Project SFR 1 SAR-08. Update of priority of FEPs from Project SAFE

International Nuclear Information System (INIS)

Gordon, Anna; Loefgren, Martin; Lindgren, Maria

2008-03-01

SFR 1 is a repository for final disposal of low and intermediate level radioactive waste produced at Swedish nuclear power plants, as well as at Swedish industrial, research, and medical treatment facilities. The repository obtained operational license in March 1988. The aim of Project SFR 1 SAR-08 is to perform an updated safety analysis, according to requirements in the regulations. A major difference between this and previous safety analyses is that repository safety should be demonstrated for 100,000 years after repository closure. This should be compared with the time frame of the safety assessment in Project SAFE that was 10,000 years. Due to the extended time frame, permafrost and glaciation have to be considered in the reference evolution of Project SFR 1 SAR-08. Other rationales for the update are recent input from the authorities concerning SAFE documents and the SFR 1 repository, as well as new data concerning the SFR 1 inventory. This report describes the outcome of revisiting the qualitative FEP (Features, Events and Processes) analysis carried out within Project SAFE for the SFR 1 repository. Each and every interaction definition, as defined in SAFE, has been examined with the aim at assuring that the SAFE interaction matrices are also applicable for SAR-08. It was found that this is generally the case, but seven new interactions were defined in order to make the interaction matrices more applicable for SAR-08. The priority of all interactions assigned priority 1 and many interactions assigned priority 2 in SAFE have been carefully examined. The examination has been made in the context of the general initial and boundary conditions that should also form the basis for the SAR-08 main scenario and less probable scenarios. In 48 cases, the priority of the interaction needed upgrading, compared to in SAFE. In a majority of these cases, the upgrade is due to the extended time frame of the safety assessment, from 10,000 years in SAFE to 100,000 years in SAR

Project SFR 1 SAR-08. Update of priority of FEPs from Project SAFE

Energy Technology Data Exchange (ETDEWEB)

Gordon, Anna (Swedish Nuclear Fuel and Waste Management Co., Stockholm (SE)); Loefgren, Martin; Lindgren, Maria (Kemakta Konsult AB, Stockholm (SE)) (eds.)

2008-03-15

SFR 1 is a repository for final disposal of low and intermediate level radioactive waste produced at Swedish nuclear power plants, as well as at Swedish industrial, research, and medical treatment facilities. The repository obtained operational license in March 1988. The aim of Project SFR 1 SAR-08 is to perform an updated safety analysis, according to requirements in the regulations. A major difference between this and previous safety analyses is that repository safety should be demonstrated for 100,000 years after repository closure. This should be compared with the time frame of the safety assessment in Project SAFE that was 10,000 years. Due to the extended time frame, permafrost and glaciation have to be considered in the reference evolution of Project SFR 1 SAR-08. Other rationales for the update are recent input from the authorities concerning SAFE documents and the SFR 1 repository, as well as new data concerning the SFR 1 inventory. This report describes the outcome of revisiting the qualitative FEP (Features, Events and Processes) analysis carried out within Project SAFE for the SFR 1 repository. Each and every interaction definition, as defined in SAFE, has been examined with the aim at assuring that the SAFE interaction matrices are also applicable for SAR-08. It was found that this is generally the case, but seven new interactions were defined in order to make the interaction matrices more applicable for SAR-08. The priority of all interactions assigned priority 1 and many interactions assigned priority 2 in SAFE have been carefully examined. The examination has been made in the context of the general initial and boundary conditions that should also form the basis for the SAR-08 main scenario and less probable scenarios. In 48 cases, the priority of the interaction needed upgrading, compared to in SAFE. In a majority of these cases, the upgrade is due to the extended time frame of the safety assessment, from 10,000 years in SAFE to 100,000 years in SAR

Project SFR 1 SAR-08. Update of priority of FEPs from Project SAFE

Energy Technology Data Exchange (ETDEWEB)

Gordon, Anna [Swedish Nuclear Fuel and Waste Management Co., Stockholm (SE); Loefgren, Martin; Lindgren, Maria [Kemakta Konsult AB, Stockholm (SE); eds.

2008-03-15

SFR 1 is a repository for final disposal of low and intermediate level radioactive waste produced at Swedish nuclear power plants, as well as at Swedish industrial, research, and medical treatment facilities. The repository obtained operational license in March 1988. The aim of Project SFR 1 SAR-08 is to perform an updated safety analysis, according to requirements in the regulations. A major difference between this and previous safety analyses is that repository safety should be demonstrated for 100,000 years after repository closure. This should be compared with the time frame of the safety assessment in Project SAFE that was 10,000 years. Due to the extended time frame, permafrost and glaciation have to be considered in the reference evolution of Project SFR 1 SAR-08. Other rationales for the update are recent input from the authorities concerning SAFE documents and the SFR 1 repository, as well as new data concerning the SFR 1 inventory. This report describes the outcome of revisiting the qualitative FEP (Features, Events and Processes) analysis carried out within Project SAFE for the SFR 1 repository. Each and every interaction definition, as defined in SAFE, has been examined with the aim at assuring that the SAFE interaction matrices are also applicable for SAR-08. It was found that this is generally the case, but seven new interactions were defined in order to make the interaction matrices more applicable for SAR-08. The priority of all interactions assigned priority 1 and many interactions assigned priority 2 in SAFE have been carefully examined. The examination has been made in the context of the general initial and boundary conditions that should also form the basis for the SAR-08 main scenario and less probable scenarios. In 48 cases, the priority of the interaction needed upgrading, compared to in SAFE. In a majority of these cases, the upgrade is due to the extended time frame of the safety assessment, from 10,000 years in SAFE to 100,000 years in SAR

Project management plan for Reactor 105-C Interim Safe Storage project

International Nuclear Information System (INIS)

Plagge, H.A.

1996-09-01

Reactor 105-C (located on the Hanford Site in Richland, Washington) will be placed into an interim safe storage condition such that (1) interim inspection can be limited to a 5-year frequency; (2) containment ensures that releases to the environmental are not credible under design basis conditions; and (3) final safe storage configuration shall not preclude or significantly increase the cost for any decommissioning alternatives for the reactor assembly.This project management plan establishes plans, organizational responsibilities, control systems, and procedures for managing the execution of Reactor 105-C interim safe storage activities to meet programmatic requirements within authorized funding and approved schedules

Ensuring safe operation at the Loviisa nuclear power plant

International Nuclear Information System (INIS)

Regnell, B.

1985-01-01

Safe operation of a nuclear plant can be achieved only if the plant is designed according to stringent safety principles, if the construction and commissioning work meets high standards and finally if proper attention is paid to the safety aspects in all operational activities. Clearly formulated safety principles and standards are required for all these steps. In the early phases of the Loviisa project only a few IAEA codes of practice and safety guides were available. Their usefulness was, however, felt early, and valuable guidance was offered by them in formulating the quality assurance programme, for example. The paper describes the approach taken in order to achieve high operational safety at the first nuclear power station in Finland, the Loviisa plant. The involvement in the project of the plant owner, Imatran Voima Oy (IVO), was very large, the company serving as its own architect-engineer. Experience has shown that the thorough knowledge of the plant, down to the finest details, obtained by extensive participation in design, erection and commissioning of the plant, is invaluable in the actual operation of the plant. This manifests itself most clearly in the event of malfunctions and incidents or if modifications have to be undertaken. Many different activities affecting the operational safety can be identified: actual operation of the plant, including the creation and maintaining of technical specifications, procedures, instructions, documentation systems, etc.; maintenance, repair and modification work; in-service inspection and testing practices; component failure data collection and analysis; incident reporting, collection and evaluation systems; operator training; quality assurance programme; procedures and implementation; reviews of operational safety by an independent safety committee; and supervision by the safety authorities. In the paper, all these activities are described in some detail. (author)

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

Guideline for the preparation of safe operating procedures

International Nuclear Information System (INIS)

Stinnett, L.; Carroll, M.M.; Crooks, D.L.; Doyle, J.R.; Jeblick, H.G.; Kessel, D.S.; Tippy, M.W.; Stuckey, J.M.

1981-03-01

These procedures are written for activities that involve the use of explosives, dangerous chemicals, radioactive materials, hazardous sytems, and for certain types of operational facilities which present hazards. This guideline presents a suggested Safe Operating Procedures format

Method of safely operating nuclear reactor

International Nuclear Information System (INIS)

Ochiai, Kanehiro.

1976-01-01

Purpose: To provide a method of safely operating an nuclear reactor, comprising supporting a load applied to a reactor container partly with secondary container facilities thereby reducing the load borne by the reactor container when water is injected into the core to submerge the core in an emergency. Method: In a reactor emergency, water is injected into the reactor core thereby to submerge the core. Further, water is injected into a gap between the reactor container and the secondary container facilities. By the injection of water into the gap between the reactor container and the secondary container facilities a large apparent mass is applied to the reactor container, as a result of which the reactor container undergoes the same vibration as that of the secondary container facilities. Therefore, the load borne by the reactor container itself is reduced and stress at the bottom part of the reactor container is released. This permits the reactor to be operated more safely. (Moriyama, K.)

Guideline for the preparation of safe operating procedures

International Nuclear Information System (INIS)

Stinnett, L.; Armbrust, E.F.; Christy, V.W.; Doyle, J.R.; Kesinger, J.H.

1977-03-01

Sandia Laboratories Safe Operating Procedures (SOP) are written for activities which involve the use of explosives, dangerous chemicals, radioactive materials, hazardous systems, and certain types of operational facilities which present hazards. This guideline presents a suggested SOP format

Embracing Safe Ground Test Facility Operations and Maintenance

Science.gov (United States)

Dunn, Steven C.; Green, Donald R.

2010-01-01

Conducting integrated operations and maintenance in wind tunnel ground test facilities requires a balance of meeting due dates, efficient operation, responsiveness to the test customer, data quality, effective maintenance (relating to readiness and reliability), and personnel and facility safety. Safety is non-negotiable, so the balance must be an "and" with other requirements and needs. Pressure to deliver services faster at increasing levels of quality in under-maintained facilities is typical. A challenge for management is to balance the "need for speed" with safety and quality. It s especially important to communicate this balance across the organization - workers, with a desire to perform, can be tempted to cut corners on defined processes to increase speed. Having a lean staff can extend the time required for pre-test preparations, so providing a safe work environment for facility personnel and providing good stewardship for expensive National capabilities can be put at risk by one well-intending person using at-risk behavior. This paper documents a specific, though typical, operational environment and cites management and worker safety initiatives and tools used to provide a safe work environment. Results are presented and clearly show that the work environment is a relatively safe one, though still not good enough to keep from preventing injury. So, the journey to a zero injury work environment - both in measured reality and in the minds of each employee - continues. The intent of this paper is to provide a benchmark for others with operational environments and stimulate additional sharing and discussion on having and keeping a safe work environment.

Project management plan for the 105-C Reactor interim safe storage project. Revision 1

International Nuclear Information System (INIS)

Miller, R.L.

1997-01-01

In 1942, the Hanford Site was commissioned by the US Government to produce plutonium. Between 1942 and 1955, eight water-cooled, graphite-moderated reactors were constructed along the Columbia River at the Hanford Site to support the production of plutonium. The reactors were deactivated from 1964 to 1971 and declared surplus. The Surplus Production Reactor Decommissioning Project (BHI 1994b) will decommission these reactors and has selected the 105-C Reactor to be used as a demonstration project for interim safe storage at the present location and final disposition of the entire reactor core in the 200 West Area. This project will result in lower costs, accelerated schedules, reduced worker exposure, and provide direct benefit to the US Department of Energy for decommissioning projects complex wide. This project sets forth plans, organizational responsibilities, control systems, and procedures to manage the execution of the Project Management Plan for the 105-C Reactor Interim Safe Storage Project (Project Management Plan) activities to meet programmatic requirements within authorized funding and approved schedules. The Project Management Plan is organized following the guidelines provided by US Department of Energy Order 4700.1, Project Management System and the Richland Environmental Restoration Project Plan (DOE-RL 1992b)

PROJECTIZING AN OPERATING NUCLEAR FACILITY

International Nuclear Information System (INIS)

Adams, N

2007-01-01

This paper will discuss the evolution of an operations-based organization to a project-based organization to facilitate successful deactivation of a major nuclear facility. It will describe the plan used for scope definition, staff reorganization, method estimation, baseline schedule development, project management training, and results of this transformation. It is a story of leadership and teamwork, pride and success. Workers at the Savannah River Site's (SRS) F Canyon Complex (FCC) started with a challenge--take all the hazardous byproducts from nearly 50 years of operations in a major, first-of-its-kind nuclear complex and safely get rid of them, leaving the facility cold, dark, dry and ready for whatever end state is ultimately determined by the United States Department of Energy (DOE). And do it in four years, with a constantly changing workforce and steadily declining funding. The goal was to reduce the overall operating staff by 93% and budget by 94%. The facilities, F Canyon and its adjoined sister, FB Line, are located at SRS, a 310-square-mile nuclear reservation near Aiken, S.C., owned by DOE and managed by Washington Group International subsidiary Washington Savannah River Company (WSRC). These facilities were supported by more than 50 surrounding buildings, whose purpose was to provide support services during operations. The radiological, chemical and industrial hazards inventory in the old buildings was significant. The historical mission at F Canyon was to extract plutonium-239 and uranium-238 from irradiated spent nuclear fuel through chemical processing. FB Line's mission included conversion of plutonium solutions into metal, characterization, stabilization and packaging, and storage of both metal and oxide forms. The plutonium metal was sent to another DOE site for use in weapons. Deactivation in F Canyon began when chemical separations activities were completed in 2002, and a cross-functional project team concept was implemented to successfully

Engineering and planning for reactor 105-C interim safe storage project subcontract no. 0100C-SC-G0001 conceptual design report. Volume 1

International Nuclear Information System (INIS)

1996-04-01

The 105-C Reactor, one of eight surplus production reactors at the Hanford Site, has been proposed by the U.S. Department of Energy, Richland, Operations Office to be the first large-scale technology demonstration project in the decontamination and decommissioning (D ampersand D) focus area as part of the project for dismantlement and interim safe storage. The 105-C Reactor will be placed in an interim safe storage condition, then undergo the decontamination and decommissioning phase. After D ampersand D, the reactor will be placed in long- term safe storage. This report provides the conceptual design for these activities

[Prevention of adverse effects in latex allergic patients: organizing a latex safe operating theatre].

Science.gov (United States)

Bonalumi, Sabrina; Barbonaglia, Patrizia; Bertocchi, Carmen

2006-01-01

In 2001 the General Health Direction of Region Lombardia approved (decree n. 22303) a guideline for the prevention of latex allergic reactions in patients and health care workers. This document provides general recommendations in order to standardize behaviors in regional health care facilities. The reason is due to a rise in the incident of reactions to latex products in the last 20 years. Nowadays the prevalence is higher in certain risk groups (subjected to frequent and repeated exposures) rather than the general population. The aim of the project was to organize a latex safe operating theatre in the Ospedale Maggiore Policlinico, Mangiagalli e Regina Elena of Milan (Fondazione) and to standardize behaviors in order to prevent adverse effects in latex allergic patients. Thanks to the literature review and the creation of a multidisciplinar team, we produced a protocol. Therefore, we requested manufacturers the certification of the latex content of their products. Results and conclusion. When latex allergic patients need to undergone surgery in our hospital, a latex safe operating theatre is organized by personnel following a multidisciplinar protocol. No allergic reactions were experienced during surgical procedures after the creation of an environment as free as possible from latex contamination. The project will involve an emergency room, one room or more of a ward and of the outpatients department.

Importance of safety review to the safe operation of a nuclear plant

International Nuclear Information System (INIS)

Brinkerhoff, L.C.

1978-01-01

Widely differing standards of construction of nuclear reactors are employed in different countries. Although the reactor vendors, including designers and construction contractors, have a vested interest in safety, the ultimate responsibility for safety rests with the reactor facility operator. Even though governmental agencies, either directly or indirectly, must take a strong lead in developing policies and practices of safe operation, the reactor facility operator must recognize and accept the full responsibility for safe operation of the facility. The policies and practices of safe operation imposed by governmental agencies must help assure the prudent operation and the adequate maintenance of those structures, systems, and components of importance to safety. Since each country has a slightly different philosophy for achieving safety and each vendor utilizes different structures, systems, and components to fulfil this philosophy, it is imperative that the facility operator adequately maintain those engineered safety features and those plant protective systems which have been engineered into achieving the desired levels of safety. An additional method of helping to assure that those structures, systems, and components of importance to safety are prudently operated and adequately maintained is to assign the full safety responsibility for the overall operations of the reactor facility to the operating organization, i.e. assigning a 'line of responsibility' within the reactor facility operator. This assurance can be further strengthened by requiring that the facility operator establish a safety review body that overviews the operation and assures that the operating organization complies with those policies and practices of safe operation which have been imposed on the reactor facility. (author)

Digital image monitoring to optimise safe port operation

CSIR Research Space (South Africa)

Phelp, D

2008-11-01

Full Text Available This paper describes a low cost video system ‘Harbour Watch’, which can be used to support safe port operations, especially in developing countries. Preset digital images are geo-referenced and then archived for later analysis to improve...

Safe Operation of Nuclear Power Plants. Code of Practice and Technical Appendices

International Nuclear Information System (INIS)

1969-01-01

This book is in two parts. The first is a Code of Practice for the Safe Operation of Nuclear Power Plants and the second part is a compilation of technical appendices. Its object is to give information and illustrative examples that would be helpful in implementing the Code of Practice. This second part, although published under the same cover, is not part of the Code. Safe operation of a nuclear power plant postulates suitable siting and proper design, construction and management of the plant. Under the present Code of Practice for the Safe Operation of Nuclear Power Plants, those intending to operate the plant are recommended to prepare documentation which would deal with its operation and include safety analyses. The documentation in question would be reviewed by a regulatory body independent of the operating organization; operation would be authorized on the understanding that it would comply with limits and conditions designed to ensure safety. The Code may be subject to revision in the light of experience. The Appendices provide additional information together with some examples relating to certain topics dealt with in the Code; it must be emphasized that they are included as examples for information only and are not part of any recommendation. Purpose and scope: The recommendations in the Code are designed to protect the general public and the operating personnel from radiation hazards, and the Code forms part of the Agency's Safety Standards. The Code, which should be used in conjunction with the Agency's other Safety Standards, provides guidance and information to persons and authorities responsible for the operation of stationary nuclear power plants whose main function is the generation of thermal, mechanical or electrical power; it is not intended to apply to reactors used solely for experimental or research purposes. It sets forth minimum requirements which, it is believed, in the light of experience, must be met in order to achieve safe operation of a

Systems for the safe operation of the JET tokamak with tritium

International Nuclear Information System (INIS)

Stork, D.; Ageladarakis, P.; Bell, A.C.

1999-01-01

In 1997, the JET device was operated for an extensive campaign with deuterium-tritium (D-T) plasmas (the DTE1 campaign). A comprehensive network of machine protection systems was necessary so that this experimental campaign could be executed safely without damage to the machine or release of activated material. This network had been developed over many years of JET deuterium plasma operation and therefore the modifications for D-T operation was not a significant problem. The DTE1 campaign was executed successfully and safely and the machine protection systems proved reliable and robust and, in the limited cases where they were required to act, functioned correctly. The machine protection systems at JET are described and their categorisation and development over time are summarised. The management, commissioning and operational experience during DTE1 are discussed and some examples of fault scenarios are described. The experience with protection systems at JET highlights the importance of correct design and philosophy decisions being taken at an early stage. It is shown that this experience will be invaluable data input to the safe operation of future large fusion machines. (orig.)

Manpower development for safe operation of nuclear power plant. China. Simulator software development. UNDP-Activity: 2.1.8-IAEA-Task-01. Technical report

International Nuclear Information System (INIS)

Feng, C.P.

1994-01-01

In the frameworks of the project ''manpower development for safe operation of nuclear power plant'' the development of reactor simulator software is described. Qinshan nuclear power plant was chosen as a reference one

VISIR: technological infrastructure of an operational service for safe and efficient navigation in the Mediterranean Sea

Science.gov (United States)

Mannarini, Gianandrea; Turrisi, Giuseppe; D'Anca, Alessandro; Scalas, Mario; Pinardi, Nadia; Coppini, Giovanni; Palermo, Francesco; Carluccio, Ivano; Scuro, Matteo; Cretì, Sergio; Lecci, Rita; Nassisi, Paola; Tedesco, Luca

2016-08-01

VISIR (discoVerIng Safe and effIcient Routes) is an operational decision support system (DSS) for optimal ship routing designed and implemented in the frame of the TESSA (TEchnology for Situational Sea Awareness) project. The system is aimed to increase safety and efficiency of navigation through the use of forecast environmental fields and route optimization. VISIR can be accessed through a web interface (www.visir-nav.com) and mobile applications for both iOS and Android devices. This paper focuses on the technological infrastructure developed for operating VISIR as a DSS. Its main components are described, the performance of the operational system is assessed through experimental measurements, and a few case studies are presented.

Safe Operation of Nuclear Power Plants: Impacts of Human and Organisational Factors and Emerging Technologies

International Nuclear Information System (INIS)

2001-01-01

In co-operation with the OECD Nuclear Energy Agency (NEA), the Halden Reactor Project organised a Summer School on ''Safe Operation of Nuclear Power Plants: Impacts of Human and Organisational Factors and Emerging Technologies'' in the period August 27-August 31, 2001. The Summer School was intended for scientists, engineers and technicians working for nuclear installations, engineering companies, industry and members of universities and research institutes, who wanted to broaden their nuclear background by getting acquainted with Man-Technology-Organisation-related subjects and issues. The Summer School should also serve to transfer knowledge to the ''young generation'' in the nuclear field. The following presentations were given: (1) Overview of the Nuclear Community and Current issues, (2) The Elements of Safety Culture; Evaluation of Events, (3) Quality Management (QM), (4) Probabilistic Risk Assessment (PSA), (5) Human Behaviour from the Viewpoint of Industrial Psychology, (6) Technical tour of the Halden Project Experimental Facilities, (7) Human Factors in Control Room Design, (8) Computerised Operator Support Systems (COSSs) and (9) Artificial Intelligence; a new Approach. Most of the contributions are overhead figures from spoken lectures

Safe Operation of Nuclear Power Plants: Impacts of Human and Organisational Factors and Emerging Technologies

Energy Technology Data Exchange (ETDEWEB)

NONE

2001-07-01

In co-operation with the OECD Nuclear Energy Agency (NEA), the Halden Reactor Project organised a Summer School on ''Safe Operation of Nuclear Power Plants: Impacts of Human and Organisational Factors and Emerging Technologies'' in the period August 27-August 31, 2001. The Summer School was intended for scientists, engineers and technicians working for nuclear installations, engineering companies, industry and members of universities and research institutes, who wanted to broaden their nuclear background by getting acquainted with Man-Technology-Organisation-related subjects and issues. The Summer School should also serve to transfer knowledge to the ''young generation'' in the nuclear field. The following presentations were given: (1) Overview of the Nuclear Community and Current issues, (2) The Elements of Safety Culture; Evaluation of Events, (3) Quality Management (QM), (4) Probabilistic Risk Assessment (PSA), (5) Human Behaviour from the Viewpoint of Industrial Psychology, (6) Technical tour of the Halden Project Experimental Facilities, (7) Human Factors in Control Room Design, (8) Computerised Operator Support Systems (COSSs) and (9) Artificial Intelligence; a new Approach. Most of the contributions are overhead figures from spoken lectures.

Safety analysis to support a safe operating envelope for fuel

International Nuclear Information System (INIS)

Gibb, R.A.; Reid, P.J.

1998-01-01

This paper presents an approach for defining a safe operating envelope for fuel. 'Safe operating envelope' is defined as an envelope of fuel parameters defined for application in safety analysis that can be related to, or used to define, the acceptable range of fuel conditions due to operational transients or deviations in fuel manufacturing processes. The paper describes the motivation for developing such a methodology. The methodology involved four steps: the update of fission product inventories, the review of sheath failure criteria, a review of input parameters to be used in fuel modelling codes, and the development of an improved fission product release code. This paper discusses the aspects of fuel sheath failure criteria that pertain to operating or manufacturing conditions and to the evaluation and selection of modelling input data. The other steps are not addressed in this paper since they have been presented elsewhere. (author)

VISIR: technological infrastructure of an operational service for safe and efficient navigation in the Mediterranean Sea

OpenAIRE

G. Mannarini; G. Turrisi; A. D'Anca; M. Scalas; N. Pinardi; G. Coppini; F. Palermo; I. Carluccio; M. Scuro; S. Cretì; R. Lecci; P. Nassisi; L. Tedesco

2016-01-01

VISIR (discoVerIng Safe and effIcient Routes) is an operational decision support system (DSS) for optimal ship routing designed and implemented in the frame of the TESSA (TEchnology for Situational Sea Awareness) project. The system is aimed to increase safety and efficiency of navigation through the use of forecast environmental fields and route optimization. VISIR can be accessed through a web interface (www.visir-nav.com) and mobile applications for both iOS and Androi...

Characteristics of Young Children Exposed to Violence: The Safe Start Demonstration Project

Science.gov (United States)

Kaufman, Joy S.; Ortega, Sandra; Schewe, Paul A.; Kracke, Kristen

2011-01-01

The Safe Start demonstration projects, funded by the Office of Juvenile Justice and Delinquency Prevention (OJJDP) under the first phase of the Safe Start initiative, are primarily designed to influence change at the systems or macrolevels to reduce the incidence of and impact of exposure to violence for children aged birth to 6 years; direct…

Operationalizing safe operating space for regional social-ecological systems.

Science.gov (United States)

Hossain, Md Sarwar; Dearing, John A; Eigenbrod, Felix; Johnson, Fiifi Amoako

2017-04-15

This study makes a first attempt to operationalize the safe operating space concept at a regional scale by considering the complex dynamics (e.g. non-linearity, feedbacks, and interactions) within a systems dynamic model (SD). We employ the model to explore eight 'what if' scenarios based on well-known challenges (e.g. climate change) and current policy debates (e.g. subsidy withdrawal). The findings show that the social-ecological system in the Bangladesh delta may move beyond a safe operating space when a withdrawal of a 50% subsidy for agriculture is combined with the effects of a 2°C temperature increase and sea level rise. Further reductions in upstream river discharge in the Ganges would push the system towards a dangerous zone once a 3.5°C temperature increase was reached. The social-ecological system in Bangladesh delta may be operated within a safe space by: 1) managing feedback (e.g. by reducing production costs) and the slow biophysical variables (e.g. temperature, rainfall) to increase the long-term resilience, 2) negotiating for transboundary water resources, and 3) revising global policies (e.g. withdrawal of subsidy) that negatively impact at regional scales. This study demonstrates how the concepts of tipping points, limits to adaptations, and boundaries for sustainable development may be defined in real world social-ecological systems. Copyright © 2017 The Authors. Published by Elsevier B.V. All rights reserved.

Safe Operation of Critical Assemblies and Research Reactors

Energy Technology Data Exchange (ETDEWEB)

NONE

1961-05-15

This Manual is provided as a guide to the safe operation of critical assemblies and small research reactors. It is intended that it should be used by all authorities and persons concerned with, or responsible for, the use of such equipment, in addition to the scientists and technologists who are actually working with, or operating it. It is suggested that it will be of use to those wishing to design and manufacture, or purchase, critical assemblies or research reactors, as well as those already in possession of them, and that it will prove particularly helpful to those users who have no direct access to other collected sources of information. This Manual is not a set of rules or a code of practice, but a series of recommendations which must be interpreted with scientific judgement in their application to any particular problem. The guiding principles are given from which good operational procedures may be established and improved. The promulgation of rigid standards is both impossible and undesirable at the present time, since the topics discussed form part of a rapidly growing science and technology. Therefore, any recommendations made should not be used to restrict or inhibit future developments. The Manual is intended mainly for use in those Member States where there has been little experience in the operation of critical assemblies and research reactors. It has been compounded from the best practices which exist in Member States having a large amount of such experience, so that nothing in it should conflict with the best practices to be encountered in the field of safe operation.

Safe Operation of Critical Assemblies and Research Reactors

International Nuclear Information System (INIS)

1961-01-01

This Manual is provided as a guide to the safe operation of critical assemblies and small research reactors. It is intended that it should be used by all authorities and persons concerned with, or responsible for, the use of such equipment, in addition to the scientists and technologists who are actually working with, or operating it. It is suggested that it will be of use to those wishing to design and manufacture, or purchase, critical assemblies or research reactors, as well as those already in possession of them, and that it will prove particularly helpful to those users who have no direct access to other collected sources of information. This Manual is not a set of rules or a code of practice, but a series of recommendations which must be interpreted with scientific judgement in their application to any particular problem. The guiding principles are given from which good operational procedures may be established and improved. The promulgation of rigid standards is both impossible and undesirable at the present time, since the topics discussed form part of a rapidly growing science and technology. Therefore, any recommendations made should not be used to restrict or inhibit future developments. The Manual is intended mainly for use in those Member States where there has been little experience in the operation of critical assemblies and research reactors. It has been compounded from the best practices which exist in Member States having a large amount of such experience, so that nothing in it should conflict with the best practices to be encountered in the field of safe operation.

IAEA Project UKR/4/003, Ukraine: Training for safe operation and management of nuclear power plants

International Nuclear Information System (INIS)

Kossilov, A.; Ivanytskyy, V.

1998-01-01

The IAEA Project UKR/4/003 was established with the aim to develop and upgrade Ukrainian NPP personnel training system in order to enhance the NPP operational safety and improve NPP management, through development of the SAT concept for personnel training

Operational support of a safe operating envelope for fuel

International Nuclear Information System (INIS)

Chapman, T.J.; Gibb, R.A.

1998-01-01

The mandate of a station safety analysis group is to ensure that the station is operated and maintained in a manner consistent with the basis for our understanding of the safety consequences of process or human failures. As operating experience has developed an awareness of the significance of fuel manufacture and operating conditions on safety consequences has also grown. This awareness has led to a program that is designed to ensure that these influences are appropriately considered. This paper describes the projects that make up this program. (author)

Safe Operation of Nuclear Power Plants: Impacts of Human and Organisational Factors and Emerging Technologies

Energy Technology Data Exchange (ETDEWEB)

NONE

2001-07-01

In co-operation with the OECD Nuclear Energy Agency (NEA), the Halden Reactor Project organised a Summer School on ''Safe Operation of Nuclear Power Plants: Impacts of Human and Organisational Factors and Emerging Technologies'' in the period August 27-August 31, 2001. The Summer School was intended for scientists, engineers and technicians working for nuclear installations, engineering companies, industry and members of universities and research institutes, who wanted to broaden their nuclear background by getting acquainted with Man-Technology-Organisation-related subjects and issues. The Summer School should also serve to transfer knowledge to the ''young generation'' in the nuclear field. The following presentations were given: (1) Overview of the Nuclear Community and Current issues, (2) The Elements of Safety Culture; Evaluation of Events, (3) Quality Management (QM), (4) Probabilistic Risk Assessment (PSA), (5) Human Behaviour from the Viewpoint of Industrial Psychology, (6) Technical tour of the Halden Project Experimental Facilities, (7) Human Factors in Control Room Design, (8) Computerised Operator Support Systems (COSSs) and (9) Artificial Intelligence; a new Approach. Most of the contributions are overhead figures from spoken lectures.

Making operations on standard-library containers strongly exception safe

DEFF Research Database (Denmark)

Katajainen, Jyrki

2007-01-01

-library containers to provide the strong guarantee of exception safety, instead of the default guarantee, without violating the stringent performance requirements specified in the C++ standard. In particular, we show that every strongly exception-safe operation on dynamic arrays and ordered dictionaries is only...... a constant factor slower than the corresponding default-guarantee operation. In terms of the amount of space, the overhead introduced is linear in the number of elements stored....

Management for nuclear power plants for safe operation

International Nuclear Information System (INIS)

Kueffer, K.

1981-01-01

This lecture covers management aspects which have an immediate bearing on safety and identifies the objectives and tasks of management which are required for safe operation of a nuclear power plant and is based on the Codes of Practice and Safety Guides of the IAEA as well as arrangements in use at the Swiss Nuclear Power Station Beznau. (orig./RW)

Management of nuclear power plants for safe operation

International Nuclear Information System (INIS)

1984-01-01

This Guide identifies the main objectives and responsibilities of management with respect to safe operation of nuclear power plants. The Guide discusses the factors to be considered in structuring the operating organization to meet these objectives, to establish the management programmes that assure the safety tasks are performed, and to see that the services and facilities needed to accomplish the tasks are available. The Guide is primarily addressed to safety matters directly related to the operating phase. It assumes, in other words, that the safety aspects of siting, design, manufacturing and construction have been resolved. However, it also covers the interrelationships between operations and design, construction and commissioning, including the involvement of the operating organization in appropriate reviews of safety issues with reference to the future operating phase. The Guide is mainly restricted to matters of principle in relation to management-level decision making aimed at establishing safety policies. It is therefore not suitable for implementing such policies at the operational level. The IAEA Codes of Practice and Safety Guides provide detailed guidance for the latter purpose in those areas considered appropriate

Evaluation of safe performance secondary school driver education curriculum demonstration project

Science.gov (United States)

1983-06-01

The primary objective of this Project was to determine the crash reduction potential of a quality, competency-based driver training program known as the Safe Performance Curriculum (SPC). The experimental design called for the random assignment of 18...

Project Management Plan to Maintain Safe and Compliant Conditions at the Plutonium Finishing Plant

International Nuclear Information System (INIS)

COX, G.J.

1999-01-01

This Project Management Plan presents the overall plan, description, mission, and workscope for the Plutonium Finishing Plant (PFP) maintain safe and compliant conditions project at PFP. This plan presents the overall description, mission, work scope, and planning for the Plutonium Finishing Plant (PFP) Maintain Safe and Compliant Conditions Project at PFP. This project includes all tasks required to maintain the safety boundary for the PFP Complex, except for the 2736-2 Vault Complex and the 234-52 vaults and vault-type rooms. The intent of this plan is to describe how this project will be managed and integrated with the stabilization, and deactivation activities. This plan supplements the overall integrated plan presented in the Plutonium Finishing Plant Integrated Project Management Plan (IPMP), HNF-3617, Rev. 0. This is the top-level definitive project management document that specifies the technical (work scope), schedule, and cost baselines that will manage the execution of this project. It describes the organizational approach and roles/responsibilities implemented to execute the project. This plan is under configuration management and any deviations must be authorized by appropriate change control action

A Pilot Project Demonstrating that Combat Medics Can Safely Administer Parenteral Medications in the Emergency Department.

Science.gov (United States)

Schauer, Steven G; Cunningham, Cord W; Fisher, Andrew D; DeLorenzo, Robert A

2017-12-01

Introduction Select units in the military have improved combat medic training by integrating their functions into routine clinical care activities with measurable improvements in battlefield care. This level of integration is currently limited to special operations units. It is unknown if regular Army units and combat medics can emulate these successes. The goal of this project was to determine whether US Army combat medics can be integrated into routine emergency department (ED) clinical care, specifically medication administration. Project Design This was a quality assurance project that monitored training of combat medics to administer parenteral medications and to ensure patient safety. Combat medics were provided training that included direct supervision during medication administration. Once proficiency was demonstrated, combat medics would prepare the medications under direct supervision, followed by indirect supervision during administration. As part of the quality assurance and safety processes, combat medics were required to document all medication administrations, supervising provider, and unexpected adverse events. Additional quality assurance follow-up occurred via complete chart review by the project lead. Data During the project period, the combat medics administered the following medications: ketamine (n=13), morphine (n=8), ketorolac (n=7), fentanyl (n=5), ondansetron (n=4), and other (n=6). No adverse events or patient safety events were reported by the combat medics or discovered during the quality assurance process. In this limited case series, combat medics safely administered parenteral medications under indirect provider supervision. Future research is needed to further develop this training model for both the military and civilian setting. Schauer SG , Cunningham C W, Fisher AD , DeLorenzo RA . A pilot project demonstrating that combat medics can safely administer parenteral medications in the emergency department. Prehosp Disaster Med. 2017;32(6):679-681.

Software functions for safe operation - learning from Sizewell-B

International Nuclear Information System (INIS)

Welbourne, D.

1996-01-01

Future nuclear plants will use computer-based systems extensively. Regulatory acceptance must be planned and not underestimated. Commercial software packages will simplify it, but costly analysis and demonstration may be needed. Multiplexed control needs preparation of extensive configuration data and careful checking. On-screen soft control will need consideration of the integrity of the control path. Display design should follow human factors analysis of the operators' needs, and display layout needs great care for clarity. Computer-based system with planned quality will then bring great benefits in safe operation. (author) 1 fig., 3 refs

Planetary boundaries: exploring the safe operating space for humanity

Science.gov (United States)

Johan Rockström; Will Steffen; Kevin Noone; Asa Persson; F. Stuart Chapin; Eric Lambin; Timothy M. Lenton; Marten Scheffer; Carl Folke; Hans Joachim Schellnhuber; Björn Nykvist; Cynthia A. de Wit; Terry Hughes; Sander van der Leeuw; Henning Rodhe; Sverker Sörlin; Peter K. Snyder; Robert Costanza; Uno Svedin; Malin Falkenmark; Louise Karlberg; Robert W. Corell; Victoria J. Fabry; James Hansen; Brian Walker; Diana Liverman; Katherine Richardson; Paul Crutzen; Jonathan Foley

2009-01-01

Anthropogenic pressures on the Earth System have reached a scale where abrupt global environmental change can no longer be excluded. We propose a new approach to global sustainability in which we define planetary boundaries within which we expect that humanity can operate safely. Transgressing one or more planetary boundaries may be deleterious or even catastrophic due...

Psychosocial aspect of safe operation in Japanese nuclear power plants

International Nuclear Information System (INIS)

Kuroda, Isao

1988-01-01

It is not easy to reveal the reasons of safe operation of N.P.P. because many complicated factors are interrelated. However, to clarify the effective factors of the recent safe operation of Japanese N.P.P. is the important thema of research to continue this condition and the more improved level. At present, the follwing factors can be pointed out; 1) Influential safety policy of regulatory structures. 2) Enthusiastic and careful company policy on N.P.P. safety. 3) Close and stable relationship of the industries with companies on research, training and maintenance. 4) Collaborated safety research among scientific facilities, companies and manufacturers. 5) Good organization and management for N.P.P. personnel. 6) Well organized training program in company and training facilities. 7) Highly motivated N.P.P. personnel with high educational background. 8) Company atmosphere on N.P.P. safety. 9) Public opinion on nuclear power safety. (author)

A logic scheme for regulating safe operation of research reactors

Energy Technology Data Exchange (ETDEWEB)

Ahmad, E E [Reactor Department, Nuclear Research Center, Atomic Energy Authority, Cairo (Egypt); Effat, A; Rahman, F A [Operational Saety Dept, National Center of Nuclear Safety and Radiation Control Atomic Energy Authority, Cairo (Egypt)

1997-12-31

This investigation presents a logic scheme for regulating the safe operation of research reactor in accordance with the new revision of SS-35 and revised by the 10 CFR. It emphasizes the regulatory inspection and enforcement (RI end E) during the reactor operation phase. IT is developed to provide information, guidance and recommendations to be taken when constructing the RI and E program that could be applied to the operational phase of the egyptian Research Reactors. In the operational phase, the regulatory inspection (RI) means an examination, observation, measurement, or test undertaken or on behalf of the nuclear regulatory body (NRB) during operation to verify that the nuclear materials, components, systems and structures as well operational activities, processes, procedures and personnel competence and performance are in accordance with the requirements established or the provisions approved by NRB or specified in the operational license or contained in regulations. Regulatory inspection includes both routine and non-routine ones. Any of them may be announced or unannounced. The problems identified by the RI must be resolved by the proper RE actions. The RE actions include investigative and corrective RE actions. These RI and E procedures for regulating safe operation of research reactors are presented as flow charts and then developed as a computer logic scheme. The software program is very efficient, very friendly, very simple and is interactive in nature such that the program asks the user certain questions about essential steps that guide the (RI and E) for research reactors, and user responds. The program proceeds based on this response until all the necessary steps for (RI and E) are accomplished. 5 figs.

Changing pattern of landslide risk in Europe - The SafeLand project

Science.gov (United States)

Nadim, F.; Kalsnes, B.

2012-04-01

The need to protect people and property with a changing pattern of landslide hazard and risk caused by climate change and changes in demography, and the reality for societies in Europe to live with the risk associated with natural hazards, were the motives for the project SafeLand: "Living with landslide risk in Europe: Assessment, effects of global change, and risk management strategies." SafeLand is a large, integrating research project under the European Commission's 7th Framework Programme (FP7). The project started on 1 May 2009 and will end on 30 April 2012. It involves 27 partners from 12 European countries, and has international collaborators and advisers from China, India, USA, Japan and Hong Kong. SafeLand also involves 25 End-Users from 11 countries. SafeLand is coordinated by the International Centre for Geohazards (ICG) at Norwegian Geotechnical Institute in Norway. Further information on the SafeLand project can be found at its web site http://safeland-fp7.eu/. Main results achieved in SafeLand include: - Various guidelines related to landslide triggering processes and run-out modelling. - Development and testing of several empirical methods for predicting the characteristics of threshold rainfall events for triggering of precipitation-induced landslides, and development of an empirical model for assessing the changes in landslide frequency (hazard) as a function of changes in the demography and population density. - Guideline for landslide susceptibility, hazard and risk assessment and zoning. - New methodologies for physical and societal vulnerability assessment. - Identification of landslide hazard and risk hotspots for Europe. The results show clearly where areas with the largest landslide risk are located in Europe and the objective approach allows a ranking of the countries by exposed area and population. - Different regional and local climate model simulations over selected regions of Europe at spatial resolutions of 10x10 km and 2.8x2.8 km

Management of nuclear power plants for safe operation

International Nuclear Information System (INIS)

Kueffer, K.

1980-01-01

This lecture covers management aspects which have an immediate bearing on safety and identifies the objectives and tasks of management which are required for safe operation of a nuclear power plant and is based on the Codes of Practice and Safety Guides of the IAEA as well as arrangements in use at the Swiss Nuclear Power Station Beznau. This lecture - discusses the factors to be considered in structuring the operating organization, the support to be provided to plant management, the services and facilities needed and the management system for assuring the safety tasks are performed - describes the responsibilities of plant management and operating organization - outlines the requirements for recruitment, training and retraining as well as qualification and authorization of personnel - describes the programmes for maintenance, testing, examination, inspection, radiological protection, quality assurance, waste management, fuel management, emergency arrangement and security - describes the development of plant operating procedures including procedures to protect the personnel - outlines the requirements for initial and subsequent operation - describes the importance for evaluation and feedback of operating experience - describes the procedures for changes in hardware, procedures and set points - outlines the information flow and the requirements in reference to records and reports. (orig./RW)

105-C Reactor interim safe storage project technology integration plan

International Nuclear Information System (INIS)

Pulsford, S.K.

1997-01-01

The 105-C Reactor Interim Safe Storage Project Technology Integration Plan involves the decontamination, dismantlement, and interim safe storage of a surplus production reactor. A major goal is to identify and demonstrate new and innovative D and D technologies that will reduce costs, shorten schedules, enhance safety, and have the potential for general use across the RL complex. Innovative technologies are to be demonstrated in the following areas: Characterization; Decontamination; Waste Disposition; Dismantlement, Segmentation, and Demolition; Facility Stabilization; and Health and Safety. The evaluation and ranking of innovative technologies has been completed. Demonstrations will be selected from the ranked technologies according to priority. The contractor team members will review and evaluate the demonstration performances and make final recommendations to DOE

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

Spent Nuclear Fuel project, project management plan

International Nuclear Information System (INIS)

Fuquay, B.J.

1995-01-01

The Hanford Spent Nuclear Fuel Project has been established to safely store spent nuclear fuel at the Hanford Site. This Project Management Plan sets forth the management basis for the Spent Nuclear Fuel Project. The plan applies to all fabrication and construction projects, operation of the Spent Nuclear Fuel Project facilities, and necessary engineering and management functions within the scope of the project

Design review report: 200 East upgrades for Project W-314, tank farm restoration and safe operations

International Nuclear Information System (INIS)

Boes, K.A.

1998-01-01

This Design Review Report (DRR) documents the contractor design verification methodology and records associated with project W-314's 200 East (200E) Upgrades design package. The DRR includes the documented comments and their respective dispositions for this design. Acceptance of the comment dispositions and closure of the review comments is indicated by the signatures of the participating reviewers. Project W-314 is a project within the Tank Waste Remediation System (TWRS) Tank Waste Retrieval Program. This project provides capital upgrades for the existing Hanford tank farm waste transfer, instrumentation, ventilation, and electrical infrastructure systems. To support established TWRS programmatic objectives, the project is organized into two distinct phases. The initial focus of the project (i.e., Phase 1) is on waste transfer system upgrades needed to support the TWRS Privatization waste feed delivery system. Phase 2 of the project will provide upgrades to support resolution of regulatory compliance issues, improve tank infrastructure reliability, and reduce overall plant operating/maintenance costs. Within Phase 1 of the W-314 project, the waste transfer system upgrades are further broken down into six major packages which align with the project's work breakdown structure. Each of these six sub-elements includes the design, procurement, and construction activities necessary to accomplish the specific tank farm upgrades contained within the package. The first design package (AN Valve Pit Upgrades) was completed in November 1997, and the associated design verification activities are documented in HNF-1893. The second design package, 200 East (200E) Upgrades, was completed in March 1998. This design package identifies modifications to existing valve pits 241-AX-B and 241-A-B, as well as several new waste transfer pipelines to be constructed within the A Farm Complex of the 200E Area. The scope of the valve pit modifications includes new pit cover blocks, valve

Technical innovations at NPP Dukovany - for safe and efficient operation

International Nuclear Information System (INIS)

Sabata, M.; Vasa, I.

2000-01-01

Inherent features of the NPP Dukovany design provide a significant confidence in its nuclear safety assurance; among these features should be emphasised the reactor core stability and its control and protection system capability to hold the reactor in safe state following scram or accident conditions. Nevertheless, NPP Dukovany was designed in the early seventies, and current requirements for nuclear safety assurance are more strict and/or specific as a result of the technical development and lessons learned from nuclear accidents. The paper compares the safety design base established at the time of NPP Dukovany project implementation and the current reference design base. The paper also presents procedures applied to implement technical and operational measures which are introduced to fulfil the current basic safety criteria. The scope of such measures applied at NPP Dukovany is compared with that of EU countries introduced for the same reason - to meet the updated safety related requirements. Examples of some innovations already implemented or under implementation give an idea how NPP Dukovany proceeds in reaching the goal of harmonising its safety with the requirements to be met before the Czech Republic becomes a member country of the European Union. (author)

Recommended Practices for the Safe Design and Operation of Flywheels

Energy Technology Data Exchange (ETDEWEB)

Bender, Donald Arthur [Sandia National Lab. (SNL-CA), Livermore, CA (United States); Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

2015-12-01

Flywheel energy storage systems are in use globally in increasing numbers . No codes pertaining specifically to flywheel energy storage exist. A number of industrial incidents have occurred. This protocol recommends a technical basis for safe flywheel de sign and operation for consideration by flywheel developers, users of flywheel systems and standards setting organizations.

Polyfire project- an example of an industrial research project promoting safe industrial production of fire-resistant nanocomposites

International Nuclear Information System (INIS)

Vaquero, C; Lopez de Ipina, J; Galarza, N; Hargreaves, B; Weager, B; Breen, C

2011-01-01

New developments based on nanotechnology have to guarantee safe products and processes to be accepted by society. The Polyfire project will develop and scale-up techniques for processing halogen-free, fire-retardant nanocomposite materials and coatings based on unsaturated polyester resins and organoclays. The project includes a work package that will assess the Health and Environmental impacts derived from the manipulation of nanoparticles. This work package includes the following tasks: (1) Identification of Health and Environment Impacts derived from the processes, (2) Experimentation to study specific Nanoparticle Emissions, (3) Development of a Risk Management Methodology for the process, and (4) A Comparison of the Health and Environmental Impact of New and Existing Materials. To date, potential exposure scenarios to nanomaterials have been identified through the development of a Preliminary Hazard Analysis (PHA) of the new production processes. In the next step, these scenarios will be studied and simulated to evaluate potential emissions of nanomaterials. Polyfire is a collaborative European project, funded by the European Commission 7th Framework Programme (Grant Agreement No 229220). It features 11 partners from 5 countries (5 SMEs, 3 research institutes, 2 large companies, 1 association) and runs for three years (1st September 2009 - 31st August 2012). This project is an example of an industrial research development which aims to introduce to the market new products promoting the safe use of nanomaterials.

Polyfire project- an example of an industrial research project promoting safe industrial production of fire-resistant nanocomposites

Energy Technology Data Exchange (ETDEWEB)

Vaquero, C; Lopez de Ipina, J; Galarza, N [TECNALIA, Leonardo Da Vinci No 11, 01510 Minano (Alava) (Spain); Hargreaves, B; Weager, B [NetComposites Ltd, 4A Broom Business Park, Chesterfield S41 9QG (United Kingdom); Breen, C, E-mail: celinav@leia.es [Materials and Engineering Research Institute, Sheffield Hallam University, Sheffield S1 1WB (United Kingdom)

2011-07-06

New developments based on nanotechnology have to guarantee safe products and processes to be accepted by society. The Polyfire project will develop and scale-up techniques for processing halogen-free, fire-retardant nanocomposite materials and coatings based on unsaturated polyester resins and organoclays. The project includes a work package that will assess the Health and Environmental impacts derived from the manipulation of nanoparticles. This work package includes the following tasks: (1) Identification of Health and Environment Impacts derived from the processes, (2) Experimentation to study specific Nanoparticle Emissions, (3) Development of a Risk Management Methodology for the process, and (4) A Comparison of the Health and Environmental Impact of New and Existing Materials. To date, potential exposure scenarios to nanomaterials have been identified through the development of a Preliminary Hazard Analysis (PHA) of the new production processes. In the next step, these scenarios will be studied and simulated to evaluate potential emissions of nanomaterials. Polyfire is a collaborative European project, funded by the European Commission 7th Framework Programme (Grant Agreement No 229220). It features 11 partners from 5 countries (5 SMEs, 3 research institutes, 2 large companies, 1 association) and runs for three years (1st September 2009 - 31st August 2012). This project is an example of an industrial research development which aims to introduce to the market new products promoting the safe use of nanomaterials.

LHC collimator controls for a safe LHC operation

International Nuclear Information System (INIS)

Redaelli, S.; Assmann, R.; Losito, R.; Donze, M.; Masi, A.

2012-01-01

The Large Hadron Collider (LHC) collimation system is designed to protect the machine against beam losses and consists of 108 collimators, 100 of which are movable, located along the 27 km long ring and in the transfer lines. The cleaning performance and machine protection role of the system depend critically on accurate jaw positioning. A fully redundant control system has been developed to ensure that the collimators dynamically follow optimum settings in all phases of the LHC operational cycle. Jaw positions and collimator gaps are interlocked against dump limits defined redundantly as functions of time, beam energy and the β functions, which describe the focusing property of the beams. In this paper, the architectural choices that guarantee a safe LHC operation are presented. Hardware and software implementations that ensure the required performance are described. (authors)

`95 computer system operation project

Energy Technology Data Exchange (ETDEWEB)

Kim, Young Taek; Lee, Hae Cho; Park, Soo Jin; Kim, Hee Kyung; Lee, Ho Yeun; Lee, Sung Kyu; Choi, Mi Kyung [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

1995-12-01

This report describes overall project works related to the operation of mainframe computers, the management of nuclear computer codes and the project of nuclear computer code conversion. The results of the project are as follows ; 1. The operation and maintenance of the three mainframe computers and other utilities. 2. The management of the nuclear computer codes. 3. The finishing of the computer codes conversion project. 26 tabs., 5 figs., 17 refs. (Author) .new.

'95 computer system operation project

International Nuclear Information System (INIS)

Kim, Young Taek; Lee, Hae Cho; Park, Soo Jin; Kim, Hee Kyung; Lee, Ho Yeun; Lee, Sung Kyu; Choi, Mi Kyung

1995-12-01

This report describes overall project works related to the operation of mainframe computers, the management of nuclear computer codes and the project of nuclear computer code conversion. The results of the project are as follows ; 1. The operation and maintenance of the three mainframe computers and other utilities. 2. The management of the nuclear computer codes. 3. The finishing of the computer codes conversion project. 26 tabs., 5 figs., 17 refs. (Author) .new

Safety Analysis For Evaluating (SAFE) sUAS, Phase I

Data.gov (United States)

National Aeronautics and Space Administration — NASA's Unmanned Aircraft Systems Integration in the NAS (UAS in the NAS) project is aimed at developing new technologies to enable safe operations of UAS in the NAS....

Seniority in projection operator formalism

International Nuclear Information System (INIS)

Ullah, N.

1976-01-01

It is shown that the concept of seniority can be introduced in projection operator formalism through the use of the operator Q, which has been defined by de-Shalit and Talmi. The usefulness of seniority concept in projection operator formalism is discussed. An example of four nucleons in j=3/2 configuration is given for illustrative purposes

Unmanned Aerial Systems Traffic Management (UTM): Safely Enabling UAS Operations in Low-Altitude Airspace

Science.gov (United States)

Jung, Jaewoo; Kopardekar, Parimal H.

2016-01-01

Flexibility where possible, and structure where necessary. Consider the needs of national security, safe airspace operations, economic opportunities, and emerging technologies. Risk-based approach based on population density, assets on the ground, density of operations, etc. Digital, virtual, dynamic, and as needed UTM services to manage operations.

Blue limits of the Blue Planet : An exploratory analysis of safe operating spaces for human water use under deep uncertainty

NARCIS (Netherlands)

Kwakkel, J.H.; Timmermans, J.S.

2012-01-01

In the Nature article ‘A safe operating space for humanity’, Rockström et al. (2009) introduce the concept of a safe operating space for humanity. A safe operating space is the space for human activities that will not push the planet out of the ‘Holocene state’ that has seen human civilizations

49 CFR 398.5 - Parts and accessories necessary for safe operation.

Science.gov (United States)

2010-10-01

... REGULATIONS TRANSPORTATION OF MIGRANT WORKERS § 398.5 Parts and accessories necessary for safe operation. (a... not be of welded construction. The installation shall be such as not to cause cracking, warping, or... high, by attachment of sideboards to the permanent body construction if necessary. Stake body...

Light water ultra-safe plant concept

International Nuclear Information System (INIS)

Klevans, E.

1989-01-01

Since the accident at Three Mile Island (TMI), Penn State Nuclear Engineering Department Faculty and Staff have considered various methods to improve already safe reactor designs and public perception of the safety of Nuclear Power. During 1987 and 1988, the Department of Energy provided funds to the Nuclear Engineering Department at Penn State to investigate a plant reconfiguration originated by M.A. Schultz called ''The Light Water Ultra-Safe Plant Concept''. This report presents a final summary of the project with references to several masters' theses and addendum reports for further detail. The two year research effort included design verification with detailed computer simulation of: (a) normal operation characteristics of the unique pressurizing concept, (b) severe transients without loss of coolant, (c) combined primary and secondary system modeling, and (d) small break and large break loss of coolant accidents. Other studies included safety analysis, low power density core design, and control system design to greatly simplify the control room and required operator responses to plant upset conditions. The overall conclusion is that a reconfigured pressurized water reactor can achieve real and perceived safety improvements. Additionally, control system research to produce greatly simplified control rooms and operator requirements should be continued in future projects

Plant life time management for safe long term operation

International Nuclear Information System (INIS)

Burket, Danes

2010-01-01

The topics discussed include LTO (long-term operation) and licensing procedure in general and specifically for the Dukovany NPP, components of an LTO programme, the PLIM (plant life management) concept for Dukovany and Temelin, the LTO implementation project for Dukovany, LTO strategy, LTO risk study, international verification. The Conclusions include the following items: (i) Technical-economic study of Dukovany NPP LTO demonstrates technical feasibility and economic profitability of Dukovany NPP LTO with perspective for up to 60 years of operation. (ii) Safety part of Program for assurance of Dukovany NPP LTO complies with IAEA SALTO recommendations. (iii) Dukovany NPP LTO programme incorporated IAEA SALTO Peer Review Mission recommendations. (iv) LTO Implementation Project for 2009-2015 was approved with major targets to renew operational permission and prepare NPP for operation up to 60 years. (v) Preparation of Temelin NPP LTO programme has been started. (P.A.)

Water hydraulic manipulator for fail safe and fault tolerant remote handling operations at ITER

International Nuclear Information System (INIS)

Nieminen, Peetu; Esque, Salvador; Muhammad, Ali; Mattila, Jouni; Vaeyrynen, Jukka; Siuko, Mikko; Vilenius, Matti

2009-01-01

Department of Intelligent Hydraulics and Automation (IHA) of Tampere University of Technology has been involved in the European Fusion program since 1994 within the ITER reactor maintenance activities. In this paper we discuss the design and development of a six degrees of freedom water hydraulic manipulator with a force feedback for teleoperation tasks. The manipulator is planned to be delivered to Divertor Test Platform 2 (DTP2) during year 2008. The paper also discusses the possibility to improve the fail safe and redundant operation of the manipulator. During the design of the water hydraulic manipulator, special provisions have been made in order to meet the safety requirements such as servo valve block for redundant operation and safety vane brakes for fail safe operation.

SKB's Project SAFE for the SFR 1 Repository. A Review by Consultants to SKI

International Nuclear Information System (INIS)

Chapman, N.A.; Maul, P.R.; Robinson, P.C.; Savage, D.

2002-06-01

The SFR 1 repository used for final disposal of low- and intermediate level radioactive waste produced by the Swedish nuclear power programme, industry, medicine and research. In 1992 it was granted a full-scale operating permit following additional reporting on long-term safety aspects by SKB, including the first in-depth safety assessment in 1991. It was stipulated as part of the full-scale licence for SFR 1 that a revised safety assessment should be carried out by SKB at least every ten years during the continued operation of the facility. The first 10-year SKB re-evaluation, called 'Project SAFE', was submitted to the regulators in 2001. The review of Project SAFE presented in this report is the culmination of several years' work with SKI including: 1. The extension and application of SKI's 'systems' approach to set up a description of the SFR 1 repository using Process Influence Diagrams (PIDs). 2. Participation in the development of a flexible Performance Assessment (PA) software tool (the AMBER code) that enables time-dependent analyses to be made of system behaviour. 3. Use of the PID database to explore, from first principles, issues that are likely to be important in the safety performance of SFR 1 and thereby to identify topics to be explored by PA modelling. 4. Peer review of the main SKB Project SAFE supporting documentation to evaluate quality, completeness and the implications of the results. 5. An independent PA exercise, using the AMBER code. 6. A review of an English translation of Section 5 of SKB's Project SAFE Final Safety Report. The present report covers only items 3 to 6, and a separate report provides a more detailed description of item 5. As a result of this review, the key issues that the regulatory authorities will need to address when reviewing SKB's safety case for SFR 1 have been identified as: 1. There is no clear statement of SKB's overall safety concept for SFR 1. It is therefore difficult to judge the results of the PA against

Projected evolution superoperators and the density operator

International Nuclear Information System (INIS)

Turner, R.E.; Dahler, J.S.; Snider, R.F.

1982-01-01

The projection operator method of Zwanzig and Feshbach is used to construct the time dependent density operator associated with a binary scattering event. The formula developed to describe this time dependence involves time-ordered cosine and sine projected evolution (memory) superoperators. Both Schroedinger and interaction picture results are presented. The former is used to demonstrate the equivalence of the time dependent solution of the von Neumann equation and the more familiar frequency dependent Laplace transform solution. For two particular classes of projection superoperators projected density operators are shown to be equivalent to projected wave functions. Except for these two special cases, no projected wave function analogs of projected density operators exist. Along with the decoupled-motions approximation, projected interaction picture density operators are applied to inelastic scattering events. Simple illustrations are provided of how this formalism is related to previously established results for two-state processes, namely, the theory of resonant transfer events, the first order Magnus approximation, and the Landau-Zener theory

Safe and efficient operation of multistage cold compressor systems

International Nuclear Information System (INIS)

Kauschke, M.; Haberstroh, C.; Quack, H.

1996-01-01

Large refrigeration rates in the temperature range of super fluid helium can only be obtained with the help of centrifugal cold compressors. For the large 2 K systems, four compression stages are necessary to reach atmospheric pressure. Centrifugal cold compressors are quite sensitive to mass flow and suction temperature variations; but these have to be expected in a real system. The first step in the systems design is to find safe and efficient quasi-stationary modes of operation. The system which is being proposed for the TESLA refrigerators relies on two features. The first is to allow the room temperature screw compressor, downstream of the cold compressors to work occasionally with a subatmospheric suction pressure. The second is to stabilize the suction temperature of the third stage of compression at about 10 K. With these features it is possible, that in all modes of operation all four compressor stages operate exactly at their design point

Gas Bearing Control for Safe Operation in Critical Speed Regions - Experimental Verification

DEFF Research Database (Denmark)

Theisen, Lukas R. S.; Niemann, Hans H.; Galeazzi, Roberto

2015-01-01

supported by gas bearings to extend their operating range. Using H∞-design methods, active lubrication techniques are proposed to enhance the damping, which in turn reduces the vibrations to a desired safe level. The control design is validated experimentally on a laboratory test rig, and shown to allow...... and deceleration patterns and avoidance of operation near the critical speeds, which is a limiting factor during operation, specially during run-downs. An approach for reducing the vibrations is by feedback controlled lubrication. This paper addresses the challenge of reducing vibrations in rotating machines...

Organisational factors important to the safe operation of NPPs

International Nuclear Information System (INIS)

Frischknecht, Albert; Baumont, Genevieve

2000-01-01

The purpose of this paper is to present the achievements of a group of human factor specialists known as Expanded Task Force on Human Factors (ETF). ETF is part of the Principal Working Group No.1 (PWG1) on 'Operating Experience and Human Factors' of the Committee on Nuclear Safety Installations (CSNI) of the OECD Nuclear Energy Agency (NEA). Today, as shown by incident analysis, technology is so far developed that human behaviour and organisational deficiencies can contribute to a major part of the root causes of incidents in nuclear power plants. The influence of the organisation on the safe behaviour and performance of individuals is recognised as a relevant issue for the safety of nuclear power plants (NPPs). The need for an up-to-date basis of knowledge in this area was recognised by CSNI and therefore the ETF organised a workshop, in Switzerland, in 1998, on Organisational Factors. During the workshop, different aspects of organisational influences on the safe operation of NPPs were discussed and twelve important organisational factors concerning safety related activities in a NPP were identified. The result of the workshop is summarised in a state-of-the-art Report (SOAR) 'Identification and Assessment of Organisational Factors Related to the Safety of NPPs' issued by the OECD/NEA. The present paper gives an overview on the main findings of the workshop and conclusions concerning the evaluation of organisational factors. (author)

DQO Summary Report for 105-N/109-N Interim Safe Storage Project Waste Characterization

Energy Technology Data Exchange (ETDEWEB)

T. A. Lee

2005-09-15

The DQO summary report provides the results of the DQO process completed for waste characterization activities for the 105-N/109-N Reactor Interim Safe Storage Project including decommission, deactivate, decontaminate, and demolish activities for six associated buildings.

DQO Summary Report for 105-N/109-N Interim Safe Storage Project Waste Characterization

International Nuclear Information System (INIS)

Lee, T.A.

2005-01-01

The DQO summary report provides the results of the DQO process completed for waste characterization activities for the 105-N/109-N Reactor Interim Safe Storage Project including decommission, deactivate, decontaminate, and demolish activities for six associated buildings.

Safe Reentry for False Aneurysm Operations in High-Risk Patients.

Science.gov (United States)

Martinelli, Gian Luca; Cotroneo, Attilio; Caimmi, Philippe Primo; Musica, Gabriele; Barillà, David; Stelian, Edmond; Romano, Angelo; Novelli, Eugenio; Renzi, Luca; Diena, Marco

2017-06-01

In the absence of a standardized safe surgical reentry strategy for high-risk patients with large or anterior postoperative aortic false aneurysm (PAFA), we aimed to describe an effective and safe approach for such patients. We prospectively analyzed patients treated for PAFA between 2006 and 2015. According to the preoperative computed tomography scan examination, patients were divided into two groups according to the anatomy and extension of PAFA: in group A, high-risk PAFA (diameter ≥3 cm) developed in the anterior mediastinum; in group B, low-risk PAFA (diameter <3 cm) was situated posteriorly. For group A, a safe surgical strategy, including continuous cerebral, visceral, and coronary perfusion was adopted before resternotomy; group B patients underwent conventional surgery. We treated 27 patients (safe reentry, n = 13; standard approach, n = 14). Mean age was 60 years (range, 29 to 80); 17 patients were male. Mean interval between the first operation and the last procedure was 4.3 years. Overall 30-day mortality rate was 7.4% (1 patient in each group). No aorta-related mortality was observed at 1 and 5 years in either group. The Kaplan-Meier overall survival estimates at 1 and 5 years were, respectively, 92.3% ± 7.4% and 73.4% ± 13.4% in group A, and 92.9% ± 6.9% and 72.2% ± 13.9% in group B (log rank test, p = 0.830). Freedom from reoperation for recurrent aortic disease was 100% at 1 year and 88% at 5 years. The safe reentry technique with continuous cerebral, visceral, and coronary perfusion for high-risk patients resulted in early and midterm outcomes similar to those observed for low-risk patients undergoing conventional surgery. Copyright © 2017 The Society of Thoracic Surgeons. Published by Elsevier Inc. All rights reserved.

Implementation of project Safe in Amber. Verification study for SFR 1 SAR-08

Energy Technology Data Exchange (ETDEWEB)

Thomson, Gavin; Herben, Martin; Lloyd, Pam; Rose, Danny; Smith, Chris; Barraclough, Ian (Enviros Consulting Ltd (GB))

2008-03-15

This report documents an exercise in which AMBER has been used to represent the models used in Project SAFE, a safety assessment undertaken on SFR 1. (AMBER is a flexible, graphical-user-interface based tool that allows users to build their own dynamic compartmental models to represent the migration, degradation and fate of contaminants in an environmental system. AMBER allows the user to assess routine, accidental and long-term contaminant release.) AMBER has been used to undertake assessment calculations on all of the disposal system, including all disposal tunnels and the Silo, the geosphere and several biosphere modules. The near-field conceptual models were implemented with minimal changes to the approach undertaken previously in Project SAFE. Model complexity varied significantly between individual disposal facilities increasing significantly from the BLA to the BTF and BMA tunnels and Silo. Radionuclide transport through the fractured granite geosphere was approximated using a compartment model approach in AMBER. Several biosphere models were implemented in AMBER including reasonable biosphere development, which considered the evolution of the Forsmark area from coastal to lacustrine to agricultural environments in response to land uplift. Parameters were sampled from distributions and simulations were run for 1,000 realisations. In undertaking the comparison of AMBER with the various codes and calculation tools used in Project SAFE it was necessary to undertake a detailed analysis of the modelling approach previously adopted, with particular focus given to the near-field models. As a result some discrepancies in the implementation of the models and documentation were noted. The exercise demonstrates that AMBER is fully capable of representing the features of the SFR 1 disposal system in a safety assessment suitable for SAR-08

Implementation of project Safe in Amber. Verification study for SFR 1 SAR-08

International Nuclear Information System (INIS)

Thomson, Gavin; Herben, Martin; Lloyd, Pam; Rose, Danny; Smith, Chris; Barra clough, Ian

2008-03-01

This report documents an exercise in which AMBER has been used to represent the models used in Project SAFE, a safety assessment undertaken on SFR 1. (AMBER is a flexible, graphical-user-interface based tool that allows users to build their own dynamic compartmental models to represent the migration, degradation and fate of contaminants in an environmental system. AMBER allows the user to assess routine, accidental and long-term contaminant release.) AMBER has been used to undertake assessment calculations on all of the disposal system, including all disposal tunnels and the Silo, the geosphere and several biosphere modules. The near-field conceptual models were implemented with minimal changes to the approach undertaken previously in Project SAFE. Model complexity varied significantly between individual disposal facilities increasing significantly from the BLA to the BTF and BMA tunnels and Silo. Radionuclide transport through the fractured granite geosphere was approximated using a compartment model approach in AMBER. Several biosphere models were implemented in AMBER including reasonable biosphere development, which considered the evolution of the Forsmark area from coastal to lacustrine to agricultural environments in response to land uplift. Parameters were sampled from distributions and simulations were run for 1,000 realisations. In undertaking the comparison of AMBER with the various codes and calculation tools used in Project SAFE it was necessary to undertake a detailed analysis of the modelling approach previously adopted, with particular focus given to the near-field models. As a result some discrepancies in the implementation of the models and documentation were noted. The exercise demonstrates that AMBER is fully capable of representing the features of the SFR 1 disposal system in a safety assessment suitable for SAR-08

Safe design and operation of fluidized-bed reactors: Choice between reactor models

NARCIS (Netherlands)

Westerink, E.J.; Westerterp, K.R.

1990-01-01

For three different catalytic fluidized bed reactor models, two models presented by Werther and a model presented by van Deemter, the region of safe and unique operation for a chosen reaction system was investigated. Three reaction systems were used: the oxidation of benzene to maleic anhydride, the

Basic national requirements for safe design, construction and operation

International Nuclear Information System (INIS)

Franzen, L.F.

1980-01-01

Nuclear power plants have to be save. Vendors and utilities operating such plants, are convinced that their plants meet this requirement. Who, however, is establishing the safety requirements to be met by those manufacturing and operating nuclear power plants. What are the mechanisms to control whether the features provided assure the required safety level. Who controls whether the required and planned safety features are really provided. Who is eventually responsible for assuring safety after commissioning of a nuclear power plant. These fundamental questions being raised in many discussions on safety and environmental protection are dealt with in the following sections: (1) Fundamental safety requirements on nuclear power plants, in which such items as risk, legal bases and licensing procedure are discussed, (2) Surveillance during construction, in which safety analysis report, siting, safety evaluation, document examination, quality assurance, and commissioning testing are dealt with, (3) Operating tests and conditions in which recurrent inspections, environmental protection during operation, investigation of abnormal occurences and backfitting requirements as reviewed, and (4) Safety philosophy and safety policy to conclude this presentation. The German approach to nuclear safety serves as an example for an effective way of assuring safe nuclear power. (orig.)

Manpower development for safe operation of nuclear power plant. China. Emergency operating procedures. Activity: 5.1.4-Task-11. Technical report

International Nuclear Information System (INIS)

Walsh, L.A.

1994-01-01

This report covers the period of engagement from July 11, 1994 through July 22, 1994. The events and topics of discussion are as follows: History of Emergency Operating Procedure EOP Development; Emergency Operating Procedures (Event Based, Critical Safe Function Status Trees and Functional Recovery Response Procedures); Transition from Emergency Operating Procedures to Severe Accident Management Guidelines

Integration of health physics, safety and operational processes for management and disposition of recycled uranium wastes at the Fernald Environmental Management Project (FEMP)

International Nuclear Information System (INIS)

Barber, James; Buckley, James

2003-01-01

Fluor Fernald, Inc. (Fluor Fernald), the contractor for the U. S. Department of Energy (DOE) Fernald Environmental Management Project (FEMP), recently submitted a new baseline plan for achieving site closure by the end of calendar year 2006. This plan was submitted at DOE's request, as the FEMP was selected as one of the sites for their accelerated closure initiative. In accordance with the accelerated baseline, the FEMP Waste Management Project (WMP) is actively evaluating innovative processes for the management and disposition of low-level uranium, fissile material, and thorium, all of which have been classified as waste. These activities are being conducted by the Low Level Waste (LLW) and Uranium Waste Disposition (UWD) projects. Alternatives associated with operational processing of individual waste streams, each of which poses potentially unique health physics, industrial hygiene and industrial hazards, are being evaluated for determination of the most cost effective and safe met hod for handling and disposition. Low-level Mixed Waste (LLMW) projects are not addressed in this paper. This paper summarizes historical uranium recycling programs and resultant trace quantity contamination of uranium waste streams with radionuclides, other than uranium. The presentation then describes how waste characterization data is reviewed for radiological and/or chemical hazards and exposure mitigation techniques, in conjunction with proposed operations for handling and disposition. The final part of the presentation consists of an overview of recent operations within LLW and UWD project dispositions, which have been safely completed, and a description of several current operations

Tank farm restoration and safe operation, Project W-314, upgrade scope summary report (USSR)

International Nuclear Information System (INIS)

Gilbert, J.L.

1998-01-01

The revision to the Project W-314 Upgrade Scope Summary Report (USSR), incorporates changes to the project scope from customer guidance. Included are incorporation of the recommendations from HNF-2500, agreements regarding interfaces with Project W-211, and assumption of scope previously assigned to Project W-454

Unmanned Aerial Systems Traffic Management (UTM): Safely Enabling UAS Operations in Low-Altitude Airspace

Science.gov (United States)

Rios, Joseph

2016-01-01

Currently, there is no established infrastructure to enable and safely manage the widespread use of low-altitude airspace and UAS flight operations. Given this, and understanding that the FAA faces a mandate to modernize the present air traffic management system through computer automation and significantly reduce the number of air traffic controllers by FY 2020, the FAA maintains that a comprehensive, yet fully automated UAS traffic management (UTM) system for low-altitude airspace is needed. The concept of UTM is to begin by leveraging concepts from the system of roads, lanes, stop signs, rules and lights that govern vehicles on the ground today. Building on its legacy of work in air traffic management (ATM), NASA is working with industry to develop prototype technologies for a UAS Traffic Management (UTM) system that would evolve airspace integration procedures for enabling safe, efficient low-altitude flight operations that autonomously manage UAS operating in an approved low-altitude airspace environment. UTM is a cloud-based system that will autonomously manage all traffic at low altitudes to include UASs being operated beyond visual line of sight of an operator. UTM would thus enable safe and efficient flight operations by providing fully integrated traffic management services such as airspace design, corridors, dynamic geofencing, severe weather and wind avoidance, congestion management, terrain avoidance, route planning re-routing, separation management, sequencing spacing, and contingency management. UTM removes the need for human operators to continuously monitor aircraft operating in approved areas. NASA envisions concepts for two types of UTM systems. The first would be a small portable system, which could be moved between geographical areas in support of operations such as precision agriculture and public safety. The second would be a Persistent system, which would support low-altitude operations in an approved area by providing continuous automated

NEA international co-operative projects

International Nuclear Information System (INIS)

1989-01-01

This text is consecrated at the international co-operative projects of the OECD Nuclear Energy Agency (NEA) in the field of reactor safety (Halden reactor project, Loft project, studies on the damaged Three Mile Island unit-2 reactor, inspection of reactor steel components, incident reporting system) and in the field of radioactive waste management (Stripa project, geochemical data bases, Alligator river project, seabed disposal of high-level radioactive waste, decommissioning of nuclear facilities)

Risk Management Plan for Tank Farm Restoration and Safe Operations, Project W-314

International Nuclear Information System (INIS)

MCGREW, D.L.

2000-01-01

The Risk Management Plan for Project W-314 describes the systems, processes and procedures for implementation of applicable risk management practices described in HNF-0842, Volume IV, Section 2.6, ''Risk Management''. This plan is tailored specifically for use by Project W-314

The BMC ACCESS project: the development of a medically enhanced safe haven shelter.

Science.gov (United States)

Lincoln, Alisa; Johnson, Peggy; Espejo, Dennis; Plachta-Elliott, Sara; Lester, Peggy; Shanahan, Christopher; Abbott, Susan; Cabral, Howard; Jamanka, Amber; Delman, Jonathan; Kenny, Patty

2009-10-01

This paper describes the development and implementation of the Boston Medical Center (BMC) Advanced Clinical Capacity for Engagement, Safety, and Services Project. In October 2002, the BMC Division of Psychiatry became the first such entity to open a Safe Haven shelter for people who are chronically homeless, struggling with severe mental illness, and actively substance abusing. The low-demand Safe Haven model targets the most difficult to reach population and serves as a "portal of entry" to the mental health and addiction service systems. In this paper, the process by which this blended funded, multi-level collaboration, consisting of a medical center, state, city, local, and community-based consumer organizations, was created and is maintained, as well as the clinical model of care is described. Lessons learned from creating the Safe Haven Shelter and the development and implementation of the consumer-informed evaluation are discussed as well as implications for future work with this population.

Deep geological repositories. Safe operation and long-term safety in the prism of reversibility

Energy Technology Data Exchange (ETDEWEB)

Espivent, Camille; Tichauer, Michael [IRSN, Fontenay-aux-Roses (France)

2015-07-01

A deep geological repository is the reference solution enshrined in the French law for the long-term management of high-level radioactive waste. The current project is led by Andra, the French radioactive waste management organization. As a technical support organization, IRSN's mission is, on the basis of the safety case produced by Andra, to assess the safety of such a facility at its various stages of development, that is to say the design, construction, operation and post-closure phases of the facility. Such a facility will have to meet specific requirements, within different time frames as stated above. One of the requirements is ''reversibility'': in fact, French law poses that the geological disposal will have to be ''reversible'' for a certain time, yet not fully defined. Reversibility is nevertheless believed encompassing both the decision making process related to the waste emplacement process during operational phase and the ability to retrieve waste, should such a decision be made. Thus, underground structures have to be designed and operated to allow both waste emplacement and removal. Moreover, future decision making about the disposal process will have to rely on a sound technical basis. This implies a data collection scheme and a monitoring program of the facility to check if the disposal process is bound by limits, controls and conditions compatible with (i) a safe operation of the facility and (ii) the state of the facility that the operator wants to achieve at the time of its closure, so that long-term safety is guaranteed. Therefore, technical criteria and key parameters have to be selected and monitored during construction and operation, that is to say for decades. Then, reversibility have to make room for corrective actions, including the retrieval of waste, if something goes wrong and especially if the facility is not seen as safe anymore, especially in the perspective of long-term safety. To

Deep geological repositories. Safe operation and long-term safety in the prism of reversibility

International Nuclear Information System (INIS)

Espivent, Camille; Tichauer, Michael

2015-01-01

A deep geological repository is the reference solution enshrined in the French law for the long-term management of high-level radioactive waste. The current project is led by Andra, the French radioactive waste management organization. As a technical support organization, IRSN's mission is, on the basis of the safety case produced by Andra, to assess the safety of such a facility at its various stages of development, that is to say the design, construction, operation and post-closure phases of the facility. Such a facility will have to meet specific requirements, within different time frames as stated above. One of the requirements is ''reversibility'': in fact, French law poses that the geological disposal will have to be ''reversible'' for a certain time, yet not fully defined. Reversibility is nevertheless believed encompassing both the decision making process related to the waste emplacement process during operational phase and the ability to retrieve waste, should such a decision be made. Thus, underground structures have to be designed and operated to allow both waste emplacement and removal. Moreover, future decision making about the disposal process will have to rely on a sound technical basis. This implies a data collection scheme and a monitoring program of the facility to check if the disposal process is bound by limits, controls and conditions compatible with (i) a safe operation of the facility and (ii) the state of the facility that the operator wants to achieve at the time of its closure, so that long-term safety is guaranteed. Therefore, technical criteria and key parameters have to be selected and monitored during construction and operation, that is to say for decades. Then, reversibility have to make room for corrective actions, including the retrieval of waste, if something goes wrong and especially if the facility is not seen as safe anymore, especially in the perspective of long-term safety. To

Review of Project SAFE: Comments on biosphere conceptual model description and risk assessment methodology

International Nuclear Information System (INIS)

Klos, Richard; Wilmot, Roger

2002-09-01

The Swedish Nuclear Fuel and Waste Management Company's (SKB's) most recent assessment of the safety of the Forsmark repository for low-level and intermediate-level waste (Project SAFE) is currently undergoing review by the Swedish regulators. As part of its review, the Swedish Radiation Protection Institute (SSI) identified that two components of SAFE require more detailed review: (i) the conceptual model description of the biosphere system, and (ii) SKB's risk assessment methodology. We have reviewed the biosphere system interaction matrix and how this has been used in the identification, justification and description of biosphere models for radiological assessment purposes. The risk assessment methodology has been reviewed considering in particular issues associated with scenario selection, assessment timescale, and the probability and risk associated with the well scenario. There is an extensive range of supporting information on which biosphere modelling in Project SAFE is based. However, the link between this material and the biosphere models themselves is not clearly set out. This leads to some contradictions and mis-matches between description and implementation. One example concerns the representation of the geosphere-biosphere interface. The supporting description of lakes indicates that interaction between groundwaters entering the biosphere through lake bed sediments could lead to accumulations of radionuclides in sediments. These sediments may become agricultural areas at some time in the future. In the numerical modelling of the biosphere carried out in Project SAFE, the direct accumulation of contaminants in bed sediments is not represented. Application of a more rigorous procedure to ensure numerical models are fit for purpose is recommended, paying more attention to issues associated with the geosphere-biosphere interface. A more structured approach to risk assessment would be beneficial, with a better explanation of the difference between

78 FR 7477 - Multistate Corridor Operations and Management Program

Science.gov (United States)

2013-02-01

... in the Multistate Corridor Operations and Management Program authorized by the Safe, Accountable... projects to improve multimodal transportation system management and operations. This notice seeks... Multistate Corridor Operations and Management (MCOM) programs and projects. The purpose of these investments...

Operational waste volume projection. Revision 20

International Nuclear Information System (INIS)

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

1994-01-01

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 July 1994

Project Design Concept for Monitoring and Control System

International Nuclear Information System (INIS)

MCGREW, D.L.

2000-01-01

This Project Design Concept represents operational requirements established for use in design the tank farm Monitoring and Control System. These upgrades are included within the scope of Project W-314, Tank Farm Restoration and Safe Operations

Graduate Student Project: Operations Management Product Plan

Science.gov (United States)

Fish, Lynn

2007-01-01

An operations management product project is an effective instructional technique that fills a void in current operations management literature in product planning. More than 94.1% of 286 graduates favored the project as a learning tool, and results demonstrate the significant impact the project had in predicting student performance. The author…

Unmanned Aircraft Systems Traffic Management (UTM) Safely Enabling UAS Operations in Low-Altitude Airspace

Science.gov (United States)

Kopardekar, Parimal H.

2016-01-01

Unmanned Aircraft System (UAS) Traffic Management (UTM) Enabling Civilian Low-Altitude Airspace and Unmanned Aircraft System Operations What is the problem? Many beneficial civilian applications of UAS have been proposed, from goods delivery and infrastructure surveillance, to search and rescue, and agricultural monitoring. Currently, there is no established infrastructure to enable and safely manage the widespread use of low-altitude airspace and UAS operations, regardless of the type of UAS. A UAS traffic management (UTM) system for low-altitude airspace may be needed, perhaps leveraging concepts from the system of roads, lanes, stop signs, rules and lights that govern vehicles on the ground today, whether the vehicles are driven by humans or are automated. What system technologies is NASA exploring? Building on its legacy of work in air traffic management for crewed aircraft, NASA is researching prototype technologies for a UAS Traffic Management (UTM) system that could develop airspace integration requirements for enabling safe, efficient low-altitude operations. While incorporating lessons learned from the today's well-established air traffic management system, which was a response that grew out of a mid-air collision over the Grand Canyon in the early days of commercial aviation, the UTM system would enable safe and efficient low-altitude airspace operations by providing services such as airspace design, corridors, dynamic geofencing, severe weather and wind avoidance, congestion management, terrain avoidance, route planning and re-routing, separation management, sequencing and spacing, and contingency management. One of the attributes of the UTM system is that it would not require human operators to monitor every vehicle continuously. The system could provide to human managers the data to make strategic decisions related to initiation, continuation, and termination of airspace operations. This approach would ensure that only authenticated UAS could operate

Application of digital solutions to help the safe and efficient operation of nuclear power plants

International Nuclear Information System (INIS)

Ortega P, F.; Fernandez F, S.

2017-09-01

In the search for excellence, the emergence of solutions to digitize nuclear power plants is an opportunity to optimize the operation and safety of them. The new technologies available today in the market, applied under a global vision of the operation, can contribute to the excellent operation of nuclear power plants in terms of efficiency and effectiveness. Tecnatom has a long experience in various areas related to the operation of the plants, giving the aforementioned global vision, essential to develop global solutions that pursue the safe and efficient operation of the operation. (Author)

Review of Project SAFE: Comments on biosphere conceptual model description and risk assessment methodology

Energy Technology Data Exchange (ETDEWEB)

Klos, Richard; Wilmot, Roger [Galson Sciences Ltd (United Kingdom)

2002-09-01

The Swedish Nuclear Fuel and Waste Management Company's (SKB's) most recent assessment of the safety of the Forsmark repository for low-level and intermediate-level waste (Project SAFE) is currently undergoing review by the Swedish regulators. As part of its review, the Swedish Radiation Protection Institute (SSI) identified that two components of SAFE require more detailed review: (i) the conceptual model description of the biosphere system, and (ii) SKB's risk assessment methodology. We have reviewed the biosphere system interaction matrix and how this has been used in the identification, justification and description of biosphere models for radiological assessment purposes. The risk assessment methodology has been reviewed considering in particular issues associated with scenario selection, assessment timescale, and the probability and risk associated with the well scenario. There is an extensive range of supporting information on which biosphere modelling in Project SAFE is based. However, the link between this material and the biosphere models themselves is not clearly set out. This leads to some contradictions and mis-matches between description and implementation. One example concerns the representation of the geosphere-biosphere interface. The supporting description of lakes indicates that interaction between groundwaters entering the biosphere through lake bed sediments could lead to accumulations of radionuclides in sediments. These sediments may become agricultural areas at some time in the future. In the numerical modelling of the biosphere carried out in Project SAFE, the direct accumulation of contaminants in bed sediments is not represented. Application of a more rigorous procedure to ensure numerical models are fit for purpose is recommended, paying more attention to issues associated with the geosphere-biosphere interface. A more structured approach to risk assessment would be beneficial, with a better explanation of the difference

Main corrective measures in an early phase of nuclear power plants’ preparation for safe long term operation

Energy Technology Data Exchange (ETDEWEB)

Krivanek, Robert, E-mail: r.krivanek@iaea.org [International Atomic Energy Agency (IAEA), Department of Nuclear Safety and Security, Operational Safety Section, Vienna 1400 (Austria); Fiedler, Jan, E-mail: fiedler@fme.vutbr.cz [University of Technology Brno, Faculty of Mechanical Engineering, Energy Institute, Technická 2896/2, 616 69 Brno (Czech Republic)

2017-05-15

Highlights: • Results of SALTO missions provide the most important issues for safe long term operation (LTO) of nuclear power plants. • The most important technical corrective measures in an early phase of preparation for safe LTO are described. • Their satisfactory resolution creates a basis for further activities to demonstrate preparedness for safe LTO. - Abstract: This paper presents the analysis of main technical deficiencies of nuclear power plants (NPPs) in preparedness for safe long term operation (LTO) and the main corrective measures in an early phase of preparation for safe LTO of NPPs. It focuses on technical aspects connected with management of physical ageing of NPP structures, systems and components (SSCs). It uses as a basis results of IAEA SALTO missions performed between 2005 and 2016 (see also paper NED8805 in Nuclear Engineering and Design in May 2016) and the personal experiences of the authors with preparation of NPPs for safe LTO. This paper does not discuss other important aspects of safe LTO of NPPs, e.g. national nuclear energy policies, compliance of NPPs with the latest international requirements on design, obsolescence, environmental impact and economic aspects of LTO. Chapter 1 provides a brief introduction of the current status of the NPP’ fleet in connection with LTO. Chapter 2 provides an overview of SALTO peer review service results with a focus on deficiencies related to physical ageing of safety SSCs and a demonstration that SSCs will perform their safety function during the intended period of LTO. Chapter 3 discusses the main corrective measures which NPPs typically face during the preparation for demonstration of safe LTO. Chapter 4 summarizes the current status of the NPP’ fleet in connection with LTO and outlines further steps needed in preparation for safe LTO.

Safe Distribution of Declarative Processes

DEFF Research Database (Denmark)

Hildebrandt, Thomas; Mukkamala, Raghava Rao; Slaats, Tijs

2011-01-01

of projections that covers a DCR Graph that the network of synchronously communicating DCR Graphs given by the projections is bisimilar to the original global process graph. We exemplify the distribution technique on a process identified in a case study of an cross-organizational case management system carried...... process model generalizing labelled prime event structures to a systems model able to finitely represent ω-regular languages. An operational semantics given as a transition semantics between markings of the graph allows DCR Graphs to be conveniently used as both specification and execution model....... The technique for distribution is based on a new general notion of projection of DCR Graphs relative to a subset of labels and events identifying the set of external events that must be communicated from the other processes in the network in order for the distribution to be safe.We prove that for any vector...

Identification of efforts required for continued safe operation of KANUPP

International Nuclear Information System (INIS)

Ghafoor, M.A.; Hashmi, J.A.; Siddiqui, Z.H.

1991-01-01

Kanupp, the first commercial CANDU PHWR, rated at 137 MWe, was built on turnkey basis by the Canadian General Electric Company for the Pakistan Atomic Energy Commission, and went operational in October, 1972 near Karachi. It has operated since then with a lifetime average availability factor of 51.5% and capacity factor of 25%. In 1976, Kanupp suffered loss of technical support from its original vendors due to the Canadian embargo on export of nuclear technology. Simultaneously, the world experienced the most explosive development and advancement in electronic and computer technology, accelerating the obsolescence of such equipment and systems installed in Kanupp. Replacement upgrading of obsolete computers, control and instrumentation was thus the first major set of efforts realized as essential f or continued safe operation. On the other hand, Kanupp was able to cope with the normal maintenance of its process, mechanical and electrical equipment till the late 80's. But now many of these components are reaching the end of their useful life, and developing chronic problems due to ageing, which can only be solved by complete replacement. This is much more difficult for custom-made nuclear process equipment, e.g. the reactor internals and the fuelling machine. Public awareness and international concern about nuclear safety have increased significantly since the TMI and Chernobyl events. Corresponding realization of the critical role of human factors and the importance of operational experience feedback, has helped Kanupp by opening international channels of communication, including renewed cooperation on CANDU technology. The safety standards and criteria for CANDU as well as other NPPs have matured and evolved gradually over the past two decades. First Kanupp has to ensure that its present ageing-induced equipment problems are resolved to satisfy the original safety requirements and public risk targets which are still internationally acceptable. But as a policy, we

Identification of efforts required for continued safe operation of KANUPP

Energy Technology Data Exchange (ETDEWEB)

Ghafoor, M A; Hashmi, J A; Siddiqui, Z H [Karachi Nuclear Power Plant, Karachi (Pakistan)

1991-04-01

Kanupp, the first commercial CANDU PHWR, rated at 137 MWe, was built on turnkey basis by the Canadian General Electric Company for the Pakistan Atomic Energy Commission, and went operational in October, 1972 near Karachi. It has operated since then with a lifetime average availability factor of 51.5% and capacity factor of 25%. In 1976, Kanupp suffered loss of technical support from its original vendors due to the Canadian embargo on export of nuclear technology. Simultaneously, the world experienced the most explosive development and advancement in electronic and computer technology, accelerating the obsolescence of such equipment and systems installed in Kanupp. Replacement upgrading of obsolete computers, control and instrumentation was thus the first major set of efforts realized as essential f or continued safe operation. On the other hand, Kanupp was able to cope with the normal maintenance of its process, mechanical and electrical equipment till the late 80's. But now many of these components are reaching the end of their useful life, and developing chronic problems due to ageing, which can only be solved by complete replacement. This is much more difficult for custom-made nuclear process equipment, e.g. the reactor internals and the fuelling machine. Public awareness and international concern about nuclear safety have increased significantly since the TMI and Chernobyl events. Corresponding realization of the critical role of human factors and the importance of operational experience feedback, has helped Kanupp by opening international channels of communication, including renewed cooperation on CANDU technology. The safety standards and criteria for CANDU as well as other NPPs have matured and evolved gradually over the past two decades. First Kanupp has to ensure that its present ageing-induced equipment problems are resolved to satisfy the original safety requirements and public risk targets which are still internationally acceptable. But as a policy, we

Tank farm restoration and safe operation, project W-314, upgrade scope summary report (USSR)

International Nuclear Information System (INIS)

Jacobson, R.W.

1997-01-01

This revision to the Project W-314 Upgrade Scope Summary Report (USSR), incorporates changes to the project scope from Alternative Generation Analysis (AGA), customer guidance, and changing requirements. It defines the actual upgrades currently in scope, and provides traceability to the requirements and/or drivers

Iterative co-creation for improved hand hygiene and aseptic techniques in the operating room: experiences from the safe hands study.

Science.gov (United States)

Erichsen Andersson, Annette; Frödin, Maria; Dellenborg, Lisen; Wallin, Lars; Hök, Jesper; Gillespie, Brigid M; Wikström, Ewa

2018-01-04

Hand hygiene and aseptic techniques are essential preventives in combating hospital-acquired infections. However, implementation of these strategies in the operating room remains suboptimal. There is a paucity of intervention studies providing detailed information on effective methods for change. This study aimed to evaluate the process of implementing a theory-driven knowledge translation program for improved use of hand hygiene and aseptic techniques in the operating room. The study was set in an operating department of a university hospital. The intervention was underpinned by theories on organizational learning, culture and person centeredness. Qualitative process data were collected via participant observations and analyzed using a thematic approach. Doubts that hand-hygiene practices are effective in preventing hospital acquired infections, strong boundaries and distrust between professional groups and a lack of psychological safety were identified as barriers towards change. Facilitated interprofessional dialogue and learning in "safe spaces" worked as mechanisms for motivation and engagement. Allowing for the free expression of different opinions, doubts and viewing resistance as a natural part of any change was effective in engaging all professional categories in co-creation of clinical relevant solutions to improve hand hygiene. Enabling nurses and physicians to think and talk differently about hospital acquired infections and hand hygiene requires a shift from the concept of one-way directed compliance towards change and learning as the result of a participatory and meaning-making process. The present study is a part of the Safe Hands project, and is registered with ClinicalTrials.gov (ID: NCT02983136 ). Date of registration 2016/11/28, retrospectively registered.

Effective and Safe Ships

DEFF Research Database (Denmark)

Pedersen, Preben Terndrup; Amdahl, Jørgen; Rutgersson, Olle

1996-01-01

A Joint Nordic Research project "Effecive and Safe Ships" is presented. The project is aiming to develop methods and tools for quantitative evaluation fo ship safety. This report is the report of the preliminary phase where the plan for the main project is developed. The objectives of the project...

UAV Research at NASA Langley: Towards Safe, Reliable, and Autonomous Operations

Science.gov (United States)

Davila, Carlos G.

2016-01-01

Unmanned Aerial Vehicles (UAV) are fundamental components in several aspects of research at NASA Langley, such as flight dynamics, mission-driven airframe design, airspace integration demonstrations, atmospheric science projects, and more. In particular, NASA Langley Research Center (Langley) is using UAVs to develop and demonstrate innovative capabilities that meet the autonomy and robotics challenges that are anticipated in science, space exploration, and aeronautics. These capabilities will enable new NASA missions such as asteroid rendezvous and retrieval (ARRM), Mars exploration, in-situ resource utilization (ISRU), pollution measurements in historically inaccessible areas, and the integration of UAVs into our everyday lives all missions of increasing complexity, distance, pace, and/or accessibility. Building on decades of NASA experience and success in the design, fabrication, and integration of robust and reliable automated systems for space and aeronautics, Langley Autonomy Incubator seeks to bridge the gap between automation and autonomy by enabling safe autonomous operations via onboard sensing and perception systems in both data-rich and data-deprived environments. The Autonomy Incubator is focused on the challenge of mobility and manipulation in dynamic and unstructured environments by integrating technologies such as computer vision, visual odometry, real-time mapping, path planning, object detection and avoidance, object classification, adaptive control, sensor fusion, machine learning, and natural human-machine teaming. These technologies are implemented in an architectural framework developed in-house for easy integration and interoperability of cutting-edge hardware and software.

Functions and requirements for tank farm restoration and safe operations, Project W-314. Revision 3

International Nuclear Information System (INIS)

Garrison, R.C.

1995-01-01

This Functions and Requirements document (FRD) establishes the basic performance criteria for Project W-314, in accordance with the guidance outlined in the letter from R.W. Brown, RL, to President, WHC, ''Tank Waste Remediation System (TWRS) Project Documentation Methodology,'' 94-PRJ-018, dated 3/18/94. The FRD replaces the Functional Design Criteria (FDC) as the project technical baseline documentation. Project W-314 will improve the reliability of safety related systems, minimize onsite health and safety hazards, and support waste retrieval and disposal activities by restoring and/or upgrading existing Tank Farm facilities and systems. The scope of Project W-314 encompasses the necessary restoration upgrades of the Tank Farms' instrumentation, ventilation, electrical distribution, and waste transfer systems

Hanford high level waste (HLW) tank mixer pump safe operating envelope reliability assessment

International Nuclear Information System (INIS)

Fischer, S.R.; Clark, J.

1993-01-01

The US Department of Energy and its contractor, Westinghouse Corp., are responsible for the management and safe storage of waste accumulated from processing defense reactor irradiated fuels for plutonium recovery at the Hanford Site. These wastes, which consist of liquids and precipitated solids, are stored in underground storage tanks pending final disposition. Currently, 23 waste tanks have been placed on a safety watch list because of their potential for generating, storing, and periodically releasing various quantities of hydrogen and other gases. Tank 101-SY in the Hanford SY Tank Farm has been found to release hydrogen concentrations greater than the lower flammable limit (LFL) during periodic gas release events. In the unlikely event that an ignition source is present during a hydrogen release, a hydrogen burn could occur with a potential to release nuclear waste materials. To mitigate the periodic gas releases occurring from Tank 101-SY, a large mixer pump currently is being installed in the tank to promote a sustained release of hydrogen gas to the tank dome space. An extensive safety analysis (SA) effort was undertaken and documented to ensure the safe operation of the mixer pump after it is installed in Tank 101-SY.1 The SA identified a need for detailed operating, alarm, and abort limits to ensure that analyzed safety limits were not exceeded during pump operations

Falls prevention in hospitals and mental health units: an extended evaluation of the FallSafe quality improvement project.

Science.gov (United States)

Healey, Frances; Lowe, Derek; Darowski, Adam; Windsor, Julie; Treml, Jonathan; Byrne, Lisa; Husk, Janet; Phipps, Jill

2014-07-01

inpatient falls are a major patient safety issue causing distress, injury and death. Systematic review suggests multifactorial assessment and intervention can reduce falls by 20-30%, but large-scale studies of implementation are few. This paper describes an extended evaluation of the FallSafe quality improvement project, which presented key components of multifactorial assessment and intervention as a care bundle. : data on delivery of falls prevention processes were collected at baseline and for 18 months from nine FallSafe units and nine control units. Data on falls were collected from local risk management systems for 24 months, and data on under-reporting through staff surveys. : in FallSafe units, delivery of seven care bundle components significantly improved; most improvements were sustained after active project support was withdrawn. Twelve-month moving average of reported fall rates showed a consistent downward trend in FallSafe units but not controls. Significant reductions in reported fall rate were found in FallSafe units (adjusted rate ratio (ARR) 0.75, 95% confidence interval (CI) 0.68-0.84 P control units (ARR 0.91, 95% CI 0.81-1.03 P = 0.13). No significant changes in injurious fall rate were found in FallSafe units (ARR 0.86, 95% CI 0.71-1.03 P = 0.11), or controls (ARR 0.88, 95% CI 0.72-1.08 P = 0.13). In FallSafe units, staff certain falls had been reported increased from 60 to 77%. : introducing evidence-based care bundles of multifactorial assessment and intervention using a quality improvement approach resulted in improved delivery of multifactorial assessment and intervention and significant reductions in fall rates, but not in injurious fall rates. © The Author 2013. Published by Oxford University Press on behalf of the British Geriatrics Society. All rights reserved. For Permissions, please email: journals.permissions@oup.com.

Safe Routes to School Local School Project: A health evaluation at 10 low-income schools

OpenAIRE

Cooper, Jill F MSW; McMillan, Tracy MPH, PHD

2010-01-01

fe Routes to School National Partnership (Partnership) founded the Local School Project (Project) in 2008 to assist ten schools in lowincome communities to: 1) develop and evaluate a school-based SRTS program, 2) build local capacity to apply for state or federal SRTS funding, and 3) increase safe walking and bicycling to and from the school and in the community. The Centers for Disease Control and Prevention, Kaiser Permanente, and the Robert Wood Johnson Foundation provided funding for the ...

Safely Enabling Civilian Unmanned Aerial System (UAS) Operations in Low-Altitude Airspace by Unmanned Aerial System Traffic Management (UTM)

Science.gov (United States)

Kopardekar, Parimal Hemchandra

2015-01-01

Many UAS will operate at lower altitude (Class G, below 2000 feet). There is an urgent need for a system for civilian low-altitude airspace and UAS operations. Stakeholders want to work with NASA to enable safe operations.

Projection operator techniques in nonequilibrium statistical mechanics

International Nuclear Information System (INIS)

Grabert, H.

1982-01-01

This book is an introduction to the application of the projection operator technique to the statistical mechanics of irreversible processes. After a general introduction to the projection operator technique and statistical thermodynamics the Fokker-Planck and the master equation approach are described together with the response theory. Then, as applications the damped harmonic oscillator, simple fluids, and the spin relaxation are considered. (HSI)

Integrated Life Cycle Management: A Strategy for Plants to Extend Operating Lifetimes Safely with High Operational Reliability

International Nuclear Information System (INIS)

Esselman, Thomas; Bruck, Paul; Mengers, Charles

2012-01-01

Nuclear plant operators are studying the possibility of extending their existing generating facilities operating lifetime to 60 years and beyond. Many nuclear plants have been granted licenses to operate their facilities beyond the original 40 year term; however, in order to optimize the long term operating strategies, plant decision-makers need a consistent approach to support their options. This paper proposes a standard methodology to support effective decision-making for the long-term management of selected station assets. Methods detailed are intended to be used by nuclear plant site management, equipment reliability personnel, long term planners, capital asset planners, license renewal staff, and others that intend to look at operation between the current time and the end of operation. This methodology, named Integrated Life Cycle Management (ILCM), will provide a technical basis to assist decision makers regarding the timing of large capital investments required to get to the end of operation safely and with high plant reliability. ILCM seeks to identify end of life cycle failure probabilities for individual plant large capital assets and attendant costs associated with their refurbishment or replacement. It will provide a standard basis for evaluation of replacement and refurbishment options for these components. ILCM will also develop methods to integrate the individual assets over the entire plant thus assisting nuclear plant decision-makers in their facility long term operating strategies. (author)

An impact evaluation of the safe motherhood promotion project in Bangladesh: evidence from Japanese aid-funded technical cooperation.

Science.gov (United States)

Kamiya, Yusuke; Yoshimura, Yukie; Islam, Mohammad Tajul

2013-04-01

This paper reports the findings from a quasi-experimental impact evaluation of the Safe Motherhood Promotion Project (SMPP) conducted in the Narsingdi district of Bangladesh. SMPP is a Japanese aid-funded technical cooperation project aimed at developing local capacities to tackle maternal and newborn health problems in rural areas. We assessed whether the project interventions, in particular, community-based activities under the Model Union approach, had a favorable impact on women's access to and knowledge of maternal health care during pregnancy and childbirth. The project comprises a package of interlinked interventions to facilitate safe motherhood practices at primary and secondary care levels. The primary-level activities focused on community mobilization through participatory approaches. The secondary-level activities aimed at strengthening organizational and personnel capacities for delivering emergency obstetric care (EmOC) at district and sub-district level hospitals. The project impact was estimated by difference-in-differences logistic regressions using two rounds of cross-sectional household survey data. The results showed that the project successfully increased the utilization of antenatal visits and postpartum EmOC services and also enhanced women's knowledge of danger signs during pregnancy and delivery. The project also reduced income inequalities in access to antenatal care. In contrast, we found no significant increase in the use of skilled birth attendants (SBA) in the project site. Nonetheless, community mobilization activities and the government's voucher scheme played a complementary role in promoting the use of SBA. Copyright © 2013 Elsevier Ltd. All rights reserved.

Il sistema EGNOS a supporto della navigazione sicura nei porti: il progetto SafePort

Directory of Open Access Journals (Sweden)

Antonio Casoria

2012-09-01

Full Text Available Il progetto SafePort, sviluppato all’interno del 7° Programma Quadro promosso dalla Unione Europea con la supervisione di European GNSS Agency (GSA che segue tutti i programmi applicativi inerenti ai sistemi GNSS europei, Galileo ed EGNOS, ha l’obbiettivo di migliorare la capacità recettiva dei porti europei, aumentando al contempo la sicurezza delle operazioni di navigazione, di attracco e di ormeggio. The EGNOS system to support safe navigation in ports: the project SafePORT SafePORT The project, developed within the 7 th Framework Programme  sponsored  by  European  Union  under  the  super-vision of European GNSS Agency (GSA, which follows all ap-plications relating to the European GNSS systems, Galileo and EGNOS, has the aim to improve receptive capacity of Europe-an ports, while increasing the safety of operations, navigation, docking and mooring.

Who's Got the Bridge? - Towards Safe, Robust Autonomous Operations at NASA Langley's Autonomy Incubator

Science.gov (United States)

Allen, B. Danette; Cross, Charles D.; Motter, Mark A.; Neilan, James H.; Qualls, Garry D.; Rothhaar, Paul M.; Tran, Loc; Trujillo, Anna C.; Crisp, Vicki K.

2015-01-01

NASA aeronautics research has made decades of contributions to aviation. Both aircraft and air traffic management (ATM) systems in use today contain NASA-developed and NASA sponsored technologies that improve safety and efficiency. Recent innovations in robotics and autonomy for automobiles and unmanned systems point to a future with increased personal mobility and access to transportation, including aviation. Automation and autonomous operations will transform the way we move people and goods. Achieving this mobility will require safe, robust, reliable operations for both the vehicle and the airspace and challenges to this inevitable future are being addressed now in government labs, universities, and industry. These challenges are the focus of NASA Langley Research Center's Autonomy Incubator whose R&D portfolio includes mission planning, trajectory and path planning, object detection and avoidance, object classification, sensor fusion, controls, machine learning, computer vision, human-machine teaming, geo-containment, open architecture design and development, as well as the test and evaluation environment that will be critical to prove system reliability and support certification. Safe autonomous operations will be enabled via onboard sensing and perception systems in both data-rich and data-deprived environments. Applied autonomy will enable safety, efficiency and unprecedented mobility as people and goods take to the skies tomorrow just as we do on the road today.

Conditions Of Safe Ship Operations And Sea Waterway Parameters Based On The Reconstruction Of Świnoujście-Szczecin Fairway

Directory of Open Access Journals (Sweden)

Gucma Stanisław

2015-09-01

Full Text Available This paper describes the state vector of safe ship operation on sea waterways. The author determines relationships between the state vector of safe ship operation and parameters of sea waterway system elements. These include three subsystems: area, navigation and traffic control. These relationships have been exemplified with the 68-kilometre Świnoujście-Szczecin fairway, presently under reconstruction. A systematic approach to sea waterway design is globally unique.

Proceedings of the conference on the Safety in Reactor Operations - TopSafe 2012 Transactions

International Nuclear Information System (INIS)

2012-01-01

TopSafe 2012 provides a forum for addressing the current status and future perspectives with regards to safety at nuclear installations worldwide. In view of the on-going discussions and initiatives that have been taken over the last months the European Nuclear Society (ENS) decided organising this edition of this topical conference from 22 to 26 April 2012 in Helsinki, Finland. TopSafe 2012 focus on three main subjects: Safety and related analyses in operating nuclear power plants and other nuclear installations; Safety and Risk Assessment; Trends in nuclear safety for existing and future installations. The conference is directed at a broad range of experts in the area of nuclear safety, including professionals from the different disciplines involved in the safety of nuclear power plants, fuel cycle installations and research reactors. It is aimed at professionals coming from the research organisations, universities, vendors, operators, regulatory bodies as well as policy makers. Top level representatives of the Countries that are constructing new nuclear power plants are invited. Regulators of all individual Countries with nuclear programme are expected to contribute the Conference. (authors)

Two-spinor description of massive particles and relativistic spin projection operators

Science.gov (United States)

Isaev, A. P.; Podoinitsyn, M. A.

2018-04-01

On the basis of the Wigner unitary representations of the covering group ISL (2 , C) of the Poincaré group, we obtain spin-tensor wave functions of free massive particles with arbitrary spin. The wave functions automatically satisfy the Dirac-Pauli-Fierz equations. In the framework of the two-spinor formalism we construct spin-vectors of polarizations and obtain conditions that fix the corresponding relativistic spin projection operators (Behrends-Fronsdal projection operators). With the help of these conditions we find explicit expressions for relativistic spin projection operators for integer spins (Behrends-Fronsdal projection operators) and then find relativistic spin projection operators for half integer spins. These projection operators determine the numerators in the propagators of fields of relativistic particles. We deduce generalizations of the Behrends-Fronsdal projection operators for arbitrary space-time dimensions D > 2.

Two-spinor description of massive particles and relativistic spin projection operators

Directory of Open Access Journals (Sweden)

A.P. Isaev

2018-04-01

Full Text Available On the basis of the Wigner unitary representations of the covering group ISL(2,C of the Poincaré group, we obtain spin-tensor wave functions of free massive particles with arbitrary spin. The wave functions automatically satisfy the Dirac–Pauli–Fierz equations. In the framework of the two-spinor formalism we construct spin-vectors of polarizations and obtain conditions that fix the corresponding relativistic spin projection operators (Behrends–Fronsdal projection operators. With the help of these conditions we find explicit expressions for relativistic spin projection operators for integer spins (Behrends–Fronsdal projection operators and then find relativistic spin projection operators for half integer spins. These projection operators determine the numerators in the propagators of fields of relativistic particles. We deduce generalizations of the Behrends–Fronsdal projection operators for arbitrary space–time dimensions D>2.

Safe operation of research reactors and critical assemblies. Code of practice and annexes. 1984 ed

International Nuclear Information System (INIS)

1984-01-01

The safe operation of research reactors and critical assemblies (hereafter termed 'reactors') requires proper design, construction, management and supervision. This Code of Practice deals mainly with management and supervision. The provisions of the Code apply to the whole life of the reactor, including modification, updating and upgrading. The Code may be subject to revision in the light of experience and the state of technology. The Code is aimed at defining minimum requirements for the safe operation of reactors. Emphasis is placed on which safety requirements should be met rather than on specifying how these requirements may be met. The Code also provides guidance and information to persons and authorities responsible for the operation of reactors. The Code recommends that documents dealing with the operation of reactors and including safety analyses be prepared and submitted for review and approval to a regulatory body. Operation would be authorized on the understanding that it would comply with limits and conditions designed to ensure safety. The Code covers a wide range of reactor types, which gives rise to a variety of safety issues. Safety issues applicable to specific reactor types only (e.g. fast reactors) are not necessarily covered in this Code. Some of the recommendations in the Code are not directly applicable to critical assemblies. A recommendation may therefore be interpreted according to the type of reactor concerned. In such cases the words 'adequate' and 'appropriate' are used to mean 'adequate' or 'appropriate' for the type of reactor under consideration.

What influences youth to operate all-terrain vehicles safely?

Science.gov (United States)

Grummon, A. H.; Heaney, C. A.; Dellinger, W. A.; Wilkins, J. R.

2014-01-01

The operation of all-terrain vehicles (ATVs) by youth has contributed to the incidence of serious and fatal injuries among children. This study explored factors related to the frequency with which youth wore a helmet and refrained from engaging in three risky driving behaviors (driving at risky speeds, on paved roads and on unfamiliar terrain) while operating an ATV. Youth (n = 248) aged 9–14 from central Ohio and one of their parents completed self-report measures of ATV safety behaviors, youth general propensity for risk taking, protection motivation and parental behaviors to facilitate youth safety. Data from two focus groups provided insight on quantitative results. Analyses revealed considerable variation in the frequency with which youth performed the safety behaviors, with 13- and 14-year-olds reporting less frequent safe behavior than 9- to 12-year-olds. Multiple regression analyses suggested that parental behaviors, such as providing reminders to wear a helmet, were associated with more frequent helmet use but were not associated with risky driving behaviors. Youth’s general propensity toward risk taking was not associated with helmet use and only associated with riskydriving behaviors among the 13- and 14-year-olds. Self-efficacy was an important predictor across both age groups and behaviors. Implications for injury prevention are discussed. PMID:24740837

IAEA Coordinated Research Project on the Establishment of a Material Properties Database for Irradiated Core Structural Components for Continued Safe Operation and Lifetime Extension of Ageing Research Reactors

Energy Technology Data Exchange (ETDEWEB)

Borio Di Tigliole, A.; Schaaf, Van Der; Barnea, Y.; Bradley, E.; Morris, C.; Rao, D. V. H. [Research Reactor Section, Vianna (Australia); Shokr, A. [Research Reactor Safety Section, Vienna (Australia); Zeman, A. [International Atomic Energy Agency, Vienna (Australia)

2013-07-01

Today more than 50% of operating Research Reactors (RRs) are over 45 years old. Thus, ageing management is one of the most important issues to face in order to ensure availability (including life extension), reliability and safe operation of these facilities for the future. Management of the ageing process requires, amongst others, the predictions for the behavior of structural materials of primary components subjected to irradiation such as reactor vessel and core support structures, many of which are extremely difficult or impossible to replace. In fact, age-related material degradation mechanisms resulted in high profile, unplanned and lengthy shutdowns and unique regulatory processes of relicensing the facilities in recent years. These could likely have been prevented by utilizing available data for the implementation of appropriate maintenance and surveillance programmes. This IAEA Coordinated Research Project (CRP) will provide an international forum to establish a material properties Database for irradiated core structural materials and components. It is expected that this Database will be used by research reactor operators and regulators to help predict ageing related degradation. This would be useful to minimize unpredicted outages due to ageing processes of primary components and to mitigate lengthy and costly shutdowns. The Database will be a compilation of data from RRs operators' inputs, comprehensive literature reviews and experimental data from RRs. Moreover, the CRP will specify further activities needed to be addressed in order to bridge the gaps in the new created Database, for potential follow-on activities. As per today, 13 Member States (MS) confirmed their agreement to contribute to the development of the Database, covering a wide number of materials and properties. The present publication incorporates two parts: the first part includes details on the pre-CRP Questionnaire, including the conclusions drawn from the answers received from

IAEA Coordinated Research Project on the Establishment of a Material Properties Database for Irradiated Core Structural Components for Continued Safe Operation and Lifetime Extension of Ageing Research Reactors

International Nuclear Information System (INIS)

Borio Di Tigliole, A.; Schaaf, Van Der; Barnea, Y.; Bradley, E.; Morris, C.; Rao, D. V. H.; Shokr, A.; Zeman, A.

2013-01-01

Today more than 50% of operating Research Reactors (RRs) are over 45 years old. Thus, ageing management is one of the most important issues to face in order to ensure availability (including life extension), reliability and safe operation of these facilities for the future. Management of the ageing process requires, amongst others, the predictions for the behavior of structural materials of primary components subjected to irradiation such as reactor vessel and core support structures, many of which are extremely difficult or impossible to replace. In fact, age-related material degradation mechanisms resulted in high profile, unplanned and lengthy shutdowns and unique regulatory processes of relicensing the facilities in recent years. These could likely have been prevented by utilizing available data for the implementation of appropriate maintenance and surveillance programmes. This IAEA Coordinated Research Project (CRP) will provide an international forum to establish a material properties Database for irradiated core structural materials and components. It is expected that this Database will be used by research reactor operators and regulators to help predict ageing related degradation. This would be useful to minimize unpredicted outages due to ageing processes of primary components and to mitigate lengthy and costly shutdowns. The Database will be a compilation of data from RRs operators' inputs, comprehensive literature reviews and experimental data from RRs. Moreover, the CRP will specify further activities needed to be addressed in order to bridge the gaps in the new created Database, for potential follow-on activities. As per today, 13 Member States (MS) confirmed their agreement to contribute to the development of the Database, covering a wide number of materials and properties. The present publication incorporates two parts: the first part includes details on the pre-CRP Questionnaire, including the conclusions drawn from the answers received from the MS

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

Investigation on the Short Circuit Safe Operation Area of SiC MOSFET Power Modules

DEFF Research Database (Denmark)

Reigosa, Paula Diaz; Luo, Haoze; Iannuzzo, Francesco

2016-01-01

This paper gives a better insight of the short circuit capability of state-of-the-art SiC MOSFET power modules rated at 1.2 kV by highlighting the physical limits under different operating conditions. Two different failure mechanisms have been identified, both reducing the short-circuit capability...... of SiC power modules in respect to discrete SiC devices. Based on such failure mechanisms, two short circuit criteria (i.e., short circuit current-based criterion and gate voltage-based criterion) are proposed in order to ensure their robustness under short-circuit conditions. A Safe Operation Area (SOA...

Spent Nuclear Fuel Project operational staffing plan

International Nuclear Information System (INIS)

Debban, B.L.

1996-03-01

Using the Spent Nuclear Fuel (SNF) Project's current process flow concepts and knowledge from cognizant engineering and operational personnel, an initial assessment of the SNF Project radiological exposure and resource requirements was completed. A small project team completed a step by step analysis of fuel movement in the K Basins to the new interim storage location, the Canister Storage Building (CSB). This analysis looked at fuel retrieval, conditioning of the fuel, and transportation of the fuel. This plan describes the staffing structure for fuel processing, fuel movement, and the maintenance and operation (M ampersand O) staffing requirements of the facilities. This initial draft does not identify the support function resources required for M ampersand O, i.e., administrative and engineering (technical support). These will be included in future revisions to the plan. This plan looks at the resource requirements for the SNF subprojects, specifically, the operations of the facilities, balances resources where applicable, rotates crews where applicable, and attempts to use individuals in multi-task assignments. This plan does not apply to the construction phase of planned projects that affect staffing levels of K Basins

Early detection of power system disturbances as a condition for safe operation of the Dukovany NPP in the 'Island operation mode'

International Nuclear Information System (INIS)

Petruzela, I.

1997-01-01

The ''Frequency Plan'' worked out for the Czech Power System specifies a set of preventive measures along with the set of the frequency ranges. This problem was solved in details for the Dukovany nuclear power plant. The design changes under preparation support a reliable as well as safe operation in the island-operation mode until a full restoration of the whole power system. The design modifications are based on the following three main innovations: An incorporation of the FREA 16 frequency relay into the protection circuits; large modifications in turbine control loops; installation of software routine for the operator to support the island operation mode. The capability of the island operation has been demanded by relevant regulations both for the operating units and for that under construction. The capability can be tested under the transition to houseloads, as well as through the direct simulation of abnormal grid conditions. 1 fig

The Role of Well Control Training in Developing Safe Onshore and Offshore Oil Drilling Operations

Science.gov (United States)

Abulhassn, Aber

2016-01-01

This research investigates the role of the International Well Control Forum (IWCF) Rotary Drilling Well Control Training Program in developing safe oil drilling operations from the perspective of onshore and offshore drilling crews. The research methodology is a qualitative case study. A total of 40 IWCF candidates were interviewed, with 10 from…

LTO License Application Project NPP Borssele

International Nuclear Information System (INIS)

Jong, A.E. de; Blom, F.J.; Leilich, J.

2012-01-01

Borssele NPP plans to extend its operating life with 20 years until 2034. Borssele has started the project LTO 'bewijsvoering' (LTO 'Justification') in order to meet the requirements of the Dutch regulator. The outline of the project is based on IAEA safety guide 57 'Safe Long Term Operation of Nuclear Power Plants'. This paper describes the contents and coherence of the different parts in the project and how these respond to the IAEA guidelines on LTO. The goal of the project LTO 'bewijsvoering' is to ensure that safety and safety relevant systems, structures and components continue to perform their intended functions during long term operation. The outcome of the project LTO 'bewijsvoering' will be used for a license change application and this will be submitted to the Dutch regulator KFD for approval of prolonged operation of Borssele NPP after 2013. (author)

Science operations management. [with Infrared Astronomy Satellite project

Science.gov (United States)

Squibb, G. F.

1984-01-01

The operation teams engaged in the IR Astronomical Satellite (IRAS) project included scientists from the IRAS International Science Team. The detailed involvement of these scientists in the design, testing, validation, and operations phases of the IRAS mission contributed to the success of this project. The Project Management Group spent a substantial amount of time discussing science-related issues, because science team coleaders were members from the outset. A single scientific point-of-contact for the Management Group enhanced the depth and continuity of agreement reached in decision-making.

Safe Energy Source in Battery-operated Toys for Children.

Science.gov (United States)

Rossi, Alfredo; Vignola, Silvia; Nason, Francesca; Boschetti, Federica; Bramerio, Manuela; Bailini, Alessandro; Pinarello, Giordano

2017-11-01

Serious and even fatal consequences of disk batteries ingestion in children are well known. Among other applications, disk batteries are used to power small toys, from which they can be unexpectedly extracted and swallowed. We tested a new cell intended for little toys (green cell [GC]), after 6 and 12 hours of in vitro close contact with esophageal swine mucosa. The GC was compared with lithium and silver button batteries under the same experimental conditions. Tissues in contact with the GC did not show pH variations nor histological alterations after 6 and 12 hours. In such conditions, statistically significant differences were found between the GC and the lithium and silver batteries. So far, multidisciplinary medical effort has been driven to both emergency approach and subsequent operative strategies in children with ingested batteries. Our trial demonstrates the possibility to primarily prevent battery-induced damages by designing new-generation safe cells with no tissue toxicity to power little toys intended for children.

Management aspects of Gemini's base facility operations project

Science.gov (United States)

Arriagada, Gustavo; Nitta, Atsuko; Adamson, A. J.; Nunez, Arturo; Serio, Andrew; Cordova, Martin

2016-08-01

Gemini's Base Facilities Operations (BFO) Project provided the capabilities to perform routine nighttime operations without anyone on the summit. The expected benefits were to achieve money savings and to become an enabler of the future development of remote operations. The project was executed using a tailored version of Prince2 project management methodology. It was schedule driven and managing it demanded flexibility and creativity to produce what was needed, taking into consideration all the constraints present at the time: Time available to implement BFO at Gemini North (GN), two years. The project had to be done in a matrix resources environment. There were only three resources assigned exclusively to BFO. The implementation of new capabilities had to be done without disrupting operations. And we needed to succeed, introducing the new operational model that implied Telescope and instrumentation Operators (Science Operations Specialists - SOS) relying on technology to assess summit conditions. To meet schedule we created a large number of concurrent smaller projects called Work Packages (WP). To be reassured that we would successfully implement BFO, we initially spent a good portion of time and effort, collecting and learning about user's needs. This was done through close interaction with SOSs, Observers, Engineers and Technicians. Once we had a clear understanding of the requirements, we took the approach of implementing the "bare minimum" necessary technology that would meet them and that would be maintainable in the long term. Another key element was the introduction of the "gradual descent" concept. In this, we increasingly provided tools to the SOSs and Observers to prevent them from going outside the control room during nighttime operations, giving them the opportunity of familiarizing themselves with the new tools over a time span of several months. Also, by using these tools at an early stage, Engineers and Technicians had more time for debugging

Dynamic operator actions analysis for inherently safe fast reactors and light water reactors

International Nuclear Information System (INIS)

Ho, V.; Apostolakis, G.

1988-01-01

A comparative dynamic human actions analysis of inherently safe fast reactors (ISFRs) and light water reactors (LWRs) in terms of systems response and estimated human error rates is presented. Brief overviews of the ISFR and LWR systems are given to illustrate the design differences. Key operator actions required by the ISFR reactor shutdown and decay heat removal systems are identified and are compared with those of the LWR. It is observed that, because of the passive nature of the ISFR safety-related systems, a large time window is available for operator actions during transient events. Furthermore, these actions are fewer in number, are less complex, and have lower error rates and less severe consequences than those of the LWRs. We expect the ISFR operator errors' contribution to risk is smaller (at least in the context of the existing human reliability models) than that of the LWRs. (author)

Phasor Simulator for Operator Training Project

Energy Technology Data Exchange (ETDEWEB)

Dyer, Jim [Electric Power Group, Llc, Pasadena, CA (United States)

2016-09-14

Synchrophasor systems are being deployed in power systems throughout the North American Power Grid and there are plans to integrate this technology and its associated tools into Independent System Operator (ISO)/utility control room operations. A pre-requisite to using synchrophasor technologies in control rooms is for operators to obtain training and understand how to use this technology in real-time situations. The Phasor Simulator for Operator Training (PSOT) project objective was to develop, deploy and demonstrate a pre-commercial training simulator for operators on the use of this technology and to promote acceptance of the technology in utility and ISO/Regional Transmission Owner (RTO) control centers.

A completely automatic operation type super-safe fast reactor, RAPID. Its application to dispersion source on lunar and earth surfaces

International Nuclear Information System (INIS)

Kanbe, Mitsuru; Tsunoda, Hirokazu; Mishima, Kaichiro; Kawasaki, Akira; Iwamura, Takamichi

2002-01-01

At a viewpoint of flexible measures to future electric power demands, expectation onto a small-scale reactor for dispersion source is increasing gradually. This is thought to increase its importance not only for a source at proximity of its market in advanced nations but also for the one in developing nations. A study on development of the completely automatic operation type super-safe fast reactor, RAPID (refueling by all pins integrated design) has been carried out as a part of the nuclear energy basic research promoting system under three years project since 1999 by a trust of the Japan Atomic Energy Research Institute to a group of the Central Research Institute of Electric Power Industry (CRIEPI) and so on. As the reactor is a lithium cooled fast reactor with 200 Kw of electric output supposing to use at lunar surface, it can be applied to a super-small scale nuclear reactor on the earth, and has feasibility to become a new option of future nuclear power generation. On the other hand, CRIEPI has investigated on various types of fast reactors (RAPID series) for fast reactor for dispersion source on the earth. Here was introduced on such super-safe fast reactors at a center of RAPID-L. (G.K.)

Il sistema EGNOS a supporto della navigazione sicura nei porti: il progetto SafePort

Directory of Open Access Journals (Sweden)

Antonio Casoria

2012-09-01

Full Text Available Il progetto SafePort, sviluppato all’interno del 7° Programma Quadro promosso dalla Unione Europea con la supervisione di European GNSS Agency (GSA che segue tutti i programmi applicativi inerenti ai sistemi GNSS europei, Galileo ed EGNOS, ha l’obbiettivo di migliorare la capacità recettiva dei porti europei, aumentando al contempo la sicurezza delle operazioni di navigazione, di attracco e di ormeggio.The EGNOS system to support safe navigation in ports: the project SafePORTSafePORT The project, developed within the 7 th Framework Programme  sponsored  by  European  Union  under  the  super-vision of European GNSS Agency (GSA, which follows all ap-plications relating to the European GNSS systems, Galileo and EGNOS, has the aim to improve receptive capacity of Europe-an ports, while increasing the safety of operations, navigation, docking and mooring.

User's operating procedures. Volume 1: Scout project information programs

Science.gov (United States)

Harris, 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 given. SPADS is the result of the past seven years of software development on a Prime minicomputer located at the Scout Project Office. 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. The instructions to operate the Scout Project Information programs in data retrieval and file maintenance via the user friendly menu drivers is presented.

Safe decommissioning of the Romanian VVR-S research reactor

International Nuclear Information System (INIS)

Garlea, C.; Garlea, I.; Kelerman, C.; Rodna, A.

2002-01-01

The VVR-S Romania research reactor was operated between 1957-1997, at 2 MW nominal power, for research and radioisotopical production. The detailed decommissioning plan was developed between 1995-1998, in the frame of the International Atomic Energy Agency Technical assistance project ROM/9/017. The proposed strategy agreed by the counterpart as well as international experts was stage 1. In 1997, an independent analysis performed by European Commission experts, in the frame of PHARE project PH04.1/1994 was dedicated to the 'Study of Soviet Design Research Reactors', had consolidated the development of the project emphasizing technical options of safe management for radioactive wastes and VVR-S spent fuel. The paper presents the main technical aspects as well as those of social impact, which lead to the establishment of strategy for safe management of decommissioning. Technical analysis of the VVR-S reactor and associated radwaste facilities (Radioactive Waste Treatment Plant - Magurele and National Repository Baita-Bihor) proved the possibility of the classical method utilization for dismantling of the facility and treatment-conditioning-disposal of the arrised wastes in safe conditions. The decommissioning plan at stage 2 has been developed based on radiological safety assessment, evaluation of radwaste inventory (removed as well as preserved on site), cost analysis and environmental impact. Technical data were provided by the R and D programme including neutron calculations and experiments, radiological characterizing (for facility and its influence area), seismic analysis and environmental balance during the operation and after shut down of the reactor. A special chapter is dedicated to regulatory issues concerning the development of decommissioning under nuclear safety. Based on the Fundamental Norms of Radiological Safety, the Regulatory Body defined the clearance levels and safety criteria for the process. The development of National Norms for the

Felder uranium project--renewed operations

International Nuclear Information System (INIS)

Anon.

1979-01-01

Exxon owns a uranium mill and holds two mining leases in Live Oak County, Texas, about halfway between San Antonio and Corpus Christi. The properties made up the Felder Uranium Operations which was reopened earlier this year. The feasibility study for reopening the Felder Project began in late 1975 and was not completed until late 1976. This paper discusses several areas of the feasibility study that required additional work prior to making the decision to renew operations. Mine planning evaluation and the actual mine planning are described briefly

Safe operation of existing radioactive waste management facilities at Dalat Nuclear Research Institute

International Nuclear Information System (INIS)

Pham Van Lam; Ong Van Ngoc; Nguyen Thi Nang

2000-01-01

The Dalat Nuclear Research Reactor was reconstructed from the former TRIGA MARK-II in 1982 and put into operation in March 1984. The combined technology for radioactive waste management was newly designed and put into operation in 1984. The system for radioactive waste management at the Dalat Nuclear Research Institute (DNRI) consists of radioactive liquid waste treatment station and disposal facilities. The treatment methods used for radioactive liquid waste are coagulation and precipitation, mechanical filtering and ion- exchange. Near-surface disposal of radioactive wastes is practiced at DNRI In the disposal facilities eight concrete pits are constructed for solidification and disposal of low level radioactive waste. Many types of waste generated in DNRI and in some Nuclear Medicine Departments in the South of Vietnam are stored in the disposal facilities. The solidification of sludge has been done by cementation. Hydraulic compactor has done volume reduction of compatible waste. This paper presents fifteen-years of safe operation of radioactive waste management facilities at DNRI. (author)

Graduate Student Project: Employer Operations Management Analysis

Science.gov (United States)

Fish, Lynn A.

2008-01-01

Part-time graduate students at an Association to Advance Collegiate Schools of Business-accredited college complete a unique project by applying operations management concepts to their current employer. More than 92% of 368 graduates indicated that this experiential project was a positive learning experience, and results show a positive impact on…

Proposal for a new normalization reference in LCA based on “safe operating space”: presentation of framework and global factors at midpoint level

DEFF Research Database (Denmark)

Bjørn, Anders; Hauschild, Michael Zwicky

Planetary boundaries have been suggested for a range of environmental impacts,such as climate change, eutrophying nutrients and land use. The boundaries demarcate the safe operating space of humanity: Staying within the space ensures environmental sustainability, while exceeding it risks pushing...... ecosystems into alternative regimes, leading to adverse effects for humanity. Planetary boundaries can be applied as policy targets. To promote a societal development in the direction of these targets, an indicator system is needed that measures the fraction of the safe operating space that a given activity...... normalization factors in units compatible with characterized results at midpoint level in LCA. Our suggested framework allows expressing normalized results in units of “sustainable person years”. Normalization factors are derived by dividing the safe operating space by the global population. The proposed...

WIPP operations planning: an overview

International Nuclear Information System (INIS)

Miskimin, P.A.; Cossel, S.C.; Plung, D.L.

1985-01-01

The Waste Isolation Pilot Plant (WIPP) is the first-of-a-kind facility for emplacement of radioactive waste in a geologic repository. The concern for safe and efficient operations - coupled with the domestic and international significance of this project - necessitates that WIPP be a ''model plant.'' To develop WIPP as a model plant, a unique planning methodology was employed to identify, evaluate, incorporate, and implement these elements that together will form the best possible overall operation. The resulting improvements in communication among project participants and the smooth transition being made from construction are equally attributable to the methodology employed and the operating program plan developed. 1 fig

An Integrated Data-Driven Strategy for Safe-by-Design Nanoparticles: The FP7 MODERN Project.

Science.gov (United States)

Brehm, Martin; Kafka, Alexander; Bamler, Markus; Kühne, Ralph; Schüürmann, Gerrit; Sikk, Lauri; Burk, Jaanus; Burk, Peeter; Tamm, Tarmo; Tämm, Kaido; Pokhrel, Suman; Mädler, Lutz; Kahru, Anne; Aruoja, Villem; Sihtmäe, Mariliis; Scott-Fordsmand, Janeck; Sorensen, Peter B; Escorihuela, Laura; Roca, Carlos P; Fernández, Alberto; Giralt, Francesc; Rallo, Robert

2017-01-01

The development and implementation of safe-by-design strategies is key for the safe development of future generations of nanotechnology enabled products. The safety testing of the huge variety of nanomaterials that can be synthetized is unfeasible due to time and cost constraints. Computational modeling facilitates the implementation of alternative testing strategies in a time and cost effective way. The development of predictive nanotoxicology models requires the use of high quality experimental data on the structure, physicochemical properties and bioactivity of nanomaterials. The FP7 Project MODERN has developed and evaluated the main components of a computational framework for the evaluation of the environmental and health impacts of nanoparticles. This chapter describes each of the elements of the framework including aspects related to data generation, management and integration; development of nanodescriptors; establishment of nanostructure-activity relationships; identification of nanoparticle categories; hazard ranking and risk assessment.

How to operate safely steam generators with multiple tube through-wall defects

International Nuclear Information System (INIS)

Hernalsteen, P.

1993-01-01

For a Nuclear Power Plant (NPP) of the Pressurized Water Reactor (PWR) type, the Steam Generator (SG) tube bundle represents the major but also the thinnest part of the primary pressure boundary. To the extent that no tube material has yet been identified to be immune to corrosion, defects may initiate in service and easily propagate through wall. While not a desirable feature, a Through Wall Deep (TWD) defect does not necessarily pose a threat to either the structural integrity or leaktightness and this paper shows how SG can (and indeed, do) operate safely and reliably while having many tubes affected by deep and even TWD defects

Quark shell model using projection operators

International Nuclear Information System (INIS)

Ullah, N.

1988-01-01

Using the projection operators in the quark shell model, the wave functions for proton are calculated and expressions for calculating the wave function of neutron and also magnetic moment of proton and neutron are derived. (M.G.B.)

Safe and High Quality Food Production using Low Quality Waters and Improved Irrigation Systems and Management, EU Project

DEFF Research Database (Denmark)

Plauborg, Finn; Jensen, Christian Richardt; Dalsgaard, Anders

2009-01-01

: the safety and quality of food products, and the increasing competition for clean freshwater. SAFIR is funded for the period 2005-2009 under the Food Quality and Safety thematic area of the EU 6th Framework Research Programme. The challenge for the next years will be to produce safe and high quality foods...... a multi-disciplinary team, with food safety and quality experts, engineers, agronomists and economists from17 research institutes and private companies in Europe, Israel and China working together. The project assesses potential risks to farmers. Coupled with farm management and economic models, a new...... intelligent tool for efficient and safe use and re-use of low-quality water are being developed. Already published results indicate water saving in the order of 25-30% in agricultural crops as potatoes and tomatoes are possible without yield reduction. Slightly treated waste water can be used safely when...

46th Annual meeting on nuclear technology (AMNT 2015). Key topic / Enhanced safety and operation excellence / Sustainable reactor operation management - safe, efficient, valuable

International Nuclear Information System (INIS)

Fischer, Erwin

2015-01-01

Summary report on the following Topical Session of the 46 th Annual Conference on Nuclear Technology (AMNT 2015) held in Berlin, 5 to 7 May 2015: - Sustainable Reactor Operation Management - Safe, Efficient, Valuable (Erwin Fischer) The other Sessions of the Key Topics - ''Outstanding Know-How and Sustainable Innovations'', - ''Enhanced Safety and Operation Excellence'' and - ''Decommissioning Experience and Waste Management Solutions'' have been covered in atw 7 (2015) and will be covered in further issues of atw.

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.

Safe Cooperating Cyber-Physical Systems using Wireless Communication

DEFF Research Database (Denmark)

Pop, Paul; Scholle, Detlef; Sljivo, Irfan

2017-01-01

This paper presents an overview of the ECSEL project entitled ―Safe Cooperating Cyber-Physical Systems using Wireless Communication‖ (SafeCOP), which runs during the period 2016–2019. SafeCOP targets safety-related Cooperating Cyber-Physical Systems (CO-CPS) characterised by use of wireless...... detection of abnormal behaviour, triggering if needed a safe degraded mode. SafeCOP will also develop methods and tools, which will be used to produce safety assurance evidence needed to certify cooperative functions. SafeCOP will extend current wireless technologies to ensure safe and secure cooperation...

Operational Experience from Solar Thermal Energy Projects

Science.gov (United States)

Cameron, C. P.

1984-01-01

Over the past few years, Sandia National Laboratories were involved in the design, construction, and operation of a number of DOE-sponsored solar thermal energy systems. Among the systems currently in operation are several industrial process heat projects and the Modular Industrial Solar Retrofit qualification test systems, all of which use parabolic troughs, and the Shenandoah Total Energy Project, which uses parabolic dishes. Operational experience has provided insight to both desirable and undesirable features of the designs of these systems. Features of these systems which are also relevant to the design of parabolic concentrator thermal electric systems are discussed. Other design features discussed are system control functions which were found to be especially convenient or effective, such as local concentrator controls, rainwash controls, and system response to changing isolation. Drive systems are also discussed with particular emphasis of the need for reliability and the usefulness of a manual drive capability.

Quantum canonical ensemble: A projection operator approach

Science.gov (United States)

Magnus, Wim; Lemmens, Lucien; Brosens, Fons

2017-09-01

Knowing the exact number of particles N, and taking this knowledge into account, the quantum canonical ensemble imposes a constraint on the occupation number operators. The constraint particularly hampers the systematic calculation of the partition function and any relevant thermodynamic expectation value for arbitrary but fixed N. On the other hand, fixing only the average number of particles, one may remove the above constraint and simply factorize the traces in Fock space into traces over single-particle states. As is well known, that would be the strategy of the grand-canonical ensemble which, however, comes with an additional Lagrange multiplier to impose the average number of particles. The appearance of this multiplier can be avoided by invoking a projection operator that enables a constraint-free computation of the partition function and its derived quantities in the canonical ensemble, at the price of an angular or contour integration. Introduced in the recent past to handle various issues related to particle-number projected statistics, the projection operator approach proves beneficial to a wide variety of problems in condensed matter physics for which the canonical ensemble offers a natural and appropriate environment. In this light, we present a systematic treatment of the canonical ensemble that embeds the projection operator into the formalism of second quantization while explicitly fixing N, the very number of particles rather than the average. Being applicable to both bosonic and fermionic systems in arbitrary dimensions, transparent integral representations are provided for the partition function ZN and the Helmholtz free energy FN as well as for two- and four-point correlation functions. The chemical potential is not a Lagrange multiplier regulating the average particle number but can be extracted from FN+1 -FN, as illustrated for a two-dimensional fermion gas.

105-H Reactor Interim Safe Storage Project Final Report

International Nuclear Information System (INIS)

Ison, E.G.

2008-01-01

The following information documents the decontamination and decommissioning of the 105-H Reactor facility, and placement of the reactor core into interim safe storage. The D and D of the facility included characterization, engineering, removal of hazardous and radiologically contaminated materials, equipment removal, decontamination, demolition of the structure, and restoration of the site. The ISS work also included construction of the safe storage enclosure, which required the installation of a new roofing system, power and lighting, a remote monitoring system, and ventilation components.

Projection operator and propagator for an arbitrary integral spin

CERN Document Server

Huang Shi Zhong; Wu Ning; Zheng Zhi Peng

2002-01-01

Based on the solution of the Bargmann-Wigner equation for an arbitrary integral spin, a direct derivation of the projection operator and propagator for an arbitrary integral spin is presented. The explicit form for the spin projection operators constructed by Behrends and Fronsdal is confirmed. The commutation rules and a general expression for the Feynman propagator for a free particle of arbitrary integral spin are deduced

Wabash River coal gasification repowering project -- first year operation experience

Energy Technology Data Exchange (ETDEWEB)

Troxclair, E.J. [Destec Energy, Inc., Houston, TX (United States); Stultz, J. [PSI Energy, Inc., West Terre Haute, IN (United States)

1997-12-31

The Wabash River Coal Gasification Repowering Project (WRCGRP), a joint venture between Destec Energy, Inc. and PSI Energy, Inc., began commercial operation in November of 1995. The Project, selected by the United States Department of Energy (DOE) under the Clean Coal Program (Round IV) represents the largest operating coal gasification combined cycle plant in the world. This Demonstration Project has allowed PSI Energy to repower a 1950`s vintage steam turbine and install a new syngas fired combustion turbine to provide 262 MW (net) of electricity in a clean, efficient manner in a commercial utility setting while utilizing locally mined high sulfur Indiana bituminous coal. In doing so, the Project is also demonstrating some novel technology while advancing the commercialization of integrated coal gasification combined cycle technology. This paper discusses the first year operation experience of the Wabash Project, focusing on the progress towards achievement of the demonstration objectives.

Denying Sanctuary: Rejecting Safe Havens in Counterinsurgency Operations

National Research Council Canada - National Science Library

Monarch, Robert M

2009-01-01

Physical sanctuary is one of the bedrocks of a successful insurgency. Denial of these safe havens is critical to a successful counterinsurgency campaign and the eventual defeat of the insurgents by the host state...

Advanced Hard Real-Time Operating System, The Maruti Project. Part 1.

Science.gov (United States)

1997-01-01

REAL - TIME OPERATING SYSTEM , THE MARUTI PROJECT Part 1 of 2 Ashok K. Agrawala Satish K. Tripathi Department of Computer Science University of Maryland...Hard Real - Time Operating System , The Maruti Project DASG-60-92-C-0055 5b. Program Element # 62301E 6. Author(s) 5c. Project # DRPB Ashok K. Agrawala...SdSA94), a real - time operating system developed at the I3nversity of Maryland, and conducted extensive experiments under various task

Mathematical foundations of the projection-operator method

International Nuclear Information System (INIS)

Moore, S.M.

1979-01-01

Mathematical foundations are determined for the projection-operator method developed by Zwanzig and Mori and used in the study of cooperative phenomena in non-equilibrium processes. It is shown that the Hilbert space of operators can be taken as the Hilbert-Schmidt class. Comments are made on the possibility of a complete formulation of quantum mechanics in terms of this Hilbert space. (author)

Status of the RA research reactor decommissioning project

International Nuclear Information System (INIS)

Ljubenov, V.; Nikolic, D.; Pesic, M.; Milosevic, M.; Kostic, Lj.; Steljic, M.; Sotic, O.; Antic, D. . E-mail address of corresponding author: vladan@vin.bg.ac.yu; Ljubenov, V.)

2005-01-01

The 6.5 MW heavy water RA research reactor at the VINCA Institute of Nuclear Sciences operated from 1959 to 1984. After 18 years of extended shutdown in 2002 it was decided that the reactor shutdown should be final. Preliminary decommissioning activities have been initiated by the end of 2002 under the Technical Co-operation Programme of the International Atomic Energy Agency. The objective of the project is to implement safe, timely and cost-effective decommissioning of the RA reactor up to unrestricted use of the site. Decommissioning project is closely related to two other projects: Safe Removal of the RA Reactor Spent Nuclear Fuel and Radioactive Waste Management in VINCA Institute. The main phases of the project include preparation of the detailed decommissioning plan, radiological characterization of the reactor site, dismantling and removal of the reactor components and structures, decontamination, final radiological site survey and the documentation of all the activities in order to obtain the approval for unrestricted use of the facility site. In this paper a review of the activities related to the preparation and realization of the RA reactor decommissioning project is given. Status of the project's organizational and technical aspects as for July 2004 are presented and plans for the forthcoming phases of the project realization are outlined. (author)

46{sup th} Annual meeting on nuclear technology (AMNT 2015). Key topic / Enhanced safety and operation excellence / Sustainable reactor operation management - safe, efficient, valuable

Energy Technology Data Exchange (ETDEWEB)

Fischer, Erwin [E.ON Kernkraft GmbH, Global Unit Next Generation, Hannover (Germany)

2015-08-15

Summary report on the following Topical Session of the 46{sup th} Annual Conference on Nuclear Technology (AMNT 2015) held in Berlin, 5 to 7 May 2015: - Sustainable Reactor Operation Management - Safe, Efficient, Valuable (Erwin Fischer) The other Sessions of the Key Topics - ''Outstanding Know-How and Sustainable Innovations'', - ''Enhanced Safety and Operation Excellence'' and - ''Decommissioning Experience and Waste Management Solutions'' have been covered in atw 7 (2015) and will be covered in further issues of atw.

Dukovany NPP - Safely 16 TERA

International Nuclear Information System (INIS)

Vlcek, J.

2008-01-01

In this presentation increasing of power output of the Dukovany NPP is reviewed. To operate all Dukovany Units safely with the perspective of long-term operation (LTO) of 50 - 60 years it is proposed.

Managing Cassini Safe Mode Attitude at Saturn

Science.gov (United States)

Burk, Thomas A.

2010-01-01

The Cassini spacecraft was launched on October 15, 1997 and arrived at Saturn on June 30, 2004. It has performed detailed observations and remote sensing of Saturn, its rings, and its satellites since that time. In the event safe mode interrupts normal orbital operations, Cassini has flight software fault protection algorithms to detect, isolate, and recover to a thermally safe and commandable attitude and then wait for further instructions from the ground. But the Saturn environment is complex, and safety hazards change depending on where Cassini is in its orbital trajectory around Saturn. Selecting an appropriate safe mode attitude that insures safe operation in the Saturn environment, including keeping the star tracker field of view clear of bright bodies, while maintaining a quiescent, commandable attitude, is a significant challenge. This paper discusses the Cassini safe table management strategy and the key criteria that must be considered, especially during low altitude flybys of Titan, in deciding what spacecraft attitude should be used in the event of safe mode.

The safe operation zone of the spark ignition engine working with dual renewable supplemented fuels (hydrogen+ethyl alcohol)

Energy Technology Data Exchange (ETDEWEB)

Al-Baghdadi, Maher Abdul-Resul Sadiq [Babylon Univ., Dept. of Mechanical Engineering, Babylon (Iraq)

2001-04-01

The effect of the amount of hydrogen/ethyl alcohol addition on the performance and pollutant emission of a four-stroke spark ignition engine has been studied. The results of the study show that all engine performance parameters have been improved when operating the gasoline spark ignition engine with dual addition of hydrogen and ethyl alcohol. The important improvements of alcohol addition are to reduce the NOx emission while increasing the higher useful compression ratio and output power of hydrogen-supplemented engine. An equation has been derived from experimental data to specify the least quantity of ethyl alcohol blended with gasoline and satisfying constant NOx emission when hydrogen is added. A chart limiting the safe operation zone of the engine fueled with dual renewable supplemented fuel, (hydrogen and ethyl alcohol) has been produced. The safe zone provides lower NOx and CO emission, lower s.f.c. and higher brake power compared to an equivalent gasoline engine. When ethyl alcohol is increased over 30%, it causes unstable engine operation which can be related to the fact that the fuel is not vaporized, and this causes a reduction in both brake power and efficiency. (Author)

An Operational ’Project Management Culture’ Framework (Part 1

Directory of Open Access Journals (Sweden)

Yvonne du Plessis

2006-11-01

Full Text Available The aim of this research is to develop an operational ‘project management culture’ framework, which can be used by project managers and organisations to support project work. One of the main causes of project failure is attributed to a non-supportive project management culture in organisations. A triangulation method is followed inclusive of a thorough literature review, a survey questionnaire and a concept mapping process. A project management culture framework with descriptive elements, based on Deal and Kennedy’s (1982 definition of organisational culture, comprising of four dimensions i.e. project process; people in projects; project systems and structure, and project environment was developed.

Light water ultra-safe plant concept: First annual report

International Nuclear Information System (INIS)

Klevans, E.

1987-01-01

Since the accident at Three Mile Island (TMI) Penn State Nuclear Engineering Department Faculty and Staff have considered various methods to improve already safe reactor designs and public perception of the safety of Nuclear Power. During the last year, the Department of Energy funded the study of a plant reconfiguration originally proposed by M.A. Shultz. This report presents the status of the project at the end of the first year. A broad set of specifications to improve safety and public perception were set forth and the realization of these goals is achieved in a plant design named, ''The Light Water Ultra-Safe Plant Concept.'' The most significant goals of the concept address the station black-out problem and simplification of required operator actions during abnormal situations. These goals are achieved in the Ultra-Safe Concept by addition of an in-containment atmospheric tank containing a large quantity of cool water, replacement of the conventional PWR pressurizer system with a pressurizing pump, internal emergency power generation, and arrangement of components to utilize natural circulation at shut-down. The first year effort included an evaluation of the normal operation characteristics of the primary system pressurizing concept, evaluating parameters and modeling for analysis of the shutdown scenario, design of a low power density core, design of a low-pressure waste handling system, arrangement of a drainage system for pipe break considerations, and failure modes and effects analysis

From Planetary Boundaries to national fair shares of the global safe operating space - How can the scales be bridged?

Science.gov (United States)

Häyhä, Tiina; Cornell, Sarah; Lucas, Paul; van Vuuren, Detlef; Hoff, Holger

2016-04-01

The planetary boundaries framework proposes precautionary quantitative global limits to the anthropogenic perturbation of crucial Earth system processes. In this way, it marks out a planetary 'safe operating space' for human activities. However, decisions regarding resource use and emissions are mostly made at much smaller scales, mostly by (sub-)national and regional governments, businesses, and other local actors. To operationalize the planetary boundaries, they need to be translated into and aligned with targets that are relevant at these smaller scales. In this paper, we develop a framework that addresses the three dimension of bridging across scales: biophysical, socio-economic and ethical, to provide a consistent universally applicable approach for translating the planetary boundaries into national level context-specific and fair shares of the safe operating space. We discuss our findings in the context of previous studies and their implications for future analyses and policymaking. In this way, we help link the planetary boundaries framework to widely- applied operational and policy concepts for more robust strong sustainability decision-making.

The Conceptual Design of Innovative Safe PWR

Energy Technology Data Exchange (ETDEWEB)

Kim, Han-Gon [Centural Research Institute, Daejeon (Korea, Republic of); Heo, Sun [Korea Hydro and Nuclear Power Co., Daejeon (Korea, Republic of)

2016-10-15

Most of countries operating NPPs have been performed post-Fukushima improvements as short-term countermeasure to enhance the safety of operating NPPs. Separately, vendors have made efforts on developing passive safety systems as long-term and ultimate countermeasures. AP1000 designed by Westinghouse Electric Company has passive safety systems including the passive emergency core cooling system (PECCS), the passive residual heat removal system (PRHRS), and the passive containment cooling system (PCCS). ESBWR designed by GE-Hitachi also has passive safety systems consisting of the isolation condenser system, the gravity driven cooling system and the PCCS. Other countries including China and Russia have made efforts on developing passive safety systems for enhancing the safety of their plants. In this paper, we summarize the design goals and main design feature of innovative safe PWR, iPOWER which is standing for Innovative Passive Optimized World-wide Economical Reactor, and show the developing status and results of research projects. To mitigate an accident without electric power and enhance the safety level of PWR, the conceptual designs of passive safety system and innovative safe PWR have been performed. It includes the PECCS for core cooling and the PCCS for containment cooling. Now we are performing the small scale and separate effect tests for the PECCS and the PCCS and preparing the integral effect test for the PECCS and real scale test for the PCCS.

Water chemistry technology. One of the key technologies for safe and reliable nuclear power plant operation

International Nuclear Information System (INIS)

Uchida, Shunsuke; Katsumura, Yosuke

2013-01-01

Water chemistry control is one of the key technologies to establish safe and reliable operation of nuclear power plants. Continuous and collaborative efforts of plant manufacturers and plant operator utilities have been focused on optimal water chemistry control, for which, a trio of requirements for water chemistry should be simultaneously satisfied: (1) better reliability of reactor structures and fuel rods; (2) lower occupational exposure and (3) fewer radwaste sources. Various groups in academia have carried out basic research to support the technical bases of water chemistry in plants. The Research Committee on Water Chemistry of the Atomic Energy Society of Japan (AESJ), which has now been reorganized as the Division of Water Chemistry (DWC) of AESJ, has played important roles to promote improvements in water chemistry control, to share knowledge about and experiences with water chemistry control among plant operators and manufacturers and to establish common technological bases for plant water chemistry and then to transfer them to the next generation of plant workers engaged in water chemistry. Furthermore, the DWC has tried and succeeded arranging R and D proposals for further improvement in water chemistry control through roadmap planning. In the paper, major achievements in plant technologies and in basic research studies of water chemistry in Japan are reviewed. The contributions of the DWC to the long-term safe management of the damaged reactors at the Fukushima Daiichi Nuclear Power Plant until their decommissioning are introduced. (author)

78 FR 47817 - Parts and Accessories Necessary for Safe Operation; Application for an Exemption From Van Hool N...

Science.gov (United States)

2013-08-06

... DEPARTMENT OF TRANSPORTATION Federal Motor Carrier Safety Administration [Docket No. FMCSA-2013-0314] Parts and Accessories Necessary for Safe Operation; Application for an Exemption From Van Hool N... exemption from Van Hool N.V. and Coach USA (Van Hool/Coach USA) to allow the use of double deck motorcoaches...

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.

Review of Issues Associated with Safe Operation and Management of the Space Shuttle Program

Science.gov (United States)

Johnstone, Paul M.; Blomberg, Richard D.; Gleghorn, George J.; Krone, Norris J.; Voltz, Richard A.; Dunn, Robert F.; Donlan, Charles J.; Kauderer, Bernard M.; Brill, Yvonne C.; Englar, Kenneth G.;

Approach to Issues in Planning and Operation of Railway BOT Projects

Institute of Scientific and Technical Information of China (English)

Zhao Xianghong; Chen Min

2009-01-01

As an internationally popular mode of public infrastructures' investment,construction and operation,BOT (build-operate-transfer) has been successfully applied in some countries and regions of the world for their infrastructures' construction and playing an important role in promoting the construction of public infrastructures.The Ministry of Railways clearly proposed in its Suggestions for Implementation of Encouraging,Supporting and Guiding Participation of Non-public-owned Economy in Railway Construction and Operation that it was necessary to study and take for reference multiple modes of public infrastructures'investment,construction and operation including BOT.It is more complicated and risky for the process of planning and operation of BOT projects.The paper takes for reference the domestic and foreign experiences in the operation of BOT projects,analyzes the issues that will arise such as risk control in implementing railway BOT projects,employment of professional consultants,financing coordination,tariff making,non-commercial subsidy,as well as operation and management,and puts forward corresponding suggestions for these issues.

Promoting Safe Motherhood in Jimma Zone, Ethiopia (IMCHA ...

International Development Research Centre (IDRC) Digital Library (Canada)

Technology, communication, skills development. This project will ... -developing healthcare worker skills for safe deliveries. The project ... Canada launches new funding opportunity to support Canadian-African research teams studying Ebola.

A Short-Circuit Safe Operation Area Identification Criterion for SiC MOSFET Power Modules

DEFF Research Database (Denmark)

Reigosa, Paula Diaz; Iannuzzo, Francesco; Luo, Haoze

2017-01-01

This paper proposes a new method for the investigation of the short-circuit safe operation area (SCSOA) of state-of-the-art SiC MOSFET power modules rated at 1.2 kV based on the variations in SiC MOSFET electrical parameters (e.g., short-circuit current and gate–source voltage). According...... to the experimental results, two different failure mechanisms have been identified, both reducing the short-circuit capability of SiC power modules with respect to discrete SiC devices. Based on such failure mechanisms, two short-circuit safety criteria have been formulated: 1) the short-circuit...

MANAGEMENT OF TRANSURANIC (TRU) WASTE RETRIEVAL PROJECT RISKS SUCCESSES IN THE STARTUP OF THE HANFORD 200 AREA TRU WASTE RETRIEVAL PROJECT

International Nuclear Information System (INIS)

GREENWLL, R.D.

2005-01-01

A risk identification and mitigation method applied to the Transuranic (TRU) Waste Retrieval Project performed at the Hanford 200 Area burial grounds is described. Retrieval operations are analyzed using process flow diagramming. and the anticipated project contingencies are included in the Authorization Basis and operational plans. Examples of uncertainties assessed include degraded container integrity, bulged drums, unknown containers, and releases to the environment. Identification and mitigation of project risks contributed to the safe retrieval of over 1700 cubic meters of waste without significant work stoppage and below the targeted cost per cubic meter retrieved. This paper will be of interest to managers, project engineers, regulators, and others who are responsible for successful performance of waste retrieval and other projects with high safety and performance risks

Safe and economic performance of nuclear power plant. Operation through meticulous Q/A programmes - a german example

International Nuclear Information System (INIS)

Schenk, H.J.

1989-01-01

Safe and reliable operation of a nuclear power plant over its life time of 40 to 60 years is the essential condition for an economic performance. This goal can be achieved by a qualified responsible staff realizing a high quality of operation and by maintaining high quality and technical standards in the plant in accordance with the status of science and technology. Quality assurance procedures have to verify this in detail, in close contact with the work to be performed. In this presentation I would like to describe our approach in Philippsburg to cope with this task

Water chemistry - one of the key technologies for safe and reliable nuclear power plant operation

International Nuclear Information System (INIS)

Uchida, S.; Otoha, K.; Ishigure, K.

2006-01-01

Full text: Full text: Water chemistry control is one of the key technologies to establish safe and reliable operation of nuclear power plants. Continuous and collaborative efforts of plant manufacturers and plant operator utilities have been focused on optimal water chemistry control, for which, a trio of requirements for water chemistry, a) better reliability of reactor structures and fuels, b) lower occupational exposure, and c) fewer radwaste sources, should be simultaneously satisfied. The research committee related to water chemistry of the Atomic Energy Society of Japan has played important roles to enhance improvement in water chemistry control, to share knowledge and experience with water chemistry among plant operators and manufacturers, to establish common technological bases for plant water chemistry and then to transfer them to the next generation related to water chemistry. Furthermore, the committee has tried to contribute to arranging R and D proposals for further improvement in water chemistry control through road map planning

A large-scale forest fragmentation experiment: the Stability of Altered Forest Ecosystems Project

Science.gov (United States)

Ewers, Robert M.; Didham, Raphael K.; Fahrig, Lenore; Ferraz, Gonçalo; Hector, Andy; Holt, Robert D.; Kapos, Valerie; Reynolds, Glen; Sinun, Waidi; Snaddon, Jake L.; Turner, Edgar C.

2011-01-01

Opportunities to conduct large-scale field experiments are rare, but provide a unique opportunity to reveal the complex processes that operate within natural ecosystems. Here, we review the design of existing, large-scale forest fragmentation experiments. Based on this review, we develop a design for the Stability of Altered Forest Ecosystems (SAFE) Project, a new forest fragmentation experiment to be located in the lowland tropical forests of Borneo (Sabah, Malaysia). The SAFE Project represents an advance on existing experiments in that it: (i) allows discrimination of the effects of landscape-level forest cover from patch-level processes; (ii) is designed to facilitate the unification of a wide range of data types on ecological patterns and processes that operate over a wide range of spatial scales; (iii) has greater replication than existing experiments; (iv) incorporates an experimental manipulation of riparian corridors; and (v) embeds the experimentally fragmented landscape within a wider gradient of land-use intensity than do existing projects. The SAFE Project represents an opportunity for ecologists across disciplines to participate in a large initiative designed to generate a broad understanding of the ecological impacts of tropical forest modification. PMID:22006969

A large-scale forest fragmentation experiment: the Stability of Altered Forest Ecosystems Project.

Science.gov (United States)

Ewers, Robert M; Didham, Raphael K; Fahrig, Lenore; Ferraz, Gonçalo; Hector, Andy; Holt, Robert D; Kapos, Valerie; Reynolds, Glen; Sinun, Waidi; Snaddon, Jake L; Turner, Edgar C

2011-11-27

Opportunities to conduct large-scale field experiments are rare, but provide a unique opportunity to reveal the complex processes that operate within natural ecosystems. Here, we review the design of existing, large-scale forest fragmentation experiments. Based on this review, we develop a design for the Stability of Altered Forest Ecosystems (SAFE) Project, a new forest fragmentation experiment to be located in the lowland tropical forests of Borneo (Sabah, Malaysia). The SAFE Project represents an advance on existing experiments in that it: (i) allows discrimination of the effects of landscape-level forest cover from patch-level processes; (ii) is designed to facilitate the unification of a wide range of data types on ecological patterns and processes that operate over a wide range of spatial scales; (iii) has greater replication than existing experiments; (iv) incorporates an experimental manipulation of riparian corridors; and (v) embeds the experimentally fragmented landscape within a wider gradient of land-use intensity than do existing projects. The SAFE Project represents an opportunity for ecologists across disciplines to participate in a large initiative designed to generate a broad understanding of the ecological impacts of tropical forest modification.

Development of human factors engineering guide for nuclear power project

International Nuclear Information System (INIS)

Wu Dangshi; Sheng Jufang

1997-01-01

'THE PRACTICAL GUIDE FOR APPLICATION OF HUMAN FACTORS ENGINEERING TO NUCLEAR POWER PROJECT (First Draft, in Chinese)', which was developed under a research program sponsored by National Nuclear Safety Administration (NNSA) is described briefly. It is hoped that more conscious, more systematical and more comprehensive application of Human Factors Engineering to the nuclear power projects from the preliminary feasibility studies up to the commercial operation will benefit the safe, efficient and economical operations of nuclear power plants in China

The appliction of project management in operations preparation of nuclear power station

International Nuclear Information System (INIS)

Tang Zhengrong; Zhang Zhixiong

2001-01-01

Concept, history, characteristics of the project management is introduced. Analysis is performed on the suitability of application of project management approach in nuclear power station operations preparation. Then the application of project management is detailed in order to present the readers our study and practice. Theory and practice indicate that the project management is a useful management tool for operations preparation of nuclear power station to achieve a good performance

System supplier approach to projects and operations efficiency

Energy Technology Data Exchange (ETDEWEB)

Moe, P O [Siemens Offshore A/S (Norway)

1994-12-31

The conference paper outlines the most important elements for a new approach to project realisation that enable a cost reduction of 30-50% compared to conventional methods. The achievements are based on studies and evaluations to the Norwegian Vigdis development project. The system elements covered are the electrical and automation systems including safety and process control and all traditional phases of a project from concept design to the operational phase. The concept involves new principles for project execution where traditional borderlines and interfaces between the various participants have been redefined. Management attention has been verified as an important prerequisite for a successful implementation of this strategy. 2 figs.

Breckinridge Project, initial effort. Report VII, Volume 4. Safety and health plan

Energy Technology Data Exchange (ETDEWEB)

None

1982-01-01

The Safety and Health Plan recognizes the potential hazards associated with the Project and has been developed specifically to respond to these risks in a positive manner. Prevention, the primary objective of the Plan, starts with building safety controls into the process design and continues through engineering, construction, start-up, and operation of the Project facilities and equipment. Compliance with applicable federal, state, and local health and safety laws, regulations, and codes throughout all Project phases is required and assured. The Plan requires that each major Project phase be thoroughly reviewed and analyzed to determine that those provisions required to assure the safety and health of all employees and the public, and to prevent property and equipment losses, have been provided. The Plan requires followup on those items or situations where corrective action needs were identified to assure that the action was taken and is effective. Emphasis is placed on loss prevention. Exhibit 1 provides a breakdown of Ashland Synthetic Fuels, Inc.'s (ASFI's) Loss Prevention Program. The Plan recognizes that the varied nature of the work is such as to require the services of skilled, trained, and responsible personnel who are aware of the hazards and know that the work can be done safely, if done correctly. Good operating practice is likewise safe operating practice. Training is provided to familiarize personnel with good operational practice, the general sequence of activities, reporting requirements, and above all, the concept that each step in the operating procedures must be successfully concluded before the following step can be safely initiated. The Plan provides for periodic review and evaluation of all safety and loss prevention activities at the plant and departmental levels.

Design, qualification and operation of nuclear rockets for safe Mars missions

International Nuclear Information System (INIS)

Buden, D.; Madsen, W.W.; Olson, T.S.; Redd, L.R.

1993-01-01

Nuclear thermal propulsion modules planned for use on crew missions to Mars improve mission reliability and overall safety of the mission. This, as well as all other systems, are greatly enhanced if the system specifications take into account safety from design initiation, and operational considerations are well thought through and applied. For instance, the use of multiple engines in the propulsion module can lead to very high system safety and reliability. Operational safety enhancements may include: the use of multiple perigee burns, thus allowing time to ensure that all systems are functioning properly prior to departure from Earth orbit; the ability to perform all other parts of the mission in a degraded mode with little or no degradation of the mission; and the safe disposal of the nuclear propulsion module in a heliocentric orbit out of the ecliptic plane. The standards used to qualify nuclear rockets are one of the main cost drivers of the program. Concepts and systems that minimize cost and risk will rely on use of the element and component levels to demonstrate technology readiness and validation. Subsystem or systems testing then is only needed for verification of performance. Also, these will be the safest concepts because they will be more thoroughly understood and the safety margins will be well established and confirmed by tests

Digital Handover of Data from Building Projects to Building Operation

DEFF Research Database (Denmark)

Jensen, Per Anker

2006-01-01

pro-jects to building operation. This project started in 2004 with research and analyses fol-lowed by development of a proposal for client requirements and in 2005 a first test on a real construction project has been carried out. After revision of the requirements a second test will be started early...... and construction and on the other side in building opera-tion and facilities management. In Denmark the government has launched a development program called Digital Construction and one of the projects concerns specifying require-ments for building clients in relation to digital handover of data from construction...... by a consortium called DACaPo consisting of a building client/facilities manager, a consulting company, a contractor and a university institute. This paper presents some of the results from the project with the main focus on the initial research....

The carbon market: major operational carbon funds and financed projects

International Nuclear Information System (INIS)

Markandya, A.; Nobili, V.

2008-01-01

The flexible mechanisms envisaged by the Kyoto Protocol have led gradually to a global carbon market that has become very appetizing for companies operating in the sector. Financial instruments such as carbon funds, and investments in greenhouse-gas-reduction projects, now operate at the international level, counting on the development of new technologies and energy efficiency, and contributing to sustainable development in the countries that host the projects [it

International co-operation for safe radioactive waste management

International Nuclear Information System (INIS)

1983-01-01

As a specialised inter-governmental body, NEA pursues three main objectives for its radioactive waste management programme: - The promotion of studies to improve the data base available in support of national programmes. - The support of Research and Development through co-ordination of national activities and promotion of international projects. - An improvement in the general level of understanding of waste management issues and options, particularly in the field of waste disposal. The management of radioactive waste from nuclear activities covers several sequences of complex technical operations. However, as the ultimate objective of radioactive waste management is the disposal of the waste, the largest part of the work programme is directed towards the analysis of disposal options. In addition, NEA is active in various other areas of waste management, such as the treatment and conditioning of waste, the decommissioning of nuclear facilities and the institutional aspects of the long term management of radioactive waste

A study on the Safe Operation of RHRS during Shut-Down and Low Power Operations of Nuclear Power Plants

Energy Technology Data Exchange (ETDEWEB)

Jeon, Moon Hun; Sung, Chang Kyung; Kim, Yang Suk; You, Sun Oh; Joo, In Chul [Korea Advanced Institute of Science and Technology, Taejon (Korea, Republic of)

1996-08-01

The main objective is to perform basic research for safe operation of RHRs, which is an important part in the safety analysis of nuclear reactors during a mid-loop operation of nuclear power plants. To achieve this objective, a series of experiments have been performed to simulate the wave phenomena of countercurrent flow that may occur in the hot legs during a mid-loop operation. The major contents and the scope are as follows, To collect and to analyse existing experimental works and also numerical works which have been carried out using large computer codes. To collect and to analyse existing works on the flow patterns of two-phase flows. To perform a series of experiments to simulate the wave phenomena for the countercurrent two-phase flow in hot legs. To obtain correlations for the interfacial friction factor and the flow patterns for a countercurrent flow from the experimentally measured parameters. To obtain the interfacial friction factor between the two-phases of air-water countercurrent flow in a horizontal pipe, a series of experiments have been performed using two different sections of 0.05 m in diameter, whose lengths are 2 m and 4 m, respectively. The results presented here can be used as the fundamental information to obtain the most important thermal-hydraulic parameters such as flow patterns and interfacial friction factors for air-water two-phase flows, which are necessary for safety analyses and operation of nuclear power plants during a mid-loop operation. 46 refs., 8 tabs., 35 figs., 3 ills. (author)

Providing an integrated waste management strategy and operation focused on project end states at the Hanford site

International Nuclear Information System (INIS)

Blackford, L.

2009-01-01

CH2M HILL Plateau Remediation Company (CHPRC) is the U.S. Department of Energy's (DOE) contractor responsible for the safe, environmental cleanup of the Central Plateau of the Hanford Site. The 586-square-mile Hanford Site is located along the Columbia River in southeastern Washington State. A plutonium production complex with nine nuclear reactors and associated processing facilities, Hanford played a pivotal role in the nation's defense for more than 40 years, beginning in the 1940's with the Manhattan Project. Today, under the direction of the DOE, Hanford is engaged in the world's largest environmental cleanup project. The Plateau Remediation Contract (PRC) is a 10-year project paving the way for closure of the Hanford Site through demolition of the Plutonium Finishing Plant; remediation of six burial grounds and 11 groundwater systems; treatment of 43.8 meters of sludge; and disposition of 8,200 meters of transuranic waste, 800 spent nuclear material containers, 2,100 metric tons of spent nuclear fuel, and two reactors. The $4.5 billion project, funded through the U.S. DOE Office of Environmental Management, focuses equally on reducing risks to workers, the public, and the environment and on protecting the Columbia River. The DOE, which operates the Hanford Site, the U.S. Environmental Protection Agency (EPA), and the State of Washington Department of Ecology (Ecology) signed a comprehensive cleanup and compliance agreement on May 15, 1989. The Hanford Federal Facility Agreement and Consent Order, or Tri-Party Agreement (TPA), is an agreement for achieving compliance with the Comprehensive Environmental Response Compensation and Liability Act (CERCLA) remedial action provisions and with the Resource Conservation and Recovery Act (RCRA) treatment, storage, and disposal (TSD) unit regulations and corrective action provisions . More specifically, the Tri-Party Agreement does the following: 1) defines and ranks CERCLA and RCRA cleanup commitments; 2) establishes

Projection Operator: A Step Towards Certification of Adaptive Controllers

Science.gov (United States)

Larchev, Gregory V.; Campbell, Stefan F.; Kaneshige, John T.

2010-01-01

One of the major barriers to wider use of adaptive controllers in commercial aviation is the lack of appropriate certification procedures. In order to be certified by the Federal Aviation Administration (FAA), an aircraft controller is expected to meet a set of guidelines on functionality and reliability while not negatively impacting other systems or safety of aircraft operations. Due to their inherent time-variant and non-linear behavior, adaptive controllers cannot be certified via the metrics used for linear conventional controllers, such as gain and phase margin. Projection Operator is a robustness augmentation technique that bounds the output of a non-linear adaptive controller while conforming to the Lyapunov stability rules. It can also be used to limit the control authority of the adaptive component so that the said control authority can be arbitrarily close to that of a linear controller. In this paper we will present the results of applying the Projection Operator to a Model-Reference Adaptive Controller (MRAC), varying the amount of control authority, and comparing controller s performance and stability characteristics with those of a linear controller. We will also show how adjusting Projection Operator parameters can make it easier for the controller to satisfy the certification guidelines by enabling a tradeoff between controller s performance and robustness.

Study on operation I and C DCS test method of EPR project

International Nuclear Information System (INIS)

Meng Ying; Lv Zhihong; Huang Xinnian; Fan Haiying; Li Zhuojia; Xiao Shushu

2014-01-01

Through summarization and optimization of the method for operation I and C DCS test of the European pressurized reactor project, the conclusions play a guiding role on the operation I and C DCS test of the domestic advanced nuclear power plant. The study of the method focuses on the test platform, the test process and the optimization of method of operation I and C DCS test with the practical experience. The reasonable and reliable test method for operation I and C DCS test of the European pressurized reactor project is worthy of the reference and the development in the project of the domestic advanced nuclear power plant. (authors)

Transfer pricing and safe harbours

Directory of Open Access Journals (Sweden)

Veronika Solilová

2013-01-01

Full Text Available Transfer prices are significant for both taxpayers and tax administrations because they determine in large part taxable profits of associated enterprises in different tax jurisdictions. Moreover, in the context of taxation, transfer prices must be complied with the arm’s length principle. However, Multinational Enterprises have been faced daily by conflicting rules and approaches to applying the arm’s length principle, burdensome documentation requirements, inconsistent audit standards and unpredictable competent authority outcomes. Therefore, the Committee on Fiscal Affairs launched another project on the administrative aspects of transfer pricing in 2010. On 16 May 2013 as a partial solution of this project was approved by the OECD Council the Revised Section E on Safe Harbours in Chapter IV of the Transfer Pricing Guidelines for Multinational Enterprises and Tax Authorities. The paper is focused on significant changes of newly approved chapter IV of the Transfer Pricing Guidelines for Multinational Enterprises and Tax Authorities, further on analysis of practice in this area, on advantages and disadvantages of safe harbours for taxpayers and competent authorities with aim to suggest recommendations on use of safe harbours in the Czech Republic.

The application of project management in operations preparation of nuclear power station

International Nuclear Information System (INIS)

Zhang Zhixiong; Tang Zhengrong

2000-01-01

The author first presents a brief introduction of the concept, history, characteristics of project management. Analysis is performed on the suitability of application of project management approach in nuclear power station operations preparation. Then the application of project management is detailed in order to present the readers authors' study and practice. Theory and practice indicate that the project management is a useful management tool for operations preparation of nuclear power station to achieve a good performance

Successful integration of fast track projects into turnarounds

Energy Technology Data Exchange (ETDEWEB)

Williams, J. Patrick; Loureiro, Ramon C. [KBC Advanced Technologies, Surrey (United Kingdom)

2012-07-01

Fast track projects can provide quick wins and competitive advantage. However, in most cases the implementation of these projects requires a shutdown for installing the necessary tie-ins or integration into an upcoming turnaround (TA). Depending on the nature of the project and complexity of the TA, the integration can be seamless or result in cost or duration overruns and safety incidents. The risk of such overruns and safety incidents increases with the amount of project work to be integrated into the operations, maintenance and inspection schedules to be executed during the TA. The risk further increases with TA size and other factors. If not planned and scheduled properly and in a timely fashion, capital projects, in particular fast track projects trying to take advantage of an upcoming TA, can severely impact both TA performance, and the safety and reliability of the facility until the next opportunity for eliminating the defects introduced during the TA. Successful TAs are those delivered in a safe, on time, on budget manner, and with the quality standards needed for a leak-free start-up and a safe and reliable operation over the next run cycle. This paper discusses the key elements that are required to minimize the TA risks derived from the inclusion of fast track projects and how to establish the cut off criteria to either cancel or defer the project, or delay the TA in order to balance TA scope freeze and the case for compelling economics.(author)

Projection operator method for collective tunneling transitions

International Nuclear Information System (INIS)

Kohmura, Toshitake; Ohta, Hirofumi; Hashimoto, Yukio; Maruyama, Masahiro

2002-01-01

Collective tunneling transitions take place in the case that a system has two nearly degenerate ground states with a slight energy splitting, which provides the time scale of the tunneling. The Liouville equation determines the evolution of the density matrix, while the Schroedinger equation determines that of a state. The Liouville equation seems to be more powerful for calculating accurately the energy splitting of two nearly degenerate eigenstates. However, no method to exactly solve the Liouville eigenvalue equation has been established. The usual projection operator method for the Liouville equation is not feasible. We analytically solve the Liouville evolution equation for nuclear collective tunneling from one Hartree minimum to another, proposing a simple and solvable model Hamiltonian for the transition. We derive an analytical expression for the splitting of energy eigenvalues from a spectral function of the Liouville evolution using a half-projected operator method. A full-order analytical expression for the energy splitting is obtained. We define the collective tunneling path of a microscopic Hamiltonian for collective tunneling, projecting the nuclear ground states onto n-particle n-hole state spaces. It is argued that the collective tunneling path sector of a microscopic Hamiltonian can be transformed into the present solvable model Hamiltonian. (author)

From Planetary Boundaries to national fair shares of the global safe operating space — How can the scales be bridged?

NARCIS (Netherlands)

Häyhä, Tiina; Lucas, Paul L.|info:eu-repo/dai/nl/272607444; van Vuuren, Detlef P.|info:eu-repo/dai/nl/11522016X; Cornell, Sarah E.; Hoff, Holger

2016-01-01

The planetary boundaries framework proposes quantitative global limits to the anthropogenic perturbation of crucial Earth system processes, and thus marks out a planetary safe operating space for human activities. Yet, decisions regarding resource use and emissions are mostly made at less aggregated

Case Writing Projects in Co-Operation with Companies and Organizations

OpenAIRE

Bengtsson, Lars; Asplund, Carl-Johan

2008-01-01

The purpose of this paper is to present the process and evaluation of case writing projects in co-operation with companies and organizations in a course for engineering students. The case writing projects could provide an illustration and example framework for working with companies in constructing cases. Normally cases are constructed for teaching purposes in higher education. However, in order to get closer co-operation and more interest from the companies the authors encouraged the student...

Feedback control of a primary pump for safe and stable operation of a PIUS-type reactor

International Nuclear Information System (INIS)

Tasaka, K.; Imai, S.; Masaoka, H.; Tamaki, M.; Kukita, Y.

1993-01-01

A new automatic pump speed control system by using a measurement of the temperature distribution in the lower density lock is proposed for the PIUS-type reactor. This control system maintains the fluid temperature at the axial center of the lower density lock at the average of the fluid temperatures below and above the density lock in order to prevent the poison water from penetrating into the core during normal operation. The effectiveness of this control system was successfully confirmed by a series of experiments such as start-up and power ramping tests for the stable normal operation and a loss-of-feedwater test for the safe shutdown in an accident condition, using a small scale atmospheric pressure test loop which simulated the PIUS principle. (orig.)

Walla Walla River Fish Passage Operations Project : Annual Progress Report October 2007 - September 2008.

Energy Technology Data Exchange (ETDEWEB)

Bronson, James P.; Duke, Bill; Loffink, Ken

2008-12-30

In the late 1990s, the Confederated Tribes of the Umatilla Indian Reservation, Oregon Department of Fish and Wildlife, and Washington Department of Fish and Wildlife, along with many other agencies, began implementing fisheries restoration activities in the Walla Walla Basin. An integral part of these efforts is to alleviate the inadequate fish migration conditions in the basin. Migration concerns are being addressed by removing diversion structures, constructing fish passage facilities, implementing minimum instream flow requirements, and providing trap and haul efforts when needed. The objective of the Walla Walla River Fish Passage Operations Project is to increase the survival of migrating adult and juvenile salmonids in the Walla Walla River basin. The project is responsible for coordinating operation and maintenance of ladders, screen sites, bypasses, trap facilities, and transportation equipment. In addition, the project provides technical input on passage and trapping facility design, operation, and criteria. Operation of the various passage facilities and passage criteria guidelines are outlined in an annual operations plan that the project develops. Beginning in March of 2007, two work elements from the Walla Walla Fish Passage Operations Project were transferred to other projects. The work element Enumeration of Adult Migration at Nursery Bridge Dam is now conducted under the Walla Walla Basin Natural Production Monitoring and Evaluation Project and the work element Provide Transportation Assistance is conducted under the Umatilla Satellite Facilities Operation and Maintenance Project. Details of these activities can be found in those project's respective annual reports.

Safety and emergency preparedness considerations for geotechnical field operations

Energy Technology Data Exchange (ETDEWEB)

Wemple, R.P.

1989-04-01

The GEO Energy Technology Department at Sandia National Laboratories is involved in several remote-site drilling and/or experimental operations each year. In 1987, the Geothermal Research Division of the Department developed a general set of Safe Operating Procedures (SOPs) that could be applied to a variety of projects. This general set is supplemented by site-specific SOPs as needed. Effective field operations require: integration of safety and emergency preparedness planning with overall project planning, training of field personnel and inventorying of local emergency support resources, and, developing a clear line of responsibility and authority to enforce the safety requirements. Copies of SOPs used in recent operations are included as examples of working documents for the reader.

Projection Operators and Moment Invariants to Image Blurring

Czech Academy of Sciences Publication Activity Database

Flusser, Jan; Suk, Tomáš; Boldyš, Jiří; Zitová, Barbara

2015-01-01

Roč. 37, č. 4 (2015), s. 786-802 ISSN 0162-8828 R&D Projects: GA ČR GA13-29225S; GA ČR GAP103/11/1552 Institutional support: RVO:67985556 Keywords : Blurred image * N-fold rotation symmetry * projection operators * image moments * moment invariants * blur invariants * object recognition Subject RIV: JD - Computer Applications, Robotics Impact factor: 6.077, year: 2015 http://library.utia.cas.cz/separaty/2014/ZOI/flusser-0434521.pdf

Earning the social licence for nuclear operations

International Nuclear Information System (INIS)

Duguay, A.K.; Hoornweg, B.J.

2010-01-01

In addition to safe nuclear operation, a critical component of earning the social licence is effective communication. This paper outlines development of a communications strategy contributing to overall utility operation and project goals through: 1) Relationships with employees, host communities and the general public that are transparent and honest; 2) Processes that effectively interconnect the internal and external communications; and 3) Organizational leadership models that support communication excellence. With strategic development of these three focus areas the nuclear operator will contribute to increased support of the operator's own licence to operate and of support for the nuclear industry as a whole. (author)

Safe 15 Terawatt of Temelin NPP

International Nuclear Information System (INIS)

Sula, M.

2010-01-01

In this work author presents a project Safe 15 Terawatt realised on the Temelin NPP. This project is one of the eight key projects of the CEZ group, associated in the 'Programme of efficiency'. The project started in June 2007 with long-term goals for horizon of year 2012. The safety indicators will be reached of the first quarter level of world's nuclear power plant - by the end of the first decade. By the end of year 2012 we will have achieved annual production of 15 billion kWh - in the Czech Republic: 15 Terawatt.

The Safe Zone Range for Cup Anteversion Is Narrower Than for Inclination in THA.

Science.gov (United States)

Murphy, William S; Yun, Ho Hyun; Hayden, Brett; Kowal, Jens H; Murphy, Stephen B

2018-02-01

Cup malposition is a common cause of impingement, limitation of ROM, acceleration of bearing wear, liner fracture, and instability in THA. Previous studies of the safe zone based on plain radiographs have limitations inherent to measuring angles from two-dimensional projections. The current study uses CT to measure component position in stable and unstable hips to assess the presence of a safe zone for cup position in THA. (1) Does acetabular component orientation, when measured on CT, differ in stable components and those revised for recurrent instability? (2) Do CT data support historic safe zone definitions for component orientation in THA? We identified 34 hips that had undergone revision of the acetabulum for recurrent instability that also had a CT scan of the pelvis between August 2003 and February 2017. We also identified 175 patients with stable hip replacements who also had a CT study for preoperative planning and intraoperative navigation of the contralateral side. For each CT study, one observer analyzed major factors including acetabular orientation, femoral anteversion, combined anteversion (the sum of femoral and anatomic anteversion), pelvic tilt, total offset difference, head diameter, age, sex, and body mass index. These measures were then compared among stable hips, hips with cup revision for anterior instability, and hips with cup revision for posterior instability. We used a clinically relevant measurement of operative anteversion and inclination as opposed to the historic use of radiographic anteversion and inclination. The percentage of unstable hips in the historic Lewinnek safe zone was calculated, and a new safe zone was proposed based on an area with no unstable hips. Anteriorly unstable hips compared with stable hips had higher operative anteversion of the cup (44° ± 12° versus 31° ± 11°, respectively; mean difference, 13°; 95% confidence interval [CI], 5°-21°; p = 0.003), tilt-adjusted operative anteversion of the cup (40° �

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

Curiosity's Autonomous Surface Safing Behavior Design

Science.gov (United States)

Neilson, Tracy A.; Manning, Robert M.

2013-01-01

The safing routines on all robotic deep-space vehicles are designed to put the vehicle in a power and thermally safe configuration, enabling communication with the mission operators on Earth. Achieving this goal is made a little more difficult on Curiosity because the power requirements for the core avionics and the telecommunication equipment exceed the capability of the single power source, the Multi-Mission Radioisotope Thermoelectric Generator. This drove the system design to create an operational mode, called "sleep mode", where the vehicle turns off most of the loads in order to charge the two Li-ion batteries. The system must keep the vehicle safe from over-heat and under-heat conditions, battery cell failures, under-voltage conditions, and clock failures, both while the computer is running and while the system is sleeping. The other goal of a safing routine is to communicate. On most spacecraft, this simply involves turning on the receiver and transmitter continuously. For Curiosity, Earth is above the horizon only a part of the day for direct communication to the Earth, and the orbiter overpass opportunities only occur a few times a day. The design must robustly place the Rover in a communicable condition at the correct time. This paper discusses Curiosity's autonomous safing behavior and describes how the vehicle remains power and thermally safe while sleeping, as well as a description of how the Rover communicates with the orbiters and Earth at specific times.

Allowing variance may enlarge the safe operating space for exploited ecosystems.

Science.gov (United States)

Carpenter, Stephen R; Brock, William A; Folke, Carl; van Nes, Egbert H; Scheffer, Marten

2015-11-17

Variable flows of food, water, or other ecosystem services complicate planning. Management strategies that decrease variability and increase predictability may therefore be preferred. However, actions to decrease variance over short timescales (2-4 y), when applied continuously, may lead to long-term ecosystem changes with adverse consequences. We investigated the effects of managing short-term variance in three well-understood models of ecosystem services: lake eutrophication, harvest of a wild population, and yield of domestic herbivores on a rangeland. In all cases, actions to decrease variance can increase the risk of crossing critical ecosystem thresholds, resulting in less desirable ecosystem states. Managing to decrease short-term variance creates ecosystem fragility by changing the boundaries of safe operating spaces, suppressing information needed for adaptive management, cancelling signals of declining resilience, and removing pressures that may build tolerance of stress. Thus, the management of variance interacts strongly and inseparably with the management of resilience. By allowing for variation, learning, and flexibility while observing change, managers can detect opportunities and problems as they develop while sustaining the capacity to deal with them.

FY 1998 New Sunshine Project. International co-operative project (Summary); 1998 nendo new sunshine keikaku. Kokusai kyoryoku jigyo (sogoban)

Energy Technology Data Exchange (ETDEWEB)

NONE

1999-03-01

Described herein are the basic plans for the international co-operative projects for development of technologies for commercialization of photovoltaic power systems (e.g., IEA co-operative programme on Photovoltaic Power Systems), and the minutes of the FY 1997 and 1998 meetings of the Solar Energy Technology International Research Co-operative Committee. Japan is responsible for implementing the following projects for promoting international cooperation for, e.g., IEA Photovoltaic Power Systems (PVPS): research and development, demonstration, analysis, information exchange, introduction promotion, etc. for IEA/PVPS Programme; and research and development, demonstration, analysis, information exchange, introduction promotion, etc. for IEA/Solar Heating and Cooling Programme. Japan is also implementing the co-operative projects for the photovoltaic power systems with the Summit participants, based on Science and Technology Working Group established by the Versailles Summit, technology cooperation with, e.g., Australia, and bilateral information exchange and technological survey projects with those countries which have already developed solar energy systems, e.g., USA, France, Spain and Italy. (NEDO)

Phased project planning and development in anticipation of operational programs

Science.gov (United States)

Stroud, W. G.

1973-01-01

The impact of future operational status on the planning and execution of the research and development activities for major space flight projects is assessed. These projects, within NASA, are part of the Applications Program involving communications and meteorology. The NASA management approach to these projects is determined by national policies governing the responsibilities and relationships among the various government agencies and private industries.

Compliant Task Execution and Learning for Safe Mixed-Initiative Human-Robot Operations

Science.gov (United States)

Dong, Shuonan; Conrad, Patrick R.; Shah, Julie A.; Williams, Brian C.; Mittman, David S.; Ingham, Michel D.; Verma, Vandana

2011-01-01

We introduce a novel task execution capability that enhances the ability of in-situ crew members to function independently from Earth by enabling safe and efficient interaction with automated systems. This task execution capability provides the ability to (1) map goal-directed commands from humans into safe, compliant, automated actions, (2) quickly and safely respond to human commands and actions during task execution, and (3) specify complex motions through teaching by demonstration. Our results are applicable to future surface robotic systems, and we have demonstrated these capabilities on JPL's All-Terrain Hex-Limbed Extra-Terrestrial Explorer (ATHLETE) robot.

Designing a 'safe and just operating space' for the Chilika lagoon fishery of the Mahanadi delta, India

Science.gov (United States)

Cooper, Gregory; Dearing, John

2017-04-01

Annual fish production from the Chilika lagoon is worth US25-million/year, underpinning the livelihoods of 35,000 fishers and 200,000 secondary dependants. The system has a legacy of collapse, transitioning from annual production rates of 9000 tonnes to 1300 tonnes during the late-1980s, with resulting livelihood losses triggering the first recorded instances of economic migration from Chilika. Despite engineered recovery since 2000, the future persistence of Chilika's resource stock is uncertain. Climate change may strengthen freshwater and sediment delivery, promoting ecohydrological degradation through tidal outlet sedimentation, reduced salinity and freshwater weed growth. Simultaneously, human population growth, fleet motorisation and consumption demands threaten overexploitation driven collapse. These critical social-ecological drivers and feedbacks are projected into future by integrating system dynamics modelling with Monte Carlo inputs. Sustainable pathways are identified from outputs producing social-ecologically desirable futures, such as mid-century catch equalling maximum sustainable yield. The 'safe and just operating space' metaphor is regionalised by the limits of sustainable trajectories, such as the permissible number of active fishers, motorised boats and juvenile catch under alternative governance scenarios. These critical thresholds suggest policy-relevant guardrails for the sustainable governance of Chilika, in order to avoid regional productivity collapse, ecological degradation and livelihood losses. Benefits and trade-offs of alternative governance approaches are also discussed, aiding the optimisation of future regulatory decision-making.

Early awareness of emerging risks associated with food and feed production: Synopsis of pertinent work carried out within the SAFE FOODS project

NARCIS (Netherlands)

Marvin, H.J.P.; Kleter, G.A.

2009-01-01

This introduction to the journal¿s supplement on emerging food and feed safety issues summarizes the objectives and activities of the EU-funded SAFE FOODS project in general and its work package focusing on the early identification of emerging food safety risks, in particular. Within this work

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

Nuclear operations summary Engineering organization for Plowshare nuclear operations

Energy Technology Data Exchange (ETDEWEB)

Broadman, Gene A [Lawrence Radiation Laboratory, University of California, Livermore, CA (United States)

1970-05-15

The availability of nuclear explosives for peaceful projects has given the engineer a new dimension in his thinking. He can now seek methods of adapting Plowshare to a variety of industrial applications. The full potential of the Plowshare Program can only be attained when industry begins to use nuclear explosives on a regular basis, for economically sound projects. It is the purpose of this paper to help the engineer familiarize himself with Plowshare technology to hasten the day when 'Plowsharee goes commercial'. An engineering project utilizing nuclear exposives ordinarily involves three main phases: Phase I (a) The theoretical and empirical analysis of effects. (b) Projected economic and/or scientific evaluation. (c) A safety analysis. Phase II (a) Field construction. (b) Safe detonation of the nuclear explosive. (c) Data acquisition. Phase III The evaluation and/or exploitation of the results. This paper will be restricted to Phase II, referred to collectively as the 'nuclear operation'.

Reactive, Safe Navigation for Lunar and Planetary Robots

Science.gov (United States)

Utz, Hans; Ruland, Thomas

2008-01-01

When humans return to the moon, Astronauts will be accompanied by robotic helpers. Enabling robots to safely operate near astronauts on the lunar surface has the potential to significantly improve the efficiency of crew surface operations. Safely operating robots in close proximity to astronauts on the lunar surface requires reactive obstacle avoidance capabilities not available on existing planetary robots. In this paper we present work on safe, reactive navigation using a stereo based high-speed terrain analysis and obstacle avoidance system. Advances in the design of the algorithms allow it to run terrain analysis and obstacle avoidance algorithms at full frame rate (30Hz) on off the shelf hardware. The results of this analysis are fed into a fast, reactive path selection module, enforcing the safety of the chosen actions. The key components of the system are discussed and test results are presented.

Influencing behaviour for safe working environments

OpenAIRE

Boer, de, J. (Johannes); Teeuw, W.B. (Wouter)

2011-01-01

Safety at work The objective of the project Safety at Work is to increase safety at the workplace by applying and combining state of the art artefacts from personal protective equipment and ambient intelligence technology. In this state of the art document we focus on the developments with respect to how (persuasive) technology can help to influence behaviour in a natural, automatic way in order to make industrial environments safer. We focus on personal safety, safe environments and safe beh...

Projection-iteration methods for solving nonlinear operator equations

International Nuclear Information System (INIS)

Nguyen Minh Chuong; Tran thi Lan Anh; Tran Quoc Binh

1989-09-01

In this paper, the authors investigate a nonlinear operator equation in uniformly convex Banach spaces as in metric spaces by using stationary and nonstationary generalized projection-iteration methods. Convergence theorems in the strong and weak sense were established. (author). 7 refs

Projection operator treatment of single particle resonances

International Nuclear Information System (INIS)

Lev, A.; Beres, W.P.

1976-01-01

A projection operator method is used to obtain the energy and width of a single particle resonance. The resonance energy is found without scanning. An example of the first g/sub 9/2/ neutron resonance in 40 Ca is given and compared with the traditional phase shift method. The results of both approaches are quite similar. 4 figures

A life cycle cost economics model for projects with uniformly varying operating costs. [management planning

Science.gov (United States)

Remer, D. S.

1977-01-01

A mathematical model is developed for calculating the life cycle costs for a project where the operating costs increase or decrease in a linear manner with time. The life cycle cost is shown to be a function of the investment costs, initial operating costs, operating cost gradient, project life time, interest rate for capital and salvage value. The results show that the life cycle cost for a project can be grossly underestimated (or overestimated) if the operating costs increase (or decrease) uniformly over time rather than being constant as is often assumed in project economic evaluations. The following range of variables is examined: (1) project life from 2 to 30 years; (2) interest rate from 0 to 15 percent per year; and (3) operating cost gradient from 5 to 90 percent of the initial operating costs. A numerical example plus tables and graphs is given to help calculate project life cycle costs over a wide range of variables.

Project W-320, operational test procedure OTP-320-003 test report

International Nuclear Information System (INIS)

Bevins, R.R.

1998-01-01

This report documents and summarizes the results of OTP-320-003 Project W-320 Operational Testing of the WRSS Supernate Transfer System. Project W-320 Operational Test OTP-320-003 was performed to verify components of the Waste Retrieval Sluicing System (WRSS) supernate transfer system functioned as designed following construction completion and turnover to operations. All equipment operation was performed by Tank Farms Operations personnel following the operational test procedure and referenced operating procedures. Supernate Transfer line Flushing System Testing was completed over the course of approximately 4 weeks as tank farm conditions and configuration, equipment availability, and operations resources allowed. All testing was performed with the 702-AZ ventilation system and the 296-P-16 ventilation systems in operation. Test procedure OTP-320-003 required two revisions during testing to incorporate Procedure Changes Authorizations (PCAs) necessary to facilitate testing. Various sections of testing are documented on each procedure revision. The completed test procedure is included as Attachment A. Exception Reports generated during the course of testing are included as Attachment B

Instructional maps of safe working methods and practices for separate types of opera-tions conducted in the oil mine

Directory of Open Access Journals (Sweden)

И. В. Климова

2017-06-01

Full Text Available Instructing personnel in the issues of labor protection and industrial safety at hazardous facilities is one of the main tasks that face the employer; the quality with which this procedure is organized and carried out defines not only company’s indicators, but the mere possibility of its normal functioning. The paper contains a detailed overview of the typical content of standard documentation, which is currently used when conducting operations in the oil mines of Yarega high-viscosity oil deposit. Distinct features and unique nature of this oil field require special measures to guarantee safety of personnel and all facilities in general.The author proposes and reviews an additional type of operating guidelines – instructional map of safe working methods and practices. It is more illustrative than existing documentation (charts of inclined shaft development, labor protection regulations, which allows to upgrade the process of instructing personnel in the oil mines, to improve the quality of instructions and to reduce the risk of emergencies, accidents, industrial injuries.The author reviews the structure of suggested instructional map, offers a detailed arrangement diagram for the main thematic sections of the map, as well as their content. Instructional maps are regarded as a type of operating guidelines that include: description and characteristics of equipment, instruments and appliances; general safety requirements; content and execution sequence of operational elements with their graphical images; distribution of responsibilities with an indication of their priority in case the operations are conducted by several workers; specific safety requirements for equipment, materials, instruments, safety clothes and footwear, personal protective gear etc. (prohibitions, warnings.Advantages and disadvantages of proposed instructional maps of safe working methods and practices are highlighted.

Capital planning for operating theatres based on projecting future theatre requirements.

Science.gov (United States)

Sheehan, Jennifer A; Tyler, Peter; Jayasinha, Hirani; Meleady, Kathleen T; Jones, Neill

2011-05-01

During 2006, NSW and ACT Health Departments jointly engaged KPMG to develop an Operating Theatre Requirements' Projection Model and an accompanying planning guideline. A research scan was carried out to identify drivers of surgical demand, theatre capacity and theatre performance, as well as locating existing approaches to modelling operating theatre requirements for planning purposes. The project delivered a Microsoft Excel-based model for projecting future operating theatre requirements, together with an accompanying guideline for use of the model and interpretation of its outputs. It provides a valuable addition to the suite of tools available to Health staff for service and capital planning. The model operates with several limitations, largely due to being data dependent, and the state and completeness of available theatre activity data. However, the operational flexibility built into the model allows users to compensate for these limitations, on a case by case basis, when the user has access to suitable, local data. The design flexibility of the model means that updating the model as improved data become available is not difficult; resulting in revisions being able to be made quickly, and disseminated to users rapidly.

EDF EPR project: operating principles validation and human factor engineering program

International Nuclear Information System (INIS)

Lefebvre, B.; Berard, E.; Arpino, J.-M.

2005-01-01

This article describes the specificities of the operating principles chosen by EDF for the EPR project as a result of an extensive Human Factor Engineering program successfully implemented in an industrial project context. The design process and its achievements benefit of the EDF experience feedback not only in term of NPP operation - including the fully computerized control room of the N4-serie - but also in term of NPP designer. The elements exposed hereafter correspond to the basic design phase of EPR HMI which has been completed and successfully validated by the end of 2003. The article aims to remind the context of the project which basically consists in designing a modern and efficient HMI taking into account the operating needs while relying on proven and reliable technologies. The Human Factor Engineering program implemented merges these both aspects by : 1) being fully integrated within the project activities and scheduling; 2) efficiently taking into account the users needs as well as the feasibility constraints by relying on a multidisciplinary design team including HF specialists, I and C specialists, Process specialists and experienced operator representatives. The resulting design process makes a wide use of experience feedback and experienced operator knowledge to complete largely the existing standards for providing a fully useable and successful design method in an industrial context. The article underlines the design process highlights that largely contribute to the successful implementation of a Human Factor Engineering program for EPR. (authors)

Large hadron collider (LHC) project quality assurance plan

Energy Technology Data Exchange (ETDEWEB)

Gullo, Lisa; Karpenko, Victor; Robinson, Kem; Turner, William; Wong, Otis

2002-09-30

The LHC Quality Assurance Plan is a set of operating principles, requirements, and practices used to support Berkeley Lab's participation in the Large Hadron Collider Project. The LHC/QAP is intended to achieve reliable, safe, and quality performance in the LHC project activities. The LHC/QAP is also designed to fulfill the following objectives: (1) The LHC/QAP is Berkeley Lab's QA program document that describes the elements necessary to integrate quality assurance, safety management, and conduct of operations into the Berkeley Lab's portion of the LHC operations. (2) The LHC/QAP provides the framework for Berkeley Lab LHC Project administrators, managers, supervisors, and staff to plan, manage, perform, and assess their Laboratory work. (3) The LHC/QAP is the compliance document that conforms to the requirements of the Laboratory's Work Smart Standards for quality assurance (DOE O 414.1, 10 CFR 830.120), facility operations (DOE O 5480.19), and safety management (DOE P 450.4).

Large hadron collider (LHC) project quality assurance plan

International Nuclear Information System (INIS)

Gullo, Lisa; Karpenko, Victor; Robinson, Kem; Turner, William; Wong, Otis

2002-01-01

The LHC Quality Assurance Plan is a set of operating principles, requirements, and practices used to support Berkeley Lab's participation in the Large Hadron Collider Project. The LHC/QAP is intended to achieve reliable, safe, and quality performance in the LHC project activities. The LHC/QAP is also designed to fulfill the following objectives: (1) The LHC/QAP is Berkeley Lab's QA program document that describes the elements necessary to integrate quality assurance, safety management, and conduct of operations into the Berkeley Lab's portion of the LHC operations. (2) The LHC/QAP provides the framework for Berkeley Lab LHC Project administrators, managers, supervisors, and staff to plan, manage, perform, and assess their Laboratory work. (3) The LHC/QAP is the compliance document that conforms to the requirements of the Laboratory's Work Smart Standards for quality assurance (DOE O 414.1, 10 CFR 830.120), facility operations (DOE O 5480.19), and safety management (DOE P 450.4)

Earning the social licence for nuclear operations

Energy Technology Data Exchange (ETDEWEB)

Duguay, A.K. [New Brunswick Power, New Brunswick (Canada); Hoornweg, B.J. [Ontario Power Generation, Ontario (Canada)

2010-07-01

In addition to safe nuclear operation, a critical component of earning the social licence is effective communication. This paper outlines development of a communications strategy contributing to overall utility operation and project goals through: 1) Relationships with employees, host communities and the general public that are transparent and honest; 2) Processes that effectively interconnect the internal and external communications; and 3) Organizational leadership models that support communication excellence. With strategic development of these three focus areas the nuclear operator will contribute to increased support of the operator's own licence to operate and of support for the nuclear industry as a whole. (author)

Operations Strategy Development in Project-based Production – a building contractor implements Lean

DEFF Research Database (Denmark)

Koch, Christian; Friis, Ole Uhrskov

2015-01-01

Purpose: To study how operations strategy innovation occurs in project-based production and organisation. Design/methodology/approach: A longitudinal case study encompassing the processes at the company headquarters and in two projects using Lean. Findings: The operations strategy development com...

Progress of the radioactive waste management at the Dalat Nuclear Research Institute and the role of an IAEA technical co-operation project in this process

International Nuclear Information System (INIS)

Nang, N.T.; Ngoc, O.V.; Nhu Thuy, T.T.; Nghi, D.V.; Thu, N.T.

2002-01-01

At present, the main radioactive waste generator in Vietnam is the Dalat Nuclear Research Institute (DNRI). For safe management of radioactive waste generated from this nuclear center, in 1982 Soviet specialists newly constructed one combined technology system for low level radioactive waste management. The existing system consists of two main parts, a Liquid Radioactive Waste Treatment Station and a Storage/Disposal Facility. The liquid treatment station can in principle meet the needs for this nuclear center but disposal technology and storage/disposal facilities are not good enough both with respect to safety and economy, especially the storage/disposal facility placed in Dalat, the tourist city. In order to help DNRI and Vietnam to solve the radioactive waste management problem, the IAEA Technical Co-operation (TC) project VIE/9/007 was implemented in Vietnam. The facilities and IAEA experts provided under this project gradually help to develop radioactive waste management at DNRI, Vietnam. This paper outlines progress under way in the management of the radioactive waste at the Nuclear Research Institute (NRI), Dalat, Vietnam, and the role of the IAEA Technical Co-operation (TC) project in this process. (author)

Range of expert system for control, modeling and safely operation in nuclear energy

International Nuclear Information System (INIS)

Gorlin, A.; Semenov, S.

1990-01-01

The paper describes expert system projects which had been developed formerly and are under the development now in NVIIAES Institute, Moscow. One of the accomplished systems (PEX) is a ES-shell of classical type able to manipulate fuzzy expert assessments. The system is used as a shell for ES-advisor for MCP failures diagnostics and in some applications of the same sort. Another realized system (EDES) is on-line express-diagnostical ES for NPP unit emergency regimes identification. EDES is implemented now as a component of NPP system of control and operation conditions diagnostics. Both systems are realized on conventional programming languages Pascal and C, respectively. The presentation describes current developments in ES as well, including classification system for material researches, the project of training ES for second circuit diagnostics based on event tree generating and expert planner for neutron-physical three-dimensional reactor calculations. All this projects are implemented on different versions of PROLOG programming language

Remote handling techniques in decommissioning - A report of the NEA Co-operative Programme on Decommissioning (CPD) project

International Nuclear Information System (INIS)

Borchardt, Ralf; Denissen, Luc; Desbats, Philippe; Jeanjacques, Michel; Nokhamzon, Jean-Guy; Valentin, Pierre; Slater, Steve; Valencia, Luis; Wittenauer, Stephan; Yamauchi, Toyoaki; Burton, Bob

2011-01-01

The NEA Co-operative Programme for the Exchange of Scientific and Technical Information Concerning Nuclear Installation Decommissioning Projects (CPD) is a joint undertaking of a limited number of organisations actively executing on planning the decommissioning of nuclear facilities. The objective of the CPD is to acquire information from operational experience in decommissioning nuclear installations that is useful for future projects. Although part of the information exchanged within CPD is confidential in nature and is restricted to programme participants, experience of general interest gained under the programme's auspices is released for broader use. Such information is brought to the attention of all NEA members through regular reports to the NEA Radioactive Waste Management Committee (RWMC), as well as through published studies. This report describes generic results obtained by a CPD Task Group analysing the needs for remote technologies. The existing technologies able to meet these needs, the lessons learned and showing where improvements or further developments should be made in this domain. During the D and D process, the handling of highly radioactive materials, the deployment of tools and sensors and the dismantling of components built from many different materials can be a long, labor-intensive process that has the potential for high exposure rates, heat stress and injury to personnel. Mobile robotics systems provide solutions to these hazards. Such remote handling systems are required to perform tasks within budget and on schedule while justifying the expense by a saving in cumulative doses received by project personnel. To reach this goal, the following are additional factors that need to be evaluated when preparing a project: - System and peripherals must be operator-friendly. Ideally, the system must be designed to allow personnel currently available for the D and D project to become trained as operators within a reasonable time frame. - The

Fail-safe computer-based plant protection systems

International Nuclear Information System (INIS)

Keats, A.B.

1983-01-01

A fail-safe mode of operation for computers used in nuclear reactor protection systems was first evolved in the UK for application to a sodium cooled fast reactor. The fail-safe properties of both the hardware and the software were achieved by permanently connecting test signals to some of the multiplexed inputs. This results in an unambiguous data pattern, each time the inputs are sequentially scanned by the multiplexer. The ''test inputs'' simulate transient excursions beyond defined safe limits. The alternating response of the trip algorithms to the ''out-of-limits'' test signals and the normal plant measurements is recognised by hardwired pattern recognition logic external to the computer system. For more general application to plant protection systems, a ''Test Signal Generator'' (TSG) is used to compute and generate test signals derived from prevailing operational conditions. The TSG, from its knowledge of the sensitivity of the trip algorithm to each of the input variables, generates a ''test disturbance'' which is superimposed upon each variable in turn, to simulate a transient excursion beyond the safe limits. The ''tripped'' status yielded by the trip algorithm when using data from a ''disturbed'' input forms part of a pattern determined by the order in which the disturbances are applied to the multiplexer inputs. The data pattern formed by the interleaved test disturbances is again recognised by logic external to the protection system's computers. This fail-safe mode of operation of computer-based protection systems provides a powerful defence against common-mode failure. It also reduces the importance of software verification in the licensing procedure. (author)

State of Montana ITS/CVO business plan : intelligent transportation system commercial vehicle operations

Science.gov (United States)

1998-01-01

This plans purpose is to encourage coordinated, efficient and safe commercial vehicle operations throughout Montana, and to promote inter-agency and regional cooperation as ITS/CVO projects are developed and deployed. The Plan discusses Montana...

Project configured supply networks: Governance of delivery and failures in operations

DEFF Research Database (Denmark)

Koch, Christian

2008-01-01

of delivery types; parts, components and subsystems. The project configuration and orchestrated governance forms are not always successful, and failures emerge. The paper aims at studying governance forms in delivery networks using operational failures as litmus. Operation management approaches is used...... failures occurred during three month observation. The costs were 8 pct. of the production budget. None of the mobilised governance forms fully prevented failures, especially subsystem delivery and internal integration was underperforming.......  Supply networks in complex B2B- construction deliver knowledge, materials, components, subsystems, competences, workforce and management. The delivery network and its governance forms are partly permanent, partly project specific. Integration upstream varies by project, constituting a range...

Safeguards Automated Facility Evaluation (SAFE) methodology

International Nuclear Information System (INIS)

Chapman, L.D.; Grady, L.M.; Bennett, H.A.; Sasser, D.W.; Engi, D.

1978-01-01

The SAFE procedure is an efficient method of evaluating the physical protection system of a nuclear facility. Since the algorithms used in SAFE for path generation and evaluation are analytical, many paths can be evaluated with a modest investment in computer time. SAFE is easy to use because the information required is well-defined and the interactive nature of this procedure lends itself to straightforward operation. The modular approach that has been taken allows other functionally equivalent modules to be substituted as they become available. The SAFE procedure has broad applications in the nuclear facility safeguards field as well as in the security field in general. Any fixed facility containing valuable materials or components to be protected from theft or sabotage could be analyzed using this same automated evaluation technique

Transition plan: Project C-018H, 200-E Area Effluent Treatment Facility

International Nuclear Information System (INIS)

Connor, M.D.

1994-01-01

The purpose of this transition plan is to ensure an orderly transfer of project information to operations to satisfy Westinghouse Hanford Company (WHC) operational requirements and objectives, and ensure safe and efficient operation of Project C-018H, the 200-E Area Effluent Treatment Facility (ETF). This plan identifies the deliverables for Project C-018H upon completion of construction and turnover to WHC for operations, and includes acceptance criteria to objectively assess the adequacy of the contract deliverables in relation to present requirements. The scope of this plan includes a general discussion of the need for complete and accurate design basis documentation and design documents as project deliverables. This plan also proposes that a configuration management plan be prepared to protect and control the transferred design documents and reconstitute the design basis and design requirements, in the event that the deliverables and project documentation received from the contractor are less than adequate at turnover

Potential Operating Orbits for the SAFE-400

International Nuclear Information System (INIS)

Houts, Mike; Kos, Larry; Poston, David

2002-01-01

Safety must be ensured during all phases of space fission system design, development, fabrication, launch, operation, and shutdown. One potential space fission system application is fission electric propulsion (FEP), in which fission energy is converted into electricity and used to power high efficiency (Isp > 3000 s) electric thrusters. For these types of systems it is important to determine which operational scenarios ensure safety while allowing maximum mission performance and flexibility. Space fission systems are essentially non-radioactive at launch, prior to extended operation at high power. Once high power operation begins, system radiological inventory steadily increases as fission products build up. For a given fission product isotope, the maximum radiological inventory is typically achieved once the system has operated for a length of time equivalent to several half-lives. After that time, the isotope decays at the same rate it is produced, and no further inventory builds in. For an FEP mission beginning in Earth orbit, altitude and orbital lifetime increase as the propulsion system operates. Two simultaneous effects of fission propulsion system operation are thus (1) increasing fission product inventory and (2) increasing orbital lifetime. Phrased differently, as fission products build up, more time is required for the fission products to naturally convert back into non-radioactive isotopes. Simultaneously, as fission products build up, orbital lifetime increases, providing more time for the fission products to naturally convert back into nonradioactive isotopes. Operational constraints required to ensure safety can thus be quantified. (authors)

Cooperative project on methods and techniques for assessment of ageing and safety of nuclear objects

International Nuclear Information System (INIS)

Bundara, B.; Udovc, M.; Cvelbar, R.; Vojvodic Tuma, J.; Celin, R.; Cizelj, L.; Simonovski, I.; Pirs, B.; Zabric, I.

2007-01-01

Nuclear Power Plants are so far the most demanding electric power plants concerning the extent and complexity of knowledge that is needed for design, construction, installation, safe operation and proper maintenance. For safe operation of the NPP it is important to have reliable inspection procedures and methods to detect the relevant defects in the components. It is also important to have effective techniques and efficient methodology that enable precise estimation of the material degradation and reliable prediction of the remaining period of the safe service of structures and components. During the operation of NPP its materials, structures and components are exposed to various impacts that have for the result changes in the material. Changes usually manifest as deviation from the origin (generally considered as defects) and can be observed at level of microstructure and/or at structural level. Defects are consequence of ageing and ageing is a consequence of mechanical, thermal, chemical, radiation induced and other processes. Complexity of the NPP and continuous operation at high level of safety demands extensive cooperation of researchers and engineers with different scientific and educational background. In the paper is discussed the importance of sufficient support to the NPP related research projects and the need for cooperation between institutes. As an example is presented the cooperative project that bands the research groups with different scientific background into complementary team working on multidisciplinary project focused on assessment of ageing and safety of nuclear objects. (author)

MONDO Project: real time ocean monitoring through Lagrangian drifters during offshore drilling operations

Energy Technology Data Exchange (ETDEWEB)

Mafra, Tatiana [Eni Oil do Brasil, Rio de Janeiro, RJ (Brazil); Fragoso, Mauricio da Rocha; Santos, Francisco Alves dos; Cruz, Leonardo M. Marques A.; Pellegrini, Julio A.C.; Cerrone, Bruna Nogueira [Prooceano, Rio de Janeiro, RJ (Brazil); Assireu, Arcilan Trevenzoli [Instituto Nacional de Pesquisas Espaciais (INPE), Sao Jose dos Campos, SP (Brazil)

2008-07-01

Monitoring the ocean conditions during offshore operations is essential for both operational and environmental aspects. Environmentally, not only to know better the environment where the activity is taking place, but also to be able to provide fast and accurate response in case of accidents. MONDO Project (Monitoring by Ocean Drifters) is a pioneer initiative from ENI Oil do Brasil and PROOCEANO that aimed to monitor currents as a part of a metoceanographic data monitoring project of drilling operations in Brazilian Waters, in Santos Basin throughout September to November 2007, 40 satellite tracked ocean drifters were deployed will be transmitting data up to November 2008. The results of this project can be used to study a wide range of subjects about ocean dynamics. Following the principles of social and environmental responsibility, MONDO Project aims to benefit the local ecosystem in increasing the scientific knowledge of the area to calibrate hydrodynamic models that will lead to more accurate modeling results and, as a consequence, to a better management of contingency plans. Based on these principles, the project will also provide unrestricted access to oceanographic data even after the end of operations. (author)

Safe operation of nuclear ships

International Nuclear Information System (INIS)

Danilov, L.

1982-01-01

A summary is given of the experience with the three Soviet nuclear icebreakers, Lenin, Arktika and Sibir. Engineering problems, especially of reactor maintenance, and the way they have been overcome, are described. Reference is also made to improvements in reactor fuel and core design, and to safety aspects of the refuelling operation. (U.K.)

Cooperation and dialogical modeling for designing a safe Human space exploration mission to Mars

Science.gov (United States)

Grès, Stéphane; Tognini, Michel; Le Cardinal, Gilles; Zalila, Zyed; Gueydan, Guillaume

2014-11-01

This paper proposes an approach for a complex and innovative project requiring international contributions from different communities of knowledge and expertise. Designing a safe and reliable architecture for a manned mission to Mars or the Asteroids necessitates strong cooperation during the early stages of design to prevent and reduce risks for the astronauts at each step of the mission. The stake during design is to deal with the contradictions, antagonisms and paradoxes of the involved partners for the definition and modeling of a shared project of reference. As we see in our research which analyses the cognitive and social aspects of technological risks in major accidents, in such a project, the complexity of the global organization (during design and use) and the integration of a wide and varie d range of sciences and innovative technologies is likely to increase systemic risks as follows: human and cultural mistakes, potential defaults, failures and accidents. We identify as the main danger antiquated centralized models of organization and the operational limits of interdisciplinarity in the sciences. Beyond this, we can see that we need to take carefully into account human cooperation and the quality of relations between heterogeneous partners. Designing an open, self-learning and reliable exploration system able to self-adapt in dangerous and unforeseen situations implies a collective networked intelligence led by a safe process that organizes interaction between the actors and the aims of the project. Our work, supported by the CNES (French Space Agency), proposes an innovative approach to the coordination of a complex project.

Safe application of a restrictive transfusion protocol in moderate-risk patients undergoing cardiac operations.

Science.gov (United States)

Song, Howard K; von Heymann, Christian; Jespersen, Christian M; Karkouti, Keyvan; Korte, Wolfgang; Levy, Jerrold H; Ranucci, Marco; Saugstrup, Trine; Sellke, Frank W

2014-05-01

Perioperative red blood cell transfusion is associated with adverse outcomes after cardiac operations. Although restrictive transfusion protocols have been developed, their safety and efficacy are not well demonstrated, and considerable variation in transfusion practice persists. We report our experience with a restrictive transfusion protocol. We analyzed the outcomes in 409 patients undergoing cardiac operations enrolled in a trial conducted at 30 centers worldwide. Blood products were administered on the basis of a transfusion algorithm applied across all centers, with a restrictive transfusion trigger of hemoglobin less than or equal to 6 g/dL. Transfusion was acceptable but not mandatory for hemoglobin 6 to 8 g/dL. For hemoglobin 8 to 10 g/dL, transfusion was acceptable only with evidence for end-organ ischemia. The patient population was moderately complex, with 20.5% having combined procedures and 29.6% having nonelective operations. The mean EuroSCORE for the population was 4.3, which predicted a substantial incidence of morbidity and mortality. Actual outcomes were excellent, with observed mortality of 0.49% and rates of cerebrovascular accident, myocardial infarction, and acute renal failure 1.2%, 6.1%, and 0.98%, respectively. The frequency of red blood cell transfusion was 33.7%, which varied significantly by center. Most transfusions (71.9%) were administered for hemoglobin 6 to 8 g/dL; 21.4% were administered for hemoglobin 8 to 10 g/dL with evidence for end-organ ischemia; 65.0% of patients avoided allogeneic transfusion altogether. A restrictive transfusion protocol can be safely applied in the care of moderate-risk patients undergoing cardiac operations. This strategy has significant potential to reduce transfusion and resource utilization in these patients, standardize transfusion practices across institutions, and increase the safety of cardiac operations. Copyright © 2014 The Society of Thoracic Surgeons. Published by Elsevier Inc. All rights

Sixteen Years of International Co-operation. The OECD/NEA Co-operative Programme on Decommissioning

International Nuclear Information System (INIS)

Menon, S.; Valencia, L.

2002-01-01

The Co-operative Programme on Decommissioning under the administration of the Radioactive Waste Management Committee of the OECD Nuclear Energy Agency (NEA) has recently completed sixteen years of operation. The Programme, which is essentially an information exchange programme between decommissioning projects, came into being in 1985. It has grown from an initial 10 decommissioning projects from 7 countries to 39 projects from 14 countries today. From purely information exchange to start with, the Programme has, in later years, been functioning as a voice for the collective expression of views of the implementers of nuclear decommissioning. During the first sixteen years of the operation of the Co-operative Programme, nuclear decommissioning has grown from local specialist activities within projects to a competitive commercial industry. By the dismantling and release from regulatory control of over a dozen diverse nuclear facilities, the Programme has been able to demonstrate in practice, that nuclear decommissioning can be performed safely both for the workers and the public, and that this can be done at reasonable costs in an environmentally friendly fashion. During the recent years, discussions and work within the Co-operative Programme, specially within some of the Task Groups, have had/are having effects and repercussions not just in the field of nuclear decommissioning, but can possibly affect activities and regulations in other industries. This paper describes how the Programme and its activities and procedures have evolved over the years and indicate the directions of developments in the organization and execution of decommissioning projects. Finally, it gives a brief overview of the achievements of the Cooperative Programme and visualizes future developments in the field of nuclear decommissioning

A guide to safe field operations

Science.gov (United States)

Yobbi, D.K.; Yorke, T.H.; Mycyk, R.T.

1996-01-01

Most functions of the U.S. Geological Survey (USGS), Water Resources Division (WRD) require employees to participate in numerous field activities ranging from routine meetings with cooperators, other federal and public officials, and private citizens to potentially hazardous assignments, such as making flood measurements and scuba diving to service underwater instruments. It is paramount that each employee be aware of safety procedures and operational policies of the WRD to ensure that (1) their activities avoid or minimize personal injury to the employee, coworkers, or anyone in the vicinity of the field activity, and (2) their conduct does not infringe on the personal or property rights of any individual or organization. The purpose of the guide is to familiarize employees with the operational and safety procedures expected to be followed by each employee as a representative of the WRD. It is also intended as a training tool for all new employees and a document to be reviewed by each employee before undertaking a field assignment. It includes general procedures that are standard and applicable to all field operations, such as communication, vehicle operation, and adequate preparation for anticipated weather conditions. It also includes a discussion of specific procedures and safety considerations for most of the routine field assignments undertaken by hydrologists and hydrologic technicians of the WRD. The guide is not intended to be a technical handbook outlining step-by-step procedures for performing specific tasks or a comprehensive discussion of every possible activity that may be undertaken by a USGS employee. Employees are referred to the Techniques for Water-Resources Investigations (TWRI) series for specific technical procedures and to the U.S. Geological Survey Safety and Environmental Health Handbook 445-1-H (USGS, August 1989), USGS Occupational Hazards and Safety Procedures Handbook 445-2-H (December 1993), the WRD notebook on Safety Policy and

How should grid operators govern smart grid innovation projects? An embedded case study approach

International Nuclear Information System (INIS)

Reuver, Mark de; Lei, Telli van der; Lukszo, Zofia

2016-01-01

Grid operators increasingly have to collaborate with other actors in order to realize smart grid innovations. For routine maintenance, grid operators typically acquire technologies in one-off transactions, but the innovative nature of smart grid projects may require more collaborate relationships. This paper studies how a transactional versus relational approach to governing smart grid innovation projects affects incentives for other actors to collaborate. We analyse 34 cases of smart grid innovation projects based on extensive archival data as well as interviews. We find that projects relying on relational governance are more likely to provide incentives for collaboration. Especially non-financial incentives such as reputational benefits and shared intellectual property rights are more likely to be found in projects relying on relational governance. Policy makers that wish to stimulate smart grid innovation projects should consider stimulating long-term relationships between grid operators and third parties, because such relationships are more likely to produce incentives for collaboration. - Highlights: • Smart grids require collaboration between grid operators and other actors. • We contrast transactional and relational governance of smart grid projects. • Long-term relations produce more incentives for smart grid collaboration. • Non-financial incentives are more important in long-term relations. • Policy makers should stimulate long-term relations to stimulate smart grids.

Projection-operator calculations of the lowest e--He resonance

International Nuclear Information System (INIS)

Berk, A.; Bhatia, A.K.; Junker, B.R.; Temkin, A.

1986-01-01

Results for the lowest (Schulz) autodetaching state of He - [1s(2s) 2 ] are reported. The calculation utilizes the full projection-operator formalism as explicitly developed by Temkin and Bhatia [Phys. Rev. A 31, 1259 (1985)]. Eigenvalues, scrE = , are calculated using projection operators Q depending on increasingly elaborate target wave functions going up to a 10-term Hylleraas-form, and a configuration-interaction total wave function Phi of 40 configurations. Results are well converged, but our best value is --0.13 eV above the experimental position at 19.37 eV. We conclude that the shift (Δ) in the Feshbach formalism gives a large contribution (relative to the width) to the position E/sub r/ ( = scrE+Δ). An appendix is devoted to the evaluation of the most complicated type of three-center integral involved in the calculation

¡VAMOS! (Viable Alternative Mine Operating System) - a 'Horizon 2020' project

Science.gov (United States)

Sword, Cameron; Bodo, Balazs; Kapusniak, Stef; Bosman, Frank; Rainbird, Jenny; Silva, Eduardo

2017-04-01

The 42-month ¡VAMOS! project (Viable Alternative Mine Operating System, Grant Agreement 642477, www.vamos-project.eu), funded by the EC H2020 Programme, will enable access to high-grade EU reserves of mineral ore-bodies by developing an innovative clean and low visibility mining technique. The project will demonstrate the technological and economic viability of the underwater extraction of metallic mineral deposits which are currently technologically, economically, and environmentally unobtainable. In doing so, ¡VAMOS! hopes to encourage investment in abandoned open-pit mines and prospective mines, helping to put the EU back on a level playing field with the rest of the world in terms of access to strategically important minerals. The ¡VAMOS! concept is defined by a remotely-operated underwater mining vehicle, adapted and improved from existing subsea mining technology. Operating in tandem with an HROV, the mining vehicle will connect to a flexible riser through which slurried mined material will be pumped from the mudline to onshore dewatering facilities via a floating mobile deployment-module, on which will be fitted a bypass system linked to an LIBS, allowing real-time grade-control. Analysis of European and national regulation and stakeholder assessments found there is significant support for developing the technology among local communities and governments. An initial environmental assessment of the potential impact of the innovative mining operation concluded the project has a smaller environmental footprint than conventional mining operations: this is due to factors including the quieter operation and absence of blasting, zero water-table flux, and the higher stripping ratio enabled by higher fluid pressure acting on the sidewalls of the mine. The prototypes are currently in their construction phase following a final design freeze in October 2016. Work is now underway on the foresight visioning, economic evaluation and policy guidelines for the �

Managing Operating Procedures in Distributed Collaborative Projects

Science.gov (United States)

Hool, A.; Beuzelin Ollivier, M.-G.; Roubert, F.

2013-04-01

In recent years, large distributed collaborative projects have become very prominent in scientific research, allowing exchanges between laboratories located in different institutions and countries and between various domains of competence. Particularly the work on nanotoxicity - a field which has only been under investigation for a few years and is still lacking regulatory framework - highlighted the need for well-controlled methods, as well as rules for the handling and disposal of used materials. To obtain comparable and reproducible results of experiments conducted in a distributed context, the standardisation and proper documentation of the applied methods is crucial. The European project NanoDiaRA, whose aim is to develop nanoparticles and biomarkers for the early diagnosis of inflammatory disease, faces this situation as it involves 15 European partners and brings together different scientific cultures and professional backgrounds. Protocols especially developed for Superparamagnetic Iron Oxide Nanoparticles and a management system were designed and implemented within the NanoDiaRA project to fulfil those needs. The main goals were the establishment of standardised Standard Operating Procedures assuring transparency and reproducibility and the provision of access to these protocols to every project partner, as well as their clear allocation to carry out precise measurements and production steps.

Managing Operating Procedures in Distributed Collaborative Projects

International Nuclear Information System (INIS)

Hool, A; Ollivier, M-G Beuzelin; Roubert, F

2013-01-01

In recent years, large distributed collaborative projects have become very prominent in scientific research, allowing exchanges between laboratories located in different institutions and countries and between various domains of competence. Particularly the work on nanotoxicity – a field which has only been under investigation for a few years and is still lacking regulatory framework – highlighted the need for well-controlled methods, as well as rules for the handling and disposal of used materials. To obtain comparable and reproducible results of experiments conducted in a distributed context, the standardisation and proper documentation of the applied methods is crucial. The European project NanoDiaRA, whose aim is to develop nanoparticles and biomarkers for the early diagnosis of inflammatory disease, faces this situation as it involves 15 European partners and brings together different scientific cultures and professional backgrounds. Protocols especially developed for Superparamagnetic Iron Oxide Nanoparticles and a management system were designed and implemented within the NanoDiaRA project to fulfil those needs. The main goals were the establishment of standardised Standard Operating Procedures assuring transparency and reproducibility and the provision of access to these protocols to every project partner, as well as their clear allocation to carry out precise measurements and production steps.

Environmental management compliance reengineering project, FY 1997 report

International Nuclear Information System (INIS)

VanVliet, J.A.; Davis, J.N.

1997-09-01

Through an integrated reengineering effort, the Idaho National Engineering and Environmental Laboratory (INEEL) is successfully implementing process improvements that will permit safe and compliant operations to continue during the next 5 years, even though $80 million was removed from the Environmental Management (EM) program budget. A 2-year analysis, design, and implementation project will reengineer compliance-related activities and reduce operating costs by approximately $17 million per year from Fiscal Year (FY) 1998 through 2002, while continuing to meet the INEEL''s environment, safety, and health requirements and milestone commitments. Compliance reengineer''s focus is improving processes, not avoiding full compliance with environmental, safety, and health laws. In FY 1997, compliance reengineering used a three-phase approach to analyze, design, and implement the changes that would decrease operating costs. Implementation for seven specific improvement projects was completed in FY 1997, while five projects will complete implementation in FY 1998. During FY 1998, the three-phase process will be repeated to continue reengineering the INEEL

Environmental management compliance reengineering project, FY 1997 report

Energy Technology Data Exchange (ETDEWEB)

VanVliet, J.A.; Davis, J.N.

1997-09-01

Through an integrated reengineering effort, the Idaho National Engineering and Environmental Laboratory (INEEL) is successfully implementing process improvements that will permit safe and compliant operations to continue during the next 5 years, even though $80 million was removed from the Environmental Management (EM) program budget. A 2-year analysis, design, and implementation project will reengineer compliance-related activities and reduce operating costs by approximately $17 million per year from Fiscal Year (FY) 1998 through 2002, while continuing to meet the INEEL`s environment, safety, and health requirements and milestone commitments. Compliance reengineer`s focus is improving processes, not avoiding full compliance with environmental, safety, and health laws. In FY 1997, compliance reengineering used a three-phase approach to analyze, design, and implement the changes that would decrease operating costs. Implementation for seven specific improvement projects was completed in FY 1997, while five projects will complete implementation in FY 1998. During FY 1998, the three-phase process will be repeated to continue reengineering the INEEL.

Double Star project - master science operations plan

Science.gov (United States)

Shen, C.; Liu, Z.

2005-11-01

For Double Star Project (DSP) exploration, the scientific operations are very important and essential for achieving its scientific objectives. Two years before the launch of the DSP satellites (TC-1 and TC-2) and during the mission operating phase, the long-term and short-term master science operations plans (MSOP) were produced. MSOP is composed of the operation schedules of all the scientific instruments, the modes and timelines of the Payload Service System on TC-1 and TC-2, and the data receiving schedules of the three ground stations. The MSOP of TC-1 and TC-2 have been generated according to the scientific objectives of DSP, the orbits of DSP, the near-Earth space environments and the coordination with Cluster, etc., so as to make full use of the exploration resources provided by DSP and to acquire as much quality scientific data as possible for the scientific communities. This paper has summarized the observation resources of DSP, the states of DSP and its evolution since the launch, the strategies and rules followed for operating the payload and utilizing the ground stations, and the production of MSOP. Until now, the generation and execution of MSOP is smooth and successful, the operating of DSP is satisfactory, and most of the scientific objectives of DSP have been fulfilled.

Double Star project - master science operations plan

Directory of Open Access Journals (Sweden)

C. Shen

2005-11-01

Full Text Available For Double Star Project (DSP exploration, the scientific operations are very important and essential for achieving its scientific objectives. Two years before the launch of the DSP satellites (TC-1 and TC-2 and during the mission operating phase, the long-term and short-term master science operations plans (MSOP were produced. MSOP is composed of the operation schedules of all the scientific instruments, the modes and timelines of the Payload Service System on TC-1 and TC-2, and the data receiving schedules of the three ground stations. The MSOP of TC-1 and TC-2 have been generated according to the scientific objectives of DSP, the orbits of DSP, the near-Earth space environments and the coordination with Cluster, etc., so as to make full use of the exploration resources provided by DSP and to acquire as much quality scientific data as possible for the scientific communities. This paper has summarized the observation resources of DSP, the states of DSP and its evolution since the launch, the strategies and rules followed for operating the payload and utilizing the ground stations, and the production of MSOP. Until now, the generation and execution of MSOP is smooth and successful, the operating of DSP is satisfactory, and most of the scientific objectives of DSP have been fulfilled.

Reservoir adaptive operating rules based on both of historical streamflow and future projections

Science.gov (United States)

Zhang, Wei; Liu, Pan; Wang, Hao; Chen, Jie; Lei, Xiaohui; Feng, Maoyuan

2017-10-01

Climate change is affecting hydrological variables and consequently is impacting water resources management. Historical strategies are no longer applicable under climate change. Therefore, adaptive management, especially adaptive operating rules for reservoirs, has been developed to mitigate the possible adverse effects of climate change. However, to date, adaptive operating rules are generally based on future projections involving uncertainties under climate change, yet ignoring historical information. To address this, we propose an approach for deriving adaptive operating rules considering both historical information and future projections, namely historical and future operating rules (HAFOR). A robustness index was developed by comparing benefits from HAFOR with benefits from conventional operating rules (COR). For both historical and future streamflow series, maximizations of both average benefits and the robustness index were employed as objectives, and four trade-offs were implemented to solve the multi-objective problem. Based on the integrated objective, the simulation-based optimization method was used to optimize the parameters of HAFOR. Using the Dongwushi Reservoir in China as a case study, HAFOR was demonstrated to be an effective and robust method for developing adaptive operating rules under the uncertain changing environment. Compared with historical or projected future operating rules (HOR or FPOR), HAFOR can reduce the uncertainty and increase the robustness for future projections, especially regarding results of reservoir releases and volumes. HAFOR, therefore, facilitates adaptive management in the context that climate change is difficult to predict accurately.

Safety aspects of long term operation of water moderated reactors. Recommendations on the scope and content of programmes for safe long term operation. Final report of the extrabudgetary programme on safety aspects long term operation of water moderated reactors

International Nuclear Information System (INIS)

2007-07-01

During the last two decades, the number of IAEA Member States giving high priority to continuing the operation of nuclear power plants beyond the time frame originally anticipated is increasing. This is related to the age of nuclear power plants connected to the grid worldwide. The IAEA started to develop guidance on the safety aspects of ageing management in the 1990s. Recognizing the development in a number of its Member States, the IAEA initiated this Extrabudgetary Programme on Safety Aspects of Long Term Operation of Water Moderated Reactors in 2003. The objective of the Programme was to establish recommendations on the scope and content of activities to ensure safe long term operation of water moderated reactors. The term long term operation is used to accommodate various approaches in Member States and is defined as operation beyond an initial time frame set forth in design, standards, licence, and/or regulations, that is justified by safety assessment, considering life limiting processes and features for systems, structures and components. The scope of the Programme included general long term operation framework, mechanical components and materials, electrical components and instrumentation and control, and structural components and structures. The scope of the Programme was limited to physical structures of the NPPs. Four working groups addressed the above indicated technical areas. The Programme steering committee provided coordination and guidance and served as a forum for the exchange of information. The Programme implementation relied on voluntary in kind and financial contributions from the Czech Republic, Hungary, Slovakia, Sweden, the United Kingdom and the USA as well as in kind contributions from Bulgaria, Finland, the Netherlands, the Russian Federation, Spain, the Ukraine, and the European Commission. This report summarizes the main results, conclusions and recommendations of this Programme and provides in the Appendices I-IV detailed

Assessment of safety levels in operation rooms at two major tertiary care public hospitals of Karachi. Safe surgery saves life

International Nuclear Information System (INIS)

Minhas, M.S.; Muzzammil, M.; Effendi, J.

2017-01-01

The objectives of this study are to determine the knowledge and attitude towards surgical safety among the health care professionals including surgeons, anaesthetist, hospital administrators, and operation room personnel and raise awareness towards the importance of safe surgery. Method: A pilot cross- sectional study of 543 healthcare providers working in the operating rooms and the surgical intensive care units was conducted in two tertiary care hospitals, within a study period of one month. A structured questionnaire was constructed and an informed verbal consent was taken. The questionnaire was then distributed; data collected and analysed on SPSS 20.0. Results: A total of 543 respondents participated in the study out of which there were 375 (69%) men and 168 (31%) women. The ages ranged between 23-58 years, mean 40.5+-24.74. There were 110 (20.25%) surgeons, 58 (10.68%) anaesthetist, 132 (24.30%) trainees, 125 (23.02%) technicians, and were 118 (21.73%) nurses. The question regarding briefing operation room personnel is important for patient safety was agreed by 532 (98%) respondents. Amongst the respondents, 239 (44%) did not feel safe to be operated in their own setup. Team communication improvement through the check list implementation was agreed by 483 (89%) respondents. 514 (94.7%) opted for the checklist to be used while they are being operated. That operation room personnel frequently disregard established protocols was agreed by 374 (69%) respondents. 193 (35.54%) of the respondents stated that it is difficult for them to speak up in the or if they perceive a problem with patient care. Conclusion: Operation room personnel were not aware of several important areas related to briefing, communication, safety attitude, following standard protocols and use of WHO Surgical Safety check list. A pre-post intervention study should be conducted after formal introduction of the Checklist. Successful implementation will require taking all stake holders on board

Safe operation of critical assemblies and research reactors. Code of practice and Technical appendix. 1971 ed

International Nuclear Information System (INIS)

Cox, J.

1971-01-01

This book is in two parts. The first is a Code of Practice for the Safe Operation of Critical Assemblies and Research Reactors, prepared as a result of a meeting of experts which took place in Vienna on 20-24 May 1968. The Code has been prepared by the International Atomic Energy Agency in co-operation with the World Health Organization, and its publication is sponsored by both organizations. In addition, the Code was approved by the Board of Governors of the International Atomic Energy Agency on 16 December 1968 as part of the Agency's safety standards, which are applied to operations undertaken by Member States with the assistance of the Agency. The Board, in approving the publication of the present book, also recommended Member States to take the Code into account in the formulation of national regulations and recommendations. The second part of the book is a Technical Appendix to give information and illustrative samples that would be helpful in implementing the Code of Practice. This second part, although published under the same cover, is not part of the Code. An extensive Bibliography, amplifying the Technical Appendix, is included at the end.

CONFLICTS AND OPERATIONAL HURDLES IN THE MANAGEMENT OF INNOVATIVE PROJECTS: AN EMPIRICAL STUDY

Directory of Open Access Journals (Sweden)

José Varela Donato

2013-12-01

Full Text Available This article aims at describing how conflicts and operational hurdles manifest themselves in the management of innovative projects in a development bank (DB. The research characterizes itself as a qualitative and exploratory approach; the data collection consisted of interviews with consultants and project managers and by documents on management projects in Development Bank; the interviews have undergone the content analysis by utilizing the Atlas.ti. The research revealed that the project management in its new implemented model faces difficulties similar to those observed in traditional hierarchies. It was observed that conflicts regarding interests, values, psychological aspects and operational hurdles are intrinsic to the life cycle of innovative projects, which implementation requires a lot of political capacity from their leaders to be effective.

Supervisory and managerial aspects on the safe operation of the Egyptian second research reactor

International Nuclear Information System (INIS)

Abdelrazek, I.D.; Shokr, A.M.

2000-01-01

ETRR-2 is a multipurpose reactor for radioisotopes production, neutron beam experiments, basic and applied research in physics and engineering, fuels and material tests, and for training. The reactor is an open pool type, 22 MW power, with average thermal neutron flux of 1.4x10 14 n/cm 2 sec, cooled and moderated by light water and with beryllium reflectors. Various experimental devices and irradiation facilities are integrated with the reactor. The reactor has been licensed for operation in November 1998. Several principles and regulations have been applied to all the reactor project stages to achieve safety. Moreover, other several principals, regulations, and aspects are enforced by the AEA, National Center for Nuclear Safety and Radiation Control, NCNSRC, and reactor management to achieve safety during reactor operation and utilization. Responsibility on Safety and Supervision Aspects AEA chairman has the ultimate responsibility on the reactor safety during operation and utilization. The primary responsible on the safety is the ETRR-2 supervisor, who is supervising the ETRR-2 site that includes the ETRR-2 reactor, Fuel Manufacturing Plant, and other two projects (under execution): Radioisotopes Production Plant and Dry Fuel Storage Facility. ETRR-2 supervisor is responsible to ensure that: the reactor is operated in accordance with the safety requirements by qualified and trained personnel, updating and enforcement of the reactor mandatory documentation, and the services are adequate for the reactor operation. He is responsible, also, to guarantee that: the reactor manager has enough authority and resources to carry out his function effectively and the reactor is kept operated in agreement with established procedures. A Technical Revision Committee, TRC, is formed to advice the ETRR-2 supervisor on the safety of the reactor and experiments. The committee members are from AEA experts with no direct relation to the reactor and experiments being performed. Members

Advanced Hard Real-Time Operating System, the Maruti Project. Part 2.

Science.gov (United States)

1997-01-01

Real - Time Operating System , The Maruti Project DASG-60-92-C-0055 5b. Program Element # 62301E 6. Author(s...The maruti hard real - time " operating system . A CM SIGOPS, Operating Systems Review. 23:90-106, July 1989. 254 !1 110) C. L. Liu and J. Layland...February 14, 1995 Abstract The Maruti Real - Time Operating System was developed for applications that must meet hard real-time constraints. In order

Examination of a University-Affiliated Safe Ride Program

Science.gov (United States)

Gieck, D. Joseph; Slagle, David M.

2010-01-01

A university-affiliated safe ride program was evaluated to determine whether these programs can reduce drunk-driving related costs. Data was collected from 187 safe ride passengers during three nights of operation. Among the passengers, 93% were enrolled at a local University, 31% were younger than 21, and 40% reported a prior alcohol-related…

LearnSafe. Learning organisations for nuclear safety

International Nuclear Information System (INIS)

Wahlstroem, B.; Kettunen, J.; Reiman, T.

2005-03-01

The nuclear power industry is currently undergoing a period of major change, which has brought with it a number of challenges. These changes have forced the nuclear power plants to initiate their own processes of change in order to adapt to the new situation. This adaptation must not compromise safety at any time, but during a rapid process of change there is a danger that minor problems may trigger a chain of events leading to a degraded safety. Organisational learning has been identified as an important component in ensuring the continued safety and efficiency of nuclear organisations. In response to these challenges a project LearnSafe 'Learning organisations for nuclear safety' was set up and funded by the European Community under the 5th Euratom Framework Programme. The present report gives an account of the LearnSafe project and its major results. (orig.)

Quality performance-based training enhances safe and effective transport operations

International Nuclear Information System (INIS)

McCall, D.L.

1993-01-01

If the hazardous materials transportation industry is to reduce human error, reduce accidents, and improve its public image, there must be assurance that transportation personnel are properly trained and qualified to perform their jobs in a safe and efficient manner. This training must make them intimately aware of the hazards and risks associated with transport activities, ensure understanding of responsibilities and liabilities unique to their job, and ensure that they can competently perform functional duties vital to safety. To ensure that trained and qualified personnel are on the job, it is essential that the training be performance-based and require trainees to demonstrate functional proficiency. Performance-based training has proven to be a highly effective means of ensuring personnel are qualified to conduct their assignments safely and efficiently. This training is designed around the basic premise that training must be provided that supplies the information necessary for each worker to perform their assigned duties at a predetermined and acceptable level of expertise and skill. (J.P.N.)

76 FR 11554 - Fiscal Year 2010 Public Transportation on Indian Reservations Program Project Selections

Science.gov (United States)

2011-03-02

... DEPARTMENT OF TRANSPORTATION Federal Transit Administration Fiscal Year 2010 Public Transportation... Interior for public transportation capital projects, operating costs and planning activities that are... authorized by the Safe, Accountable, Flexible, Efficient Transportation Equity Act: A Legacy for Users...

Applying the TOC Project Management to Operation and Maintenance Scheduling of a Research Vessel

Science.gov (United States)

Manti, M. Firdausi; Fujimoto, Hideo; Chen, Lian-Yi

Marine research vessels and their systems are major assets in the marine resources development. Since the running costs for the ship are very high, it is necessary to reduce the total cost by an efficient scheduling for operation and maintenance. To reduce project period and make it efficient, we applied TOC project management method that is a project management approach developed by Dr. Eli Goldratt. It challenges traditional approaches to project management. It will become the most important improvement in the project management since the development of PERT and critical path methodologies. As a case study, we presented the marine geology research project for the purpose of operations in addition to repair on the repairing dock projects for maintenance of vessels.

The projection operator in a Hilbert space and its directional derivative. Consequences for the theory of projected dynamical systems

Directory of Open Access Journals (Sweden)

George Isac

2004-01-01

Full Text Available In the first part of this paper we present a representation theorem for the directional derivative of the metric projection operator in an arbitrary Hilbert space. As a consequence of the representation theorem, we present in the second part the development of the theory of projected dynamical systems in infinite dimensional Hilbert space. We show that this development is possible if we use the viable solutions of differential inclusions. We use also pseudomonotone operators.

Optimizing hourly hydro operations at the Salt Lake City Area integrated projects

International Nuclear Information System (INIS)

Veselka, T.D.; Hamilton, S.; McCoy, J.

1995-01-01

The Salt Lake City Area (SLCA) office of the Western Area Power Administration (Western) is responsible for marketing the capacity and energy generated by the Colorado Storage, Collbran, and Rio Grande hydropower projects. These federal resources are collectively called the Salt Lake City Area Integrated Projects (SLCA/IP). In recent years, stringent operational limitations have been placed on several of these hydropower plants including the Glen Canyon Dam, which accounts for approximately 80% of the SLCA/IP resources. Operational limitations on SLCA/IP hydropower plants continue to evolve as a result of decisions currently being made in the Glen Canyon Dam Environmental Impact Statement (EIS) and the Power Marketing EIS. To analyze a broad range of issues associated with many possible future operational restrictions, Argonne National Laboratory (ANL), with technical assistance from Western has developed the Hydro LP (Linear Program) Model. This model simulates hourly operations at SLCA/IP hydropower plants for weekly periods with the objective of maximizing Western's net revenues. The model considers hydropower operations for the purpose of serving SLCA firm loads, loads for special projects, Inland Power Pool (IPP) spinning reserve requirements, and Western's purchasing programs. The model estimates hourly SLCA/IP generation and spot market activities. For this paper, hourly SLCA/IP hydropower plant generation is simulated under three operational scenarios and three hydropower conditions. For each scenario an estimate of Western's net revenue is computed

Project margins of advanced reactor design WWER-500

International Nuclear Information System (INIS)

Rogov, M.F.; Birukov, G.I.; Ershov, V.G.; Volkov, B.E.

1994-01-01

Project criteria for design of advanced WWER-500 reactor within design conditions are compared to the requirements of the Russian regulatory guides. Normal operation limits, safe operation limits for main anticipated operational occurrences and design limits accepted for design basis accidents are considered as in preliminary safety report. It is shown that the basic design criteria in the design of WWER-500 for the anticipated operational occurrences and for design basis accidents are more severe than required in the following regulatory guides General Safety Regulations for Nuclear Power Plants and Nuclear Safety Rules for Reactors of Nuclear Power Plants. This provides certain margins from safety point of view

A rapid parallelization of cone-beam projection and back-projection operator based on texture fetching interpolation

Science.gov (United States)

Xie, Lizhe; Hu, Yining; Chen, Yang; Shi, Luyao

2015-03-01

Projection and back-projection are the most computational consuming parts in Computed Tomography (CT) reconstruction. Parallelization strategies using GPU computing techniques have been introduced. We in this paper present a new parallelization scheme for both projection and back-projection. The proposed method is based on CUDA technology carried out by NVIDIA Corporation. Instead of build complex model, we aimed on optimizing the existing algorithm and make it suitable for CUDA implementation so as to gain fast computation speed. Besides making use of texture fetching operation which helps gain faster interpolation speed, we fixed sampling numbers in the computation of projection, to ensure the synchronization of blocks and threads, thus prevents the latency caused by inconsistent computation complexity. Experiment results have proven the computational efficiency and imaging quality of the proposed method.

Project SAFE. Complexing agents in SFR

Energy Technology Data Exchange (ETDEWEB)

Fanger, G.; Skagius, K.; Wiborgh, M. [Kemakta Konsult AB, Stockholm (Sweden)

2001-01-01

Low- and intermediate level radioactive waste, produced at Swedish nuclear power plants, will be deposited in an underground repository, SFR. Different substances in the waste or in degradation products emanating from the waste, and chemicals added during the building of cementitious barriers in the repository, may exhibit complexing properties. The complexation of radionuclides with such ligands may increase the mobility of the deposited radionuclides as sorption on the cement phases is decreased and solubility increased. This could lead to an increased leaching of the radionuclides from the repository to the geosphere and biosphere. To be able to evaluate the implications for the function and long-term safety of the repository a study has been performed on complexants in SFR. The study is a part of project SAFE (Safety Assessment of Final Repository for operational Radioactive Waste) at the Swedish Nuclear Fuel and Waste Management Co, SKB. Concentrations of complexants were calculated in different waste types in the repository and compared to critical levels above which radionuclide sorption may be affected. The analysis is based on recent research presented in international and national literature sources. The waste in SFR that may act or give rise to substances with complexing properties mainly consists of cellulose materials, including cement additives used in waste conditioning and backfill grout. The radioactive waste also contains chemicals mainly used in decontamination processes at the nuclear power plants, e.g. EDTA, NTA, gluconate, citric acid and oxalic acid. The calculations performed in this report show that the presence of complexants in SFR may lead to a sorption reduction for some radionuclides in certain waste types. This may have to be considered when performing calculations of the radionuclide transport. Concentration calculations of isosaccharinic acid (ISA), using a degradation yield of 0.1 mole/kg cellulose (2%), showed that the limit above

Project SAFE. Complexing agents in SFR

International Nuclear Information System (INIS)

Fanger, G.; Skagius, K.; Wiborgh, M.

2001-01-01

Low- and intermediate level radioactive waste, produced at Swedish nuclear power plants, will be deposited in an underground repository, SFR. Different substances in the waste or in degradation products emanating from the waste, and chemicals added during the building of cementitious barriers in the repository, may exhibit complexing properties. The complexation of radionuclides with such ligands may increase the mobility of the deposited radionuclides as sorption on the cement phases is decreased and solubility increased. This could lead to an increased leaching of the radionuclides from the repository to the geosphere and biosphere. To be able to evaluate the implications for the function and long-term safety of the repository a study has been performed on complexants in SFR. The study is a part of project SAFE (Safety Assessment of Final Repository for operational Radioactive Waste) at the Swedish Nuclear Fuel and Waste Management Co, SKB. Concentrations of complexants were calculated in different waste types in the repository and compared to critical levels above which radionuclide sorption may be affected. The analysis is based on recent research presented in international and national literature sources. The waste in SFR that may act or give rise to substances with complexing properties mainly consists of cellulose materials, including cement additives used in waste conditioning and backfill grout. The radioactive waste also contains chemicals mainly used in decontamination processes at the nuclear power plants, e.g. EDTA, NTA, gluconate, citric acid and oxalic acid. The calculations performed in this report show that the presence of complexants in SFR may lead to a sorption reduction for some radionuclides in certain waste types. This may have to be considered when performing calculations of the radionuclide transport. Concentration calculations of isosaccharinic acid (ISA), using a degradation yield of 0.1 mole/kg cellulose (2%), showed that the limit above

InaSAFE applications in disaster preparedness

Science.gov (United States)

Pranantyo, Ignatius Ryan; Fadmastuti, Mahardika; Chandra, Fredy

2015-04-01

Disaster preparedness activities aim to reduce the impact of disasters by being better prepared to respond when a disaster occurs. In order to better anticipate requirements during a disaster, contingency planning activities can be undertaken prior to a disaster based on a realistic disaster scenario. InaSAFE is a tool that can inform this process. InaSAFE is a free and open source software that estimates the impact to people and infrastructure from potential hazard scenarios. By using InaSAFE, disaster managers can develop scenarios of disaster impacts (people and infrastructures affected) to inform their contingency plan and emergency response operation plan. While InaSAFE provides the software framework exposure data and hazard data are needed as inputs to run this software. Then InaSAFE can be used to forecast the impact of the hazard scenario to the exposure data. InaSAFE outputs include estimates of the number of people, buildings and roads are affected, list of minimum needs (rice and clean water), and response checklist. InaSAFE is developed by Indonesia's National Disaster Management Agency (BNPB) and the Australian Government, through the Australia-Indonesia Facility for Disaster Reduction (AIFDR), in partnership with the World Bank - Global Facility for Disaster Reduction and Recovery (GFDRR). This software has been used in many parts of Indonesia, including Padang, Maumere, Jakarta, and Slamet Mountain for emergency response and contingency planning.

Apollo-Soyuz test project. Operations handbook command/service/docking modules (CSM 119/DM 1): Operational procedures reference issue

Science.gov (United States)

1974-01-01

Operational and configuration checks for the Apollo-Soyuz Test Project are presented. The checks include: backup crew prelaunch, prime crew prelaunch, boost and insertion, G and C reference data, G and N reference modes, rendezvous, navigation, Apollo-Soyuz operations, abort procedures, and emergency procedures.

Shippingport Station Decommissioning Project (SSDP): configuration control system and project activity controls

International Nuclear Information System (INIS)

Mullee, G.R.

1986-01-01

The SSDP has been using a Configuration Control system as a significant element in the management plan for the safe and effective performance of the project. The objective of the Configuration Control system is to control the physical plant configuration, system status, work schedules, status tracking, and day-to-day problem resolution. Prior to the Decommissioning Operations Contractor (DOC) assuming operational responsibility for the Shippingport Plant, an assessment was made of the status of the configuration of the systems and related documentation. Action was taken as required to match the operating procedures and system documentation with the actual physical condition of the plant. During the first stage of the project, planning was put in place for subsequent decommissioning activities. This planning included defining organizational responsibilities, completing the necessary project instructions and procedures, and doing the planning and scheduling for the subsequent decommissioning phase activities. Detailed instructions for the performance of the various decommissioning tasks were prepared. Prior to the start of any work on a given Activity Package, a Work Authorization is required. The Work Authorization form provides a complete checklist to ensure that all necessary prerequisites are completed. A computerized Communications Configuration Control Information system monitors status including information on system status, tag-outs, radiological work permits, etc. An ongoing effort is being directed toward maintaining operating instructions and system schematics, etc. current as the Plant configuration changes. The experience with the Configuration Control System to date has been favorable

Ageing management and knowledge base for safe long-term operation of japanese light water reactors

International Nuclear Information System (INIS)

Sekimura, N.

2008-01-01

There are 55 operating commercial light water reactor plants (32 BWRs and 23 PWRs) in Japan. Twelve (12) plants have been operating for more than 30 years. Utility companies are required to perform an 'Ageing Management Technical Assessment' be-fore the end of 30 years operation of each plant. The assessments for each plant have been evaluated by the Nuclear and Industry Safety Agency (NISA) of the Ministry of Economy Trade and Industry (WTI) for these 12 plants. The Japan Nuclear Energy Safety Organisation (JNES) has compiled Technical Review Manuals for six major degradation phenomena for the evaluation of Ageing Management Technical Assessment. A 'Road-map for Ageing and Plant Life Management' was established in 2005 by the Special Committee in the Atomic Energy Society of Japan under the commission from the JNES. Within the framework of the road-map, the major research and development fields are divided into the following four categories: 1) engineering information systems; 2) research and development of technologies for inspection, evaluation and repair of the components and materials; 3) development of codes and standards; 4) synthesised maintenance engineering. Continuous revision of the 'Strategy Maps for Ageing Management and Safe Long-term Operation' has been performed under the Coordinating Committee of Ageing Management to promote research and development activities by industries, government and academia, effectively and efficiently. Systematic development of the information basis for database and knowledge-base has been undertaken in addition to the development of codes and standards by academic societies through intensive domestic safety research collaborations and international collaboration. (author)

Inherently safe in situ uranium recovery

International Nuclear Information System (INIS)

Krumhansl, James Lee; Beauheim, Richard Louis; Brady, Patrick Vane; Arnold, Bill Walter; Kanney, Joseph F.; McKenna, Sean Andrew

2009-01-01

Expansion of uranium mining in the United States is a concern to some environmental groups and sovereign Native American Nations. An approach which may alleviate some problems is to develop inherently safe in situ uranium recovery ('ISR') technologies. Current ISR technology relies on chemical extraction of trace levels of uranium from aquifers that, once mined, can still contain dissolved uranium and other trace metals that are a health concern. Existing ISR operations are few in number; however, high uranium prices are driving the industry to consider expanding operations nation-wide. Environmental concerns and enforcement of the new 30 ppb uranium drinking water standard may make opening new mining operations more difficult and costly. Here we propose a technological fix: the development of inherently safe in situ recovery (ISISR) methods. The four central features of an ISISR approach are: (1) New 'green' leachants that break down predictably in the subsurface, leaving uranium, and associated trace metals, in an immobile form; (2) Post-leachant uranium/metals-immobilizing washes that provide a backup decontamination process; (3) An optimized well-field design that increases uranium recovery efficiency and minimizes excursions of contaminated water; and (4) A combined hydrologic/geochemical protocol for designing low-cost post-extraction long-term monitoring. ISISR would bring larger amounts of uranium to the surface, leave fewer toxic metals in the aquifer, and cost less to monitor safely - thus providing a 'win-win-win' solution to all stakeholders.

Transition projects FY 1995 multi-year program/fiscal year work plan WBS 1.3.1. and 7.1

Energy Technology Data Exchange (ETDEWEB)

1994-09-01

The primary Transition Projects mission is to deactivate facilities on the Hanford site, in preparation for decontamination and decommissioning, and secondarily to provide safe and secure storage of special nuclear materials, nuclear materials, and nuclear fuel. Transition projects will protect the health and safety of the public and of workers, protect the environment, and provide beneficial use of the facilities and other resources. Goals include the following: Achieve deactivation of facilities for transfer to the Hanford Surplus Facility Program, suing PUREX plant deactivation as a model; Achieve excellence in the conduct of operations and maintenance of nuclear facilities in support of the Hanford Site Mission; manage nuclear materials in a safe and secure condition; treat nuclear materials as necessary and store onsite in long-term interim safe storage awaiting a final disposition decision. Description of the program and projects is included.

Transition projects FY 1995 multi-year program/fiscal year work plan WBS 1.3.1. and 7.1

International Nuclear Information System (INIS)

1994-09-01

The primary Transition Projects mission is to deactivate facilities on the Hanford site, in preparation for decontamination and decommissioning, and secondarily to provide safe and secure storage of special nuclear materials, nuclear materials, and nuclear fuel. Transition projects will protect the health and safety of the public and of workers, protect the environment, and provide beneficial use of the facilities and other resources. Goals include the following: Achieve deactivation of facilities for transfer to the Hanford Surplus Facility Program, suing PUREX plant deactivation as a model; Achieve excellence in the conduct of operations and maintenance of nuclear facilities in support of the Hanford Site Mission; manage nuclear materials in a safe and secure condition; treat nuclear materials as necessary and store onsite in long-term interim safe storage awaiting a final disposition decision. Description of the program and projects is included

Safe sex

Science.gov (United States)

... sex; Sexually transmitted - safe sex; GC - safe sex; Gonorrhea - safe sex; Herpes - safe sex; HIV - safe sex; ... contact. STIs include: Chlamydia Genital herpes Genital warts Gonorrhea Hepatitis HIV HPV Syphilis STIs are also called ...

Operational safety of nuclear installations, Netherlands, Borssele, 6-10 April, 1987

International Nuclear Information System (INIS)

1987-01-01

The OSART team observed the increased supervision during shift operations and noticed a positive impact due to increased management presence in the plant. No discrepancies or instances of questionable safety system status was found. The completion of these post OSART long term projects will more clearly identify and formalize some of the processes in the plant in order to continue to assure that the Borssele plant will continue to be operated safely

The Quest CCS Project - MMV Technology Deployment Through Two Years of Operation

Science.gov (United States)

O'Brien, S.

2017-12-01

In September 2012, Shell, on behalf of the Athabasca Oil Sands Project venture (Shell Canada Energy, Chevron Canada Limited, Marathon Oil Canada Corporation), announced that it was proceeding to construct the Quest Carbon Capture and Storage (CCS) project near Fort Saskatchewan. Quest is the world's first large-scale commercial application of CCS at an oil sands operation, and it is now capturing more than one million tonnes of CO2 per year from the Scotford Upgrader. It is a fully integrated project, involving CO2 capture at the bitumen upgrader, transportation along a 65 km pipeline, and CO2 storage in a deep saline aquifer (the Basal Cambrian Sands). Construction was completed in August 2015, and the Quest project was certified for commercial operation in September 2015. The Measurement, Monitoring and Verification (MMV) program for Quest is comprehensive, with a variety of technologies being used to monitor the atmosphere, hydrosphere, biosphere and geosphere. These include a Lightsource system for atmospheric monitoring, extensive groundwater sampling, DAS VSPs to assess the development of the CO2 plume, a microseismic array to measure any induced seismic activity, and temperature and pressure gauges for reservoir monitoring. Over two years of operations, this program has been optimized to address key risks while improving operational efficiency. Quest has now successfully captured and stored more than 2 million tonnes of CO2 with no MMV indications of any storage issues.

Telerobotic Perception During Asteroid and Mars Regolith Operations Project

Science.gov (United States)

Gaddis, Steven; Zeitlin, Nancy (Compiler); Mueller, Robert (Compiler)

2015-01-01

Current space telerobotic systems are constrained to only operating in bright light and dust-free conditions. This project will study the effects of difficult lighting and dust conditions on telerobotic perception systems to better assess and refine regolith operations on other neighboring celestial bodies. In partnership with Embry-Riddle Aeronautical University and Caterpillar, Inc., optical, LiDAR and RADAR sensing equipment will be used in performing the study. This project will create a known dust environment in the Swamp Works Granular Mechanics & Regolith Operations (GMRO) Laboratory regolith test bin to characterize the behavior of the sensing equipment in various calibrated lighting and dust conditions. It will also identify potential methods for mitigating the impacts of these undesirable conditions on the performance of the sensing equipment. Enhancing the capability of telerobotic perception systems will help improve life on earth for those working in dangerous, dusty mining conditions, as well as help advance the same technologies used for safer self-driving automobiles in various lighting and weather conditions. It will also prove to be a critical skill needed for advancing robotic and human exploration throughout our solar system, for activities such as mining on an asteroid or pioneering the first colony on Mars.

Requirements Verification Report AN Farm to 200E Waste Transfer System for Project W-314, Tank Farm Restoration and Safe Operations

International Nuclear Information System (INIS)

MCGREW, D.L.

1999-01-01

This Requirements Verification Report (RVR) for Project W-314 ''AN Farm to 200E Waste Transfer System'' package provides documented verification of design compliance to all the applicable Project Development Specification (PDS) requirements. Additional PDS requirements verification will be performed during the project's procurement, construction, and testing phases, and the RVR will be updated to reflect this information as appropriate

A standardized and safe method of sterile field maintenance during intra-operative horizontal plane fluoroscopy

Directory of Open Access Journals (Sweden)

Kaska Serge C

2010-12-01

Full Text Available Abstract Background Intra-operative fluoroscopy for orthopaedic procedures frequently involves imaging in the horizontal plane, which requires the lower portion of the C-arm (x-ray tube to be rotated from an unsterile zone (beneath the table into the sterile field. To protect the integrity of the sterile field the C-arm must be draped repeatedly throughout the surgical case. The current, un-standardized, practice employs draping procedures which violate the Association of peri-Operative Registered Nurses (AORN Standards and Recommended Practices, waste time and material, and pose an increased risk for surgical site infection. Presentation of the hypothesis Use of a novel sterile C-arm drape (C-armor that maintains the integrity of the sterile field, will improve operating room efficiency and reduce surgical site infection risk factors. This reduction in risk factors may potentially reduce surgical site infections in orthopaedic surgical cases requiring repeated horizontal x-ray imaging. Testing the Hypothesis Savings in time and material and the reduction in surgical site infection risk factors afforded by using C-armor are intuitive to those skilled in the practice of orthopaedic surgery. Testing for a reduction in the number of microorganisms introduced to the surgical site by improved C-arm draping would be challenging due to the multiple confounding factors during a surgical operation. Determination of an absolute reduction in surgical site infections may be possible, but will require accounting for many confounding variables and a large study sample in order to achieve statistical significance. Implications of the Hypothesis Improved intraoperative workflow, healthcare savings and a reduction in surgical site infection risk factors will be achieved by utilizing a standardized and safe method of sterile field maintenance during intra-operative horizontal plane fluoroscopy.

Safe and green nuclear power

International Nuclear Information System (INIS)

Kushwaha, H.S.

2010-01-01

Energy development plays an important role in the national economic growth. Presently the per capita consumption of energy in our country is about 750 kWh including captive power generation which is low in comparison to that in the developed countries like USA where it is about 12,000 kWh. As of now the total installed capacity of electricity generation is about 152,148 MW(e) which is drawn from Thermal (65%), Hydel (24%), Nuclear (3%) power plants and Renewables (8%). It is expected that by the end of year 2020, the required installed capacity would be more than 3,00,000 MW(e), if we assume per capita consumption of about 800-1000 kWh for Indian population of well over one billion. To meet the projected power requirement in India, suitable options need to be identified and explored for generation of electricity. For choosing better alternatives various factors such as availability of resources, potential to generate commercial power, economic viability, etc. need to be considered. Besides these factors, an important factor which must be taken into consideration is protection of environment around the operating power stations. This paper attempts to demonstrate that the nuclear power generation is an environmentally benign option for meeting the future requirement of electricity in India. It also discusses the need for creating the public awareness about the safe operations of the nuclear power plants and ionising radiation. (author)

Safe handling of tritium

International Nuclear Information System (INIS)

1991-01-01

The main objective of this publication is to provide practical guidance and recommendations on operational radiation protection aspects related to the safe handling of tritium in laboratories, industrial-scale nuclear facilities such as heavy-water reactors, tritium removal plants and fission fuel reprocessing plants, and facilities for manufacturing commercial tritium-containing devices and radiochemicals. The requirements of nuclear fusion reactors are not addressed specifically, since there is as yet no tritium handling experience with them. However, much of the material covered is expected to be relevant to them as well. Annex III briefly addresses problems in the comparatively small-scale use of tritium at universities, medical research centres and similar establishments. However, the main subject of this publication is the handling of larger quantities of tritium. Operational aspects include designing for tritium safety, safe handling practice, the selection of tritium-compatible materials and equipment, exposure assessment, monitoring, contamination control and the design and use of personal protective equipment. This publication does not address the technologies involved in tritium control and cleanup of effluents, tritium removal, or immobilization and disposal of tritium wastes, nor does it address the environmental behaviour of tritium. Refs, figs and tabs

Safe handling of renewable fuels and fuel mixtures

Energy Technology Data Exchange (ETDEWEB)

Wilen, C; Rautalin, A [VTT Energy, Espoo (Finland)

1997-12-01

VTT Energy has for several years carried out co-operation with many European research institutes on contractional basis on safety issues of fuels handling. A two-year co-operational project between VTT Energy and these research institutes was started in EU`s JOULE 3 programme in 1996, the total budget of which is 6.9 million FIM. Dust explosion testing method for `difficult` fuels, and for tests at elevated pressures and temperatures, will be developed in the task `Safe handling of renewable fuels and fuel mixtures`. Self- ignition and dust-explosion characteristics will be generated for wood and agro-biomass based biomasses and for the mixtures of them and coal. Inertization requirements will be studied, and the quenching method, combined with partial inertization, will be tested in 1.0 m{sup 3} test equipment. The ignition properties of the fuels under normal and elevated pressures will be characterised with thermobalances. The self-ignition tests with wood and forest residue dusts at 25 bar pressure have been carried out as scheduled. In addition to this, several fuels have undergone thermobalance tests, sieve analyses and microscopic studies for the characterisation of the fuels

Database basic design for safe management radioactive waste

International Nuclear Information System (INIS)

Son, D. C.; Ahn, K. I.; Jung, D. J.; Cho, Y. B.

2003-01-01

As the amount of radioactive waste and related information to be managed are increasing, some organizations are trying or planning to computerize the management on radioactive waste. When we consider that information on safe management of radioactive waste should be used in association with national radioactive waste management project, standardization of data form and its protocol is required, Korea Institute of Nuclear Safety(KINS) will establish and operate nationwide integrated database in order to effectively manage a large amount of information on national radioactive waste. This database allows not only to trace and manage the trend of radioactive waste occurrence and in storage but also to produce reliable analysis results for the quantity accumulated. Consequently, we can provide necessary information for national radioactive waste management policy and related industry's planing. This study explains the database design which is the essential element for information management

A knowledge-based operator advisor system for integration of fault detection, control, and diagnosis to enhance the safe and reliable operation of nuclear power plants

International Nuclear Information System (INIS)

Bhatnagar, R.

1989-01-01

A Knowledged-Based Operator Advisor System has been developed for enhancing the complex task of maintaining safe and reliable operation of nuclear power plants. The operator's activities have been organized into the four tasks of data interpretation for abstracting high level information from sensor data, plant state monitoring for identification of faults, plan execution for controlling the faults, and diagnosis for determination of root causes of faults. The Operator Advisor System is capable of identifying the abnormal functioning of the plant in terms of: (1) deviations from normality, (2) pre-enumerated abnormal events, and (3) safety threats. The classification of abnormal functioning into the three categories of deviations from normality, abnormal events, and safety threats allows the detection of faults at three levels of: (1) developing faults, (2) developed faults, and (3) safety threatening faults. After the identification of abnormal functioning the system will identify the procedures to be executed to mitigate the consequences of abnormal functioning and will help the operator by displaying the procedure steps and monitoring the success of actions taken. The system also is capable of diagnosing the root causes of abnormal functioning. The identification, and diagnosis of root causes of abnormal functioning are done in parallel to the task of procedure execution, allowing the detection of more critical safety threats while executing procedures to control abnormal events

Safe specification of operator precedence rules

NARCIS (Netherlands)

Afroozeh, A.; Brand, van den M.G.J.; Johnstone, A.; Scott, E.; Vinju, J.J.; Erwig, M.; Paige, R.F.; Van Wyk, E.

2013-01-01

In this paper we present an approach to specifying operator precedence based on declarative disambiguation constructs and an implementation mechanism based on grammar rewriting. We identify a problem with existing generalized context-free parsing and disambiguation technology: generating a correct

Projection operators and supplementary conditions for superfields with an arbitrary spin

International Nuclear Information System (INIS)

Sokatchev, E.

1975-01-01

It is shown that a superfield with an external spin j and a nonzero mass contains four non reducible representations of supersymmetry algebra. A general method is proposed for the evolution the representations out of the superfield by using projection operators, derived from Casimir operators. This expansion is also expressed in terms of additional differential conditions

Aviation System Capacity Program Terminal Area Productivity Project: Ground and Airborne Technologies

Science.gov (United States)

Giulianetti, Demo J.

2001-01-01

Ground and airborne technologies were developed in the Terminal Area Productivity (TAP) project for increasing throughput at major airports by safely maintaining good-weather operating capacity during bad weather. Methods were demonstrated for accurately predicting vortices to prevent wake-turbulence encounters and to reduce in-trail separation requirements for aircraft approaching the same runway for landing. Technology was demonstrated that safely enabled independent simultaneous approaches in poor weather conditions to parallel runways spaced less than 3,400 ft apart. Guidance, control, and situation-awareness systems were developed to reduce congestion in airport surface operations resulting from the increased throughput, particularly during night and instrument meteorological conditions (IMC). These systems decreased runway occupancy time by safely and smoothly decelerating the aircraft, increasing taxi speed, and safely steering the aircraft off the runway. Simulations were performed in which optimal trajectories were determined by air traffic control (ATC) and communicated to flight crews by means of Center TRACON Automation System/Flight Management System (CTASFMS) automation to reduce flight delays, increase throughput, and ensure flight safety.

Installation and commissioning of operation nuclear power plant reactor protection system modernization project

International Nuclear Information System (INIS)

Lu Weiwei

2010-01-01

Qinshan Nuclear Power Plant is the first nuclear power plant in mainland China; it is also the first one which realizes the modernization of analog technology based Reactor Protection System in the operation nuclear power plant of China. The implementation schedule is the shortest one which use same digital technology platform (TELEPERM XS of AREVA NP) to modifying the safety class I and C system in the world, the whole project spent 28 months from equipment contract signed to putting system into operation. It open up a era for operation nuclear power plant using mature digital technology to make safety class I and C system modernization in China. The important practical significance of this successful project is very obvious. This article focus on two important project stage--equipment installation and system commissioning, it is based on a large number of engineering implementation fact, it covers the problems and solutions happened during the installation and commission. The purpose of the article is to share the experience and lessons of safety I and C system modernization for other operation nuclear power plant. (authors)

Planetary Boundaries: Exploring the Safe Operating Space for Humanity

DEFF Research Database (Denmark)

Richardson, Katherine; Rockström, Johan; Steffen, Will

2009-01-01

boundaries are rough, first estimates only, surrounded by large uncertainties and knowledge gaps. Filling these gaps will require major advancements in Earth System and resilience science. The proposed concept of "planetary boundaries" lays the groundwork for shifting our approach to governance...... and management, away from the essentially sectoral analyses of limits to growth aimed at minimizing negative externalities, toward the estimation of the safe space for human development. Planetary boundaries define, as it were, the boundaries of the "planetary playing field" for humanity if we want to be sure...

Project SAFE. Update of the SFR-1 safety assessment. Phase 1. Appendix A2: Scenarios

International Nuclear Information System (INIS)

Skagius, K.; Wiborgh, M.

1998-01-01

This appendix gives a short description of the scenario methodology adopted in the previous safety assessment of SFR. Since then new methodologies for developing structured descriptions of how processes and interactions between processes affect the evolution of a repository system. Two such methods are briefly described. These methods are very similar, but they differ in the way the system is graphically structured. One of the methods is based on Process Influence Diagrams, PID, and the other on Interaction matrices. It is proposed that the method based on Interaction matrices is used for the scenario work in project SAFE. The main reason for this is that the method already has been applied by SKB, which means that it will be possible to use already existing procedures and documentation systems. The proposed procedure involves the development of Interaction matrices for a defined Reference scenario and the use of these matrices to illustrate the effect of different Scenario initiating FEPs. The proposed procedure is described in this appendix

Study on evaluation of construction reliability for engineering project based on fuzzy language operator

Science.gov (United States)

Shi, Yu-Fang; Ma, Yi-Yi; Song, Ping-Ping

2018-03-01

System Reliability Theory is a research hotspot of management science and system engineering in recent years, and construction reliability is useful for quantitative evaluation of project management level. According to reliability theory and target system of engineering project management, the defination of construction reliability appears. Based on fuzzy mathematics theory and language operator, value space of construction reliability is divided into seven fuzzy subsets and correspondingly, seven membership function and fuzzy evaluation intervals are got with the operation of language operator, which provides the basis of corresponding method and parameter for the evaluation of construction reliability. This method is proved to be scientific and reasonable for construction condition and an useful attempt for theory and method research of engineering project system reliability.

Selected Area Fishery Evaluation Project Economic Analysis Study Final Report, Final Draft Revision 4: November 10, 2006.

Energy Technology Data Exchange (ETDEWEB)

Bonneville Power Administration; Washington Department of Fish and Wildlife; Oregon Department of Fish and Wildlife

2006-11-01

The purpose of this Study is to provide an economic review of current and proposed changes to the Select Area Fishery Evaluation Project (SAFE or Project). The Study results are the information requested in comments made on the Project by a joint review dated March 2005 by the Northwest Power and Conservation Council (NPCC) Independent Scientific Review Panel (ISRP) and Independent Economic Analysis Board (IEAB). North et al. (2006) addressed technical questions about operations and plans, and this report contains the response information for comments concerning Project economics. This report can be considered an economic feasibility review meeting guidelines for cost-effective analysis developed by the IEAB (2003). It also contains other economic measurement descriptions to illustrate the economic effects of SAFE. The SAFE is an expansion of a hatchery project (locally called the Clatsop Economic Development Council Fisheries Project or CEDC) started in 1977 that released an early run coho (COH) stock into the Youngs River. The Youngs River entrance to the Columbia River at River Mile 12 is called Youngs Bay, which is located near Astoria, Oregon. The purpose of the hatchery project was to provide increased fishing opportunities for the in-river commercial fishing gillnet fleet. Instead of just releasing fish at the hatchery, a small scale net pen acclimation project in Youngs Bay was tried in 1987. Hirose et al. (1998) found that 1991-1992 COH broodstock over-wintered at the net pens had double the smolt-to-adult return rate (SAR) of traditional hatchery release, less than one percent stray rates, and 99 percent fishery harvests. It was surmised that smolts from other Columbia River hatcheries could be hauled to the net pens for acclimation and release to take advantage of the SAR's and fishing rates. Proposals were tendered to Bonneville Power Administration (BPA) and other agencies to fund the expansion for using other hatcheries smolts and other off

Beam interlock system and safe machine parameters system 2010 and beyond

CERN Document Server

Todd, B

2010-01-01

The Beam Interlock System (BIS) and Safe Machine Parameters (SMP) system are central to the protection of the Large Hadron Collider (LHC) machine. The BIS has been critical for the safe operation of LHC from the first day of operation. It has been installed and commissioned, only minor enhancements are required in order to accommodate all future LHC machine protection requirements. At reduced intensity, the SMP system is less critical for LHC operation. As such, the current system satisfies the 2010 operational requirements. Further developments are required, both at the SMP Controller level, and at the system level, in order to accommodate the requirements of the LHC beyond 2010.

Fail-safe logic elements for use with reactor safety systems

International Nuclear Information System (INIS)

Bobis, J.P.; McDowell, W.P.

1976-01-01

A complete fail-safe trip circuit is described which utilizes fail-safe logic elements. The logic elements used are analog multipliers and active bandpass filter networks. These elements perform Boolean operations on a set of AC signals from the output of a reactor safety-channel trip comparator

OECD/NEA component operational experience, degradation and ageing project

International Nuclear Information System (INIS)

Gott, K.; Nevander, O.; Riznic, J.; Lydell, B.

2015-01-01

Several OECD Member Countries have agreed to establish the OECD/NEA 'Component Operational Experience, Degradation and Ageing Programme' (CODAP) to encourage multilateral co-operation in the collection and analysis of data relating to degradation and failure of metallic piping and non-piping metallic passive components in commercial nuclear power plants. The scope of the data collection includes service-induced wall thinning, part through-wall cracks, through-wall cracks with and without active leakage, and instances of significant degradation of metallic passive components, including piping pressure boundary integrity. CODAP is the continuation of the 2002-2011 'OECD/NEA Pipe Failure Data Exchange Project' (OPDE) and the Stress Corrosion Cracking Working Group of the 2006-2010 - OECD/NEA SCC and Cable Ageing project - (SCAP). OPDE was formally launched in May 2002. Upon completion of the 3. Term (May 2011), the OPDE project was officially closed to be succeeded by CODAP. In May 2011, 13 countries signed the CODAP first Term agreement. The first Term (2011-2014) work plan includes the development of a web-based relational event database on passive, metallic components in commercial nuclear power plants, a web-based knowledge base on material degradation, codes and standards relating to structural integrity and national practices for managing material degradation. The work plan also addresses the preparation of Topical Reports to foster technical cooperation and to deepen the understanding of national differences in ageing management. These Topical Reports are in the public domain and available for download on the NEA web site. Published in 2014, a first Topical Report addressed flow accelerated corrosion (FAC) of carbon steel and low alloy steel piping. A second Topical Report addresses operating experience with electro-hydraulic control (EHC) and instrument air (IA) system piping

Safe Active Scanning for Energy Delivery Systems Final Report

Energy Technology Data Exchange (ETDEWEB)

Helms, J. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Salazar, B. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Scheibel, P. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Engels, M. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Reiger, C. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

2017-09-30

The Department of Energy’s Cybersecurity for Energy Delivery Systems Program has funded Safe(r) Active Scanning for Energy Delivery Systems, led by Lawrence Livermore National Laboratory, to investigate and analyze the impacts of active scanning in the operational environment of energy delivery systems. In collaboration with Pacific Northwest National Laboratory and Idaho National Laboratory, active scans across three testbeds including 38 devices were performed. This report gives a summary of the initial literature survey performed on the SASEDS project as well as industry partner interview summaries and main findings from Phase 1 of the project. Additionally, the report goes into the details of scanning techniques, methodologies for testing, testbed descriptions, and scanning results, with appendices to elaborate on the specific scans that were performed. As a result of testing, a single device out of 38 exhibited problems when actively scanned, and a reboot was required to fix it. This single failure indicates that active scanning is not likely to have a detrimental effect on the safety and resilience of energy delivery systems. We provide a path forward for future research that could enable wide adoption of active scanning and lead utilities to incorporate active scanning as part of their default network security plans to discover and rectify rogue devices, adversaries, and services that may be on the network. This increased network visibility will allow operational technology cybersecurity practitioners to improve their situational awareness of networks and their vulnerabilities.

New maintenance strategy of Tokyo Electric Power Company and Fukushima Dai-ichi Nuclear Power Plant for effective ageing management and safe long-term operation

International Nuclear Information System (INIS)

Inagaki, Takeyuki; Yamashita, Norimichi

2009-01-01

Fukushima Dai-ichi Nuclear Power Plant is the oldest among three nuclear power plants owned and operated by Tokyo Electric Power Company, which consists of six boiling water reactor units. The commercial operation of Unit 1 was commenced in 1971 (37 years old) and Unit 6 in 1978 (29 years old). Currently ageing degradations of systems, structures and components are managed through maintenance programs, component replacement/refurbishment programs and long-term maintenance plans. The long-term maintenance plans are established through ageing management component replacement/refurbishment programs reviews performed before the 30th year of operation and they are for safe and reliable operation after 30 years (long-term operation). However the past maintenance actions and past component replacement/refurbishment programs were not always proactive and past operational experience and maintenance practices suggest that effective/proactive ageing management programs be introduced in earlier stage of the plant operation. In this circumstance, Tokyo Electric Power Company and Fukushima Dai-ichi Nuclear Power Plant are setting up a new maintenance strategy that includes 1) improving the normal maintenance programs by using ageing degradation data, 2) effective use of information on internal/external operational experience and maintenance practices related to ageing, and 3) proactive component/equipment refurbishment programs during a refreshment outage for safe and reliable long-term operation. To accomplish the goal of this strategy, strengthening engineering capability of plant staff members is a crucial required for the plant. The objective of this paper is to briefly explain main results ageing management reviews, past and current significant ageing issues and management programs against them, and the new maintenance strategy established by Tokyo Electric Power Company and Fukushima Dai-ichi Nuclear Power Plant. (author)

Operations planning and analysis handbook for NASA/MSFC phase B development projects

Science.gov (United States)

Batson, Robert C.

1986-01-01

Current operations planning and analysis practices on NASA/MSFC Phase B projects were investigated with the objectives of (1) formalizing these practices into a handbook and (2) suggesting improvements. The study focused on how Science and Engineering (S&E) Operational Personnel support Program Development (PD) Task Teams. The intimate relationship between systems engineering and operations analysis was examined. Methods identified for use by operations analysts during Phase B include functional analysis, interface analysis methods to calculate/allocate such criteria as reliability, Maintainability, and operations and support cost.

78 FR 57319 - Children's Online Privacy Protection Rule Safe Harbor Proposed Self-Regulatory Guidelines...

Science.gov (United States)

2013-09-18

...-AB20 Children's Online Privacy Protection Rule Safe Harbor Proposed Self-Regulatory Guidelines; kidSAFE... proposed self-regulatory guidelines submitted by the kidSAFE Seal Program (``kidSAFE''), owned and operated... enabling industry groups or others to submit to the Commission for approval self-regulatory guidelines that...

Digital computer operation of a nuclear reactor

International Nuclear Information System (INIS)

Colley, R.W.

1984-01-01

A method is described for the safe operation of a complex system such as a nuclear reactor using a digital computer. The computer is supplied with a data base containing a list of the safe state of the reactor and a list of operating instructions for achieving a safe state when the actual state of the reactor does not correspond to a listed safe state, the computer selects operating instructions to return the reactor to a safe state

Financing Build, Operate and Transfer (BOT) Projects: The Case of Islamic Instruments

OpenAIRE

Khan, Tariqullah

2002-01-01

Several member countries of the Islamic Development Bank have embarked upon a program of developing and maintaining infrastructure projects by the private sector in the framework of build operate and transfer (BOT) mechanism and its various variants. The present paper reviews these experiences and the peculiar risks associated with investments in these projects as compared to the risks of traditional manufacturing sector and offers a framework for Islamic instruments to finance BOT projects.

Spent Nuclear Fuel Project Cold Vacuum Drying Facility Operations Manual

International Nuclear Information System (INIS)

IRWIN, J.J.

1999-01-01

This document provides the Operations Manual for the Cold Vacuum Drying Facility (CVDF). The Manual was developed in conjunction with HNF-553, Spent Nuclear Fuel Project Final Safety Analysis Report Annex B--Cold Vacuum Drying Facility. The HNF-SD-SNF-DRD-002, 1999, (Cold Vacuum Drying Facility Design Requirements), Rev. 4. and the CVDF Final Design Report. The Operations Manual contains general descriptions of all the process, safety and facility systems in the CVDF, a general CVD operations sequence and references to the CVDF System Design Descriptions (SDDs). This manual has been developed for the SNFP Operations Organization and shall be updated, expanded, and revised in accordance with future design, construction and startup phases of the CVDF until the CVDF final ORR is approved

Independent technical review of the Sandia National Laboratories Environmental Restoration Project

International Nuclear Information System (INIS)

1994-11-01

An Independent Technical Review was conducted of the Environmental Restoration Project. The objective of the review was recommendations, from a commercial perspective, on a systems level path forward to safe, minimum cost and schedule project completion. The work presented represents the consensus analysis and recommendations of thirteen individuals with varied backgrounds, expertise, and experience. The ITR team recommends that the barriers to the opportunity described in the diagnosis be eliminated using an integrated DOE-Sandia system approach. Piecemeal changes will not result in the desired commercial efficiency. DOE needs to operate as the contracting agency for a Major System Acquisition. If it does not, commercial performance will not be achieved regardless of the contractor. Likewise, Sandia needs to establish and implement the necessary project structure and management systems to operate with commercial contractor like efficiency

Lessons learned in demonstration projects regarding operational safety during final disposal of vitrified waste and spent fuel

International Nuclear Information System (INIS)

Filbert, Wolfgang; Herold, Philipp

2015-01-01

The paper summarizes the lessons learned in demonstration projects regarding operational safety during the final disposal of vitrified waste and spent fuel. The three demonstration projects for the direct disposal of vitrified waste and spent fuel are described. The first two demonstration projects concern the shaft transport of heavy payloads of up to 85 t and the emplacement operations in the mine. The third demonstration project concerns the borehole emplacement operation. Finally, open issues for the next steps up to licensing of the emplacement and disposal systems are summarized.

Project Design Concept - Primary Ventilation System

International Nuclear Information System (INIS)

MCGREW, D.L.

2000-01-01

Tank Farm Restoration and Safe Operation (TFRSO), Project W-3 14 was established to provide upgrades that would improve the reliability and extend the system life of portions of the waste transfer, electrical, ventilation, instrumentation and control systems for the Hanford Site Tank Farms. An assessment of the tank farm system was conducted and the results are documented in system assessment reports. Based on the deficiencies identified in the tank farm system assessment reports, and additional requirements analysis performed in support of the River Protection Project (RPP), an approved scope for the TFRSO effort was developed and documented in the Upgrade Scope Summary Report (USSR), WHC-SD-W314-RPT-003, Rev. 4. The USSR establishes the need for the upgrades and identifies the specific equipment to be addressed by this project. This Project Design Concept (PDC) is in support of the Phase 2 upgrades and provides an overall description of the operations concept for the W-314 Primary Ventilation Systems. Actual specifications, test requirements, and procedures are not included in this PDC. The PDC is a ''living'' document, which will be updated throughout the design development process to provide a progressively more detailed description of the W-314 Primary Ventilation Systems design. The Phase 2 upgrades to the Primary Ventilation Systems shall ensure that the applicable current requirements are met for: Regulatory Compliance; Safety; Mission Requirements; Reliability; and Operational Requirements

IUE project comes to an end after 18+ years of extremely successful orbital operations

Science.gov (United States)

1996-08-01

At a meeting of the Science Programme Committee (SPC) of the European Space Agency (ESA) in February, the decision was taken to terminate the orbital operations of the International Ultraviolet Explorer (IUE) satellite on September 30. Science operations will terminate shortly before that date to allow the necessary end-of-life testing of the spacecraft. Only a year ago, when NASA - the major partner in the IUE project - decided to terminate its IUE science operations, ESA had been able to extend its support to include full responsibility for the scientific operations, under the "hybrid science operations" scheme, and thus maintain this important capability for the astrophysics community. As a consequence of the budgetary restrictions placed on ESA's Science Programme, the earlier recommendation of the Space Science Advisory Committee (SSAC), to terminate the operations of IUE in coordination with NASA in September, was accepted by the SPC. The IUE project, using a 45cm ultraviolet telescope for spectroscopic observations in the waveband 115 to 320 nm, has been carried out jointly by NASA, ESA and the British PPARC (formerly SERC). Launched in 1978, its designed lifetime was only three years. In July, the SPC agreed to complete the IUE Final Archive by the end of 1997, allowing the project to reprocess all its spectroscopic observations (numbering over 100,000) with a newly designed reduction, significantly improving on the normal direct processing done during the operational phase of the IUE project. The resulting homogeneous data archive on the ultraviolet radiation of cosmic sources, collected over the 18+ years of the operational project, will remain an important resource for astrophysical studies for many years to come. This has been one of the most successful astrophysics projects in space science, with more than 3,500 papers in refereed journals based on the observational results of the spectrographs. Over 500 doctoral dissertations have used its results

Plant life management in Belgium: an integrated project

International Nuclear Information System (INIS)

Wacquier, W.; Smet, M. de; Hennart, J.C.; Greer, J.L.; Breesch, Ch.; Havard, P.

2001-01-01

In Belgium, a specific plant life management project, named ''Continuous Operation of Belgian NPPs'' is currently developing. Its final objective is to centralize all safety and economic aspects of plant life management in order to determine, for each NPP unit, the optimal actions required to maintain their safe and reliable operation. As the lifetime of safety-related active components is permanently controlled by the current maintenance programs, the project focuses only on passive safety-related components and on non-safety components important for the availability of the plants. These structures and components were evaluated and compared on the basis of a set of weighted criteria in order to measure their criticality and to identify those which must be considered in the project. The selection and the ranking of those components is based on the KBM TM methodology (Knowledge Based Maintenance). This methodology facilitates the collection, formalization and exchange of know-how and gives immediate results thanks to a sequential and systematic step by step analysis. (author)

Premiering SAFE for Safety Added Fuel Element - 15020

International Nuclear Information System (INIS)

Bhowmik, P.K.; Shamim, J.A.; Suh, K.Y.; Suh, K.S.

2015-01-01

The impact of the Fukushima accident has been the willingness to implement passive safety measures in reactor design and to simplify reactor design itself. Within this framework, a new fuel element, named SAFE (Safety Added Fuel Element) based on the concept of accident tolerant fuel, is presented. SAFE is a new type of fuel element cooled internally and externally by light water and with stainless steel as the cladding material. The removal of boron may trigger a series of changes which may simplify the system greatly. A simplified thermal analysis of SAFE shows that the fuel centerline temperature is well below the maximal limit during the normal operation of the plant

The application of post-project reviews in events management by cultural operators

OpenAIRE

Benadict Rajasegaram, Annet

2016-01-01

Organisations have evidently shifted towards the projectification of their activities and operations across the world and across industries by which project management is not only limited to construction and engineering projects anymore. The projectification has shed light on the amount of project success and failure in which both have been noted to have a steep difference between each other. Whilst many factors have been discovered to be a trigger of failure or success one emerging subject t...

The Resident-Run Minor Surgery Clinic: A Pilot Study to Safely Increase Operative Autonomy.

Science.gov (United States)

Wojcik, Brandon M; Fong, Zhi Ven; Patel, Madhukar S; Chang, David C; Petrusa, Emil; Mullen, John T; Phitayakorn, Roy

increased operative autonomy as the greatest strength. Implementation of a resident-run minor surgery clinic is a safe and effective method to increase trainee operative autonomy. The rotation is well suited for mid-level residents, as it provides an opportunity for realistic self-evaluation and focused learning that may enhance their operative experience during senior level rotations. Copyright © 2016 Association of Program Directors in Surgery. Published by Elsevier Inc. All rights reserved.

Safeguards Automated Facility Evaluation (SAFE) methodology

International Nuclear Information System (INIS)

Chapman, L.D.; Grady, L.M.; Bennett, H.A.; Sasser, D.W.; Engi, D.

1978-08-01

An automated approach to facility safeguards effectiveness evaluation has been developed. This automated process, called Safeguards Automated Facility Evaluation (SAFE), consists of a collection of a continuous stream of operational modules for facility characterization, the selection of critical paths, and the evaluation of safeguards effectiveness along these paths. The technique has been implemented on an interactive computer time-sharing system and makes use of computer graphics for the processing and presentation of information. Using this technique, a comprehensive evaluation of a safeguards system can be provided by systematically varying the parameters that characterize the physical protection components of a facility to reflect the perceived adversary attributes and strategy, environmental conditions, and site operational conditions. The SAFE procedure has broad applications in the nuclear facility safeguards field as well as in the security field in general. Any fixed facility containing valuable materials or components to be protected from theft or sabotage could be analyzed using this same automated evaluation technique

CHANGING THE LANDSCAPE--LOW-TECH SOLUTIONS TO THE PADUCAH SCRAP METAL REMOVAL PROJECT ARE PROVIDING SAFE, COST-EFFECTIVE REMEDIATION OF CONTAMINATED SCRAP YARDS

International Nuclear Information System (INIS)

Watson, Dan; Eyman, Jeff

2003-01-01

Between 1974 and 1983, contaminated equipment was removed from the Paducah Gaseous Diffusion Plant (PGDP) process buildings as part of an enrichment process upgrade program. The upgrades consisted of the dismantlement, removal, and on-site storage of contaminated equipment, cell components, and scrap material (e.g., metal) from the cascade facilities. Scrap metal including other materials (e.g., drums, obsolete equipment) not related to this upgrade program have thus far accumulated in nine contiguous radiologically-contaminated and non-contaminated scrap yards covering 1.05E5 m2 (26 acres) located in the northwestern portion of the PGDP. This paper presents the sequencing of field operations and methods used to achieve the safe removal and disposition of over 47,000 tonnes (53,000 tons) of metal and miscellaneous items contained in these yards. The methods of accomplishment consist of mobilization, performing nuclear criticality safety evaluations, moving scrap metal to ground level, inspection and segregation, sampling and characterization, scrap metal sizing, packaging and disposal, and finally demobilization. Preventing the intermingling of characteristically hazardous and non-hazardous wastes promotes waste minimization, allowing for the metal and materials to be segregated into 13 separate waste streams. Low-tech solutions such as using heavy equipment to retrieve, size, and package scrap materials in conjunction with thorough planning that integrates safe work practices, commitment to teamwork, and incorporating lessons learned ensures that field operations will be conducted efficiently and safely

Guidelines for safe process operations and maintenance

CERN Document Server

2010-01-01

First-line managers have to maintain the integrity of facilities, control manufacturing processes, and handle unusual or emergency situations, as well as respond to the pressures of production demand. On a daily basis, they are closest to the operating personnel who may be injured by a process accident, and they are in the best position to spot problem conditions and to act to contain them. This book offers these managers ""how-to"" information on process safety management program execution in the operations and maintenance departments, recommending technical and administrative process safety

Department of Energy Operation Quality Assurance Program for the Waste Isolation Pilot Plant (WIPP) Project (Carlsbad, New Mexico)

International Nuclear Information System (INIS)

1987-12-01

The purpose of this plan is to describe the Quality Assurance (QA)reverse arrow Program to be established and implemented by the US Department of Energy (DOE) Waste Isolation Pilot Plant (WIPP) Project Office (WPO) and by the Project Participants: the Scientific Advisor (Sandia National Laboratory) and the Management and Operating Contractor (Westinghouse Electric Corporation). This plan addresses the Pre-Operational and Operational phases of the WIPP Project not addressed under the construction phase. This plan also requires the QA Programs for DOE and Project Participants to be structured so as to comply with this plan and ANSI-ASME NQA-1. The prime responsibility for Operational Quality Assurance rests with the DOE WIPP Project Office and is implemented through the combined efforts of the Scientific Advisor and the Management and Operating Contractor. Overviews of selected operational and testing activities will be are conducted in accordance with prescribed requirements and that adequate documentation of these activities is maintained. 4 figs

Guideline for safe and eco-friendly biomass gasification

Energy Technology Data Exchange (ETDEWEB)

Vos, J.; Knoef, H. (BTG biomass technology group, Enschede (Netherlands)); Hauth, M. (Graz Univ. of Technology. Institute of Thermal Engineering, Graz (Austria)) (and others)

2009-11-15

The objective of the Gasification Guide project is to accelerate the market penetration of small-scale biomass gasification systems (< 5 MW fuel power) by the development of a Guideline and Software Tool to facilitate risk assessment of HSE aspects. The Guideline may also be applied in retrofitting or converting old thermal plants in the Eastern European countries - with rich biomass recourses - to new gasification plants. The objective of this document is to guide key target groups identifying potential hazards and make a proper risk assessment. The software tool is an additional aid in the risk assessment. This guideline is intended to be a training tool and a resource for workers and employers to safely design, fabricate, construct, operate and maintain small-scale biomass gasification facilities. The Guideline is applicable with the following constraints: 1) The maximum scale of the gasification plant was agreed to be about 1 MW{sub e}. The reason is that large companies do have normally their safety rules in place; 2) This means in principle only fixed bed gasifier designs. However, most parts are also valid to other designs and even other thermal conversion processes; 3) The use of contaminated biomass is beyond the scope of this Guideline. The Guideline contains five major chapters; Chapter 2 briefly describes the gasification technology in general. Chapter 3 gives an overview of major legal framework issues on plant permission and operation. The legal frame is changing and the description is based on the situation by the end of 2007. Chapter 4 explains the theory behind the risk assessment method and risk reduction measures. Chapter 5 is the heart of the Guideline and gives practical examples of good design, operation and maintenance principles. The practical examples and feedback have been received throughout the project and the description is based on mid-2009. Chapter 6 describes the best techniques currently available for emission abatement which are

Offset project report : Cleanit Greenit aerobic composting project

Energy Technology Data Exchange (ETDEWEB)

NONE

2009-02-15

The Cleanit Greenit site is owned and operated by Cleanit Greenit Composting System Inc. and is a composting facility located in Edmonton, Alberta. The facility has an annual processing capacity of 20,000 tonnes of organic waste and was the first in Canada to compost a large variety of industrial by-products containing hydrocarbons, through controlled blending with other wastes and monitoring of moisture, temperature and pH. The composting process turns organic waste material from industrial, commercial and domestic sources into finished projects, thus removing these materials from conditions where treatment and disposal is often difficult, expensive and environmentally harmful. This protocol document covered the diversion of organic residues from landfill for biological decomposition to a condition sufficiently stable for nuisance-free storage and for safe use in land application. A wide variety of organic residues were considered, including agricultural and agri-food residues; the organic portion of municipal solid waste; food wastes; and forestry and landscaping wastes. The document presented information on the Cleanit Greenit project and discussed the calculation of greenhouse gas emission reductions. An appendix that contained the Cleanit Greenit aerobic composting offset project plan was also provided. tabs., figs.

Co-operation between Slovenia and Croatia in the low- and intermediate level radioactive waste repository project

International Nuclear Information System (INIS)

Schaller, A.; Lokner, V.; Subasic, D.; Zeleznik, N.; Mele, I.; Tomse, P.

2001-01-01

The paper describes the LILW repository project development in Slovenia and Croatia from the viewpoint of co-operation of national agencies for radioactive waste management - ARAO in Slovenia and APO in Croatia. The project performance, as well as the co-operation itself, are based on the fact that NPP Krsko, sited in Slovenia, is the joint venture facility of both countries, which are consequently obliged to find a proper solution for final disposal of operational and decommissioning radioactive waste generated by the plant. The main aspects of the project development in both countries, such as LILW repository site selection and characterisation, development of repository conceptual design, performance assessment/safety analysis procedures and public participation, are presented in the paper. Based on separate descriptions of the project development in Slovenia and Croatia respectively, the main aspects of co-operation between ARAO and APO are elaborated.(author)

Coherent State Projection Operator Representation of Symplectic Transformations as a Loyal Representation of Symplectic Group

Science.gov (United States)

Fan, Hong-Yi; Chen, Jun-Hua

2002-08-01

We find that the coherent state projection operator representation of symplectic transformation constitutes a loyal group representation of symplectic group. The result of successively applying squeezing operators on number state can be easily derived. The project supported by National Natural Science Foundation of China under Grant No. 10575057 and the President Foundation of the Chinese Academy of Sciences

OR.NET: a service-oriented architecture for safe and dynamic medical device interoperability.

Science.gov (United States)

Kasparick, Martin; Schmitz, Malte; Andersen, Björn; Rockstroh, Max; Franke, Stefan; Schlichting, Stefan; Golatowski, Frank; Timmermann, Dirk

2018-02-23

Modern surgical departments are characterized by a high degree of automation supporting complex procedures. It recently became apparent that integrated operating rooms can improve the quality of care, simplify clinical workflows, and mitigate equipment-related incidents and human errors. Particularly using computer assistance based on data from integrated surgical devices is a promising opportunity. However, the lack of manufacturer-independent interoperability often prevents the deployment of collaborative assistive systems. The German flagship project OR.NET has therefore developed, implemented, validated, and standardized concepts for open medical device interoperability. This paper describes the universal OR.NET interoperability concept enabling a safe and dynamic manufacturer-independent interconnection of point-of-care (PoC) medical devices in the operating room and the whole clinic. It is based on a protocol specifically addressing the requirements of device-to-device communication, yet also provides solutions for connecting the clinical information technology (IT) infrastructure. We present the concept of a service-oriented medical device architecture (SOMDA) as well as an introduction to the technical specification implementing the SOMDA paradigm, currently being standardized within the IEEE 11073 service-oriented device connectivity (SDC) series. In addition, the Session concept is introduced as a key enabler for safe device interconnection in highly dynamic ensembles of networked medical devices; and finally, some security aspects of a SOMDA are discussed.

The safe use of radiation sources

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-12-01

As a means of promoting safety in the use of radiation sources, as well as encouraging consistency in regulatory control, the IAEA has from time to time organized training courses with the co-operation of Member State governments and organizations, to inform individuals from developing countries with appropriate responsibilities on the provisions for the safe use and regulation of radiation sources. Three such courses on the safe use of radiation sources have been held in both the USA, with the co-operation of the United States Government, and in Dublin, Ireland, with the co-operation of the Irish Government. The Training Course on the Safe Use and Regulation of Radiation Sources has been successfully given to over 77 participants from over 30 countries during the last years. The course is aimed at providing a basis of radiation protection knowledge in all aspects of the uses of radiation and of radiation sources that are used today. It is the intention of this course to provide a systematic enhancement of radioisotope safety in countries with developing radiological programmes through a core group of national authorities. The IAEA's training programmes provide an excellent opportunity for direct contact with lecturers that have extensive experience in resolving issues faced by developing countries and in providing guidance documents useful in addressing their problems. This document uses this collective experience and provides valuable technical information regarding the safety aspects of the uses not only of sealed and unsealed sources of radiation, but also for those machines that produce ionizing radiation. The first of these training courses, 'Safety and Regulation of Unsealed Sources' was held in Dublin, Ireland, June through July 1989 with the co-operation of the Nuclear Energy Board and Trinity College. This was an interregional training course, the participants came from all over the world. The second and third interregional courses, 'Safety and Regulation

The safe use of radiation sources

International Nuclear Information System (INIS)

1995-01-01

As a means of promoting safety in the use of radiation sources, as well as encouraging consistency in regulatory control, the IAEA has from time to time organized training courses with the co-operation of Member State governments and organizations, to inform individuals from developing countries with appropriate responsibilities on the provisions for the safe use and regulation of radiation sources. Three such courses on the safe use of radiation sources have been held in both the USA, with the co-operation of the United States Government, and in Dublin, Ireland, with the co-operation of the Irish Government. The Training Course on the Safe Use and Regulation of Radiation Sources has been successfully given to over 77 participants from over 30 countries during the last years. The course is aimed at providing a basis of radiation protection knowledge in all aspects of the uses of radiation and of radiation sources that are used today. It is the intention of this course to provide a systematic enhancement of radioisotope safety in countries with developing radiological programmes through a core group of national authorities. The IAEA's training programmes provide an excellent opportunity for direct contact with lecturers that have extensive experience in resolving issues faced by developing countries and in providing guidance documents useful in addressing their problems. This document uses this collective experience and provides valuable technical information regarding the safety aspects of the uses not only of sealed and unsealed sources of radiation, but also for those machines that produce ionizing radiation. The first of these training courses, 'Safety and Regulation of Unsealed Sources' was held in Dublin, Ireland, June through July 1989 with the co-operation of the Nuclear Energy Board and Trinity College. This was an interregional training course, the participants came from all over the world. The second and third interregional courses, 'Safety and Regulation

Budgeting for International Projects: In-Country Business Operations and Long-Term Residential Assignments.

Science.gov (United States)

Richey, John B.

1994-01-01

A discussion of international sponsored research program administration looks at budgeting, costs, and procedures for both projects with in-country business operations in developing nations and projects with long-term residential assignments. It is intended for university administrators providing new services to faculty working on international…

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

Safe operation and maintenance of research reactor

International Nuclear Information System (INIS)

Munsorn, S.

1999-01-01

The first Thai Research Reactor (TRR-1) was established in 1961 at the Office of Atomic Energy for Peace (OAEP), Bangkok. The reactor was light water moderated and cooled, using HEU plate-type with U 3 O 8 - Al fuel meat and swimming pool type. The reactor went first critical on October 27, 1962 and had been licensed to operate at 1 MW (thermal). On June 30, 1975 the reactor was shutdown for modification and the core and control system was disassemble and replaced by that of TRIGA Mark III type while the pool cooling system, irradiation facilities and other were kept. Thus the name TRR-1/M1' has been designed due to this modification the fuel has been changed from HEU plate type to Uranium Zirconium Hydride (UZrH) Low Enrichment Uranium (LEU) which include 4 Fuel Follower Control Rods and 1 Air Follower Control Rod. The TRR-1/M1 went critical on November 7, 1977 and the purpose of the operation are training, isotope production and research. Nowadays the TRR-1/M1 has been operated with core loading No.12 which released power of 1,056 MWD. (as of October 1998). The TRR-1/M1 has been operated at the power of 1.2 MW, three days a week with 34 hours per week, Shut-down on Monday for weekly maintenance and Tuesday for special experiment. The everage energy released is about 40.8 MW-hour per week. Every year, the TRR-1/M1 is shut-down about 2 months between February to March for yearly maintenance. (author)

Safe operation and maintenance of research reactor

Energy Technology Data Exchange (ETDEWEB)

Munsorn, S. [Reactor Operation Division, Office of Atomic Energy for Peace, Chatuchak, Bangkok (Thailand)

1999-10-01

The first Thai Research Reactor (TRR-1) was established in 1961 at the Office of Atomic Energy for Peace (OAEP), Bangkok. The reactor was light water moderated and cooled, using HEU plate-type with U{sub 3}O{sub 8}- Al fuel meat and swimming pool type. The reactor went first critical on October 27, 1962 and had been licensed to operate at 1 MW (thermal). On June 30, 1975 the reactor was shutdown for modification and the core and control system was disassemble and replaced by that of TRIGA Mark III type while the pool cooling system, irradiation facilities and other were kept. Thus the name TRR-1/M1' has been designed due to this modification the fuel has been changed from HEU plate type to Uranium Zirconium Hydride (UZrH) Low Enrichment Uranium (LEU) which include 4 Fuel Follower Control Rods and 1 Air Follower Control Rod. The TRR-1/M1 went critical on November 7, 1977 and the purpose of the operation are training, isotope production and research. Nowadays the TRR-1/M1 has been operated with core loading No.12 which released power of 1,056 MWD. (as of October 1998). The TRR-1/M1 has been operated at the power of 1.2 MW, three days a week with 34 hours per week, Shut-down on Monday for weekly maintenance and Tuesday for special experiment. The everage energy released is about 40.8 MW-hour per week. Every year, the TRR-1/M1 is shut-down about 2 months between February to March for yearly maintenance. (author)

Canadian East Coast offshore petroleum industry safe lifting practices respecting offshore pedestal cranes, offshore containers, loose gear, other lifting devices, and operational best practices : standard practices

Energy Technology Data Exchange (ETDEWEB)

NONE

2007-11-15

This document was developed by a working group with representatives from the petroleum industry, the Offshore Petroleum Boards and Certifying Authorities. It outlines industry best practices for operators responsible for the management, planning and execution of offshore lifting operations. Its purpose is to assist in the interpretation of applicable legislation and standards. Considered within the practice are safe design requirements, manufacture, certification, testing, maintenance and inspection requirements for pedestal cranes, offshore containers, loose gear and lifting devices. Operational best practices for lifting operations are also included along with a section that identifies additional requirements for personnel lifting operations, including personnel transfers by crane and man-riding operations. 82 refs., 2 tabs., 4 figs., 3 appendices.

Natural gas distribution operation and maintenance dissemination project Kaunas City, Lithuania. Final report

Energy Technology Data Exchange (ETDEWEB)

NONE

2000-03-01

The main objective of this project has been to disseminate the results and experiences achieved during the former projects in Kaunas to other Lithuanian gas companies and the gas sector in general. Also new subjects selected in co-operation with Kaunas Gas Company, the Lithuanian Energy Institute and the Lithuanian Gas Training Centre, where improvements were required, have been implemented. The components of the project were the following: (1) A training course in cathodic protection. One course concerning measuring and registration and one course concerning design and implementation. (2) A pilot project to develop methods for measuring cathodic protection on coherent steel pipe network. (3) Analysis of gas losses related to types of gas meters and calibration of meters. (4) A training course and technology transfer concerning relations between gas companies and consumers. (5) Dissemination of the experience of 1998 from the preparation of an operation and maintenance manual for Kaunas Gas Company. Dissemination of the ideas to other Lithuanian gas companies. (EHS)

Experiences in managing the Prometheus Project

Science.gov (United States)

Lehman, David H.; Clark, Karla B.; Cook, Beverly A.; Gavit, Sarah A.; Kayali, Sammy A.; McKinney, John C.; Milkovich, David C.; Reh, Kim R.; Taylor, Randall L.; Casani, John R.

2006-01-01

Congress authorized NASA?s Prometheus Project in February 2003, with the first Prometheus mission slated to explore the icy moons of Jupiter. The Project had two major objectives: (1) to develop a nuclear reactor that would provide unprecedented levels of power and show that it could be processed safely and operated reliably in space for long-duration, deep-space exploration and (2) to explore the three icy moons of Jupiter - Callisto, Ganymede, and Europa - and return science data that would meet the scientific goals as set forth in the Decadal Survey Report of the National Academy of Sciences. Early in Project planning, it was determined that the development of the Prometheus nuclear powered Spaceship would be complex and require the intellectual knowledge residing at numerous organizations across the country. In addition, because of the complex nature of the Project and the multiple partners, approaches beyond those successfully used to manage a typical JPL project would be needed. This paper1 will describe the key experiences in managing Prometheus that should prove useful for future projects of similar scope and magnitude

A team leadership approach to managing the transition from construction to operations for an environmental project

International Nuclear Information System (INIS)

Kelly, J.W.

1994-06-01

This presentation describes a team approach, at the totalproject level that focused team members with common objectives, for the transition to start-up and operation of the project. The Integrated Management Team (IMT) approach has been successful for this US Department of Energy (DOE) environmental restoration project at the Hanford Site in Richland, Washington. The $53.8-million project will collect, treat, and dispose of low-level mixed waste water discharges from the Hanford Site. Construction is scheduled for completion in September 1994 and facility start-up in June 1995. The project challenge is for leadership that is committed to the transition from construction to operation of the environmental restoration project

Protection and control of modeled local power systems and simulation of safe power feeding systems; Proteccion y control local de sistemas electricos de potencia modelado y simulacion de sistemas de alimentacion segura

Energy Technology Data Exchange (ETDEWEB)

Rothschild, Marcelo A. [SADE SKANSKA S.A., Buenos Aires (Argentina)]. E-mail: mrothsch@sade.com.ar

2001-07-01

This document presents a guideline for modeling and simulation of safe feeding systems. Examples of systems currently in operation are presented for which, based on attended project by simulation, it has been possible to introduce substantial improvements in relation to the reliability and security of those installations.

Project Management Approach to Transition of the Miamisburg Closure Project From Environmental Cleanup to Post-Closure Operations

International Nuclear Information System (INIS)

Carpenter, C.P.; Marks, M.L.; Smiley, S.L.; Gallaher, D.M.; Williams, K.D.

2006-01-01

The U.S. Department of Energy (DOE) used a project management approach to transition the Miamisburg Closure Project from cleanup by the Office of Environmental Management (EM) to post-closure operations by the Office of Legacy Management (LM). Two primary DOE orders were used to guide the site transition: DOE Order 430.1B, Real Property Asset Management, for assessment and disposition of real property assets and DOE Order 413.3, Program and Project Management for Acquisition of Capital Assets, for project closeout of environmental cleanup activities and project transition of post-closure activities. To effectively manage these multiple policy requirements, DOE chose to manage the Miamisburg Closure Project as a project under a cross-member transitional team using representatives from four principal organizations: DOE-LM, the LM contractor S.M. Stoller Corporation, DOE-EM, and the EM contractor CH2M Hill Mound Inc. The mission of LM is to manage the Department's post-transition responsibilities and long-term care of legacy liabilities and to ensure the future protection of human health and the environment for cleanup sites after the EM has completed its cleanup activities. (authors)

Gentilly-2 refurbishment pre-project

International Nuclear Information System (INIS)

Pageau, Rene; Doyon, Martial; Rheaume, M.R.

2002-01-01

The conceptual design life of Gentilly-2 station is 30 years and the station was put in service in 1982. Hydro-Quebec has initiated a project to assess the refurbishment of the station in the horizon 2008-2010 and for an expected life extension of 25 years. The reactor has been successfully operated since its first full-power operation in early 80's, nearly 20 years ago. Although the overall performance of Gentilly-2 continues to be very good, it is reasonable to expect that age-related degradation of key plant components will have an increasing impact on operations as the plant continues to age. The replacement of the reactor channels component is required around 2008-2009. The replacement of the reactor tubes is a major activity and it is necessary to assess the capability of the station to operate safely and reliably for a an extended period of 25 years bringing the design life of the station to over 50 years. The challenges associated with extended life operation until at least 2030-33 horizon are to maintain the margin of safety for plant operations by ensuring reliability of safety-related systems, to reduce plant unavailability due to age-related component failures, and to minimize the costs for repairs and replacement of aging components. As shown on the next figure, the overall project is expected to spread over an 8 years period starting in 2001. A project feasibility study (phase-1) of four (4) years has been planned to assess the plant condition and to make an overall safety review. This project phase will confirm the economical viability of extended operation. A period of thirty-nine (39) months would be necessary for the procurement and manufacturing of all the reactor components, and for the engineering work related to safety and economic improvements. Reactor channel replacement is planned for an outage not exceeding 18 months. (author)

Spanish collaboration in the OECD Halden Reactor Project research on Gadolinia Fuel

International Nuclear Information System (INIS)

Horvath, M. I.; Jenssen, H. K.; Munoz-Reja, C.; Tverberg, T.

2011-01-01

Safe and reliable operation of nuclear power plants benefit from research and development advances and related technical solutions. One research platform is the OECD Halden Reactor Project (HRP), HRP is a joint undertaking of national organisations in 18 countries sponsoring a jointly financed programme under the auspices of the OECD-Nuclear Energy Agency (NEA). As a member state, Spain is participating HRP research programs with ENUSA as partner in the fuel research programs. Various experiments are developed and performed also by providing materials, ENUSA collaborates with HRP on various experiments investigating the fuel behaviour, especially on Gd-bearing fuel. 20 years of successful collaboration between HRP and ENUSA is continuing with promising and results to ensure and enhance the safe operation of the Spanish and all other NPPs in the world. (Author) 12 refs.

Cernavoda - Unit 2. A strategic project for Romania

International Nuclear Information System (INIS)

Saroudis, J.I.; Chirica, T.; Villabruna, G.

1999-01-01

The paper presents some key aspects of the Romanian nuclear program, focusing on Cernavoda NPP Unit No. 2 and the partnership with Atomic Energy of Canada Ltd. (AECL) and ANSALDO Italy for completion of this project. A brief historical presentation of the Romanian nuclear program is included. The success of Cernavoda NPP Unit 1 represents an important element in finalizing Unit 2 in an advanced state of equipment installation and more than 40 % complete. Also, the national infrastructure, including the legal framework and new Electricity Law represents a positive element for Project completion. The Romanian Nuclear Regulatory Body represents the guarantee for the safe operation of CANDU reactors in Romania.(author)

Windscale advanced gas-cooled reactor (WAGR) decommissioning project overview

International Nuclear Information System (INIS)

Pattinson, A.

2003-01-01

The current BNFL reactor decommissioning projects are presented. The projects concern power reactor sites at Berkely, Trawsfynydd, Hunterstone, Bradwell, Hinkley Point; UKAEA Windscale Pile 1; Research reactors within UK Scottish Universities at East Kilbride and ICI (both complete); WAGR. The BNFL environmental role include contract management; effective dismantling strategy development; implementation and operation; sentencing, encapsulation and transportation of waste. In addition for the own sites it includes strategy development; baseline decommissioning planning; site management and regulator interface. The project objectives for the Windscale Advanced Gas-Cooled Reactor (WAGR) are 1) Safe and efficient decommissioning; 2) Building of good relationships with customer; 3) Completion of reactor decommissioning in 2005. The completed WAGR decommissioning campaigns are: Operational Waste; Hot Box; Loop Tubes; Neutron Shield; Graphite Core and Restrain System; Thermal Shield. The current campaign is Lower Structures and the remaining are: Pressure vessel and Insulation; Thermal Columns and Outer Vault Membrane. An overview of each campaign is presented

Unmanned Aircraft Systems (UAS) Integration in the National Airspace System (NAS) Project KDP-C Review

Science.gov (United States)

Grindle, Laurie; Sakahara, Robert; Hackenberg, Davis; Johnson, William

2017-01-01

safety and operational challenges of national airspace access by unmanned aircraft systems, or UAS. In the process, the project will work with other key stakeholders to define necessary deliverables and products to help enable such access. Within the project, NASA is focusing on five sub-projects. These five focus areas include assurance of safe separation of unmanned aircraft from manned aircraft when flying in the national airspace; safety-critical command and control systems and radio frequencies to enable safe operation of UAS; human factors issues for ground control stations; airworthiness certification standards for UAS avionics and integrated tests and evaluation designed to determine the viability of emerging UAS technology. Five Focus Areas of the UAS Integration in the NAS Project Separation Assurance Provide an assessment of how planned Next Generation Air Transportation System (NextGen) separation assurance systems, with different functional allocations, perform for UAS in mixed operations with manned aircraft Assess the applicability to UAS and the performance of NASA NextGen separation assurance systems in flight tests with realistic latencies and uncertain trajectories Assess functional allocations ranging from today's ground-based, controller-provided aircraft separation to fully autonomous airborne self-separation Communications Develop data and rationale to obtain appropriate frequency spectrum allocations to enable safe and efficient operation of UAS in the NAS Develop and validate candidate secure safety-critical command and control system/subsystem test equipment for UAS that complies with UAS international/national frequency regulations, standards and recommended practices and minimum operational and aviation system performance standards for UAS Perform analysis to support recommendations for integration of safety-critical command and control systems and air traffic control communications to ensure safe and efficient operation of UAS in the NAS

Hyper-Spectral Networking Concept of Operations and Future Air Traffic Management Simulations

Science.gov (United States)

Davis, Paul; Boisvert, Benjamin

2017-01-01

The NASA sponsored Hyper-Spectral Communications and Networking for Air Traffic Management (ATM) (HSCNA) project is conducting research to improve the operational efficiency of the future National Airspace System (NAS) through diverse and secure multi-band, multi-mode, and millimeter-wave (mmWave) wireless links. Worldwide growth of air transportation and the coming of unmanned aircraft systems (UAS) will increase air traffic density and complexity. Safe coordination of aircraft will require more capable technologies for communications, navigation, and surveillance (CNS). The HSCNA project will provide a foundation for technology and operational concepts to accommodate a significantly greater number of networked aircraft. This paper describes two of the HSCNA projects technical challenges. The first technical challenge is to develop a multi-band networking concept of operations (ConOps) for use in multiple phases of flight and all communication link types. This ConOps will integrate the advanced technologies explored by the HSCNA project and future operational concepts into a harmonized vision of future NAS communications and networking. The second technical challenge discussed is to conduct simulations of future ATM operations using multi-bandmulti-mode networking and technologies. Large-scale simulations will assess the impact, compared to todays system, of the new and integrated networks and technologies under future air traffic demand.

Multiscale Support Vector Learning With Projection Operator Wavelet Kernel for Nonlinear Dynamical System Identification.

Science.gov (United States)

Lu, Zhao; Sun, Jing; Butts, Kenneth

2016-02-03

A giant leap has been made in the past couple of decades with the introduction of kernel-based learning as a mainstay for designing effective nonlinear computational learning algorithms. In view of the geometric interpretation of conditional expectation and the ubiquity of multiscale characteristics in highly complex nonlinear dynamic systems [1]-[3], this paper presents a new orthogonal projection operator wavelet kernel, aiming at developing an efficient computational learning approach for nonlinear dynamical system identification. In the framework of multiresolution analysis, the proposed projection operator wavelet kernel can fulfill the multiscale, multidimensional learning to estimate complex dependencies. The special advantage of the projection operator wavelet kernel developed in this paper lies in the fact that it has a closed-form expression, which greatly facilitates its application in kernel learning. To the best of our knowledge, it is the first closed-form orthogonal projection wavelet kernel reported in the literature. It provides a link between grid-based wavelets and mesh-free kernel-based methods. Simulation studies for identifying the parallel models of two benchmark nonlinear dynamical systems confirm its superiority in model accuracy and sparsity.

How safe are nuclear power plants

International Nuclear Information System (INIS)

Danzmann, H.J.

1976-01-01

The question 'how safe are nuclear power plants' can be answered differently - it depends on how the term 'safety' is understood. If the 'safety of supply' is left out as a possibility of interpretation, then the alternative views remain: Operational safety in the sense of reliability and safety of personnel and population. (orig.) [de

Safe laparoscopic colorectal surgery performed by trainees

DEFF Research Database (Denmark)

Langhoff, Peter Koch; Schultz, Martin; Harvald, Thomas

2013-01-01

Laparoscopic surgery for colorectal cancer is safe, but there have been hesitations to implement the technique in all departments. One of the reasons for this may be suboptimal learning possibilities since supervised trainees have not been allowed to do the operations to an adequate extent...

Safe injection procedures, injection practices, and needlestick ...

African Journals Online (AJOL)

Nermine Mohamed Tawfik Foda

2017-01-10

Jan 10, 2017 ... Background: Of the estimated 384,000 needle-stick injuries occurring in hospitals each year, 23% occur in surgical settings. This study was conducted to assess safe injection procedures, injection practices, and circumstances contributing to needlestick and sharps injures (NSSIs) in operating rooms.

The inherently-safe power reactor DYONISOS (Dynamic Nuclear Inherently-Safe Reactor Operating with Spheres)

International Nuclear Information System (INIS)

Taube, M.; Lanfranchi, M.; Weissenfluh, Th. von; Ligou, J.; Yadigaroglu, G.; Taube, P.

1986-01-01

A philosophy of inherent safety is formulated and an inherently-safe thermal power reactor is presented. Solid fuel in the form of spheres a few centimetres in diameter is suspended under the hydro-dynamic pressure of molten lead coolant in vertical channels within the graphite moderator. Loss of main pump pressure, or a loss-of-coolant accident (LOCA), results in immediate removal of the fuel to rigid sieves below the core, with consequent subcriticality. Residual and decay heat are carried away by thermal conduction through the coolant or, in the case of a LOCA, by a combination of radiation and natural convection of cover gas or incoming air from the fuel to the reactor vessel and convection of air between the vessel and steel containment wall. All decay heat removal systems are passive, though actively initiated external spray cooling of the containment can be used to reduce wall temperature. This, however, is only necessary in the case of a LOCA and after a period of 24 h. (author)

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.

RISK MANAGEMENT IN THE OPERATING ACTIVITIES OF AN ENTERPRISE AND IN PUBLIC-PRIVATE PARTNERSHIP PROJECTS

Directory of Open Access Journals (Sweden)

Lech Jędrzejewski

2017-03-01

Full Text Available The paper is devoted to issues related to building a risk management system for businesses in the areas of operations and implementation of infrastructure projects. The article defines the concept of risk in business processes and identifies risks occurring in infrastructure projects. In the text, the principles have been presented for protection against the effects of political, contracting, environmental, ecological, product, process, operational and personnel risk.

Joint-operation in water resources project in Indonesia: Integrated or non-integrated

Science.gov (United States)

Ophiyandri, Taufika; Istijono, Bambang; Hidayat, Benny

2017-11-01

The construction of large water resources infrastructure project often involved a joint-operation (JO) project between two or more construction companies. The form of JO can be grouped into two categories - an integrated type and a non-integrated type. This paper investigates the reason of forming a JO project made by companies. The specific advantages and problems of JO project is also analysed in this paper. In order to achieve the objectives, three water resources infrastructure projects were selected as case studies. Data was gathered by conducting 11 semi-structured interviews to project owners, contractor managers, and project staffs. Data was analysed by means of content analysis. It was found that the most fundamental factor to form a JO is to win a competition or tender. An integrated model is in favour because it can reduce overhead costs and has a simple management system, while a non-integrated model is selected because it can avoid a sleeping partner and make contractor more responsible for their own job.

Lake Charles CCS Project

Energy Technology Data Exchange (ETDEWEB)

Leib, Thomas [Leucadia Energy, LLC, Salt Lake City, UT (United States); Cole, Dan [Denbury Onshore, LLC, Plano, TX (United States)

2015-06-30

In late September 2014 development of the Lake Charles Clean Energy (LCCE) Plant was abandoned resulting in termination of Lake Charles Carbon Capture and Sequestration (CCS) Project which was a subset the LCCE Plant. As a result, the project was only funded through Phase 2A (Design) and did not enter Phase 2B (Construction) or Phase 2C (Operations). This report was prepared relying on information prepared and provided by engineering companies which were engaged by Leucadia Energy, LLC to prepare or review Front End Engineering and Design (FEED) for the Lake Charles Clean Energy Project, which includes the Carbon Capture and Sequestration (CCS) Project in Lake Charles, Louisiana. The Lake Charles Carbon Capture and Sequestration (CCS) Project was to be a large-scale industrial CCS project intended to demonstrate advanced technologies that capture and sequester carbon dioxide (CO₂) emissions from industrial sources into underground formations. The Scope of work was divided into two discrete sections; 1) Capture and Compression prepared by the Recipient Leucadia Energy, LLC, and 2) Transport and Sequestration prepared by sub-Recipient Denbury Onshore, LLC. Capture and Compression-The Lake Charles CCS Project Final Technical Report describes the systems and equipment that would be necessary to capture CO₂ generated in a large industrial gasification process and sequester the CO₂ into underground formations. The purpose of each system is defined along with a description of its equipment and operation. Criteria for selection of major equipment are provided and ancillary utilities necessary for safe and reliable operation in compliance with environmental regulations are described. Construction considerations are described including a general arrangement of the CCS process units within the overall gasification project. A cost estimate is provided, delineated by system area with cost breakdown showing equipment, piping and materials

Projection operator approach to the self-energy

International Nuclear Information System (INIS)

Capuzzi, F.; Mahaux, C.

1996-01-01

Feshbach close-quote s projection operator formalism is extended to the description of the self-energy. This necessitates the introduction of open-quote open-quote extended close-quote close-quote projection operators. They act within an open-quote open-quote extended close-quote close-quote Hilbert space in which the number of nucleons is not fixed. The compact formula derived for the self-energy is formally similar to Feshbach close-quote s original expression of the open-quote open-quote generalized close-quote close-quote optical-model potential. The theory is formulated in the nuclear case, but it also applies to atomic systems. It covers both the open-quote open-quote retarded close-quote close-quote and the open-quote open-quote time-ordered close-quote close-quote Green close-quote s functions, and the open-quote open-quote proper close-quote close-quote and open-quote open-quote improper close-quote close-quote self-energies. It is first worked out in a stationary formalism, in order to better exhibit its analogy with Feshbach close-quote s original theory of the generalized optical-model potential. The main results are then also derived in a time-dependent framework. It is shown that, in finite systems, Dyson close-quote s equation does not uniquely determine the self-energy, in contrast to common assumption. However, the difference between the various possibilities has little practical consequence. We exhibit the relationship between the present approach and a recent open-quote open-quote configuration interaction formulation of the Dyson equation.close-quote close-quote Contact is also established with the open-quote open-quote linked-cluster close-quote close-quote perturbation expansion of the self-energy in powers of the strength of the nucleon endash nucleon interaction. Copyright copyright 1996 Academic Press, Inc

Towards an ethics safe harbor for global biomedical research

Science.gov (United States)

Dove, Edward S.; Knoppers, Bartha M.; Zawati, Ma'n H.

2014-01-01

Although increasingly global, data-driven genomics and other ‘omics’-focused research hold great promise for health discoveries, current research ethics review systems around the world challenge potential improvements in human health from such research. To overcome this challenge, we propose a ‘Safe Harbor Framework for International Ethics Equivalency’ that facilitates the harmonization of ethics review of specific types of data-driven international research projects while respecting globally transposable research ethics norms and principles. The Safe Harbor would consist in part of an agency supporting an International Federation for Ethics Review (IFER), formed by a voluntary compact among countries, granting agencies, philanthropies, institutions, and healthcare, patient advocacy, and research organizations. IFER would be both a central ethics review body, and also a forum for review and follow-up of policies concerning ethics norms for international research projects. It would be built on five principle elements: (1) registration, (2) compliance review, (3) recognition, (4) monitoring and enforcement, and (5) public participation. The Safe Harbor would create many benefits for researchers, countries, and the general public, and may eventually have application beyond (gen)omics to other areas of biomedical research that increasingly engage in secondary use of data and present only negligible risks. PMID:27774154

Shippingport Station Decommissioning Project Start of Physical Decommissioning

International Nuclear Information System (INIS)

Crimi, F. P.

1987-01-01

The Shippingport Atomic Power Station consists of the nuclear steam supply system and associated radioactive waste processing systems, which are owned by the United States Department of Energy, and the turbine-generator and balance of plant, which is owned by the Duquesne Light Company. The station is located at Shippingport, Pennsylvania on seven acres of land leased by DOE from Duquesne Light Company. The Shippingport Station Decommissioning Project is being performed under contract to the DOE by the General Electric Company and its integrated subcontractor, Morrison-Knudsen Company. as the Decommissioning Operations Contractor. This paper describes the current status of the physical decommissioning work, which started September 1985. The preparations required to start a major decommissioning work effort in a safe and cost effective manner are discussed including the development and implementation of a cost/schedule control system. The detailed plan required to ensure that people, property, and procedures are ready in sufficient time to support the start of physical decommissioning is also discussed. The total estimated cost of the Shippingport Station Decommissioning Project should be $98.3 M, with the Project scheduled for completion in April 1990. As the decommissioning of the first commercial-scale nuclear power plant, the Shippingport Project is expected to set the standard for safe, cost-effective demolition of nuclear plants

Managing your engineering consultants: Steps for simultaneously improving operations, project implementation, and your bottom line

International Nuclear Information System (INIS)

Kirchen, E.R.; Perilloux, B.L.

1997-01-01

The domestic oil and gas industry has responded to depleting reserves and increasing operating costs by downsizing the overhead required to maintain production and processing facilities. For many companies this downsizing has resulted in a reduced in-house engineering staff and a greater reliance on consulting engineering services. To get the most benefit from consulting engineering companies, the partnership between consultants and the oil and gas company needs to be carefully considered. Unfortunately, these partnerships are often developed at the home office with visionary goals in mind, only to be implemented reluctantly on a local level. A better strategy is to implement partnering tools on the local level and allow these partnerships to develop naturally, and at times, uniquely, at each location. The following such tools detailed in this paper are: manpower leveraging -- using field-trained consulting engineers to address project design/implementation and field/construction support so that the operating company's engineers may focus on management and detailed development of high-return projects; enhanced project scope and design review -- developing and reviewing project scope(s) and preliminary engineering designs to minimize engineering/construction costs as well as optimize the operability and constructability of the project; and consulting rate standardization -- understanding and structuring the consultant's rates so that neither side is exploited and so that the project is staffed in the interest of project execution and not maximum profits for the consultant

EOS: A project to investigate the design and construction of real-time distributed Embedded Operating Systems

Science.gov (United States)

Campbell, R. H.; Essick, Ray B.; Johnston, Gary; Kenny, Kevin; Russo, Vince

1987-01-01

Project EOS is studying the problems of building adaptable real-time embedded operating systems for the scientific missions of NASA. Choices (A Class Hierarchical Open Interface for Custom Embedded Systems) is an operating system designed and built by Project EOS to address the following specific issues: the software architecture for adaptable embedded parallel operating systems, the achievement of high-performance and real-time operation, the simplification of interprocess communications, the isolation of operating system mechanisms from one another, and the separation of mechanisms from policy decisions. Choices is written in C++ and runs on a ten processor Encore Multimax. The system is intended for use in constructing specialized computer applications and research on advanced operating system features including fault tolerance and parallelism.

Using accounting information systems by operations managers in a project company

NARCIS (Netherlands)

Wouters, Marc; van der Veeken, Henk J.M.

2002-01-01

This paper describes the results of a case study that investigated the use of accounting information by operations managers in a road building company. There was considerable preplanning before the execution of project activities, but task uncertainty during execution created the need to take

76 FR 12719 - Safe Schools/Healthy Students Program; Office of Safe and Drug-Free Schools; Safe Schools/Healthy...

Science.gov (United States)

2011-03-08

... DEPARTMENT OF EDUCATION Safe Schools/Healthy Students Program; Office of Safe and Drug- Free Schools; Safe Schools/Healthy Students Program; Catalog of Federal Domestic Assistance (CFDA) Numbers: 84... priorities, requirements, and definitions under the Safe Schools/Healthy Students (SS/HS) program. Since...

Implications of inherent safe nuclear power system

International Nuclear Information System (INIS)

Song, Yo-Taik

1987-01-01

The safety of present day nuclear power reactors and research reactors depends on a combination of design features of passive and active systems, and the alert judgement of their operators. A few inherently safe designs of nuclear reactors for power plants are currently under development. In these designs, the passive systems are emphasized, and the active systems are minimized. Also efforts are made to eliminate the potential for human failures that initiate the series of accidents. If a major system fails in these designs, the core is flooded automatically with coolants that flow by gravity, not by mechanical pumps or electromagnetic actuators. Depending on the choice of the coolants--water, liquid metal and helium gas--there are three principal types of inherently safe reactors. In this paper, these inherently safe reactor designs are reviewed and their implications are discussed. Further, future perspectives of their acceptance by nuclear industries are discussed. (author)

River Protection Project Integrated safety management system phase II verification review plan - 7/29/99

International Nuclear Information System (INIS)

SHOOP, D.S.

1999-01-01

The purpose of this review is to verify the implementation status of the Integrated Safety Management System (ISMS) for the River Protection Project (RPP) facilities managed by Fluor Daniel Hanford, Inc. (FDH) and operated by Lockheed Martin Hanford Company (LMHC). This review will also ascertain whether within RPP facilities and operations the work planning and execution processes are in place and functioning to effectively protect the health and safety of the workers, public, environment, and federal property over the RPP life cycle. The RPP ISMS should support the Hanford Strategic Plan (DOERL-96-92) to safely clean up and manage the site's legacy waste and deploy science and technology while incorporating the ISMS central theme to ''Do work safely'' and protect human health and the environment

IAEA's technical co-operation programme and its role in assisting member states in the safe utilisation of nuclear power

International Nuclear Information System (INIS)

Reed, J.

2000-01-01

In this contribution the author deals with the technical co-operation projects of the IAEA. The Agency's technical co-operation programme is a most welcome mechanism for the transfer of nuclear technology, and to developing countries it is certainly the most attractive side of the Agency, since it is through this programme that the IAEA can contribute to the solution of their problems through the provision of know-how, technology and training. (authors)

Inherently safe in situ uranium recovery

Science.gov (United States)

Krumhansl, James L; Brady, Patrick V

2014-04-29

An in situ recovery of uranium operation involves circulating reactive fluids through an underground uranium deposit. These fluids contain chemicals that dissolve the uranium ore. Uranium is recovered from the fluids after they are pumped back to the surface. Chemicals used to accomplish this include complexing agents that are organic, readily degradable, and/or have a predictable lifetime in an aquifer. Efficiency is increased through development of organic agents targeted to complexing tetravalent uranium rather than hexavalent uranium. The operation provides for in situ immobilization of some oxy-anion pollutants under oxidizing conditions as well as reducing conditions. The operation also artificially reestablishes reducing conditions on the aquifer after uranium recovery is completed. With the ability to have the impacted aquifer reliably remediated, the uranium recovery operation can be considered inherently safe.

Analysis of the F. Calogero Type Projection-Algebraic Scheme for Differential Operator Equations

International Nuclear Information System (INIS)

Lustyk, Miroslaw; Bogolubov, Nikolai N. Jr.; Blackmore, Denis; Prykarpatsky, Anatoliy K.

2010-12-01

The existence, convergence, realizability and stability of solutions of differential operator equations obtained via a novel projection-algebraic scheme are analyzed in detail. This analysis is based upon classical discrete approximation techniques coupled with a recent generalization of the Leray-Schauder fixed point theorem. An example is included to illustrate the efficacy of the projection scheme and analysis strategy. (author)

Artificial intelligence applications for operation and maintenance

International Nuclear Information System (INIS)

Itoh, M.; Tai, I.; Monta, K.; Sekimizu, K.

1987-01-01

A nuclear power plant as a typical man-machine system of the modern industry needs an efficient human window through which operators can observe every necessary detail of the plant for its safe and reliable operation. Much efforts have been devoted to the development of the computerized operator support systems (COSS). Recent development of artificial intelligence (AI) seems to offer new possibility to strengthen the performance of the COSS such as more powerful diagnosis and procedure synthesis and user friendly man-machine interfaces. From this point of view, a national project of Advanced Man-Machine System Development for Nuclear Power Plants has been carried out. Artificial intelligence application to nuclear power plant operation and maintenance is also selected as a major theme for the promotion of research and development on frontiers in the recently revised long term national program for development and utilization of nuclear energy in JAPAN

Managing radioactive waste safely. Engaging Scotland

International Nuclear Information System (INIS)

Elrick, D.; Boyes, L.; McCormick, J.

2002-01-01

Between January and May 2002 the Scottish Council Foundation undertook a research project to assess 1 the level of public awareness about and interest in engaging the public in decision-making on managing radioactive waste safely in Scotland. This paper presents the main findings from the research that involved 70 people from across Scotland, aged between 14 and over 65 years old, and a literature review of Scottish, UK and international experience in engaging the public

Power demand operation - environment and potential. Proposals for main project

International Nuclear Information System (INIS)

Wathne, M.

1995-01-01

This report discusses proposals for a main project on environmental and other problems arising when hydroelectric power stations supply energy at gigawatt levels. The project aims in particular to identify environmental problems where too little is known today for proper planning of this type of operation. The proposals emphasize the consequences which cannot be adequately analysed in terms of current techniques. These techniques presuppose steady state conditions. One proposal concerns market terms for power sales. Other proposals deal with hydrological data and uncertainty, capacity of watercourses, ice and temperature, aquatic eco-systems, erosion, supersaturation of water with air, flooding and dam breaks, impact on climate, inflow of fresh water in fjords and impact on algae. 33 refs., 4 tabs

CarbonSAFE Illinois - Macon County

Energy Technology Data Exchange (ETDEWEB)

Whittaker, Steve [University of Illinois; Illinois State Geological Survey

2017-08-03

CarbonSAFE Illinois is a a Feasibility study to develop an established geologic storage complex in Macon County, Illinois, for commercial-scale storage of industrially sourced CO2. Feasibility activities are focused on the Mt. Simon Storage Complex; a step-out well will be drilled near existing storage sites (i.e., the Midwest Geological Sequestration Consortium’s Illinois Basin – Decatur Project and the Illinois Industrial Carbon Capture and Storage Project) to further establish commercial viability of this complex and to evaluate EOR potential in a co-located oil-field trend. The Archer Daniels Midland facility (ethanol plant), City Water, Light, and Power in Springfield, Illinois (coal-fired power station), and other regional industries are potential sources of anthropogenic CO2 for storage at this complex. Site feasibility will be evaluated through drilling results, static and dynamic modeling, and quantitative risk assessment. Both studies will entail stakeholder engagement, consideration of infrastructure requirements, existing policy, and business models. Project data will help calibrate the National Risk Assessment Partnership (NRAP) Toolkit to better understand the risks of commercial-scale carbon storage.

TFTR tritium operations lessons learned

International Nuclear Information System (INIS)

Gentile, C.A.; Raftopoulos, S.; LaMarche, P.

1996-01-01

The Tokamak Fusion Test Reactor which is the progenitor for full D-T operating tokamaks has successfully processed > 81 grams of tritium in a safe and efficient fashion. Many of the fundamental operational techniques associated with the safe movement of tritium through the TFTR facility were developed over the course of many years of DOE tritium facilities (LANL, LLNL, SRS, Mound). In the mid 1980's The Tritium Systems Test Assembly (TSTA) at LANL began reporting operational techniques for the safe handling of tritium, and became a major conduit for the transfer of safe tritium handling technology from DOE weapons laboratories to non-weapon facilities. TFTR has built on many of the TSTA operational techniques and has had the opportunity of performing and enhancing these techniques at America's first operational D-T fusion reactor. This paper will discuss negative pressure employing 'elephant trunks' in the control and mitigation of tritium contamination at the TFTR facility, and the interaction between contaminated line operations and Δ pressure control. In addition the strategy employed in managing the movement of tritium through TFTR while maintaining an active tritium inventory of < 50,000 Ci will be discussed. 5 refs

An overview of ALARA considerations during Yankee Atomic`s Component Removal Project

Energy Technology Data Exchange (ETDEWEB)

Granados, B.; Babineau, G.; Colby, B.; Cox, B. [Yankee Nuclear Power Station, Rowe, MA (United States)

1995-03-01

In Februrary 1992, Yankee Atomic Electric Company (YAEC) permanently shutdown Yankee Nuclear Power Station in Rowe, Massachusetts, after thirty-two years of efficient operation. Yankee`s plan decommissioning is to defer dismantlement until a low level radioactive waste (LLRW) disposal facility is available. The plant will be maintained in a safe storage condition until a firm contract for the disposal of LLRW generated during decommissioning can be secured. Limited access to a LLRW disposal facility may occur during the safe storage period. Yankee intends to use these opportunities to remove components and structures. A Component Removal Project (CRP) was initiated in 1993 to take advantage of one of these opportunities. A Componenet Removal Project (CRP) was initiated in 1993 to take advantage of one of these opportunities. The CRP includes removal of four steam generators, the pressurizer, and segmentation of reactor vessel internals and preparation of LLRW for shipment and disposal at Chem-Nuclear`s Barnwell, South Carolina facility. The CRP is projected to be completed by June 1994 at an estimated total worker exposure of less than 160 person-rem.

Methods of projecting operations and maintenance costs for nuclear power plants

International Nuclear Information System (INIS)

1995-01-01

Operations and maintenance cost (OMC) had increased its relative importance to the total generation cost for future nuclear power stations, according to the latest update of the OECD Nuclear Energy Agency (NEA) study on Projected Costs of Generating Electricity (EGC studies). OMC is some 20 to 30% of total generation cost for future nuclear power stations in most NEA member countries. However, nuclear OMC that countries projected in the latest EGC study are spread over a wide range, from 5 to 16 US mills/kWh. In order to understand better the reasons for this wide diversity in nuclear OMC projections, the NEA set up an Expert Group. The focus of this study was on projected OMC that were reported in the past EGC studies, but the Group studied actual OMC experienced from existing units, because knowledge or experience concerning actual OMC certainly influences the choice of assumptions or calculation procedure for estimating OMC for future plants. Cost informations from 14 NEA countries have been analysed on the basis of a standardized framework of detailed components of OMC costs. The rationale for different OMC cost projections reported in previous NEA studies on generation cost is discussed and suggestions are made for future studies on both generation cost and OMC cost. Despite the methodological approach and the reduced extent of differences when excluding exceptional figures, it was not possible fully to clarify the origins and to understand the remaining differences in OMC figures. Several countries which have a long and a good experience of operating nuclear units did not provide sufficient detailed data or did not provide any quantitative data at all. (J.S.). 14 refs., 5 figs., 19 tabs., 4 annexes

SAFE-KBS, Substantiating the safety of systems containing knowledge-based components

International Nuclear Information System (INIS)

Mesa, E.; Jimenez, A.

1998-01-01

The overall objective of the Safe-KBS project is to develop generic development and certification methodologies that allow the introduction of knowledge-based components in safety-related applications. The expert system technology presents a set of features, such as the capability to provide the rationale for its conclusions, that may significantly contribute to the new operation support systems. Nevertheless, the use of this technology in safety-related applications is limited by the lack of recognised methodologies and standards that allow a formal demonstration of the quality and reliability of these systems, as required for obtaining the approval for their use at nuclear power plants. The development methodology is structured in three hierarchical levels: life cycle model, i.e., processes and activities constituting the life cycle, life cycle plans, i.e., tasks, and support packages, i.e., set of techniques and methods to perform certain activities or tasks. The certification methodology consists of a set of certification requirements and a certification scheme for demonstrating the compliance with these requirements. This project was developed within the European framework ESPRIT, with the collaboration of Sextant, Cise, Qualience, Ilog, Computes, DNV and Uninfo. (Author)

Connection between perturbation theory, projection-operator techniques, and statistical linearization for nonlinear systems

International Nuclear Information System (INIS)

Budgor, A.B.; West, B.J.

1978-01-01

We employ the equivalence between Zwanzig's projection-operator formalism and perturbation theory to demonstrate that the approximate-solution technique of statistical linearization for nonlinear stochastic differential equations corresponds to the lowest-order β truncation in both the consolidated perturbation expansions and in the ''mass operator'' of a renormalized Green's function equation. Other consolidated equations can be obtained by selectively modifying this mass operator. We particularize the results of this paper to the Duffing anharmonic oscillator equation

The End-To-End Safety Verification Process Implemented to Ensure Safe Operations of the Columbus Research Module

Science.gov (United States)

Arndt, J.; Kreimer, J.

2010-09-01

The European Space Laboratory COLUMBUS was launched in February 2008 with NASA Space Shuttle Atlantis. Since successful docking and activation this manned laboratory forms part of the International Space Station(ISS). Depending on the objectives of the Mission Increments the on-orbit configuration of the COLUMBUS Module varies with each increment. This paper describes the end-to-end verification which has been implemented to ensure safe operations under the condition of a changing on-orbit configuration. That verification process has to cover not only the configuration changes as foreseen by the Mission Increment planning but also those configuration changes on short notice which become necessary due to near real-time requests initiated by crew or Flight Control, and changes - most challenging since unpredictable - due to on-orbit anomalies. Subject of the safety verification is on one hand the on orbit configuration itself including the hardware and software products, on the other hand the related Ground facilities needed for commanding of and communication to the on-orbit System. But also the operational products, e.g. the procedures prepared for crew and ground control in accordance to increment planning, are subject of the overall safety verification. In order to analyse the on-orbit configuration for potential hazards and to verify the implementation of the related Safety required hazard controls, a hierarchical approach is applied. The key element of the analytical safety integration of the whole COLUMBUS Payload Complement including hardware owned by International Partners is the Integrated Experiment Hazard Assessment(IEHA). The IEHA especially identifies those hazardous scenarios which could potentially arise through physical and operational interaction of experiments. A major challenge is the implementation of a Safety process which owns quite some rigidity in order to provide reliable verification of on-board Safety and which likewise provides enough

Cost effective solutions for field development. System supplier approach to projects and operations

International Nuclear Information System (INIS)

Moe, P.O.

1994-01-01

The conference paper outlines the most important elements for a new approach to project realisation that enable a cost reduction of 30-50% compared to conventional methods. The achievements are based on studies and evaluations to the Norwegian Vigdis development project. The system elements covered are the electrical and automation systems including safety and process control and all traditional phases of a project from concept design to the operational phase. The concept involves new principles for project execution where traditional borderlines and interfaces between the various participants have been redefined. Management attention has been verified as an important prerequisite for a successful implementation of this strategy. 2 figs

The economic and social significance of RCA regional co-operative projects

International Nuclear Information System (INIS)

Fowler, E.E.

1979-01-01

The regional Co-operative Agreement for Research, Development and Training Related to Nuclear Science and Technology (RCA) is an established and valuable instrument between the International Atomic Energy Agency (IAEA) and Member States in South Asia, Southeast Asia and the Pacific or Far East for assisting in the transfer of modern technology to areas having economic and social importance to the region. The purpose of this review is to identify on-going or planned work which is designed to help achieve this goal. Currently approved RCA Regional Co-operative Research Projects are listed

Cool and Safe: Multiplicity in Safe Innovation at Unilever

Science.gov (United States)

Penders, Bart

2011-01-01

This article presents the making of a safe innovation: the application of ice structuring protein (ISP) in edible ices. It argues that safety is not the absence of risk but is an active accomplishment; innovations are not "made safe afterward" but "safe innovations are made". Furthermore, there are multiple safeties to be accomplished in the…

ETHEL's systems and facilities for safe management of tritiated wastes

International Nuclear Information System (INIS)

Mannone, F.; Dworschak, H.; Vassallo, G.

1992-01-01

The European Tritium Handling Experimental Laboratory (ETHEL) is a new tritium facility at the Commission of the European Community's Joint Research Centre, Ispra Site. The laboratory, destined to handle multigram amounts of tritium for safety related R and D purposes, is foreseen to start radioactive operations in late 1992. The general operation and maintenance of laboratory systems and future experiments will generate tritiated wastes in gaseous, liquid and solid forms. The management of such wastes under safe working conditions is a stringent laboratory requirement aimed at minimizing the risk of unacceptable tritium exposures to workers and the general public. This paper describes the main systems and facilities installed in ETHEL for the safe management of tritiated wastes

Operating results and experience and operating regimes in changing demands of energy world

International Nuclear Information System (INIS)

Hobza, L.

2004-01-01

In this paper, there are stated some operating results and experience obtained from trial operation of Temelin NPP. In Europe, Temelin NPP is presently one of the latest implemented projects of the series of VVER 1000 nuclear units with proven V-320 pressurized water reactor. The distinction between Temelin NPP and original project lays mainly in supply of nuclear fuel and in I and C systems delivered by Westinghouse Company. Temelin NPP has passed through commissioning period and trial operation. The main goal of the trial operation was to meet the requirements of section 2, par. 4, point b) of Decree No. 106/98 Sb. and verification of project parameters and stability of operation, and the situation leading to violation of safety functions fulfilment according to Pre-operational Safety Report should not occur. The integral part of trial operation assessment was also successful performing of determined monitoring programmes, first refuelling and performing of prescribed tests and operational inspections. Simultaneously, first experience was obtained with nuclear fuel; providing of ancillary services; reliability of important components; operation of turbine-generator 1000 MW; chemical regime; influence to environment; and quality of contractors. As safety is the most important indicator, it can be stated that: no facts which would lead to decreasing of safety systems operability have been detected; no facts which would lead to negative affecting of barriers against fading the radioactivity into both working areas and environment, have been detected; good condition of fire safety has been continuously documented; requirements of limits for releasing waste water into environment have been continuously complied with; requirements of limits for releasing radioactive substances (in gaseous and/or liquid state) into environment have been continuously complied with. From the operation regimes point of view is clear, that it would be suitable for the power plant if the

UMTRA Ground Water Project management action process document

International Nuclear Information System (INIS)

1996-03-01

A critical U.S. Department of Energy (DOE) mission is to plan, implement, and complete DOE Environmental Restoration (ER) programs at facilities that were operated by or in support of the former Atomic Energy Commission (AEC). These facilities include the 24 inactive processing sites the Uranium Mill Tailings Radiation Control Act (UMTRCA) (42 USC Section 7901 et seq.) identified as Title I sites, which had operated from the late 1940s through the 1970s. In UMTRCA, Congress acknowledged the potentially harmful health effects associated with uranium mill tailings and directed the DOE to stabilize, dispose of, and control the tailings in a safe and environmentally sound manner. The UMTRA Surface Project deals with buildings, tailings, and contaminated soils at the processing sites and any associated vicinity properties (VP). Surface remediation at the processing sites will be completed in 1997 when the Naturita, Colorado, site is scheduled to be finished. The UMTRA Ground Water Project was authorized in an amendment to the UMTRCA (42 USC Section 7922(a)), when Congress directed DOE to comply with U.S. Environmental Protection Agency (EPA) ground water standards. The UMTRA Ground Water Project addresses any contamination derived from the milling operation that is determined to be present at levels above the EPA standards

Operational Features of the Kamehameha Early Education Project. Technical Report #4.

Science.gov (United States)

Gallimore, Ronald; And Others

This report summarizes the operational features of the initial phases of the Kamehameha Early Education Project (KEEP). The rationale for KEEP's focus on conducting research on programs similar to those in the public schools rather than on developing radically innovative educational programs is discussed. Start up procedures such as recruitment of…

Asian regional co-operative project on food irradiation: Technology transfer

International Nuclear Information System (INIS)

1992-01-01

These Proceedings include the final reports of work performed by different institutions under the scope of Phase II of the Asian Regional Co-operative Project on Food Irradiation. The topics covered include the disinfestation and decontamination of stored products; improvements in the hygiene of processed seafood; insect disinfestation of fruits; and sprout inhibition of root crops. The individual presentations are indexed separately. Refs, figs and tabs

Analytical verification of requirements for safe and timely lay-down of ...

African Journals Online (AJOL)

Analytical verification of requirements for safe and timely lay-down of an offshore slay pipeline abandonment head during some pipe-lay stops: a case study of Forcados Yokri integrated pipeline project in Nigerian shallow offshore.

IUS/TUG orbital operations and mission support study. Volume 4: Project planning data

Science.gov (United States)

1975-01-01

Planning data are presented for the development phases of interim upper stage (IUS) and tug systems. Major project planning requirements, major event schedules, milestones, system development and operations process networks, and relevant support research and technology requirements are included. Topics discussed include: IUS flight software; tug flight software; IUS/tug ground control center facilities, personnel, data systems, software, and equipment; IUS mission events; tug mission events; tug/spacecraft rendezvous and docking; tug/orbiter operations interface, and IUS/orbiter operations interface.

Spent Nuclear Fuel (SNF) Project Cold Vacuum Drying (CVD) Facility Operations Manual

International Nuclear Information System (INIS)

IRWIN, J.J.

2000-01-01

The mission of the Spent Nuclear Fuel (SNF) Project Cold Vacuum Drying Facility (CVDF) is to achieve the earliest possible removal of free water from Multi-Canister Overpacks (MCOs). The MCOs contain metallic uranium SNF that have been removed from the 100K Area fuel storage water basins (i.e., the K East and K West Basins) at the US. Department of Energy Hanford Site in Southeastern Washington state. Removal of free water is necessary to halt water-induced corrosion of exposed uranium surfaces and to allow the MCOs and their SNF payloads to be safely transported to the Hanford Site 200 East Area and stored within the SNF Project Canister Storage Building (CSB). The CVDF is located within a few hundred yards of the basins, southwest of the 165KW Power Control Building and the 105KW Reactor Building. The site area required for the facility and vehicle circulation is approximately 2 acres. Access and egress is provided by the main entrance to the 100K inner area using existing roadways. The CVDF will remove free. water from the MCOs to reduce the potential for continued fuel-water corrosion reactions. The cold vacuum drying process involves the draining of bulk water from the MCO and subsequent vacuum drying. The MCO will be evacuated to a pressure of 8 torr or less and backfilled with an inert gas (helium). The MCO will be sealed, leak tested, and then transported to the CSB within a sealed shipping cask. (The MCO remains within the same shipping Cask from the time it enters the basin to receive its SNF payload until it is removed from the Cask by the CSB MCO handling machine.) The CVDF subproject acquired the required process systems, supporting equipment, and facilities. The cold vacuum drying operations result in an MCO containing dried fuel that is prepared for shipment to the CSB by the Cask transportation system. The CVDF subproject also provides equipment to dispose of solid wastes generated by the cold vacuum drying process and transfer process water removed

Operational test report - Project W-320 cathodic protection systems

International Nuclear Information System (INIS)

Bowman, T.J.

1998-01-01

Washington Administrative Code (WAC) 173-303-640 specifies that corrosion protection must be designed into tank systems that treat or store dangerous wastes. Project W-320, Waste Retrieval Sluicing System (WRSS), utilizes underground encased waste transfer piping between tanks 241-C-106 and 241-AY-102. Corrosion protection is afforded to the encasements of the WRSS waste transfer piping through the application of earthen ionic currents onto the surface of the piping encasements. Cathodic protection is used in conjunction with the protective coatings that are applied upon the WRSS encasement piping. WRSS installed two new two rectifier systems (46 and 47) and modified one rectifier system (31). WAC 173-303-640 specifies that the proper operation of cathodic protection systems must be confirmed within six months after initial installation. The WRSS cathodic protection systems were energized to begin continuous operation on 5/5/98. Sixteen days after the initial steady-state start-up of the WRSS rectifier systems, the operational testing was accomplished with procedure OTP-320-006 Rev/Mod A-0. This operational test report documents the OTP-320-006 results and documents the results of configuration testing of integrated piping and rectifier systems associated with the W-320 cathodic protection systems

Small Explorer project: Submillimeter Wave Astronomy Satellite (SWAS). Mission operations and data analysis plan

Science.gov (United States)

Melnick, Gary J.

1990-01-01

The Mission Operations and Data Analysis Plan is presented for the Submillimeter Wave Astronomy Satellite (SWAS) Project. It defines organizational responsibilities, discusses target selection and navigation, specifies instrument command and data requirements, defines data reduction and analysis hardware and software requirements, and discusses mission operations center staffing requirements.

Community participation in fire management planning: The Trinity county fire safe council's fire plan

Science.gov (United States)

Yvonne Everett

2008-01-01

In 1999, Trinity County CA, initiated a participatory fire management planning effort. Since that time, the Trinity County Fire Safe Council has completed critical portions of a fire safe plan and has begun to implement projects defined in the plan. Completion of a GIS based, landscape scale fuels reduction element in the plan defined by volunteer fire fighters, agency...

Expansion of Michigan EOR Operations Using Advanced Amine Technology at a 600 MW Project Wolverine Carbon Capture and Storage Project

Energy Technology Data Exchange (ETDEWEB)

H Hoffman; Y kishinevsky; S. Wu; R. Pardini; E. Tripp; D. Barnes

2010-06-16

Wolverine Power Supply Cooperative Inc, a member owned cooperative utility based in Cadillac Michigan, proposes to demonstrate the capture, beneficial utilization and storage of CO{sub 2} in the expansion of existing Enhanced Oil Recovery operations. This project is being proposed in response to the US Department of Energy Solicitation DE-FOA-0000015 Section III D, 'Large Scale Industrial CCS projects from Industrial Sources' Technology Area 1. The project will remove 1,000 metric tons per day of CO{sub 2} from the Wolverine Clean Energy Venture 600 MW CFB power plant owned and operated by WPC. CO{sub 2} from the flue gas will be captured using Hitachi's CO{sub 2} capture system and advanced amine technology. The capture system with the advanced amine-based solvent supplied by Hitachi is expected to significantly reduce the cost and energy requirements of CO{sub 2} capture compared to current technologies. The captured CO{sub 2} will be compressed and transported for Enhanced Oil Recovery and CO{sub 2} storage purposes. Enhanced Oil Recovery is a proven concept, widely used to recover otherwise inaccessible petroleum reserves. While post-combustion CO{sub 2} capture technologies have been tested at the pilot scale on coal power plant flue gas, they have not yet been demonstrated at a commercial scale and integrated with EOR and storage operations. Amine-based CO{sub 2} capture is the leading technology expected to be available commercially within this decade to enable CCS for utility and industrial facilities firing coal and waste fuels such as petroleum coke. However, traditional CO{sub 2} capture process utilizing commercial amine solvents is very energy intensive for regeneration and is also susceptible to solvent degradation by oxygen as well as SOx and NO{sub 2} in the flue gas, resulting in large operating costs. The large volume of combustion flue gas with its low CO{sub 2} concentration requires large equipment sizes, which together with the

Recommendations of the NUSS programme to achieve safe operation

International Nuclear Information System (INIS)

Bertini, A.

1985-01-01

The paper exposes essentially the spirit of the Code of Practice and of the Safety Guides on Operation. Emphasis is put on the fact that safety operation is the outcome of a mental habit which must permeate all levels of the operating organization, rather than just being due to the effect of specific rules, which, like safety factors in design, ensure achievement of the safety goals. The paper, starting from what is written in the NUSS documents, deals with what is not actually written in these, because a mental habit cannot be codified and a safety-minded organization cannot be created by a law or by a regulation. The paper underlines the necessity for all problems connected with nuclear operation to be tackled without prejudices, without reference to irrelevant precedents or practices, in the exclusive interest of safety. (author)

Operating test report for project W-417, T-plant steam removal upgrade, waste transfer portion

International Nuclear Information System (INIS)

Myers, N.K.

1997-01-01

This Operating Test Report (OTR) documents the performance results of the Operating Test Procedure HNF-SD-W417-OTP-001 that provides steps to test the waste transfer system installed in the 221-T Canyon under project W-417. Recent modifications have been performed on the T Plant Rail Car Waste Transfer System. This Operating Test Procedure (OTP) will document the satisfactory operation of the 221-T Rail Car Waste Transfer System modified by project W-417. Project W-417 installed a pump in Tank 5-7 to replace the steam jets used for transferring liquid waste. This testing is required to verify that operational requirements of the modified transfer system have been met. Figure 2 and 3 shows the new and existing system to be tested. The scope of this testing includes the submersible air driven pump operation in Tank 5-7, liquid waste transfer operation from Tank 5-7 to rail car (HO-IOH-3663 or HO-IOH-3664), associated line flushing, and the operation of the flow meter. This testing is designed to demonstrate the satisfactory operation-of the transfer line at normal operating conditions and proper functioning of instruments. Favorable results will support continued use of this system for liquid waste transfer. The Functional Design Criteria for this system requires a transfer flow rate of 40 gallons per minute (GPM). To establish these conditions the pump will be supplied up to 90 psi air pressure from the existing air system routed in the canyon. An air regulator valve will regulate the air pressure. Tank capacity and operating ranges are the following: Tank No. Capacity (gal) Operating Range (gal) 5-7 10,046 0 8040 (80%) Rail car (HO-IOH-3663 HO-IOH-3664) 097219,157 Existing Tank level instrumentation, rail car level detection, and pressure indicators will be utilized for acceptance/rejection Criteria. The flow meter will be verified for accuracy against the Tank 5-7 level indicator. The level indicator is accurate to within 2.2 %. This will be for information only

Spent Nuclear Fuel (SNF) Project Cold Vacuum Drying (CVD) Facility Operations Manual

Energy Technology Data Exchange (ETDEWEB)

IRWIN, J.J.

2000-02-03

This document provides the Operations Manual for the Cold Vacuum Drying Facility (CVDF). The Manual was developed in conjunction with HNF-SD-SNF-SAR-002, Safety Analysis Report for the Cold Vacuum Drying Facility, Phase 2, Supporting Installation of the Processing Systems (Garvin 1998) and, the HNF-SD-SNF-DRD-002, 1997, Cold Vacuum Drying Facility Design Requirements, Rev. 3a. The Operations Manual contains general descriptions of all the process, safety and facility systems in the CVDF, a general CVD operations sequence, and has been developed for the spent nuclear fuel project (SNFP) Operations Organization and shall be updated, expanded, and revised in accordance with future design, construction and startup phases of the CVDF until the CVDF final ORR is approved.

Spent Nuclear Fuel (SNF) Project Cold Vacuum Drying (CVD) Facility Operations Manual

International Nuclear Information System (INIS)

IRWIN, J.J.

2000-01-01

This document provides the Operations Manual for the Cold Vacuum Drying Facility (CVDF). The Manual was developed in conjunction with HNF-SD-SNF-SAR-002, Safety Analysis Report for the Cold Vacuum Drying Facility, Phase 2, Supporting Installation of the Processing Systems (Garvin 1998) and, the HNF-SD-SNF-DRD-002, 1997, Cold Vacuum Drying Facility Design Requirements, Rev. 3a. The Operations Manual contains general descriptions of all the process, safety and facility systems in the CVDF, a general CVD operations sequence, and has been developed for the spent nuclear fuel project (SNFP) Operations Organization and shall be updated, expanded, and revised in accordance with future design, construction and startup phases of the CVDF until the CVDF final ORR is approved

Clinical evaluation of semiautonomous smart wheelchair architecture (Drive-Safe System) with visually impaired individuals.

Science.gov (United States)

Sharma, Vinod; Simpson, Richard C; LoPresti, Edmund F; Schmeler, Mark

2012-01-01

Nonambulatory, visually impaired individuals mostly rely on caregivers for their day-to-day mobility needs. The Drive-Safe System (DSS) is a modular, semiautonomous smart wheelchair system aimed at providing independent mobility to people with visual and mobility impairments. In this project, clinical evaluation of the DSS was performed in a controlled laboratory setting with individuals who have visual impairment but no mobility impairment. Their performance using DSS was compared with their performance using a standard cane for navigation assistance. Participants rated their subjective appraisal of the DSS by using the National Aeronautics and Space Administration-Task Load Index inventory. DSS significantly reduced the number and severity of collisions compared with using a cane alone and without increasing the time required to complete the task. Users rated DSS favorably; they experienced less physical demand when using the DSS, but did not feel any difference in perceived effort, mental demand, and level of frustration when using the DSS alone or along with a cane in comparison with using a cane alone. These findings suggest that the DSS can be a safe, reliable, and easy-to-learn and operate independent mobility solution for visually impaired wheelchair users.

A Safe Cooperative Framework for Atmospheric Science Missions with Multiple Heterogeneous UAS using Piecewise Bezier Curves

Science.gov (United States)

Mehdi, S. Bilal; Puig-Navarro, Javier; Choe, Ronald; Cichella, Venanzio; Hovakimyan, Naira; Chandarana, Meghan; Trujillo, Anna; Rothhaar, Paul M.; Tran, Loc; Neilan, James H.;

The role of safe practices in hospitals’ total factor productivity

Directory of Open Access Journals (Sweden)

Timothy R Huerta

2011-01-01

Full Text Available Timothy R Huerta1, Mark A Thompson2, Eric W Ford31Center for Health Innovation, Education, and Research, 2Rawls College of Business, Texas Tech University, Lubbock, TX, USA; 3Forsyth Medical Center Distinguished Professor of Health Care, The University of North Carolina Greensboro, Greensboro, NC, USAAbstract: The dual aims of improving safety and productivity are a major part of the health care reform movement hospital leaders must manage. Studies exploring the two phenomena conjointly and over time are critical to understanding how change in one dimension influences the other over time. A Malmquist approach is used to assess hospitals’ relative productivity levels over time. Analysis of variance (ANOVA algorithms were executed to assess whether or not the Malmquist Indices (MIs correlate with the safe practices measure. The American Hospital Association’s annual survey and the Centers for Medicare and Medicaid Services’ Case Mix Index for fiscal years 2002–2006, along with Leapfrog Group’s annual survey for 2006 were used for this study. Leapfrog Group respondents have significantly higher technological change (TC and total factor productivity (TFP than nonrespondents without sacrificing technical efficiency changes. Of the three MIs, TC (P < 0.10 and TFP (P < 0.05 had significant relationships with the National Quality Forum’s Safe Practices score. The ANOVA also indicates that the mean differences of TFP measures progressed in a monotonic fashion up the Safe Practices scale. Adherence to the National Quality Forum’s Safe Practices recommendations had a major impact on hospitals’ operating processes and productivity. Specifically, there is evidence that hospitals reporting higher Safe Practices scores had above average levels of TC and TFP gains over the period assessed. Leaders should strive for increased transparency to promote both quality improvement and increased productivity.Keywords: safety, productivity, quality, safe

Maintaining staff competence-a NPP operator viewpoint

International Nuclear Information System (INIS)

Patrakka, E.

2000-01-01

For a nuclear power plant operator, it is crucial to guarantee the safe and economic operation of the power plant as well as to look after the general acceptability of nuclear power. As to human resources management, this requires continuous maintenance and enhancement of the performance of the individuals and organisation. To this end, several development projects have recently been implemented by Teollisuuden Voima Oy (TVO) at the Olkiluoto nuclear power plant, which consists of twin 840 MWe BWR units that commenced their operation in 1978 and 1980. Systematic initial and continuing training programmes are needed to maintain the technical and managerial skills and know-how at a high level. The present stabile state of nuclear power, i.e. operation of ageing plants with personnel ageing as well, requires a variety of actions to reinforce the training efforts. At Olkiluoto NPP, we have carried out an extensive modernization programme that allowed the personnel to strengthen their knowledge and supplement it with the most recent results of development. We have also closely monitored the NPP development projects of the vendors, which has added to the preservation of know-how and understanding of advanced nuclear power technology. We have close contacts to the research institutes and universities, and have performed R and D activities to limited extent. In addition to the projects mentioned above, a co-ordinated development programme, 'TVO 2002', was initiated last year. The main objective of this programme is to ensure the functional preconditions and the competitiveness of the company in a changing environment. The management and operational procedures will be developed in such a way that the goals set for year 2002 will be achieved. The programme is organised as ten projects, which cover a variety of development subjects. One of the focal areas includes projects that can be characterised with the words 'Survey of competencies' and 'Preservation of know

Contributions of the European Operating Experience Feedback Project to Support Regulatory Bodies

International Nuclear Information System (INIS)

Heitsch, M.

2016-01-01

Operating Experience Feedback (OEF) is one of the ways of improving the nuclear safety of operating nuclear power plants. The EC-Clearinghouse initiative was set up in 2008 to support nuclear regulatory authorities of EU Member States, but also Technical Support Organizations, international organizations and the broader nuclear community, to enhance nuclear safety. The differing regulatory regimes in the EU member countries and a significant diversity of the nuclear power plant (NPP) designs have been a challenge in the establishment of the European Clearinghouse. The European Clearinghouse is organized as a Network operated by a Central Office located at the Institute for Energy and Transport (IET) which is part of Joint Research Centre (JRC) of the European Commission. It gathers 17 European regulatory authorities and 3 major European Technical Support organizations (TSO). The Clearinghouse aims at providing lessons learned, recommendations and best practices from operational experience of NPPs based on support and commitment from the EU nuclear regulatory authorities. One of the objectives of the European Clearinghouse is to establish European best practices for the assessment of unusual events in NPPs. The paper will present the main activities of the European Clearinghouse. These include: • Topical studies providing in-depth assessment of selected topics important for the safe operation of NPPs. Statistical tools help to identify interesting subjects for these studies; • Quarterly reports on operating experience; • Training courses in the field of root cause analysis and event investigation; • Development, maintenance and population of a database for storage of operating experience related information; • Collaboration with international organizations such as IAEA and OECD/NEA on all aspects of OEF. All activities of the Clearinghouse initiative focus on providing an added value for nuclear regulation. (author)

Safety training and safe operating procedures written for PBFA (Particle Beam Fusion Accelerator) II and applicable to other pulsed power facilities

Energy Technology Data Exchange (ETDEWEB)

Donovan, G.L.; Goldstein, S.A.

1986-12-01

To ensure that work in advancing pulsed power technology is performed with an acceptably low risk, pulsed power research facilities at Sandia National Laboratories must satisfy general safety guidelines established by the Department of Energy, policies and formats of the Environment, Safety, and Health (ES and H) Department, and detailed procedures formulated by the Pulsed Power Sciences Directorate. The approach to safety training and to writing safe operating procedures, and the procedures presented here are specific to the Particle Beam Fusion Accelerator II (PBFA II) Facility but are applicable as guidelines to other research and development facilities which have similar hazards.

Safety training and safe operating procedures written for PBFA [Particle Beam Fusion Accelerator] II and applicable to other pulsed power facilities

International Nuclear Information System (INIS)

Donovan, G.L.; Goldstein, S.A.

1986-12-01

To ensure that work in advancing pulsed power technology is performed with an acceptably low risk, pulsed power research facilities at Sandia National Laboratories must satisfy general safety guidelines established by the Department of Energy, policies and formats of the Environment, Safety, and Health (ES and H) Department, and detailed procedures formulated by the Pulsed Power Sciences Directorate. The approach to safety training and to writing safe operating procedures, and the procedures presented here are specific to the Particle Beam Fusion Accelerator II (PBFA II) Facility but are applicable as guidelines to other research and development facilities which have similar hazards

Application of digital solutions to help the safe and efficient operation of nuclear power plants; Aplicacion de soluciones digitales para la ayuda a la operacion segura y eficiente de las centrales nucleares

Energy Technology Data Exchange (ETDEWEB)

Ortega P, F.; Fernandez F, S., E-mail: fortega@tecnatom.es [Tecnatom S. A., Av. Montes de Oca 1, 28703 San Sebastian de los Reyes, Madrid (Spain)

2017-09-15

In the search for excellence, the emergence of solutions to digitize nuclear power plants is an opportunity to optimize the operation and safety of them. The new technologies available today in the market, applied under a global vision of the operation, can contribute to the excellent operation of nuclear power plants in terms of efficiency and effectiveness. Tecnatom has a long experience in various areas related to the operation of the plants, giving the aforementioned global vision, essential to develop global solutions that pursue the safe and efficient operation of the operation. (Author)

Toeplitz Operators, Pseudo-Homogeneous Symbols, and Moment Maps on the Complex Projective Space

Directory of Open Access Journals (Sweden)

Miguel Antonio Morales-Ramos

2017-01-01

Full Text Available Following previous works for the unit ball due to Nikolai Vasilevski, we define quasi-radial pseudo-homogeneous symbols on the projective space and obtain the corresponding commutativity results for Toeplitz operators. A geometric interpretation of these symbols in terms of moment maps is developed. This leads us to the introduction of a new family of symbols, extended pseudo-homogeneous, that provide larger commutative Banach algebras generated by Toeplitz operators. This family of symbols provides new commutative Banach algebras generated by Toeplitz operators on the unit ball.

Eye safe laser range finders

International Nuclear Information System (INIS)

Snir, M.; Margaliot, M.; Amitzi, A.

2004-01-01

During the 1970's, Ruby (Q switched) laser based range finders with a wavelength of 694nm were first used. These lasers operated in a pulse mode within the visible light range and produced a risk for the eye retina. The laser beam striking the macula could damage the eye and might cause blindness. Over the years, Nd:YAG (Q switched) lasers were developed (operating at 1064nm) for range finding and designation uses. The wavelength of these lasers, operating in the near Infra-Red range (invisible), is also focused tightly on the retina. The human eye does not respond to the invisible light so there is no natural protection (eye blink reflex) as in the visible light. The operation of these lasers worldwide, especially when the laser beam is exposed, causes occasional eye accidents. Another risk is stemming from the use of observation systems with a high optical gain, in the laser operation areas, which enlarge the range of risk quite significantly. Therefore, research and development efforts were invested in order to introduce eye safe lasers. One of the solutions for this problem is presented in following document

Lessons learned at the Fernald thorium removal project

International Nuclear Information System (INIS)

Boyd, R.

1990-01-01

In 1987, IT Corporation was awarded a subcontract through Rust Engineering Co. to provide decontamination and decommissioning services at the US Department of Energy Feed Materials Production Center (FMPC) near Fernald, Ohio. The work included the removal and repackaging of approximately 8,000 cubic feet of thorium oxide from several structures, including a silo, elevated bins, bucket elevators, and the silo understructure. The removal and repackaging project was undertaken because the integrity of the containment structures was questionable. Rust and Westinghouse (the operating contractor at FMPC) also felt that the repackaging and warehousing of the thorium would reduce occupational radiation exposure to site workers. Worker safety and environmental protection being of primary importance, the removal work was performed within specially-designed radiological containment facilities. The project presented challenges which, according to Westinghouse and Rust personnel, made it one of the most hazardous projects ever attempted at Fernald. Challenges included relations between non-union and union personnel, a strike by craft labor, interactions among DOE, EPA, and Westinghouse and their impact on a fixed-price contract, the impact of hazardous waste regulations, safe operations, and the contamination-free release of materials

High Altitude Long Endurance Remotely Operated Aircraft - National Airspace System Integration - Simulation IPT: Detailed Airspace Operations Simulation Plan. Version 1.0

Science.gov (United States)

2004-01-01

The primary goal of Access 5 is to allow safe, reliable and routine operations of High Altitude-Long Endurance Remotely Operated Aircraft (HALE ROAs) within the National Airspace System (NAS). Step 1 of Access 5 addresses the policies, procedures, technologies and implementation issues of introducing such operations into the NAS above pressure altitude 40,000 ft (Flight Level 400 or FL400). Routine HALE ROA activity within the NAS represents a potentially significant change to the tasks and concerns of NAS users, service providers and other stakeholders. Due to the complexity of the NAS, and the importance of maintaining current high levels of safety in the NAS, any significant changes must be thoroughly evaluated prior to implementation. The Access 5 community has been tasked with performing this detailed evaluation of routine HALE-ROA activities in the NAS, and providing to key NAS stakeholders a set of recommended policies and procedures to achieve this goal. Extensive simulation, in concert with a directed flight demonstration program are intended to provide the required supporting evidence that these recommendations are based on sound methods and offer a clear roadmap to achieving safe, reliable and routine HALE ROA operations in the NAS. Through coordination with NAS service providers and policy makers, and with significant input from HALE-ROA manufacturers, operators and pilots, this document presents the detailed simulation plan for Step 1 of Access 5. A brief background of the Access 5 project will be presented with focus on Steps 1 and 2, concerning HALE-ROA operations above FL400 and FL180 respectively. An overview of project management structure follows with particular emphasis on the role of the Simulation IPT and its relationships to other project entities. This discussion will include a description of work packages assigned to the Simulation IPT, and present the specific goals to be achieved for each simulation work package, along with the associated

Statement of John H. Anttonen, Project Manager, Basalt Waste Isolation Project, Richland Operations Office, Department of Energy

International Nuclear Information System (INIS)

Anon.

1987-01-01

My name is John Anttonen and I am the Project Manager for the Basalt Waste Isolation Project (BWIP) at the Department of Energy Richland Operation Office. The responsibilities of may office are to manage the day-to-day activities of the site suitability investigations of the basalt formations at the Hanford Site, a Department complex that is involved in a variety of national missions, including defense materials production, nuclear energy research, and radioactive waste management. In may prepared comments today I would like to touch upon four specific subject areas relating to the BWIP program and then I would be happy to answer any questions you might have. The topics I will cover are: (1) historical aspects; (2) site specific technical issues and how they will be addressed during site characterization of the basalt site at Hanford; (3) current project status and; (4) institutional interaction. For clarity, I have attached several charts to my statement

Characterization of Sensitive Species and Habitats Affected by the Operation of USACE Water Resource Development Projects

National Research Council Canada - National Science Library

Kasul, Richard

2000-01-01

...) work unit titled "Reservoir Operations - Impacts on Target Species." Current knowledge regarding the occurrence of sensitive species that have been identified as a management concern in the operation of Corps projects is reviewed...

Fuel supply shutdown facility interim operational safety requirements

International Nuclear Information System (INIS)

Besser, R.L.; Brehm, J.R.; Benecke, M.W.; Remaize, J.A.

1995-01-01

These Interim Operational Safety Requirements (IOSR) for the Fuel Supply Shutdown (FSS) facility define acceptable conditions, safe boundaries, bases thereof, and management or administrative controls to ensure safe operation. The IOSRs apply to the fuel material storage buildings in various modes (operation, storage, surveillance)

The new EC FP7 MatISSE project: materials' innovations for a safe and sustainable nuclear in Europe

International Nuclear Information System (INIS)

Cabet, C.; Michaux, A.; Fazio, C.; Malerba, L.; Maday, M.F.; Serrano, M.; Nilsson, K.F.; )

2015-01-01

The European Energy Research Alliance (EERA), set-up under the European SET-Plan, has launched an initiative for a Joint Programme on Nuclear Materials (JPNM). The JNMP aims to establish key priorities in the area of advanced nuclear materials, identify funding opportunities and harmonise this scientific and technical domain at the European level by maximising complementarities and synergies with the major actors of the field. The JPNM partners submitted the MatISSE proposal which was accepted by the European Commission. The MatISSE project has the ambition to prepare the building of a European integrated research programme on materials innovation for a safe and sustainable nuclear. Emphasis is on advanced nuclear systems in particular sodium-cooled fast reactor (SFR), lead-cooled fast reactor (LFR) and gas-cooled fast reactor (GFR). The aim of the selected scientific and technical work is to make progress in the fields of conventional materials, advanced materials and predictive capabilities for fuel elements and structural components. (authors)

Working safely with electronics racks

CERN Document Server

Simon Baird, HSE Unit Head

2016-01-01

Think of CERN and you’ll probably think of particle accelerators and detectors. These are the tools of the trade in particle physics, but behind them are the racks of electronics that include power supplies, control systems and data acquisition networks.   Inside an electronics rack: danger could be lurking if the rack is not powered off. In routine operation, these are no more harmful than the home entertainment system in your living room. But unscrew the cover and it’s a different matter. Even after following appropriate training, and with formal authorisation from your group leader or equivalent to carry out electrical work or any work in the vicinity of electrical hazards, and even with extensive experience of carrying out such operations, it’s important to incorporate safe working practices into your routine. At CERN, before the racks of electronics reach their operational configurations for the accelerators and detectors, they play a vital role in test set-ups ...

The Model of Lake Operation in Water Transfer Projects Based on the Theory of Water- right

Science.gov (United States)

Bi-peng, Yan; Chao, Liu; Fang-ping, Tang

the lake operation is a very important content in Water Transfer Projects. The previous studies have not any related to water-right and water- price previous. In this paper, water right is divided into three parts, one is initialization waterright, another is by investment, and the third is government's water- right re-distribution. The water-right distribution model is also build. After analyzing the cost in water transfer project, a model and computation method for the capacity price as well as quantity price is proposed. The model of lake operation in water transfer projects base on the theory of water- right is also build. The simulation regulation for the lake was carried out by using historical data and Genetic Algorithms. Water supply and impoundment control line of the lake was proposed. The result can be used by south to north water transfer projects.

Fuel Supply Shutdown Facility Interim Operational Safety Requirements

International Nuclear Information System (INIS)

BENECKE, M.W.

2000-01-01

The Interim Operational Safety Requirements for the Fuel Supply Shutdown (FSS) Facility define acceptable conditions, safe boundaries, bases thereof, and management of administrative controls to ensure safe operation of the facility

Safe operation of power plants. Pt. 1

International Nuclear Information System (INIS)

Freymeyer, P.

1977-01-01

Electrotechniques were given a dominating role in the construction of nuclear power plants. The operation of power plants - particularly nuclear power plants - is impossible without the use of electrotechnical and control means. Despite of all reserve in the development and despite of the conservative attitude it is necessary to use the newest results of development and to incite the development ot new electronic systems for the solution of these tasks. (orig.) [de

Evaluation of Nuclear Facility Decommissioning Projects program

International Nuclear Information System (INIS)

Baumann, B.L.

1983-01-01

The objective of the Evaluation of Nuclear Facility Decommissioning Projects (ENFDP) program is to provide the NRC licensing staff with data which will allow an assessment of radiation exposure during decommissioning and the implementation of ALARA techniques. The data will also provide information to determine the funding level necessary to ensure timely and safe decommissioning operations. Actual decommissioning costs, methods and radiation exposures are compared with those estimated by the Battelle-PNL and ORNL NUREGs on decommissioning. Exposure reduction techniques applied to decommissioning activities to meet ALARA objectives are described. The lessons learned concerning various decommissioning methods are evaluated

The operation and maintenance manual

International Nuclear Information System (INIS)

Stoll, A.; Krotil, H.; Klein, W.

1976-01-01

The operating manual is one of many technical documents which the nuclear power plant operator needs for ensuring safe operation. For the operating staff, however, there is only one document, namely the operating manual. The operating manual is an essential element in bringing man and machine in harmony. This is necessary for safe and, as far as possible, uninterrupted operation of the power plant. The operating manual is the only document containing binding instructions for plant operation. All the tasks of plant operation which are carried out by plant staff are described in the operating manual in a form which is as clear and comprehensible as possible. A considerable number of these tasks can only be carried out by man, namely: 1) tasks concerning operational organization, 2) all non-automated areas of plant operation. (orig./TK) [de