process of a remedial action (decontamination and decommissioning) project. The scope was interpreted broadly enough to include such environmental, safety and health issues as public image, legal obligation and quality assurance, as well as more obvious concerns such as those involving the direct protection of public and worker health. The nineteen elements are discussed along with suggested ways to use a data management software system to organize and report results

Proceedings of the first annual Nuclear Criticality Safety Technology Project

International Nuclear Information System (INIS)

Rutherford, D.A.

1994-09-01

This document represents the published proceedings of the first annual Nuclear Criticality Safety Technology Project (NCSTP) Workshop, which took place May 12--14, 1992, in Gaithersburg, Md. The conference consisted of four sessions, each dealing with a specific aspect of nuclear criticality safety issues. The session titles were ''Criticality Code Development, Usage, and Validation,'' ''Experimental Needs, Facilities, and Measurements,'' ''Regulation, Compliance, and Their Effects on Nuclear Criticality Technology and Safety,'' and ''The Nuclear Criticality Community Response to the USDOE Regulations and Compliance Directives.'' The conference also sponsored a Working Group session, a report of the NCSTP Working Group is also presented. Individual papers have been cataloged separately

International intercomparison and harmonization projects for demonstrating the safety of radioactive waste management, decommissioning and radioactive waste disposal

International Nuclear Information System (INIS)

Metcalf, Phil; O'Donnell, Patricio; Jova Sed, Luis; Batandjieva, Borislava; Rowat, John; Kinker, Monica

2008-01-01

Full text: The Joint Convention on the safety of spent fuel management and the safety of radioactive waste management and the international safety standards on radioactive waste management, decommissioning and radioactive waste disposal call for assessment and demonstration of the safety of facilities and activities; during siting, design and construction prior to operation, periodically during operation and at the end of lifetime or upon closure of a waste disposal facility. In addition, more recent revisions of the international safety standards require the development of a safety case for such facilities and activities, documentation presenting all the arguments supporting the safety of the facilities and activities covering site and engineering features, quantitative safety assessment and management systems. Guidance on meeting these safety requirements also indicates the need for a graded approach to safety assessment, with the extent and complexity of the assessment being proportional to the complexity of the activity or facility, and its propensity for radiation hazard. Safety assessment approaches and methodologies have evolved over several decades and international interest in these developments has been considerable as they can be complex and often subjective, which has led to international projects being established aimed at harmonization. The IAEA has sponsored a number of such initiatives, particularly in the area of disposal facility safety, but more recently in the areas of pre disposal waste management and decommissioning, including projects known as ISAM, ASAM, SADRWMS and DeSa. The projects have a number of common aspects including development of standardized methodological approaches, application on test cases and assessment review; they also have activity and facility specific elements. The paper presents an overview of the projects, the outcomes from the projects to date and their future direction aimed very much at practical application of

Technical realization of the VISA-2 Project, contract: 2.01/ I phase, Volume No. I

International Nuclear Information System (INIS)

1963-12-01

Cooperation between the Institutes in Vinca and Saclay has started by carrying out the task 'Technical realization of the VISA-2 project' which should enable: obtaining new experimental spaces in the RA reactor with high fast neutron flux for sample irradiation; obtaining experience in reactor continual operation for few months at nominal power of 6.5 MW and increase of RA reactor utilization; solving the problem of activated channels and samples transport, problems of working in hot cells; obtaining irradiated samples for examining radiation effects first in Saclay and later in Vinca. The project is divided in three phases. Phase one covers the reconstruction of the RA reactor fuel channels according to the VISA-2 project demands. The second phase includes the activities related to measuring devices for measuring the temperatures at the incoming and outgoing heavy water in 5 VISA-2 channels, as well as temperature of the samples (55 thermocouples) and testing the channels and capsules after their insertion in the reactor. The third phase includes activities are related to problems of transport of radioactive channels and VISA-2 capsules, problems of cutting as well as packing and transporting of irradiated samples from Vinca to Saclay. This volume includes all the relevant documents for completing the task including contracts, needed preliminary calculations as well as safety analysis [sr

Safety in Academic Chemistry Laboratories: Volume 1. Accident Prevention for College and University Students, 7th Edition.

Science.gov (United States)

American Chemical Society, Washington, DC.

This book contains volume 1 of 2 and describes safety guidelines for academic chemistry laboratories to prevent accidents for college and university students. Contents include: (1) "Your Responsibility for Accident Prevention"; (2) "Guide to Chemical Hazards"; (3) "Recommended Laboratory Techniques"; and (4) "Safety Equipment and Emergency…

RAAK PRO project: measuring safety in aviation : concept for the design of new metrics

NARCIS (Netherlands)

Karanikas, Nektarios; Kaspers, Steffen; Roelen, Alfred; Piric, Selma; van Aalst, Robbert; de Boer, Robert

2017-01-01

Following the completion of the 1st phase of the RAAK PRO project Aviation Safety Metrics, during which the researchers mapped the current practice in safety metrics and explored the validity of monotonic relationships of SMS, activity and demographic metrics with safety outcomes, this report

1980 survey and evaluation of utility conservation, load management, and solar end-use projects. Volume 3: utility load management projects. Final report

Energy Technology Data Exchange (ETDEWEB)

1982-01-01

The results of the 1980 survey of electric utility-sponsored energy conservation, load management, and end-use solar energy conversion projects are described. The work is an expansion of a previous survey and evaluation and has been jointly sponsored by EPRI and DOE through the Oak Ridge National Laboratory. There are three volumes and a summary document. Each volume presents the results of an extensive survey to determine electric utility involvement in customer-side projects related to the particular technology (i.e., conservation, solar, or load management), selected descriptions of utility projects and results, and first-level technical and economic evaluations.

Seismic safety margins research program. Project I SONGS 1 AFWS Project

International Nuclear Information System (INIS)

Chuang, T.Y.; Smith, P.D.; Dong, R.G.; Bernreuter, D.L.; Bohn, M.P.; Cummings, G.E.; Wells, J.E.

1981-01-01

The seismic qualification requirements of auxiliary feedwater systems (AFWS) of Pressurized Water Reactors (PWR) were developed over a number of years. These are formalized in the publication General Design Criteria (Appendix A to 10CFR50). The full recognition of the system as an engineered safety feature did not occur until publication of the Standard Review Plan (1975). Efforts to determine how to backfit seismic requirements to earlier plants has been undertaken primarily in the Systematic Evaluation Program (SEP) for a limited number of operating reactors. Nuclear Reactor Research (RES) and NRR have requested LLNL to perform a probabilistic study on the AFWS of San Onofre Nuclear Generating Station (SONGS) Unit 1 utilizing the tools developed by the Seismic Safety Margins Research Program (SSMRP). The main objectives of this project are to: identify the weak links of AFWS; compare the failure probabilities of SONGS 1 and Zion 1 AFWS: and compare the seismic responses due to different input spectra and design values

Evaluation of research projects and studies on nuclear safety in the context of implementation of the German Atomic Energy Act (AtG). Vol. 9

International Nuclear Information System (INIS)

Casper, H.

2000-01-01

The content of this report is a collection of research projects and investigations in the field of nuclear safety evaluated in 1999 and 2000 with regard to the application of the Atomic Energy Act (Atomgesetz). In addition the report gives an overview on objectives and procedures used for the evaluation. The purpose of this project, being executed for the Federal Ministry for Environment, Nature Conservation and Nuclear Safety (BMU) of the Federal Republic of Germany is to inform all parties involved in the licensing procedure as well as the consulting councils on the latest nuclear safety research results and the status of their verification in a precise short manner. In addition experts' opinions are given with regard to the relevance of these research results to nuclear rules and guidelines as well as to the execution of the Atomic Energy Act. The information consists of precise and short evaluations of final research reports or technical reports. These evaluations are prepared by specialists who are acquainted with the technical aspects of the licensing procedure of nuclear plants in the Federal Republic of Germany. This volume is the ninth report of this series. (orig.) [de

Radiological safety research for nuclear excavation projects - Interoceanic canal studies

Energy Technology Data Exchange (ETDEWEB)

Klement, Jr, A W [U.S. Atomic Energy Commission, Las Vegas, NV (United States)

1969-07-01

The general radiological problems encountered in nuclear cratering and nuclear excavation projects are discussed. Procedures for assessing radiological problems in such projects are outlined. Included in the discussions are source term, meteorology, fallout prediction and ecological factors. Continuing research requirements as well as pre- and post-excavation studies are important considerations. The procedures followed in the current interoceanic canal feasibility studies provide examples of radiological safety problems, current solutions and needed research. (author)

Radiological safety research for nuclear excavation projects - Interoceanic canal studies

International Nuclear Information System (INIS)

Klement, A.W. Jr.

1969-01-01

The general radiological problems encountered in nuclear cratering and nuclear excavation projects are discussed. Procedures for assessing radiological problems in such projects are outlined. Included in the discussions are source term, meteorology, fallout prediction and ecological factors. Continuing research requirements as well as pre- and post-excavation studies are important considerations. The procedures followed in the current interoceanic canal feasibility studies provide examples of radiological safety problems, current solutions and needed research. (author)

Quality and Safety Assurance - Priority Task at Nuclear Power Projects Implementation

International Nuclear Information System (INIS)

Nenkova, B.; Manchev, B.; Tomov, E.

2010-01-01

Quality and safety assurance at implementation of nuclear power engineering projects is important and difficult task for realization. Many problems arise during this process, when many companies from different countries participate, with various kinds of activities and services provided. The scope of activities necessary for quality and safety assurance is therefore quite expanded and diverse. In order to increase the safety and reliability of Kozloduy NPP Plc (KNPP) Units 5 and 6, as well as to bring the units in conformity with the newest international requirements for quality and safety in the field of nuclear energy, a program for their modernization on the basis of different technical studies and assessments was implemented. The Units 5 and 6 Modernization Program of Kozloduy Nuclear Power Plant was composed of 212 modifications aimed to improve the safety, operability, and reliability of the Units. The Program was realized by stages during yearly planned outages since year 2002 to 2007, without additional outages. A major Program Objective was to extend the Units Life Time in at least 15 Years, under a continuous, safe, and reliable operation. The Modernization Program of Units 5 and 6 of the Bulgarian Nuclear Power Plant in Kozloduy was the first and for the time being the only one in the world, program in the field of nuclear power engineering, by which the full scope of recommendations for improvement of the Kozloduy NPP units was applied. The main goal of the National Electric Company, which is the Employer for the construction of new nuclear facility in Bulgaria, is after completion of all activities regarding construction of Belene NPP the plant to meet or exceed the requirements of the respective national and international quality and safety codes and standards, as well as the IAEA guidelines, as they are established. The objective of this report is to describe different aspects of the quality assurance according to the requirements of quality and

Technical safety appraisal of the West Valley Demonstration Project

International Nuclear Information System (INIS)

1989-09-01

This report presents the results of one in a series of Technical Safety Appraisals (TSAs) being conducted of DOE nuclear operations by the Assistant Secretary for Environment, Safety, and Health Office of Safety Appraisals TSAs are one of the ititiatives announced by the Secretary of Energy on September 18, 1985, to enhance the DOE environment, safety and health program. This report presents the results of a TSA of the West Valley Demonstration Project (WVDP). The appraisal was conducted by a team of exerts assembled by the DOE Office of Safety Appraisal and was conducted during onsite visits of June 26-30 and July 10-21, 1989. West Valley, about 30 miles south of Buffalo, New York is the location of the only commercial nuclear fuel reprocessing facility operated in the United States. Nuclear Fuels Services, Inc. (NFS) operated the plant from 1966 to 1972 and processed about 640 metric tons of spent reactor fuel. The reprocessing operation generated about 560,000 gallons of high-level radioactive waste, which was transferred into underground tanks for storage. In 1972 NFS closed the plant and subsequently decided not to reopen it

Project for the completion of a probabilistic safety analysis of an industrial irradiation

International Nuclear Information System (INIS)

Ferro, R.; Troncoso, M.

1995-01-01

The probabilistic safety analysis is a very valuable instrument in safety studies of facilities with potential risk for the personnel, population and environment. One of the possible field of use of PSA techniques in the safety studies for industrial irradiation where serious accidents have occurred. For this reason a project has been undertaken to carry out the PSA in the Irradiation Plant of Research Institute of the Food Industry, which complements the safety studies of this facility

Pacific Northwest Laboratory annual report for 1985 to the DOE Office of the Assistant Secretary for Environment, Safety and Health. Part 5. Overview and assessment

International Nuclear Information System (INIS)

Faust, L.G.

1986-02-01

This volume is progress on work performed for the Office of Nuclear Safety, the Office of Operational Safety, and for the Office of Environmental Analysis for each project. Separate abstracts have been prepared for individual projects. ACR

Inventory of Federal Energy-Related Environment and Safety Research for FY 1978. Volume III, interactive terminal users guide

Energy Technology Data Exchange (ETDEWEB)

Miller, C. E.; Barker, Janice F.

1979-12-01

This users' guide was prepared to provide interested persons access to, via computer terminals, federally funded energy-related environmental and safety research projects for FY 1978. Although this information is also available in hardbound volumes, this on-line searching capability is expected to reduce the time required to answer ad hoc questions and, at the same time, produce meaningful reports. The data contained in this data base are not exhaustive and represent research reported by the following agencies: Department of Agriculture, Department of Commerce, Department of Defense, Department of Energy, Department of Health, Education, and Welfare, Department of the Interior, Department of Transportation, Federal Energy Administration, National Aeronautics and Space Administration, National Science Foundation, Nuclear Regulatory Commission, Tennessee Valley Authority, U.S. Coast Guard, and the U.S. Environmental Protection Agency.

Bridging the Divide between Safety and Risk Management for your Project or Program

Science.gov (United States)

Lutomski, Mike

2005-01-01

This presentation will bridge the divide between these separate but overlapping disciplines and help explain how to use Risk Management as an effective management decision support tool that includes safety. Risk Management is an over arching communication tool used by management to prioritize and effectively mitigate potential problems before they concur. Risk Management encompasses every kind of potential problem that can occur on a program or project. Some of these are safety issues such as hazards that have a specific likelihood and consequence that need to be controlled and included to show an integrated picture of accepted) mitigated, and residual risk. Integrating safety and other assurance disciplines is paramount to accurately representing a program s or projects risk posture. Risk is made up of several components such as technical) cost, schedule, or supportability. Safety should also be a consideration for every risk. The safety component can also have an impact on the technical, cost, and schedule aspect of a given risk. The current formats used for communication of safety and risk issues are not consistent or integrated. The presentation will explore the history of these disciplines, current work to integrate them, and suggestions for integration for the future.

Safety reassessment of the Paks NPP (the AGNES project)

Energy Technology Data Exchange (ETDEWEB)

Gado, J [Hungarian Academy of Sciences, Budapest (Hungary). Central Research Inst. for Physics; Bajsz, J; Cserhati, A; Elter, J [Paksi Atomeroemue Vallalat, Paks (Hungary); Hollo, E [Energiagazdalkodasi Intezet, Budapest (Hungary); Kovacs, K [EROTERV Engineering and Contractor Co (Hungary); Maroti, L [Hungarian Academy of Sciences, Budapest (Hungary). Central Research Inst. for Physics; Miko, S [Paksi Atomeroemue Vallalat, Paks (Hungary); Techy, Z [Energiagazdalkodasi Intezet, Budapest (Hungary); Vidovszky, I [Hungarian Academy of Sciences, Budapest (Hungary). Central Research Inst. for Physics

1996-12-31

The reassessment of the Paks NPP safety according to internationally recognized criteria of the Advanced General and New Evaluation of Safety (AGNES) project is outlined. The Paks NPP consists of four WWER-440/V-213 units. The following groups of analysis have been performed: system analysis and description; analysis of design basis accidents; severe accidents analysis; level 1 probabilistic safety analysis. Postulated accidents (PA) and Anticipated Operational Occurrences (AOO) are estimated in detail for the following initiating events: increase/decrease in secondary heat removal; decrease in primary coolant inventory; increase/decrease of reactor coolant inventory; reactivity and power distribution anomalies; analysis of transients with the failure of reactor scram (ATWS); pressurized thermal shock analyses. Severe accident analysis was made for the accidents on in-vessel phase and containment phase, for radioactive release and for accident management.

Safety reassessment of the Paks NPP (the AGNES project)

International Nuclear Information System (INIS)

Gado, J.; Hollo, E.; Kovacs, K.; Maroti, L.; Techy, Z.; Vidovszky, I.

1995-01-01

The reassessment of the Paks NPP safety according to internationally recognized criteria of the Advanced General and New Evaluation of Safety (AGNES) project is outlined. The Paks NPP consists of four WWER-440/V-213 units. The following groups of analysis have been performed: system analysis and description; analysis of design basis accidents; severe accidents analysis; level 1 probabilistic safety analysis. Postulated accidents (PA) and Anticipated Operational Occurrences (AOO) are estimated in detail for the following initiating events: increase/decrease in secondary heat removal; decrease in primary coolant inventory; increase/decrease of reactor coolant inventory; reactivity and power distribution anomalies; analysis of transients with the failure of reactor scram (ATWS); pressurized thermal shock analyses. Severe accident analysis was made for the accidents on in-vessel phase and containment phase, for radioactive release and for accident management

Site Environmental Report for 2006. Volume I, Environment, Health, and Safety Division

Energy Technology Data Exchange (ETDEWEB)

None

2007-09-30

Each year, Ernest Orlando Lawrence Berkeley National Laboratory prepares an integrated report on its environmental programs to satisfy the requirements of United States Department of Energy Order 231.1A, Environment, Safety, and Health Reporting.1 The Site Environmental Report for 2006 summarizes Berkeley Lab’s environmental management performance, presents environmental monitoring results, and describes significant programs for calendar year 2006. (Throughout this report, Ernest Orlando Lawrence Berkeley National Laboratory is referred to as “Berkeley Lab,” “the Laboratory,” “Lawrence Berkeley National Laboratory,” and “LBNL.”) The report is separated into two volumes. Volume I is organized into an executive summary followed by six chapters that contain an overview of the Laboratory, a discussion of the Laboratory’s environmental management system, the status of environmental programs, and summarized results from surveillance and monitoring activities. Volume II contains individual data results from surveillance and monitoring activities.

Accident consequence calculations for project W-058 safety analysis

International Nuclear Information System (INIS)

Van Keuren, J.C.

1997-01-01

This document describes the calculations performed to determine the accident consequences for the W-058 safety analysis. Project W-058 is the replacement cross site transfer system (RCSTS), which is designed to transort liquid waste between the 200 W and 200 E areas. Calculations for RCSTS safety analyses used the same methods as the calculations for the Tank Waste Remediation System (TWRS) Basis for Interim Operation (BIO) and its supporting calculation notes. Revised analyses were performed for the spray and pool leak accidents since the RCSTS flows and pressures differ from those assumed in the TWRS BIO. Revision 1 of the document incorporates review comments

Nordic nuclear safety research 1994-1997. Project on disposal of radioactive waste

International Nuclear Information System (INIS)

Broden, Karin

1999-01-01

This presentation describes the Nordic Nuclear Safety Research (NKS) programme, which is a scientific co-operation programme in nuclear safety, radiation protection and emergence preparedness. The purpose of the programme is to carry out cost-effective Nordic projects, thus producing research results, exercises, information, manuals, recommendations, and other types of background material. This material is to serve decision-makers and other concerned staff members at authorities, research establishments and enterprises in the nuclear field. Three waste disposal projects under NKS are briefly described: (1) Waste characterisation, (2) Performance analysis of the engineered barrier system of the repositories for low- and intermediate-level waste, (3) Environmental impact assessment

Safety research in the field of energy production. Plan for continued Nordic projects

Energy Technology Data Exchange (ETDEWEB)

Ahlstroem, P E [Statens Vattenfallsverk, Stockholm (Sweden); Berg, J [Institutt for Atomenergi, Kjeller (Norway); Eckered, T [Statens Kaernkraftinspektion, Stockholm (Sweden)

1980-01-01

NGS, an ad hoc group of the Nordic Co-ordination Committee for Atomic Energy, has prepared this survey of proposed cooperative projects as a continuation of previous projects. New areas to be given priority are:- reactor safety, environmental effects in energy production and human reliability. Continued projects are:- quality assurance, radioactive waste and radioecology. (JIW)

Yucca Mountain Project Site Atlas: Volume 1: Draft

International Nuclear Information System (INIS)

1988-10-01

The Nevada Nuclear Waste Storage Investigations (NNWSI) Project Site Atlas is a reference document of field activities which have been, or are being, conducted by the US Department of Energy (DOE) to support investigations of Yucca Mountain as a potential site for an underground repository for high-level radioactive waste. These investigations, as well as future investigations, will yield geologic, geophysical, geochemical, geomechanical, hydrologic, volcanic, seismic, and environmental data necessary to characterize Yucca Mountain and its regional setting. This chapter summarizes the background of the NNWSI Project and the objective, scope, structure, and preparation of the Site Atlas. Chapter 2 describes in more detail the bibliography and map portfolio portions of the Atlas, which are presented in Chapter 4 and Volume 2, respectively. Chapter 3 describes how to use the Atlas. The objective of the Site Atlas is to create a management tool for the DOE Waste Management Project Office (WMPO) that will allow the WMPO to compile and disseminate information regarding the location of NNWSI Project field investigations, and document the permits acquired and the environmental, archaeological, and socioeconomic surveys conducted to support those investigations. The information contained in the Atlas will serve as a historical reference of site investigation field activities. A companion document to the Atlas is the NNWSI Project Surface Based Investigations Plan (SBIP)

Safety cases for radioactive waste disposal facilities: guidance on confidence building and regulatory review IAEA-ASAM co-ordinated research project

International Nuclear Information System (INIS)

Ben Belfadhel, M.; Bennett, D.G.; Metcalf, P.; Nys, V.; Goldammer, W.

2008-01-01

The IAEA has been conducting two co-ordinated research programmes (CRPs) projects to develop and apply improved safety assessment methodologies for near-surface radioactive waste disposal facilities. The more recent of these projects, ASAM (application of safety assessment methodologies), included a Regulatory Review Working Group (RRWG) which has been working to develop guidance on how to gain confidence in safety assessments and safety cases, and on how to conduct regulatory reviews of safety assessments. This paper provides an overview of the ASAM project, focusing on the safety case and regulatory review. (authors)

The Safety Assessment Framework Tool (SAFRAN) - Description, Overview and Applicability

International Nuclear Information System (INIS)

Alujevic, Luka

2014-01-01

The SAFRAN tool (Safety Assessment Framework) is a user-friendly software application that incorporates the methodologies developed in the SADRWMS (Safety Assessment Driven Radioactive Waste Management Solutions) project. The International Atomic Energy Agency (IAEA) organized the International Project on Safety Assessment Driving Radioactive Waste Management Solutions (SADRWMS) to examine international approaches to safety assessment for predisposal management of all types of radioactive waste, including disused sources, small volumes, legacy and decommissioning waste, operational waste, and large volume naturally occurring radioactive material residues. SAFRAN provides aid in: Describing the predisposal RW management activities in a systematic way, Conducting the SA (safety assessment) with clear documentation of the methodology, assumptions, input data and models, Establishing a traceable and transparent record of the safety basis for decisions on the proposed RW management solutions, Demonstrating clear consideration of and compliance with national and international safety standards and recommendations. The SAFRAN tool allows the user to visibly, systematically and logically address predisposal radioactive waste management and decommissioning challenges in a structured way. It also records the decisions taken in such a way that it constitutes a justifiable safety assessment of the proposed management solutions. The objective of this paper is to describe the SAFRAN architecture and features, properly define the terms safety case and safety assessment, and to predict the future development of the SAFRAN tool and assess its applicability to the construction of a future LILW (Low and Intermediate Level Waste) storage facility and repository in Croatia, taking into account all the capabilities and modelling features of the SAFRAN tool. (author)

Solid Waste Operations Complex W-113: Project cost estimate. Preliminary design report. Volume IV

International Nuclear Information System (INIS)

1995-01-01

This document contains Volume IV of the Preliminary Design Report for the Solid Waste Operations Complex W-113 which is the Project Cost Estimate and construction schedule. The estimate was developed based upon Title 1 material take-offs, budgetary equipment quotes and Raytheon historical in-house data. The W-113 project cost estimate and project construction schedule were integrated together to provide a resource loaded project network

Designing and Developing an Effective Safety Program for a Student Project Team

Directory of Open Access Journals (Sweden)

John Catton

2018-05-01

Full Text Available In the workplace, safety must be the first priority of all employers and employees alike. In order to maintain the safety and well-being of their employees, employers must demonstrate due diligence and provide the appropriate safety training to familiarize employees with the hazards within the workplace. Although, a student “project team” is not a business, the work done by students for their respective teams is synonymous with the work done in a place of business and thus requires that similar safety precautions and training be administered to students by their team leads and faculty advisors. They take on the role of supervisors within the team dynamic. Student teams often utilize the guidelines and policies that their universities or colleges have developed in order to build a set of standard operating procedures and safety training modules. These guidelines aid in providing a base for training for the team, however, they are no substitute for training specific to the safety risks associated with the work the team is doing. In order to comply with these requirements, a full analysis of the workplace is required to be completed. A variety of safety analysis techniques need to be applied to define the hazards within the workplace and institute appropriate measures to mitigate them. In this work, a process is developed for establishing a safety training program for a student project team, utilizing systems safety management techniques and the aspect of gamification to produce incentives for students to continue developing their skills. Although, systems safety management is typically applied to the design of active safety components or systems, the techniques for identifying and mitigating hazards can be applied in the same fashion to the workplace. They allow one to analyze their workplace and determine the hazards their employees might encounter, assign appropriate hazard ratings and segregate each respective hazard by their risks. In so

Status of safety issues at licensed power plants

International Nuclear Information System (INIS)

1991-05-01

As part of ongoing US Nuclear Regulatory Commission (NRC) efforts to ensure the quality and accountability of safety issue information, a program has been established whereby an annual NUREG report will be published on the status of licensee implementation and NRC verification of safety issues in major NRC requirement areas. This report, the second volume of a three-volume series, addresses the status of unresolved safety issues (USIs) at licensed plants. The data contained in these NUREG reports are a product of the NRC's Safety Issues Management System (SIMS) database, which is maintained by the Project Management Staff in the Office of Nuclear Reactor Regulation and by NRC regional personnel. The purpose of this report is to provide a comprehensive description of the status of implementation and verification of the 27 safety issues designated as USIs and to make this information available to other interested parties, including the public. A corollary purpose of this NUREG report is to serve as a follow-on to NUREG-0933, ''A Prioritization of Generic Safety Issues,'' which tracks safety issues up until requirements are approved for imposition at licensed plants. 3 figs., 4 tabs

Experience of Hungarian model project: 'Strengthening training for operational safety at Paks NPP'

International Nuclear Information System (INIS)

Kiss, I.

1998-01-01

Training of Operational Safety at Paks NPP is described including all the features of the project including namely: description of Paks NPP, its properties and performances; reasons for establishing Hungarian Model Project, its main goals, mentioning Hungarian and IAEA experts involved in the Project, its organization, operation, budget, current status together with its short term and long term impact

Bayesian-network-based safety risk analysis in construction projects

International Nuclear Information System (INIS)

Zhang, Limao; Wu, Xianguo; Skibniewski, Miroslaw J.; Zhong, Jingbing; Lu, Yujie

2014-01-01

This paper presents a systemic decision support approach for safety risk analysis under uncertainty in tunnel construction. Fuzzy Bayesian Networks (FBN) is used to investigate causal relationships between tunnel-induced damage and its influential variables based upon the risk/hazard mechanism analysis. Aiming to overcome limitations on the current probability estimation, an expert confidence indicator is proposed to ensure the reliability of the surveyed data for fuzzy probability assessment of basic risk factors. A detailed fuzzy-based inference procedure is developed, which has a capacity of implementing deductive reasoning, sensitivity analysis and abductive reasoning. The “3σ criterion” is adopted to calculate the characteristic values of a triangular fuzzy number in the probability fuzzification process, and the α-weighted valuation method is adopted for defuzzification. The construction safety analysis progress is extended to the entire life cycle of risk-prone events, including the pre-accident, during-construction continuous and post-accident control. A typical hazard concerning the tunnel leakage in the construction of Wuhan Yangtze Metro Tunnel in China is presented as a case study, in order to verify the applicability of the proposed approach. The results demonstrate the feasibility of the proposed approach and its application potential. A comparison of advantages and disadvantages between FBN and fuzzy fault tree analysis (FFTA) as risk analysis tools is also conducted. The proposed approach can be used to provide guidelines for safety analysis and management in construction projects, and thus increase the likelihood of a successful project in a complex environment. - Highlights: • A systemic Bayesian network based approach for safety risk analysis is developed. • An expert confidence indicator for probability fuzzification is proposed. • Safety risk analysis progress is extended to entire life cycle of risk-prone events. • A typical

IAEA TC Project 'Strengthening safety and reliability of fuel and materials in nuclear power plants'

International Nuclear Information System (INIS)

Makihara, Y.

2008-01-01

The Regional TC Project in Europe RER9076 'Strengthening Safety and Reliability of Fuel and Materials in Nuclear Power Plants' was launched in 2003 as a four-year project and was subsequently extended in 2006 to run through 2008. The purpose of the Project is to support the Central and Eastern European countries with the necessary tools to fulfill their own fuel and material licensing needs. The main objective will be to provide quality data on fuel and materials irradiated in power reactors and in dedicated experiments carried out in material test reactors (MTRs). Within the framework of the Project, ten tasks were implemented. These included experiments performed at the test facilities in the region, training courses and workshops related to fuel safety. While several tasks are expected to be completed by the end of RER9076, some remain. It would be desirable to initiate a new RER Project from the next TC cycle (2009-2011) in order to take over RER9076 and to implement new tasks required for enhancing fuel safety in the region. (author)

The Environmental Health/Home Safety Education Project: a successful and practical U.S.-Mexico border initiative.

Science.gov (United States)

Forster-Cox, Susan C; Mangadu, Thenral; Jacquez, Benjamín; Fullerton, Lynne

2010-05-01

The Environmental Health/Home Safety Education Project (Proyecto de Salud Ambiental y Seguridad en el Hogar) has been developed in response to a wide array of severe and often preventable environmental health issues occurring in and around homes on the U.S.-Mexico border. Utilizing well-trained community members, called promotoras , homes are visited and assessed for potential environmental hazards, including home fire and food safety issues. Data analyzed from project years 2002 to 2005 shows a significant impact in knowledge levels and initial behavior change among targeted participants as it relates to fire and food safety issues. Since the initiation of the project in 1999, hundreds of participants have improved their quality of life by making their homes safer. The project has proven to be sustainable, replicable, flexible, and attractive to funders.

Application of project management methodology in design management of nuclear safety related structure

International Nuclear Information System (INIS)

Chen Mao

2004-01-01

This paper focuses on the application of project management methodology in the design management of Nuclear Safety Related Structure (NSRS), considering the design management features of its civil construction. Based on the experiences from the management of several projects, the project management triangle is proposed to be used in the management, to well treat the position of design interface in the project management. Some other management methods are also proposed

Safety Research Experiment Facility Project. Conceptual design report. Volume II. Building and facilities

International Nuclear Information System (INIS)

1975-12-01

The conceptual design of Safety Research Experiment Facility (SAREF) site system includes a review and evaluation of previous geotechnical reports for the area where SAREF will be constructed and the conceptual design of access and in-plant roads, parking, experiment-transport-vehicle maneuvering areas, security fencing, drainage, borrow area development and restoration, and landscaping

SKI SITE-94. Deep Repository Performance Assessment Project Volume I and II

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-12-01

The function of SITE-94 is to provide the Swedish Nuclear Power Inspectorate (SKI) with the capacity and supporting knowledge needed for reviewing the Swedish nuclear industry`s R and D programs and for reviewing license applications, as stipulated in Swedish legislation. The report is structured as a Performance Assessment exercise needed for input to decisions regarding repository safety, but the SITE-94 is not a safety assessment or a model for future assessments to be undertaken by the prospective licensee. The specific project objectives of SITE-94 comprise site evaluation, performance assessment methodology, canister integrity and radionuclide release and transport calculations. The report gives a detailed description of the many inter-related studies undertaken as part of the research project. As a general conclusion it is noted that the SITE-94 project has significantly advanced SKI`s capability of reviewing performance assessments and has led to the development of a tool-kit for carrying out assessment calculations, both in terms of numerical and scoping analyses. The study has highlighted a number of key issues for safety assessment (and consequently for disposal system design): Canister performance; Derived parameters of geosphere retention properties; Spatial variability of groundwater flow and geochemistry of migration paths; Time dependency (more emphasis on transient, time-dependent processes); Buffer evolution over long time. 488 refs.

SKI SITE-94. Deep Repository Performance Assessment Project Volume I and II

International Nuclear Information System (INIS)

1996-12-01

The function of SITE-94 is to provide the Swedish Nuclear Power Inspectorate (SKI) with the capacity and supporting knowledge needed for reviewing the Swedish nuclear industry's R and D programs and for reviewing license applications, as stipulated in Swedish legislation. The report is structured as a Performance Assessment exercise needed for input to decisions regarding repository safety, but the SITE-94 is not a safety assessment or a model for future assessments to be undertaken by the prospective licensee. The specific project objectives of SITE-94 comprise site evaluation, performance assessment methodology, canister integrity and radionuclide release and transport calculations. The report gives a detailed description of the many inter-related studies undertaken as part of the research project. As a general conclusion it is noted that the SITE-94 project has significantly advanced SKI's capability of reviewing performance assessments and has led to the development of a tool-kit for carrying out assessment calculations, both in terms of numerical and scoping analyses. The study has highlighted a number of key issues for safety assessment (and consequently for disposal system design): Canister performance; Derived parameters of geosphere retention properties; Spatial variability of groundwater flow and geochemistry of migration paths; Time dependency (more emphasis on transient, time-dependent processes); Buffer evolution over long time. 488 refs

Road safety in Poland : a contribution to the improvement of road safety in Poland in the framework of the GAMBIT project.

NARCIS (Netherlands)

Brouwer, M. Koornstra, M.J. Mulder, J.A.G. & Wegman, F.C.M.

1995-01-01

This report describes a SWOV Institute for Road Safety Research study. The study was commissioned: (1) to give a general opinion on the "GAMBIT" project contents; and (2) to express an expectation about the future traffic safety development in Poland. The SWOV contribution has been realized within

Developing tools for the safety specification in risk management plans: lessons learned from a pilot project.

Science.gov (United States)

Cooper, Andrew J P; Lettis, Sally; Chapman, Charlotte L; Evans, Stephen J W; Waller, Patrick C; Shakir, Saad; Payvandi, Nassrin; Murray, Alison B

2008-05-01

Following the adoption of the ICH E2E guideline, risk management plans (RMP) defining the cumulative safety experience and identifying limitations in safety information are now required for marketing authorisation applications (MAA). A collaborative research project was conducted to gain experience with tools for presenting and evaluating data in the safety specification. This paper presents those tools found to be useful and the lessons learned from their use. Archive data from a successful MAA were utilised. Methods were assessed for demonstrating the extent of clinical safety experience, evaluating the sensitivity of the clinical trial data to detect treatment differences and identifying safety signals from adverse event and laboratory data to define the extent of safety knowledge with the drug. The extent of clinical safety experience was demonstrated by plots of patient exposure over time. Adverse event data were presented using dot plots, which display the percentages of patients with the events of interest, the odds ratio, and 95% confidence interval. Power and confidence interval plots were utilised for evaluating the sensitivity of the clinical database to detect treatment differences. Box and whisker plots were used to display laboratory data. This project enabled us to identify new evidence-based methods for presenting and evaluating clinical safety data. These methods represent an advance in the way safety data from clinical trials can be analysed and presented. This project emphasises the importance of early and comprehensive planning of the safety package, including evaluation of the use of epidemiology data.

Definition of user needs and “hot topics”, Deliverable 2.1 of the H2020 project SafetyCube (Safety CaUsation, Benefits and Efficiency).

NARCIS (Netherlands)

Hagström, L. Thomson, R. Skogsmo, I. Houtenbos, M. Durso, C. Thomas, P. Elvik, R. & Wismans, J.

2016-01-01

Safety CaUsation, Benefits and Efficiency (SafetyCube) is a European Commission supported Horizon 2020 project with the objective of developing an innovative road safety Decision Support System (DSS) that will enable policymakers and stakeholders to select and implement the most appropriate

I and C safety research at the OECD Halden reactor project

International Nuclear Information System (INIS)

Gran, B.A.

2007-01-01

The overall objective of the Halden Reactor Project research on software systems dependability is to contribute to the successful introduction of digital I and C systems into NPPs. When celebrating the 50 years of the Halden Project in 2008, about 100 written reports have been delivered within this research. This research covers a number of topics covering safety, reliability, validation and verification, quality assurance, risk assessment, requirement engineering, error propagation, qualitative and quantitative assessment. In the paper some activities are described, pinpointing the importance of good joint projects with organisations in the member countries

The arrangement of deformation monitoring project and analysis of monitoring data of a hydropower engineering safety monitoring system

Science.gov (United States)

Wang, Wanshun; Chen, Zhuo; Li, Xiuwen

2018-03-01

The safety monitoring is very important in the operation and management of water resources and hydropower projects. It is the important means to understand the dam running status, to ensure the dam safety, to safeguard people’s life and property security, and to make full use of engineering benefits. This paper introduces the arrangement of engineering safety monitoring system based on the example of a water resource control project. The monitoring results of each monitoring project are analyzed intensively to show the operating status of the monitoring system and to provide useful reference for similar projects.

Construction safety monitoring based on the project's characteristic with fuzzy logic approach

Science.gov (United States)

Winanda, Lila Ayu Ratna; Adi, Trijoko Wahyu; Anwar, Nadjadji; Wahyuni, Febriana Santi

2017-11-01

Construction workers accident is the highest number compared with other industries and falls are the main cause of fatal and serious injuries in high rise projects. Generally, construction workers accidents are caused by unsafe act and unsafe condition that can occur separately or together, thus a safety monitoring system based on influencing factors is needed to achieve zero accident in construction industry. The dynamic characteristic in construction causes high mobility for workers while doing the task, so it requires a continuously monitoring system to detect unsafe condition and to protect workers from potential hazards. In accordance with the unique nature of project, fuzzy logic approach is one of the appropriate methods for workers safety monitoring on site. In this study, the focus of discussion is based on the characteristic of construction projects in analyzing "potential hazard" and the "protection planning" to be used in accident prevention. The data have been collected from literature review, expert opinion and institution of safety and health. This data used to determine hazard identification. Then, an application model is created using Delphi programming. The process in fuzzy is divided into fuzzification, inference and defuzzification, according to the data collection. Then, the input and final output data are given back to the expert for assessment as a validation of application model. The result of the study showed that the potential hazard of construction workers accident could be analysed based on characteristic of project and protection system on site and fuzzy logic approach can be used for construction workers accident analysis. Based on case study and the feedback assessment from expert, it showed that the application model can be used as one of the safety monitoring tools.

Final disposal of radioactive wastes in Switzerland: concept and overview of Project Guarantee 1985

International Nuclear Information System (INIS)

Anon.

1985-01-01

The validity of the operational licences of the existing Swiss nuclear power plants (NPP) Beznau I and II, Muehleberg, Goesgen and Leibstadt after 31st. December 1985 is, because of official requirements, dependent on the demonstration of permanent, safe management and final disposal of radioactive waste. For this purpose, the NPP companies have to prepare a so-called guarantee project and present this to the Bundesrat for review. The appropriate investigations and research have been carried out by Nagra (National Cooperative for the Storage of Radioactive Waste). The 1985 Project Gewaehr (Guarantee) is described in an eight volume report NGB 85-01 to 85-08 and individual research projects are reported on in separate NTB-series reference reports. The present volume NGB 85-01 takes the form of a self-contained project overview in which the concepts for nuclear waste management are described, the contents of the remaining volumes NGB 85-02 to 85-08 are summarized and Project conclusions are drawn from Project Gewaehr 1985. Project Gewaehr 1985 covers two repository types: Type C repository for high-level and certain alpha-containing intermediate-level waste, and Type B repository for all remaining intermediate- and low-level waste. The Project shows in detail that technical feasibility of final disposal can be assumed given presently available methods, that the technical safety barriers show a high level of efficiency and that suitable geological options are available to ensure long-term safety in Switzerland as the concept is defined by official requirements. The Project safety analyses show that the chosen disposal concepts assure the protection of mankind and the environment under all realistically anticipated conditions

Procedures for initiation, cost-sharing and management of OECD projects in nuclear safety

International Nuclear Information System (INIS)

2002-01-01

The OECD (CSNI) projects aim to produce results relevant for the safe operation of nuclear power plants through international collaborative projects. In general, the projects consist of advanced experimental programmes that are conducted at specialized facilities. At present, the following OECD (CSNI) projects are in operation: - The Halden Project, covering fuel/materials and I and C/Human Factors issues; - The Cabri Project, addressing reactivity transients on high burnup fuels; - The MASCA Project, which deals with in-vessel corium phenomena; - The OLHF Project, dealing with lower head failure mechanisms; - The SETH Project addressing thermal-hydraulics issues, started in 2001; - The MCCI Project on ex-vessel coolability and melt-concrete interaction. There are significant differences among these projects in terms of their motivation, size and scope. The Halden Project and the Cabri Water Loop Project are large undertakings where the host organisations assume full and direct responsibility for the project establishment and administration - as well as for the negotiation with relevant parties on the terms of participation. In the other cases, instead, the NEA secretariat has a more direct responsibility, conferred by the CSNI, in establishing the project technical and financial basis, as well as for its implementation and administration. The objective of this procedure is to provide a common basis for the establishment and management of the OECD projects in the area of nuclear safety. It is a follow-up of a recommendation expressed by the CSNI Bureau during its meeting in October 2001, where the procedures for the establishment and management of the OECD (CSNI) projects in nuclear safety were addressed. While this procedure attempts at defining general guidelines for project initiation, financing and management, one should bear in mind that each project has its own motivation, background and framework. Thus, some degree of flexibility in project structure

Data base on dose reduction research projects for nuclear power plants. Volume 4

Energy Technology Data Exchange (ETDEWEB)

Khan, T.A.; Vulin, D.S.; Liang, H.; Baum, J.W. [Brookhaven National Lab., Upton, NY (United States)

1992-08-01

This is the fourth volume in a series of reports that provide information on dose reduction research and health physics technology for nuclear power plants. The information is taken from a data base maintained by Brookhaven National Laboratory`s ALARA Center for the Nuclear Regulatory Commission. This report presents information on 118 new or updated projects, covering a wide range of activities. Projects including steam generator degradation, decontamination, robotics, improvement in reactor materials, and inspection techniques, among others, are described in the research section of the report. The section on health physics technology includes some simple and very cost-effective projects to reduce radiation exposures. Included in this volume is a detailed description of how to access the BNL data bases which store this information. All project abstracts from this report, as well as many other useful documents, can be accessed, with permission, through our on-line system, ACE. A computer equipped with a modem, or a fax machine is all that is required to connect to ACE. Many features of ACE, including software, hardware, and communications specifics, are explained in this report.

Demons Registration of CT Volume and CBCT Projections for Adaptive Radiotherapy: Avoiding CBCT Reconstruction

DEFF Research Database (Denmark)

Bjerre, Troels; Aznar, M.; Munck af Rosenschöld, P.

2012-01-01

with adaptive fluidity (smoothing kernel width). For forward/back-projection, the separable footprints algorithm with trapezoid functions was applied. The similarity between the simulated and measured projections was measured as the SSD. Results: The figure shows a slice of; the CT volume (reference), the CT...

The International Criticality Safety Benchmark Evaluation Project on the Internet

International Nuclear Information System (INIS)

Briggs, J.B.; Brennan, S.A.; Scott, L.

2000-01-01

The International Criticality Safety Benchmark Evaluation Project (ICSBEP) was initiated in October 1992 by the US Department of Energy's (DOE's) defense programs and is documented in the Transactions of numerous American Nuclear Society and International Criticality Safety Conferences. The work of the ICSBEP is documented as an Organization for Economic Cooperation and Development (OECD) handbook, International Handbook of Evaluated Criticality Safety Benchmark Experiments. The ICSBEP Internet site was established in 1996 and its address is http://icsbep.inel.gov/icsbep. A copy of the ICSBEP home page is shown in Fig. 1. The ICSBEP Internet site contains the five primary links. Internal sublinks to other relevant sites are also provided within the ICSBEP Internet site. A brief description of each of the five primary ICSBEP Internet site links is given

Natural Gas Vehicle Cylinder Safety, Training and Inspection Project

Energy Technology Data Exchange (ETDEWEB)

Hank Seiff

2008-12-31

Under the auspices of the National Energy Technology Laboratory and the US Department of Energy, the Clean Vehicle Education Foundation conducted a three-year program to increase the understanding of the safe and proper use and maintenance of vehicular compressed natural gas (CNG) fuel systems. High-pressure fuel systems require periodic inspection and maintenance to insure safe and proper operation. The project addressed the needs of CNG fuel containers (cylinders) and associated high-pressure fuel system components related to existing law, codes and standards (C&S), available training and inspection programs, and assured coordination among vehicle users, public safety officials, fueling station operators and training providers. The program included a public and industry awareness campaign, establishment and administration of a cylinder inspector certification training scholarship program, evaluation of current safety training and testing practices, monitoring and investigation of CNG vehicle incidents, evaluation of a cylinder recertification program and the migration of CNG vehicle safety knowledge to the nascent hydrogen vehicle community.

Renewable Resources: a national catalog of model projects. Volume 3. Southern Solar Energy Center Region

Energy Technology Data Exchange (ETDEWEB)

None

1980-07-01

This compilation of diverse conservation and renewable energy projects across the United States was prepared through the enthusiastic participation of solar and alternate energy groups from every state and region. Compiled and edited by the Center for Renewable Resources, these projects reflect many levels of innovation and technical expertise. In many cases, a critique analysis is presented of how projects performed and of the institutional conditions associated with their success or failure. Some 2000 projects are included in this compilation; most have worked, some have not. Information about all is presented to aid learning from these experiences. The four volumes in this set are arranged in state sections by geographic region, coinciding with the four Regional Solar Energy Centers. The table of contents is organized by project category so that maximum cross-referencing may be obtained. This volume includes information on the Southern Solar Energy Center Region. (WHK)

Renewable Resources: a national catalog of model projects. Volume 1. Northeast Solar Energy Center Region

Energy Technology Data Exchange (ETDEWEB)

None

1980-07-01

This compilation of diverse conservation and renewable energy projects across the United States was prepared through the enthusiastic participation of solar and alternate energy groups from every state and region. Compiled and edited by the Center for Renewable Resources, these projects reflect many levels of innovation and technical expertise. In many cases, a critique analysis is presented of how projects performed and of the institutional conditions associated with their success or failure. Some 2000 projects are included in this compilation; most have worked, some have not. Information about all is presented to aid learning from these experiences. The four volumes in this set are arranged in state sections by geographic region, coinciding with the four Regional Solar Energy Centers. The table of contents is organized by project category so that maximum cross-referencing may be obtained. This volume includes information on the Northeast Solar Energy Center Region. (WHK).

Renewable Resources: a national catalog of model projects. Volume 4. Western Solar Utilization Network Region

Energy Technology Data Exchange (ETDEWEB)

None

1980-07-01

This compilation of diverse conservation and renewable energy projects across the United States was prepared through the enthusiastic participation of solar and alternate energy groups from every state and region. Compiled and edited by the Center for Renewable Resources, these projects reflect many levels of innovation and technical expertise. In many cases, a critique analysis is presented of how projects performed and of the institutional conditions associated with their success or failure. Some 2000 projects are included in this compilation; most have worked, some have not. Information about all is presented to aid learning from these experiences. The four volumes in this set are arranged in state sections by geographic region, coinciding with the four Regional Solar Energy Centers. The table of contents is organized by project category so that maximum cross-referencing may be obtained. This volume includes information on the Western Solar Utilization Network Region. (WHK)

Activity measurements at a waste volume reduction facility

International Nuclear Information System (INIS)

Richardson, J.; Lee, D.A.

1979-01-01

The monitoring program for Ontario Hydro's radioactive waste management site will be described, several aspects of which will be discussed in detail. The program at this facility includes categorization, volume reduction processing, and storage of solid radioactive wastes from nuclear generating stations of the CANDU type. At the present time, two types of volume reduction process are in operation - incineration and compaction. Following categorization and processing, wastes are stored in in-ground concrete trenches or tile-holes, or in above-ground quadricells. The monitoring program is divided into three areas: public safety, worker safety, and structural integrity. Development projects with respect to the monitoring program have been undertaken to achieve activity accounting for the total waste management program. In particular, a field measurement for the radioactivity content of radioactive ash containers and compacted waste drums

Safety Research Experiment Facility Project. Conceptual design report. Volume VII. Reactor cooling

International Nuclear Information System (INIS)

1975-12-01

The Reactor Cooling System (RCS) will provide the required cooling during test operations of the Safety Research Experiment Facility (SAREF) reactor. The RCS transfers the reactor energy generated in the core to a closed-loop water storage system located completely inside the reactor containment building. After the reactor core has cooled to a safe level, the stored heat is rejected through intermediate heat exchangers to a common forced-draft evaporative cooling tower. The RCS is comprised of three independent cooling loops of which any two can remove sufficient heat from the core to prevent structural damage to the system components

Hanford tank waste operation simulator operational waste volume projection verification and validation procedure

International Nuclear Information System (INIS)

HARMSEN, R.W.

1999-01-01

The Hanford Tank Waste Operation Simulator is tested to determine if it can replace the FORTRAN-based Operational Waste Volume Projection computer simulation that has traditionally served to project double-shell tank utilization. Three Test Cases are used to compare the results of the two simulators; one incorporates the cleanup schedule of the Tri Party Agreement

West Virginia peer exchange : streamlining highway safety improvement program project delivery.

Science.gov (United States)

2015-01-01

The West Virginia Division of Highways (WV DOH) hosted a Peer Exchange to share information and experiences : for streamlining Highway Safety Improvement Program (HSIP) project delivery. The event was held September : 22 to 23, 2014 in Charleston, We...

Probabilistic safety analysis procedures guide. Sections 1-7 and appendices. Volume 1, Revision 1

International Nuclear Information System (INIS)

Bari, R.A.; Buslik, A.J.; Cho, N.Z.

1985-08-01

A procedures guide for the performance of probabilistic safety assessment has been prepared for interim use in the Nuclear Regulatory Commission programs. It will be revised as comments are received, and as experience is gained from its use. The probabilistic safety assessment studies performed are intended to produce probabilistic predictive models that can be used and extended by the utilities and by NRC to sharpen the focus of inquiries into a range of issues affecting reactor safety. This first volume of the guide describes the determination of the probability (per year) of core damage resulting from accident initiators internal to the plant (i.e., intrinsic to plant operation) and from loss of off-site electric power. The scope includes human reliability analysis, a determination of the importance of various core damage accident sequences, and an explicit treatment and display of uncertainties for key accident sequences. The second volume deals with the treatment of the so-called external events including seismic disturbances, fires, floods, etc. Ultimately, the guide will be augmented to include the plant-specific analysis of in-plant processes (i.e., containment performance). This guide provides the structure of a probabilistic safety study to be performed, and indicates what products of the study are valuable for regulatory decision making. For internal events, methodology is treated in the guide only to the extent necessary to indicate the range of methods which is acceptable; ample reference is given to alternative methodologies which may be utilized in the performance of the study. For external events, more explicit guidance is given

Study of Evaluation OSH Management System Policy Based On Safety Culture Dimensions in Construction Project

Science.gov (United States)

Latief, Yusuf; Armyn Machfudiyanto, Rossy; Arifuddin, Rosmariani; Mahendra Fira Setiawan, R.; Yogiswara, Yoko

2017-07-01

Safety Culture in the construction industry is very influential on the socio economic conditions that resulted in the country’s competitiveness. Based on the data, the accident rate of construction projects in Indonesia is very high. In the era of the Asian Economic Community (AEC) Indonesian contractor is required to improve competitiveness, one of which is the implementation of the project without zero accident. Research using primary and secondary data validated the results of the literature experts and questionnaire respondents were analyzed using methods SmartPLS, obtained pattern of relationships between dimensions of safety culture to improve the performance of Safety. The results showed that the behaviors and Cost of Safety into dimensions that significantly affect the performance of safety. an increase in visible policy-based on Regulation of Public Work and Housing No 5/PRT/M/2014 to improve to lower the accident rate.

EC-funded project (HTR-L) for the definition of a European safety approach for HTR's

International Nuclear Information System (INIS)

Ehster, S.; Dominguez, M.T.; Coe, I.; Brinkmann, G.; Lensa, W. von; Mheen, W. van der; Alessandroni, C.; Pirson, J.

2002-01-01

The inherent safety features of the HTRs make events leading to severe core damage highly unlikely and constitute the main differentiating aspects compared to LWRs. While a known and stable regulatory environment has long been established for Light Water Reactors, a different approach is necessary for the licensing of HTR based power plants. Among the R and D projects funded by the European Commission for HTR reactors, the HTR-L project is dedicated to the definition of a common and coherent European safety approach and the identification of the main licensing issues for the licensing framework of the Modular HTRs. Other specific objectives of this project are : To develop a methodology to classify the accidental conditions; To define the preliminary requirements for the confinement of radioactive products and to assess the need for a 'conventional' containment structure; To establish a SSC (2) classification and to define the rules for equipment qualification; To identify the key issues that need to be addressed in the licensing process of the HTRs; To organize a workshop with the concerned Safety Authorities at the end of the project. This paper will explain the project objectives and its final expected outcomes. (author)

Severe accident assessment. Results of the reactor safety research project VAHTI

International Nuclear Information System (INIS)

Sairanen, R.

1997-10-01

The report provides a summary of the publicly funded nuclear reactor safety research project Severe Accident Management (VAHTI). The project has been conducted at the Technical Research Centre of Finland (VTT) during the years 1994-96. The main objective was to assist the severe accident management programmes of the Finnish nuclear power plants. The project was divided into five work packages: (1) thermal hydraulic validation of the APROS code, (2) core melt progression within a BWR pressure vessel, (3) failure mode of the BWR pressure vessel, (4) Aerosol behaviour experiments, and (5) development of a computerized severe accident training tool

Extending Occupational Health and Safety to Urban Street Vendors: Reflections From a Project in Durban, South Africa.

Science.gov (United States)

Alfers, Laura; Xulu, Phumzile; Dobson, Richard; Hariparsad, Sujatha

2016-08-01

This article focuses on an action-research project which is attempting to extend occupational health and safety to a group of street traders in Durban, South Africa, using a variety of different (and sometimes unconventional) institutional actors. The article is written from the perspective of key people who have played a role in conceptualizing and administering the project and is intended to deepen the conversation about what it means to extend occupational health to the informal economy. It explores this question through a reflection on three key project activities: the setting up of a trader-led health and safety committee, an occupational health and safety training course, and a clinical health assessment. It concludes with a discussion of the issues that emerge from the reflections of project participants, which include the need to bring occupational health and urban health into closer conversation with one another, the need to be cognizant of local "informal" politics and the impact that has on occupational health and safety interventions, and the need to create greater opportunities for occupational health and safety professionals to interact with workers in the informal economy. © The Author(s) 2016.

Synthesis of the IRSN report on its analysis of the safety guidance package (DOrS) of the ASTRID reactor project. Safety guidance document for the ASTRID prototype: Referral to the GPR. Opinion related to the safety guidance document of the ASTRID reactor project. ASTRID prototype: Safety guidance document for the ASTRID prototype

International Nuclear Information System (INIS)

Lachaume, Jean-Luc; Niel, Jean-Christophe

2013-01-01

A first document indicates the improvement guidelines for the ASTRID project based on the French experience in the field of sodium-cooled fast neutron reactors, addresses the safety objectives as they are presented for the ASTRID project, discusses how the project includes a regulation and design referential, and how it addresses various aspects of the design approach (ranking and analysis of operation situations, defence in depth, use of probabilistic studies, safety classification and qualification to accidental situations, taking internal and external aggressions into account and taking severe accidents into account at the design level). It comments the guidelines related to the first two barriers, to main safety functions (control of reactivity and of reactor cooling, containment of radioactive and toxic materials), to dismantling, to R and D for safety support. A second document is a letter sent by the ASN to the GPR (permanent group of experts in charge of nuclear reactors) about the safety guidance document for the ASTRID prototype. The third document is the answer and contains comments and recommendations by this group about the content of this document, and therefore addresses the same topics as the first document. The last document defines the framework of the approach to this document

International Handbook of Evaluated Criticality Safety Benchmark Experiments - ICSBEP (DVD), Version 2013

International Nuclear Information System (INIS)

2013-01-01

The Criticality Safety Benchmark Evaluation Project (CSBEP) was initiated in October of 1992 by the United States Department of Energy. The project quickly became an international effort as scientists from other interested countries became involved. The International Criticality Safety Benchmark Evaluation Project (ICSBEP) became an official activity of the Organisation for Economic Co-operation and Development (OECD) Nuclear Energy Agency (NEA) in 1995. This handbook contains criticality safety benchmark specifications that have been derived from experiments performed at various nuclear critical experiment facilities around the world. The benchmark specifications are intended for use by criticality safety engineers to validate calculational techniques used to establish minimum subcritical margins for operations with fissile material and to determine criticality alarm requirement and placement. Many of the specifications are also useful for nuclear data testing. Example calculations are presented; however, these calculations do not constitute a validation of the codes or cross section data. The evaluated criticality safety benchmark data are given in nine volumes. These volumes span nearly 66,000 pages and contain 558 evaluations with benchmark specifications for 4,798 critical, near critical or subcritical configurations, 24 criticality alarm placement/shielding configurations with multiple dose points for each and 200 configurations that have been categorised as fundamental physics measurements that are relevant to criticality safety applications. New to the Handbook are benchmark specifications for Critical, Bare, HEU(93.2)- Metal Sphere experiments referred to as ORSphere that were performed by a team of experimenters at Oak Ridge National Laboratory in the early 1970's. A photograph of this assembly is shown on the front cover

Nuclear Criticality Technology and Safety Project parameter study database

International Nuclear Information System (INIS)

Toffer, H.; Erickson, D.G.; Samuel, T.J.; Pearson, J.S.

1993-03-01

A computerized, knowledge-screened, comprehensive database of the nuclear criticality safety documentation has been assembled as part of the Nuclear Criticality Technology and Safety (NCTS) Project. The database is focused on nuclear criticality parameter studies. The database has been computerized using dBASE III Plus and can be used on a personal computer or a workstation. More than 1300 documents have been reviewed by nuclear criticality specialists over the last 5 years to produce over 800 database entries. Nuclear criticality specialists will be able to access the database and retrieve information about topical parameter studies, authors, and chronology. The database places the accumulated knowledge in the nuclear criticality area over the last 50 years at the fingertips of a criticality analyst

The National Program for Occupational Safety and Health in Agriculture. 1992 Project Facts.

Science.gov (United States)

National Inst. for Occupational Safety and Health (DHHS/PHS), Cincinnati, OH.

This book contains information about a project instituted in 1990 by the National Institute for Occupational Safety and Health (NIOSH) to prevent work-related diseases and injuries among agricultural workers. Included are facts about 25 projects within NIOSH and 42 cooperative agreements between NIOSH and institutions in 25 states. These…

Analysis of Aviation Safety Reporting System Incident Data Associated With the Technical Challenges of the Vehicle Systems Safety Technology Project

Science.gov (United States)

Withrow, Colleen A.; Reveley, Mary S.

2014-01-01

This analysis was conducted to support the Vehicle Systems Safety Technology (VSST) Project of the Aviation Safety Program (AVsP) milestone VSST4.2.1.01, "Identification of VSST-Related Trends." In particular, this is a review of incident data from the NASA Aviation Safety Reporting System (ASRS). The following three VSST-related technical challenges (TCs) were the focus of the incidents searched in the ASRS database: (1) Vechicle health assurance, (2) Effective crew-system interactions and decisions in all conditions; and (3) Aircraft loss of control prevention, mitigation, and recovery.

Compilation of reports of the Advisory Committee on Reactor Safeguards, 1957-1984. Volume 1. Project Reviews A-F

International Nuclear Information System (INIS)

1985-04-01

This six-volume compilation contains over 1000 reports prepared by the Advisory Committee on Reactor Safeguards from September 1957 through December 1984. The reports are divided into two groups: Part 1: ACRS Reports on Project Reviews, and Part 2: ACRS Reports on Generic Subjects. Part 1 contains ACRS reports alphabetized by project name and within project name by chronological order. Part 2 categorizes the reports by the most appropriate generic subject area and within subject area by chronological order. This volume contains project reviews arranged alphabetically from A to F

Project Aquarius. Control of radioisotopes and safety

Energy Technology Data Exchange (ETDEWEB)

Post, Roy G [Department of Nuclear Engineering, University of Arizona (United States)

1970-05-15

The potential application of nuclear explosives to the development of water resources provides real hope for substantial increases in the availability of water from our natural water supplies. A wide range, exploratory project sponsored by the United States Atomic Energy Commission, the Bureau of Reclamation, the Arizona Atomic Energy Commission, and The University of Arizona was conducted by the Hydrology and Water Resources Office, the Department of Nuclear Engineering, and various state and federal governmental agencies in exploring the potential applications of nuclear explosives for developing water resources in the State of Arizona. The primary objective of the project was of a scouting nature, a reconnaissance effort to assess the potential for Arizona. This work, Project Aquarius, is at an early state and any significant conclusions are certainly premature. Since this is a survey, detailed analyses are not justified. Our purpose is to define limiting problems and estimate our ability to solve them. We do not seek to formulate a detailed solution until the project has been defined better. In all of the plowshare activities the primary responsibility of the Atomic Energy Commission for safety and control of not only radiological but all hazards has been well defined and documented. Thus, the work here does not reflect any opinion or voice of the Atomic Energy Commission but is based on my own views and conclusions. I have referred to the work of the various laboratories, offices, and contractors of the Atomic Energy Commission.

Project Aquarius. Control of radioisotopes and safety

International Nuclear Information System (INIS)

Post, Roy G.

1970-01-01

The potential application of nuclear explosives to the development of water resources provides real hope for substantial increases in the availability of water from our natural water supplies. A wide range, exploratory project sponsored by the United States Atomic Energy Commission, the Bureau of Reclamation, the Arizona Atomic Energy Commission, and The University of Arizona was conducted by the Hydrology and Water Resources Office, the Department of Nuclear Engineering, and various state and federal governmental agencies in exploring the potential applications of nuclear explosives for developing water resources in the State of Arizona. The primary objective of the project was of a scouting nature, a reconnaissance effort to assess the potential for Arizona. This work, Project Aquarius, is at an early state and any significant conclusions are certainly premature. Since this is a survey, detailed analyses are not justified. Our purpose is to define limiting problems and estimate our ability to solve them. We do not seek to formulate a detailed solution until the project has been defined better. In all of the plowshare activities the primary responsibility of the Atomic Energy Commission for safety and control of not only radiological but all hazards has been well defined and documented. Thus, the work here does not reflect any opinion or voice of the Atomic Energy Commission but is based on my own views and conclusions. I have referred to the work of the various laboratories, offices, and contractors of the Atomic Energy Commission

GEOSAF Part II. Demonstration of the operational and long-term safety of geological disposal facilities for radioactive waste. IAEA international intercomparison and harmonization project

Energy Technology Data Exchange (ETDEWEB)

Kumano, Yumiko; Bruno, Gerard [International Atomic Energy Agency, Vienna (Austria). Vienna International Centre; Tichauer, Michael [IRSN, Institut de Radioprotection et de Surete Nucleaire, Fontenay-aux-Roses (France); Hedberg, Bengt [Swedish Radiation Safety Authority, Stockholm (Sweden)

2015-07-01

International intercomparison and harmonization projects are one of the mechanisms developed by the IAEA for examining the application and use of safety standards, with a view to ensuring their effectiveness and working towards harmonization of approaches to the safety of radioactive waste management. The IAEA has organized a number of international projects on the safety of radioactive waste management; in particular on the issues related to safety demonstration for radioactive waste management facilities. In 2008, GEOSAF, Demonstration of The Operational and Long-Term Safety of Geological Disposal Facilities for Radioactive Waste, project was initiated. This project was completed in 2011 by delivering a project report focusing on the safety case for geological disposal facilities, a concept that has gained in recent years considerable prominence in the waste management area and is addressed in several international safety standards. During the course of the project, it was recognized that little work was undertaken internationally to develop a common view on the safety approach related to the operational phase of a geological disposal although long-term safety of disposal facility has been discussed for several decades. Upon completion of the first part of the GEOSAF project, it was decided to commence a follow-up project aiming at harmonizing approaches on the safety of geological disposal facilities for radioactive waste through the development of an integrated safety case covering both operational and long-term safety. The new project was named as GEOSAF Part II, which was initiated in 2012 initially as 2-year project, involving regulators and operators. GEOSAF Part II provides a forum to exchange ideas and experience on the development and review of an integrated operational and post-closure safety case for geological disposal facilities. It also aims at providing a platform for knowledge transfer. The project is of particular interest to regulatory

Twenty-third water reactor safety information meeting: Volume 1, plenary session, high burnup fuel behavior, thermal hydraulic research. Proceedings

Energy Technology Data Exchange (ETDEWEB)

Monteleone, S. [comp.] [Brookhaven National Lab., Upton, NY (United States)

1996-03-01

This three-volume report contains papers presented at the Twenty- Third Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, October 23-25, 1995. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from France, Italy, Japan, Norway, Russia, Sweden, and Switzerland. This document, Volume 1, present topics on High Burnup Fuel Behavior, Thermal Hydraulic Research, and Plenary Session topics. Individual papers have been cataloged separately.

Twenty-third water reactor safety information meeting: Volume 1, plenary session, high burnup fuel behavior, thermal hydraulic research. Proceedings

International Nuclear Information System (INIS)

Monteleone, S.

1996-03-01

This three-volume report contains papers presented at the Twenty- Third Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, October 23-25, 1995. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from France, Italy, Japan, Norway, Russia, Sweden, and Switzerland. This document, Volume 1, present topics on High Burnup Fuel Behavior, Thermal Hydraulic Research, and Plenary Session topics. Individual papers have been cataloged separately

Performance assessment and the safety case: Lessons from recent international projects and areas for further development

International Nuclear Information System (INIS)

Galson, Daniel A.; Bailey, Lucy

2014-01-01

The European Commission (EC) PAMINA project - Performance Assessment Methodologies in Application to Guide the Development of the Safety Case - was conducted over the period 2006-2009 and brought together 27 organisations from 10 countries. PAMINA had the aim of improving and developing a common understanding of performance assessment (PA) methodologies for disposal concepts for spent fuel and other long-lived radioactive wastes in a range of geological environments. This was followed by a Nuclear Energy Agency (NEA) sponsored project on Methods for Safety Assessment of Geological Disposal Facilities for Radioactive Waste (MeSA), which was completed in 2012. This paper presents a selection of conclusions from these projects, in the context of general understanding developed on what would constitute an acceptable safety case for a geological disposal facility, and outlines areas for further development. The paper also introduces a new project on PA that is under consideration within the context of the EC Implementing Geological Disposal of Radioactive Waste Technology Platform (IGD-TP). (authors)

THESEUS - a research project to improve the safety standard of tank vehicles for dangerous goods

International Nuclear Information System (INIS)

Guenther, B.

1992-01-01

A research project reffered to as THESEUS was initiated by the Federal Ministry of Research and Technology of Germany. The intent of the investigation is to generate measures designed to enhance the safety standard of commercial transports of dangerous goods in tank vehicles. Hereby, the analysis of real accidents by teams within the project will provide the relevant parameters for the experimental and theoretical investigation of vehicles, tank components and safety devices. The project started in summer 1990. This paper will focus main features and the work done so far. Special consideration will be made to the failure behaviour of tank components as the authors field of activity. (orig.)

77 FR 70684 - Safety Zone; Bridge Demolition Project; Indiana Harbor Canal, East Chicago, IN

Science.gov (United States)

2012-11-27

... environmental risk to health or risk to safety that may disproportionately affect children. 10. Indian Tribal... the Cline Avenue bridge in East Chicago, IN. The Captain of the Port, Sector Lake Michigan, has determined that this demolition project will pose a significant risk to public safety and property. Such...

TIBER II/ETR final design report: Volume 3, 5.0 Radiation safety and environment; 6.0 Physics and technology R and D needs

International Nuclear Information System (INIS)

Lee, J.D.

1987-09-01

This paper discusses the design of the TIBER II Tokamak. This particular volume discusses: safety and environmental requirements and design targets; accident analyses; personnel safety and maintenance exposure; effluent control; waste management and decommissioning; safety considerations in building design; and safety and environmental conclusions and recommendations

Proceedings of the Nuclear Criticality Technology and Safety Project Workshop

Energy Technology Data Exchange (ETDEWEB)

Sanchez, R.G. [comp.

1994-01-01

This report is the proceedings of the annual Nuclear Criticality Technology and Safety Project (NCTSP) Workshop held in Monterey, California, on April 16--28, 1993. The NCTSP was sponsored by the Department of Energy and organized by the Los Alamos Critical Experiments Facility. The report is divided into six sections reflecting the sessions outlined on the workshop agenda.

Proceedings of the Nuclear Criticality Technology and Safety Project Workshop

International Nuclear Information System (INIS)

Sanchez, R.G.

1994-01-01

This report is the proceedings of the annual Nuclear Criticality Technology and Safety Project (NCTSP) Workshop held in Monterey, California, on April 16--28, 1993. The NCTSP was sponsored by the Department of Energy and organized by the Los Alamos Critical Experiments Facility. The report is divided into six sections reflecting the sessions outlined on the workshop agenda

77 FR 63732 - Safety Zone; Bridge Demolition Project; Indiana Harbor Canal, East Chicago, IN

Science.gov (United States)

2012-10-17

..., Protection of Children from Environmental Health Risks and Safety Risks. This rule is not an economically significant rule and does not create an environmental risk to health or risk to safety that may.... The Captain of the Port, Sector Lake Michigan, has determined that this demolition project will pose a...

Surveys of research projects concerning nuclear facility safety, financed by the Federal Ministry for the Environment, Nature Protection and Reactor Safety, 1989. (14. annual report on SR-projects)

International Nuclear Information System (INIS)

1990-11-01

Each progress report is a collection of individual reports, categorized by subject matter. They are a documentation of the contractor's progress, rendered by themselves on standardized forms, published, for the sake of general information on progress made in investigations concerning reactor safety, by the project attendance department of the GRS. The individual reports have serial numbers. Each report includes particulars of the objective, work carried out, results obtained and plans for project continuation. (orig.) [de

Aviation Trends Related to Atmospheric Environment Safety Technologies Project Technical Challenges

Science.gov (United States)

Reveley, Mary S.; Withrow, Colleen A.; Barr, Lawrence C.; Evans, Joni K.; Leone, Karen M.; Jones, Sharon M.

2014-01-01

Current and future aviation safety trends related to the National Aeronautics and Space Administration's Atmospheric Environment Safety Technologies Project's three technical challenges (engine icing characterization and simulation capability; airframe icing simulation and engineering tool capability; and atmospheric hazard sensing and mitigation technology capability) were assessed by examining the National Transportation Safety Board (NTSB) accident database (1989 to 2008), incidents from the Federal Aviation Administration (FAA) accident/incident database (1989 to 2006), and literature from various industry and government sources. The accident and incident data were examined for events involving fixed-wing airplanes operating under Federal Aviation Regulation (FAR) Parts 121, 135, and 91 for atmospheric conditions related to airframe icing, ice-crystal engine icing, turbulence, clear air turbulence, wake vortex, lightning, and low visibility (fog, low ceiling, clouds, precipitation, and low lighting). Five future aviation safety risk areas associated with the three AEST technical challenges were identified after an exhaustive survey of a variety of sources and include: approach and landing accident reduction, icing/ice detection, loss of control in flight, super density operations, and runway safety.

Integrated Safety Management System Phase 1 and 2 Verification for the Environmental Restoration Contractor Volumes 1 and 2

Energy Technology Data Exchange (ETDEWEB)

CARTER, R.P.

2000-04-04

DOE Policy 450.4 mandates that safety be integrated into all aspects of the management and operations of its facilities. The goal of an institutionalized Integrated Safety Management System (ISMS) is to have a single integrated system that includes Environment, Safety, and Health requirements in the work planning and execution processes to ensure the protection of the worker, public, environment, and the federal property over the life cycle of the Environmental Restoration (ER) Project. The purpose of this Environmental Restoration Contractor (ERC) ISMS Phase MI Verification was to determine whether ISMS programs and processes were institutionalized within the ER Project, whether these programs and processes were implemented, and whether the system had promoted the development of a safety conscious work culture.

Renewable Resources: a national catalog of model projects. Volume 2. Mid-American Solar Energy Complex Region

Energy Technology Data Exchange (ETDEWEB)

None

1980-07-01

This compilation of diverse conservation and renewable energy projects across the United States was prepared through the enthusiastic participation of solar and alternate energy groups from every state and region. Compiled and edited by the Center for Renewable Resources, these projects reflect many levels of innovation and technical expertise. In many cases, a critique analysis is presented of how projects performed and of the institutional conditions associated with their success or failure. Some 2000 projects are included in this compilation; most have worked, some have not. Information about all is presented to aid learning from these experiences. The four volumes in this set are arranged in state sections by geographic region, coinciding with the four Regional Solar Energy Centers. The table of contents is organized by project category so that maximum cross-referencing may be obtained. This volume includes information on the Mid-American Solar Energy Complex Region. (WHK)

Solid low-level radioactive waste volume projections at Los Alamos National Laboratory

International Nuclear Information System (INIS)

Art, K.; Minton-Hughes, J.; Peper, C.

1995-01-01

In response to regulatory requirements, the current economic environment, and diminishing on-site low-level radioactive waste (LLW) disposal capacity, LANL needed to develop a system to collect data on future LLW generation that would comply with DOE Order 5820. 2A and be an effective facility planning tool. The LANL Volume Projections Project (VPP) was created to meet these needs. This paper describes objectives, scope, and components of the VPP that will provide information essential to future facility planning and development

Methodology for Safety Assessment Applied to Predisposal Waste Management. Report of the Results of the International Project on Safety Assessment Driving Radioactive Waste Management Solutions (SADRWMS) 2004–2010)

International Nuclear Information System (INIS)

2015-12-01

Report of the Results of the International Project on Safety Assessment Driving Radioactive Waste Management Solutions (SADRWMS) (2004–2010) The IAEA’s progamme on Safety Assessment Driving Radioactive Waste Management Solutions (SADRWMS) focused on approaches and mechanisms for application of safety assessment methodologies for the predisposal management of radioactive waste. The initial outcome of the SADRWMS Project was achieved through the development of flowcharts, which have since been incorporated into IAEA Safety Standards Series No. GSG-3, Safety Case and Safety Assessment for Predisposal Management of Radioactive Waste. In 2005, an initial specification was developed for the Safety Assessment Framework (SAFRAN) software tool to apply the SADRWMS flowcharts. In 2008, an in-depth application of the SAFRAN tool and the SADRWMS methodology was carried out on the predisposal management facilities of the Thailand Institute of Nuclear Technology Radioactive Waste Management Centre (TINT Facility). This publication summarizes the content and outcomes of the SADRWMS programme. The Chairman’s Report of the SADRWMS Project and the Report of the TINT test case are provided on the CD-ROM which accompanies this report

Estimation of the 3D positioning of anatomic structures from radiographic projection and volume knowledge

Energy Technology Data Exchange (ETDEWEB)

Bifulco, P; Cesarelli, M; Roccasalva Firenze, M; Verso, E; Sansone, M; Bracale, M [University of Naples, Federico II, Electronic Engineering Department, Bioengineering Unit, Via Claudio, 21 - 80125 Naples (Italy)

1999-12-31

The aim of this study is to develop a method to estimate the 3D positioning of an anatomic structure using the knowledge of its volume (provided by CT or MRI) combined with a single radiographic projection. This method could be applied in stereotactic surgery or in the study of 3D body joints kinematics. The knowledge of the 3D anatomical structure, available from CT (or in future MRI) is used to estimate the orientation of the projection that better match the actual 2D available projection. For this purpose it was necessary to develop an algorithm to simulate the radiographic projections. The radiographic image formation process has been simulated utilizing the geometrical characteristics of a real radiographic device and the volumetric anatomical data of the patient, obtained by 3D diagnostic CT images. The position of the patient volume respect to the radiological device is estimated comparing the actual radiographic projection with those simulated, maximising a similarity index. To assess the estimation, the 3D positioning of a segmented vertebra has been used as a test volume. The assessment has been carried out only by means of simulation. Estimation errors have been statistically evaluated. Conditions of mispositioning and noise have been also considered. The results relative to the simulation show the feasibility of the method. From the analysis of the errors emerges that the searching procedure results robust respect to the addition of white Gaussian noise. (authors) 13 fers., 4 figs., 1 tabs.

Estimation of the 3D positioning of anatomic structures from radiographic projection and volume knowledge

International Nuclear Information System (INIS)

Bifulco, P.; Cesarelli, M.; Roccasalva Firenze, M.; Verso, E.; Sansone, M.; Bracale, M.

1998-01-01

The aim of this study is to develop a method to estimate the 3D positioning of an anatomic structure using the knowledge of its volume (provided by CT or MRI) combined with a single radiographic projection. This method could be applied in stereotactic surgery or in the study of 3D body joints kinematics. The knowledge of the 3D anatomical structure, available from CT (or in future MRI) is used to estimate the orientation of the projection that better match the actual 2D available projection. For this purpose it was necessary to develop an algorithm to simulate the radiographic projections. The radiographic image formation process has been simulated utilizing the geometrical characteristics of a real radiographic device and the volumetric anatomical data of the patient, obtained by 3D diagnostic CT images. The position of the patient volume respect to the radiological device is estimated comparing the actual radiographic projection with those simulated, maximising a similarity index. To assess the estimation, the 3D positioning of a segmented vertebra has been used as a test volume. The assessment has been carried out only by means of simulation. Estimation errors have been statistically evaluated. Conditions of mispositioning and noise have been also considered. The results relative to the simulation show the feasibility of the method. From the analysis of the errors emerges that the searching procedure results robust respect to the addition of white Gaussian noise. (authors)

Technology, safety and costs of decommissioning a reference small mixed oxide fuel fabrication plant. Volume 2. Appendices

Energy Technology Data Exchange (ETDEWEB)

Jenkins, C. E.; Murphy, E. S.; Schneider, K. J.

1979-01-01

Volume 2 contains appendixes on small MOX fuel fabrication facility description, site description, residual radionuclide inventory estimates, decommissioning, financing, radiation dose methodology, general considerations, packaging and shipping of radioactive materials, cost assessment, and safety (JRD)

Ferrocyanide Safety Project Task 3 Ferrocyanide Aging Studies FY 1993 annual report

International Nuclear Information System (INIS)

Lilga, M.A.; Lumetta, M.R.; Schiefelbein, G.F.

1993-10-01

The Hanford Ferrocyanide Task Team is addressing issues involving ferrocyanide precipitates in single-shell waste storage tanks (SSTs), in particular the storage of waste in a safe manner. This Task Team, composed of researchers from Westinghouse Hanford Company (WHC), Pacific Northwest Laboratory (PNL), and outside consultants, was formed in response to the need for an updated analysis of safety questions about the Hanford ferrocyanide tanks. The Ferrocyanides Safety Project at PNL is part of the Waste Tank Safety Program led by WHC. The overall purpose of the WHC program, sponsored by the US Department of Energy's Tank Farm Project Office, is to (1) maintain the ferrocyanide tanks with minimal risk of an accident, (2) select one or more strategies to assure safe storage, and (3) close out the unreviewed safety question (USQ). This annual report gives the results of the work conducted by PNL in FY 1993 on Task 3, Ferrocyanides Aging Studies, which deals with the aging behavior of simulated ferrocyanide wastes. Aging processes include the dissolution and hydrolysis of nickel ferrocyanides in high pH aqueous solutions. Investigated were the effects of pH variation; ionic strength and sodium ion concentration; the presence of anions such as phosphate, carbonate, and nitrate; temperature; and gamma radiation on solubility of ferrocyanide materials including In-Farm-lA, Rev. 4 flowsheet-prepared Na 2 NiFe(CN) 6

Specific issues, exact locations: case study of a community mapping project to improve safety in a disadvantaged community.

Science.gov (United States)

Qummouh, Rana; Rose, Vanessa; Hall, Pat

2012-12-01

Safety is a health issue and a significant concern in disadvantaged communities. This paper describes an example of community-initiated action to address perceptions of fear and safety in a suburb in south-west Sydney which led to the development of a local, community-driven research project. As a first step in developing community capacity to take action on issues of safety, a joint resident-agency group implemented a community safety mapping project to identify the extent of safety issues in the community and their exact geographical location. Two aerial maps of the suburb, measuring one metre by two metres, were placed on display at different locations for four months. Residents used coloured stickers to identify specific issues and exact locations where crime and safety were a concern. Residents identified 294 specific safety issues in the suburb, 41.9% (n=123) associated with public infrastructure, such as poor lighting and pathways, and 31.9% (n=94) associated with drug-related issues such as drug activity and discarded syringes. Good health promotion practice reflects community need. In a very practical sense, this project responded to community calls for action by mapping resident knowledge on specific safety issues and exact locations and presenting these maps to local decision makers for further action.

Space Biology and Medicine. Volume 4; Health, Performance, and Safety of Space Crews

Science.gov (United States)

Dietlein, Lawrence F. (Editor); Pestov, Igor D. (Editor)

2004-01-01

Volume IV is devoted to examining the medical and associated organizational measures used to maintain the health of space crews and to support their performance before, during, and after space flight. These measures, collectively known as the medical flight support system, are important contributors to the safety and success of space flight. The contributions of space hardware and the spacecraft environment to flight safety and mission success are covered in previous volumes of the Space Biology and Medicine series. In Volume IV, we address means of improving the reliability of people who are required to function in the unfamiliar environment of space flight as well as the importance of those who support the crew. Please note that the extensive collaboration between Russian and American teams for this volume of work resulted in a timeframe of publication longer than originally anticipated. Therefore, new research or insights may have emerged since the authors composed their chapters and references. This volume includes a list of authors' names and addresses should readers seek specifics on new information. At least three groups of factors act to perturb human physiological homeostasis during space flight. All have significant influence on health, psychological, and emotional status, tolerance, and work capacity. The first and most important of these factors is weightlessness, the most specific and radical change in the ambient environment; it causes a variety of functional and structural changes in human physiology. The second group of factors precludes the constraints associated with living in the sealed, confined environment of spacecraft. Although these factors are not unique to space flight, the limitations they entail in terms of an uncomfortable environment can diminish the well-being and performance of crewmembers in space. The third group of factors includes the occupational and social factors associated with the difficult, critical nature of the

The FORO Project on Safety Culture in Organizations, Facilities and Activities With Sources of Ionizing Radiation

International Nuclear Information System (INIS)

Bomben, A. M.; Ferro Fernández, R.; Arciniega Torres, J.; Ordoñez Gutiérrez, E.; Blanes Tabernero, A.; Cruz Suárez, R.; Da Silva Silveira, C.; Perera Meas, J.; Ramírez Quijada, R.; Videla Valdebenito, R.

2016-01-01

The aim of this paper is to present the Ibero-American Forum of Nuclear and Radiological Regulatory Authorities’ (FORO) Project on Safety Culture in organizations, facilities and activities with sources of ionizing radiation developed by experts from the Regulatory Authorities of Argentina, Brazil, Chile, Cuba, Spain, Mexico, Peru and Uruguay, under the scientific coordination of the International Atomic Energy Agency (IAEA). Taking into account that Safety Culture problems have been widely recognised as one of the major contributors to many radiological events, several international and regional initiatives are being carried out to foster and develop a strong Safety Culture. One of these initiatives is the two-year project sponsored by the FORO with the purpose to prepare a document to allow its member states understanding, promoting and achieving a higher level of Safety Culture.

Health and safety impacts of nuclear, geothermal, and fossil-fuel electric generation in California. Volume 1. Health and safety impacts of nuclear, geothermal, and fossil-fuel electric generation in California

International Nuclear Information System (INIS)

Nero, A.V. Jr.

1977-01-01

This report presents an overview of a project on the health and safety impacts of nuclear, geothermal, and fossil-fuel electric generation in California. In addition to presenting an executive summary of the project, it sets forth the main results of the four tasks of the project: to review the health impacts (and related standards) of these forms of power generation, to review the status of standards related to plant safety (with an emphasis on nuclear power), to consider the role of the California Energy Resources Conservation and Development Commission in selection of standards, and to set forth methodologies whereby that Commission may review the health and safety aspects of proposed sites and facilities

Projections for the Production of Bulk Volume Bio-Based Polymers in Europe and Environmental Implications

NARCIS (Netherlands)

Patel, M.K.; Crank, M.

2007-01-01

In this paper we provide an overview of the most important emerging groups of bio-based polymers for bulk volume applications and we discuss market projections for these types of bio-based polymers in the EU, thereby distinguishing between three scenarios. Bio-based polymers are projected to reach a

Surveys of research projects concerning nuclear facility safety, financed by the Bundesminister des Innern. 9th annual report on SR-projects 1984

International Nuclear Information System (INIS)

1985-06-01

The FRG's Ministry of the Interior finances studies, expertises and investigations in the field of nuclear safety. The results of such work are meant to clarify questions left open concerning the execution of licensing procedures for nuclear facilities. The GRS (Reactor Safety Company) regularly provides information on the state of such studies, on the authority of the Ministry of the Interior. Each progress report is a collection of individual reports, categorized by subject matter. They are a documentation of the contractor's progress, rendered by themselves on standardized forms, published, for the sake of general information on progress made in investigations concerning reactor safety, by the project attendance department of the GRS. The individual reports have serial numbers. Each report includes particulars of the objective, work carried out, results obtained and plans for project continuation. (orig./HP) [de

Site Environmental Report for 2004. Volume 1, Environment, Health, and Safety Division

Energy Technology Data Exchange (ETDEWEB)

None

2005-09-30

Each year, Ernest Orlando Lawrence Berkeley National Laboratory prepares an integrated report on its environmental programs to satisfy the requirements of United States Department of Energy Order 231.1A, Environment, Safety, and Health Reporting.1 The Site Environmental Report for 2004 summarizes Berkeley Lab’s environmental management performance, presents environmental monitoring results, and describes significant programs for calendar year 2004. (Throughout this report, Ernest Orlando Lawrence Berkeley National Laboratory is referred to as “Berkeley Lab,” “the Laboratory,” “Lawrence Berkeley National Laboratory,” and “LBNL.”) The report is separated into two volumes. Volume I contains an overview of the Laboratory, the status of environmental programs, and summarized results from surveillance and monitoring activities. Volume II contains individual data results from these activities. This year, the Site Environmental Report was distributed by releasing it on the Web from the Berkeley Lab Environmental Services Group (ESG) home page, which is located at http://www.lbl.gov/ehs/esg/. Many of the documents cited in this report also are accessible from the ESG Web page. CD and printed copies of this Site Environmental Report are available upon request.

Nuclear emergency preparedness. Final report of the Nordic Nuclear Safety Research Project BOK-1

DEFF Research Database (Denmark)

Lauritzen, B.

2002-01-01

Final report of the Nordic Nuclear Safety Research project BOK-1. The BOK-1 project, “Nuclear Emergency Preparedness”, was carried out in 1998-2001 with participants from the Nordic and Baltic Sea regions. The project consists of six sub-projects:Laboratory measurements and quality assurance (BOK-1.......1); Mobile measurements and measurement strategies (BOK-1.2); Field measurements and data assimilation (BOK-1.3); Countermeasures in agriculture and forestry (BOK-1.4); Emergency monitoring in theNordic and Baltic Sea countries (BOK-1.5); and Nuclear exercises (BOK-1.6). For each sub-project, the project...

RISMC Advanced Safety Analysis Project Plan – FY 2015 - FY 2019

Energy Technology Data Exchange (ETDEWEB)

Szilard, Ronaldo H. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Smith, Curtis L. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Youngblood, Robert [Idaho National Lab. (INL), Idaho Falls, ID (United States)

2014-09-01

In this report, a project plan is developed, focused on industry applications, using Risk-Informed Safety Margin Characterization (RISMC) tools and methods applied to realistic, relevant, and current interest issues to the operating nuclear fleet. RISMC focuses on modernization of nuclear power safety analysis (tools, methods and data); implementing state-of-the-art modeling techniques (which include, for example, enabling incorporation of more detailed physics as they become available); taking advantage of modern computing hardware; and combining probabilistic and mechanistic analyses to enable a risk informed safety analysis process. The modernized tools will maintain the current high level of safety in our nuclear power plant fleet, while providing an improved understanding of safety margins and the critical parameters that affect them. Thus, the set of tools will provide information to inform decisions on plant modifications, refurbishments, and surveillance programs, while improving economics. This set of tools will also benefit the design of new reactors, enhancing safety per unit cost of a nuclear plant. The proposed plan will focus on application of the RISMC toolkit, in particular, solving realistic problems of important current issues to the nuclear industry, in collaboration with plant owners and operators to demonstrate the usefulness of these tools in decision making.

Compilation of reports of the Advisory Committee on Reactor Safeguards, 1957-1984. Volume 3. Project Reviews Q-Z

International Nuclear Information System (INIS)

1985-04-01

This six-volume compilation contains over 1000 reports prepared by the Advisory Committee on Reactor Safeguards from September 1957 through December 1984. The reports are divided into two groups: Part 1: ACRS Resports on Project Reviews, and Part 2: ACRS Reports on Generic Subjects. Part 1 contains ACRS reports alphabetized by project name and within project name by chronological order. Part 2 categorizes the reports by the most appropriate generic subject area and within subject area by chronological order. This volume includes reports arranged alpbabetically from Q to Z

Energy Storage Project

Science.gov (United States)

Mercer, Carolyn R.; Jankovsky, Amy L.; Reid, Concha M.; Miller, Thomas B.; Hoberecht, Mark A.

2011-01-01

NASA's Exploration Technology Development Program funded the Energy Storage Project to develop battery and fuel cell technology to meet the expected energy storage needs of the Constellation Program for human exploration. Technology needs were determined by architecture studies and risk assessments conducted by the Constellation Program, focused on a mission for a long-duration lunar outpost. Critical energy storage needs were identified as batteries for EVA suits, surface mobility systems, and a lander ascent stage; fuel cells for the lander and mobility systems; and a regenerative fuel cell for surface power. To address these needs, the Energy Storage Project developed advanced lithium-ion battery technology, targeting cell-level safety and very high specific energy and energy density. Key accomplishments include the development of silicon composite anodes, lithiated-mixed-metal-oxide cathodes, low-flammability electrolytes, and cell-incorporated safety devices that promise to substantially improve battery performance while providing a high level of safety. The project also developed "non-flow-through" proton-exchange-membrane fuel cell stacks. The primary advantage of this technology set is the reduction of ancillary parts in the balance-of-plant--fewer pumps, separators and related components should result in fewer failure modes and hence a higher probability of achieving very reliable operation, and reduced parasitic power losses enable smaller reactant tanks and therefore systems with lower mass and volume. Key accomplishments include the fabrication and testing of several robust, small-scale nonflow-through fuel cell stacks that have demonstrated proof-of-concept. This report summarizes the project s goals, objectives, technical accomplishments, and risk assessments. A bibliography spanning the life of the project is also included.

Ground-water monitoring compliance projects for Hanford Site Facilities: Progress report for the period April 1--June 30, 1988: Volume 1, Text

International Nuclear Information System (INIS)

1988-09-01

This is Volume 1 of a two-volume set of documents that describes the progress of 10 Hanford Site ground-water monitoring projects for the period April 1 to June 30, 1988. This volume discusses the projects; Volume 2 provides as-built diagrams, drilling logs, and geophysical logs for wells drilled during this period in the 100-N Area and near the 216-A-36B Crib

Review of the Norwegian-Russian Cooperation on Safety Projects at Kola and Leningrad Nuclear Power Plants 2005 - 2009

International Nuclear Information System (INIS)

Mattsson, H.; Tishakov, P.

2010-11-01

In this report, Norwegian Radiation Protection Authority (NRPA) has reviewed the Norwegian funded projects on nuclear safety performed in the period 2005-2009 under the Norwegian Action Plan. NRPA has evaluated the progress of eight projects implemented by the Institute for Energy Technology (IFE) at Kola Nuclear Power Plant (KNPP) and Leningrad Nuclear Power Plant (LNPP). NRPA has visited the plants, inspected delivered equipment and discussed the projects implementation with relevant personnel at the plants. One of NRPA findings is that the equipment has been delivered to KNPP and LNPP, it is in regular use by competent personnel, and the equipment contributes to safety of both plants. Furthermore, the cooperation between three main project partners - IFE, LNPP and KNPP, seems to be very productive. NRPA's main conclusion is therefore that the projects have been implemented as described in IFE's project reports and that the goals are met. Furthermore, this report reviews safety levels at the KNPP and LNPP. Safety parameters at the plants indicate that the safety level has been significantly improved since early 1990s when the cooperation between Norway and Russia was initiated. Probabilistic safety assessment (PSA) values and number of INES (International Nuclear Event Scale) events, two internationally acknowledged safety parameters, indicate that the safety level has been much improved since the early 1990s when the cooperation between Norway and Russia started. Although it is clear that the Norwegian-funded projects have contributed positively to this development it is difficult to quantify the contribution. Moreover, the report also reviews the planned life-time of and the decommissioning plans for the reactors at KNPP and LNPP. Construction of new LNPP reactors has started and it is estimated that they will be operational in 2013- 2015. The license of the oldest reactor at LNPP expires in 2018 and if the new reactors are in operation by that time, it is

Using historical crash data as part of traffic work zone safety planning and project management strategies.

Science.gov (United States)

2014-07-01

This funding enabled the project entitled, USING HISTORICAL CRASH DATA AS PART OF TRAFFIC WORK ZONE SAFETY : PLANNING AND PROJECT MANAGEMENT STRATEGIES to address the following: : Evaluate current organizational strategies with respect to w...

From demonstration projects to volume market : Market development for advanced housing renovation

NARCIS (Netherlands)

Mlecnik, E.; Prendergast, E.; Rodsjo, A.; Haavik, T.; Parker, P.

2010-01-01

How do we get from demonstration projects to a volume market for very low energy demand in advanced housing renovation? The contributors to this report have been working with this issue for many years. Some worked in both IEA SHC Task 28 Sustainable Housing (2000-2005) and in SHC Task 37 Advanced

Practical guidelines for the registration and monitoring of serious traffic injuries, Deliverable 7.1 of the H2020 project SafetyCube (Safety CaUsation, Benefits and Efficiency).

NARCIS (Netherlands)

Pérez, K. Weijermars, W.A.M. Amoros, E. Bauer, R. Bos, N. Dupont, E. Filtness, A. Houwing, S. Johannsen, H. Leskovsek, B. Machata, K. Martin, JL. Nuyttens, N. Olabarria, M. Pascal, L. & Van den Berghe, W.

2017-01-01

Safety CaUsation, Benefits and Efficiency (SafetyCube) is a European Commission supported Horizon 2020 project. The project’s main objective is the development of an innovative road safety Decision Support System (DSS) that will enable policy-makers and stakeholders to select and implement the most

Research projects into the safety of nuclear power plants. Period cover 01. January - 30. June 2017. Progress report

International Nuclear Information System (INIS)

2017-01-01

Within its competence for energy research the Federal Ministry for Economic Affairs and Energy (BMWi) sponsors research projects on the safety of nuclear power plants currently in operation. The objective of these projects 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 fur Anlagen- und Reaktorsicherheit (GRS) gGmbH, by order of the BMWi, continuously issues information on the status of such research projects 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 steps of the work etc. The individual reports are prepared in a standard form by the research organisations themselves as documentation of their progress in work. The progress reports are published by the Project Management Agency/ Authority Support Division of GRS. The reports as of the year 2000 are available in the internet-based information system on results and data of reactor safety research (https://www.grs-fbw.de). The compilation of the reports is classified according to the topic areas of reactor safety research. The reports are arranged in sequence of their project numbers. Ilt has to be pointed out that the authors of the reports are responsible for the contents of this compilation. The BMWi does not take any responsibility for the correctness, exactness and completeness of the information nor for the observance of private claims of third parties.

Growth and Expansion of the International Criticality Safety Benchmark Evaluation Project and the Newly Organized International Reactor Physics Experiment Evaluation Project

International Nuclear Information System (INIS)

J. Blair Briggs; Lori Scott; Yolanda Rugama; Enrico Satori

2007-01-01

Since ICNC 2003, the International Criticality Safety Benchmark Evaluation Project (ICSBEP) has continued to expand its efforts and broaden its scope. Criticality-alarm/shielding type benchmarks and fundamental physics measurements that are relevant to criticality safety applications are not only included in the scope of the project, but benchmark data are also included in the latest version of the handbook. A considerable number of improvements have been made to the searchable database, DICE and the criticality-alarm/shielding benchmarks and fundamental physics measurements have been included in the database. There were 12 countries participating on the ICSBEP in 2003. That number has increased to 18 with recent contributions of data and/or resources from Brazil, Czech Republic, Poland, India, Canada, and China. South Africa, Germany, Argentina, and Australia have been invited to participate. Since ICNC 2003, the contents of the ''International Handbook of Evaluated Criticality Safety Benchmark Experiments'' have increased from 350 evaluations (28,000 pages) containing benchmark specifications for 3070 critical or subcritical configurations to 442 evaluations (over 38,000 pages) containing benchmark specifications for 3957 critical or subcritical configurations, 23 criticality-alarm-placement/shielding configurations with multiple dose points for each, and 20 configurations that have been categorized as fundamental physics measurements that are relevant to criticality safety applications in the 2006 Edition of the ICSBEP Handbook. Approximately 30 new evaluations and 250 additional configurations are expected to be added to the 2007 Edition of the Handbook. Since ICNC 2003, a reactor physics counterpart to the ICSBEP, The International Reactor Physics Experiment Evaluation Project (IRPhEP) was initiated. Beginning in 1999, the IRPhEP was conducted as a pilot activity by the by the Organization of Economic Cooperation and Development (OECD) Nuclear Energy Agency

Nuclear emergency preparedness. Final report of the Nordic nuclear safety research project BOK-1

Energy Technology Data Exchange (ETDEWEB)

Lauritzen, Bent [Risoe National Lab., Roskilde (Denmark)

2002-02-01

Final report of the Nordic Nuclear Safety Research project BOK-1. The BOK-1 project, 'Nuclear Emergency Preparedness', was carried out in 1998-2001 with participants from the Nordic and Baltic Sea regions. The project consists of six sub-projects: Laboratory measurements and quality assurance (BOK-1.1); Mobile measurements and measurement strategies (BOK-1.2); Field measurement and data assimilation (BOK-1.3); Countermeasures in agriculture and forestry (BOK-1.4); Emergency monitoring in the Nordic and Baltic Sea countries (BOK-1.5); and Nuclear exercises (BOK-1.6). For each sub-project, the project outline, objectives and organization are described and main results presented. (au)

Nuclear emergency preparedness. Final report of the Nordic nuclear safety research project BOK-1

International Nuclear Information System (INIS)

Lauritzen, Bent

2002-02-01

Final report of the Nordic Nuclear Safety Research project BOK-1. The BOK-1 project, 'Nuclear Emergency Preparedness', was carried out in 1998-2001 with participants from the Nordic and Baltic Sea regions. The project consists of six sub-projects: Laboratory measurements and quality assurance (BOK-1.1); Mobile measurements and measurement strategies (BOK-1.2); Field measurement and data assimilation (BOK-1.3); Countermeasures in agriculture and forestry (BOK-1.4); Emergency monitoring in the Nordic and Baltic Sea countries (BOK-1.5); and Nuclear exercises (BOK-1.6). For each sub-project, the project outline, objectives and organization are described and main results presented. (au)

ASEAN--USAID Buildings Energy Conservation Project final report. Volume 2, Technology

Energy Technology Data Exchange (ETDEWEB)

Levine, M.D.; Busch, J.F. [eds.

1992-06-01

This volume reports on research in the area of energy conservation technology applied to commercial buildings in the Association of Southeast Asian Nations (ASEAN) region. Unlike Volume I of this series, this volume is a compilation of original technical papers prepared by different authors in the project. In this regard, this volume is much like a technical journal. The papers that follow report on research conducted by both US and ASEAN researchers. The authors representing Indonesia, Malaysia, Philippines, and Thailand, come from a range of positions in the energy arena, including government energy agencies, electric utilities, and universities. As such, they account for a wide range of perspectives on energy problems and the role that technology can play in solving them. This volume is about using energy more intelligently. In some cases, the effort is towards the use of more advanced technologies, such as low-emittance coatings on window glass, thermal energy storage, or cogeneration. In others, the emphasis is towards reclaiming traditional techniques for rendering energy services, but in new contexts such as lighting office buildings with natural light, or cooling buildings of all types with natural ventilation. Used in its broadest sense, the term ``technology`` encompasses all of the topics addressed in this volume. Along with the more customary associations of technology, such as advanced materials and equipment and the analysis of their performance, this volume treats design concepts and techniques, analysis of ``secondary`` impacts from applying technologies (i.e., unintended impacts, or impacts on parties not directly involved in the purchase and use of the technology), and the collection of primary data used for conducting technical analyses.

GROWTH OF THE INTERNATIONAL CRITICALITY SAFETY AND REACTOR PHYSICS EXPERIMENT EVALUATION PROJECTS

Energy Technology Data Exchange (ETDEWEB)

J. Blair Briggs; John D. Bess; Jim Gulliford

2011-09-01

Since the International Conference on Nuclear Criticality Safety (ICNC) 2007, the International Criticality Safety Benchmark Evaluation Project (ICSBEP) and the International Reactor Physics Experiment Evaluation Project (IRPhEP) have continued to expand their efforts and broaden their scope. Eighteen countries participated on the ICSBEP in 2007. Now, there are 20, with recent contributions from Sweden and Argentina. The IRPhEP has also expanded from eight contributing countries in 2007 to 16 in 2011. Since ICNC 2007, the contents of the 'International Handbook of Evaluated Criticality Safety Benchmark Experiments1' have increased from 442 evaluations (38000 pages), containing benchmark specifications for 3955 critical or subcritical configurations to 516 evaluations (nearly 55000 pages), containing benchmark specifications for 4405 critical or subcritical configurations in the 2010 Edition of the ICSBEP Handbook. The contents of the Handbook have also increased from 21 to 24 criticality-alarm-placement/shielding configurations with multiple dose points for each, and from 20 to 200 configurations categorized as fundamental physics measurements relevant to criticality safety applications. Approximately 25 new evaluations and 150 additional configurations are expected to be added to the 2011 edition of the Handbook. Since ICNC 2007, the contents of the 'International Handbook of Evaluated Reactor Physics Benchmark Experiments2' have increased from 16 different experimental series that were performed at 12 different reactor facilities to 53 experimental series that were performed at 30 different reactor facilities in the 2011 edition of the Handbook. Considerable effort has also been made to improve the functionality of the searchable database, DICE (Database for the International Criticality Benchmark Evaluation Project) and verify the accuracy of the data contained therein. DICE will be discussed in separate papers at ICNC 2011. The status of the

Reports on BMBF-sponsored research projects in the field of reactor safety. Reporting period 1 July - 31 December 1995

International Nuclear Information System (INIS)

1996-01-01

The Gesellschaft fuer Anlagen- und Reaktorsicherheit informs of the status of LWR tasks and projects on the safety of advanced reactors. Each progress report represents a compilation of individual reports about objectives, the work performed, the results, and the next steps of the works. The individual reports of quality assurance, safety of reactor component, emergency core cooling, lors of coolant, meltdown, fission product release, risk and reliability, are classified according to projects to the reactor safety research program. Another table uses the same classification system as applied in the nuclear safety index of the CEC. (DG)

Breckinridge Project, initial effort. Report III, Volume 2. Specifications

Energy Technology Data Exchange (ETDEWEB)

None

1982-01-01

Report III, Volume 2 contains those specifications numbered K through Y, as follows: Specifications for Compressors (K); Specifications for Piping (L); Specifications for Structures (M); Specifications for Insulation (N); Specifications for Electrical (P); Specifications for Concrete (Q); Specifications for Civil (S); Specifications for Welding (W); Specifications for Painting (X); and Specifications for Special (Y). The standard specifications of Bechtel Petroleum Incorporated have been amended as necessary to reflect the specific requirements of the Breckinridge Project and the more stringent specifications of Ashland Synthetic Fuels, Inc. These standard specifications are available for the Initial Effort (Phase Zero) work performed by all contractors and subcontractors.

Slope excavation quality assessment and excavated volume calculation in hydraulic projects based on laser scanning technology

Directory of Open Access Journals (Sweden)

Chao Hu

2015-04-01

Full Text Available Slope excavation is one of the most crucial steps in the construction of a hydraulic project. Excavation project quality assessment and excavated volume calculation are critical in construction management. The positioning of excavation projects using traditional instruments is inefficient and may cause error. To improve the efficiency and precision of calculation and assessment, three-dimensional laser scanning technology was used for slope excavation quality assessment. An efficient data acquisition, processing, and management workflow was presented in this study. Based on the quality control indices, including the average gradient, slope toe elevation, and overbreak and underbreak, cross-sectional quality assessment and holistic quality assessment methods were proposed to assess the slope excavation quality with laser-scanned data. An algorithm was also presented to calculate the excavated volume with laser-scanned data. A field application and a laboratory experiment were carried out to verify the feasibility of these methods for excavation quality assessment and excavated volume calculation. The results show that the quality assessment indices can be obtained rapidly and accurately with design parameters and scanned data, and the results of holistic quality assessment are consistent with those of cross-sectional quality assessment. In addition, the time consumption in excavation quality assessment with the laser scanning technology can be reduced by 70%–90%, as compared with the traditional method. The excavated volume calculated with the scanned data only slightly differs from measured data, demonstrating the applicability of the excavated volume calculation method presented in this study.

Analysis of Aviation Safety Reporting System Incident Data Associated with the Technical Challenges of the System-Wide Safety and Assurance Technologies Project

Science.gov (United States)

Withrow, Colleen A.; Reveley, Mary S.

2015-01-01

The Aviation Safety Program (AvSP) System-Wide Safety and Assurance Technologies (SSAT) Project asked the AvSP Systems and Portfolio Analysis Team to identify SSAT-related trends. SSAT had four technical challenges: advance safety assurance to enable deployment of NextGen systems; automated discovery of precursors to aviation safety incidents; increasing safety of human-automation interaction by incorporating human performance, and prognostic algorithm design for safety assurance. This report reviews incident data from the NASA Aviation Safety Reporting System (ASRS) for system-component-failure- or-malfunction- (SCFM-) related and human-factor-related incidents for commercial or cargo air carriers (Part 121), commuter airlines (Part 135), and general aviation (Part 91). The data was analyzed by Federal Aviation Regulations (FAR) part, phase of flight, SCFM category, human factor category, and a variety of anomalies and results. There were 38 894 SCFM-related incidents and 83 478 human-factorrelated incidents analyzed between January 1993 and April 2011.

Proceedings of the US Nuclear Regulatory Commission fifteenth water reactor safety information meeting: Volume 6, Decontamination and decommissioning, accident management, TMI-2

International Nuclear Information System (INIS)

Weiss, A.J.

1988-02-01

This six-volume report contains 140 papers out of the 164 that were presented at the Fifteenth Water Reactor Safety Information Meeting held at the National Bureau of Standards, Gaithersburg, Maryland, during the week of October 26-29, 1987. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. This report, Volume 6, discusses decontamination and decommissioning, accident management, and the Three Mile Island-2 reactor accident. Thirteen reports have been cataloged separately

Nuclear criticality safety experiments, calculations, and analyses - 1958 to 1982. Volume 2. Summaries. Complilation of papers from the Transactions of the American Nuclear Society

International Nuclear Information System (INIS)

Koponen, B.L.; Hampel, V.E.

1982-01-01

This compilation contains 688 complete summaries of papers on nuclear criticality safety as presented at meetings of the American Nuclear Society (ANS). The selected papers contain criticality parameters for fissile materials derived from experiments and calculations, as well as criticality safety analyses for fissile material processing, transport, and storage. The compilation was developed as a component of the Nuclear Criticality Information System (NCIS) now under development at the Lawrence Livermore National Laboratory. The compilation is presented in two volumes: Volume 1 contains a directory to the ANS Transaction volume and page number where each summary was originally published, the author concordance, and the subject concordance derived from the keyphrases in titles. Volume 2 contains-in chronological order-the full-text summaries, reproduced here by permission of the American Nuclear Society from their Transactions, volumes 1-41

Nuclear criticality safety experiments, calculations, and analyses - 1958 to 1982. Volume 2. Summaries. Complilation of papers from the Transactions of the American Nuclear Society

Energy Technology Data Exchange (ETDEWEB)

Koponen, B.L.; Hampel, V.E.

1982-10-21

This compilation contains 688 complete summaries of papers on nuclear criticality safety as presented at meetings of the American Nuclear Society (ANS). The selected papers contain criticality parameters for fissile materials derived from experiments and calculations, as well as criticality safety analyses for fissile material processing, transport, and storage. The compilation was developed as a component of the Nuclear Criticality Information System (NCIS) now under development at the Lawrence Livermore National Laboratory. The compilation is presented in two volumes: Volume 1 contains a directory to the ANS Transaction volume and page number where each summary was originally published, the author concordance, and the subject concordance derived from the keyphrases in titles. Volume 2 contains-in chronological order-the full-text summaries, reproduced here by permission of the American Nuclear Society from their Transactions, volumes 1-41.

Safety assessment methodologies and their application in development of near surface waste disposal facilities - the ASAM project

International Nuclear Information System (INIS)

Metcalf, P.

2003-01-01

The scope of ASAM project covers near surface disposal facilities for all types of low and intermediate level wastes with emphasis of the post-closure safety assessment.The objectives are to explore practical application to a range of disposal facilities for a number of purposes e.g. development of design concepts, safety re-assessment, upgrading safety and to develop practical approaches to assist regulators, operators and other experts in review of safety assessment. The task of the Co-ordination Group are: reassessment of existing facilities - use of safety assessment in decision making on selection of options (volunteer site Hungary); disused sealed sources - evaluation of disposability of disused sealed sources in near surface facilities (volunteer site Saratov, Russia); mining and minerals processing waste - evaluation of long-term safety (volunteer site pmc S. Africa). An agreement on the scope and objectives of the project are reached and the further consideration, such as human intrusion/institutional control/security; waste from oil/gas industry; very low level waste; categorization of sealed sources coordinated with other IAEA activities are outlined

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

International Nuclear Information System (INIS)

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

2002-01-01

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

Geo-scientific Information in the Radioactive Waste Management Safety Case Main Messages from the AMIGO Project

International Nuclear Information System (INIS)

2010-01-01

Radioactive waste is associated with all phases of the nuclear fuel cycle as well as the use of radioactive materials in medicine, research and industry. For the most hazardous and long-lived waste, the solution being investigated worldwide is disposal in engineered repositories deep underground. The importance of geo-scientific information in selecting a site for geological disposal has long been recognised, but there has been growing acknowledgement of the broader role of this information in assessing and documenting the safety of disposal. The OECD/NEA Approaches and Methods for Integrating Geological Information in the Safety Case (AMIGO) project has demonstrated that geological data and understanding serve numerous roles in safety cases. The project, which ran from 2002 to 2008, underscored the importance of integrating geo-scientific information in the development of a disposal safety case and increasingly in the overall process of repository development, including, for example, siting decisions and ensuring the practical feasibility of repository layout and engineering. (authors)

Savannah River Plant engineering, design, and construction history of ``S`` projects and other work, January 1961--December 1964. Volume 2

Energy Technology Data Exchange (ETDEWEB)

1970-03-01

The work described in this volume of ``S`` Projects History is an extension of the type of work described in Volume I. E.I. du Pont de flemours & Company had entered into Contract AT (07-2)-l with the United States Atomic Energy Commission to develop, design, construct, install, and operate facilities to produce heavy water, fissionable materials, and related products. Under this contract,, Du Pont constructed and operated the Savannah River Plant. The engineering, design, and construction for most of the larger ``S`` projects was performed by the Engineering DeDartment. For some of the large and many of the smaller projects the Engineering Department was responsible only for the construction because the Atomic Energy Division (AED) of the Explosives Department handled the other phases. The Engineering Department Costruction Division also performed the physical work for many of the plant work orders. This volume includes a general description of the Du Pont Engineering Department activities pertaining to the engineering, design, and construction of the ``S`` projects at the Savannah River Plant; brief summaries of the projects and principal work requests; and supplementary informaticn on a few subjects in Volume I for which final data was not available at the closing date. Projects and other plant engineering work which were handled entirely by the Explosives Department -- AED are not included in this history.

Final report of the 'Nordic thermal-hydraulic and safety network (NOTNET)' - Project

International Nuclear Information System (INIS)

Tuunanen, J.; Tuomainen, M.

2005-04-01

A Nordic network for thermal-hydraulics and nuclear safety research was started. The idea of the network is to combine the resources of different research teams in order to carry out more ambitious and extensive research programs than would be possible for the individual teams. From the very beginning, the end users of the research results have been integrated to the network. Aim of the network is to benefit the partners involved in nuclear energy in the Nordic Countries (power companies, reactor vendors, safety regulators, research units). First task within the project was to describe the resources (personnel, know-how, simulation tools, test facilities) of the various teams. Next step was to discuss with the end users about their research needs. Based on these steps, few most important research topics with defined goals were selected, and coarse road maps were prepared for reaching the targets. These road maps will be used as a starting point for planning the actual research projects in the future. The organisation and work plan for the network were established. National coordinators were appointed, as well as contact persons in each participating organisation, whether research unit or end user. This organisation scheme is valid for the short-term operation of NOTNET when only Nordic organisations take part in the work. Later on, it is possible to enlarge the network e.g. within EC framework programme. The network can now start preparing project proposals and searching funding for the first common research projects. (au)

OREDA offshore and onshore reliability data volume 1 - topside equipment

CERN Document Server

OREDA

2015-01-01

This handbook presents high quality reliability data for offshore equipment collected during phase VI to IX (project period 2000 – 2009) of the OREDA project. The intention of the handbook is to provide both quantitative and qualitative information as a basis for Performance Forecasting or RAMS (Reliability, Availability, Maintainability and Safety) analyses. Volume 1 is about Topside Equipment. Compared to earlier editions, there are only minor changes in the reliability data presentation. To obtain a reasonable population for presenting reliability data for topside equipment in the 2015 edition, some data from phases VI and VII already issued in the previous 2009 handbook (5th edition) have also been included. The 2015 topside volume is divided into two parts. Part I describes the OREDA project, different data collection phases and the estimation procedures used to generate the data tables presented in Part II of the handbook. Topside data are in general not covering the whole lifetime of equipment, but ...

State partnership in environmental health and safety phase of Plowshare projects

Energy Technology Data Exchange (ETDEWEB)

Kinsman, S [California State Department of Public Health, Berkeley, CA (United States)

1969-07-01

When experiments on projects involving Plowshare devices are conceived, the state chosen for the project should be invited to participate in planning the health and safety aspects and be prepared to actively participate in the D-Day phase as well as the post-detonation activity. In California nuclear science technology and competence have preceded the social acceptance and use of nuclear devices for large scale Plowshare projects. However, the environmental surveillance program of the Bureau of Radiological Health in the State Department of Public Health has established an operative program which will be ready and able to function as an active participant or in a support role in environmental health phases of nuclear projects scheduled in the State. A description of our present program will be included in this paper. This will enable the attendees and readers to realize capabilities which will be activated for participation and/or support roles during Plowshare activities in the State or in a neighboring state if the need arises. (author)

State partnership in environmental health and safety phase of Plowshare projects

International Nuclear Information System (INIS)

Kinsman, S.

1969-01-01

When experiments on projects involving Plowshare devices are conceived, the state chosen for the project should be invited to participate in planning the health and safety aspects and be prepared to actively participate in the D-Day phase as well as the post-detonation activity. In California nuclear science technology and competence have preceded the social acceptance and use of nuclear devices for large scale Plowshare projects. However, the environmental surveillance program of the Bureau of Radiological Health in the State Department of Public Health has established an operative program which will be ready and able to function as an active participant or in a support role in environmental health phases of nuclear projects scheduled in the State. A description of our present program will be included in this paper. This will enable the attendees and readers to realize capabilities which will be activated for participation and/or support roles during Plowshare activities in the State or in a neighboring state if the need arises. (author)

Growth and Expansion of the International Criticality Safety Benchmark Evaluation Project and the Newly Organized International Reactor Physics Experiment Evaluation Project

Energy Technology Data Exchange (ETDEWEB)

J. Blair Briggs; Lori Scott; Yolanda Rugama; Enrico Satori

2007-05-01

Since ICNC 2003, the International Criticality Safety Benchmark Evaluation Project (ICSBEP) has continued to expand its efforts and broaden its scope. Criticality-alarm / shielding type benchmarks and fundamental physics measurements that are relevant to criticality safety applications are not only included in the scope of the project, but benchmark data are also included in the latest version of the handbook. A considerable number of improvements have been made to the searchable database, DICE and the criticality-alarm / shielding benchmarks and fundamental physics measurements have been included in the database. There were 12 countries participating on the ICSBEP in 2003. That number has increased to 18 with recent contributions of data and/or resources from Brazil, Czech Republic, Poland, India, Canada, and China. South Africa, Germany, Argentina, and Australia have been invited to participate. Since ICNC 2003, the contents of the “International Handbook of Evaluated Criticality Safety Benchmark Experiments” have increased from 350 evaluations (28,000 pages) containing benchmark specifications for 3070 critical or subcritical configurations to 442 evaluations (over 38,000 pages) containing benchmark specifications for 3957 critical or subcritical configurations, 23 criticality-alarm-placement / shielding configurations with multiple dose points for each, and 20 configurations that have been categorized as fundamental physics measurements that are relevant to criticality safety applications in the 2006 Edition of the ICSBEP Handbook. Approximately 30 new evaluations and 250 additional configurations are expected to be added to the 2007 Edition of the Handbook. Since ICNC 2003, a reactor physics counterpart to the ICSBEP, The International Reactor Physics Experiment Evaluation Project (IRPhEP) was initiated. Beginning in 1999, the IRPhEP was conducted as a pilot activity by the by the Organization of Economic Cooperation and Development (OECD) Nuclear Energy

Flat-plate solar array project. Volume 6: Engineering sciences and reliability

Science.gov (United States)

Ross, R. G., Jr.; Smokler, M. I.

1986-01-01

The Flat-Plate Solar Array (FSA) Project activities directed at developing the engineering technology base required to achieve modules that meet the functional, safety, and reliability requirements of large scale terrestrial photovoltaic systems applications are reported. These activities included: (1) development of functional, safety, and reliability requirements for such applications; (2) development of the engineering analytical approaches, test techniques, and design solutions required to meet the requirements; (3) synthesis and procurement of candidate designs for test and evaluation; and (4) performance of extensive testing, evaluation, and failure analysis of define design shortfalls and, thus, areas requiring additional research and development. A summary of the approach and technical outcome of these activities are provided along with a complete bibliography of the published documentation covering the detailed accomplishments and technologies developed.

The NPPR Trnava participation in the NPP V-2 modernisation and safety improvement project

International Nuclear Information System (INIS)

Michal, V.; Losonsky, B.; Magdolen, J.

1999-01-01

The presented contribution deals with form, present state and results of Nuclear Power Plants Research Inst.e participation in the NPP V-2 Jaslovske Bohunice Modernization and Safety Improvement Project.(author)

Management response plan for the Chemical Safety Vulnerability Working Group report. Volume 1

International Nuclear Information System (INIS)

1994-09-01

The Chemical Safety Vulnerability (CSV) Working Group was established to identify adverse conditions involving hazardous chemicals at DOE facilities that might result in fires or explosions, release of hazardous chemicals to the environment, or exposure of workers or the public to chemicals. A CSV Review was conducted in 146 facilities at 29 sites. Eight generic vulnerabilities were documented related to: abandoned chemicals and chemical residuals; past chemical spills and ground releases; characterization of legacy chemicals and wastes; disposition of legacy chemicals; storage facilities and conditions; condition of facilities and support systems; unanalyzed and unaddressed hazards; and inventory control and tracking. Weaknesses in five programmatic areas were also identified related to: management commitment and planning; chemical safety management programs; aging facilities that continue to operate; nonoperating facilities awaiting deactivation; and resource allocations. Volume 1 contains a discussion of the chemical safety improvements planned or already underway at DOE sites to correct facility or site-specific vulnerabilities. The main part of the report is a discussion of each of the programmatic deficiencies; a description of the tasks to be accomplished; the specific actions to be taken; and the organizational responsibilities for implementation

Proceedings of the twenty-fourth water reactor safety information meeting. Volume 1: Plenary session; High burnup fuel; Containment and structural aging

International Nuclear Information System (INIS)

Monteleone, S.

1997-01-01

This three-volume report contains papers presented at the Twenty-Fourth Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, maryland, October 21--23, 1996. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from Czech Republic, Finland, France, Japan, Norway, Russia and United Kingdom. This first volume is divided into 3 sections: plenary session; high burnup fuel; and containment and structural aging. Selected papers are indexed separately for inclusion in the Energy Science and Technology Database

Proceedings of the twenty-fourth water reactor safety information meeting. Volume 1: Plenary session; High burnup fuel; Containment and structural aging

Energy Technology Data Exchange (ETDEWEB)

Monteleone, S. [comp.] [Brookhaven National Lab., Upton, NY (United States)

1997-01-01

This three-volume report contains papers presented at the Twenty-Fourth Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, maryland, October 21--23, 1996. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from Czech Republic, Finland, France, Japan, Norway, Russia and United Kingdom. This first volume is divided into 3 sections: plenary session; high burnup fuel; and containment and structural aging. Selected papers are indexed separately for inclusion in the Energy Science and Technology Database.

International handbook of evaluated criticality safety benchmark experiments

International Nuclear Information System (INIS)

2010-01-01

The Criticality Safety Benchmark Evaluation Project (CSBEP) was initiated in October of 1992 by the United States Department of Energy. The project quickly became an international effort as scientists from other interested countries became involved. The International Criticality Safety Benchmark Evaluation Project (ICSBEP) became an official activity of the Organization for Economic Cooperation and Development - Nuclear Energy Agency (OECD-NEA) in 1995. This handbook contains criticality safety benchmark specifications that have been derived from experiments performed at various nuclear critical facilities around the world. The benchmark specifications are intended for use by criticality safety engineers to validate calculational techniques used to establish minimum subcritical margins for operations with fissile material and to determine criticality alarm requirement and placement. Many of the specifications are also useful for nuclear data testing. Example calculations are presented; however, these calculations do not constitute a validation of the codes or cross section data. The evaluated criticality safety benchmark data are given in nine volumes. These volumes span over 55,000 pages and contain 516 evaluations with benchmark specifications for 4,405 critical, near critical, or subcritical configurations, 24 criticality alarm placement / shielding configurations with multiple dose points for each, and 200 configurations that have been categorized as fundamental physics measurements that are relevant to criticality safety applications. Experiments that are found unacceptable for use as criticality safety benchmark experiments are discussed in these evaluations; however, benchmark specifications are not derived for such experiments (in some cases models are provided in an appendix). Approximately 770 experimental configurations are categorized as unacceptable for use as criticality safety benchmark experiments. Additional evaluations are in progress and will be

The application of integrated safety management principles to the Tritium Extraction Facility project

International Nuclear Information System (INIS)

Hickman, M.O.; Viviano, R.R.

2000-01-01

The DOE has developed a program that is accomplishing a heightened safety posture across the complex. The Integrated Safety Management (ISM) System (ISMS) program utilizes five core functions and seven guiding principles as the basis for implementation. The core functions define the work scope, analyze the hazards, develop and implement hazard controls, perform the work, and provide feedback for improvement. The guiding principles include line management responsibility, clear roles and responsibilities, competence per responsibilities, identification of safety standards/requirements, tailored hazard control, balanced priorities, and operations authorization. There exists an unspecified eighth principle, that is, worker involvement. A program requiring the direct involvement of the employees who are actually performing the work has been shown to be quite an effective method of communicating safety requirements, controlling work in a safe manner, and reducing safety violations and injuries. The Tritium Extraction Facility (TEF) projects, a component of the DOE's Commercial Light Water Reactor Tritium Production program, has taken the ISM principles and core functions and applied them to the project's design. The task of the design team is to design a facility and systems that will meet the production requirements of the DOE tritium mission as well as a design that minimizes the workers' exposure to adverse safety situations and hazards/hazardous materials. During the development of the preliminary design for the TEF, design teams consisted of not only designers but also personnel who had operational experience in the existing tritium and personnel who had operational experience in the existing tritium and personnel who had specialized experience from across the DOE complex. This design team reviewed multiple documents associated with the TEF operation in order to identify and document the hazards associated with the tritium process. These documents include hazards

Technical Assistance in Evaluating Career Education Projects. Final Report. Volume II: Final Career Education Evaluation Report.

Science.gov (United States)

Stenner, A. Jackson; And Others

This document contains the second of five volumes reporting the activities and results of a career education evaluation project conducted to accomplish the following two objectives: (1) to improve the quality of evaluations by career education projects funded by the United States Office of Career Education (OCE) through the provision of technical…

Occupational Safety and Health Program at the West Valley Demonstration Project

International Nuclear Information System (INIS)

L. M. Calderon

1999-01-01

The West Valley Nuclear Services Co. LLC (WVNS) is committed to provide a safe, clean, working environment for employees, and to implement U.S. Department of Energy (DOE) requirements affecting worker safety. The West Valley Demonstration Project (WVDP) Occupational Safety and Health Program is designed to protect the safety, health, and well-being of WVDP employees by identifying, evaluating, and controlling biological, chemical, and physical hazards in the work place. Hazards are controlled within the requirements set forth in the reference section at the end of this report. It is the intent of the WVDP Occupational Safety and Health Program to assure that each employee is provided with a safe and healthy work environment. This report shows the logical path toward ensuring employee safety in planning work at the WVDP. In general, planning work to be performed safely includes: combining requirements from specific programs such as occupational safety, industrial hygiene, radiological control, nuclear safety, fire safety, environmental protection, etc.; including WVDP employees in the safety decision-making processes; pre-planning using safety support re-sources; and integrating the safety processes into the work instructions. Safety management principles help to define the path forward for the WVDP Occupational Safety and Health Program. Roles, responsibilities, and authority of personnel stem from these ideals. WVNS and its subcontractors are guided by the following fundamental safety management principles: ''Protection of the environment, workers, and the public is the highest priority. The safety and well-being of our employees, the public, and the environment must never be compromised in the aggressive pursuit of results and accomplishment of work product. A graded approach to environment, safety, and health in design, construction, operation, maintenance, and deactivation is incorporated to ensure the protection of the workers, the public, and the environment

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

International Nuclear Information System (INIS)

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

2002-01-01

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

An integrated framework for cost- benefit analysis in road safety projects using AHP method

Directory of Open Access Journals (Sweden)

Mahsa Mohamadian

2011-10-01

Full Text Available Cost benefit analysis (CBA is a useful tool for investment decision-making from economic point of view. When the decision involves conflicting goals, the multi-attribute analysis approach is more capable; because there are some social and environmental criteria that cannot be valued or monetized by cost benefit analysis. The complex nature of decision-making in road safety normally makes it difficult to reach a single alternative solution that can satisfy all decision-making problems. Generally, the application of multi-attribute analysis in road sector is promising; however, the applications are in preliminary stage. Some multi-attribute analysis techniques, such as analytic hierarchy process (AHP have been widely used in practice. This paper presents an integrated framework with CBA and AHP methods to select proper alternative in road safety projects. The proposed model of this paper is implemented for a case study of improving a road to reduce the accidents in Iran. The framework is used as an aid to cost benefit tool in road safety projects.

On integration and innovation of sino-foreign safety culture in Haiyang AP1000 Project

International Nuclear Information System (INIS)

Li Ruipu; Song Fengwei

2010-01-01

The undergoing Haiyang Nuclear Power Plant is not only introducing the top-advanced AP1000 nuclear technology, but also the mature HSE management system from U.S.A. It's very important for both sides to communicate, comprehend and acculturation of both different culture. After over 1 year discussion and practice, the experts of Westinghouse Consortium and Chinese HSE engineers have established an distinctive safety culture of AP1000 Project initially, demonstrating the followings: Exemplary actions of the expat experts and the SNPTC leaders, the high level standard HSE procedures, HSE audit, various training, HSE inspection all-around, the safety performance assessment for prospective index, JHA/JSA , emergency system, humanism rewards and punishment etc.. Haiyang SPMO has made Three-Step master plan for AP1000 project HSE Routine by analysis the site problems and the difference between Chinese and American, that is, from 2008 to 2020, when nuclear power achieve to independent, safety culture of Haiyang AP1000 will change from 'dependent' to 'independent', until the last 'interdependent'. (authors)

Nuclear proliferation and civilian nuclear power. Report of the Nonproliferation Alternative Systems Assessment Program. Volume VI. Safety and environmental considerations for licensing

International Nuclear Information System (INIS)

1980-06-01

This volume of the Nonproliferation Alternative Systems Assessment Program report addresses safety and environmental considerations in licensing the principal alternative nuclear reactors and fuel cycles in the United States for large-scale commercial nuclear power plants. In addition, this volume examines the safety and environmental considerations for licensing fuel service centers. These centers, which have been proposed for controlling sensitive fuel-cycle facilities and special nuclear materials, would contain a combination of such facilities as reprocessing plants, fabrication plants, and reactors. For this analysis, two fuel service center concepts were selected - one with power - generating capability and one without

Alligator Rivers Analogue Project. Final Report - Volume 1

Energy Technology Data Exchange (ETDEWEB)

Duerden, P [Australian Nuclear Science and Technology Organisation (ANSTO), Lucas Heights, NSW (Australia); Lever, D A [AEA Technology, Harwell (United Kingdom); Sverjensky, D A [Johns Hopkins Univ., Baltimore, MD (United States); Townley, L R [Commonwealth Scientific and Industrial Research Organisation (CSIRO), Wembley, WA (Australia). Div. of Water Resources

1992-07-01

This summary report, which highlights the work and findings of the Alligator Rivers Analogue Project (ARAP) is one of a series of 16 volumes, listed below. Detailed descriptions and results are provided in Volumes 2 to 16. Full acknowledgment to individual contributions is provided in the individual reports, and in Appendix I of this report. The findings from the technical studies are discussed in the context of assessments of the long-term performance of geological repositories for radioactive wastes, which are being undertaken in many countries. They are also considered in an integrated 'Scenario Development' approach, aimed to understand the formation of the ore deposit. Despite their inherent uncertainties, the findings provide a basis for assessing the way in which radionuclides will migrate in environments with a variety of geologic settings and over a range of different geologic timescales. Thus, section 2 of this report discusses the concept of using uranium deposits as natural analogues and refers to a number of such studies, including those at the Koongarra deposit in the Alligator Rivers Region of the Northern Territory of Australia. Section 3 reviews early scientific work in the Alligator Rivers Region and summarises the results of the analogue studies undertaken between 1981 and 1987 that were funded by the US Nuclear Regulatory Commission (USNRC) and the UK Department of the Environment (UKDoE). Section 4 describes the objectives of ARAP and the manner in which the study was conducted and provides a general outline of the project and a summary of the findings. A general description of the Koongarra ore deposit, the focus of ARAP, is provided in Section 5, with Sections 6-13 providing summaries of the work carried out to characterise the site in detail and provide data for modelling. Sections 14-18 discuss how this data was used in modelling and how the results may be applied for performance assessment studies. Finally, Section 19 considers the

Alligator Rivers Analogue Project. Final Report - Volume 1

International Nuclear Information System (INIS)

Duerden, P.; Lever, D.A.; Sverjensky, D.A.; Townley, L.R.

1992-01-01

This summary report, which highlights the work and findings of the Alligator Rivers Analogue Project (ARAP) is one of a series of 16 volumes, listed below. Detailed descriptions and results are provided in Volumes 2 to 16. Full acknowledgment to individual contributions is provided in the individual reports, and in Appendix I of this report. The findings from the technical studies are discussed in the context of assessments of the long-term performance of geological repositories for radioactive wastes, which are being undertaken in many countries. They are also considered in an integrated 'Scenario Development' approach, aimed to understand the formation of the ore deposit. Despite their inherent uncertainties, the findings provide a basis for assessing the way in which radionuclides will migrate in environments with a variety of geologic settings and over a range of different geologic timescales. Thus, section 2 of this report discusses the concept of using uranium deposits as natural analogues and refers to a number of such studies, including those at the Koongarra deposit in the Alligator Rivers Region of the Northern Territory of Australia. Section 3 reviews early scientific work in the Alligator Rivers Region and summarises the results of the analogue studies undertaken between 1981 and 1987 that were funded by the US Nuclear Regulatory Commission (USNRC) and the UK Department of the Environment (UKDoE). Section 4 describes the objectives of ARAP and the manner in which the study was conducted and provides a general outline of the project and a summary of the findings. A general description of the Koongarra ore deposit, the focus of ARAP, is provided in Section 5, with Sections 6-13 providing summaries of the work carried out to characterise the site in detail and provide data for modelling. Sections 14-18 discuss how this data was used in modelling and how the results may be applied for performance assessment studies. Finally, Section 19 considers the

Guidance for the application of an assessment methodology for innovative nuclear energy systems. INPRO manual - Safety of nuclear fuel cycle facilities. Vol. 9 of the final report of phase 1 of the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO)

International Nuclear Information System (INIS)

2008-11-01

The International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO) was initiated in the year 2000, based on a resolution of the IAEA General Conference (GC(44)/RES/21). The main objectives of INPRO are (1) to help to ensure that nuclear energy is available to contribute in fulfilling energy needs in the 21st century in a sustainable manner, (2) to bring together both technology holders and technology users to consider jointly the international and national actions required to achieve desired innovations in nuclear reactors and fuel cycles; and (3) to create a forum to involve all relevant stakeholders that will have an impact on, draw from, and complement the activities of existing institutions, as well as ongoing initiatives at the national and international level. The INPRO manual is comprised of an overview volume (No. 1), and eight additional volumes covering the areas of economics (Volume 2), infrastructure (Volume 3), waste management (Volume 4), proliferation resistance (Volume 5), physical protection (Volume 6), environment (Volume 7), safety of nuclear reactors (Volume 8), and safety of nuclear fuel cycle facilities (laid out in this report) (Volume 9).This report elaborates on the guidance given in the INPRO report 'Methodology for the assessment of innovative nuclear reactors and fuel cycles', IAEA-TECDOC-1434, and the previous INPRO report 'Guidance for the evaluation for innovative nuclear reactors and fuel cycles', IAEA-TECDOC-1362 (2003), in the area of safety of nuclear reactors. The present version of this manual deals with safety issues related to design and operation of mining, milling, refining, conversion, enrichment, fuel fabrication, fuel storage and fuel reprocessing facilities. The INPRO Manual starts with an introduction in Chapter 1. Chapter 2 sets out the necessary input for an INPRO assessment of the safety of an innovative nuclear fuel cycle facility. This includes information on the design for the plant and the safety

Reports on the projects in the field of reactor safety sponsored by the Federal Ministry for Research and Technology

International Nuclear Information System (INIS)

1977-06-01

Investigations on the safety of Light Water Reactors (LWR) being performed in the framework of the Research Program Reactor Safety (RS-projects) are sponsored by the BMFT (Federal Minister for Research and Technology), Bundesminister fuer Forschung und Technologie. Objective of this program is to investigate in greater detail the safety margins of nuclear energy plants and their systems and the further development of safety technology. The GRS (Reactor Safety Association), Gesellschaft fuer Reaktorsicherheit mbH, by order of the BMFT, informs continuously of the status of these investigations within the series 'GRS-F-Forschrittsberichte' (GRS-F-Progress Reports). Each progress report represents a compilation of individual reports about the different projects of the search program. The individual reports are prepared by the contractors themselves as a documentation of their progress in work and published by the GRS-FB (Research Coordination Department), Forschungsbetreuung at the GRS, within the framework of general information of the progress in reactor safety research. Each report describes the work performed, the results and the next steps of the work. The individual reports are attached to the classification system established by the CEC (Commission of the European Communities). The GRS-F-Progress Reports also include a list of the current investigations arranged according to the projects of the BMFT-Research Program Reactor Safety. This compilation, in addition to the LWR-investigations, also contains first contributions on the safety of advanced reactors. (orig.) [de

Reports on the projects in the field of reactor safety sponsored by the Federal Ministry for Research and Technology

International Nuclear Information System (INIS)

1977-11-01

Investigations on the safety of Light Water Reactors (LWR) being performed in the framework of the Research Program Reactor Safety (RS-projects) are sponsored by the BMFT (Federal Minister for Research and Technology), Bundesminister fuer Forschung und Technologie. Objective of this program is to investigate in greater detail the safety margins of nuclear energy plants and their systems and the further development of safety technology. The GRS (Reactor Safety Association), Gesellschaft fuer Reaktorsicherheit mbH, by order of BMFT, informs continuously of the status of these investigations within the series 'GRS-F-Fortschrittsberichte' (GRS-F-Progress Reports). Each progress report represents a compilation of individual reports about the different projects of the search program. The individual reports are prepared by the contractors themselves as a documentation of their progress in work and published by the GRS-FB (Research Coordination Department), Forschungsbetreuung at the GRS, within the framework of general information of the progress in reactor safety research. Each report describes the work performed, the results and the next steps of the work. The individual reports are attached to the classification system established by the CEC (Commission of the European Communities). The GRS-F-Progress Reports also include a list of the current investigations arranged according to the projects of the BMFT-Research Program Reactor Safety. This compilation, in addition to the LWR-investigations, also contains first contributions on the safety of advanced reactors. (orig.) [de

Reports on the projects in the field of reactor safety sponsored by the Federal Ministry for Research and Technology

International Nuclear Information System (INIS)

1977-12-01

Investigations on the safety of Light Water Reactors (LWR) being performed in the framework of the Research Program Reactor Safety (RS-projects) are sponsored by the BMFT (Federal Minister for Research and Technology), Bundesminister fuer Forschung und Technologie. Objective of this program is to investigate in greater detail the safety margins of nuclear energy plants and their systems and the further development of safety technology. The GRS (Reactor Safety Association), Gesellschaft fuer Reaktorsicherheit mbH, by order of the BMFT, informs continuously of the status of these investigations within the series 'GRS-F-Fortschrittsberichte' (GRS-F-Progress Reports). Each progress report represents a compilation of individual reports about the different projects of the search program. The individual reports are prepared by the contractors themselves as a documentation of their progress in work and published by the GRS-FB (Research Coordination Department), Forschungsbetreuung at the GRS, within the framework of general information of the progress in reactor safety research. Each report describes the work performed, the results and the next steps of the work. The individual reports are attached to the classification system established by the CEC (Commission of the European Communities). The GRS-F-Progress Reports also include a list of the current investigations arranged according to the projects of the BMFT-Research Program Reactor Safety. This compilation, in addition to the LWR-investigations, also contains first contributions on the safety of advanced reactors. (orig.) [de

Trans-Caspian gas pipeline feasibility study. Volume 2

International Nuclear Information System (INIS)

1999-01-01

This study, conducted by Enron Engineering and Construction Company, was funded by the US Trade and Development Agency. The study provides detailed information concerning natural gas demand in Turkey and Southern Europe. The purpose of the study is to estimate the rate at which new gas can be absorbed in the Turkish market and be re-exported to the markets in Europe, as well as to forecast Turkish natural gas demand for the period up to 2020. The study also evaluates gas demand and pricing for the market in the 2002--2005 time frame. This is Volume 2 of a 3-volume report, and it is divided into the following sections: (1) Executive Summary; (2) Policy, Legal and Administrative Framework; (3) Assessment of Alternatives; (4) Baseline Conditions in the Project Area; (5) Potential (Unmitigated) Environment, Health and Safety Impacts; (6) Proposed Environmental Prevention and Mitigation; (7) Projected Net Environmental Impacts; (8) Bibliography

Sodium fast reactor safety and licensing research plan - Volume II

International Nuclear Information System (INIS)

Ludewig, H.; Powers, D.A.; Hewson, John C.; LaChance, Jeffrey L.; Wright, A.; Phillips, J.; Zeyen, R.; Clement, B.; Garner, Frank; Walters, Leon; Wright, Steve; Ott, Larry J.; Suo-Anttila, Ahti Jorma; Denning, Richard; Ohshima, Hiroyuki; Ohno, S.; Miyhara, S.; Yacout, Abdellatif; Farmer, M.; Wade, D.; Grandy, C.; Schmidt, R.; Cahalen, J.; Olivier, Tara Jean; Budnitz, R.; Tobita, Yoshiharu; Serre, Frederic; Natesan, Ken; Carbajo, Juan J.; Jeong, Hae-Yong; Wigeland, Roald; Corradini, Michael; Thomas, Justin; Wei, Tom; Sofu, Tanju; Flanagan, George F.; Bari, R.; Porter D.

2012-01-01

Expert panels comprised of subject matter experts identified at the U.S. National Laboratories (SNL, ANL, INL, ORNL, LBL, and BNL), universities (University of Wisconsin and Ohio State University), international agencies (IRSN, CEA, JAEA, KAERI, and JRC-IE) and private consultation companies (Radiation Effects Consulting) were assembled to perform a gap analysis for sodium fast reactor licensing. Expert-opinion elicitation was performed to qualitatively assess the current state of sodium fast reactor technologies. Five independent gap analyses were performed resulting in the following topical reports: (1) Accident Initiators and Sequences (i.e., Initiators/Sequences Technology Gap Analysis), (2) Sodium Technology Phenomena (i.e., Advanced Burner Reactor Sodium Technology Gap Analysis), (3) Fuels and Materials (i.e., Sodium Fast Reactor Fuels and Materials: Research Needs), (4) Source Term Characterization (i.e., Advanced Sodium Fast Reactor Accident Source Terms: Research Needs), and (5) Computer Codes and Models (i.e., Sodium Fast Reactor Gaps Analysis of Computer Codes and Models for Accident Analysis and Reactor Safety). Volume II of the Sodium Research Plan consolidates the five gap analysis reports produced by each expert panel, wherein the importance of the identified phenomena and necessities of further experimental research and code development were addressed. The findings from these five reports comprised the basis for the analysis in Sodium Fast Reactor Research Plan Volume I.

Sodium fast reactor safety and licensing research plan. Volume II.

Energy Technology Data Exchange (ETDEWEB)

Ludewig, H. (Brokhaven National Laboratory, Upton, NY); Powers, D. A.; Hewson, John C.; LaChance, Jeffrey L.; Wright, A. (Argonne National Laboratory, Argonne, IL); Phillips, J.; Zeyen, R. (Institute for Energy Petten, Saint-Paul-lez-Durance, France); Clement, B. (IRSN/DPAM.SEMIC Bt 702, Saint-Paul-lez-Durance, France); Garner, Frank (Radiation Effects Consulting, Richland, WA); Walters, Leon (Advanced Reactor Concepts, Los Alamos, NM); Wright, Steve; Ott, Larry J. (Oak Ridge National Laboratory, Oak Ridge, TN); Suo-Anttila, Ahti Jorma; Denning, Richard (Ohio State University, Columbus, OH); Ohshima, Hiroyuki (Japan Atomic Energy Agency, Ibaraki, Japan); Ohno, S. (Japan Atomic Energy Agency, Ibaraki, Japan); Miyhara, S. (Japan Atomic Energy Agency, Ibaraki, Japan); Yacout, Abdellatif (Argonne National Laboratory, Argonne, IL); Farmer, M. (Argonne National Laboratory, Argonne, IL); Wade, D. (Argonne National Laboratory, Argonne, IL); Grandy, C. (Argonne National Laboratory, Argonne, IL); Schmidt, R.; Cahalen, J. (Argonne National Laboratory, Argonne, IL); Olivier, Tara Jean; Budnitz, R. (Lawrence Berkeley National Laboratory, Berkeley, CA); Tobita, Yoshiharu (Japan Atomic Energy Agency, Ibaraki, Japan); Serre, Frederic (Centre d' %C3%94etudes nucl%C3%94eaires de Cadarache, Cea, France); Natesan, Ken (Argonne National Laboratory, Argonne, IL); Carbajo, Juan J. (Oak Ridge National Laboratory, Oak Ridge, TN); Jeong, Hae-Yong (Korea Atomic Energy Research Institute, Daejeon, Korea); Wigeland, Roald (Idaho National Laboratory, Idaho Falls, ID); Corradini, Michael (University of Wisconsin-Madison, Madison, WI); Thomas, Justin (Argonne National Laboratory, Argonne, IL); Wei, Tom (Argonne National Laboratory, Argonne, IL); Sofu, Tanju (Argonne National Laboratory, Argonne, IL); Flanagan, George F. (Oak Ridge National Laboratory, Oak Ridge, TN); Bari, R. (Brokhaven National Laboratory, Upton, NY); Porter D. (Idaho National Laboratory, Idaho Falls, ID); Lambert, J. (Argonne National Laboratory, Argonne, IL); Hayes, S. (Idaho National Laboratory, Idaho Falls, ID); Sackett, J. (Idaho National Laboratory, Idaho Falls, ID); Denman, Matthew R.

2012-05-01

Expert panels comprised of subject matter experts identified at the U.S. National Laboratories (SNL, ANL, INL, ORNL, LBL, and BNL), universities (University of Wisconsin and Ohio State University), international agencies (IRSN, CEA, JAEA, KAERI, and JRC-IE) and private consultation companies (Radiation Effects Consulting) were assembled to perform a gap analysis for sodium fast reactor licensing. Expert-opinion elicitation was performed to qualitatively assess the current state of sodium fast reactor technologies. Five independent gap analyses were performed resulting in the following topical reports: (1) Accident Initiators and Sequences (i.e., Initiators/Sequences Technology Gap Analysis), (2) Sodium Technology Phenomena (i.e., Advanced Burner Reactor Sodium Technology Gap Analysis), (3) Fuels and Materials (i.e., Sodium Fast Reactor Fuels and Materials: Research Needs), (4) Source Term Characterization (i.e., Advanced Sodium Fast Reactor Accident Source Terms: Research Needs), and (5) Computer Codes and Models (i.e., Sodium Fast Reactor Gaps Analysis of Computer Codes and Models for Accident Analysis and Reactor Safety). Volume II of the Sodium Research Plan consolidates the five gap analysis reports produced by each expert panel, wherein the importance of the identified phenomena and necessities of further experimental research and code development were addressed. The findings from these five reports comprised the basis for the analysis in Sodium Fast Reactor Research Plan Volume I.

Technical and administrative approach for the West Valley Demonstration Project Safety Program

International Nuclear Information System (INIS)

Newsom, P.C.; Roberts, C.J.; Yuchien Yuan; Marchetti, S.

1987-06-01

The principal objective of the West Valley Demonstration Project (WVDP) is to vitrify the 2.2 million liters of high-level radioactive waste (HLW) stored at the Western New York Nuclear Service Center (WNYNSC). This simple statement of purpose, however, does not convey a sense of the complexity of the undertaking. The vitrification task is not only complex in and of itself, but requires a myriad of other activities to be accomplished on an intricate and fast paced schedule in order to support it. The West Valley Demonstration Project Act (P.L 96-368), U.S. Department of Energy Order DOE-5481.1A, Idaho Operations Office Order ID-5481.1 and standard nuclear industry practice all require that proposed systems and operations involving hazards not routinely encountered by the general public be analyzed to identify potential hazards and consequences, and to assure that reasonable measures are taken to eliminate, control, or mitigate these potential consequences. Virtually every substantive aspect of the WVDP involves hazards beyond those routinely encountered and accepted by the general public. In order to assure the safety of the public and the workers at the WVDP, a system of hazard identification, categorization, analysis and review has been established. In parallel with this system, a procedure for developing the minimum design specifications and quality assurance requirements has been developed for Project systems, components, and structures which play a role in the safety of a specific major facility or the overall Project. 29 refs., 3 figs., 6 tabs

Project SAFE. Update of the SFR-1 safety assessment. Phase 1. Appendix A1: Inventory

International Nuclear Information System (INIS)

Riggare, P.

1998-01-01

One of the aims in the safety assessment of SFR-1 is to estimate the release to the environment. In order to make these calculations there is a need to describe the inventory in greater detail. The new computerised database of waste in SFR-1 gives a good possibility to achieve this. The aim for project SAFE is to make both conservative and realistic radionuclide transport calculations. To achieve this goal there must be two inventories. The conservative inventory is the inventory used in the design of the repository, which in most parts is identical with the limits in the licence for SFR-1. There is a great interest to have good estimates of the volumes of the different waste types. A thorough prognosis should be made in 1999, but until then the latest one from 1995 could be used in the calculations. The total (actual) inventory of nuclides is calculated from the measurements of the easy-to-measure nuclides since, in principle, all hard-to-measure nuclides are calculated by correlation factors to 60 Co and 137 Cs . These factors should be reviewed since there are quite large uncertainties involved. 14 C dominates the individual doses after a few hundred years and the collective dose in the inland-scenario. The amount of the nuclide is uncertain since the correlation factor is very uncertain. The chemical speciation of 14 C is also of interest due to different properties of organic and inorganic carbon. 36 Cl is very hard to measure. Although the authorities in their reviews of the safety reports say that there probably are small doses from chlorine, the inventory should be improved. 59 Ni is a long-lived nuclide that sets a limit to the close-to-the-core metal scrap that can be taken to SFR- 1. There is an ongoing research project to provide a better measuring method for 59 Ni. This should make it possible to improve the knowledge about 59 Ni inventory. The assumption that 90 % of the inventory is collected in the ion-exchange resins should be checked. Actinides

The Citizenship Safety Project: a pilot study.

Science.gov (United States)

Frederick, K; Barlow, J

2006-02-01

The Government White Paper Saving Lives: Our Healthier Nation (1999) provides a clear indication that accidents are a serious public health problem and have been targeted by the Department of Health as a key area for prevention over the next 10 years. School-based injury prevention programmes have been identified as one of the key settings for the implementation of the White Paper's heath promotion strategies. The Citizen Safety Project (CSP) is a peer-delivered injury prevention programme for Year 10 students (14-15 years) and Year 2 pupils (6-7 years). This paper summarizes the findings of a pilot study that assessed the feasibility of implementing the CSP in schools and of conducting a larger study. Working as part of their Personal Social Health Education lessons, 11 pairs (n = 22) of Year 10 students developed a project to take one accident prevention theme of their choice into a primary school to teach small groups of five or six Year 2 pupils (n = 55). A formative evaluation was conducted, based on interviews with Year 2 and Year 10 teachers (n = 2), and the diaries of Year 10 students. Knowledge of accident prevention and risk awareness was measured in Year 2 pupils using the Draw and Write technique, and impact on Year 10 students was measured using self-esteem and locus of control inventories. Using both statistical and thematic analysis the study concludes that the CSP is well accepted, improves knowledge in Year 2 pupils and boosts confidence in Year 10 students, while concurrently achieving key stage attainment targets. Implications of the study are discussed in terms of future research, as are recommendations with regard to modifications to the project.

The funding of dangerous nuclear projects. Nuclear trade and safety: the role of French private banks. What are we talking about?

International Nuclear Information System (INIS)

Philippe, Isabelle

2011-01-01

Countries which export nuclear technologies, notably France, have developed mechanisms of financial support to incite private banks to finance the sale of reactors to foreign countries, notably EPRs in the case of France. After having briefly introduced this issue, and dealing with the French case, this publication indicates the concerned banks, and outlines that some of them finance nuclear projects which have been assessed by NGOs as dangerous in terms of nuclear safety. It notably presents the Angra 3 project in Brazil: its cost, its planning, its main safety problems (obsolete technology, building authorization awarded without any actual safety analysis, situation of conflict of interest for the Brazilian regulator). It also presents the Jaitapur project in India in which Areva is as well involved: costs, funding, planning, main risks (seismic risk area, safety level much lower than the one required in France, controversy on the impact study). The document finally explains why banks must not fund nuclear projects

Seismic safety margins research program. Phase I final report - Major structure response (Project IV)

International Nuclear Information System (INIS)

Benda, B.J.; Johnson, J.J.; Lo, T.Y.

1981-08-01

The primary task of the Major Structure Response Project within the Seismic Safety Margins Research Program (SSMRP) was to develop detailed finite element models of the Zion Nuclear Power Plant's containment building and auxiliary-fuel-turbine (AFT) complex. The resulting models served as input to the seismic methodology analysis chain. The containment shell was modeled as a series of beam elements with the shear and bending characteristics of a circular cylindrical shell. Masses and rotary inertias were lumped at nodal points; thirteen modes were included in the analysis. The internal structure was modeled with three-dimensional finite elements, with masses again lumped at selected nodes; sixty modes were included in the analysis. The model of the AFT complex employed thin plate and shell elements to represent the concrete shear walls and floor diaphragms, and beam and truss elements to model the braced frames. Because of the size and complexity of the model, and the potentially large number of degrees of freedom, masses were lumped at a limited number of node points. These points were selected so as to minimize the effect of the discrete mass distribution on structural response. One hundred and thirteen modes were extracted. A second objective of Project IV was to investigate the effects of uncertainty and variability on structural response. To this end, four side studies were conducted. Three of them, briefly summarized in this volume, addressed themselves respectively to an investigation of sources of random variability in the dynamic response of nuclear power plant structures; formulation of a methodology for modeling and evaluating the effects of structural uncertainty on predicted modal characteristics of major nuclear power plant structures and substructures; and a preliminary evaluation of nonlinear responses in shear-wall structures. A fourth side study, reported in detail in this volume, quantified variations in dynamic characteristics and seismic

Operational waste volume projection

International Nuclear Information System (INIS)

Koreski, G.M.; Strode, J.N.

1995-06-01

Waste receipts to the double-shell tank system are analyzed and wastes through the year 2015 are projected based on generation trends of the past 12 months. A computer simulation of site operations is performed, which results in projections of tank fill schedules, tank transfers, evaporator operations, tank retrieval, and aging waste tank usage. This projection incorporates current budget planning and the clean-up schedule of the tri-party agreement. Assumptions are current as of June 1995

Operational Waste Volume Projection

Energy Technology Data Exchange (ETDEWEB)

STRODE, J.N.

2000-08-28

Waste receipts to the double-shell tank system are analyzed and wastes through the year 2015 are projected based on generation trends of the past 12 months. A computer simulation of site operations is performed, which results in projections of tank fill schedules, tank transfers, evaporator operations, tank retrieval, and aging waste tank usage. This projection incorporates current budget planning and the clean-up schedule of the Tri-Party Agreement. Assumptions were current as of June. 2000.

Operational Waste Volume Projection

International Nuclear Information System (INIS)

STRODE, J.N.

2000-01-01

Waste receipts to the double-shell tank system are analyzed and wastes through the year 2015 are projected based on generation trends of the past 12 months. A computer simulation of site operations is performed, which results in projections of tank fill schedules, tank transfers, evaporator operations, tank retrieval, and aging waste tank usage. This projection incorporates current budget planning and the clean-up schedule of the Tri-Party Agreement. Assumptions were current as of June. 2000

76 FR 63988 - Pilot Project on NAFTA Trucking Provisions; Pre-Authorization Safety Audits

Science.gov (United States)

2011-10-14

...-0097] Pilot Project on NAFTA Trucking Provisions; Pre-Authorization Safety Audits AGENCY: Federal Motor... motor carriers that applied to participate in the Agency's long-haul pilot program to test and... intent to proceed with the initiation of a United States- Mexico cross-border long-haul trucking pilot...

Final Hazard Classification and Auditable Safety Analysis for the 105-F Building Interim Safe Storage Project

International Nuclear Information System (INIS)

Rodovsky, T.J.; Bond, S.L.

1998-07-01

The auditable safety analysis (ASA) documents the authorization basis for the partial decommissioning and facility modifications to place the 105-F Building into interim safe storage (ISS). Placement into the ISS is consistent with the preferred alternative identified in the Record of Decision (58 FR). Modifications will reduce the potential for release and worker exposure to hazardous and radioactive materials, as well as lower surveillance and maintenance (S ampersand M) costs. This analysis includes the following: A description of the activities to be performed in the course of the 105-F Building ISS Project. An assessment of the inventory of radioactive and other hazardous materials within the 105-F Building. Identification of the hazards associated with the activities of the 105-F Building ISS Project. Identification of internally and externally initiated accident scenarios with the potential to produce significant local or offsite consequences during the 105-F Building ISS Project. Bounding evaluation of the consequences of the potentially significant accident scenarios. Hazard classification based on the bounding consequence evaluation. Associated safety function and controls, including commitments. Radiological and other employee safety and health considerations

Surveys of research projects concerning nuclear facility safety financed by the Federal Ministry for the Environment, Nature Protection and Reactor Safety, 1991

International Nuclear Information System (INIS)

1992-09-01

Each progress report is a collection of individual reports, categorized by subject matter. They are a documentation of the contractor's progress, rendered by themselves on standardized forms, published, for the sake of general information on progress made in investigations concerning reactor safety, by the project attendance department of the GRS. The individual reports have serial numbers. Each report includes particulars of the objective, work carried out, results obtained and plans for project continuation. (orig.) [de

Surveys of research projects concerning nuclear facility safety, financed by the Federal Ministry for the Environment, Nature Protection and Reactor Safety, 1988

International Nuclear Information System (INIS)

1989-11-01

Each progress report is a collection of individual reports, categorized by subject matter. They are a documentation of the contractor's progress, rendered by themselves on standardized forms, published, for the sake of general information on progress made in investigations concerning reactor safety, by the project attendance department of the GRS. The individual reports have serial numbers. Each report includes particulars of the objective, work carried out, results obtained and plans for project continuation. (orig.) [de

Surveys of research projects concerning nuclear facility safety, financed by the Federal Ministry for the Environment, Nature Protection and Reactor Safety, 1987

International Nuclear Information System (INIS)

1988-06-01

Each progress report is a collection of individual reports, categorized by subject matter. They are a documentation of the contractor's progress, rendered by themselves on standardized forms, published, for the sake of general information on progress made in investigations concerning reactor safety, by the project attendance department of the GRS. The individual reports have serial numbers. Each report includes particulars of the objective, work carried out, results obtained and plans for project continuation. (orig.) [de

Design data and safety features of commercial nuclear power plants including cumulative index for Volumes I--VI

International Nuclear Information System (INIS)

Heddleson, F.A.

1977-01-01

Design data, safety features, and site characteristics are summarized for 12 nuclear power units in 6 power stations in the United States. Six pages of data are presented for each station, consisting of thermal-hydraulic and nuclear factors, containment features, emergency-core-cooling systems, site features, circulating water system data, and miscellaneous factors. In addition, an aerial perspective is presented for each plant. This volume covers plants with docket numbers 50-553 through 50-569 (Phipps Bend, Black Fox, Yellow Creek, and NEP) and two earlier plants not previously reported--Hope Creek (50-354, 50-355) and WPPSS 1 and 4 (50-460, 50-513). Indexes for this volume and the five earlier volumes are presented in three forms--by docket number, by plant name, and by participating utility

Sensitivity and uncertainty analyses applied to criticality safety validation, methods development. Volume 1

International Nuclear Information System (INIS)

Broadhead, B.L.; Hopper, C.M.; Childs, R.L.; Parks, C.V.

1999-01-01

This report presents the application of sensitivity and uncertainty (S/U) analysis methodologies to the code/data validation tasks of a criticality safety computational study. Sensitivity and uncertainty analysis methods were first developed for application to fast reactor studies in the 1970s. This work has revitalized and updated the available S/U computational capabilities such that they can be used as prototypic modules of the SCALE code system, which contains criticality analysis tools currently used by criticality safety practitioners. After complete development, simplified tools are expected to be released for general use. The S/U methods that are presented in this volume are designed to provide a formal means of establishing the range (or area) of applicability for criticality safety data validation studies. The development of parameters that are analogous to the standard trending parameters forms the key to the technique. These parameters are the D parameters, which represent the differences by group of sensitivity profiles, and the ck parameters, which are the correlation coefficients for the calculational uncertainties between systems; each set of parameters gives information relative to the similarity between pairs of selected systems, e.g., a critical experiment and a specific real-world system (the application)

The safety of risk or the risk of safety?

NARCIS (Netherlands)

Suddle, S.I.; Waarts, P.H.

2003-01-01

Safety is nowadays one of the main items on the agenda during the planning, realisation and management of most large-scale projects, particularly in infrastructure and building projects in intensively used areas such as multiple use of land projects. It is vital that safety aspects are properly

Progress report projects in the field of nuclear safety sponsered by the Federal Minister for Research and Technology

International Nuclear Information System (INIS)

1980-03-01

Investigations on the safety of Light Water Reactors (LWR) being performed in the framework of the Research Program Reactor Safety (RS-Projects) are sponsored by the BMFT (Federal Minister for Research and Technology), Bundesminister fuer Forschung und Technologie. Objective of this program is to investigate in greater detail the safety margins of nuclear energy plants and their systems and the further development of safety technology. Besides the investigations of LWR tasks first projects on the safety of FBR type reactors are sponsored by the BMFT. The GRS (Reactor Safety Association), Gesellschaft fuer Reaktorsicherheit mbH, by order of the BMFT, informs continuously of the status of such investigations by means of quarterly and annually publication of progress reports within the series GRS-F-Fortschrittsberichte (GRS-F-Progress Reports). Each progress report represents a compilation of individual reports about objectives, the work performed, the results, the next steps of the work etc. The individual reports are prepared in a standard form by the contractors themselves as a documentation of their progress in work at the GRS, within the framework of general information of the progress in reactor safety research. The individual reports are arranged according to the amended LWR Safety Research Program of the BMFT. Another table contents uses the same classification system as applied in the Nuclear Safety Index of the CEC and the OECD. (orig./HP) [de

77 FR 59551 - Safety Zone, Changes to Original Rule; Boston Harbor's Rock Removal Project, Boston Inner Harbor...

Science.gov (United States)

2012-09-28

... DEPARTMENT OF HOMELAND SECURITY Coast Guard 33 CFR Part 165 [Docket No. USCG-2012-0767] RIN 1625-AA00 Safety Zone, Changes to Original Rule; Boston Harbor's Rock Removal Project, Boston Inner Harbor... original provisions of that temporary final rule, but adds two additional safety zones necessary for the...

Engineered materials characterization report for the Yucca Mountain Site Characterization Project. Volume 3: Corrosion and data modeling

International Nuclear Information System (INIS)

Van Konynenburg, R.A.; McCright, R.D.; Roy, A.K.; Jones, D.A.

1995-08-01

This three-volume report serves several purposes. The first volume provides an introduction to the engineered materials effort for the Yucca Mountain Site Characterization Project. It defines terms and outlines the history of selection and characterization of these materials. A summary of the recent engineered barrier materials characterization workshop is presented, and the current candidate materials are listed. The second volume tabulates design data for engineered materials, and the third volume is devoted to corrosion data, radiation effects on corrosion, and corrosion modeling. The second and third volumes are intended to be evolving documents, to which new data will be added as they become available from additional studies. The initial version of Volume 3 is devoted to information currently available for environments most similar to those expected in the potential Yucca Mountain repository. This is volume three

JANNAF 28th Propellant Development and Characterization Subcommittee and 17th Safety and Environmental Protection Subcommittee Joint Meeting. Volume 1

Science.gov (United States)

Cocchiaro, James E. (Editor); Mulder, Edwin J. (Editor); Gomez-Knight, Sylvia J. (Editor)

1999-01-01

This volume contains 37 unclassified/unlimited-distribution technical papers that were presented at the JANNAF 28th Propellant Development & Characterization Subcommittee (PDCS) and 17th Safety & Environmental Protection Subcommittee (S&EPS) Joint Meeting, held 26-30 April 1999 at the Town & Country Hotel and the Naval Submarine Base, San Diego, California. Volume II contains 29 unclassified/limited-distribution papers that were presented at the 28th PDCS and 17th S&EPS Joint Meeting. Volume III contains a classified paper that was presented at the 28th PDCS Meeting on 27 April 1999. Topics covered in PDCS sessions include: solid propellant rheology; solid propellant surveillance and aging; propellant process engineering; new solid propellant ingredients and formulation development; reduced toxicity liquid propellants; characterization of hypergolic propellants; and solid propellant chemical analysis methods. Topics covered in S&EPS sessions include: space launch range safety; liquid propellant hazards; vapor detection methods for toxic propellant vapors and other hazardous gases; toxicity of propellants, ingredients, and propellant combustion products; personal protective equipment for toxic liquid propellants; and demilitarization/treatment of energetic material wastes.

TSO Study Project on Development of a Common Safety Approach in the EU for Large Evolutionary Pressurised Water Reactors

International Nuclear Information System (INIS)

2001-10-01

In pursuance of the objectives of the Council Resolutions of 1975 and 1992 on the technological issues of nuclear safety, the European Commission (EC) is seeking to promote a sustained joint in-depth study on possible significant future nuclear power reactor safety cases. To that end the EC decided to support financially a study by the grouping of the European Union Technical Safety Organisations (TSOG). The general objective of the study programme was to promote, through a collaboration of European Union Technical Safety Organisations (TSOs), common views on technical safety issues related to large evolutionary PWRs in Europe, which could be ready for operation during the next decade. AVN (Belgium) (Technical project leader), AEA Technology (United Kingdom), ANPA (Italy) CIEMAT (Spain), GRS (Germany), IPSN (France), were the TSOs participating in the study which was co-ordinated by RISKAUDIT. The study focused notably on the EPR project initiated by the French and German utilities and vendors. It also considered relevant projects, even of plants of different size, developed outside the European Union in order to provide elements important for the safety characterisation and which could contribute to the credibility and confidence of EPR. It is expected that this study will constitute a significant step towards the development of a common safety approach in EU countries. The study constitutes an important step forward in the development of a common approach of the TSOs to the safety of advanced evolutionary pressurised water reactors. This goal was mainly achieved by an in-depth analysis of the key safety issues, taking into account new developments in the national technical safety objectives and in the EPR design. For this reason the Commission has decided to publish at least the present summary report containing the main outcomes of the TSO study. Confidentiality considerations unfortunately prevent the open publication of the full series of reports. (author)

Nuclear safety projects 1995

International Nuclear Information System (INIS)

Carl-Erik Christoffersen

1996-01-01

Action plans for the prevention of contamination in the Arctic regions is concretized in a number of international projects. The Norwegian Radiation Protection Authority is responsible for the follow-up of 13 projects. The report describes the development of these projects in 1995

LIFAC sorbent injection desulfurization demonstration project. Final report, volume II: Project performance and economics

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-01-01

This publication discusses the demonstration of the LIFAC sorbent injection technology at Richmond Power and Light`s Whitewater Valley Unit No. 2, performed under the auspices of the U.S. Department of Energy`s (DOE) Clean Coal Technology Program. LIFAC is a sorbent injection technology capable of removing 75 to 85 percent of a power plant`s SO{sub 2} emissions using limestone at calcium to sulfur molar ratios of between 2 and 2.5 to 1. The site of the demonstration is a coal-fired electric utility power plant located in Richmond, Indiana. The project is being conducted by LIFAC North America (LIFAC NA), a joint venture partnership of Tampella Power Corporation and ICF Kaiser Engineers, in cooperation with DOE, RP&L, and Research Institute (EPRI), the State of Indiana, and Black Beauty Coal Company. The purpose of Public Design Report Volume 2: Project Performance and Economics is to consolidate, for public use, the technical efficiency and economy of the LIFAC Process. The report has been prepared pursuant to the Cooperative Agreement No. DE-FC22-90PC90548 between LIFAC NA and the U.S. Department of Energy.

Probing Aircraft Flight Test Hazard Mitigation for the Alternative Fuel Effects on Contrails and Cruise Emissions (ACCESS) Research Team . Volume 2; Appendices

Science.gov (United States)

Kelly, Michael J.

2013-01-01

The Alternative Fuel Effects on Contrails and Cruise Emissions (ACCESS) Project Integration Manager requested in July 2012 that the NASA Engineering and Safety Center (NESC) form a team to independently assess aircraft structural failure hazards associated with the ACCESS experiment and to identify potential flight test hazard mitigations to ensure flight safety. The ACCESS Project Integration Manager subsequently requested that the assessment scope be focused predominantly on structural failure risks to the aircraft empennage (horizontal and vertical tail). This report contains the Appendices to Volume I.

75 FR 47602 - Clinical Studies of Safety and Effectiveness of Orphan Products Research Project Grant (R01)

Science.gov (United States)

2010-08-06

...] Clinical Studies of Safety and Effectiveness of Orphan Products Research Project Grant (R01) AGENCY: Food... (OPD) grant program. The goal of FDA's OPD grant program is to support the clinical development of... product will be superior to the existing therapy. FDA provides grants for clinical studies on safety and...

Nuclear proliferation and civilian nuclear power: report of the Nonproliferation Alternative Systems Assessment Program. Volume VI. Safety and environmental considerations for licensing

International Nuclear Information System (INIS)

1979-12-01

Volume 6 of the Nonproliferation Alternative Systems Assessment Program report addresses safety and environmental considerations in licensing the principal alternative nuclear reactors and fuel cycles in the United States for large-scale commercial nuclear power plants. In addition, this volume examines the safety and environmental considerations for licensing fuel service centers. These centers, which have been proposed for controlling sensitive fuel-cycle facilities and special nuclear materials, would contain a combination of such facilities as reprocessing plants, fabrication plants, and reactors. For this analysis, two fuel service center concepts were selected - one with power-generating capability and one without. This volume also provides estimates of the time required for development of large-scale commercial reactor systems to reach the construction permit application stage and for fuel-cycle facilities to reach the operating license application stage, which is a measure of the relative technical status of alternative nuclear systems

Clean coal technology project to Polk Power Station, Tampa Electric Company, Florida, Volume 1: Report

International Nuclear Information System (INIS)

1994-06-01

Tampa Electric Company proposes to construct and operate a 1,150-MW power station in southwestern Polk County, Florida. The proposed Polk Power Station would require an EPA NPDES permit for a new source and would include a 260-MW IGCC unit as a DOE Clean Coal Technology demonstration project. This EIS document assesses the proposed project and alternatives with respect to environmental impacts. Mitigative measures are also evaluated for the preferred alternative. Included in this Volume I are the following: alternatives including Tampa Electric Companies proposed project (preferred alternative with DOE financial assistance); affected environment; environmental consequences of the alternatives

Safety in the Utilization and Modification of Research Reactors. Specific Safety Guide

Energy Technology Data Exchange (ETDEWEB)

NONE

2012-07-15

This Safety Guide is a revision of Safety Series No. 35-G2 on safety in the utilization and modification of research reactors. It provides recommendations on meeting the requirements for the categorization, safety assessment and approval of research reactor experiments and modification projects. Specific safety considerations in different phases of utilization and modification projects are covered, including the pre-implementation, implementation and post-implementation phases. Guidance is also provided on the operational safety of experiments, including in the handling, dismantling, post-irradiation examination and disposal of experimental devices. Examples of the application of the safety categorization process for experiments and modification projects and of the content of the safety analysis report for an experiment are also provided. Contents: 1. Introduction; 2. Management system for the utilization and modification of a research reactor; 3. Categorization, safety assessment and approval of an experiment or modification; 4. Safety considerations for the design of an experiment or modification; 5. Pre-implementation phase of a modification or utilization project; 6. Implementation phase of a modification or utilization project; 7. Post-implementation phase of a utilization or modification project; 8. Operational safety of experiments at a research reactor; 9. Safety considerations in the handling, dismantling, post-irradiation examination and disposal of experimental devices; 10. Safety aspects of out-of-reactor-core installations; Annex I: Example of a checklist for the categorization of an experiment or modification at a research reactor; Annex II: Example of the content of the safety analysis report for an experiment at a research reactor; Annex III: Examples of reasons for a modification at a research reactor.

Safety in the Utilization and Modification of Research Reactors. Specific Safety Guide

International Nuclear Information System (INIS)

2012-01-01

This Safety Guide is a revision of Safety Series No. 35-G2 on safety in the utilization and modification of research reactors. It provides recommendations on meeting the requirements for the categorization, safety assessment and approval of research reactor experiments and modification projects. Specific safety considerations in different phases of utilization and modification projects are covered, including the pre-implementation, implementation and post-implementation phases. Guidance is also provided on the operational safety of experiments, including in the handling, dismantling, post-irradiation examination and disposal of experimental devices. Examples of the application of the safety categorization process for experiments and modification projects and of the content of the safety analysis report for an experiment are also provided. Contents: 1. Introduction; 2. Management system for the utilization and modification of a research reactor; 3. Categorization, safety assessment and approval of an experiment or modification; 4. Safety considerations for the design of an experiment or modification; 5. Pre-implementation phase of a modification or utilization project; 6. Implementation phase of a modification or utilization project; 7. Post-implementation phase of a utilization or modification project; 8. Operational safety of experiments at a research reactor; 9. Safety considerations in the handling, dismantling, post-irradiation examination and disposal of experimental devices; 10. Safety aspects of out-of-reactor-core installations; Annex I: Example of a checklist for the categorization of an experiment or modification at a research reactor; Annex II: Example of the content of the safety analysis report for an experiment at a research reactor; Annex III: Examples of reasons for a modification at a research reactor.

Large-Scale Spacecraft Fire Safety Tests

Science.gov (United States)

Urban, David; Ruff, Gary A.; Ferkul, Paul V.; Olson, Sandra; Fernandez-Pello, A. Carlos; T'ien, James S.; Torero, Jose L.; Cowlard, Adam J.; Rouvreau, Sebastien; Minster, Olivier;

Integrated Framework for Patient Safety and Energy Efficiency in Healthcare Facilities Retrofit Projects.

Science.gov (United States)

Mohammadpour, Atefeh; Anumba, Chimay J; Messner, John I

2016-07-01

There is a growing focus on enhancing energy efficiency in healthcare facilities, many of which are decades old. Since replacement of all aging healthcare facilities is not economically feasible, the retrofitting of these facilities is an appropriate path, which also provides an opportunity to incorporate energy efficiency measures. In undertaking energy efficiency retrofits, it is vital that the safety of the patients in these facilities is maintained or enhanced. However, the interactions between patient safety and energy efficiency have not been adequately addressed to realize the full benefits of retrofitting healthcare facilities. To address this, an innovative integrated framework, the Patient Safety and Energy Efficiency (PATSiE) framework, was developed to simultaneously enhance patient safety and energy efficiency. The framework includes a step -: by -: step procedure for enhancing both patient safety and energy efficiency. It provides a structured overview of the different stages involved in retrofitting healthcare facilities and improves understanding of the intricacies associated with integrating patient safety improvements with energy efficiency enhancements. Evaluation of the PATSiE framework was conducted through focus groups with the key stakeholders in two case study healthcare facilities. The feedback from these stakeholders was generally positive, as they considered the framework useful and applicable to retrofit projects in the healthcare industry. © The Author(s) 2016.

Paul Scherrer Institut Scientific Report 2001. Volume IV: Nuclear Energy and Safety

International Nuclear Information System (INIS)

Smith, B. L.

2002-03-01

The year 2001 was marked by the extensive audit of energy research at PSI. The audit took place on 21/22 June, and nuclear energy research was evaluated by five international experts. It was possible to present the quality and relevance of our research in a convincing way. This, together with optimal use of the available resources in our department Nuclear Energy and Safety (NES), prompted the highly welcome result that the auditors attested a high degree of scientific quality to the NES projects in general, with some of them judged to be of world-class standard. They recommended all audited projects be maintained, adequate resources to be allocated accordingly and, if necessary, an increase of public funding in nuclear energy research to be granted to achieve this. Finally, it was recommended that energy research should be explicitly mentioned in the statement of the ultimate mission of PSI. At the level of 'daily work', efforts in several directions related to the future of the Hotlab were one of the main focuses during the past year. On the one hand, the safety-related backfitting of the facility (particularly in regard to fire protection) has been continued, and was coupled with intensive planning studies, and with a thorough radiological cleaning of the labs; this invariably led to some impediment to the current research activities. Despite external burdens, which have led to some delays and additional costs, three of the four refurbishment phases have been completed, and the corresponding laboratories were brought back into operation after inspection and approval by the regulatory authority HSK. Given the size and complexity of the project, progress must be considered very satisfactory. A list of scientific publications in 2000 is also provided

Paul Scherrer Institut Scientific Report 2001. Volume IV: Nuclear Energy and Safety

Energy Technology Data Exchange (ETDEWEB)

Smith, B.L. (ed.)

2002-03-01

The year 2001 was marked by the extensive audit of energy research at PSI. The audit took place on 21/22 June, and nuclear energy research was evaluated by five international experts. It was possible to present the quality and relevance of our research in a convincing way. This, together with optimal use of the available resources in our department Nuclear Energy and Safety (NES), prompted the highly welcome result that the auditors attested a high degree of scientific quality to the NES projects in general, with some of them judged to be of world-class standard. They recommended all audited projects be maintained, adequate resources to be allocated accordingly and, if necessary, an increase of public funding in nuclear energy research to be granted to achieve this. Finally, it was recommended that energy research should be explicitly mentioned in the statement of the ultimate mission of PSI. At the level of 'daily work', efforts in several directions related to the future of the Hotlab were one of the main focuses during the past year. On the one hand, the safety-related backfitting of the facility (particularly in regard to fire protection) has been continued, and was coupled with intensive planning studies, and with a thorough radiological cleaning of the labs; this invariably led to some impediment to the current research activities. Despite external burdens, which have led to some delays and additional costs, three of the four refurbishment phases have been completed, and the corresponding laboratories were brought back into operation after inspection and approval by the regulatory authority HSK. Given the size and complexity of the project, progress must be considered very satisfactory. A list of scientific publications in 2000 is also provided.

DNFSB Recommendation 94-1 Hanford Site Integrated Stabilization Management Plan. Volume 2

International Nuclear Information System (INIS)

Gerber, E.W.

1995-10-01

The Hanford Site Integrated Stabilization Management Plan (SISMP) was developed in support of the US Department of Energy's (DOE) Defense Nuclear Facilities Safety Board (DNFSB) Recommendation 94-1 Integrated Program Plan (IPP). Volume 1 of the SISMP identifies the technical scope and costs associated with Hanford Site plans to resolve concerns identified in DNFSB Recommendation 94-1. Volume 2 of the SISMP provides the Resource Loaded Integrated Schedules for Spent Nuclear Fuel Project and Plutonium Finishing Plant activities identified in Volume 1 of the SISMP. Appendix A provides the schedules and progress curves related to spent nuclear fuel management. Appendix B provides the schedules and progress curves related to plutonium-bearing material management. Appendix C provides programmatic logic diagrams that were referenced in Volume 1 of the SISMP

Spent Nuclear Fuel Project technical baseline document. Fiscal year 1995: Volume 1, Baseline description

International Nuclear Information System (INIS)

Womack, J.C.; Cramond, R.; Paedon, R.J.

1995-01-01

This document is a revision to WHC-SD-SNF-SD-002, and is issued to support the individual projects that make up the Spent Nuclear Fuel Project in the lower-tier functions, requirements, interfaces, and technical baseline items. It presents results of engineering analyses since Sept. 1994. The mission of the SNFP on the Hanford site is to provide safety, economic, environmentally sound management of Hanford SNF in a manner that stages it to final disposition. This particularly involves K Basin fuel, although other SNF is involved also

Fluorescence Exclusion: A Simple Method to Assess Projected Surface, Volume and Morphology of Red Blood Cells Stored in Blood Bank

Directory of Open Access Journals (Sweden)

Camille Roussel

2018-05-01

Full Text Available Red blood cells (RBC ability to circulate is closely related to their surface area-to-volume ratio. A decrease in this ratio induces a decrease in RBC deformability that can lead to their retention and elimination in the spleen. We recently showed that a subpopulation of “small RBC” with reduced projected surface area accumulated upon storage in blood bank concentrates, but data on the volume of these altered RBC are lacking. So far, single cell measurement of RBC volume has remained a challenging task achieved by a few sophisticated methods some being subject to potential artifacts. We aimed to develop a reproducible and ergonomic method to assess simultaneously RBC volume and morphology at the single cell level. We adapted the fluorescence exclusion measurement of volume in nucleated cells to the measurement of RBC volume. This method requires no pre-treatment of the cell and can be performed in physiological or experimental buffer. In addition to RBC volume assessment, brightfield images enabling a precise definition of the morphology and the measurement of projected surface area can be generated simultaneously. We first verified that fluorescence exclusion is precise, reproducible and can quantify volume modifications following morphological changes induced by heating or incubation in non-physiological medium. We then used the method to characterize RBC stored for 42 days in SAG-M in blood bank conditions. Simultaneous determination of the volume, projected surface area and morphology allowed to evaluate the surface area-to-volume ratio of individual RBC upon storage. We observed a similar surface area-to-volume ratio in discocytes (D and echinocytes I (EI, which decreased in EII (7% and EIII (24%, sphero-echinocytes (SE; 41% and spherocytes (S; 47%. If RBC dimensions determine indeed the ability of RBC to cross the spleen, these modifications are expected to induce the rapid splenic entrapment of the most morphologically altered RBC

Passive ALWR safety: the ALPHA project at Switzerland's PSI - a progress report

International Nuclear Information System (INIS)

Yadigaroglu, G.; Varadi, G.; Dreier, J.

1995-01-01

The Paul Scherrer Institute (PSI) initiated the ALPHA project in 1991 for the experimental and analytical investigation of the long-term decay heat removal from the containment of the next generation of 'passive' advanced light water reactors (ALWRs). The dynamic containment response to such systems, as well as containment phenomena, are investigated. The ALPHA project includes integral system tests in the large-scale (1:25 in volume) PANDA facility; the smaller-scale separate effects LINX series of tests related to various passive containment mixing, stratification, and condensation phenomena in the presence of non-condensable gases; the AIDA tests on the behavior of aerosols in passive containment cooling systems (PCCS); and supporting analytical work. The project has been, so far, directed mainly to the investigation of the General Electric simplified boiling water reactor (SBWR) PCCS and related phenomena. (author) 2 figs., 4 refs

Kilowatt isotope power system. Phase II plan. Volume V. Safety, quality assurance and reliability

International Nuclear Information System (INIS)

1978-01-01

The development of a Kilowatt Isotope Power System (KIPS) was begun in 1975 for the purpose of satisfying the power requirements of satellites in the 1980's. The KIPS is a 238 PuO 2 -fueled organic Rankine cycle turbine power system to provide a design output of 500 to 2000 W. Included in this volume are: launch and flight safety considerations; quality assurance techniques and procedures to be followed through system fabrication, assembly and inspection; and the reliability program made up of reliability prediction analysis, failure mode analysis and criticality analysis

Criticality Safety Support to a Project Addressing SNM Legacy Items at LLNL

International Nuclear Information System (INIS)

Pearson, J S; Burch, J G; Dodson, K E; Huang, S T

2005-01-01

The programmatic, facility and criticality safety support staffs at the LLNL Plutonium Facility worked together to successfully develop and implement a project to process legacy (DNFSB Recommendation 94-1 and non-Environmental, Safety, and Health (ES and H) labeled) materials in storage. Over many years, material had accumulated in storage that lacked information to adequately characterize the material for current criticality safety controls used in the facility. Generally, the fissionable material mass information was well known, but other information such as form, impurities, internal packaging, and presence of internal moderating or reflecting materials were not well documented. In many cases, the material was excess to programmatic need, but such a determination was difficult with the little information given on MC and A labels and in the MC and A database. The material was not packaged as efficiently as possible, so it also occupied much more valuable storage space than was necessary. Although safe as stored, the inadequately characterized material posed a risk for criticality safety noncompliances if moved within the facility under current criticality safety controls. A Legacy Item Implementation Plan was developed and implemented to deal with this problem. Reasonable bounding conditions were determined for the material involved, and criticality safety evaluations were completed. Two appropriately designated glove boxes were identified and criticality safety controls were developed to safely inspect the material. Inspecting the material involved identifying containers of legacy material, followed by opening, evaluating, processing if necessary, characterizing and repackaging the material. Material from multiple containers was consolidated more efficiently thus decreasing the total number of stored items to about one half of the highest count. Current packaging requirements were implemented. Detailed characterization of the material was captured in databases

ARIES-AT safety design and analysis

Energy Technology Data Exchange (ETDEWEB)

Petti, D.A. [Idaho National Engineering and Environmental Laboratory, Fusion Safety Program, P.O. Box 1625, Idaho Falls, ID 83415 (United States)]. E-mail: David.Petti@inl.gov; Merrill, B.J. [Idaho National Engineering and Environmental Laboratory, Fusion Safety Program, P.O. Box 1625, Idaho Falls, ID 83415 (United States); Moore, R.L. [Idaho National Engineering and Environmental Laboratory, Fusion Safety Program, P.O. Box 1625, Idaho Falls, ID 83415 (United States); Longhurst, G.R. [Idaho National Engineering and Environmental Laboratory, Fusion Safety Program, P.O. Box 1625, Idaho Falls, ID 83415 (United States); El-Guebaly, L. [Fusion Technology Institute, 1500 Engineering Drive, University of Wisconsin-Madison, Madison, WI 53706 (United States); Mogahed, E. [Fusion Technology Institute, 1500 Engineering Drive, University of Wisconsin-Madison, Madison, WI 53706 (United States); Henderson, D. [Fusion Technology Institute, 1500 Engineering Drive, University of Wisconsin-Madison, Madison, WI 53706 (United States); Wilson, P. [Fusion Technology Institute, 1500 Engineering Drive, University of Wisconsin-Madison, Madison, WI 53706 (United States); Abdou, A. [Fusion Technology Institute, 1500 Engineering Drive, University of Wisconsin-Madison, Madison, WI 53706 (United States)

2006-01-15

ARIES-AT is a 1000 MWe conceptual fusion power plant design with a very low projected cost of electricity. The design contains many innovative features to improve both the physics and engineering performance of the system. From the safety and environmental perspective, there is greater depth to the overall analysis than in past ARIES studies. For ARIES-AT, the overall spectrum of off-normal events to be examined has been broadened. They include conventional loss of coolant and loss of flow events, an ex-vessel loss of coolant, and in-vessel off-normal events that mobilize in-vessel inventories (e.g., tritium and tokamak dust) and bypass primary confinement such as a loss of vacuum and an in-vessel loss of coolant with bypass. This broader examination of accidents improves the robustness of the design from the safety perspective and gives additional confidence that the facility can meet the no-evacuation requirement under average weather conditions. We also provide a systematic assessment of the design to address key safety functions such as confinement, decay heat removal, and chemical energy control. In the area of waste management, both the volume of the component and its hazard are used to classify the waste. In comparison to previous ARIES designs, the overall waste volume is less because of the compact design.

Reports on research projects sponsored by the Federal Minister for Research and Technology in the field of reactor safety

International Nuclear Information System (INIS)

1979-03-01

Investigations on the safety of Light Water Reactors (LWR) being performed in the framework of the Research Program Reactor Safety (RS - Projects) are sponsored by the BMFT (Federal Minister for Research and Technology), Bundesminister fuer Forschung und Technologie. Objective of this program is to investigate in greater detail the safety margins of nuclear power plants and their systems and the further development of safety technology. Besides the investigations of LWR tasks first projects on the safety of FBR type reactors are sponsored by the BMFT. The GRS (Reactor Safety Association), Gesellschaft fuer Reaktorsicherheit mbH, by order of the BMFT, informs continuously of the status of such investigations by means of quarterly and annually publication of progress reports within the series GRS - F - Fortschrittsberichte (GRS - F - Progress Reports). Each progress report represents a compilation of individual reports about objectives, the work performed, the results, the next steps of the work etc. The individual reports are prepared in a standard form by the contractors themselves as a documentation of their progress in work. The individual reports are arranged according to the amended LWR Safety Research Program of the BMFT. Another table contents uses the same classification system as applied in the Nuclear Safety Index of the CEC European Communities and the OECD. (orig./HP) [de

Waste Tank Organic Safety Project organic concentration mechanisms task. FY 1994 progress report

International Nuclear Information System (INIS)

Gerber, M.A.

1994-09-01

The Pacific Northwest Laboratory (PNL), Waste Tank Organic Safety Project is conducting research to support Westinghouse Hanford Company's (WHC) Waste Tank Safety Program, sponsored by the U.S. Department of Energy's Tank Farm Project Office. The goal of PNL's program is to provide a scientific basis for analyzing organics in Hanford's underground storage tanks (USTs) and for determining whether they are at concentrations that pose a potentially unsafe condition. Part of this research is directed toward determining what organic concentrations are safe by conducting research on organic aging mechanisms and waste energetics to assess the conditions necessary to produce an uncontrolled energy release in tanks due to reactions between the organics and the nitrate and nitrate salts in the tank wastes. The objective of the Organic Concentration Mechanisms Task is to assess the degree of localized enrichment of organics to be expected in the USTs due to concentration mechanisms. This report describes the progress of research conducted in FY 1994 on two concentration mechanisms of interest to the tank safety project: (1) permeation of a separate organic liquid phase into the interstitial spaces of the tank solids during the draining of free liquid from the tanks; and (2) concentration of organics on the surfaces of the solids due to adsorption. Three experiments were conducted to investigate permeation of air and solvent into a sludge simulant that is representative of single-shell tank sludge. The permeation behavior of air and solvent into the sludge simulant can be explained by the properties of the fluid pairs (air/supernate and solvent supernate) and the sludge. One important fluid property is the interfacial tension between the supernate and either the solvent or air. In general, the greater the interfacial tension between two fluids, the more difficult it will be for the air or solvent to displace the supernate during dewatering of the sludge