Review of Ground Systems Development and Operations (GSDO) Tools for Verifying Command and Control Software

Science.gov (United States)

Aguilar, Michael L.; Bonanne, Kevin H.; Favretto, Jeffrey A.; Jackson, Maddalena M.; Jones, Stephanie L.; Mackey, Ryan M.; Sarrel, Marc A.; Simpson, Kimberly A.

2014-01-01

The Exploration Systems Development (ESD) Standing Review Board (SRB) requested the NASA Engineering and Safety Center (NESC) conduct an independent review of the plan developed by Ground Systems Development and Operations (GSDO) for identifying models and emulators to create a tool(s) to verify their command and control software. The NESC was requested to identify any issues or weaknesses in the GSDO plan. This document contains the outcome of the NESC review.

Evaluation of Agency Non-Code Layered Pressure Vessels (LPVs)

Science.gov (United States)

Prosser, William H.

2014-01-01

In coordination with the Office of Safety and Mission Assurance and the respective Center Pressure System Managers (PSMs), the NASA Engineering and Safety Center (NESC) was requested to formulate a consensus draft proposal for the development of additional testing and analysis methods to establish the technical validity, and any limitation thereof, for the continued safe operation of facility non-code layered pressure vessels. The PSMs from each NASA Center were asked to participate as part of the assessment team by providing, collecting, and reviewing data regarding current operations of these vessels. This report contains the outcome of the assessment and the findings, observations, and NESC recommendations to the Agency and individual NASA Centers.

Evaluation of Agency Non-Code Layered Pressure Vessels (LPVs). Corrected Copy, Aug. 25, 2014

Science.gov (United States)

Prosser, William H.

2014-01-01

In coordination with the Office of Safety and Mission Assurance and the respective Center Pressure System Managers (PSMs), the NASA Engineering and Safety Center (NESC) was requested to formulate a consensus draft proposal for the development of additional testing and analysis methods to establish the technical validity, and any limitation thereof, for the continued safe operation of facility non-code layered pressure vessels. The PSMs from each NASA Center were asked to participate as part of the assessment team by providing, collecting, and reviewing data regarding current operations of these vessels. This report contains the outcome of the assessment and the findings, observations, and NESC recommendations to the Agency and individual NASA Centers.

Assessment of Ocean Wave Model used to Analyze the Constellation Program (CxP) Orion Project Crew Module Water Landing Conditions

Science.gov (United States)

Smith, Bryan K.; Bouchard, Richard; Teng, Chung-Chu; Dyson, Rodger; Jenson, Robert; OReilly, William; Rogers, Erick; Wang, David; Volovoi, Vitali

2009-01-01

Mr. Christopher Johnson, NASA's Systems Manager for the Orion Project Crew Module (CM) Landing and Recovery at the Johnson Space Center (JSC), and Mr. James Corliss, Project Engineer for the Orion CM Landing System Advanced Development Project at the Langley Research Center (LaRC) requested an independent assessment of the wave model that was developed to analyze the CM water landing conditions. A NASA Engineering and Safety Center (NESC) initial evaluation was approved November 20, 2008. Mr. Bryan Smith, NESC Chief Engineer at the NASA Glenn Research Center (GRC), was selected to lead this assessment. The Assessment Plan was presented and approved by the NESC Review Board (NRB) on December 18, 2008. The Assessment Report was presented to the NRB on March 12, 2009. This document is the final Assessment Report.

Support Provided to the External Tank (ET) Project on the Use of Statistical Analysis for ET Certification Consultation Position Paper

Science.gov (United States)

Null, Cynthia H.

2009-01-01

In June 2004, the June Space Flight Leadership Council (SFLC) assigned an action to the NASA Engineering and Safety Center (NESC) and External Tank (ET) project jointly to characterize the available dataset [of defect sizes from dissections of foam], identify resultant limitations to statistical treatment of ET as-built foam as part of the overall thermal protection system (TPS) certification, and report to the Program Requirements Change Board (PRCB) and SFLC in September 2004. The NESC statistics team was formed to assist the ET statistics group in August 2004. The NESC's conclusions are presented in this report.

Review of Exploration Systems Development (ESD) Integrated Hazard Development Process. Appendices; Volume 2

Science.gov (United States)

Smiles, Michael D.; Blythe, Michael P.; Bejmuk, Bohdan; Currie, Nancy J.; Doremus, Robert C.; Franzo, Jennifer C.; Gordon, Mark W.; Johnson, Tracy D.; Kowaleski, Mark M.; Laube, Jeffrey R.

2015-01-01

The Chief Engineer of the Exploration Systems Development (ESD) Office requested that the NASA Engineering and Safety Center (NESC) perform an independent assessment of the ESD's integrated hazard development process. The focus of the assessment was to review the integrated hazard analysis (IHA) process and identify any gaps/improvements in the process (e.g. missed causes, cause tree completeness, missed hazards). This document contains the outcome of the NESC assessment.

Review of Exploration Systems Development (ESD) Integrated Hazard Development Process. Volume 1; Appendices

Science.gov (United States)

Smiles, Michael D.; Blythe, Michael P.; Bejmuk, Bohdan; Currie, Nancy J.; Doremus, Robert C.; Franzo, Jennifer C.; Gordon, Mark W.; Johnson, Tracy D.; Kowaleski, Mark M.; Laube, Jeffrey R.

2015-01-01

The Chief Engineer of the Exploration Systems Development (ESD) Office requested that the NASA Engineering and Safety Center (NESC) perform an independent assessment of the ESD's integrated hazard development process. The focus of the assessment was to review the integrated hazard analysis (IHA) process and identify any gaps/improvements in the process (e.g., missed causes, cause tree completeness, missed hazards). This document contains the outcome of the NESC assessment.

NASA Workshop on Hybrid (Mixed-Actuator) Spacecraft Attitude Control

Science.gov (United States)

Dennehy, Cornelius J.; Kunz, Nans

2014-01-01

At the request of the Science Mission Directorate Chief Engineer, the NASA Technical Fellow for Guidance, Navigation & Control assembled and facilitated a workshop on Spacecraft Hybrid Attitude Control. This multi-Center, academic, and industry workshop, sponsored by the NASA Engineering and Safety Center (NESC), was held in April 2013 to unite nationwide experts to present and discuss the various innovative solutions, techniques, and lessons learned regarding the development and implementation of the various hybrid attitude control system solutions investigated or implemented. This report attempts to document these key lessons learned with the 16 findings and 9 NESC recommendations.

Patient safety goals for the proposed Federal Health Information Technology Safety Center.

Science.gov (United States)

Sittig, Dean F; Classen, David C; Singh, Hardeep

2015-03-01

The Office of the National Coordinator for Health Information Technology is expected to oversee creation of a Health Information Technology (HIT) Safety Center. While its functions are still being defined, the center is envisioned as a public-private entity focusing on promotion of HIT related patient safety. We propose that the HIT Safety Center leverages its unique position to work with key administrative and policy stakeholders, healthcare organizations (HCOs), and HIT vendors to achieve four goals: (1) facilitate creation of a nationwide 'post-marketing' surveillance system to monitor HIT related safety events; (2) develop methods and governance structures to support investigation of major HIT related safety events; (3) create the infrastructure and methods needed to carry out random assessments of HIT related safety in complex HCOs; and (4) advocate for HIT safety with government and private entities. The convening ability of a federally supported HIT Safety Center could be critically important to our transformation to a safe and effective HIT enabled healthcare system. © The Author 2014. Published by Oxford University Press on behalf of the American Medical Informatics Association. All rights reserved. For Permissions, please email: journals.permissions@oup.com.

Nuclear safety research collaborations between the US and Russian Federation international nuclear safety centers

International Nuclear Information System (INIS)

Hill, D.J; Braun, J.C; Klickman, A.E.; Bugaenko, S.E; Kabanov, L.P; Kraev, A.G.

2000-01-01

The Russian Federation Ministry for Atomic Energy (MINATOM) and the U.S. Department of Energy (USDOE) have formed International Nuclear Safety Centers to collaborate on nuclear safety research. USDOE established the U. S. Center at Argonne National Laboratory in October 1995. MINATOM established the Russian Center at the Research and Development Institute of Power Engineering in Moscow in July 1996. In April 1998 the Russian center became an independent, autonomous organization under MINATOM. The goals of the centers are to: cooperate in the development of technologies associated with nuclear safety in nuclear power engineering. be international centers for the collection of information important for safety and technical improvements in nuclear power engineering. maintain a base for fundamental knowledge needed to design nuclear reactors.The strategic approach that is being used to accomplish these goals is for the two centers to work together to use the resources and the talents of the scientists associated with the US Center and the Russian Center to do collaborative research to improve the safety of Russian-designed nuclear reactors

Crew Exploration Vehicle (CEV) (Orion) Occupant Protection. Part 1; Appendices

Science.gov (United States)

Currie-Gregg, Nancy J.; Gernhardt, Michael L.; Lawrence, Charles; Somers, Jeffrey T.

2016-01-01

Dr. Nancy J. Currie, of the NASA Engineering and Safety Center (NESC), Chief Engineer at Johnson Space Center (JSC), requested an assessment of the Crew Exploration Vehicle (CEV) occupant protection as a result of issues identified by the Constellation Program and Orion Project. The NESC, in collaboration with the Human Research Program (HRP), investigated new methods associated with occupant protection for the Crew Exploration Vehicle (CEV), known as Orion. The primary objective of this assessment was to investigate new methods associated with occupant protection for the CEV, known as Orion, that would ensure the design provided minimal risk to the crew during nominal and contingency landings in an acceptable set of environmental and spacecraft failure conditions. This documents contains the appendices to the NESC assessment report. NASA/TM-2013-217380, Application of the Brinkley Dynamic Response Criterion to Spacecraft Transient Dynamic Events supersedes this document.

Crew Exploration Vehicle (CEV) (Orion) Occupant Protection

Science.gov (United States)

Currie-Gregg, Nancy J.; Gernhardt, Michael L.; Lawrence, Charles; Somers, Jeffrey T.

2016-01-01

Dr. Nancy J. Currie, of the NASA Engineering and Safety Center (NESC), Chief Engineer at Johnson Space Center (JSC), requested an assessment of the Crew Exploration Vehicle (CEV) occupant protection as a result of issues identified by the Constellation Program and Orion Project. The NESC, in collaboration with the Human Research Program (HRP), investigated new methods associated with occupant protection for the Crew Exploration Vehicle (CEV), known as Orion. The primary objective of this assessment was to investigate new methods associated with occupant protection for the CEV, known as Orion, that would ensure the design provided minimal risk to the crew during nominal and contingency landings in an acceptable set of environmental and spacecraft failure conditions. This documents contains the outcome of the NESC assessment. NASA/TM-2013-217380, "Application of the Brinkley Dynamic Response Criterion to Spacecraft Transient Dynamic Events." supercedes this document.

The Max Launch Abort System - Concept, Flight Test, and Evolution

Science.gov (United States)

Gilbert, Michael G.

2014-01-01

The NASA Engineering and Safety Center (NESC) is an independent engineering analysis and test organization providing support across the range of NASA programs. In 2007 NASA was developing the launch escape system for the Orion spacecraft that was evolved from the traditional tower-configuration escape systems used for the historic Mercury and Apollo spacecraft. The NESC was tasked, as a programmatic risk-reduction effort to develop and flight test an alternative to the Orion baseline escape system concept. This project became known as the Max Launch Abort System (MLAS), named in honor of Maxime Faget, the developer of the original Mercury escape system. Over the course of approximately two years the NESC performed conceptual and tradeoff analyses, designed and built full-scale flight test hardware, and conducted a flight test demonstration in July 2009. Since the flight test, the NESC has continued to further develop and refine the MLAS concept.

Independent Peer Review of Communications, Navigation, and Networking re-Configurable Testbed (CoNNeCT) Project Antenna Pointing Subsystem (APS) Integrated Gimbal Assembly (IGA) Structural Analysis

Science.gov (United States)

Raju, Ivatury S.; Larsen, Curtis E.; Pellicciotti, Joseph W.

2010-01-01

Glenn Research Center Chief Engineer's Office requested an independent review of the structural analysis and modeling of the Communications, Navigation, and Networking re-Configurable Testbed (CoNNeCT) Project Antenna Pointing Subsystem (APS) Integrated Gimbal Assembly (IGA) to be conducted by the NASA Engineering and Safety Center (NESC). At this time, the IGA had completed its critical design review (CDR). The assessment was to be a peer review of the NEi-NASTRAN1 model of the APS Antenna, and not a peer review of the design and the analysis that had been completed by the GRC team for CDR. Thus, only a limited amount of information was provided on the structural analysis. However, the NESC team had difficulty separating analysis concerns from modeling issues. The team studied the NASTRAN model, but did not fully investigate how the model was used by the CoNNeCT Project and how the Project was interpreting the results. The team's findings, observations, and NESC recommendations are contained in this report.

Nuclear safety research collaborations between the U.S. and Russian Federation International Nuclear Safety Centers

International Nuclear Information System (INIS)

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

2000-01-01

The Russian Federation Ministry for Atomic Energy (MINATOM) and the US Department of Energy (USDOE) have formed International Nuclear Safety Centers to collaborate on nuclear safety research. USDOE established the US Center (ISINSC) at Argonne National Laboratory (ANL) in October 1995. MINATOM established the Russian Center (RINSC) at the Research and Development Institute of Power Engineering (RDIPE) in Moscow in July 1996. In April 1998 the Russian center became a semi-independent, autonomous organization under MINATOM. The goals of the center are to: Cooperate in the development of technologies associated with nuclear safety in nuclear power engineering; Be international centers for the collection of information important for safety and technical improvements in nuclear power engineering; and Maintain a base for fundamental knowledge needed to design nuclear reactors. The strategic approach is being used to accomplish these goals is for the two centers to work together to use the resources and the talents of the scientists associated with the US Center and the Russian Center to do collaborative research to improve the safety of Russian-designed nuclear reactors. The two centers started conducting joint research and development projects in January 1997. Since that time the following ten joint projects have been initiated: INSC databases--web server and computing center; Coupled codes--Neutronic and thermal-hydraulic; Severe accident management for Soviet-designed reactors; Transient management and advanced control; Survey of relevant nuclear safety research facilities in the Russian Federation; Computer code validation for transient analysis of VVER and RBMK reactors; Advanced structural analysis; Development of a nuclear safety research and development plan for MINATOM; Properties and applications of heavy liquid metal coolants; and Material properties measurement and assessment. Currently, there is activity in eight of these projects. Details on each of these

Center for Maritime Safety and Health Studies

Data.gov (United States)

Federal Laboratory Consortium — Established in November 2015, the Center for Maritime Safety and Health Studies (CMSHS) promotes safety and health for all maritime workers, including those employed...

76 FR 39811 - International Center for Technology Assessment and the Center for Food Safety; Noxious Weed...

Science.gov (United States)

2011-07-07

... dated July 18, 2002, the International Center for Technology Assessment and the Center for Food Safety... Inspection Service [Docket No. APHIS-2011-0081] International Center for Technology Assessment and the Center for Food Safety; Noxious Weed Status of Kentucky Bluegrass Genetically Engineered for Herbicide...

External Tank Liquid Hydrogen (LH2) Prepress Regression Analysis Independent Review Technical Consultation Report

Science.gov (United States)

Parsons, Vickie s.

2009-01-01

The request to conduct an independent review of regression models, developed for determining the expected Launch Commit Criteria (LCC) External Tank (ET)-04 cycle count for the Space Shuttle ET tanking process, was submitted to the NASA Engineering and Safety Center NESC on September 20, 2005. The NESC team performed an independent review of regression models documented in Prepress Regression Analysis, Tom Clark and Angela Krenn, 10/27/05. This consultation consisted of a peer review by statistical experts of the proposed regression models provided in the Prepress Regression Analysis. This document is the consultation's final report.

Center for Food Safety and Applied Nutrition

Data.gov (United States)

Federal Laboratory Consortium — The Center for Food Safety and Applied Nutrition, known as CFSAN, is one of six product-oriented centers, in addition to a nationwide field force, that carry out the...

Check-Cases for Verification of 6-Degree-of-Freedom Flight Vehicle Simulations. Volume 2; Appendices

Science.gov (United States)

Murri, Daniel G.; Jackson, E. Bruce; Shelton, Robert O.

2015-01-01

This NASA Engineering and Safety Center (NESC) assessment was established to develop a set of time histories for the flight behavior of increasingly complex example aerospacecraft that could be used to partially validate various simulation frameworks. The assessment was conducted by representatives from several NASA Centers and an open-source simulation project. This document contains details on models, implementation, and results.

Flight Testing of the Space Launch System (SLS) Adaptive Augmenting Control (AAC) Algorithm on an F/A-18

Science.gov (United States)

Dennehy, Cornelius J.; VanZwieten, Tannen S.; Hanson, Curtis E.; Wall, John H.; Miller, Chris J.; Gilligan, Eric T.; Orr, Jeb S.

2014-01-01

The Marshall Space Flight Center (MSFC) Flight Mechanics and Analysis Division developed an adaptive augmenting control (AAC) algorithm for launch vehicles that improves robustness and performance on an as-needed basis by adapting a classical control algorithm to unexpected environments or variations in vehicle dynamics. This was baselined as part of the Space Launch System (SLS) flight control system. The NASA Engineering and Safety Center (NESC) was asked to partner with the SLS Program and the Space Technology Mission Directorate (STMD) Game Changing Development Program (GCDP) to flight test the AAC algorithm on a manned aircraft that can achieve a high level of dynamic similarity to a launch vehicle and raise the technology readiness of the algorithm early in the program. This document reports the outcome of the NESC assessment.

Space Shuttle Program (SSP) Orbiter Main Propulsion System (MPS) Gaseous Hydrogen (GH2) Flow Control Valve (FCV) Poppet Eddy Current (EC) Inspection Probability of Detection (POD) Study. Volume 1

Science.gov (United States)

Piascik, Robert S.; Prosser, William H.

2011-01-01

The Director of the NASA Engineering and Safety Center (NESC), requested an independent assessment of the anomalous gaseous hydrogen (GH2) flow incident on the Space Shuttle Program (SSP) Orbiter Vehicle (OV)-105 during the Space Transportation System (STS)-126 mission. The main propulsion system (MPS) engine #2 GH2 flow control valve (FCV) LV-57 transition from low towards high flow position without being commanded. Post-flight examination revealed that the FCV LV-57 poppet had experienced a fatigue failure that liberated a section of the poppet flange. The NESC assessment provided a peer review of the computational fluid dynamics (CFD), stress analysis, and impact testing. A probability of detection (POD) study was requested by the SSP Orbiter Project for the eddy current (EC) nondestructive evaluation (NDE) techniques that were developed to inspect the flight FCV poppets. This report contains the findings and recommendations from the NESC assessment.

Evaluation of Agency Non-Code Layered Pressure Vessels (LPVs) . Volume 2; Appendices

Science.gov (United States)

Prosser, William H.

2014-01-01

In coordination with the Office of Safety and Mission Assurance and the respective Center Pressure System Managers (PSMs), the NASA Engineering and Safety Center (NESC) was requested to formulate a consensus draft proposal for the development of additional testing and analysis methods to establish the technical validity, and any limitation thereof, for the continued safe operation of facility non-code layered pressure vessels. The PSMs from each NASA Center were asked to participate as part of the assessment team by providing, collecting, and reviewing data regarding current operations of these vessels. This document contains the appendices to the main report.

The role of the Joint Research Centre from the European Commission in the European Structural Integrity Networks AMES, ENIQ and NESC

International Nuclear Information System (INIS)

Estorff, U. von; Torronen, K.

1999-01-01

Due to the reduction in many countries of the research budget for nuclear safety several European institutions and organisations and the Institute for Advanced Materials (IAM) of the Joint Research Centre (JRC) of the European Commission (EC) have developed co-operative programmes now organised into 'Networks' for mutual benefit. They include utilities, engineering companies, research and development (R and D) laboratories and regulatory bodies. These Networks are all organised and managed in a similar way, i.e. like the successful Programme for the Inspection of Steel Components (PISC). The IAM plays the role of Operating Agent, Reference Laboratory and Network Manager of these Networks: European Network on Ageing Materials Evaluation and Studies (AMES), European Network for Inspection Qualification (ENIQ) and Network for Evaluating Steel Components (NESC), each of them dealing with a specific aspect of fitness for purpose of materials in structural components. This article will describe how the network organisation works, which was the positive experience from the past, why the networks are a tool for integrating fragmented research in Europe and how they fit into the mission of the JRC and therefore follow the EC policy. (orig.)

Inspection of the Math Model Tools for On-Orbit Assessment of Impact Damage Report. Version 1.0

Science.gov (United States)

Harris, Charles E.; Raju, Ivatury S.; Piascik, Robert S.; Kramer White, Julie; Labbe, Steve G.; Rotter, Hank A.

2005-01-01

In Spring of 2005, the NASA Engineering Safety Center (NESC) was engaged by the Space Shuttle Program (SSP) to peer review the suite of analytical tools being developed to support the determination of impact and damage tolerance of the Orbiter Thermal Protection Systems (TPS). The NESC formed an independent review team with the core disciplines of materials, flight sciences, structures, mechanical analysis and thermal analysis. The Math Model Tools reviewed included damage prediction and stress analysis, aeroheating analysis, and thermal analysis tools. Some tools are physics-based and other tools are empirically-derived. Each tool was created for a specific use and timeframe, including certification, real-time pre-launch assessments, and real-time on-orbit assessments. The tools are used together in an integrated strategy for assessing the ramifications of impact damage to tile and RCC. The NESC teams conducted a peer review of the engineering data package for each Math Model Tool. This report contains the summary of the team observations and recommendations from these reviews.

Inspection of the Math Model Tools for On-Orbit Assessment of Impact Damage Report

Science.gov (United States)

Harris, Charles E.; Raju, Ivatury S.; Piascik, Robert S> KramerWhite, Julie A.; KramerWhite, Julie A.; Labbe, Steve G.; Rotter, Hank A.

2007-01-01

In Spring of 2005, the NASA Engineering Safety Center (NESC) was engaged by the Space Shuttle Program (SSP) to peer review the suite of analytical tools being developed to support the determination of impact and damage tolerance of the Orbiter Thermal Protection Systems (TPS). The NESC formed an independent review team with the core disciplines of materials, flight sciences, structures, mechanical analysis and thermal analysis. The Math Model Tools reviewed included damage prediction and stress analysis, aeroheating analysis, and thermal analysis tools. Some tools are physics-based and other tools are empirically-derived. Each tool was created for a specific use and timeframe, including certification, real-time pre-launch assessments. In addition, the tools are used together in an integrated strategy for assessing the ramifications of impact damage to tile and RCC. The NESC teams conducted a peer review of the engineering data package for each Math Model Tool. This report contains the summary of the team observations and recommendations from these reviews.

Probing Aircraft Flight Test Hazard Mitigation for the Alternative Fuel Effects on Contrails & Cruise Emissions (ACCESS) Research Team

Science.gov (United States)

Kelly, Michael J.

2013-01-01

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

The first symposium of Research Center for Radiation Safety, NIRS. Perspective of future studies of radiation safety

International Nuclear Information System (INIS)

Shimo, Michikuni

2002-03-01

This paper summarizes presentations given in the title symposium, held at the Conference Room of National Institute of Radiological Sciences (NIRS) on November 29 and 30, 2001. Contained are Introductory remarks: Basic presentations concerning exposure dose in man; Environmental levels of radiation and radioactivity, environmental radon level and exposure dose, and radiation levels in the specific environment (like in the aircraft): Special lecture (biological effects given by space environment) concerning various needs for studies of radiation safety; Requirement for open investigations, from the view of utilization, research and development of atomic energy, from the clinical aspect, and from the epidemiological aspect: Special lecture (safety in utilization of atomic energy and radiation-Activities of Nuclear Safety Commission of Japan) concerning present state and perspective of studies of radiation safety; Safety of radiation and studies of biological effects of radiation-perspective, and radiation protection and radiation safety studies: Studies in the Research Center for Radiation Safety; Summary of studies in the center, studies of the biological effects of neutron beam, carcinogenesis by radiation and living environmental factors-complicated effects, and studies of hereditary effects: Panel discussion (future direction of studies of radiation safety for the purpose of the center's direction): and concluding remarks. (N.I.)

International nuclear safety center database on material properties

International Nuclear Information System (INIS)

Fink, J.K.

1996-01-01

International nuclear safety center database on the following material properties is described: fuel, cladding,absorbers, moderators, structural materials, coolants, concretes, liquid mixtures, uranium dioxide

Introduction to Nuclear Power Plant Environment Supervisory Committee

International Nuclear Information System (INIS)

Lee, Byung Il

2008-01-01

In Korea, there are five nuclear power plant sites, located at Yongkwang, Kori, Shin Kori, Uljin, and Wolsong. Each administrative district has its own NESC (Nuclear plant Environment Public Supervisory Committee) which consists of a steering committee and a center. The purpose of NESC is to let the public survey and inspect nuclear plant environment and then improve a clarity and confidence in plant construction and operation by themselves. In order to understand the situation of NESC and explore ways toward a better role of NESC, in this paper we try to enumerate a few major facts related to a current status of NESC. As a summary, there must be a great role of NESC in the relationship between the residents, a nuclear industry company and the related government division. Furthermore, NESC would certainly do its role for all sides provided that more strong definition of NESC in law, more financial supporting and more philosophical speculation for the being of NESC

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

International Nuclear Information System (INIS)

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

1998-01-01

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

Stennis Space Center observes 2009 Safety and Health Day

Science.gov (United States)

2009-01-01

Sue Smith, a medical clinic employee at NASA's John C. Stennis Space Center, takes the temperature of colleague Karen Badon during 2009 Safety and Health Day activities Oct. 22. Safety Day activities included speakers, informational sessions and a number of displays on safety and health issues. Astronaut Dominic Gorie also visited the south Mississippi rocket engine testing facility during the day to address employees and present several Silver Snoopy awards for outstanding contributions to flight safety and mission success. The activities were part of an ongoing safety and health emphasis at Stennis.

International Nuclear Safety Center (INSC) database

International Nuclear Information System (INIS)

Sofu, T.; Ley, H.; Turski, R.B.

1997-01-01

As an integral part of DOE's International Nuclear Safety Center (INSC) at Argonne National Laboratory, the INSC Database has been established to provide an interactively accessible information resource for the world's nuclear facilities and to promote free and open exchange of nuclear safety information among nations. The INSC Database is a comprehensive resource database aimed at a scope and level of detail suitable for safety analysis and risk evaluation for the world's nuclear power plants and facilities. It also provides an electronic forum for international collaborative safety research for the Department of Energy and its international partners. The database is intended to provide plant design information, material properties, computational tools, and results of safety analysis. Initial emphasis in data gathering is given to Soviet-designed reactors in Russia, the former Soviet Union, and Eastern Europe. The implementation is performed under the Oracle database management system, and the World Wide Web is used to serve as the access path for remote users. An interface between the Oracle database and the Web server is established through a custom designed Web-Oracle gateway which is used mainly to perform queries on the stored data in the database tables

International Space Station Lithium-Ion Main Battery Thermal Runaway Propagation Test

Science.gov (United States)

Dalton, Penni J.; North, Tim

2017-01-01

In 2010, the ISS Program began the development of Lithium-Ion (Li-Ion) batteries to replace the aging Ni-H2 batteries on the primary Electric Power System (EPS). After the Boeing 787 Li-Ion battery fires, the NASA Engineering and Safety Center (NESC) Power Technical Discipline Team was tasked by ISS to investigate the possibility of Thermal Runaway Propagation (TRP) in all Li-Ion batteries used on the ISS. As part of that investigation, NESC funded a TRP test of an ISS EPS non-flight Li-Ion battery. The test was performed at NASA White Sands Test Facility in October 2016. This paper will discuss the work leading up to the test, the design of the test article, and the test results.

AMES, NESC and ENIQ: European networks in the field of structural integrity involving NDE and inspection effectiveness assessment

International Nuclear Information System (INIS)

Crutzen, S.; Hurst, R.; Debarberis, L.; Lemaitre, P.; Eriksen, B.

1999-01-01

Three European networks on structural integrity aspects of ageing nuclear components are presently managed by the Institute for Advanced Materials of the Joint Research Centre of the European Commission: AMES (Ageing Materials Evaluation and Studies), ENIQ (European Network for Inspection Qualification) and NESC (Network for Evaluating Steel Components). All three networks involve actions, which aim at the effectiveness and reliability assessment of NDE techniques and of inspection procedures: Either for materials damage detection and characterisation or for defect detection and evaluation. This paper is describing very generally the objectives of the three networks and is then concentrating on the results obtained in ENIQ, which are relevant with ISI and regulatory issues. (orig./DGE)

Nuclear Research Center Karlsruhe, Central Safety Department. Annual report 1992

International Nuclear Information System (INIS)

Koelzer, W.

1993-05-01

The Central Safety Department is responsible for handling all problems of radiation protection, safety and security of the institutes and departments of the Karlsruhe Nuclear Research Center, for waste water activity measurements and environmental monitoring of the whole area of the Center, and for research and development work mainly focusing on nuclear safety and radiation protection measures. The research and development work concentrates on the following aspects: Physical and chemical behavior of trace elements in the environment, biophysics of multicellular systems, behavior of tritium in the air/soil-plant system, improvement in radiation protection measurement and personnel dosimetry. This report gives details of the different duties, indicates the results of 1992 routine tasks and reports about results of investigations and developments of the working groups of the Department. The reader is referred to the English translation of Chapter 1 describing the duties and organization of the Central Safety Department. (orig.) [de

Karlsruhe Nuclear Research Center, Central Safety Department. Annual report 1993

International Nuclear Information System (INIS)

Koelzer, W.

1994-04-01

The Central Safety Department is responsible for handling all tasks of radiation protection, safety and security of the institutes and departments of the Karlsruhe Nuclear Research Center, for waste water activity measurements and environmental monitoring of the whole area of the Center, and for research and development work mainly focusing on nuclear safety and radiation protection measures. The research and development work concentrates on the following aspects: behavior of trace elements in the environment and decontamination of soil, behavior of tritium in the air/soil-plant system, improvement in radiation protection measurements and personnel dosimetry. This report gives details of the different duties, indicates the results of 1993 routine tasks and reports about results of investigations and developments of the working groups of the Department. (orig.) [de

NASA Aerospace Flight Battery Program: Generic Safety, Handling and Qualification Guidelines for Lithium-Ion (Li-Ion) Batteries; Availability of Source Materials for Lithium-Ion (Li-Ion) Batteries; Maintaining Technical Communications Related to Aerospace Batteries (NASA Aerospace Battery Workshop). Volume 1, Part 1

Science.gov (United States)

Manzo, Michelle A.; Brewer, Jeffrey C.; Bugga, Ratnakumar V.; Darcy, Eric C.; Jeevarajan, Judith A.; McKissock, Barbara I.; Schmitz, Paul C.

2010-01-01

This NASA Aerospace Flight Battery Systems Working Group was chartered within the NASA Engineering and Safety Center (NESC). The Battery Working Group was tasked to complete tasks and to propose proactive work to address battery related, agency-wide issues on an annual basis. In its first year of operation, this proactive program addressed various aspects of the validation and verification of aerospace battery systems for NASA missions. Studies were performed, issues were discussed and in many cases, test programs were executed to generate recommendations and guidelines to reduce risk associated with various aspects of implementing battery technology in the aerospace industry. This document contains Part 1 - Volume I: Generic Safety, Handling and Qualification Guidelines for Lithium-Ion (Li-Ion) Batteries, Availability of Source Materials for Lithium-Ion (Li-Ion) Batteries, and Maintaining Technical Communications Related to Aerospace Batteries (NASA Aerospace Battery Workshop).

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

Science.gov (United States)

Kelly, Michael J.

2013-01-01

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

National Resource Center for Health and Safety in Child Care and Early Education

Science.gov (United States)

... National Resource Center for Health and Safety in Child Care and Early Education (NRC) at the University of Colorado College of ... National Resource Center for Health and Safety in Child Care and Early Education Email: info@NRCKids.org Please read our disclaimer ...

Pretest analysis of the NESC-1 spinning cylinder experiment

Energy Technology Data Exchange (ETDEWEB)

Sattari-Far, Iradj [SAQ Inspection Ltd., Stockholm (Sweden)

1997-09-01

This report presents defect assessment results from a final pre-test analysis of the NESC-1 spinning cylinder based on the NDE defect definitions and the determined loading conditions. The analysis covers fracture assessments of a subclad and a surface breaking crack. Three-dimensional elastic-plastic finite element calculations, considering the crack-tip constraint, are employed in the assessment. Also performed are sensitivity studies to demonstrate how different affecting parameters, especially the cladding residual stresses, impact the crack driving force. It is found for both the surface and the subclad crack that the situations in the cladding and the deepest point of the crack front are far from critical for cleavage future. The results of the analysis indicate that a limited amount of ductile crack growth can occur along the crack front in the HAZ and adjacent base material. Cleavage fracture events can be expected in the HAZ. The results also show substantial loss of crack-tip constraint in the HAZ compared with the SSY solutions. Providing that the constraint and warm prestressing effects do not substantially affect the situations in HAZ, one can expect cleavage fracture to occur in the HAZ at a time around four minutes into the transient. From the sensitivity studies, it is observed that uncertainties due to different assumptions in the analysis, for instance crack depth and cladding residual stresses, influence the assessment results less than uncertainties of the fracture toughness properties of the materials. To perform a precise evaluation, fracture toughness data of the HAZ material corresponding to the actual constraint conditions are needed. 29 refs, 30 figs, 3 tabs.

Performance Characterization of Loctite (Registered Trademark) 242 and 271 Liquid Locking Compounds (LLCs) as a Secondary Locking Feature for International Space Station (ISS) Fasteners

Science.gov (United States)

Dube, Michael J.; Gamwell, Wayne R.

2011-01-01

Several International Space Station (ISS) hardware components use Loctite (and other polymer based liquid locking compounds (LLCs)) as a means of meeting the secondary (redundant) locking feature requirement for fasteners. The primary locking method is the fastener preload, with the application of the Loctite compound which when cured is intended to resist preload reduction. The reliability of these compounds has been questioned due to a number of failures during ground testing. The ISS Program Manager requested the NASA Engineering and Safety Center (NESC) to characterize and quantify sensitivities of Loctite being used as a secondary locking feature. The findings and recommendations provided in this investigation apply to the anaerobic LLCs Loctite 242 and 271. No other anaerobic LLCs were evaluated for this investigation. This document contains the findings and recommendations of the NESC investigation

NASA Aerospace Flight Battery Program: Generic Safety, Handling and Qualification Guidelines for Lithium-Ion (Li-Ion) Batteries; Availability of Source Materials for Lithium-Ion (Li-Ion) Batteries; Maintaining Technical Communications Related to Aerospace Batteries (NASA Aerospace Battery Workshop). Volume 2, Part 1

Science.gov (United States)

Manzo, Michelle A.; Brewer, Jeffrey C.; Bugga, Ratnakumar V.; Darcy, Eric C.; Jeevarajan, Judith A.; McKissock, Barbara I.; Schmitz, Paul C.

2010-01-01

This NASA Aerospace Flight Battery Systems Working Group was chartered within the NASA Engineering and Safety Center (NESC). The Battery Working Group was tasked to complete tasks and to propose proactive work to address battery related, agency-wide issues on an annual basis. In its first year of operation, this proactive program addressed various aspects of the validation and verification of aerospace battery systems for NASA missions. Studies were performed, issues were discussed and in many cases, test programs were executed to generate recommendations and guidelines to reduce risk associated with various aspects of implementing battery technology in the aerospace industry. This report contains the Appendices to the findings from the first year of the program's operations.

Probabilistic Requirements (Partial) Verification Methods Best Practices Improvement. Variables Acceptance Sampling Calculators: Derivations and Verification of Plans. Volume 1

Science.gov (United States)

Johnson, Kenneth L.; White, K, Preston, Jr.

2012-01-01

The NASA Engineering and Safety Center was requested to improve on the Best Practices document produced for the NESC assessment, Verification of Probabilistic Requirements for the Constellation Program, by giving a recommended procedure for using acceptance sampling by variables techniques. This recommended procedure would be used as an alternative to the potentially resource-intensive acceptance sampling by attributes method given in the document. This document contains the outcome of the assessment.

Criticality Safety Information Resource Center Web portal: www.csirc.net

International Nuclear Information System (INIS)

Harmon, C.D. II; Jones, T.

2000-01-01

The Nuclear Criticality Safety Group (ESH-6) at Los Alamos National Laboratory (LANL) is in the process of collecting and archiving historical and technical information related to nuclear criticality safety from LANL and other facilities. In an ongoing effort, this information is being made available via the Criticality Safety Information Resource Center (CSIRC) web site, which is hosted and maintained by ESH-6 staff. Recently, the CSIRC Web site was recreated as a Web portal that provides the criticality safety community with much more than just archived data

Aube storage center. Information report on nuclear safety and radiation protection 2015

International Nuclear Information System (INIS)

2016-01-01

The National Radioactive Waste Management Agency (Andra), was established by the December 1991 Waste Act as a public body in charge of the long-term management of all radioactive waste, under the supervision of the Ministry of Ecology, Energy, Sustainable Development and the Sea (formerly the Ministry of Industry and the Ministry of Environment), and the Ministry of Research. The Andra operates two storage centers in the Aube region (France): the center for short-lived low- and intermediate-level wastes, and the center for very-low-level radioactive wastes. This document is the 2015 activity report of the center for short-lived low- and intermediate-level wastes. It presents a review of the activities of the center: presentation of the installations, safety and radiation protection, security, events or incidents, environmental monitoring and effluents, wastes management, public information, recommendations of the Health and safety Committee (CHSCT)

Aube storage center. Information report on nuclear safety and radiation protection 2016

International Nuclear Information System (INIS)

2017-01-01

The National Radioactive Waste Management Agency (Andra), was established by the December 1991 Waste Act as a public body in charge of the long-term management of all radioactive waste, under the supervision of the Ministry of Ecology, Energy, Sustainable Development and the Sea (formerly the Ministry of Industry and the Ministry of Environment), and the Ministry of Research. The Andra operates two storage centers in the Aube region (France): the center for short-lived low- and intermediate-level wastes, and the center for very-low-level radioactive wastes. This document is the 2016 activity report of the center for short-lived low- and intermediate-level wastes. It presents a review of the activities of the center: presentation of the installations, safety and radiation protection, security, events or incidents, environmental monitoring and effluents, wastes management, public information, recommendations of the Health and safety Committee (CHSCT)

Computer-Aided Design (CAD) Tools to Support the Human Factors Design Teams

Science.gov (United States)

Null, Cynthia H.; Jackson, Mariea D.; Perry, Trey; Quick, Jason C.; Stokes, Jack W.

2014-01-01

The scope of this assessment was to develop a library of basic 1-Gravity (G) human posture and motion elements used to construct complex virtual simulations of ground processing and maintenance tasks for spaceflight vehicles, including launch vehicles, crewed spacecraft, robotic spacecraft, satellites, and other payloads. The report herein describes the task, its purpose, performance, findings, NASA Engineering and Safety Center (NESC) recommendations, and conclusions in the definition and assemblage of the postures and motions database (PMD).

Deep Impact Delta II Launch Vehicle Cracked Thick Film Coating on Electronic Packages Technical Consultation Report

Science.gov (United States)

Cameron, Kenneth D.; Kichak, Robert A.; Piascik, Robert S.; Leidecker, Henning W.; Wilson, Timmy R.

2009-01-01

The Deep Impact spacecraft was launched on a Boeing Delta II rocket from Cape Canaveral Air Force Station (CCAFS) on January 12, 2005. Prior to the launch, the Director of the Office of Safety and Mission Assurance (OS&MA) requested the NASA Engineering and Safety Center (NESC) lead a team to render an independent opinion on the rationale for flight and the risk code assignments for the hazard of cracked Thick Film Assemblies (TFAs) in the E-packages of the Delta II launch vehicle for the Deep Impact Mission. The results of the evaluation are contained in this report.

Space Shuttle Program (SSP) Orbiter Main Propulsion System (MPS) Gaseous Hydrogen (GH2) Flow Control Valve (FCV) Poppet Eddy Current (EC) Inspection Probability of Detection (POD) Study. Volume 2; Appendices

Science.gov (United States)

Piascik, Robert S.; Prosser, William H.

2011-01-01

The Director of the NASA Engineering and Safety Center (NESC), requested an independent assessment of the anomalous gaseous hydrogen (GH2) flow incident on the Space Shuttle Program (SSP) Orbiter Vehicle (OV)-105 during the Space Transportation System (STS)-126 mission. The main propulsion system (MPS) engine #2 GH2 flow control valve (FCV) LV-57 transition from low towards high flow position without being commanded. Post-flight examination revealed that the FCV LV-57 poppet had experienced a fatigue failure that liberated a section of the poppet flange. The NESC assessment provided a peer review of the computational fluid dynamics (CFD), stress analysis, and impact testing. A probability of detection (POD) study was requested by the SSP Orbiter Project for the eddy current (EC) nondestructive evaluation (NDE) techniques that were developed to inspect the flight FCV poppets. This report contains the Appendices to the main report.

Computerized based training in nuclear safety in the nuclear research center Negev

International Nuclear Information System (INIS)

Ben-Shachar, B.; Krubain, H.; Sberlo, E.

2002-01-01

The Department of Human Resources and Training in the Nuclear Research Center, Negev, in collaboration with the Department of Radiation Protection and Safety used to organize different kinds of training and refresher courses for different aspects of safety in nuclear centers (radiation safety, biological effects of ionizing radiation, industrial safety, fire fighting, emergency procedures, etc.). All radiation workers received a training program of several days in all these subjects, each year. The administrative employees received a shorter training, each second year. The training included only frontal lectures and no quiz or exams were done. No feedback of the employees was received after the training, as well. Recently, a new training program was developed by the NRC-Negev and the CET (Center for Educational Technology), in order to perform the refresher courses. The training includes CBT-s (Computer Based Training), e.g. tutorials and quiz. The tutorial is an interactive course in one subject, including animations, video films and photo stills. The employee gets a simple and clear explanation (including pictures). After each tutorial there is a quiz which includes 7 American style questions. In the following lecture different parts from two of the tutorials used for the refresher courses, will be presented

Annual report 1995 of the Central Safety Department, Research Center Karlsruhe

International Nuclear Information System (INIS)

Koelzer, W.

1996-04-01

The Central Safety Department is responsible for supervising, monitoring and, to some extent, also executing measures of radiation protection, industrial health and safety as well as physical protection and security at and for the institutes and departments of the Karlsruhe Research Center (Forschungszentrum Karlsruhe GmbH), and for monitoring liquid effluents and the environment of all facilities and nuclear installations on the premises of the Research Center. In addition, research and development work is carried out in the fields of behavior of tritium in the air/soil/plant system, tritium balances for nuclear fusion fuel cycles, and assessments of mining and ore dressing spoils. This report gives details of the different duties and reports the results of 1995 routine tasks, investigations and developments of the working groups of the Department. The reader is referred to the English translation of Chapter 1 describing the duties and organization of the Central Safety Department. (orig.) [de

Probabilistic Requirements (Partial) Verification Methods Best Practices Improvement. Variables Acceptance Sampling Calculators: Empirical Testing. Volume 2

Science.gov (United States)

Johnson, Kenneth L.; White, K. Preston, Jr.

2012-01-01

The NASA Engineering and Safety Center was requested to improve on the Best Practices document produced for the NESC assessment, Verification of Probabilistic Requirements for the Constellation Program, by giving a recommended procedure for using acceptance sampling by variables techniques as an alternative to the potentially resource-intensive acceptance sampling by attributes method given in the document. In this paper, the results of empirical tests intended to assess the accuracy of acceptance sampling plan calculators implemented for six variable distributions are presented.

The occupational safety of health professionals working at community and family health centers.

Science.gov (United States)

Ozturk, Havva; Babacan, Elif

2014-10-01

Healthcare professionals encounter many medical risks while providing healthcare services to individuals and the community. Thus, occupational safety studies are very important in health care organizations. They involve studies performed to establish legal, technical, and medical measures that must be taken to prevent employees from sustaining physical or mental damage because of work hazards. This study was conducted to determine if the occupational safety of health personnel at community and family health centers (CHC and FHC) has been achieved. The population of this cross-sectional study comprised 507 nurses, 199 physicians, and 237 other medical personnel working at a total of 18 family health centers (FHC) and community health centers (CHC) in Trabzon, Turkey. The sample consisted of a total of 418 nurses, 156 physicians, and 123 other medical personnel. Sampling method was not used, and the researchers tried to reach the whole population. Data were gathered with the Occupational Safety Scale (OSS) and a questionnaire regarding demographic characteristics and occupational safety. According to the evaluations of all the medical personnel, the mean ± SD of total score of the OSS was 3.57 ± 0.98; of the OSS's subscales, the mean ± SD of the health screening and registry systems was 2.76 ± 1.44, of occupational diseases and problems was 3.04 ± 1.3 and critical fields control was 3.12 ± 1.62. In addition, occupational safety was found more insufficient by nurses (F = 14.18; P occupational safety to be insufficient as related to protective and supportive activities.

Transfusion safety: is this the business of blood centers?

Science.gov (United States)

Slapak, Colleen; Fredrich, Nanci; Wagner, Jeffrey

2011-12-01

ATSO is in a unique position to break down organizational silos between hospitals and blood centers through the development of a collaborative relationship between the two entities. Use of the TSO as blood center staff centralizes the role into a consultative position thereby retaining the independence of the hospitals. The TSO position then becomes a value-added service offered by the blood center designed to supplement processes within the hospital.Whether the TSO is based in the hospital or the blood center, improvements are gained through appropriate utilization of blood components, reductions in hospital costs, ongoing education of hospital staff involved in transfusion practice, and increased availability of blood products within the community. Implementation and standardization of best practice processes for ordering and administration of blood products developed by TSOs leads to improved patient outcomes. As a liaison between hospitals and blood centers, the TSO integrates the mutual goal of transfusion safety: the provision of the safest blood product to the right patient at the right time for the right reason.

Spin Forming Aluminum Crew Module (CM) Metallic Aft Pressure Vessel Bulkhead (APVBH) - Phase II

Science.gov (United States)

Hoffman, Eric K.; Domack, Marcia S.; Torres, Pablo D.; McGill, Preston B.; Tayon, Wesley A.; Bennett, Jay E.; Murphy, Joseph T.

2015-01-01

The principal focus of this project was to assist the Multi-Purpose Crew Vehicle (MPCV) Program in developing a spin forming fabrication process for manufacture of the Orion crew module (CM) aft pressure vessel bulkhead. The spin forming process will enable a single piece aluminum (Al) alloy 2219 aft bulkhead resulting in the elimination of the current multiple piece welded construction, simplify CM fabrication, and lead to an enhanced design. Phase I (NASA TM-2014-218163 (1)) of this assessment explored spin forming the single-piece CM forward pressure vessel bulkhead. The Orion MPCV Program and Lockheed Martin (LM) recently made two critical decisions relative to the NESC Phase I work scope: (1) LM selected the spin forming process to manufacture a single-piece aft bulkhead for the Orion CM, and (2) the aft bulkhead will be manufactured from Al 2219. Based on the Program's new emphasis related to the spin forming process, the NESC was asked to conduct a Phase II assessment to assist in the LM manufacture of the aft bulkhead and to conduct a feasibility study into spin forming the Orion CM cone. This activity was approved on June 19, 2013. Dr. Robert Piascik, NASA Technical Fellow for Materials at the Langley Research Center (LaRC), was selected to lead this assessment. The project plan was approved by the NASA Engineering and Safety Center (NESC) Review Board (NRB) on July 18, 2013. The primary stakeholders for this assessment were the NASA and LM MPCV Program offices. Additional benefactors are commercial launch providers developing CM concepts.

Maximum Expected Wall Heat Flux and Maximum Pressure After Sudden Loss of Vacuum Insulation on the Stratospheric Observatory for Infrared Astronomy (SOFIA) Liquid Helium (LHe) Dewars

Science.gov (United States)

Ungar, Eugene K.

2014-01-01

The aircraft-based Stratospheric Observatory for Infrared Astronomy (SOFIA) is a platform for multiple infrared observation experiments. The experiments carry sensors cooled to liquid helium (LHe) temperatures. A question arose regarding the heat input and peak pressure that would result from a sudden loss of the dewar vacuum insulation. Owing to concerns about the adequacy of dewar pressure relief in the event of a sudden loss of the dewar vacuum insulation, the SOFIA Program engaged the NASA Engineering and Safety Center (NESC). This report summarizes and assesses the experiments that have been performed to measure the heat flux into LHe dewars following a sudden vacuum insulation failure, describes the physical limits of heat input to the dewar, and provides an NESC recommendation for the wall heat flux that should be used to assess the sudden loss of vacuum insulation case. This report also assesses the methodology used by the SOFIA Program to predict the maximum pressure that would occur following a loss of vacuum event.

Business of Nuclear Safety Analysis Office, Nuclear Technology Test Center

International Nuclear Information System (INIS)

Hayakawa, Masahiko

1981-01-01

The Nuclear Technology Test Center established the Nuclear Safety Analysis Office to execute newly the works concerning nuclear safety analysis in addition to the works related to the proving tests of nuclear machinery and equipments. The regulations for the Nuclear Safety Analysis Office concerning its organization, business and others were specially decided, and it started the business formally in August, 1980. It is a most important subject to secure the safety of nuclear facilities in nuclear fuel cycle as the premise of developing atomic energy. In Japan, the strict regulation of safety is executed by the government at each stage of the installation, construction, operation and maintenance of nuclear facilities, based on the responsibility for the security of installers themselves. The Nuclear Safety Analysis Office was established as the special organ to help the safety examination related to the installation of nuclear power stations and others by the government. It improves and puts in order the safety analysis codes required for the cross checking in the safety examination, and carries out safety analysis calculation. It is operated by the cooperation of the Science and Technology Agency and the Agency of Natural Resources and Energy. The purpose of establishment, the operation and the business of the Nuclear Safety Analysis Office, the plan of improving and putting in order of analysis codes, and the state of the similar organs in foreign countries are described. (Kako, I.)

Assess/Mitigate Risk through the Use of Computer-Aided Software Engineering (CASE) Tools

Science.gov (United States)

Aguilar, Michael L.

2013-01-01

The NASA Engineering and Safety Center (NESC) was requested to perform an independent assessment of the mitigation of the Constellation Program (CxP) Risk 4421 through the use of computer-aided software engineering (CASE) tools. With the cancellation of the CxP, the assessment goals were modified to capture lessons learned and best practices in the use of CASE tools. The assessment goal was to prepare the next program for the use of these CASE tools. The outcome of the assessment is contained in this document.

Empirical Model Development for Predicting Shock Response on Composite Materials Subjected to Pyroshock Loading

Science.gov (United States)

Gentz, Steven J.; Ordway, David O; Parsons, David S.; Garrison, Craig M.; Rodgers, C. Steven; Collins, Brian W.

2015-01-01

The NASA Engineering and Safety Center (NESC) received a request to develop an analysis model based on both frequency response and wave propagation analyses for predicting shock response spectrum (SRS) on composite materials subjected to pyroshock loading. The model would account for near-field environment (approx. 9 inches from the source) dominated by direct wave propagation, mid-field environment (approx. 2 feet from the source) characterized by wave propagation and structural resonances, and far-field environment dominated by lower frequency bending waves in the structure. This report documents the outcome of the assessment.

Empirical Model Development for Predicting Shock Response on Composite Materials Subjected to Pyroshock Loading. Volume 2, Part 1; Appendices

Science.gov (United States)

Gentz, Steven J.; Ordway, David O.; Parsons, David S.; Garrison, Craig M.; Rodgers, C. Steven; Collins, Brian W.

2015-01-01

The NASA Engineering and Safety Center (NESC) received a request to develop an analysis model based on both frequency response and wave propagation analyses for predicting shock response spectrum (SRS) on composite materials subjected to pyroshock loading. The model would account for near-field environment (approximately 9 inches from the source) dominated by direct wave propagation, mid-field environment (approximately 2 feet from the source) characterized by wave propagation and structural resonances, and far-field environment dominated by lower frequency bending waves in the structure. This document contains appendices to the Volume I report.

The Criticality Safety Information Resource Center (CSIRC) at Los Alamos National Laboratory

International Nuclear Information System (INIS)

Henderson, B.D.; Meade, R.A.; Pruvost, N.L.

1999-01-01

The Criticality Safety Information Resource Center (CSIRC) at Los Alamos National Laboratory (LANL) is a program jointly funded by the U.S. Department of Energy (DOE) and the U.S. Nuclear Regulatory Commission (NRC) in conjunction with the Defense Nuclear Facilities Safety Board (DNFSB) Recommendation 97-2. The goal of CSIRC is to preserve primary criticality safety documentation from U.S. critical experimental sites and to make this information available for the benefit of the technical community. Progress in archiving criticality safety primary documents at the LANL archives as well as efforts to make this information available to researchers are discussed. The CSIRC project has a natural linkage to the International Criticality Safety Benchmark Evaluation Project (ICSBEP). This paper raises the possibility that the CSIRC project will evolve in a fashion similar to the ICSBEP. Exploring the implications of linking the CSIRC to the international criticality safety community is the motivation for this paper

Safety and Environment- Masterplan 2020 of DLR's Rocket Test Center Lampoldhausen

Science.gov (United States)

Haberzettl, Andreas; Dommers, Michael

2013-09-01

The German Aerospace Center DLR is the German research institute with approximately 7000 employees in 16 domestic locations. Among the research priorities of the German Aerospace Center DLR includes aerospace, energy and transport. DLR is institutionally supported by federal and state governments.Next funding sources arise in the context of third-party funds business (contract research and public contracts and subsidiaries). Main activities of the test center Lampoldshausen are testing of ARIANE's main and upper stage engines in the frame of ESA contracts.In the last years the test center of the DLR in Lampoldshausen has grown strongly, so that the number of employees is actually of about 230. The testing department is mainly responsible for rocket combustion testing according to customer requirements.Two kinds of test facilities are operated, sea level test benches and the altitude simulation test facilities.In addition to the DLR's growth also the activities of the industrial partner ASTRIUM has been elevated so that actually nearly 600 employees are present on site Lampoldshausen.The management of the site in relation to safety and security requires special measures with special respect to the presence of more people inside the testing area in order to guarantee trouble-free and safe experimental operation onsite the DLR's test plants. In order to meet with the future needs of continuing growth, the security and safety requirements have to be adopted.This report gives comprehensive outlook information about future possible scenarios of our coming tasks.Main driving force for future requests is the evolution of the rocket ARIANE. The testing of the new upper stage test facility for ARIANE 5 midlife evolution has been started. A new test position P5.2 is foreseen to perform the qualification of the new upper stage with the VINCI engine. This project will be very complex, in parallel running operation processes will require special procedures related to the overall

John M. Eisenberg Patient Safety Awards. System innovation: Veterans Health Administration National Center for Patient Safety.

Science.gov (United States)

Heget, Jeffrey R; Bagian, James P; Lee, Caryl Z; Gosbee, John W

2002-12-01

In 1998 the Veterans Health Administration (VHA) created the National Center for Patient Safety (NCPS) to lead the effort to reduce adverse events and close calls systemwide. NCPS's aim is to foster a culture of safety in the Department of Veterans Affairs (VA) by developing and providing patient safety programs and delivering standardized tools, methods, and initiatives to the 163 VA facilities. To create a system-oriented approach to patient safety, NCPS looked for models in fields such as aviation, nuclear power, human factors, and safety engineering. Core concepts included a non-punitive approach to patient safety activities that emphasizes systems-based learning, the active seeking out of close calls, which are viewed as opportunities for learning and investigation, and the use of interdisciplinary teams to investigate close calls and adverse events through a root cause analysis (RCA) process. Participation by VA facilities and networks was voluntary. NCPS has always aimed to develop a program that would be applicable both within the VA and beyond. NCPS's full patient safety program was tested and implemented throughout the VA system from November 1999 to August 2000. Program components included an RCA system for use by caregivers at the front line, a system for the aggregate review of RCA results, information systems software, alerts and advisories, and cognitive acids. Following program implementation, NCPS saw a 900-fold increase in reporting of close calls of high-priority events, reflecting the level of commitment to the program by VHA leaders and staff.

Computer software summaries. Numbers 325 through 423

Energy Technology Data Exchange (ETDEWEB)

1978-08-01

The National Energy Software Center (NESC) serves as the software exchange and information center for the U.S. Department of Energy and the Nuclear Regulatory Commission. These summaries describe agency-sponsored software which is at the specification stage, under development, being checked out, in use, or available at agency offices, laboratories, and contractor installations. They describe software which is not included in the NESC library due to its preliminary status or because it is believed to be of limited interest. Codes dealing with the following subjects are included: cross section and resonance integral calculations; spectrum calculations, generation of group constants, lattice and cell problems; static design studies; depletion, fuel management, cost analysis, and power plant economics; space-independent kinetics; space--time kinetics, coupled neutronics--hydrodynamics--thermodynamics; and excursion simulations; radiological safety, hazard and accident analysis; heat transfer and fluid flow; deformation and stress distribution computations, structural analysis, and engineering design studies; gamma heating and shield design; reactor systems analysis; data preparation; data management; subsidiary calculations; experimental data processing; general mathematical and computing system routines; materials; environmental and earth sciences; space sciences; electronics and engineering equipment; chemistry; particle accelerators and high-voltage machines; physics; magnetic fusion research; biology and medicine; and data. (RWR)

Computer software summaries. Numbers 325 through 423

International Nuclear Information System (INIS)

1978-08-01

The National Energy Software Center (NESC) serves as the software exchange and information center for the U.S. Department of Energy and the Nuclear Regulatory Commission. These summaries describe agency-sponsored software which is at the specification stage, under development, being checked out, in use, or available at agency offices, laboratories, and contractor installations. They describe software which is not included in the NESC library due to its preliminary status or because it is believed to be of limited interest. Codes dealing with the following subjects are included: cross section and resonance integral calculations; spectrum calculations, generation of group constants, lattice and cell problems; static design studies; depletion, fuel management, cost analysis, and power plant economics; space-independent kinetics; space--time kinetics, coupled neutronics--hydrodynamics--thermodynamics; and excursion simulations; radiological safety, hazard and accident analysis; heat transfer and fluid flow; deformation and stress distribution computations, structural analysis, and engineering design studies; gamma heating and shield design; reactor systems analysis; data preparation; data management; subsidiary calculations; experimental data processing; general mathematical and computing system routines; materials; environmental and earth sciences; space sciences; electronics and engineering equipment; chemistry; particle accelerators and high-voltage machines; physics; magnetic fusion research; biology and medicine; and data

Knowledge management: Role of the the Radiation Safety Information Computational Center (RSICC)

Science.gov (United States)

Valentine, Timothy

2017-09-01

The Radiation Safety Information Computational Center (RSICC) at Oak Ridge National Laboratory (ORNL) is an information analysis center that collects, archives, evaluates, synthesizes and distributes information, data and codes that are used in various nuclear technology applications. RSICC retains more than 2,000 software packages that have been provided by code developers from various federal and international agencies. RSICC's customers (scientists, engineers, and students from around the world) obtain access to such computing codes (source and/or executable versions) and processed nuclear data files to promote on-going research, to ensure nuclear and radiological safety, and to advance nuclear technology. The role of such information analysis centers is critical for supporting and sustaining nuclear education and training programs both domestically and internationally, as the majority of RSICC's customers are students attending U.S. universities. Additionally, RSICC operates a secure CLOUD computing system to provide access to sensitive export-controlled modeling and simulation (M&S) tools that support both domestic and international activities. This presentation will provide a general review of RSICC's activities, services, and systems that support knowledge management and education and training in the nuclear field.

Advanced Booster Composite Case/Polybenzimidazole Nitrile Butadiene Rubber Insulation Development

Science.gov (United States)

Gentz, Steve; Taylor, Robert; Nettles, Mindy

2015-01-01

The NASA Engineering and Safety Center (NESC) was requested to examine processing sensitivities (e.g., cure temperature control/variance, debonds, density variations) of polybenzimidazole nitrile butadiene rubber (PBI-NBR) insulation, case fiber, and resin systems and to evaluate nondestructive evaluation (NDE) and damage tolerance methods/models required to support human-rated composite motor cases. The proposed use of composite motor cases in Blocks IA and II was expected to increase performance capability through optimizing operating pressure and increasing propellant mass fraction. This assessment was to support the evaluation of risk reduction for large booster component development/fabrication, NDE of low mass-to-strength ratio material structures, and solid booster propellant formulation as requested in the Space Launch System NASA Research Announcement for Advanced Booster Engineering Demonstration and/or Risk Reduction. Composite case materials and high-energy propellants represent an enabling capability in the Agency's ability to provide affordable, high-performing advanced booster concepts. The NESC team was requested to provide an assessment of co- and multiple-cure processing of composite case and PBI-NBR insulation materials and evaluation of high-energy propellant formulations.

Innovative Comparison of Transient Ignition Temperature at the Booster Interface, New Stainless Steel Pyrovalve Primer Chamber Assembly "V" (PCA) Design Versus the Current Aluminum "Y" PCA Design

Science.gov (United States)

Saulsberry, Regor L.; McDougle, Stephen H.; Garcia,Roberto; Johnson, Kenneth L.; Sipes, William; Rickman, Steven; Hosangadi, Ashvin

2011-01-01

An assessment of four spacecraft pyrovalve anomalies that occurred during ground testing was conducted by the NASA Engineering & Safety Center (NESC) in 2008. In all four cases, a common aluminum (Al) primer chamber assembly (PCA) was used with dual NASA Standard Initiators (NSIs) and the nearly simultaneous (separated by less than 80 microseconds) firing of both initiators failed to ignite the booster charge. The results of the assessment and associated test program were reported in AIAA Paper AIAA-2008-4798, NESC Independent Assessment of Pyrovalve Ground Test Anomalies. As a result of the four Al PCA anomalies, and the test results and findings of the NESC assessment, the Mars Science Laboratory (MSL) project team decided to make changes to the PCA. The material for the PCA body was changed from aluminum (Al) to stainless steel (SS) to avoid melting, distortion, and potential leakage of the NSI flow passages when the device functioned. The flow passages, which were interconnected in a Y-shaped configuration (Y-PCA) in the original design, were changed to a V-shaped configuration (V-PCA). The V-shape was used to more efficiently transfer energy from the NSIs to the booster. Development and qualification testing of the new design clearly demonstrated faster booster ignition times compared to the legacy AL Y-PCA design. However, the final NESC assessment report recommended that the SS V-PCA be experimentally characterized and quantitatively compared to the Al Y-PCA design. This data was deemed important for properly evaluating the design options for future NASA projects. This test program has successfully quantified the improvement of the SS V-PCA over the Al Y-PCA. A phase B of the project was also conducted and evaluated the effect of firing command skew and enlargement of flame channels to further assist spacecraft applications.

Key Problems of Fire Safety Enforcement in Traffic and Communication Centers (TCC)

Science.gov (United States)

Medyanik, M.; Zosimova, O.

2017-10-01

A Traffic and Communication Center (TCC) means facilities designed and used to distribute and redirect flows of humans and motor vehicles while they get serviced and operate. This paper sets forth the basic problems of fire safety enforcement on the TCC, and the causes that slow down human and vehicle traffic speeds. It proposes ways to solve the problems of fire safety enforcement on the TCC, in the Russian Federation and elsewhere. Engineering solutions are proposed for TCC design, with key outlooks of TCC future development as an alternative way to organize access in transportation.

Development and Certification of Ultrasonic Background Noise Test (UBNT) System for use on the International Space Station (ISS)

Science.gov (United States)

Prosser, William H.; Madaras, Eric I.

2011-01-01

As a next step in the development and implementation of an on-board leak detection and localization system on the International Space Station (ISS), there is a documented need to obtain measurements of the ultrasonic background noise levels that exist within the ISS. This need is documented in the ISS Integrated Risk Management System (IRMA), Watch Item #4669. To address this, scientists and engineers from the Langley Research Center (LaRC) and the Johnson Space Center (JSC), proposed to the NASA Engineering and Safety Center (NESC) and the ISS Vehicle Office a joint assessment to develop a flight package as a Station Development Test Objective (SDTO) that would perform ultrasonic background noise measurements within the United States (US) controlled ISS structure. This document contains the results of the assessment

The San Diego Center for Patient Safety: Creating a Research, Education, and Community Consortium

National Research Council Canada - National Science Library

Pratt, Nancy; Vo, Kelly; Ganiats, Theodore G; Weinger, Matthew B

2005-01-01

In response to the Agency for Healthcare Research and Quality's Developmental Centers of Education and Research in Patient Safety grant program, a group of clinicians and academicians proposed the San...

76 FR 40733 - National Institute for Occupational Safety and Health, (NIOSH), World Trade Center Health Program...

Science.gov (United States)

2011-07-11

... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention National Institute for Occupational Safety and Health, (NIOSH), World Trade Center Health Program Science/Technical Advisory Committee (WTCHP-STAC) Correction: This notice was published in the Federal Register on June 23...

Summary of the function and the safety design of the Tokai Reprocessing Utility Center

International Nuclear Information System (INIS)

Yanai, Chisato; Yamazaki, Toshihiko; Tomita, Tsuneo; Horii, Shinichi; Uryu, Mituru; Ishiguro, Nobuharu; Kobayashi, Kentarou

1998-01-01

The Tokai Reprocessing Utility Center is a new facility to replace the utilities to the Tokai Reprocessing Plant such as the emergency power supply, compressed air, etc. which are scattered about the site and have became superannuated. The Facility building has a base-isolation system that is a strongly resistant to earthquake. After completion, the center will supply utilities to the Main Plant, the Central Building, the Auxiliary Active Facility, etc. of the Tokai Reprocessing Plant. This document outlines the function and the safety design of the Tokai Reprocessing Utility Center. (author)

Pre-Test Analysis Predictions for the Shell Buckling Knockdown Factor Checkout Tests - TA01 and TA02

Science.gov (United States)

Thornburgh, Robert P.; Hilburger, Mark W.

2011-01-01

This report summarizes the pre-test analysis predictions for the SBKF-P2-CYL-TA01 and SBKF-P2-CYL-TA02 shell buckling tests conducted at the Marshall Space Flight Center (MSFC) in support of the Shell Buckling Knockdown Factor (SBKF) Project, NASA Engineering and Safety Center (NESC) Assessment. The test article (TA) is an 8-foot-diameter aluminum-lithium (Al-Li) orthogrid cylindrical shell with similar design features as that of the proposed Ares-I and Ares-V barrel structures. In support of the testing effort, detailed structural analyses were conducted and the results were used to monitor the behavior of the TA during the testing. A summary of predicted results for each of the five load sequences is presented herein.

Kazakhstan center of nuclear technology safety. Approach of work, possibilities and plans

International Nuclear Information System (INIS)

Tazhibaeva, I.L; Romanenko, O.G.; Cherepnin, Yu. S.; Planchon, H.P; Imel, G; Newton, D.

2000-01-01

NTSC was created in November, 1997 as an association of experts in all the areas of nuclear and radiation safety and radioactive materials handling The main goal of creation is investigation of safety aspects of nuclear power in the Republic of Kazakhstan, taking into account the interests of environment and human health protection in the regions of nuclear industry units allocation. The Center was created with support and special cooperation with the US, has grown and developed cooperative ties with several other countries.In the report are enumerate the main directions of NTSC activity, general directions of cooperation, current and completed activity, planing activity

Kennedy Space Center (KSC) Launch Complex 39 (LC-39) Gaseous Hydrogen (GH2) Vent Arm Behavior Prediction Model Review Technical Assessment Report

Science.gov (United States)

Wilson, Timmy R.; Beech, Geoffrey; Johnston, Ian

2009-01-01

The NESC Assessment Team reviewed a computer simulation of the LC-39 External Tank (ET) GH2 Vent Umbilical system developed by United Space Alliance (USA) for the Space Shuttle Program (SSP) and designated KSC Analytical Tool ID 451 (KSC AT-451). The team verified that the vent arm kinematics were correctly modeled, but noted that there were relevant system sensitivities. Also, the structural stiffness used in the math model varied somewhat from the analytic calculations. Results of the NESC assessment were communicated to the model developers.

The Role of the Radiation Safety Information Computational Center (RSICC) in Knowledge Management

International Nuclear Information System (INIS)

Valentine, T.

2016-01-01

Full text: The Radiation Safety Information Computational Center (RSICC) is an information analysis center that collects, archives, evaluates, synthesizes and distributes information, data and codes that are used in various nuclear technology applications. RSICC retains more than 2,000 packages that have been provided by contributors from various agencies. RSICC’s customers obtain access to such computing codes (source and/or executable versions) and processed nuclear data files to promote on-going research, to help ensure nuclear and radiological safety, and to advance nuclear technology. The role of such information analysis centers is critical for supporting and sustaining nuclear education and training programmes both domestically and internationally, as the majority of RSICC’s customers are students attending U.S. universities. RSICC also supports and promotes workshops and seminars in nuclear science and technology to further the use and/or development of computational tools and data. Additionally, RSICC operates a secure CLOUD computing system to provide access to sensitive export-controlled modeling and simulation (M&S) tools that support both domestic and international activities. This presentation will provide a general review of RSICC’s activities, services, and systems that support knowledge management and education and training in the nuclear field. (author

International Nuclear Safety Center database on thermophysical properties of reactor materials

International Nuclear Information System (INIS)

Fink, J.K.; Sofu, T.; Ley, H.

1997-01-01

The International Nuclear Safety Center (INSC) database has been established at Argonne National Laboratory to provide easily accessible data and information necessary to perform nuclear safety analyses and to promote international collaboration through the exchange of nuclear safety information. The INSC database, located on the World Wide Web at http://www.insc.anl.gov, contains critically assessed recommendations for reactor material properties for normal operating conditions, transients, and severe accidents. The initial focus of the database is on thermodynamic and transport properties of materials for water reactors. Materials that are being included in the database are fuel, absorbers, cladding, structural materials, coolant, and liquid mixtures of combinations of UO 2 , ZrO 2 , Zr, stainless steel, absorber materials, and concrete. For each property, the database includes: (1) a summary of recommended equations with uncertainties; (2) a detailed data assessment giving the basis for the recommendations, comparisons with experimental data and previous recommendations, and uncertainties; (3) graphs showing recommendations, uncertainties, and comparisons with data and other equations; and (4) property values tabulated as a function of temperature

Restructuring within an academic health center to support quality and safety: the development of the Center for Quality and Safety at the Massachusetts General Hospital.

Science.gov (United States)

Bohmer, Richard M J; Bloom, Jonathan D; Mort, Elizabeth A; Demehin, Akinluwa A; Meyer, Gregg S

2009-12-01

Recent focus on the need to improve the quality and safety of health care has created new challenges for academic health centers (AHCs). Whereas previously quality was largely assumed, today it is increasingly quantifiable and requires organized systems for improvement. Traditional structures and cultures within AHCs, although well suited to the tripartite missions of teaching, research, and clinical care, are not easily adaptable to the tasks of measuring, reporting, and improving quality. Here, the authors use a case study of Massachusetts General Hospital's efforts to restructure quality and safety to illustrate the value of beginning with a focus on organizational culture, using a systematic process of engaging clinical leadership, developing an organizational framework dependent on proven business principles, leveraging focus events, and maintaining executive dedication to execution of the initiative. The case provides a generalizable example for AHCs of how applying explicit management design can foster robust organizational change with relatively modest incremental financial resources.

Evaluating Space Weather Architecture Options to Support Human Deep Space Exploration of the Moon and Mars

Science.gov (United States)

Parker, L.; Minow, J.; Pulkkinen, A.; Fry, D.; Semones, E.; Allen, J.; St Cyr, C.; Mertens, C.; Jun, I.; Onsager, T.; Hock, R.

2018-02-01

NASA's Engineering and Space Center (NESC) is conducting an independent technical assessment of space environment monitoring and forecasting architecture options to support human and robotic deep space exploration.

Test and Analysis Correlation of a Large-Scale, Orthogrid-Stiffened Metallic Cylinder without Weld Lands

Science.gov (United States)

Rudd, Michelle T.; Hilburger, Mark W.; Lovejoy, Andrew E.; Lindell, Michael C.; Gardner, Nathaniel W.; Schultz, Marc R.

2018-01-01

The NASA Engineering Safety Center (NESC) Shell Buckling Knockdown Factor Project (SBKF) was established in 2007 by the NESC with the primary objective to develop analysis-based buckling design factors and guidelines for metallic and composite launch-vehicle structures.1 A secondary objective of the project is to advance technologies that have the potential to increase the structural efficiency of launch-vehicles. The SBKF Project has determined that weld-land stiffness discontinuities can significantly reduce the buckling load of a cylinder. In addition, the welding process can introduce localized geometric imperfections that can further exacerbate the inherent buckling imperfection sensitivity of the cylinder. Therefore, single-piece barrel fabrication technologies can improve structural efficiency by eliminating these weld-land issues. As part of this effort, SBKF partnered with the Advanced Materials and Processing Branch (AMPB) at NASA Langley Research Center (LaRC), the Mechanical and Fabrication Branch at NASA Marshall Space Flight Center (MSFC), and ATI Forged Products to design and fabricate an 8-ft-diameter orthogrid-stiffened seamless metallic cylinder. The cylinder was subjected to seven subcritical load sequences (load levels that are not intended to induce test article buckling or material failure) and one load sequence to failure. The purpose of this test effort was to demonstrate the potential benefits of building cylindrical structures with no weld lands using the flow-formed manufacturing process. This seamless barrel is the ninth 8-ft-diameter metallic barrel and the first single-piece metallic structure to be tested under this program.

Carbon Monoxide Information Center

Medline Plus

Full Text Available ... OnSafety Blog Safety Education Centers Neighborhood Safety Network Community Outreach Resource Center Toy Recall Statistics CO Poster ... Sitemap RSS E-mail Inside CPSC Accessibility Privacy Policy Budget, Performances & Finance Open Government Freedom of Information ( ...

Neonatal Safety of Elective Family-Centered Caesarean Sections: A Cohort Study

Directory of Open Access Journals (Sweden)

Ilona C. Narayen

2018-02-01

Full Text Available BackgroundAlthough little data are available concerning safety for newborns, family-centered caesarean sections (FCS are increasingly implemented. With FCS mothers can see the delivery of their baby, followed by direct skin-to-skin contact. We evaluated the safety for newborns born with FCS in the Leiden University Medical Center (LUMC, where FCS was implemented in June 2014 for singleton pregnancies with a gestational age (GA ≥38 weeks and without increased risks for respiratory morbidity.MethodsThe incidence of respiratory pathology, unplanned admission, and hypothermia in infants born after FCS in LUMC were retrospectively reviewed and compared with a historical cohort of standard elective cesarean sections (CS.ResultsFrom June 2014 to November 2015, 92 FCS were performed and compared to 71 standard CS in 2013. Incidence of respiratory morbidity, hypothermia, temperatures at arrival at the department, GA, and birth weight were comparable (ns. Unplanned admission occurred more often after FCS when compared to standard CS (21 vs 7%; p = 0.03, probably due to peripheral oxygen saturation (SpO2 monitoring. There was no increase in respiratory pathology (8 vs 6%, ns. One-third of the babies were separated from their mother during or after FCS.ConclusionUnplanned neonatal admissions after elective CS increased after implementing FCS, without an increase in respiratory morbidity or hypothermia. SpO2 monitoring might have a contribution. Separation from the mother occurred often.

Don't trust equivalency presumptions when choosing distribution poles

Energy Technology Data Exchange (ETDEWEB)

Rollins, M.

2003-08-01

The variety of electric power distribution poles are described (wood, steel, prestressed concrete) in an effort to alert utilities that simple substitution of one type of pole for another based on presumed equivalency entails the risk that the replacement poles are unfit for the load conditions and do not comply with National Electrical Safety Code (NESC) requirements. A thorough evaluation of all design loads and the proper application of the appropriate overload and strength factors must take place prior to selecting the type of replacement to avoid misapplication of a product in situations for which it was not designed. Relevant provisions of NESC are described.

NASA Aerospace Flight Battery Program: Wet Life of Nickel-Hydrogen (Ni-H2) Batteries. Volume 2, Part 3; Appendices

Science.gov (United States)

Jung, David S,; Lee, Leonine S.; Manzo, Michelle A.

2010-01-01

This NASA Aerospace Flight Battery Systems Working Group was chartered within the NASA Engineering and Safety Center (NESC). The Battery Working Group was tasked to complete tasks and to propose proactive work to address battery related, agency-wide issues on an annual basis. In its first year of operation, this proactive program addressed various aspects of the validation and verification of aerospace battery systems for NASA missions. Studies were performed, issues were discussed and in many cases, test programs were executed to generate recommendations and guidelines to reduce risk associated with various aspects of implementing battery technology in the aerospace industry. This document contains Part 3 - Volume II Appendices to Part 3 - Volume I.

Computer software summaries. Numbers 1 through 423

International Nuclear Information System (INIS)

1979-09-01

The National Energy Software Center (NESC) serves as the software exchange and information center for the US Department of Energy and the Nuclear Regulatory Commission. A major activity of the Center is the preparation and publication of two reports issued periodically - the Center's compilation of program abstracts, ANL-7411, and this software summaries report, ANL-8040. The abstracts describe the softward packages available in the software exchange library maintained and distributed by the Center. The summaries describe agency-sponsored software that is at the specification stage, under development, being checked out, in use, or available at agency offices, laboratories, and contractor installations. Summaries describe software that is not included in the NESC library due to its preliminary status or because it is believed to be of limited interest. The purpose of the summaries report is to keep agency and contractor personnel informed as to the existence, status, and availability of computer programs within the agency, and thereby minimize duplication costs and maximize the value of agency software development efforts

An interfaith workers' center approach to workplace rights: implications for workplace safety and health.

Science.gov (United States)

Cho, Chi C; Oliva, Jose; Sweitzer, Erica; Nevarez, Juan; Zanoni, Joseph; Sokas, Rosemary K

2007-03-01

Over the past decade, fatal occupational injury rates for immigrant workers have increased disproportionately, as have informal and precarious working arrangements. Workers' rights centers have emerged as a response. This descriptive report characterizes an innovative approach to encourage immigrant workers to access federal and state occupational safety and health programs through an interfaith workers' center. : Existing data obtained by volunteers at time of intake were redacted and imported into a SAS database for secondary analysis. Statistical methods used to evaluate associations between outcome of interest and various characteristics included the chi2 test of association, Fisher exact test of association, and multivariate logistic regression. A total of 934 individual records were reviewed, although for any given item, missing data was a limitation. Among 780 persons reporting their primary language, 75% spoke Spanish, 19% Polish, 4% English, and 1% Other. The following total numbers of formal complaints were filed with each of the following agencies: 110 referred to the state Department of Labor (DOL), 123 to the federal Equal Employment Opportunity Commission (EEOC), 65 concerning federal violations of wages and hours, and 47 complaints with the Occupational Safety and Health Administration (OSHA). Approximately 37% of the OSHA complaints resulted in a measurable outcome, exceeding the average for all complaints. Workers' most frequent concerns focus on pay and discrimination. Recasting occupational safety and health hazards as threats to income and as forms of discrimination may help identify hazards.

The Radiation Safety Information Computational Center (RSICC): A Resource for Nuclear Science Applications

Energy Technology Data Exchange (ETDEWEB)

Kirk, Bernadette Lugue [ORNL

2009-01-01

The Radiation Safety Information Computational Center (RSICC) has been in existence since 1963. RSICC collects, organizes, evaluates and disseminates technical information (software and nuclear data) involving the transport of neutral and charged particle radiation, and shielding and protection from the radiation associated with: nuclear weapons and materials, fission and fusion reactors, outer space, accelerators, medical facilities, and nuclear waste management. RSICC serves over 12,000 scientists and engineers from about 100 countries.

Food Safety: At the Center of a One Health Approach for Combating Zoonoses

DEFF Research Database (Denmark)

Wielinga, Pieter; Schlundt, Jørgen

2013-01-01

in three major classes: parasites, bacteria, and viruses. While parasites often relate to very specific animal hosts and contribute significantly to the human disease burden, virus have often been related to major, well-published global outbreaks, e.g. SARS and avian- and swine-influenza. The bacterial...... international organizations and national agricultural-and health authorities in most countries, for instance as was the case with avian influenza. Other diseases relate to the industrialized food production chain and have been-in some settings-dealt with efficiently through farm-to-fork preventive action......Food Safety is at the center of One Health. Many, if not most, of all important zoonoses relate in some way to animals in the food production chain. Therefore, the food becomes an important vehicle for many, but not all, of these zoonotic pathogens. One of the major issues in food safety over...

[Clinical safety audits for primary care centers. A pilot study].

Science.gov (United States)

Ruiz Sánchez, Míriam; Borrell-Carrió, Francisco; Ortodó Parra, Cristina; Fernàndez I Danés, Neus; Fité Gallego, Anna

2013-01-01

To identify organizational processes, violations of rules, or professional performances that pose clinical levels of insecurity. Descriptive cross-sectional survey with customized externally-behavioral verification and comparison of sources, conducted from June 2008 to February 2010. Thirteen of the 53 primary care teams (PCT) of the Catalonian Health Institute (ICS Costa de Ponent, Barcelona). Employees of 13 PCT classified into: director, nurse director, customer care administrators, and general practitioners. Non-random selection, teaching (TC)/non-teaching, urban (UC)/rural and small/large (LC) health care centers (HCC). A total of 33 indicators were evaluated; 15 of procedures, 9 of attitude, 3 of training, and 6 of communication. Level of uncertainty: <50% positive answers for each indicator. no collaboration. A total of 55 professionals participated (84.6% UC, 46.2% LC and 76.9% TC). Rank distribution: 13 customer care administrators, 13 nurse directors, 13 HCC directors, and 16 general practitioners. Levels of insecurity emerged from the following areas: reception of new medical professionals, injections administration, nursing weekend home calls, urgent consultations to specialists, aggressive patients, critical incidents over the agenda of the doctors, communication barriers with patients about treatment plans, and with immigrants. Clinical safety is on the agenda of the health centers. Identified areas of uncertainty are easily approachable, and are considered in the future system of accreditation of the Catalonian Government. General practitioners are more critical than directors, and teaching health care centers, rural and small HCC had a better sense of security. Copyright © 2012 Elsevier España, S.L. All rights reserved.

Safety climate and workplace violence prevention in state-run residential addiction treatment centers.

Science.gov (United States)

Lipscomb, Jane A; London, M; Chen, Y M; Flannery, K; Watt, M; Geiger-Brown, J; Johnson, J V; McPhaul, K

2012-01-01

To examine the association between violence prevention safety climate measures and self reported violence toward staff in state-run residential addiction treatment centers. In mid-2006, 409 staff from an Eastern United States state agency that oversees a system of thirteen residential addiction treatment centers (ATCs) completed a self-administered survey as part of a comprehensive risk assessment. The survey was undertaken to identify and measure facility-level risk factors for violence, including staff perceptions of the quality of existing US Occupational Safety and Health Administration (OSHA) program elements, and ultimately to guide violence prevention programming. Key informant interviews and staff focus groups provided researchers with qualitative data with which to understand safety climate and violence prevention efforts within these work settings. The frequency with which staff reported experiencing violent behavior ranged from 37% for "clients raised their voices in a threatening way to you" to 1% for "clients pushed, hit, kicked, or struck you". Findings from the staff survey included the following significant predictors of violence: "client actively resisting program" (OR=2.34, 95% CI=1.35, 4.05), "working with clients for whom the history of violence is unknown" (OR=1.91, 95% CI=1.18, 3.09) and "management commitment to violence prevention" reported as "never/hardly ever" and "seldom or sometimes" (OR=4.30 and OR=2.31 respectively), while controlling for other covariates. We utilized a combination of qualitative and quantitative research methods to begin to describe the risk and potential for violence prevention in this setting. The prevalence of staff physical violence within the agency's treatment facilities was lower than would be predicted. Possible explanations include the voluntary nature of treatment programs; strong policies and consequences for resident behavior and ongoing quality improvement efforts. Quantitative data identified low

Patient-Centered Robot-Aided Passive Neurorehabilitation Exercise Based on Safety-Motion Decision-Making Mechanism

Directory of Open Access Journals (Sweden)

Lizheng Pan

2017-01-01

Full Text Available Safety is one of the crucial issues for robot-aided neurorehabilitation exercise. When it comes to the passive rehabilitation training for stroke patients, the existing control strategies are usually just based on position control to carry out the training, and the patient is out of the controller. However, to some extent, the patient should be taken as a “cooperator” of the training activity, and the movement speed and range of the training movement should be dynamically regulated according to the internal or external state of the subject, just as what the therapist does in clinical therapy. This research presents a novel motion control strategy for patient-centered robot-aided passive neurorehabilitation exercise from the point of the safety. The safety-motion decision-making mechanism is developed to online observe and assess the physical state of training impaired-limb and motion performances and regulate the training parameters (motion speed and training rage, ensuring the safety of the supplied rehabilitation exercise. Meanwhile, position-based impedance control is employed to realize the trajectory tracking motion with interactive compliance. Functional experiments and clinical experiments are investigated with a healthy adult and four recruited stroke patients, respectively. The two types of experimental results demonstrate that the suggested control strategy not only serves with safety-motion training but also presents rehabilitation efficacy.

Burnout, Perceived Stress, and Job Satisfaction Among Trauma Nurses at a Level I Safety-Net Trauma Center.

Science.gov (United States)

Munnangi, Swapna; Dupiton, Lynore; Boutin, Anthony; Angus, L D George

Nurses are at the forefront of our health care delivery system and have been reported to exhibit a high level of burnout. Burnout and stress in trauma nurses at a safety-net hospital can negatively impact patient care. Safety-net hospitals are confronted with unique social, financial, as well as resource problems that can potentially make the work environment frustrating. The purpose of this study was to explore the levels of burnout, stress, and job satisfaction in nurses providing care to trauma patients at a Level I safety-net trauma center. A cross-sectional survey design was used to investigate principal factors including personal and professional demographics, burnout, perceived stress, and job satisfaction. Trauma nurses working at a Level I safety-net trauma center are stressed and exhibited moderate degree of burnout. The extent of emotional exhaustion experienced by the nurses varied with work location and was highest in surgical intensive care unit nurses. The level of job satisfaction in terms of opportunities for promotion differed significantly by race and the health status of the nurses. Satisfaction with coworkers was lowest in those nurses between the ages of 60-69 years. Female nurses were more satisfied with their coworkers than male nurses. In addition, the study revealed that significant relationships exist among perceived stress, burnout, and job satisfaction. Work environment significantly impacts burnout, job satisfaction, and perceived stress experienced by trauma nurses in a safety-net hospital. Nursing administration can make an effort to understand the levels of burnout and strategically improve work environment for trauma nurses in order to minimize stressors leading to attrition and enhance job satisfaction.

NASA Aerospace Flight Battery Program: Wet Life of Nickel-Hydrogen (Ni-H2) Batteries. Volume 1, Part 3

Science.gov (United States)

Jung, David S.; Lee, Leonine S.; Manzo, Michelle A.

2010-01-01

This NASA Aerospace Flight Battery Systems Working Group was chartered within the NASA Engineering and Safety Center (NESC). The Battery Working Group was tasked to complete tasks and to propose proactive work to address battery related, agency-wide issues on an annual basis. In its first year of operation, this proactive program addressed various aspects of the validation and verification of aerospace battery systems for NASA missions. Studies were performed, issues were discussed and in many cases, test programs were executed to generate recommendations and guidelines to reduce risk associated with various aspects of implementing battery technology in the aerospace industry. This document contains Part 3 - Volume I: Wet Life of Nickel-Hydrogen (Ni-H2) Batteries of the program's operations.

FBR Plant Engineering Center annual report 2012

International Nuclear Information System (INIS)

2013-12-01

This annual report shows the last year's R and D activities of currently-reorganized FBR Plant Engineering Center, which was established on April 1, 2009. FBR Safety Technology Center was founded on April 1, 2013 by the consolidation of both the activities of 'former FBR Plant Engineering Center' and a portion of 'FBR Safety Evaluation Unit, Advanced Nuclear System Research and Development Directorate', especially concentrating on safety evaluations and analyses for severe accidents. As for FBR safety technology, it is necessary to continuously make an effort for compliance with new safety regulations in preparation for 'Monju' to restart, for safety enhancement evaluation and for safety technology upgrading. In this context, the new organization was founded in order to reinforce the safety evaluation capability, which will surely and steadily promote FBR safety-technology related activities. As a result, FBR Plant Engineering Center was abolished. This report summarizes the R and D activities at the former FBR Plant Engineering Center, aiming at contributing to the commercialization by using operation experiences and technology development results derived from the actual reactor 'Monju'. The activities are divided into five areas of operation-and-maintenance engineering, sodium engineering, reactor-core-and-fuel engineering, plant engineering, and safety engineering. This annual report is intended for a report of the activities of individual researcher in the center rather than that of the progress of the center as a whole. This will clarify the individual themes, progresses and problems of each researcher, which will, hopefully, facilitate communication with the outside researchers. (author)

Report on administrative work at radiation safety center in fiscal year 2003

International Nuclear Information System (INIS)

Uda, Tatsuhiko; Asakura, Yamato; Sakuma, Yoichi; Kawano, Takao; Yamanishi, Hirokuni; Sugiyama, Takahiko; Nishimura, Kiyohiko; Miyake, Hitoshi

2005-06-01

National Institute for Fusion Science constructed the Large Helical Device (LHD) which is the largest magnetic confinement plasma experimental device using super conductive magnet coils system. It took eight years to construct and the first plasma shot was carried out on March 1998. Since then high temperature plasma and improved plasma confinement experiments have been achieved. This is the report on administrative work at the radiation safety center considering radiation protection for workers at the LHD and the Compact Helical Device (CHS), and radiation measurement and monitoring in the site. Major scope is as follows. (1) Radiation (X ray) dose measurement and monitoring in the radiation controlled area and in the site using particularly developed monitoring system named as Radiation Monitoring System Applicable to Fusion Experiments (RMSAFE). (2) Establishment of education and registration system for radiation workers and accessing control system for the LHD controlled area. As same as the published annual reports from fiscal year 1999 to 2002, this report will be helpful for the future radiation safety management in the research institute. (author)

Safety Evaluation Report for the Claiborne Enrichment Center, Homer, Louisiana (Docket No. 70-3070)

Energy Technology Data Exchange (ETDEWEB)

1994-01-01

This report documents the US Nuclear Regulatory Commission (NRC) staff review and safety evaluation of the Louisiana Energy Services, L.P. (LES, the applicant) application for a license to possess and use byproduct, source, and special nuclear material and to enrich natural uranium to a maximum of 5 percent U-235 by the gas centrifuge process. The plant, to be known as the Claiborne Enrichment Center (CEC), would be constructed near the town of Homer in Claiborne Parish, Louisiana. At full production in a given year, the plant will receive approximately 4,700 tonnes of feed UF{sub 6} and produce 870 tonnes of low-enriched UF{sub 6}, and 3,830 tonnes of depleted UF{sub 6} tails. Facility construction, operation, and decommissioning are expected to last 5, 30, and 7 years, respectively. The objective of the review is to evaluate the potential adverse impacts of operation of the facility on worker and public health and safety under both normal operating and accident conditions. The review also considers the management organization, administrative programs, and financial qualifications provided to assure safe design and operation of the facility. The NRC staff concludes that the applicant`s descriptions, specifications, and analyses provide an adequate basis for safety review of facility operations and that construction and operation of the facility does not pose an undue risk to public health and safety.

Safety Evaluation Report for the Claiborne Enrichment Center, Homer, Louisiana (Docket No. 70-3070)

International Nuclear Information System (INIS)

1994-01-01

This report documents the US Nuclear Regulatory Commission (NRC) staff review and safety evaluation of the Louisiana Energy Services, L.P. (LES, the applicant) application for a license to possess and use byproduct, source, and special nuclear material and to enrich natural uranium to a maximum of 5 percent U-235 by the gas centrifuge process. The plant, to be known as the Claiborne Enrichment Center (CEC), would be constructed near the town of Homer in Claiborne Parish, Louisiana. At full production in a given year, the plant will receive approximately 4,700 tonnes of feed UF 6 and produce 870 tonnes of low-enriched UF 6 , and 3,830 tonnes of depleted UF 6 tails. Facility construction, operation, and decommissioning are expected to last 5, 30, and 7 years, respectively. The objective of the review is to evaluate the potential adverse impacts of operation of the facility on worker and public health and safety under both normal operating and accident conditions. The review also considers the management organization, administrative programs, and financial qualifications provided to assure safe design and operation of the facility. The NRC staff concludes that the applicant's descriptions, specifications, and analyses provide an adequate basis for safety review of facility operations and that construction and operation of the facility does not pose an undue risk to public health and safety

Carbon Monoxide Information Center

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FJET Database Project: Extract, Transform, and Load

Science.gov (United States)

Samms, Kevin O.

2015-01-01

The Data Mining & Knowledge Management team at Kennedy Space Center is providing data management services to the Frangible Joint Empirical Test (FJET) project at Langley Research Center (LARC). FJET is a project under the NASA Engineering and Safety Center (NESC). The purpose of FJET is to conduct an assessment of mild detonating fuse (MDF) frangible joints (FJs) for human spacecraft separation tasks in support of the NASA Commercial Crew Program. The Data Mining & Knowledge Management team has been tasked with creating and managing a database for the efficient storage and retrieval of FJET test data. This paper details the Extract, Transform, and Load (ETL) process as it is related to gathering FJET test data into a Microsoft SQL relational database, and making that data available to the data users. Lessons learned, procedures implemented, and programming code samples are discussed to help detail the learning experienced as the Data Mining & Knowledge Management team adapted to changing requirements and new technology while maintaining flexibility of design in various aspects of the data management project.

Compliance of child care centers in Pennsylvania with national health and safety performance standards for emergency and disaster preparedness.

Science.gov (United States)

Olympia, Robert P; Brady, Jodi; Kapoor, Shawn; Mahmood, Qasim; Way, Emily; Avner, Jeffrey R

2010-04-01

To determine the preparedness of child care centers in Pennsylvania to respond to emergencies and disasters based on compliance with National Health and Safety Performance Standards for Out-of-Home Child Care Programs. A questionnaire focusing on the presence of a written evacuation plan, the presence of a written plan for urgent medical care, the immediate availability of equipment and supplies, and the training of staff in first aid/cardiopulmonary resuscitation (CPR) as delineated in Caring for Our Children: National Health and Safety Performance Standards for Out-of-Home Child Care Programs, 2nd Edition, was mailed to 1000 randomly selected child care center administrators located in Pennsylvania. Of the 1000 questionnaires sent, 496 questionnaires were available for analysis (54% usable response rate). Approximately 99% (95% confidence interval [CI], 99%-100%) of child care centers surveyed were compliant with recommendations to have a comprehensive written emergency plan (WEP) for urgent medical care and evacuation, and 85% (95% CI, 82%-88%) practice their WEP periodically throughout the year. More than 20% of centers did not have specific written procedures for floods, earthquakes, hurricanes, blizzards, or bomb threats, and approximately half of the centers did not have specific written procedures for urgent medical emergencies such as severe bleeding, unresponsiveness, poisoning, shock/heart or circulation failure, seizures, head injuries, anaphylaxis or allergic reactions, or severe dehydration. A minority of centers reported having medications available to treat an acute asthma attack or anaphylaxis. Also, 77% (95% CI, 73%-80%) of child care centers require first aid training for each one of its staff members, and 33% (95% CI, 29%-37%) require CPR training. Although many of the child care centers we surveyed are in compliance with the recommendations for emergency and disaster preparedness, specific areas for improvement include increasing the frequency

Space Shuttle Program (SSP) Shock Test and Specification Experience for Reusable Flight Hardware Equipment

Science.gov (United States)

Larsen, Curtis E.

2012-01-01

As commercial companies are nearing a preliminary design review level of design maturity, several companies are identifying the process for qualifying their multi-use electrical and mechanical components for various shock environments, including pyrotechnic, mortar firing, and water impact. The experience in quantifying the environments consists primarily of recommendations from Military Standard-1540, Product Verification Requirement for Launch, Upper Stage, and Space Vehicles. Therefore, the NASA Engineering and Safety Center (NESC) formed a team of NASA shock experts to share the NASA experience with qualifying hardware for the Space Shuttle Program (SSP) and other applicable programs and projects. Several team teleconferences were held to discuss past experience and to share ideas of possible methods for qualifying components for multiple missions. This document contains the information compiled from the discussions

Information report on the nuclear safety and radiation protection of the Aube center for short-lived low- and intermediate-level wastes storage - 2011. Annual report in the framework of article 21 of the Act on nuclear transparency and safety

International Nuclear Information System (INIS)

2012-06-01

The National Radioactive Waste Management Agency (Andra), was established by the December 1991 Waste Act as a public body in charge of the long-term management of all radioactive waste, under the supervision of the Ministry of Ecology, Energy, Sustainable Development and the Sea (formerly the Ministry of Industry and the Ministry of Environment), and the Ministry of Research. The Andra operates two storage centers in the Aube region (France): the center for short-lived low- and intermediate-level wastes, and the center for very-low-level radioactive wastes. This document is the 2011 activity report of the center for short-lived low- and intermediate-level wastes. It presents a review of the activities of the center: presentation of the installations, safety and radiation protection, events or incidents, environmental monitoring, wastes management, public information, recommendations of the Health and safety Committee (CHSCT)

Architectural Design of a Nuclear Research Center with Radiation Safety Considerations, in North Western Coast of Egypt (Using Auto CAD and 3ds Max Programs)

International Nuclear Information System (INIS)

Farahat, M.A.Z.

2016-01-01

This research discusses the design of nuclear research centers to help architects and engineers who will design these centers. Also, the research covers the site characteristics which are used in site selection of nuclear research centers. It covers the principles and standards used in design and planning of nuclear research centers. The master plan of a nuclear research center should be designed based on the system of segregation according to the level of radioactivity. Radiation safety is an important aspect in the design of nuclear research centers. The Egyptian Atomic Energy Authority consists of three nuclear research centers, namely, the Nuclear Research Center in Inshas (Grid Planning Concept), the Hot Laboratories and Waste Management Center in Inshas (Grid Planning Concept) and The National Center for Radiation Research and Technology in Nasr City (Linear Planning Concept). The Radial Planning Concept is the best among all the Planning Concepts as regard radiation safety considerations. Therefore, an architectural design of a new nuclear research center was proposed in a suitable site in North Western Coast of Egypt (Radial Planning Concept) using Auto CAD and 3ds Max programs. This site is suitable and satisfies many of the site requirements. It is recommended that the architectural design of nuclear research centers should be supervised by an architectural engineer experienced in architectural design of nuclear facilities

Carbon Monoxide Information Center

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Management of a comprehensive radiation safety program in a major American University and affiliated academic medical center

International Nuclear Information System (INIS)

Yoshizumi, T.T.; Reiman, R.E.; Vylet, V.; Clapp, J.R.; Thomann, W.R.; Lyles, K.W.

2000-01-01

Duke University, which operates under eight radiation licenses issued by the State of North Carolina, consists of a leading medical center including extensive inpatient and outpatient facilities, a medical school, biomedical research labs, and an academic campus including two major accelerator facilities. The Nuclear Medicine and Radiation Oncology departments handle over 40,000 diagnostic and therapeutic procedures annually, including approximately 160 radioiodine therapeutic cases. In biomedical research labs, about 300 professors are authorized to use radioactive materials. Over 2,000 radiation workers are identified on campus. Over the past two years, we have transformed the existing radiation safety program into a more responsive and more accountable one. Simultaneously, the institutional 'culture' changed, and the Radiation Safety Division came to be viewed as a helpful ally by investigators. The purpose of this paper is to present our experiences that have made this transformation possible. Our initiatives included; (a) defining short-term and long-term goals; (b) establishing a definitive chain of authority; (c) obtaining an external review by a consultant Health Physicist; (d) improving existing radiation safety programs; (e) reorganizing the Radiation Safety Division, with creation of multidisciplinary professional staff positions; (f) implementing campus-wide radiation safety training, (g) increasing technician positions; (h) establishing monthly medical center radiation safety executive meeting. As a result progress made at the Divisional level includes; (a) culture change by recruiting professionals with academic credentials and recent college graduates; (b) implementing weekly staff meetings and monthly quality assurance meetings; (c) achieving academic prominence by publishing and presenting papers in national meetings; (d) senior staff achieving faculty appointments with academic departments; (e) senior staff participating in graduate student

Automated system for the management of the radiological safety in a radiopharmaceutical and labelled compounds production center

International Nuclear Information System (INIS)

Amador B, Z.H.; Alvarez Builla de Sologuren, E.

2006-01-01

The establishment in the Center of Isotopes of Cuba of a managerial quality system in matter of radiological safety Y the accumulated operational experience, its constitute the foundations for the development of a system of management of the radiological safety organically structured, with the application of evaluative techniques of it management Y it integration in an automated system. The Visual Basic 5 platform for the programming of the 'SASR' system is used. The functions of each one of the 11 modules that integrate it are described. With this it can be carried out the registration of the data of the training Y the personnel's authorization, the checkup of the radioactive inventory of the installation, the annual upgrade of the registrations of the individual doses of those workers, the analysis of the state of the available equipment for magnitude to control, the radiological situation of the work positions, the public exposure by the gassy discharges, the experiences of the radiological events, the annual consolidation of the costs of the safety Y the evaluation of indicators Y of tendencies. A computer tool that facilitates the effective management of the radiological safety in a radioactive installation is obtained. (Author)

European type NPP electric power and vent systems. For safety improvement and proposal of international center

International Nuclear Information System (INIS)

Sugiyama, Kenichiro

2011-01-01

For prevention of reactor accidents of nuclear power plants, multiplicity and redundancy of emergency power would be most important. At station blackout accident, European type manually operated vent operation could minimize release amount of radioactive materials and keep safety of neighboring residents. After Fukushima Daiichi accident, nuclear power plants could not restart operation even after completion of periodical inspection. This article introduced European type emergency power and vent systems in Swiss, Sweden and Germany with state of nuclear power phaseout for reference at considering to upgrade safety and accident mitigation measures for better understanding of the public. In addition, it would be important to recover trust of nuclear technology to continue to disseminate latest information on new knowledge of accident site and decontamination technologies to domestic and overseas people. As its implementation, establishment of Fukushima international center was proposed. (T. Tanaka)

A Robust Single Primate Neuroepithelial Cell Clonal Expansion System for Neural Tube Development and Disease Studies

Directory of Open Access Journals (Sweden)

Xiaoqing Zhu

2016-02-01

Full Text Available Developing a model of primate neural tube (NT development is important to promote many NT disorder studies in model organisms. Here, we report a robust and stable system to allow for clonal expansion of single monkey neuroepithelial stem cells (NESCs to develop into miniature NT-like structures. Single NESCs can produce functional neurons in vitro, survive, and extensively regenerate neuron axons in monkey brain. NT formation and NESC maintenance depend on high metabolism activity and Wnt signaling. NESCs are regionally restricted to a telencephalic fate. Moreover, single NESCs can turn into radial glial progenitors (RGPCs. The transition is accurately regulated by Wnt signaling through regulation of Notch signaling and adhesion molecules. Finally, using the “NESC-TO-NTs” system, we model the functions of folic acid (FA on NT closure and demonstrate that FA can regulate multiple mechanisms to prevent NT defects. Our system is ideal for studying NT development and diseases.

76 FR 9351 - Patient Safety Organizations: Voluntary Delisting From West Virginia Center for Patient Safety

Science.gov (United States)

2011-02-17

... Patient Safety, a component entity of West Virginia Hospital Association, West Virginia Medical Institute (WVMI), and West Virginia State Medical. Association (WVSMA), of its status as a Patient Safety... Patient Safety, a component entity of West Virginia Hospital Association, West Virginia Medical Institute...

International Space Station (ISS) Plasma Contactor Unit (PCU) Utilization Plan Assessment Update

Science.gov (United States)

Hernandez-Pellerano, Amri; Iannello, Christopher J.; Garrett, Henry B.; Ging, Andrew T.; Katz, Ira; Keith, R. Lloyd; Minow, Joseph I.; Willis, Emily M.; Schneider, Todd A.; Whittlesey, Edward J.;

Carbon Monoxide Information Center

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Aviation Safety/Automation Program Conference

Science.gov (United States)

Morello, Samuel A. (Compiler)

1990-01-01

The Aviation Safety/Automation Program Conference - 1989 was sponsored by the NASA Langley Research Center on 11 to 12 October 1989. The conference, held at the Sheraton Beach Inn and Conference Center, Virginia Beach, Virginia, was chaired by Samuel A. Morello. The primary objective of the conference was to ensure effective communication and technology transfer by providing a forum for technical interchange of current operational problems and program results to date. The Aviation Safety/Automation Program has as its primary goal to improve the safety of the national airspace system through the development and integration of human-centered automation technologies for aircraft crews and air traffic controllers.

Environment, safety and health compliance assessment, Feed Materials Production Center, Fernald, Ohio

Energy Technology Data Exchange (ETDEWEB)

1989-09-01

The Secretary of Energy established independent Tiger Teams to conduct environment, safety, and health (ES H) compliance assessments at US Department of Energy (DOE) facilities. This report presents the assessment of the Feed Materials Production Center (FMPC) at Fernald, Ohio. The purpose of the assessment at FMPC is to provide the Secretary with information regarding current ES H compliance status, specific ES H noncompliance items, evaluation of the adequacy of the ES H organizations and resources (DOE and contractor), and root causes for noncompliance items. Areas reviewed included performance under Federal, state, and local agreements and permits; compliance with Federal, state and DOE orders and requirements; adequacy of operations and other site activities, such as training, procedures, document control, quality assurance, and emergency preparedness; and management and staff, including resources, planning, and interactions with outside agencies.

Safety related maintenance in the framework of the reliability centered maintenance concept

International Nuclear Information System (INIS)

1992-07-01

Elevated safety requirements and ever increasing costs of maintenance of nuclear power plants stimulate the interest in different methods and approaches to optimize maintenance activities. Among different concepts, the Reliability Centered Maintenance (RCM) as an approach to improve Preventive Maintenance (PM) programmes is being widely discussed an applied in several IAEA Member States. In order to summarize basic principles and current implementation of the RCM, the IAEA organized a Consultants Meeting in November 1990. The report prepared during that meeting was discussed during the Technical Committee Meeting (TCM) held in May 1991. Numerous technical presentations as well as panel and plenary discussions took place at the TCM. This document contains the report of the Consultants Meeting (modified to include comments of the TCM), a summary of the most important discussions as well as all 14 papers presented at the TCM

The Radiation Safety Information Computational Center (RSICC): A Resource for Nuclear Science Applications

International Nuclear Information System (INIS)

Kirk, Bernadette Lugue

2009-01-01

The Radiation Safety Information Computational Center (RSICC) has been in existence since 1963. RSICC collects, organizes, evaluates and disseminates technical information (software and nuclear data) involving the transport of neutral and charged particle radiation, and shielding and protection from the radiation associated with: nuclear weapons and materials, fission and fusion reactors, outer space, accelerators, medical facilities, and nuclear waste management. RSICC serves over 12,000 scientists and engineers from about 100 countries. An important activity of RSICC is its participation in international efforts on computational and experimental benchmarks. An example is the Shielding Integral Benchmarks Archival Database (SINBAD), which includes shielding benchmarks for fission, fusion and accelerators. RSICC is funded by the United States Department of Energy, Department of Homeland Security and Nuclear Regulatory Commission.

77 FR 40622 - Mine Safety and Health Research Advisory Committee, National Institute for Occupational Safety...

Science.gov (United States)

2012-07-10

... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Mine Safety and Health Research Advisory Committee, National Institute for Occupational Safety and Health (MSHRAC, NIOSH..., oxygen supply partnership, safety culture, occupational health and safety management systems, preventing...

Nuclear Reaction Data Centers

International Nuclear Information System (INIS)

McLane, V.; Nordborg, C.; Lemmel, H.D.; Manokhin, V.N.

1988-01-01

The cooperating Nuclear Reaction Data Centers are involved in the compilation and exchange of nuclear reaction data for incident neutrons, charged particles and photons. Individual centers may also have services in other areas, e.g., evaluated data, nuclear structure and decay data, reactor physics, nuclear safety; some of this information may also be exchanged between interested centers. 20 refs., 1 tab

TAURUS, Post-processor of 3-D Finite Elements Plots

International Nuclear Information System (INIS)

Brown, B.E.; Hallquist, J.O.; Kennedy, T.

2002-01-01

Description of program or function: TAURUS reads the binary plot files generated by the LLNL three-dimensional finite element analysis codes, NIKE3D (NESC 9725), DYNA3D (NESC 9909), TACO3D (NESC 9838), TOPAZ3D (NESC9599) and GEMINI and plots contours, time histories, and deformed shapes. Contours of a large number of quantities may be plotted on meshes consisting of plate, shell, and solid type elements. TAURUS can compute a variety of strain measures, reaction forces along constrained boundaries, and momentum. TAURUS has three phases: initialization, geometry display with contouring, and time history processing

Occupational chemical exposures: a collaboration between the Georgia Poison Center and the Occupational Safety and Health Administration.

Science.gov (United States)

Tustin, Aaron W; Jones, Alison; Lopez, Gaylord P; Ketcham, Glenn R; Hodgson, Michael J

2018-01-01

In the United States, regional poison centers frequently receive calls about toxic workplace exposures. Most poison centers do not share call details routinely with governmental regulatory agencies. Worker health and safety could be enhanced if regulators such as the Occupational Safety and Health Administration (OSHA) had the ability to investigate these events and prevent similar incidents. With this goal in mind, the Georgia Poison Center (GPC) began referring occupational exposures to OSHA in July 2014. GPC began collecting additional employer details when handling occupational exposure calls. When workers granted permission, GPC forwarded call details to the OSHA Regional Office in Atlanta. These referrals enabled OSHA to initiate several investigations. We also analyzed all occupational exposures reported to GPC during the study period to characterize the events, detect violations of OSHA reporting requirements, and identify hazardous scenarios that could form the basis for future OSHA rulemaking or guidance. GPC was informed about 953 occupational exposures between 1 July, 2014 and 7 January, 2016. Workers were exposed to 217 unique substances, and 70.3% of victims received treatment in a healthcare facility. Hydrogen sulfide was responsible for the largest number of severe clinical effects. GPC obtained permission to refer 89 (9.3%) calls to OSHA. As a result of these referrals, OSHA conducted 39 investigations and cited 15 employers for "serious" violations. OSHA forwarded several other referrals to other regulatory agencies when OSHA did not have jurisdiction. At least one employer failed to comply with OSHA's new rule that mandates reporting of all work-related hospitalizations. This collaboration increased OSHA's awareness of dangerous job tasks including hydrofluoric acid exposure among auto detailers and carbon monoxide poisoning with indoor use of gasoline-powered tools. Collaboration with the GPC generated a useful source of referrals to OSHA. OSHA

Carbon Monoxide Information Center

Science.gov (United States)

... 한국어 Español ภาษาไทย Tiếng Việt Text Size: Decrease Font Increase Font Contact CPSC Consumers: Businesses: Report an Unsafe Product ... Guide View All CO Safety Guides ")); jQuery(".node-type-safety-education-center .region-sidebar-second").css('display', " ...

Report on administrative work at radiation safety center in fiscal year 2000

Energy Technology Data Exchange (ETDEWEB)

Uda, Tatsuhiko; Sakuma, Yoichi; Kawano, Takao; Yamanishi, Hirokuni; Shinotsuka, Kazunori; Asakura, Yamato; Miyake, Hitoshi

2002-05-01

National Institute for Fusion Science constructed Large Helical Device (LHD) which is the largest magnetic confinement plasma experimental device using super conductive magnet coils. It took eight years to construct and the first plasma shot had been carried out on March 1998. Since then plasma confinement experiments have been improved. This is the report of administrative work at the radiation safety center considering radiation protection for workers at the LHD and related devices, and radiation monitoring in the site. Major scope is as follows. (1) Radiation measurement and dose monitoring in the radiation controlled area and in the site using particularly developed monitoring system named as Radiation Monitoring System Applicable to Fusion Experiments (RMSAFE). (2) Establishment of education and registration system for radiation workers and access control system for the LHD controlled area. I hope that as like the published report of fiscal year 1999, the present report will be helpful for management of future radiation protection in the research institute. (author)

International Space Station (ISS) External Thermal Control System (ETCS) Loop A Pump Module (PM) Jettison Options Assessment

Science.gov (United States)

Murri, Daniel G.; Dwyer Cianciolo, Alicia; Shidner, Jeremy D.; Powell, Richard W.

2014-01-01

On December 11, 2013, the International Space Station (ISS) experienced a failure of the External Thermal Control System (ETCS) Loop A Pump Module (PM). To minimize the number of extravehicular activities (EVA) required to replace the PM, jettisoning the faulty pump was evaluated. The objective of this study was to independently evaluate the jettison options considered by the ISS Trajectory Operations Officer (TOPO) and to provide recommendations for safe jettison of the ETCS Loop A PM. The simulation selected to evaluate the TOPO options was the NASA Engineering and Safety Center's (NESC) version of Program to Optimize Simulated Trajectories II (POST2) developed to support another NESC assessment. The objective of the jettison analysis was twofold: (1) to independently verify TOPO posigrade and retrograde jettison results, and (2) to determine jettison guidelines based on additional sensitivity, trade study, and Monte Carlo (MC) analysis that would prevent PM recontact. Recontact in this study designates a propagated PM trajectory that comes within 500 m of the ISS propagated trajectory. An additional simulation using Systems Tool Kit (STK) was run for independent verification of the POST2 simulation results. Ultimately, the ISS Program removed the PM jettison option from consideration. However, prior to the Program decision, the retrograde jettison option remained part of the EVA contingency plan. The jettison analysis presented showed that, in addition to separation velocity/direction and the atmosphere conditions, the key variables in determining the time to recontact the ISS is highly dependent on the ballistic number (BN) difference between the object being jettisoned and the ISS.

A Comprehensive Analysis of the X-15 Flight 3-65 Accident

Science.gov (United States)

Dennehy, Cornelius J.; Orr, Jeb S.; Barshi, Immanuel; Statler, Irving C.

2014-01-01

The November 15, 1967, loss of X-15 Flight 3-65-97 (hereafter referred to as Flight 3-65) was a unique incident in that it was the first and only aerospace flight accident involving loss of crew on a vehicle with an adaptive flight control system (AFCS). In addition, Flight 3-65 remains the only incidence of a single-pilot departure from controlled flight of a manned entry vehicle in a hypersonic flight regime. To mitigate risk to emerging aerospace systems, the NASA Engineering and Safety Center (NESC) proposed a comprehensive review of this accident. The goal of the assessment was to resolve lingering questions regarding the failure modes of the aircraft systems (including the AFCS) and thoroughly analyze the interactions among the human agents and autonomous systems that contributed to the loss of the pilot and aircraft. This document contains the outcome of the accident review.

Shuttle Ground Support Equipment (GSE) T-0 Umbilical to Space Shuttle Program (SSP) Flight Elements Consultation

Science.gov (United States)

Wilson, Timmy R.; Kichak, Robert A.; McManamen, John P.; Kramer-White, Julie; Raju, Ivatury S.; Beil, Robert J.; Weeks, John F.; Elliott, Kenny B.

2009-01-01

The NASA Engineering and Safety Center (NESC) was tasked with assessing the validity of an alternate opinion that surfaced during the investigation of recurrent failures at the Space Shuttle T-0 umbilical interface. The most visible problem occurred during the Space Transportation System (STS)-112 launch when pyrotechnics used to separate Solid Rocket Booster (SRB) Hold-Down Post (HDP) frangible nuts failed to fire. Subsequent investigations recommended several improvements to the Ground Support Equipment (GSE) and processing changes were implemented, including replacement of ground-half cables and connectors between flights, along with wiring modifications to make critical circuits quad-redundant across the interface. The alternate opinions maintained that insufficient data existed to exonerate the design, that additional data needed to be gathered under launch conditions, and that the interface should be further modified to ensure additional margin existed to preclude failure. The results of the assessment are contained in this report.

Carbon Monoxide Information Center

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Full Text Available ... 한국어 Español ภาษาไทย Tiếng Việt Text Size: Decrease Font Increase Font Contact CPSC Consumers: Businesses: Report an Unsafe Product ... Guide View All CO Safety Guides ")); jQuery(".node-type-safety-education-center .region-sidebar-second").css('display', " ...

The International Science and Technology Center (ISTC) and ISTC projects related to nuclear safety. Information review

International Nuclear Information System (INIS)

Tocheny, Lev V.

2003-01-01

The ISTC is an intergovernmental organization created ten years ago by Russia, USA, EU and Japan in Moscow. The Center supports numerous science and technology projects in different areas, from biotechnologies and environmental problems to all aspects of nuclear studies, including those focused on the development of effective innovative concepts and technologies in the nuclear field, in general, and for improvement of nuclear safety, in particular. The presentation addresses some technical results of the ISTC projects as well as methods and approaches employed by the ISTC to foster close international collaboration and manage projects towards fruitful results. (author)

78 FR 40743 - Mine Safety and Health Research Advisory Committee, National Institute for Occupational Safety...

Science.gov (United States)

2013-07-08

... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Mine Safety and Health Research Advisory Committee, National Institute for Occupational Safety and Health (MSHRAC, NIOSH... Director, NIOSH, on priorities in mine safety and health research, including grants and contracts for such...

75 FR 12554 - Mine Safety and Health Research Advisory Committee, National Institute for Occupational Safety...

Science.gov (United States)

2010-03-16

... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Mine Safety and Health Research Advisory Committee, National Institute for Occupational Safety and Health (MSHRAC, NIOSH... priorities in mine safety and health research, including grants and contracts for such research, 30 U.S.C...

User-Centered Collaborative Design and Development of an Inpatient Safety Dashboard.

Science.gov (United States)

Mlaver, Eli; Schnipper, Jeffrey L; Boxer, Robert B; Breuer, Dominic J; Gershanik, Esteban F; Dykes, Patricia C; Massaro, Anthony F; Benneyan, James; Bates, David W; Lehmann, Lisa S

2017-12-01

Patient safety remains a key concern in hospital care. This article summarizes the iterative participatory development, features, functions, and preliminary evaluation of a patient safety dashboard for interdisciplinary rounding teams on inpatient medical services. This electronic health record (EHR)-embedded dashboard collects real-time data covering 13 safety domains through web services and applies logic to generate stratified alerts with an interactive check-box function. The technological infrastructure is adaptable to other EHR environments. Surveyed users perceived the tool as highly usable and useful. Integration of the dashboard into clinical care is intended to promote communication about patient safety and facilitate identification and management of safety concerns. Copyright © 2017 The Joint Commission. All rights reserved.

Status of Nuclear Safety evaluation in China

International Nuclear Information System (INIS)

Tian Jiashu

1999-01-01

Chinese nuclear safety management and control follows international practice, the regulations are mainly from IAEA with the Chinese condition. The regulatory body is National Nuclear Safety Administration (NNSA). The nuclear safety management, surveillance, safety review and evaluation are guided by NNSA with technical support by several units. Beijing Review Center of Nuclear Safety is one of these units, which was founded in 1987 within Beijing Institute of nuclear Engineering (BINE), co-directed by NNSA and BINE, it is the first technical support team to NNSA. Most of the safety reviews and evaluations of Chinese nuclear installations has been finished by this unit. It is described briefly in this paper that the NNSA's main function and organization, regulations on the nuclear safety, procedure of application and issuing of license, the main activities performed by Beijing Review Center of Nuclear Safety, the situation of severe accident analyses in China, etc. (author)

Safety climate and attitude as evaluation measures of organizational safety.

Science.gov (United States)

Isla Díaz, R; Díaz Cabrera, D

1997-09-01

The main aim of this research is to develop a set of evaluation measures for safety attitudes and safety climate. Specifically it is intended: (a) to test the instruments; (b) to identify the essential dimensions of the safety climate in the airport ground handling companies; (c) to assess the quality of the differences in the safety climate for each company and its relation to the accident rate; (d) to analyse the relationship between attitudes and safety climate; and (e) to evaluate the influences of situational and personal factors on both safety climate and attitude. The study sample consisted of 166 subjects from three airport companies. Specifically, this research was centered on ground handling departments. The factor analysis of the safety climate instrument resulted in six factors which explained 69.8% of the total variance. We found significant differences in safety attitudes and climate in relation to type of enterprise.

Report on administrative work at radiation safety center in fiscal year 2001

Energy Technology Data Exchange (ETDEWEB)

Uda, Tatsuhiko; Asakura, Yamato; Sakuma, Yoichi; Kawano, Takao; Yamanishi, Hirokuni; Sugiyama, Takahiko; Miyake, Hitoshi

2003-03-01

National Institute for Fusion Science constructed Large Helical Device (LHD) which is the largest magnetic confinement plasma experimental device using super conductive magnet coils. It took eight years to construct and the first plasma shot had been carried out on March 1998. In the experiments high plasma temperature and improved plasma confinement have been achieved. This is the report of administrative work at the radiation safety center considering radiation protection for workers at the LHD and related devices, and radiation monitoring in the site. Major scope is as follows. (1) Radiation measurement and dose monitoring in the radiation controlled area and in the site using particularly developed monitoring system named as Radiation Monitoring System Applicable to Fusion Experiments (RMSAFE). (2) Establishment of education and registration system for radiation workers and access control system for the LHD controlled area. I hope that as like the published reports of fiscal year 1999 and 2000, the present report will be helpful for management of future radiation protection in the research institute. (author)

Building Up an On-Line Plant Information System for the Emergency Response Center of the Hungarian Nuclear Safety Directorate

International Nuclear Information System (INIS)

Vegh, Janos; Major, Csaba; Horvath, Csaba; Hozer, Zoltan; Adorjan, Ferenc; Lux, Ivan; Horvath, Kristof

2002-01-01

The main design features, services, and human-machine interface characteristics are described of the CERTA VITA on-line plant information system developed and installed by KFKI AEKI at the Nuclear Safety Directorate (NSD) of the Hungarian Atomic Energy Authority (HAEA) in cooperation with experts from the NSD. The Center for Emergency Response, Training, and Analysis (CERTA) located at the headquarters of NSD, Budapest, Hungary, was established in 1997. The center supports the NSD installation, radiological monitoring, and advisory team in case of nuclear emergencies, with appropriate hardware and software for communication, diagnosis, prognosis, and prediction. The vital information transfer and analysis (VITA) system represents an important part of the CERTA, as it provides for the continuous remote inspection of the four VVER-440/V213 units of the Hungarian Paks nuclear power plant (NPP). The on-line information system maintains a continuous data link with the NPP through a managed leased line that connects CERTA to a gateway computer located at the Paks NPP. The present scope of the system is a result of a 4-yr development project: In addition to the basic safety parameter display functions, the VITA system now includes an on-line break parameter estimation module, an extensive training package based on simulated transients, and on-line data transfer capabilities to feed accident diagnosis/analysis codes

NASA Perspective and Modeling of Thermal Runaway Propagation Mitigation in Aerospace Batteries

Science.gov (United States)

Shack, P.; Iannello, C.; Rickman, S.; Button, R.

2014-01-01

NASA has traditionally sought to reduce the likelihood of a single cell thermal runaway (TR) in their aerospace batteries to an absolute minimum by employing rigorous screening program of the cells. There was generally a belief that TR propagation resulting in catastrophic failure of the battery was a forgone conclusion for densely packed aerospace lithium-ion batteries. As it turns out, this may not be the case. An increasing number of purportedly TR propagation-resistant batteries are appearing among NASA partners in the commercial sector and the Department of Defense. In the recent update of the battery safety standard (JSC 20793) to address this paradigm shift, the NASA community included requirements for assessing TR severity and identifying simple, low-cost severity reduction measures. Unfortunately, there are no best-practice guidelines for this work in the Agency, so the first project team attempting to meet these requirements would have an undue burden placed upon them. A NASA engineering Safety Center (NESC) team set out to perform pathfinding activities for meeting those requirements. This presentation will provide contextual background to this effort, as well as initial results in attempting to model and simulate TR heat transfer and propagation within battery designs.

Space Transportation System (STS)-133/External Tank (ET)-137 Intertank (IT) Stringer Cracking Issue and Repair Assessment: Proximate Cause Determination and Material Characterization Study

Science.gov (United States)

Piascik, Robert S.

2011-01-01

Several cracks were detected in stringers located beneath the foam on the External Tank (ET) following the launch scrub of Space Transportation System (STS)-133 on November 5, 2010. The stringer material was aluminum-lithium (AL-Li) 2090-T83 fabricated from sheets that were nominally 0.064 inches thick. The mechanical properties of the stringer material were known to vary between different material lots, with the stringers from ET-137 (predominately lots 620853 and 620854) having the highest yield and ultimate stresses. Subsequent testing determined that these same lots also had the lowest fracture toughness properties. The NASA Engineering and Safety Center (NESC) supported the Space Shuttle Program (SSP)-led investigation. The objective of this investigation was to develop a database of test results to provide validation for structural analysis models, independently confirm test results obtained from other investigators, and determine the proximate cause of the anomalous low fracture toughness observed in stringer lots 620853 and 620854. This document contains the outcome of the investigation.

Guidance, Navigation and Control (GN and C) Design Overview and Flight Test Results from NASA's Max Launch Abort System (MLAS)

Science.gov (United States)

Dennehy, Cornelius J.; Lanzi, Raymond J.; Ward, Philip R.

2010-01-01

The National Aeronautics and Space Administration Engineering and Safety Center designed, developed and flew the alternative Max Launch Abort System (MLAS) as risk mitigation for the baseline Orion spacecraft launch abort system already in development. The NESC was tasked with both formulating a conceptual objective system design of this alternative MLAS as well as demonstrating this concept with a simulated pad abort flight test. Less than 2 years after Project start the MLAS simulated pad abort flight test was successfully conducted from Wallops Island on July 8, 2009. The entire flight test duration was 88 seconds during which time multiple staging events were performed and nine separate critically timed parachute deployments occurred as scheduled. This paper provides an overview of the guidance navigation and control technical approaches employed on this rapid prototyping activity; describes the methodology used to design the MLAS flight test vehicle; and lessons that were learned during this rapid prototyping project are also summarized.

Contributions to nuclear safety and radiation technologies in Ukraine by the Science and Technology Center in Ukraine (STCU)

International Nuclear Information System (INIS)

Taranenko, L.; Janouch, F.; Owsiacki, L.

2001-01-01

This paper presents Science and Technology Center in Ukraine (STCU) activities devoted to furthering nuclear and radiation safety, which is a prioritized STCU area. The STCU, an intergovernmental organization with the principle objective of non-proliferation, administers financial support from the USA, Canada, and the EU to Ukrainian projects in various scientific and technological areas; coordinates projects; and promotes the integration of Ukrainian scientists into the international scientific community, including involving western collaborators. The paper focuses on STCU's largest project to date 'Program Supporting Y2K Readiness at Ukrainian NPPs' initiated in April 1999 and designed to address possible Y2K readiness problems at 14 Ukrainian nuclear reactors. Other presented projects demonstrate a wide diversity of supported directions in the fields of nuclear and radiation safety, including reactor material improvement ('Improved Zirconium-Based Elements for Nuclear Reactors'), information technologies for nuclear industries ('Ukrainian Nuclear Data Bank in Slavutich'), and radiation health science ('Diagnostics and Treatment of Radiation-Induced Injuries of Human Biopolymers').

Does Employee Safety Matter for Patients Too? Employee Safety Climate and Patient Safety Culture in Health Care.

Science.gov (United States)

Mohr, David C; Eaton, Jennifer Lipkowitz; McPhaul, Kathleen M; Hodgson, Michael J

2015-04-22

We examined relationships between employee safety climate and patient safety culture. Because employee safety may be a precondition for the development of patient safety, we hypothesized that employee safety culture would be strongly and positively related to patient safety culture. An employee safety climate survey was administered in 2010 and assessed employees' views and experiences of safety for employees. The patient safety survey administered in 2011 assessed the safety culture for patients. We performed Pearson correlations and multiple regression analysis to examine the relationships between a composite measure of employee safety with subdimensions of patient safety culture. The regression models controlled for size, geographic characteristics, and teaching affiliation. Analyses were conducted at the group level using data from 132 medical centers. Higher employee safety climate composite scores were positively associated with all 9 patient safety culture measures examined. Standardized multivariate regression coefficients ranged from 0.44 to 0.64. Medical facilities where staff have more positive perceptions of health care workplace safety climate tended to have more positive assessments of patient safety culture. This suggests that patient safety culture and employee safety climate could be mutually reinforcing, such that investments and improvements in one domain positively impacts the other. Further research is needed to better understand the nexus between health care employee and patient safety to generalize and act upon findings.

The advantages of reliability centered maintenance for standby safety systems

International Nuclear Information System (INIS)

Dam, R.F.; Ayazzudin, S.; Nickerson, J.H.; DeLong, A.I.

2002-01-01

Full text: On standby safety systems, nuclear plants have to balance the requirements of demonstrating the reliability of each system, while maintaining the system and plant availability. With the goal of demonstrating statistical reliability, these systems have extensive testing programs, which often makes the system unavailable and this can impact the plant capacity. The inputs to the process are often safety and regulatory related, resulting in programs that provide a high level of scrutiny on the systems being considered. In such cases, the value of the application of a maintenance optimization strategy, such as Reliability Centered Maintenance (RCM), is questioned. Part of the question stems from the use of the word 'Reliability' in RCM, which implies a level of redundancy when applied to a system maintenance program driven by reliability requirements. A deeper look at the RCM process, however, shows that RCM has the goal of ensuring that the system operates 'reliably' through the application of an integrated maintenance strategy. This is a subtle, but important distinction. Although the system reliability requirements are an important part of the strategy evaluation, RCM provides a broader context where testing is only one part of an overall strategy focused on ensuring that component function is maintained through a combination of monitoring technologies (including testing), predictive techniques, and intrusive maintenance strategies. Each strategy is targeted to identify known component degradation mechanisms. The conclusion is that a maintenance program driven by reliability requirements will tend to have testing defined at a frequency intended to support the needed statistics. The testing demonstrates that the desired function is available today. Maintenance driven by functional requirements and known failure causes, as developed through an RCM assessment, will have frequencies tied to industry experience with components and rely on a higher degree of

Space Transportation System (STS)-117 External Tank (ET)-124 Hail Damage Repair Assessment

Science.gov (United States)

Wilson, Timmy R.; Gentz, Steven J.; Barth, Timothy S.; Minute, Stephen A.; Flowers, Cody P.; Hamilton, David A.; Null, Cynthia H.; Schafer, Charles F.

2009-01-01

Severe thunderstorms with associated hail and high winds struck the STS-117 stack on February 26, 2007. Peak winds were recorded at 62 knots with hail sizes ranging from 0.3 inch to 0.8 inch in diameter. As a result of the storm, the North Carolina Foam Institute (NCFI) type 24-124 Thermal Protection System (TPS) foam on the liquid oxygen (LO2) ogive acreage incurred significant impact damage. The NCFI on the ET intertank and the liquid hydrogen (LH2) acreage sustained hail damage. The Polymer Development Laboratory (PDL)-1034 foam of the LO2 ice frost ramps (IFRs) and the Super-Lightweight Ablator (SLA) of the LO2 cable tray also suffered minor damage. NASA Engineering and Safety Center (NESC) was asked to assess the technical feasibility of repairing the ET TPS, the reasonableness of conducting those repairs with the vehicle in a vertical, integrated configuration at the Kennedy Space Center (KSC) Vehicle Assemble Building (VAB), and to address attendant human factors considerations including worker fatigue and the potential for error. The outcome of the assessment is recorded in this document.

Modeling to Mars: a NASA Model Based Systems Engineering Pathfinder Effort

Science.gov (United States)

Phojanamongkolkij, Nipa; Lee, Kristopher A.; Miller, Scott T.; Vorndran, Kenneth A.; Vaden, Karl R.; Ross, Eric P.; Powell, Bobby C.; Moses, Robert W.

2017-01-01

The NASA Engineering Safety Center (NESC) Systems Engineering (SE) Technical Discipline Team (TDT) initiated the Model Based Systems Engineering (MBSE) Pathfinder effort in FY16. The goals and objectives of the MBSE Pathfinder include developing and advancing MBSE capability across NASA, applying MBSE to real NASA issues, and capturing issues and opportunities surrounding MBSE. The Pathfinder effort consisted of four teams, with each team addressing a particular focus area. This paper focuses on Pathfinder team 1 with the focus area of architectures and mission campaigns. These efforts covered the timeframe of February 2016 through September 2016. The team was comprised of eight team members from seven NASA Centers (Glenn Research Center, Langley Research Center, Ames Research Center, Goddard Space Flight Center IV&V Facility, Johnson Space Center, Marshall Space Flight Center, and Stennis Space Center). Collectively, the team had varying levels of knowledge, skills and expertise in systems engineering and MBSE. The team applied their existing and newly acquired system modeling knowledge and expertise to develop modeling products for a campaign (Program) of crew and cargo missions (Projects) to establish a human presence on Mars utilizing In-Situ Resource Utilization (ISRU). Pathfinder team 1 developed a subset of modeling products that are required for a Program System Requirement Review (SRR)/System Design Review (SDR) and Project Mission Concept Review (MCR)/SRR as defined in NASA Procedural Requirements. Additionally, Team 1 was able to perform and demonstrate some trades and constraint analyses. At the end of these efforts, over twenty lessons learned and recommended next steps have been identified.

First Ph.D. Student Workshop of the Hermann von Helmholtz Association of National Research Centers (HGF) on ''Nuclear Safety Research''

International Nuclear Information System (INIS)

Knebel, J.U.; Sanchez Espinoza, V.H.

2006-03-01

The First Ph.D. Student Workshop ''Nuclear Safety Research'' of the Helmholtz Association of National Research Centers (HGF)'' was jointly organized by the Research Center Karlsruhe GmbH and the Energie Baden-Wuerttemberg AG (EnBW) from Wednesday 9th to Friday 11th March 2005. The workshop was opened with welcome greetings by Dr. Peter Fritz, Forschungszentrum Karlsruhe. Subsequently Dr. Joachim U. Knebel explained the main goals and the content of the workshop. The young scientists reported in 28 high-level presentations about their research work which covered a wide spectrum from reactor safety, partitions and transmutation, and innovative reactor systems, to safety research for nuclear waste disposal. The junior researchs showed excellent professional competence and demonstrated presentation qualities at the highest level. The successful funding of two Virtual Institutes, namely: the ''Competence in Nuclear Technologies'' and ''Functional Characteristics of Aquatic Interfaces both co-ordinated by Forschungszentrum Karlsruhe'', by the President of the Helmholtz Association Prof. Walter Kroell was the motivation for the organization of this first Ph.D. Student Workshop. Thanks to these two Virtual Institutes, the Reseach Center Karlsruhe and Juelich together with several univer-sities i.e. RWTH Aachen, Heidelberg, Karlsruhe, Muenster, and Stuttgart, have successfully financed eight Ph.D. and two post-doctoral students. Moreover, young scientists of the European Institute for Transuranium Elements (ITU) and additional seven Ph.D. Students, who are sponsored by the German nuclear industry (Framatome ANP, RWE Power, EnBW) in the frame of the Alliance Competence in on Nuclear Technology, and who are trained at Forschungszentrum Karlsruhe, actively contributed to this workshop. The EnBW-Award was handed over by Dr. Hans-Josef Zimmer, member of the board of directors of the EnBW-Kraftwerksgesellschaft, to Mrs. Ayelet Walter from the University of Stuttgart for the best

National Center for Food Safety and Technology

Science.gov (United States)

2013-12-05

on the Determination of Copper, Iron, Manganese and Zinc in Beef and Goat Liver American Chemical Society (ACS) – September, 2013 22. Meng Xu...addresses key food safety issues facing the country and supports the development of safe food with health-promoting properties from farm to fork. This...Reddy, Renate Reimschuessel. 2013. Proficiency Test on the Determination of Copper, Iron, Manganese and Zinc in Beef and Goat Liver American

Integrated Safety in ''SARAF'

International Nuclear Information System (INIS)

Dickstein, P.; Grof, Y.; Machlev, M.; Pernick, A.

2004-01-01

As of the very early stages of the accelerator project at the Soreq Nuclear Research Center ''SARAF'' a safety group was established which has been an inseparable participant in the planning and design of the new facility. The safety group comprises of teams responsible for the shielding, radiation protection and general industrial safety aspects of ''SARAF''. The safety group prepared and documented the safety envelope for the accelerator, dealing with the safety requirements and guidelines for the first, pre-operational, stages of the project. The safety envelope, though based upon generic principles, took into account the accelerator features and the expected modes of operation. The safety envelope was prepared in a hierarchical structure, containing Basic Principles, Basic Guidelines, General Principles for Safety Implementation, Safety Requirements and Safety Underlining Issues. The above safety envelope applies to the entire facility, which entails the accelerator itself and the experimental areas and associated plant and equipment utilizing and supporting the production of the accelerated particle beams

Status of nuclear safety research - 2000

International Nuclear Information System (INIS)

Sobajima, Makoto; Sasajima, Hideo; Umemoto, Michitaka; Yamamoto, Toshihiro; Tanaka, Tadao; Togashi, Yoshihiro; Nakata, Masahito

2000-11-01

The nuclear safety research at JAERI is performed in accordance with the long term plan on nuclear research, development and use and the safety research yearly plan determined by the government and under close relationship to the related departments in and around the Nuclear Safety Research Center. The criticality accident having occurred in Tokai-mura in 1999 has been the highest level nuclear accident in Japan and ensuring safety in whole nuclear cycle is severely questioned. The causes of such an accident have to be clarified not only technical points but also organizational points, and it is extremely important to make efforts in preventing recurrence, to fulfill emergency plan and to improve the safety of whole nuclear fuel cycle for restoring the reliability by the people to nuclear energy system. The fields of conducting safety research are engineering safety research on reactor facilities and nuclear fuel cycle facilities including research on radioactive waste processing and disposal and research and development on future technology for safety improvement. Also, multinational cooperation and bilateral cooperation are promoted in international research organizations in the center to internationally share the recognition of world-common issues of nuclear safety and to attain efficient promotion of research and effective utilization of research resources. (author)

Nuclear safety endeavour in Korea

International Nuclear Information System (INIS)

Sang-hoon lee

1987-01-01

Korea's nuclear power plant program is growing. As it grows, nuclear safety becomes an important issue. This article traces the development of Korean nuclear power program, the structure of the nuclear industries, the Nuclear Safety Center and its roles in the regulation and licensing of nuclear power plant, and also identifies some of the activities carried out to enhance the safety of nuclear power plants. (author)

78 FR 64504 - Safety and Occupational Health Study Section (SOHSS), National Institute for Occupational Safety...

Science.gov (United States)

2013-10-29

... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Safety and Occupational Health Study Section (SOHSS), National Institute for Occupational Safety and Health (NIOSH or..., Number 177, Pages 56235-56236. Contact Person for More Information: Price Connor, Ph.D., NIOSH Health...

Improving patient safety in cardiothoracic surgery: an audit of surgical handover in a tertiary center.

Science.gov (United States)

Bauer, Natasha Johan

2016-01-01

Novel research has revealed that the relative risk of death increased by 10% and 15% for admissions on a Saturday and Sunday, respectively. With an imminent threat of 7-day services in the National Health Service, including weekend operating lists, handover plays a pivotal role in ensuring patient safety is paramount. This audit evaluated the quality, efficiency, and safety of surgical handover of pre- and postoperative cardiothoracic patients in a tertiary center against guidance on Safe Handover published by the Royal College of Surgeons of England and the British Medical Association. A 16-item questionnaire prospectively audited the nature, time and duration of handover, patient details, operative history and current clinical status, interruptions during handover, and difficulties cross-covering specialties over a month. Just over half (52%) of the time, no handover took place. The majority of handovers (64%) occurred over the phone; two-thirds of these were uninterrupted. All handovers were less than 10 minutes in duration. About half of the time, the senior house officer had previously met the registrar involved in the handover, but the overwhelming majority felt it would facilitate the handover process if they had prior contact. Patient details handed over 100% of the time included name, ward, and current clinical diagnosis. A third of the time, the patient's age, responsible consultant, and recent operations or procedures were not handed over, potentially compromising future management due to delays and lack of relevant information. Perhaps the most revealing result was that the overall safety of handover was perceived to be five out of ten, with ten being very safe with no aspects felt to impact negatively on optimal patient care. These findings were presented to the department, and a handover proforma was implemented. Recommendations included the need for a new face-to-face handover. A reaudit will evaluate the effects of these changes.

A knowledge-centered paradigm for operations and design

International Nuclear Information System (INIS)

Perin, C.

2005-01-01

A paradigm premised on the reactor design basis and on its systems, structures, and components also governs nuclear power plant operations. This machine-centered paradigm emphasizes a functional and discipline-based division of responsibilities, which can create hierarchical 'silos' and 'stovepipes' inhibiting the development and lateral exchange of knowledge about safety-critical system interactions. A knowledge-centered paradigm instead encourages the timely development, analysis, and exchange of information about system conditions and their likely consequences. This new paradigm puts operational focus on the importance of operating experience, informative root cause analyses, effective corrective actions, and cross-discipline exchange and cooperation. Although the knowledge-centered paradigm is already central to three main strategies of risk reduction, it is less likely to be recognized as such in terms of priorities, resources, and training: configuration control, control room operations, and root cause analysis. To maintain the capacity for safe shutdown and to preserve public trust, the knowledge-centered paradigm places as high a priority on interactions of safety-critical knowledge as it does on interactions of safety-critical systems, structures, and components. (author)

Transient analysis for resolving safety issues

International Nuclear Information System (INIS)

Chao, J.; Layman, W.

1987-01-01

The Nuclear Safety Analysis Center (NSAC) has a Generic Safety Analysis Program to help resolve high priority generic safety issues. This paper describes several high priority safety issues considered at NSAC and how they were resolved by transient analysis using thermal hydraulics and neutronics codes. These issues are pressurized thermal shock (PTS), anticipated transients without scram (ATWS), steam generator tube rupture (SGTR), and reactivity transients in light of the Chernobyl accident

Emergency Preparedness Safety Climate and Other Factors Associated With Mental Health Outcomes Among World Trade Center Disaster Evacuees.

Science.gov (United States)

Sherman, Martin F; Gershon, Robyn R; Riley, Halley E M; Zhi, Qi; Magda, Lori A; Peyrot, Mark

2017-06-01

We examined psychological outcomes in a sample of participants who evacuated from the World Trade Center towers on September 11, 2011. This study aimed to identify risk factors for psychological injury that might be amenable to change, thereby reducing adverse impacts associated with emergency high-rise evacuation. We used data from a cross-sectional survey conducted 2 years after the attacks to classify 789 evacuees into 3 self-reported psychological outcome categories: long-term psychological disorder diagnosed by a physician, short-term psychological disorder and/or memory problems, and no known psychological disorder. After nonmodifiable risk factors were controlled for, diagnosed psychological disorder was more likely for evacuees who reported lower "emergency preparedness safety climate" scores, more evacuation challenges (during exit from the towers), and evacuation-related physical injuries. Other variables associated with increased risk of psychological disorder outcome included gender (female), lower levels of education, preexisting physical disability, preexisting psychological disorder, greater distance to final exit, and more information sources during egress. Improving the "emergency preparedness safety climate" of high-rise business occupancies and reducing the number of egress challenges are potential strategies for reducing the risk of adverse psychological outcomes of high-rise evacuations. Focused safety training for individuals with physical disabilities is also warranted. (Disaster Med Public Health Preparedness. 2017;11:326-336).

Shields calculations for teletherapy equipment. Regulatory approach of the National Center of Nuclear Safety

International Nuclear Information System (INIS)

Fuente P, A. de la; Dumenigo G, C.; Quevedo G, J.R.; Lopez F, Y.

2006-01-01

The evaluation of applications of construction licenses for the new services of radiotherapy has occupied a significant space in the activity developed by the National Center of Nuclear Safety (CNSN) in the last 2 years. Presently work the experiences of the authors in the evaluation of the required shield for the local where cobalt therapy equipment and lineal accelerators of medical use are used its are exposed, the practical problems detected are approached during the application of the methodologies recommended in both cases and its are discussed which have been the suppositions of items accepted by the Regulatory Authority for the realization of these shield calculations. The accumulated experience allows to assure that the realistic application of the item data and the rational use of the engineering logic makes possible to design local for radiotherapy equipment that fulfill the established dose restrictions in the in use legislation in Cuba, without it implies an excessive expense of construction materials. (Author)

Investigation of radiation safety and safety culture of medical sanitation vocation in Suzhou

International Nuclear Information System (INIS)

Tang Bo; Tu Yu; Zhang Yin

2009-01-01

Objective: To investigate the construction of radiation safety and safety culture of medical sanitation vocation in Suzhou. Methods: All medical units registered in administration center of Suzhou were included. The above selected medical units were completely investigated, district and county under the same condition of quality control. Results: The radiation safety and safety culture are existing differences among different property and grade hospitals of medicai sanitation vocation in Suzhou. Conclusion: The construction of radiation safety and safety culture is generally occupying in good level in suhzou, but there are obvious differences among different property and grade hospitals. The main reason for the differences in the importance attached to by the hospital decision-making and department management officials as well as the staff personal. (authors)

78 FR 6820 - Patient Safety Organizations: Voluntary Relinquishment From Ryder Trauma Center

Science.gov (United States)

2013-01-31

... DEPARTMENT OF HEALTH AND HUMAN SERVICES Agency for Healthcare Research and Quality Patient Safety... Quality (AHRQ), HHS. ACTION: Notice of delisting. SUMMARY: The Patient Safety and Quality Improvement Act of 2005 (Patient Safety Act), Public Law 109-41, 42 U.S.C. 299b-21--b-26, provides for the formation...

Contributions to nuclear safety and radiation technologies in Ukraine by the Science and Technology Center in Ukraine (STCU)

Energy Technology Data Exchange (ETDEWEB)

Taranenko, L. E-mail: lyubov@stcu.kiev.ua; Janouch, F.; Owsiacki, L

2001-06-01

This paper presents Science and Technology Center in Ukraine (STCU) activities devoted to furthering nuclear and radiation safety, which is a prioritized STCU area. The STCU, an intergovernmental organization with the principle objective of non-proliferation, administers financial support from the USA, Canada, and the EU to Ukrainian projects in various scientific and technological areas; coordinates projects; and promotes the integration of Ukrainian scientists into the international scientific community, including involving western collaborators. The paper focuses on STCU's largest project to date 'Program Supporting Y2K Readiness at Ukrainian NPPs' initiated in April 1999 and designed to address possible Y2K readiness problems at 14 Ukrainian nuclear reactors. Other presented projects demonstrate a wide diversity of supported directions in the fields of nuclear and radiation safety, including reactor material improvement ('Improved Zirconium-Based Elements for Nuclear Reactors'), information technologies for nuclear industries ('Ukrainian Nuclear Data Bank in Slavutich'), and radiation health science ('Diagnostics and Treatment of Radiation-Induced Injuries of Human Biopolymers')

Rossendorf Research Center, Institute of Safety Research. Annual report 1991

International Nuclear Information System (INIS)

Boehmert, J.; Weiss, F.P.

1992-08-01

The working program covers above all topics concerning the assessment of design basis safety and the increase of operational safety of the WWER type reactors. The topics are directed to the WWER-440/213 type and to the WWER-1000 type, and are dealt with by the three departments, i.e. incident analysis, neutron embrittlement, and mechanical integrity. One paper is concerned with the determination of the neutron field of HERA. (orig.) [de

Proceeding of Radiation Safety and Environment

International Nuclear Information System (INIS)

1996-01-01

Scientific Presentation of Radiation Safety and Environment was held on 20-21 august 1996 at Center of Research Atomic Energy Pasar Jum'at, Jakarta, Indonesia. Have presented 50 papers about Radiation Safety, dosimetry and standardization, environment protection and radiation effect

Center for Worker's Compensation Studies

Data.gov (United States)

Federal Laboratory Consortium — The mission of the NIOSH Center for Workers’ Compensation Studies (CWCS) is to use workers’ compensation data and systems to improve workplace safety and health....

Progress of nuclear safety research. 2001

Energy Technology Data Exchange (ETDEWEB)

Anoda, Yoshinari; Sasajima, Hideo; Nishiyama, Yutaka (eds.) [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment] [and others

2001-10-01

JAERI is conducting nuclear safety research primarily at the Nuclear Safety Research Center in close cooperation with the related departments in accordance with the Long Term Plan for Development and Utilization of Nuclear Energy or the Safety Research Annual Plan issued by the Japanese government. The safety research at JAERI concerns the engineering safety of nuclear power plants and nuclear fuel cycle facilities, and radioactive waste management as well as advanced technology for safety improvement or assessment. Also, JAERI has conducted international collaboration to share the information on common global issues of nuclear safety. This report summarizes the nuclear safety research activities of JAERI from April 1999 through March 2001. (author)

Vocalist - an international programme for the validation of constraint based methodology in structural integrity

International Nuclear Information System (INIS)

Lidbury, D.; Bass, R.; Gilles, Ph.; Connors, D.; Eisele, U.; Keim, E.; Keinanen, H.; Marie, St.; Nagel, G.; Taylor, N.; Wadier, Y.

2001-01-01

The pattern of crack-tip stresses and strains causing plastic flow and fracture in components is different to that in test specimens. This gives rise to the so-called constraint effect. Crack-tip constraint in components is generally lower than in test specimens. Effective toughness is correspondingly higher. The fracture toughness measured on test specimens is thus likely to underestimate that exhibited by cracks in components. A 36-month programme was initiated in October 2000 as part of the Fifth Framework of the European Atomic Energy Community (EURATOM), with the objective of achieving (i) an improved defect assessment methodology for predicting safety margins; (ii) improved lifetime management arguments. The programme VOCALIST (Validation of Constraint Based Methodology in Structural Integrity) is one of a 'cluster' of Fifth Framework projects in the area of Plant Life Management (Nuclear Fission). VOCALIST is also an associated project of NESC (Network for Evaluating Steel Components). The present paper describes the aims and objectives of VOCALIST, its interactions with NESC, and gives details of its various Work Packages. (authors)

Vocalist - an international programme for the validation of constraint based methodology in structural integrity

Energy Technology Data Exchange (ETDEWEB)

Lidbury, D. [AEA Technology, Consulting (United Kingdom); Bass, R. [Oak Ridge National Lab., TN (United States); Gilles, Ph. [FRAMATOME, 92 - Paris-La-Defence (France); Connors, D. [BNFL Magnox Generation (United Kingdom); Eisele, U. [Multiphoton Absorption, MPA, Stuttgart (Germany); Keim, E. [Framatome ANP GmbH (Germany); Keinanen, H. [VTT Energy, Espoo (Finland); Marie, St. [CEA Saclay, Dept. de Mecanique et de Technologie, 91 - Gif sur Yvette (France); Nagel, G. [E.ON Kernraft (Germany); Taylor, N. [Joint Research Center, JRC-IAM (Netherlands); Wadier, Y. [Electricite de France (EDF), 93 - Saint-Denis (France). Dept. de Radioprotection

2001-07-01

The pattern of crack-tip stresses and strains causing plastic flow and fracture in components is different to that in test specimens. This gives rise to the so-called constraint effect. Crack-tip constraint in components is generally lower than in test specimens. Effective toughness is correspondingly higher. The fracture toughness measured on test specimens is thus likely to underestimate that exhibited by cracks in components. A 36-month programme was initiated in October 2000 as part of the Fifth Framework of the European Atomic Energy Community (EURATOM), with the objective of achieving (i) an improved defect assessment methodology for predicting safety margins; (ii) improved lifetime management arguments. The programme VOCALIST (Validation of Constraint Based Methodology in Structural Integrity) is one of a 'cluster' of Fifth Framework projects in the area of Plant Life Management (Nuclear Fission). VOCALIST is also an associated project of NESC (Network for Evaluating Steel Components). The present paper describes the aims and objectives of VOCALIST, its interactions with NESC, and gives details of its various Work Packages. (authors)

Vaccine Safety Datalink

Science.gov (United States)

The Vaccine Safety Datalink is part of the National Immunization Program within the Centers for Disease Control and Prevention and was started in recognition of gaps in the scientific knowledge of rare vaccine side effects.

The Austrian Research Centers activities in energy risks

International Nuclear Information System (INIS)

Sdouz, Gert

1998-01-01

Among the institutions involved in energy analyses in Austria the risk context is being treated by three different entities: the Energy Consumption Agency, internationally known as EVA, the Federal Environmental Protection Agency, or Urnweltbundesarnt assessing mainly the environmental risks involved and the Austrian Research Centers, working on safety and risk evaluation. The Austrian Research Center Seibersdorf draws form its proficiency in Reactor Safety and Fusion Research, two fields of experience it has been involved in since its foundation, for some 40 years now. Nuclear energy is not well accepted by the Austrian population. Therefore in our country only energy systems with advanced safety level might be accepted in the far future. This means that the development of methods to compare risks is an important task. The characteristics of energy systems featuring advanced safety levels are: A very low hazard potential and a focus on deterministic safety instead of probabilistic safety, meaning to rely on inherently safe physics concepts, confirmed by probabilistic safety evaluation results. This can be achieved by adequate design of fusion reactors, advanced fission reactors and all different renewable sources of energy

Handbook on data centers

CERN Document Server

Khan, Samee Ullah

2015-01-01

This handbook offers a comprehensive review of the state-of-the-art research achievements in the field of data centers. Contributions from international, leading researchers and scholars offer topics in cloud computing, virtualization in data centers, energy efficient data centers, and next generation data center architecture.  It also comprises current research trends in emerging areas, such as data security, data protection management, and network resource management in data centers. Specific attention is devoted to industry needs associated with the challenges faced by data centers, such as various power, cooling, floor space, and associated environmental health and safety issues, while still working to support growth without disrupting quality of service. The contributions cut across various IT data technology domains as a single source to discuss the interdependencies that need to be supported to enable a virtualized, next-generation, energy efficient, economical, and environmentally friendly data cente...

Central Safety Department. Annual report 1986

International Nuclear Information System (INIS)

Kiefer, H.; Koenig, L.A.

1987-03-01

The Safety Officer and the Security Officer are responsible for radiation protection and technical safety, both conventional and nuclear, for the physical protection as well as the safeguards of nuclear materials and radioactive substances within the Kernforschungszentrum Karlsruhe GmbH (KfK). To fulfill these functions they rely on the assistance of the Central Safety Department. The Central Safety Department is responsible for handling all problems of radiation protection, safety and security of the institutes and departments of the Karlsruhe Nuclear Research Center, for waste water activity measurements and environmental monitoring of the whole area of the Center, and for research and development work mainly focusing on nuclear safety and radiation protection measures. The r+d work concentrates on the following aspects: physical and chemical behavior of biologically particularly active radionuclides, behavior of HT in the air/plant/soil system, biophysics of multicellular systems, improvement in radiation protection measurement and personnel dosimetry. The report gives details of the different duties, indicates the results of 1986 routine tasks and reports about results of investigations and developments of the working groups of the Department. (orig.) [de

Crib Information Center

Science.gov (United States)

... 한국어 Español ภาษาไทย Tiếng Việt Text Size: Decrease Font Increase Font Contact CPSC Consumers: Businesses: Report an Unsafe Product ... Department of Health (HRSA) NICHD text4baby ")); jQuery(".node-type-safety-education-center .region-sidebar-second").css('display', " ...

Physical aspects of quality assurance in nuclear medicine and radiotherapy, regulatory approach of the National Nuclear Safety Center

International Nuclear Information System (INIS)

Gonzalez C, D.; Fuente P, A. de la; Quevedo G, J.R.; Lopez F, Y.; Varela C, C.

2006-01-01

The physical aspects of the quality guarantee in Nuclear Medicine and Radiotherapy its are of cardinal importance to guarantee the quality of the diagnoses and treatments that are carried out to the patients in this type of services. The OIEA, the OMS and other scientific and professional organizations have contributed significantly to the elaboration of recommendations, Protocols, etc. applicable in the quality control programs and safety of the Nuclear Medicine and Radiotherapy departments. In spite of the great effort developed in this sense the Installation of the programs of quality control and safety of the Nuclear Medicine and Radiotherapy departments can fail if the same ones are not based in three decisive elements that are: the existence of national regulations, the existence of the infrastructure required for it and the existence of enough qualified personnel to develop this programs. The present work shows the regulatory focus that on this topic, it has followed the National Center of Nuclear Safety of Cuba (CNSN). The same left of strengthen all the existent Synergies in the different organizations of the country and it went in two fundamental directions: installation of the regulatory requirements that govern this activity and the Authorization of a Cuban Entity, specialized in carrying out audits to the quality control and safety programs of the Nuclear Medicine and Radiotherapy departments. After 4 work years in this direction, the results confirm the validity of the experience developed by the CNSN, at the moment all the services of Nuclear Medicine and Radiotherapy of Cuba possess quality control and safety programs, these programs are annually Auditing by an Authorized entity by the CNSN and the Inspectors of the Regulatory Authority, control, during the inspections, the one execution of the established requirements in the national regulations. The work developed so far can serve, modestly, of reference to others countries of Latin America that

76 FR 45332 - Pipeline and Hazardous Materials Safety Administration

Science.gov (United States)

2011-07-28

... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration Office of... Hazardous Materials Safety Administration (PHMSA), DOT. ACTION: List of Applications for Modification of..., 2011. ADDRESSES: Record Center, Pipeline and Hazardous Materials Safety Administration, U.S. Department...

Impact of northern Eurasian snow cover in autumn on the warm Arctic-cold Eurasia pattern during the following January and its linkage to stationary planetary waves

Science.gov (United States)

Xu, Xinping; He, Shengping; Li, Fei; Wang, Huijun

2018-03-01

The connection between Eurasian snow cover (SC) in autumn and Eurasian winter mean surface air temperature (SAT) has been identified by many studies. However, some recent observations indicate that early and late winter climate sometimes shows an out-of-phase relationship, suggesting that the winter mean situation might obscure the important relationships that are relevant for scientific research and applications. This study investigates the relationship between October northern Eurasian SC (NESC; 58°-68°N, 30°-90°E) and Eurasian SAT during the winter months and finds a significant relationship only exists in January. Generally, following reduced October NESC, the East Asian trough and Ural high are intensified in January, and anomalous northeasterly winds prevail in mid-latitudes, causing cold anomalies over Eurasia. Meanwhile, anomalous southwesterly winds along the northern fringe of the Ural high favor warm anomalies in the Arctic. The dynamical mechanism for the connection between NESC in October and the warm Arctic-cold Eurasia (WACE) anomaly in January is further investigated from the perspective of quasi-stationary planetary wave activity. It is found that planetary waves with zonal wavenumber-1 (ZWN1) play a dominant role in this process. Specifically, the ZWN1 pattern of planetary-scale waves concurrent with October NESC anomaly extends from the surface to the upper-stratosphere. It persists in the stratosphere through November-December and propagates downward to the surface by the following January, making the connection between October NESC and January climate possible. Additionally, the influence of October NESC on the January WACE pattern has intensified since the early-2000s.

General aviation crash safety program at Langley Research Center

Science.gov (United States)

Thomson, R. G.

1976-01-01

The purpose of the crash safety program is to support development of the technology to define and demonstrate new structural concepts for improved crash safety and occupant survivability in general aviation aircraft. The program involves three basic areas of research: full-scale crash simulation testing, nonlinear structural analyses necessary to predict failure modes and collapse mechanisms of the vehicle, and evaluation of energy absorption concepts for specific component design. Both analytical and experimental methods are being used to develop expertise in these areas. Analyses include both simplified procedures for estimating energy absorption capabilities and more complex computer programs for analysis of general airframe response. Full-scale tests of typical structures as well as tests on structural components are being used to verify the analyses and to demonstrate improved design concepts.

Development and application of the analytical energy gradient for the normalized elimination of the small component method

NARCIS (Netherlands)

Zou, Wenli; Filatov, Michael; Cremer, Dieter

2011-01-01

The analytical energy gradient of the normalized elimination of the small component (NESC) method is derived for the first time and implemented for the routine calculation of NESC geometries and other first order molecular properties. Essential for the derivation is the correct calculation of the

Safety Precautions. Child Health and Safety Series (Module I).

Science.gov (United States)

Iscoe, Louise; And Others

This manual for parents and child care personnel in day care homes and centers provides guidelines and information on indoor and outdoor safety precautions, emergency preparation and first aid. Contents focus on monitoring arrivals and departures, prevention of suffocation and strangulation, control of pets and other animals, preventing and…

Live defibrillation in simulation-based medical education--a survey of simulation center practices and attitudes.

Science.gov (United States)

Turban, Joseph W; Peters, Deborah P; Berg, Benjamin W

2010-02-01

Resuscitation from cardiac arrhythmia, requiring cardioversion/defibrillation is a common simulation training scenario. Use of live defibrillation enhances simulation fidelity but is not without risk. This survey was conducted to describe the prevalence of live defibrillation use during training scenarios in healthcare simulation centers, and when used, if safety training was required before using live defibrillation. A convenience sample of attendees at the 7th annual International Meeting on Simulation in Healthcare (January 2007) was surveyed using a closed-ended 23-item survey instrument. Survey domains included responder and simulation center demographics, simulation center defibrillation safety policies, and attitudes toward defibrillation practices in simulation training environments. Fifty-seven individuals representing 39 simulation centers returned surveys, 29 of which were in the United States. Live defibrillation was used in 35 of the 39 centers (90%). A defibrillation safety training policy was in effect at 14 of 39 centers (36%). Formal training before using live defibrillation was considered necessary by 48 of 55 responders (87%). Forty-eight of 54 responders (89%) strongly agreed or agreed with the statement, "I feel using live defibrillation plays an important role in simulation-based education." Although most responders consider use of live defibrillation important and believe formal defibrillator safety training should be conducted before use, only about one third of the centers had a training policy in effect. It remains to be determined whether safety training before the use of live defibrillation during simulation-based education increases user safety.

Safety and Efficacy in Early Insulin Initiation as Comprehensive Therapy for Patients with Type 2 Diabetes in Primary Health Care Centers

Directory of Open Access Journals (Sweden)

Agung Pranoto

2015-04-01

Full Text Available Aim: to analyze the safety and efficacy of early insulin initiation therapy for patients with type 2 diabetes mellitus (T2DM in primary health care provided by general practitioners (GPs in Surabaya, East Java, Indonesia. Methods: pre-post study of ninety nine diabetic patients without previous insulin treatment with HbA1c levels >8% were involved in this study. The study was conducted in 10 primary health care centers in Surabaya between October 2011 to June 2012. Each patient received insulin therapy for 12 weeks. Laboratory examination was performed for each patient including fasting plasma glucose (FPG, 2 hours post-prandial plasma glucose (2hPPG and HbA1c examination before and after the study. Self monitoring blood glucose (SMBG examination was conducted in order to adjust the insulin dose and prevent the incidence of hypoglycemia. Data was statistically analyzed using paired-T test. Results: FPG level was decreased from baseline data (209 mg/dL to 152.07 mg/dL at the end of the study (Δ56.93 mg/dl; p=0.0001. The average of 2hPPG level was also decreased from 313.00 mg/dl to 220.72 mg/dL (Δ 92.28 mg/dL; p=0.0001. HbA1c was reduced from 11.60% at baseline to 8.95% at the end of study (Δ 2.65%; p=0.0001. Hypoglycemia was found in 6 patients (6.06% in this study, but all events were mild and did not need to be admitted to hospital. Conclusion: the safety of insulin therapy iniatiation might be provided by GPs at primary health centers with significant efficacy and minimal side effects. Key words: insulin, general practioner, primary health center.

Improving patient safety in cardiothoracic surgery: an audit of surgical handover in a tertiary center

Directory of Open Access Journals (Sweden)

Bauer NJ

2016-05-01

Full Text Available Natasha Johan Bauer Department of Cardiothoracic Surgery, Royal Brompton Hospital, London, UK Background: Novel research has revealed that the relative risk of death increased by 10% and 15% for admissions on a Saturday and Sunday, respectively. With an imminent threat of 7-day services in the National Health Service, including weekend operating lists, handover plays a pivotal role in ensuring patient safety is paramount. This audit evaluated the quality, efficiency, and safety of surgical handover of pre- and postoperative cardiothoracic patients in a tertiary center against guidance on Safe Handover published by the Royal College of Surgeons of ­England and the British Medical Association. Methods: A 16-item questionnaire prospectively audited the nature, time and duration of handover, patient details, operative history and current clinical status, interruptions during handover, and difficulties cross-covering specialties over a month. Results: Just over half (52% of the time, no handover took place. The majority of handovers (64% occurred over the phone; two-thirds of these were uninterrupted. All handovers were less than 10 minutes in duration. About half of the time, the senior house officer had previously met the registrar involved in the handover, but the overwhelming majority felt it would facilitate the handover process if they had prior contact. Patient details handed over 100% of the time included name, ward, and current clinical diagnosis. A third of the time, the patient’s age, responsible consultant, and recent operations or procedures were not handed over, potentially compromising future management due to delays and lack of relevant information. Perhaps the most revealing result was that the overall safety of handover was perceived to be five out of ten, with ten being very safe with no aspects felt to impact negatively on optimal patient care. Conclusion: These findings were presented to the department, and a handover proforma

Central Safety Department, annual report 1987

International Nuclear Information System (INIS)

Kiefer, H.; Koenig, L.A.

1988-02-01

The Central Safety Department is responsible for handling all problems of radiation protection, safety and security of the institutes and departments of the Karlsruhe Nuclear Research Center, for waste water activity measurements and environmental monitoring of the whole area of the Center, and for research and development work mainly focusing on nuclear safety and radiation protection measures. The r+d work concentrates on the following aspects: physical and chemical behaviour of biologically particularly active radionuclides, behaviour of HT in the air/plan/soil system, biophysics of multicellular systems, improvement in radiation protection measurement and personnel dosimetry. This report gives details of the different duties, indicates the results of 1987 routine tasks and reports about results of investigations and developments of the working groups of the Department. (orig./HP) [de

HSIP E911 Public Safety Answering Point (PSAP)

Data.gov (United States)

Earth Data Analysis Center, University of New Mexico — 911 Public Safety Answering Point (PSAP) service area boundaries in New Mexico According to the National Emergency Number Association (NENA), a Public Safety...

Drug Safety Crises Management in Pharmacovigilance

Directory of Open Access Journals (Sweden)

Gloria Shalviri

2018-05-01

Full Text Available Background: Adverse drug events can cause serious consequences including death. A published report by Lazarou et al in 1998 showed that adverse drug events were the 4th to 6th leading cause of death in the United States. These events may lead to drug safety crises in some issues, which need to take crises management process for solving the problem and/or preventing similar events.Objectives: To evaluate nature of drug safety crises based on adverse events reported to Iranian Pharmacovigilance Center from 1999 through 2012. To mention success and failure outcomes of crises management process taken against detected crises.Methods: All adverse drug events received by Iranian Pharmacovigilance Center from 1999 through 2012 were evaluated for reports with fatal outcome. All alerting letters and manuscripts published by the Center during the same period were reviewed for detailed information on detected crises. World Health Organization definition was used for detecting drug safety crises.Results: Among 42036 registered cases in our database, 463 deaths were recorded. The most frequent suspected drug for adverse events with fatal outcome was ceftriaxone (100 cases. Ten different drug safety crises issues were detected during the study period and their successful or failure outcomes were evaluated. There were 112 issued alerting letters and 17 published manuscript during the same period which was monitored for detailed information.  Conclusion: It is necessary for national pharmacovigilance centers to have prepared programs for crises management. This could be useful for reducing drug related mortality.

Selecting Optimal Control Portfolios to Improve Army Aviation Safety

National Research Council Canada - National Science Library

Shelton, Sarah

2001-01-01

.... The Safety Center chartered the Aviation Safety Investment Strategy Team to evaluate accidents to determine their hazards, or contributing conditions, and their controls, or reduction measures...

Calculations of electric dipole moments and static dipole polarizabilities based on the two-component normalized elimination of the small component method

Science.gov (United States)

Yoshizawa, Terutaka; Zou, Wenli; Cremer, Dieter

2016-11-01

The analytical energy gradient and Hessian of the two-component Normalized Elimination of the Small Component (2c-NESC) method with regard to the components of the electric field are derived and used to calculate spin-orbit coupling (SOC) corrected dipole moments and dipole polarizabilities of molecules, which contain elements with high atomic number. Calculated 2c-NESC dipole moments and isotropic polarizabilities agree well with the corresponding four-component-Dirac Hartree-Fock or density functional theory values. SOC corrections for the electrical properties are in general small, but become relevant for the accurate prediction of these properties when the molecules in question contain sixth and/or seventh period elements (e.g., the SO effect for At2 is about 10% of the 2c-NESC polarizability). The 2c-NESC changes in the electric molecular properties are rationalized in terms of spin-orbit splitting and SOC-induced mixing of frontier orbitals with the same j = l + s quantum numbers.

Calculations of electric dipole moments and static dipole polarizabilities based on the two-component normalized elimination of the small component method.

Science.gov (United States)

Yoshizawa, Terutaka; Zou, Wenli; Cremer, Dieter

2016-11-14

The analytical energy gradient and Hessian of the two-component Normalized Elimination of the Small Component (2c-NESC) method with regard to the components of the electric field are derived and used to calculate spin-orbit coupling (SOC) corrected dipole moments and dipole polarizabilities of molecules, which contain elements with high atomic number. Calculated 2c-NESC dipole moments and isotropic polarizabilities agree well with the corresponding four-component-Dirac Hartree-Fock or density functional theory values. SOC corrections for the electrical properties are in general small, but become relevant for the accurate prediction of these properties when the molecules in question contain sixth and/or seventh period elements (e.g., the SO effect for At 2 is about 10% of the 2c-NESC polarizability). The 2c-NESC changes in the electric molecular properties are rationalized in terms of spin-orbit splitting and SOC-induced mixing of frontier orbitals with the same j = l + s quantum numbers.

Increasing the operational efficiency and safety in operation control centers: the TRANSPETRO experience; Aumentando a seguranca e eficiencia operacional em centros de controle: a experiencia da TRANSPETRO

Energy Technology Data Exchange (ETDEWEB)

Felicio, Marco Aurelio Fierro; Frisoli, Caetano [PETROBRAS Transporte S.A. (TRANSPETRO), Rio de Janeiro, RJ (Brazil)

2009-12-19

The increase in operational efficiency and safety in operation control centers has been traditionally obtained through direct actions in the operational activity itself and on the resources and systems used for that. Modern supervisory and control systems, sophisticated simulation software, cutting-edge last generation equipment and installations, clear and comprehensive procedures definitions and intensive and constant training of the operation teams are, usually, the chosen paths followed by control centers in their incessant quest for increased operational efficiency and safety. This paper presents the path followed by the TRANSPETRO's National Operational Control Center - Natural Gas (Centro Nacional de Controle Operacional - CNCO-Gas) - that has not only focused with the traditional aspects above, but has also made intensive investments in systems and data base integrations, aiming at eliminating data inconsistencies and redundancies and at including automation, standardization and systematization of non-operational and complementary operational activities. These investments allowed TRANSPETRO CNCO-Gas face the big challenge of growing that TRANSPETRO's gas transportation activity is facing now and will be facing in the near future: from 2,600 km to 7,000 km of gas pipelines, and a volume of transported natural gas from 35 MMm{sup 3}/day to 100 MMm{sup 3}/day. (author)

Colorectal Cancer Safety Net: Is It Catching Patients Appropriately?

Science.gov (United States)

Althans, Alison R; Brady, Justin T; Times, Melissa L; Keller, Deborah S; Harvey, Alexis R; Kelly, Molly E; Patel, Nilam D; Steele, Scott R

2018-01-01

Disparities in access to colorectal cancer care are multifactorial and are affected by socioeconomic elements. Uninsured and Medicaid patients present with advanced stage disease and have worse outcomes compared with similar privately insured patients. Safety net hospitals are a major care provider to this vulnerable population. Few studies have evaluated outcomes for safety net hospitals compared with private institutions in colorectal cancer. The purpose of this study was to compare demographics, screening rates, presentation stage, and survival rates between a safety net hospital and a tertiary care center. Comparative review of patients at 2 institutions in the same metropolitan area were conducted. The study included colorectal cancer care delivered either at 1 safety net hospital or 1 private tertiary care center in the same city from 2010 to 2016. A total of 350 patients with colorectal cancer from each hospital were evaluated. Overall survival across hospital systems was measured. The safety net hospital had significantly more uninsured and Medicaid patients (46% vs 13%; p presentation, a similar percentage of patients at each hospital presented with stage IV disease (26% vs 20%; p = 0.06). For those undergoing resection, final pathologic stage distribution was similar across groups (p = 0.10). After a comparable median follow-up period (26.6 mo for safety net hospital vs 29.2 mo for tertiary care center), log-rank test for overall survival favored the safety net hospital (p = 0.05); disease-free survival was similar between hospitals (p = 0.40). This was a retrospective review, reporting from medical charts. Our results support the value of safety net hospitals for providing quality colorectal cancer care, with survival and recurrence outcomes equivalent or improved compared with a local tertiary care center. Because safety net hospitals can provide equivalent outcomes despite socioeconomic inequalities and financial constraints, emphasis should be focused

47 CFR 25.284 - Emergency Call Center Service.

Science.gov (United States)

2010-10-01

... mobile satellite service to end-user customers (part 25, subparts A-D) must provide Emergency Call Center... Center personnel must determine the emergency caller's phone number and location and then transfer or otherwise redirect the call to an appropriate public safety answering point. Providers of mobile satellite...

Safety of infliximab in Crohn's disease: a large single-center experience.

Science.gov (United States)

Hamzaoglu, H; Cooper, J; Alsahli, M; Falchuk, K R; Peppercorn, M A; Farrell, R J

2010-12-01

The aim of this study was to evaluate the short- and long-term safety experience of infliximab treatment in patients with Crohn's disease (CD) in clinical practice. The medical records of 297 consecutive patients with CD treated with infliximab at the Beth Israel Deaconess Medical Center were reviewed for demographic features and adverse events. The 297 patients received a total of 1794 infusions. Patients received a median of four infusions and had a median follow-up of 14.3 months. Forty-four patients (15%) experienced a serious adverse event, requiring the infusion to be stopped in 33 patients (11%). Acute infusion reactions occurred in 18 patients (6%) including respiratory problems in 10 patients (3%) and an anaphylactoid reaction in 1 patient (0.3%). Serum sickness-like disease occurred in one patient (0.3%) and three patients (1%) developed drug-induced lupus. One patient developed a probable new demyelination disorder. Eight patients (2.7%), all of whom were on concurrent immunosuppressants, developed a serious infection, one resulting in fatal sepsis. Six patients (2%) developed malignancies including two lymphomas and two skin cancers. A total of four (1.3%) deaths were observed (median age 72.5 years); two due to gastrointestinal bleeding, one due to sepsis, and one due to malignancy. While short- and long-term infliximab therapy was generally well tolerated, serious adverse events occurred in 15% of patients including drug-induced lupus, fatal sepsis, and malignancy. Concomitant immunosuppressants were significantly associated with infections and deaths, particularly among elderly patients. Copyright © 2010 Crohn's & Colitis Foundation of America, Inc.

Users Center closed May 2, 3, and 4 | News

Science.gov (United States)

Financial Officer Finance Section Office of the Chief Operating Officer Facilities Engineering Services Accelerator Division Accelerator Physics Center Office of the Chief Safety Officer Environment, Safety, Health and Quality Section Office of the Chief Project Officer Office of Project Support Services Office of

Center for Coastline Security Technology, Year-2

National Research Council Canada - National Science Library

Glegg, Stewart; Glenn, William; Furht, Borko; Beaujean, P. P; Frisk, G; Schock, S; VonEllenrieder, K; Ananthakrishnan, P; An, E; Granata, R

2007-01-01

...), the Imaging Technology Center, the Department of Computer Science and Engineering, and the University Consortium for Intermodal Transportation Safety and Security at Florida Atlantic University...

Advancement on safety management system of nuclear power for safety and non-anxiety of society

International Nuclear Information System (INIS)

Yoshikawa, Hidekazu

2004-01-01

Advancement on safety management system is investigated to improve safety and non-anxiety of society for nuclear power, from the standpoint of human machine system research. First, the recent progress of R and D works of human machine interface technologies since 1980 s are reviewed and then the necessity of introducing a new approach to promote technical risk communication activity to foster safety culture in nuclear industries. Finally, a new concept of Offsite Operation and Maintenance Support Center (OMSC) is proposed as the core facility to assemble human resources and their expertise in all organizations of nuclear power, for enhancing safety and non-anxiety of society for nuclear power. (author)

Karlsruhe Research Center, Nuclear Safety Research Project (PSF). Annual report 1994

International Nuclear Information System (INIS)

Hueper, R.

1995-08-01

The reactor safety R and D work of the Karlsruhe Research Centre (FZKA) has been part of the Nuclear Safety Research Projet (PSF) since 1990. The present annual report 1994 summarizes the R and D results. The research tasks are coordinated in agreement with internal and external working groups. The contributions to this report correspond to the status of early 1995. An abstract in English precedes each of them, whenever the respective article is written in German. (orig.) [de

Summary of the Safety Culture Activities in HANARO of KAERI

International Nuclear Information System (INIS)

Lim, In-Cheol; Wu, Jong-Sup; Lee, Kye-Hong

2006-01-01

The definition of safety culture in HANARO takes the IAEA's definition and it is the assembly of characteristics of attitudes in the HANARO center and individuals which establishes that, as an overriding priority, the HANARO safety issues receive the attention warranted by their significance. Since the power operation of HANARO started in 1996, HANARO has been operated for about 11 years and its degree of utilization and the number of experimental facilities have increased. This achievement is partly due to the spread of safety culture to the operators and the reactor users. In this paper, the safety culture activities done by the HANARO center of KAERI are described, and its efforts necessary for an improvement of it are presented

Variations in hospital worker perceptions of safety culture

NARCIS (Netherlands)

Listyowardojo, Tita Alissa; Nap, Raoul E.; Johnson, Addie

Objective. To compare the attitudes toward and perceptions of institutional practices that can influence patient safety between all professional groups at a university medical center. Design. A questionnaire measuring nine dimensions of organizational and safety culture was distributed to all

Department of Agriculture, Food Safety and Inspection Service

Science.gov (United States)

... Standard Forms FSIS United States Department of Agriculture Food Safety and Inspection Service About FSIS District Offices Careers Contact Us Ask ... Reports Fact Sheets Food Defense and Emergency Response Food Safety Education FSIS ... Assistance Contact Centers Cooperative Agreements Email Subscription ...

The Aube Center evaluation 2002

International Nuclear Information System (INIS)

2003-01-01

During the meeting of the information local commission, organized the 7 may 2003, the ANDRA took stock on the Aube Center activities during the year 2002. These activities presented in the document concern: the stability of the wastes packages, the personnel safety, the environmental survey, the authorizations of releases, the public information, some data on the exploitation the environment and the radiation protection and a presentation of the storage Center of Morvilliers devoted to the storage of low activity wastes. (A.L.B.)

Ensuring the safety of future PCIVs : paper 09-0316.

Science.gov (United States)

2009-06-01

NHTSA, in partnership with Federal agencies, industry, and academia, will support research on safety-centered design and performance modeling and validation to enable and foster superior, integrated safety performance of future light-weight Plastics ...

Safety in paediatric imaging

International Nuclear Information System (INIS)

Carter, D.; Filice, I.; Murray, D.; Thomas, K.

2006-01-01

Those of us working in a dedicated paediatric environment are aware of the important safety issues with regard to paediatrics. Our goal when working with paediatric patients, the goal is to obtain the best quality images while keeping patients safe and their distress to a minimum. This article will discuss some of the issues regarding paediatric safety in a diagnostic imaging department, including radiation doses and the risk to paediatric patients, reducing medication errors, safe sedation practice and environmental safety. Also discussed are some conditions requiring special consideration to maintain patient safety such as epiglottitis and suspected child abuse. Promotion of a patient/family-centered care system will create an environment of trust where parents or guardians will know that their children are being well cared for in a safe, effective environment. (author)

Use of the Home Safety Self-Assessment Tool (HSSAT) within Community Health Education to Improve Home Safety.

Science.gov (United States)

Horowitz, Beverly P; Almonte, Tiffany; Vasil, Andrea

2016-10-01

This exploratory research examined the benefits of a health education program utilizing the Home Safety Self-Assessment Tool (HSSAT) to increase perceived knowledge of home safety, recognition of unsafe activities, ability to safely perform activities, and develop home safety plans of 47 older adults. Focus groups in two senior centers explored social workers' perspectives on use of the HSSAT in community practice. Results for the health education program found significant differences between reported knowledge of home safety (p = .02), ability to recognize unsafe activities (p = .01), safely perform activities (p = .04), and develop a safety plan (p = .002). Social workers identified home safety as a major concern and the HSSAT a promising assessment tool. Research has implications for reducing environmental fall risks.

78 FR 78362 - National Institute for Occupational Safety and Health Personal; Notice of public meeting in...

Science.gov (United States)

2013-12-26

... Institute for Occupational Safety and Health Personal; Notice of public meeting in Endicott, New York AGENCY: The National Institute for Occupational Safety and Health (NIOSH) of the Centers for Disease Control.... SUMMARY: The National Institute for Occupational Safety and Health (NIOSH) of the Centers for Disease...

75 FR 57477 - Patient Safety Organizations: Voluntary Delisting

Science.gov (United States)

2010-09-21

... Organizations: Voluntary Delisting AGENCY: Agency for Healthcare Research and Quality (AHRQ), HHS. ACTION... Creighton Center for Health Services Research and Patient Safety (CHRP) Patient Safety Organization (PSO... the listing of PSOs, which are entities or component organizations whose mission and primary activity...

Interdecadal change in the summer SST-precipitation relationship around the late 1990s over the South China Sea

Science.gov (United States)

Chen, Jiepeng; Wang, Xin; Zhou, Wen; Wen, Zhiping

2017-11-01

An interdecadal change in the air-sea interaction over the South China Sea (SCS) after the late 1990s has been identified using a local contemporaneous precipitation-sea surface temperature (SST) and precipitation-SST tendency relationship. During 1979-1998, there is a negative precipitation-SST relationship over the SCS, with a larger magnitude over the northeastern SCS (NESCS) than over the southwestern SCS (SWSCS). The remote effect of warmer SST over the tropical Indian Ocean plays a crucial role in a strong anticyclone and suppressed rainfall over the SCS and western North Pacific. Due to greater mixed-layer depth over the SWSCS than over the NESCS, entrainment heat flux makes a larger contribution to a positive precipitation-SST tendency over the SWSCS than over the NESCS. The cloud-radiation effect has a dominant and positive contribution to the SST tendency over the NESCS, whereas it has a negative contribution to SST tendency over the SWSCS. In contrast, the precipitation-SST correlation becomes weakly negative over the NESCS and significantly positive over the SWSCS during 1999-2013. The CESM-CAM5 model demonstrates that cooler SST over the tropical central-eastern Pacific (TCEP) triggers a weak anticyclone, slightly suppressing rainfall over the SCS. The cloud-radiation effect still contributes mostly to a positive SST tendency over the NESCS. Warmer SST over the SWSCS induces an increase in surface evaporation and low-level moisture convergence and causes enhanced rainfall. That offsets the remote effect of TCEP SST and results in a negative precipitation-SST tendency with negative cloud-radiation feedback. The interdecadal change in remote forcing to SCS rainfall around the late 1990s is related to the evolution of TCEP SST anomalies from the preceding winter to summer, which is possibly modulated by the phase of the Pacific Decadal Oscillation.

Safety assessment in primary Mycobacterium tuberculosis smear microscopy centres in Blantyre Malawi: a facility based cross sectional survey.

Science.gov (United States)

Majamanda, J; Ndhlovu, P; Shawa, I T

2013-12-01

Tuberculosis (TB) is caused by Mycobacterium tuberculosis and is transmitted mainly through aerosolization of infected sputum which puts laboratory workers at risk in spite of the laboratory workers' risk of infection being at 3 to 9 times higher than the general public. Laboratory safety should therefore be prioritized and optimized to provide sufficient safety to laboratory workers. To assess the safety for the laboratory workers in TB primary microscopy centres in Blantyre urban. TB primary microscopy centers in Blantyre urban were assessed in aspects of equipment availability, facility layout, and work practice, using a standardized WHO/AFRO ISO 15189 checklist for the developing countries which sets the minimum safety score at ≥80%. Each center was graded according to the score it earned upon assessment. Only one (1) microscopy center out nine (9) reached the minimum safety requirement. Four (4) centers were awarded 1 star level, four (4) centers were awarded 2 star level and only one (1) center was awarded 3 star level. In Blantyre urban, 89% of the Tuberculosis microscopy centers are failing to provide the minimum safety to the laboratory workers. Government and other stake holders should be committed in addressing the safety challenges of TB microscopy centres in the country to ensure safety for the laboratory workers. It is recommended that the study be conducted at the regional or national level for both public and private laboratories in order to have a general picture of safety in Tb microscopy centres possibly across the country.

Defining safety culture and the nexus between safety goals and safety culture. 4. Enhancing Safety Culture Through the Establishment of Safety Goals

International Nuclear Information System (INIS)

Tateiwa, Kenji; Miyata, Koichi; Yahagi, Kimitoshi

2001-01-01

efficient management. To seek compatibility between safety culture and efficient management, and to build an agreeable common perception among the utility, regulatory body, and the public on rationalizing the safety level to the extent acceptable, two issues must be considered: (a) establishing safety goals and (b) quantifying the safety culture. As for the first issue, currently no generic safety goal for the nuclear industry is available in Japan. This causes difficulty in deciding whether or not a specific action that takes place in a plant leading to a certain amount of risk increment is acceptable. Therefore, it is important for us to have a safety goal established. By establishing the safety goal, we could utilize it for the following usage: 1. to enable prompt response in case a safety level has entered an unacceptable level; 2. to sustain and enhance the safety culture centered by risk information (sustaining safety culture and achieving rational management simultaneously); 3. to use public relations for plant activities, where condemnation for overlooking safety culture might arrive for a minor risk increasing activity. As for the second issue, we must devise a method to quantify the level of safety culture. This could be done based on the safety culture indicators listed in the appendix of IAEA INSAG-4 (Ref. 1). By quantifying the level of safety culture, a comprehensive safety level of a plant can be evaluated by integrating with the safety level based on PSA. For example, when considering on-line maintenance for specific equipment, it is important not only to assess the safety level in terms of PSA but also to assess the level of safety culture in order to have a comprehensive view of the safety level and to compare it with the safety goal. By both establishing safety goals and quantifying the level of safety culture in a nuclear power plant, the ability to assess the comprehensive safety level of a plant and acknowledge the quantitative margin from the safety

Safety goals and safety culture opening plenary. 1. WANO's Role in Maintaining and Improving Safety Culture

International Nuclear Information System (INIS)

Tsutsumi, Ryosuke

2001-01-01

Over the past several years, operators of the world's nuclear plants have compiled an increasingly impressive record of operational performance. Among the many factors that have led to this improvement are the unprecedented cooperation and information exchange among the world's nuclear operators. This paper presents the World Association of Nuclear Operators (WANO) operating experience program and WANO peer review program as examples of the kinds of interaction that are occurring around the globe to maintain and improve the nuclear safety culture. In addition, some unique features of WANO are discussed. WANO has established four programs to help its members communicate effectively with each other. These include the exchange of operating experiences, voluntary peer reviews, professional and technical development, and technical support and exchange. The operating experience program alerts members to events that have occurred at other NPPs and enables members to take appropriate actions to prevent event recurrence. When an event occurs at a plant, management at that plant analyses the event and completes an event report, which is then sent to the WANO regional center to which the plant belongs. After a regional center review and necessary iteration, the report is posted onto the WANO Web site to make it available to all WANO members. By the end of 2000, more than 1500 event reports had been posted. The WANO Peer Review Program is a unique opportunity for members to learn and share the best worldwide insights into safe and reliable nuclear operations. The peer review program has become one of WANO's most important activities containing all essential elements of WANO's mission. A WANO peer review team consists of 15 to 16 people with NPP experience; most team members are from countries outside the one that they are visiting. These teams of peers from plants around the world visit host plants upon request to identify strengths and areas for improvement, with a strong

Progress of nuclear safety research-2004

International Nuclear Information System (INIS)

Anoda, Yoshinari; Ebine, Noriya; Chuto, Toshinori; Sato, Satoshi; Ishikawa, Jun; Yamamoto, Toshihiro; Munakata, Masahiro; Asakura, Toshihide; Yamaguchi, Tetsuji; Kida, Takashi; Matsui, Hiroki; Haneishi, Akihiro; Araya, Fumimasa

2005-03-01

JAERI is conducting nuclear safety research primarily at the Nuclear Safety Research Center in close cooperation with the related departments in accordance with the Long Term Plan for Development and Utilization of Nuclear Energy and Annual Plan for Safety Research issued by the Japanese government. The fields of conducting safety research at JAERI are the engineering safety of nuclear power plants and nuclear fuel cycle facilities, and radioactive waste management as well as advanced technology for safety improvement or assessment. Also, JAERI has conducted international collaboration to share the information on common global issues of nuclear safety and to supplement own research. Moreover, when accidents occurred at nuclear facilities, JAERI has taken a responsible role by providing technical experts and investigation for assistance to the government or local public body. This report summarizes the nuclear safety research activities of JAERI from April 2002 through March 2004 and utilized facilities. (author)

Short presentation of the activities of the Joint Research Center, Ispra establishment in the field of material research in reactor safety

Energy Technology Data Exchange (ETDEWEB)

Larsson, H [JRC, Ispra (Italy)

1977-07-01

The Commission of the European Communities (CEC) disposes of a joint Research Center (JRC) composed of four establishments. In the ISPRA establishment, which is the largest of four, the largest project, Reactor Safety, includes the following: reliability analysis; blowdown; sodium thermohydraulics; fuel-coolant interaction and post accident heat removal; dynamic structural loading and response (LMFBR); structural failure prevention. The last is described in this paper. It deals with: code validation program for primary containment response in a LMFBR following core disruptive accident (COVA); dynamic material testing; fracture mechanics; creep fatigue; creep crack growth; creep damage evaluation; non-destructive testing.

2011 NASA Range Safety Annual Report

Science.gov (United States)

Dumont, Alan G.

2012-01-01

Welcome to the 2011 edition of the NASA Range Safety Annual Report. Funded by NASA Headquarters, this report provides a NASA Range Safety overview for current and potential range users. As is typical with odd year editions, this is an abbreviated Range Safety Annual Report providing updates and links to full articles from the previous year's report. It also provides more complete articles covering new subject areas, summaries of various NASA Range Safety Program activities conducted during the past year, and information on several projects that may have a profound impact on the way business will be done in the future. Specific topics discussed and updated in the 2011 NASA Range Safety Annual Report include a program overview and 2011 highlights; Range Safety Training; Range Safety Policy revision; Independent Assessments; Support to Program Operations at all ranges conducting NASA launch/flight operations; a continuing overview of emerging range safety-related technologies; and status reports from all of the NASA Centers that have Range Safety responsibilities. Every effort has been made to include the most current information available. We recommend this report be used only for guidance and that the validity and accuracy of all articles be verified for updates. Once again the web-based format was used to present the annual report. We continually receive positive feedback on the web-based edition and hope you enjoy this year's product as well. As is the case each year, contributors to this report are too numerous to mention, but we thank individuals from the NASA Centers, the Department of Defense, and civilian organizations for their contributions. In conclusion, it has been a busy and productive year. I'd like to extend a personal Thank You to everyone who contributed to make this year a successful one, and I look forward to working with all of you in the upcoming year.

Proceeding of the Fifth Scientific Presentation on Nuclear Safety Technology

International Nuclear Information System (INIS)

Suhaemi, Tj.; Sudarno; Sunaryo, G. R.; Supriatna, P.; Antariksawan, A. R.; Sumijanto; Febrianto; Histori; Aliq

2000-01-01

The proceedings includes the result of research and development activities on nuclear safety technology that have been done by research Center for Nuclear Safety Technology in 2000 and was presented on June 28, 2000. The proceedings is expected to give illustration of the research result on Nuclear Safety Technology

Progress of nuclear safety research, (1)

International Nuclear Information System (INIS)

Amano, Hiroshi; Nakamura, Hiroei; Nozawa, Masao

1981-01-01

The Japan Atomic Energy Research Institute was established in 1956 in conformity with the national policy to extensively conduct the research associated with nuclear energy. Since then, the research on nuclear energy safety has been conducted. In 1978, the Division of Reactor Safety was organized to conduct the large research programs with large scale test facilities. Thereafter, the Divisions of Reactor Safety Evaluation, Environmental Safety Research and Reactor Fuel Examination were organized successively in the Reactor Safety Research Center. The subjects of research have ranged from the safety of nuclear reactors to that in the recycling of nuclear fuel. In this pamphlet, the activities in JAERI associated with the safety research are reported, which have been carried out in the past two years. Also, the international cooperation research program in which JAERI participated is included. This pamphlet consists of two parts, and in this Part 1, the reactor safety research is described. The safety of nuclear fuel, the integrity and safety of pressure boundary components, the engineered safety in LOCA, fuel behavior in accident and others are reported. (Kako, I.)

Assessment of the safety of injection practices and injection-related procedures in family health units and centers in Alexandria.

Science.gov (United States)

Elhoseeny, Taghareed A; Mourad, Juidan K

2014-08-01

The Safe Injection Global Network (SIGN) developed an intervention strategy for reducing overuse of injections and promoting the administration of safe injections. Tool C--Revised is designed to assess the safety of the most common procedures that puncture the skin within health services. The aim of the study was to assess injection safety within the primary healthcare facilities in Alexandria using Tool C--Revised. A total of 45 family health units and centers in Alexandria were selected by proportional allocation from the eight regions of Alexandria. The Tool C--Revised of the WHO was used for observation of the entire facility, injection practices and injection-related procedures, and sterilization practices. Interview of different health providers and immediate supervisor of injections was carried out. Indicators that reflect risk included: deficiency of alcohol-based hand rub for cleansing hands (13.3%), compliance with hand wash before preparing a procedure (56.9% before injection practices, 61.3% before phlebotomy, and 67.6% before lancet puncture), and wearing a new pair of gloves before new procedures (48.6% before injection practices, 9.7% for phlebotomy, 11.8% for lancet puncture, and 80% for both intravenous injections and infusions). Enough disposable equipment in all facilities for at least 2 weeks dependent on the statement of the average numbers of procedures per week was shown. Only 38% of the providers had received training regarding injection safety in the last 2 years and 62.5% had completed their three doses of hepatitis B vaccine. Only 42.2% of staffs who handled healthcare waste had access to heavy gloves. Indicators related to injection and injection-related practices that reflect risk to patients include deficiency of alcohol-based hand rub tools, nonadherence to hand hygiene before preparing an injection, and inadequate adherence to using a clean barrier when opening a glass ampule and use of gloves. Indicators that may reflect risk to

Annual report 1988 of the Central Safety Department

International Nuclear Information System (INIS)

Koelzer, W.; Urban, M.

1989-04-01

The Central Safety Department is responsible for handling all problems of radiation protection, safety and security of the institutes and departments of the Karlsruhe Nuclear Research Center, for waste water activity measurements and environmental monitoring of the whole area of the Center, and for research and development work mainly focusing on nuclear safety and radiation protection measures. The r+d work concentrates on the following aspects: physical and chemical behavior of biologically particularly active radionuclides, behavior of tritium in the air/plant/soil system, biophysics of multicellular systems, improvement in radiation protection measurement and personnel dosimetry. This report gives details of the different duties, indicates the results of 1988 routine tasks and reports about results of investigations and developments of the working groups of the Department. The reader is referred to the English translation of the Table of Contents and of Chapter 1 describing the duties and organization of the Central Safety Department. (orig./HP) [de

Annual report 1991 of the Central Safety Department

International Nuclear Information System (INIS)

Koelzer, W.

1992-04-01

The Central Safety Department is responsible for handling all problems of radiation protection, safety and security of the institutes and departments of the Karlsruhe Nuclear Research Center, for waste water activity measurements and environmental monitoring of the whole area of the Center, and for research and development work mainly focusing on nuclear safety and radiation protection measures. The research and development work concentrates on the following aspects: Physical and chemical behavior of trace elements in the environment, behavior of tritium in the air/plant/soil system, biophysics of multicellular systems, improvement in radiation protection measurement and personnel dosimetry. This report gives details of the different duties, indicates the results of 1989 routine tasks and reports about results of investigations and developments of the working groups of the Department. The reader is referred to the English translation of the Table of Contents and of Chapter 1 describing the duties and organization of the Central Safety Department. (orig.) [de

Annual report 1990 of the Central Safety Department

International Nuclear Information System (INIS)

Koelzer, W.; Urban, M.

1991-04-01

The Central Safety Department is responsible for handling all problems of radiation protection, safety and security of the institutes and departments of the Karlsruhe Nuclear Research Center, for waste water activity measurements and environmental monitoring of the whole area of the Center, and for research and development work mainly focusing on nuclear safety and radiation protection measures. The research and development work concentrates on the following aspects: Physical and chemical behavior of trace elements in the environment, behavior of tritium in the air/plant/soil system, biophysics of multicellular systems, improvement in radiation protection measurement and personnel dosimetry. This report gives details of the different duties, indicates the results of 1989 routine tasks and reports about results of investigations and developments of the working groups of the Department. The reader is referred to the English translation of the Table of Contents and of Chapter 1 describing the duties and organization of the Central Safety Department. (orig.) [de

Medicine safety and children

Science.gov (United States)

... it is candy. What to Do If Your Child Takes Medicine If you think your child has taken medicine, call the poison control center ... blood pressure monitored. Preventing Medicine Mistakes When giving medicine to your young child, follow these safety tips: Use medicine made only ...

GSFC Safety and Mission Assurance Organization

Science.gov (United States)

Kelly, Michael P.

2010-01-01

This viewgraph presentation reviews NASA Goddard Space Flight Center's approach to safety and mission assurance. The contents include: 1) NASA GSFC Background; 2) Safety and Mission Assurance Directorate; 3) The Role of SMA-D and the Technical Authority; 4) GSFC Mission assurance Requirements; 5) GSFC Systems Review Office (SRO); 6) GSFC Supply Chain Management Program; and 7) GSFC ISO9001/AS9100 Status Brief.

Proceedings of the Fourth Scientific Presentation on Reactor Safety Technology

International Nuclear Information System (INIS)

1999-01-01

The proceedings includes the result of research and development activities on nuclear safety technology that have been done by research Center for Nuclear Safety Technology in 1998/1999 and was presented on May 5, 1999. The proceedings is expected to give illustration of the research result on Nuclear Safety Technology

Range Flight Safety Requirements

Science.gov (United States)

Loftin, Charles E.; Hudson, Sandra M.

2018-01-01

The purpose of this NASA Technical Standard is to provide the technical requirements for the NPR 8715.5, Range Flight Safety Program, in regards to protection of the public, the NASA workforce, and property as it pertains to risk analysis, Flight Safety Systems (FSS), and range flight operations. This standard is approved for use by NASA Headquarters and NASA Centers, including Component Facilities and Technical and Service Support Centers, and may be cited in contract, program, and other Agency documents as a technical requirement. This standard may also apply to the Jet Propulsion Laboratory or to other contractors, grant recipients, or parties to agreements to the extent specified or referenced in their contracts, grants, or agreements, when these organizations conduct or participate in missions that involve range flight operations as defined by NPR 8715.5.1.2.2 In this standard, all mandatory actions (i.e., requirements) are denoted by statements containing the term “shall.”1.3 TailoringTailoring of this standard for application to a specific program or project shall be formally documented as part of program or project requirements and approved by the responsible Technical Authority in accordance with NPR 8715.3, NASA General Safety Program Requirements.

1978 annual report of the safety department

International Nuclear Information System (INIS)

Kiefer, H.; Koelzer, W.

1979-04-01

The Safety Officer and the Security Officer, respectively, are responsible for radiation protection and technical safety, both conventional and nuclear, for the physical protection as well as the security of nuclear materials and radioactive substances within the Kernforschungszentrum Karlsruhe GmbH. (KfK). To fulfill these functions they rely on the assitance of the Safety Department. The duties of this Department cover tasks relative to radiation protection, safety and security on behalf of the institutes and departments of KfK and environmental monitoring for the whole Karlsruhe Nuclear Research Center as well as research and development work, mainly performed under the Nuclear Safety Project and the Nuclear Safeguards Project. The centers of interest of r and d activities are: investigation of the atmospheric diffusion of nuclear pollutants on the micro- and meso-scales, evaluation of the radiological consequences of accidents in reactors under probabilistic aspects, studies of the physical and chemical behavior of radionuclides with particularly high biological effectiveness in the environment, implementation of nuclear fuel safequarding systems, improvements in radiation protection measurement technology. This report gives details of the different duties, indicates the results of 1978 routine tasks, and reports about new results of investigations and developments of the working groups of the Department. (orig.) [de

Annual Report 1979 of the Safety Department

International Nuclear Information System (INIS)

Kiefer, H.; Koelzer, W.; Koenig, L.A.

1980-04-01

The Safety Officer and the Security Officer, respectively, are responsible for radiation protection and technical safety, both conventional and nuclear, for the physical protection as well as the security of nuclear materials and radioactive substances within the Kernforschungszentrum Karlsruhe GmbH. (KfK). To fulfill these functions they rely on the assistance of the Safety Department. The duties of this Department cover tasks relative to radiation protection, safety and security on behalf of the institutes and departments of KfK and environmental monitoring for the whole Karlsruhe Nuclear Research Center as well as research and development work, mainly performed under the Nuclear Safety Project and the Nuclear Safeguards Project. The centers of interest of r and d activities are: investigation of the atmospheric diffusion of nuclear pollutants on the micro- and meso-scales, evaluation of the radiological consequences of accidents in reactors under probabilistic aspects, studies of the physical and chemical behavior of radionuclides with particularly high biological effectiveness in the environment, implemantation of nuclear fuel safeguarding systems, improvements in radiation protection measurement technology. This report gives details of the different duties, indicates the results of 1979 routine tasks, and reports about results of investigations and developments of the working groups of the Department. (orig.) [de

Sandia National Laboratories: Microsystems Science & Technology Center

Science.gov (United States)

Environmental Management System Pollution Prevention History 60 impacts Diversity Locations Facts & Figures Programs Nuclear Weapons About Nuclear Weapons Safety & Security Weapons Science & Technology Robotics R&D 100 Awards Laboratory Directed Research & Development Technology Deployment Centers

Commercial Motor Vehicle Driving Safety Website

OpenAIRE

Tidwell, Scott; Trimble, Tammy; Blanco, Myra

2016-01-01

This report documents the CMV Driving Safety website (http://cmvdrivingsafety.org/), which was created by the National Surface Transportation Safety Center for Excellence (NSTSCE) as an outreach effort to assist commercial motor vehicle (CMV) fleets and drivers, driver trainers, CMV training schools, and insurance companies. The website contains 15 unique pages and provides six downloadable training modules on driver distraction, driver health, hours of service, driver drowsiness and fatigue,...

The Community Health Applied Research Network (CHARN) Data Warehouse: a Resource for Patient-Centered Outcomes Research and Quality Improvement in Underserved, Safety Net Populations.

Science.gov (United States)

Laws, Reesa; Gillespie, Suzanne; Puro, Jon; Van Rompaey, Stephan; Quach, Thu; Carroll, Joseph; Weir, Rosy Chang; Crawford, Phil; Grasso, Chris; Kaleba, Erin; McBurnie, Mary Ann

2014-01-01

The Community Health Applied Research Network, funded by the Health Resources and Services Administration, is a research network comprising 18 Community Health Centers organized into four Research Nodes (each including an academic partner) and a data coordinating center. The network represents more than 500,000 diverse safety net patients across 11 states. The primary objective of this paper is to describe the development and implementation process of the CHARN data warehouse. The methods involved regulatory and governance development and approval, development of content and structure of the warehouse and processes for extracting the data locally, performing validation, and finally submitting data to the data coordinating center. Version 1 of the warehouse has been developed. Tables have been added, the population and the years of electronic health records (EHR) have been expanded for Version 2. It is feasible to create a national, centralized data warehouse with multiple Community Health Center partners using different EHR systems. It is essential to allow sufficient time: (1) to develop collaborative, trusting relationships among new partners with varied technology, backgrounds, expertise, and interests; (2) to complete institutional, business, and regulatory review processes; (3) to identify and address technical challenges associated with diverse data environments, practices, and resources; and (4) to provide continuing data quality assessments to ensure data accuracy.

Progress of nuclear safety research, (2)

International Nuclear Information System (INIS)

Amano, Hiroshi; Nakamura, Hiroei; Nozawa, Masao

1981-01-01

The Japan Atomic Energy Research Institute was established in 1956 in conformity with the national policy to extensively conduct the research associated with nuclear energy. Since then, the research on nuclear energy safety has been conducted. In 1978, the Division of Reactor Safety was organized to conduct the large research programs with large scale test facilities. Thereafter, the Divisions of Reactor Safety Evaluation, Environmental Safety Research and Reactor Fuel Examination were organized successevely in the Reactor Safety Research Center. The subjects of research have ranged from the safety of nuclear reactors to that in the recycling of nuclear fuel. In this pamphlet, the activities in JAERI associated with the safety research are reported, which have been carried out in the past two years. Also the international cooperation research program in which JAERI participated is included. This pamphlet consists of two parts and in this Part 2, the environmental safety research is described. The evaluation and analysis of environmental radioactivity, the study on radioactive waste management and the studies on various subjects related to environmental safety are reported. (Kako, I.)

The Potential Impact of Mars' Atmospheric Dust on Future Human Exploration of the Red Planet

Science.gov (United States)

Winterhalter, D.; Levine, J. S.; Kerschmann, R.; Beaty, D. W.; Carrier, B. L.; Ashley, J. W.

2017-12-01

With the increasing focus by NASA and other space agencies on a crewed mission to Mars in the 2039 time-frame, many Mars-specific environmental factors are now starting to be considered by NASA and other engineering teams. Learning from NASA's Apollo Missions to the Moon, where lunar dust turned out to be a significant challenge to mission and crew safety, attention is now turning to the dust in Mars' atmosphere and regolith. To start the process of identifying possible dust-caused challenges to the human presence on Mars, and thus aid early engineering and mission design efforts, the NASA Engineering and Safety Center (NESC) Robotic Spacecraft Technical Discipline Team organized and conducted a Workshop on the "Dust in Mars' Atmosphere and Its Impact on the Human Exploration of Mars", held at the Lunar and Planetary Institute (LPI), Houston, TX, June 13-15, 2017. The workshop addressed the following general areas: 1. What is known about Mars' dust in terms of its physical and chemical properties, its local and global abundance and composition, and its variability.2. What is the impact of Mars atmospheric dust on human health.3. What is the impact of Mars atmospheric dust on surface mechanical systems (e.g., spacesuits, habitats, mobility systems, etc.). We present the top priority issues identified in the workshop.

Probabilistic Analysis of a Composite Crew Module

Science.gov (United States)

Mason, Brian H.; Krishnamurthy, Thiagarajan

2011-01-01

An approach for conducting reliability-based analysis (RBA) of a Composite Crew Module (CCM) is presented. The goal is to identify and quantify the benefits of probabilistic design methods for the CCM and future space vehicles. The coarse finite element model from a previous NASA Engineering and Safety Center (NESC) project is used as the baseline deterministic analysis model to evaluate the performance of the CCM using a strength-based failure index. The first step in the probabilistic analysis process is the determination of the uncertainty distributions for key parameters in the model. Analytical data from water landing simulations are used to develop an uncertainty distribution, but such data were unavailable for other load cases. The uncertainty distributions for the other load scale factors and the strength allowables are generated based on assumed coefficients of variation. Probability of first-ply failure is estimated using three methods: the first order reliability method (FORM), Monte Carlo simulation, and conditional sampling. Results for the three methods were consistent. The reliability is shown to be driven by first ply failure in one region of the CCM at the high altitude abort load set. The final predicted probability of failure is on the order of 10-11 due to the conservative nature of the factors of safety on the deterministic loads.

A web-based tool for the Comprehensive Unit-based Safety Program (CUSP).

Science.gov (United States)

Pronovost, Peter J; King, Jay; Holzmueller, Christine G; Sawyer, Melinda; Bivens, Shauna; Michael, Michelle; Haig, Kathy; Paine, Lori; Moore, Dana; Miller, Marlene

2006-03-01

An organization's ability to change is driven by its culture, which in turn has a significant impact on safety. The six-step Comprehensive Unit-Based Safety Program (CUSP) is intended to improve local culture and safety. A Web-based project management tool for CUSP was developed and then pilot tested at two hospitals. HOW ECUSP WORKS: Once a patient safety concern is identified (step 3), a unit-level interdisciplinary safety committee determines issue criticality and starts up the projects (step 4), which are managed using project management tools within eCUSP (step 5). On a project's completion, the results are disseminated through a shared story (step 6). OSF St. Joseph's Medical Center-The Medical Birthing Center (Bloomington, Illinois), identified 11 safety issues, implemented 11 projects, and created 9 shared stories--including one for its Armband Project. The Johns Hopkins Hospital (Baltimore) Medical Progressive Care (MPC4) Unit identified 5 safety issues and implemented 4 ongoing projects, including the intravenous (IV) Tubing Compliance Project. The eCUSP tool's success depends on an organizational commitment to creating a culture of safety.

Environment, Health, and Safety | NREL

Science.gov (United States)

-Wide Environmental Assessment 2014 (DOE/EA-1914). Final EA and FONSI Appendices. Natural and Cultural property, and the environment. View the Environmental Stewardship, Health, Safety, and Quality Management Environmental Assessment 2014. Final EA and FONSI Appendices. Download the National Wind Technology Center Site

Safety parameter display system for Kalinin NPP

International Nuclear Information System (INIS)

Andreev, V.I.; Videneev, E.N.; Tissot, J.C.; Joonekindt, D.; Davidenko, N.N.; Shaftan, G.I.; Dounaev, V.G.; Neboyan, V.T.

1995-01-01

The paper discusses the safety parameter display system (SPDS), which is being designed for Kalinin NPP. The assessment of the safety status of the plant is done by the continuous monitoring of six critical safety functions and the corresponding status trees. Besides, a number of additional functions are realized within the scope of KlnNPP, aimed at providing the operator and the safety engineer in the main control room with more detailed information in accidental situation as well as during the normal operation. In particular, these functions are: archiving, data logs and alarm handling, safety actions monitoring, mnemonic diagrams indicating the state of main technological equipment and basic plant parameters, reference data, etc. As compared with the traditional scope of functions of this kind of systems, the functionality of KlnNPP SPDS is significantly expanded due to the inclusion in it the operator support function ''computerized procedures''. The basic SPDS implementation platform is ADACS of SEMA GROUP design. The system architecture includes two workstations in the main control room: one is for reactor operator and the other one for safety engineer. Every station has two CRT screens which ensures computerized procedures implementation and provides for extra services for the operator. Also, the information from the SPDS is transmitted to the local crisis center and to the crisis center of the State utility organization concern ''Rosenergoatom''. (author). 3 refs, 6 figs, 1 tab

Program integration of predictive maintenance with reliability centered maintenance

International Nuclear Information System (INIS)

Strong, D.K. Jr; Wray, D.M.

1990-01-01

This paper addresses improving the safety and reliability of power plants in a cost-effective manner by integrating the recently developed reliability centered maintenance techniques with the traditional predictive maintenance techniques of nuclear power plants. The topics of the paper include a description of reliability centered maintenance (RCM), enhancing RCM with predictive maintenance, predictive maintenance programs, condition monitoring techniques, performance test techniques, the mid-Atlantic Reliability Centered Maintenance Users Group, test guides and the benefits of shared guide development

Reactor Safety Assessment System

International Nuclear Information System (INIS)

Sebo, D.E.; Bray, M.A.; King, M.A.

1987-01-01

The Reactor Safety Assessment System (RSAS) is an expert system under development for the United States Nuclear Regulatory Commission (USNRC). RSAS is designed for use at the USNRC Operations Center in the event of a serious incident at a licensed nuclear power plant. RSAS is a situation assessment expert system which uses plant parametric data to generate conclusions for use by the NRC Reactor Safety Team. RSAS uses multiple rule bases and plant specific setpoint files to be applicable to all licensed nuclear power plants in the United States. RSAS currently covers several generic reactor categories and multiple plants within each category

Reactor safety assessment system

International Nuclear Information System (INIS)

Sebo, D.E.; Bray, M.A.; King, M.A.

1987-01-01

The Reactor Safety Assessment System (RSAS) is an expert system under development for the United States Nuclear Regulatory Commission (USNRC). RSA is designed for use at the USNRC Operations Center in the event of a serious incident at a licensed nuclear power plant. RSAS is a situation assessment expert system which uses plant parametric data to generate conclusions for use by the NRC Reactor Safety Team. RSAS uses multiple rule bases and plant specific setpoint files to be applicable to all licensed nuclear power plants in the United States. RSAS currently covers several generic reactor categories and multiple plants within each category

The initiative of the ICES MR: Children teach their parents[International Center for Environmental Safety of Minatom of Russia (ICES MR)

Energy Technology Data Exchange (ETDEWEB)

Krupenina, Faina [International Center for Environmental Safety of Minatom of Russia, (ICES MR), 26, Staromonetny per., 109180 Moscow (Russian Federation)

2002-07-01

Air and soil pollution, increased water discharge and energy consumption, forest and plant fires are often caused by low general and ecological culture. Nuclear power has long been a main target of environmental campaigners, in Europe as well as America. The past 200 years have seemed to reinforce their case: the Chernobyl accident was compounded by fears that a similar disaster could occur in any of the antiquated graphite-cooled reactors, revelations that leaks and mishaps from Windscale/Sellafield were far worse than originally reported, campaigns against reprocessing in Germany and Japan and alarming data on nuclear hazards from sunken Russian submarines and leaking waste storage tanks. The International Center for Environmental Safety of Minatom of Russia (ICES MR) is an autonomous non-commercial organisation. The mission of the Center is to assist in environment improving and consolidation of international contacts in environmental safety, to assist in development of te positive public perception of nuclear power. We attach great significance to interaction with the public, administrations of regions and State Duma deputies. Very often a dread of radiation and protests against nuclear power development are caused by lack or insufficiency of information concerning what is radiation, how it influences a human being and nature, where is real and not made-up danger. Here it is very important to organize work with the youth. Our first experience was a Children Ecological Olympiad 'Sozvezdie'. The Olympiad was held in the Russian Cosmonauts Training Center in Zvezdny gorodok in May 2001. It has a success and showed the strong interest of schoolchildren, their parents and teachers in environmental problems, in the nuclear power as an environment friendly energy production. Together with the UNESCO department and the Youth Department of Russian Nuclear Society for youth interaction we have prepared proposals concerning establishing Youth Environmental Centers in

Leadership, safety climate, and continuous quality improvement: impact on process quality and patient safety.

Science.gov (United States)

McFadden, Kathleen L; Stock, Gregory N; Gowen, Charles R

2014-10-01

Successful amelioration of medical errors represents a significant problem in the health care industry. There is a need for greater understanding of the factors that lead to improved process quality and patient safety outcomes in hospitals. We present a research model that shows how transformational leadership, safety climate, and continuous quality improvement (CQI) initiatives are related to objective quality and patient safety outcome measures. The proposed framework is tested using structural equation modeling, based on data collected for 204 hospitals, and supplemented with objective outcome data from the Centers for Medicare and Medicaid Services. The results provide empirical evidence that a safety climate, which is connected to the chief executive officer's transformational leadership style, is related to CQI initiatives, which are linked to improved process quality. A unique finding of this study is that, although CQI initiatives are positively associated with improved process quality, they are also associated with higher hospital-acquired condition rates, a measure of patient safety. Likewise, safety climate is directly related to improved patient safety outcomes. The notion that patient safety climate and CQI initiatives are not interchangeable or universally beneficial is an important contribution to the literature. The results confirm the importance of using CQI to effectively enhance process quality in hospitals, and patient safety climate to improve patient safety outcomes. The overall pattern of findings suggests that simultaneous implementation of CQI initiatives and patient safety climate produces greater combined benefits.

Physical safety: using of multimedia technology

International Nuclear Information System (INIS)

Munoz Garcia, M.

1995-01-01

For managing physical safety systems in nuclear power plants sophisticated computer equipment is essential. Standard safety procedure requires systems distributed throughout the plant, especially at security posts: Entrance Door, Access Control Center, Restricted Areas, etc. Besides being highly distributed, computerized physical safety management systems have always been characterized by the need to integrate very different elements. Graphic images have always played a very important role: photographs, fingerprints, signatures, etc. This makes integrated multimedia modules the ideal solution. This presentation describes how safety systems can combine not only still images, but also other multimedia data such as sound and video. It examines methodologies for using this new technology to upgrade high cost computer systems already in operation that can not be replaced. (Author)

Implementation of the INEEL safety analyst training standard

International Nuclear Information System (INIS)

Hochhalter, E. E.

2000-01-01

The Idaho Nuclear Technology and Engineering Center (INTEC) safety analysis units at the Idaho National Engineering and Environmental Laboratory (INEEL) are in the process of implementing the recently issued INEEL Safety Analyst Training Standard (STD-1107). Safety analyst training and qualifications are integral to the development and maintenance of core safety analysis capabilities. The INEEL Safety Analyst Training Standard (STD-1107) was developed directly from EFCOG Training Subgroup draft safety analyst training plan template, but has been adapted to the needs and requirements of the INEEL safety analysis community. The implementation of this Safety Analyst Training Standard is part of the Integrated Safety Management System (ISMS) Phase II Implementation currently underway at the INEEL. The objective of this paper is to discuss (1) the INEEL Safety Analyst Training Standard, (2) the development of the safety analyst individual training plans, (3) the implementation issues encountered during this initial phase of implementation, (4) the solutions developed, and (5) the implementation activities remaining to be completed

30 CFR 75.812 - Movement of high-voltage power centers and portable transformers; permit.

Science.gov (United States)

2010-07-01

... portable transformers; permit. 75.812 Section 75.812 Mineral Resources MINE SAFETY AND HEALTH... transformers; permit. [Statutory Provisions] Power centers and portable transformers shall be deenergized... than such centers or transformers is not available, the Secretary may permit such centers and...

Use of Opioid Medications for Employees in Critical Safety or Security Positions and Positions with Safety Sensitive Duties

Science.gov (United States)

2017-01-30

can cause harm) to the physical well-being of or jeopardize the security of the employee , co-workers, customers or the general public through a lapse...DEPARTMENT OF THE ARMY US ARMY PUBLIC HEALTH CENTER 5158 BLACKHAWK ROAD ABERDEEN PROVING GROUND MARYLAND 21010-5403 Directorate of Clinical... Employees in Critical Safety or Security Positions and Positions with Safety Sensitive Duties. 1. REFERENCES. A. Army Regulation 40-5, Preventive

Airline Safety and Economy

Science.gov (United States)

1993-01-01

This video documents efforts at NASA Langley Research Center to improve safety and economy in aircraft. Featured are the cockpit weather information needs computer system, which relays real time weather information to the pilot, and efforts to improve techniques to detect structural flaws and corrosion, such as the thermal bond inspection system.

Development of a safety management protocol.

Science.gov (United States)

2008-09-01

The UC Berkeley Traffic Safety Center (TSC) has produced this report under a contract from the California Department of Transportation : (Caltrans). The aim is to address workplace injuries and accidents among Caltrans employees and develop recommend...

Annual report 1982 of the Central Safety Department

International Nuclear Information System (INIS)

Kiefer, H.; Koelzer, W.; Koenig, L.A.

1983-04-01

The Safety Officer and the Security Officer are responsible for radiation protection and technical safety, both conventional and nuclear, for the physical protection as well as the safeguards of nuclear materials and radioactive substances within the Kernforschungszentrum Karlsruhe GmbH (KfK). To fulfill these functions they rely on the assistance of the Safety Department. The duties of this Department cover tasks relative to radiation protection, safety and security on behalf of the institutes and departments of KfK and environmental monitoring for the whole Karlsruhe Nuclear Research Center as well as research and development work, mainly performed under the Nuclear Safety Project. The centers of interest of r + d activities are: investigation of the atmospheric diffusion of nuclear pollutants on the micro- and meso-scales, evaluation of the radiological consequences of accidents in reactors under probabilistic aspects, studies of the physical and chemical behavior of radionuclides with particularly high biological effectiveness in the environment, improvements in radiation protection measurement technology. This report gives details of the different duties, indicates the results of 1982 routine tasks and reports about results of investigations and developments of the working groups of the Department. The reader is referred to the English translation of the Table of Contents and of Chapter 1 describing the duties and organization of the Central Safety Department. (orig.) [de

Progress of nuclear safety research. 2002

Energy Technology Data Exchange (ETDEWEB)

Anoda, Yoshinari; Kudo, Tamotsu; Tobita, Tohru (eds.) [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment] (and others)

2002-11-01

JAERI is conducting nuclear safety research primarily at the Nuclear Safety Research Center in close cooperation with the related departments in accordance with the Long Term Plan for Development and Utilization of Nuclear Energy and Annual Plan for Safety Research issued by the Japanese government. The fields of conducting safety research at JAERI are the engineering safety of nuclear power plants and nuclear fuel cycle facilities, and radioactive waste management as well as advanced technology for safety improvement or assessment. Also, JAERI has conducted international collaboration to share the information on common global issues of nuclear safety and to supplement own research. Moreover, when accidents occurred at nuclear facilities, JAERI has taken a responsible role by providing technical experts and investigation for assistance to the government or local public body. This report summarizes the nuclear safety research activities of JAERI from April 2000 through April 2002 and utilized facilities. This report also summarizes the examination of the ruptured pipe performed for assistance to the Nuclear and Industrial Safety Agency (NISA) for investigation of the accident at the Hamaoka Nuclear Power Station Unit-1 on November, 2001. (author)

Progress of nuclear safety research - 2005

International Nuclear Information System (INIS)

Anoda, Yoshinari; Amaya, Masaki; Saito, Junichi; Sato, Atsushi; Sono, Hiroki; Tamaki, Hitoshi; Tonoike, Kotaro; Nemoto, Yoshiyuki; Motoki, Yasuo; Moriyama, Kiyofumi; Yamaguchi, Tetsuji; Araya, Fumimasa

2006-03-01

The Japan Atomic Energy Research Institute (JAERI), one of the predecessors of the Japan Atomic Energy Agency (JAEA), had conducted nuclear safety research primarily at the Nuclear Safety Research Center in close cooperation with the related departments in accordance with the Long Term Plan for Development and Utilization of Nuclear Energy and Five-Years Program for Safety Research issued by the Japanese government. The fields of conducting safety research at JAERI were the engineering safety of nuclear power plants and nuclear fuel cycle facilities, and radioactive waste management as well as advanced technology for safety improvement or assessment. Also, JAERI had conducted international collaboration to share the information on common global issues of nuclear safety and to supplement own research. Moreover, when accidents occurred at nuclear facilities, JAERI had taken a responsible role by providing experts in assistance to conducting accident investigations or emergency responses by the government or local government. These nuclear safety research and technical assistance to the government have been taken over as an important role by JAEA. This report summarizes the nuclear safety research activities of JAERI from April 2003 through September 2005 and utilized facilities. (author)

Improvement of the center boring device for the irradiated fuel pellets

Energy Technology Data Exchange (ETDEWEB)

Usami, Koji; Onozawa, Atsushi; Kimura, Yasuhiko; Sakuraba, Naotoshi; Shiina, Hidenori; Harada, Akito; Nakata, Masahito [Japan Atomic Energy Agency, Nuclear Science Research Inst., Tokai, Ibaraki (Japan)

2012-03-15

The power ramp tests performed at JMTR in Oarai R and D Center are objected to study the safety margin of the high burnup fuels. One of the important parameters measured during this test is the center temperature of the fuel pellet. For this measurement, a thermocouple is installed into the hole bored at the pellet center by the center boring device, which can fix the fuel pellet with the frozen CO{sub 2} gas during its boring process. At the Reactor Fuel Examination Facility (RFEF) in Tokai R and D Center, several improvements were applied for the previous boring device to gain its performance and reliability. The major improvements are the change of the drill bit, modification of the boring process and the optimization of the remote operability. The mock-up test will be performed with the irradiated fuel pellet to confirm the benefit of improvement. This study was conducted under a contract with the Nuclear and Industrial Safety Agency (NISA) of the Ministry of Economy, Trade and Industry (METI). (author)

The Implementation and Maintenance of a Behavioral Safety Process in a Petroleum Refinery

Science.gov (United States)

Myers, Wanda V.; McSween, Terry E.; Medina, Rixio E.; Rost, Kristen; Alvero, Alicia M.

2010-01-01

A values-centered and team-based behavioral safety process was implemented in a petroleum oil refinery. Employee teams defined the refinery's safety values and related practices, which were used to guide the process design and implementation. The process included (a) a safety assessment; (b) the clarification of safety-related values and related…

Proceedings of The First National Seminar on Safety, Public Health and Environment

International Nuclear Information System (INIS)

Hiswara, Eri; Bunawas; Dumais, Johannes P.; Alatas, Zubaidah; Melyani

2001-11-01

The first national seminar of safety, public health and environment was held in 23-24 Oct 2001 at the center for research and development of radiation safety and nuclear biomedicine natural energy agency, Indonesia have presented 27 papers, about safety, public health and environment the proceedings is expected to give illustration of the research result on safety, health and environment. (PPIN)

Nuclear safety culture based on the organizational and individual culture

International Nuclear Information System (INIS)

Li Jingxi; Ren Ou

2005-01-01

The nuclear safety culture is used increasingly and developed by countries that have nu- clear plants all over the world, since the term 'safety culture' was first introduced by IAEA in 1986. Enterprises culture reflects many terms in an enterprise, such as management level and staff quality. The safety culture is the center in a nuclear enterprises culture, and relates directly to the safety and outstanding achievement of operation. This paper discusses the nuclear safety culture from the viewpoints of the organizational and individual cultures. (authors)

Fuel safety research 1999

Energy Technology Data Exchange (ETDEWEB)

Uetsuka, Hiroshi (ed.) [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

2000-07-01

In April 1999, the Fuel Safety Research Laboratory was newly established as a result of reorganization of the Nuclear Safety Research Center, JAERI. The laboratory was organized by combining three laboratories, the Reactivity Accident Laboratory, the Fuel Reliability Laboratory, and a part of the Sever Accident Research Laboratory. Consequently, the Fuel Safety Research Laboratory is now in charge of all the fuel safety research in JAERI. Various types of experimental and analytical researches are conducted in the laboratory by using the unique facilities such as the Nuclear Safety Research Reactor (NSRR), the Japan Material Testing Reactor (JMTR), the Japan Research Reactor 3 (JRR-3) and hot cells in JAERI. The laboratory consists of five research groups corresponding to each research fields. They are; (a) Research group of fuel behavior under the reactivity initiated accident conditions (RIA group). (b) Research group of fuel behavior under the loss-of-coolant accident conditions (LOCA group). (c) Research group of fuel behavior under the normal operation conditions (JMTR/BOCA group). (d) Research group of fuel behavior analysis (FEMAXI group). (e) Research group of FP release/transport behavior from irradiated fuel (VEGA group). This report summarizes the outline of research activities and major outcomes of the research executed in 1999 in the Fuel Safety Research Laboratory. (author)

Advanced research workshop: nuclear materials safety

International Nuclear Information System (INIS)

Jardine, L J; Moshkov, M M.

1999-01-01

The Advanced Research Workshop (ARW) on Nuclear Materials Safety held June 8-10, 1998, in St. Petersburg, Russia, was attended by 27 Russian experts from 14 different Russian organizations, seven European experts from six different organizations, and 14 U.S. experts from seven different organizations. The ARW was conducted at the State Education Center (SEC), a former Minatom nuclear training center in St. Petersburg. Thirty-three technical presentations were made using simultaneous translations. These presentations are reprinted in this volume as a formal ARW Proceedings in the NATO Science Series. The representative technical papers contained here cover nuclear material safety topics on the storage and disposition of excess plutonium and high enriched uranium (HEU) fissile materials, including vitrification, mixed oxide (MOX) fuel fabrication, plutonium ceramics, reprocessing, geologic disposal, transportation, and Russian regulatory processes. This ARW completed discussions by experts of the nuclear materials safety topics that were not covered in the previous, companion ARW on Nuclear Materials Safety held in Amarillo, Texas, in March 1997. These two workshops, when viewed together as a set, have addressed most nuclear material aspects of the storage and disposition operations required for excess HEU and plutonium. As a result, specific experts in nuclear materials safety have been identified, know each other from their participation in t he two ARW interactions, and have developed a partial consensus and dialogue on the most urgent nuclear materials safety topics to be addressed in a formal bilateral program on t he subject. A strong basis now exists for maintaining and developing a continuing dialogue between Russian, European, and U.S. experts in nuclear materials safety that will improve the safety of future nuclear materials operations in all the countries involved because of t he positive synergistic effects of focusing these diverse backgrounds of

Report transparency and nuclear safety 2007 CEA Marcoule

International Nuclear Information System (INIS)

2007-01-01

This report presents the activities of the CEA Center of Marcoule for the year 2007. Since its creation in 1955 the center realizes industrial and scientific activities relative to the civil and military applications of the radioactivity. The actions concerning the safety, the radiation protection, the significant events, the release control and the environmental impacts and the wastes stored on the center are discussed. More especially the following two base activities are detailed: Atalante and Phenix. (A.L.B.)

Safety of atrial fibrillation ablation with novel multi-electrode array catheters on uninterrupted anticoagulation-a single-center experience.

LENUS (Irish Health Repository)

Hayes, Christopher Ruslan

2012-02-01

INTRODUCTION: A recent single-center report indicated that the performance of atrial fibrillation ablation in patients on uninterrupted warfarin using a conventional deflectable tip electrode ablation catheter may be as safe as periprocedural discontinuation of warfarin and bridging with heparin. Novel multi-electrode array catheters for atrial fibrillation ablation are currently undergoing clinical evaluation. While offering the possibility of more rapid atrial fibrillation ablation, they are stiffer and necessitate the deployment of larger deflectable transseptal sheaths, and it remains to be determined if they increase the risk of cardiac perforation and vascular injury. Such potential risks would have implications for a strategy of uninterrupted periprocedural anticoagulation. METHOD AND RESULTS: We audited the safety outcomes of our atrial fibrillation ablation procedures using multi-electrode array ablation catheters in patients on uninterrupted warfarin (CHADS2 score>or=2) and in patients not on warfarin (uninterrupted aspirin). Two bleeding complications occurred in 49 patients on uninterrupted warfarin, both of which were managed successfully without longterm sequelae, and no bleeding complication occurred in 32 patients not on warfarin (uninterrupted aspirin). There were no thromboembolic events or other complication with either anticoagulant regimen. CONCLUSION: Despite the larger diameter and increased stiffness of multi-electrode array catheters and their deflectable transseptal sheaths, their use for catheter ablation in patients with atrial fibrillation on uninterrupted warfarin in this single-center experience does not appear to be unsafe, and thus, an adequately powered multicenter prospective randomized controlled trial should be considered.

Real-time environmental monitoring at the Japan Nuclear Cycle Development Institute O-arai Engineering Center. Using the internet to promote safety and environmental transparency

International Nuclear Information System (INIS)

Motomatsu, Sheila; Nakashima Inoue, Naoko

2000-12-01

The report documents the results of an effort at the Japan Nuclear Cycle Development Institute O-arai Engineering Center (JNC/OEC) to provide via the Internet, in real-time, environmental monitoring data to promote safety and environmental transparency. Provided in Japanese as well as in English, the Internet site provides assurance that OEC nuclear operations are being conducted in a manner that is safe to both people in the surrounding area and the environment. This work conducted by Environmental Monitoring Team of the OEC Safety Administration Section fulfilled the assignment to release data real-time via the Internet tasked by the Information Disclosure Section of the JNC Headquarters Public Relations Division. The work conducted by the visiting exchange scientist fulfilled the experimental portion of Action Sheet 34 of the Agreement between JNC and DOE for Cooperation in Research and Development Concerning Nuclear Material Control and Accounting Measures for Safeguards and Nonproliferation. In Japan, the project for Action Sheet 34 Personnel Exchange on Remote Monitoring and Transparency' entailed both a study and an experiment on how remote monitoring technologies can be used to promote nonproliferation, environmental and safety transparency. Environmental airborne radionuclide monitoring falls under the definition of remote monitoring technology more broadly defined as 'remotely accessed unattended monitoring system technology'. (author)

Green light for the methodology file. Periodical safety review 2016 has begun

International Nuclear Information System (INIS)

2014-01-01

Every ten years, the organisational framework and the facilities of the Belgian Nuclear Research Center SCK-CEN are subject to an encompassing safety evaluation. Together with initiatives arising from the stress tests, a large number of safety studies and actions are scheduled until 2018. The article discusses the ongoing safety review.

White paper on nuclear safety in 1981

International Nuclear Information System (INIS)

1981-01-01

The measures to research, develop and utilize atomic energy in Japan have been strengthened since the Atomic Energy Act was instituted in 1955, always on the major premise of securing the safety. The Nuclear Safety Commission established in October, 1978, has executed various measures to protect the health and safety of the nation as the center of the atomic energy safety regulation administration in Japan. Now, the Nuclear Safety Commission has published this annual report on atomic energy safety, summarizing various activities for securing the safety of atomic energy since its establishment to the end of March, 1981. This report is the inaugural issue, and the course till the Nuclear Safety Commission has made its start is also described. The report is composed of general remarks, response to the TMI accident, the safety regulation and security of nuclear facilities, the treatment and disposal of radioactive wastes, the investigation of environmental radioactivity, the countermeasures for preventing disasters around nuclear power stations and others, the research on the safety of atomic energy, international cooperation, and the improvement of the basis for securing the safety. Various related materials are attached. (Kako, I.)

CLASSIFICATION AND COMPLEX STATE VALUE OF SHOPPING CENTERS: PROJECT-ORIENTED APPROACH

Directory of Open Access Journals (Sweden)

Юрій Павлович РАК

2016-02-01

Full Text Available Was done the analysis of projects objects of trade and entertainment centers from the perspective of improving the life safety and is proposed the definition of "Trade and entertainment center", "Trade and entertainment center" and "Complex value of trade and entertainment center." A classification of shopping centers on the classification criteria and the criteria are characterized by increased security status and attractiveness of their operation. The classification of trade and entertainment centers on the criteria of classification features were made. It characterizes the security situation and will increase the attractiveness of their operation. In the nearest future the most secure and modern TEC will be those buildings who will have unique qualities such as safety systems, excellent customer service, and thus by a high level of trust (the client to the mall. The important role will play those TEC, who have clearly formed value oriented project management, including communication values using innovative methods and models. Trade and entertainment centers as an organization are included in the complex process of interaction management. They being both as an enterprise that serves the public and satisfying a great range of his interests and architectural site, which is leased and increases the business attractiveness of the district of TEC location. This duality of the essence of TEC center makes difficult to assess the effectiveness of its security.

Aube storage center for short-lived low- and intermediate-level wastes. Annual report 2010

International Nuclear Information System (INIS)

2011-06-01

The National Radioactive Waste Management Agency (Andra), was established by the December 1991 Waste Act as a public body in charge of the long-term management of all radioactive waste, under the supervision of the Ministry of Ecology, Energy, Sustainable Development and the Sea (formerly the Ministry of Industry and the Ministry of Environment), and the Ministry of Research. The Andra operates two storage centers in the Aube region (France): the center for short-lived low- and intermediate-level wastes, and the center for very-low-level radioactive wastes. This document is the 2010 activity report of the center for short-lived low- and intermediate-level wastes. It presents a review of the activities of the center: presentation of the installations, safety and radiation protection, events or incidents, environmental monitoring, wastes management, public information, recommendations of the Health and safety Committee (CHSCT)

The Efficacy and Safety of Icotinib in Patients with Advanced Non-Small Cell Lung Cancer Previously Treated with Chemotherapy: A Single-Arm, Multi-Center, Prospective Study.

Directory of Open Access Journals (Sweden)

Xingsheng Hu

Full Text Available Icotinib is a small molecule targeting epidermal growth factor receptor tyrosine kinase, which shows non-inferior efficacy and better safety comparing to gefitinib in previous phase III trial. The present study was designed to further evaluate the efficacy and safety of icotinib in patients with advanced non-small-cell lung cancer (NSCLC previously treated with platinum-based chemotherapy.Patients with NSCLC progressing after one or two lines of chemotherapy were enrolled to receive oral icotinib (125 mg tablet, three times per day. The primary endpoint was progression-free survival. The secondary endpoints included overall survival, objective response rate, time to progression, quality of life and safety.From March 16, 2010 to October 9, 2011, 128 patients from 15 centers nationwide were enrolled, in which 124 patients were available for efficacy evaluation and 127 patients were evaluable for safety. The median progression-free survival and time to progression were 5.0 months (95%CI 2.9-6.6 m and 5.4 months (95%CI 3.1-7.9 m, respectively. The objective response rate and disease control rate were 25.8% and 67.7% respectively. Median overall survival exceeded 17.6 months (95%CI 14.2 m-NA according to censored data. Further follow-up of overall survival is ongoing. The most frequent treatment-related adverse events were rash (26%, 33/127, diarrhea (12.6%, 16/127 and elevation of transaminase (15.7%, 20/127.In general, this study showed similar efficacy and numerically better safety when compared with that in ICOGEN trial, further confirming the efficacy and safety of icotinib in treating patients with advanced NSCLC previously treated with chemotherapy.ClinicalTrials.gov NCT02486354.

The Efficacy and Safety of Icotinib in Patients with Advanced Non-Small Cell Lung Cancer Previously Treated with Chemotherapy: A Single-Arm, Multi-Center, Prospective Study.

Science.gov (United States)

Hu, Xingsheng; Zhang, Li; Shi, Yuankai; Zhou, Caicun; Liu, Xiaoqing; Wang, Dong; Song, Yong; Li, Qiang; Feng, Jifeng; Qin, Shukui; Xv, Nong; Zhou, Jianying; Zhang, Li; Hu, Chunhong; Zhang, Shucai; Luo, Rongcheng; Wang, Jie; Tan, Fenlai; Wang, Yinxiang; Ding, Lieming; Sun, Yan

2015-01-01

Icotinib is a small molecule targeting epidermal growth factor receptor tyrosine kinase, which shows non-inferior efficacy and better safety comparing to gefitinib in previous phase III trial. The present study was designed to further evaluate the efficacy and safety of icotinib in patients with advanced non-small-cell lung cancer (NSCLC) previously treated with platinum-based chemotherapy. Patients with NSCLC progressing after one or two lines of chemotherapy were enrolled to receive oral icotinib (125 mg tablet, three times per day). The primary endpoint was progression-free survival. The secondary endpoints included overall survival, objective response rate, time to progression, quality of life and safety. From March 16, 2010 to October 9, 2011, 128 patients from 15 centers nationwide were enrolled, in which 124 patients were available for efficacy evaluation and 127 patients were evaluable for safety. The median progression-free survival and time to progression were 5.0 months (95%CI 2.9-6.6 m) and 5.4 months (95%CI 3.1-7.9 m), respectively. The objective response rate and disease control rate were 25.8% and 67.7% respectively. Median overall survival exceeded 17.6 months (95%CI 14.2 m-NA) according to censored data. Further follow-up of overall survival is ongoing. The most frequent treatment-related adverse events were rash (26%, 33/127), diarrhea (12.6%, 16/127) and elevation of transaminase (15.7%, 20/127). In general, this study showed similar efficacy and numerically better safety when compared with that in ICOGEN trial, further confirming the efficacy and safety of icotinib in treating patients with advanced NSCLC previously treated with chemotherapy. ClinicalTrials.gov NCT02486354.

Testing Strategies and Methodologies for the Max Launch Abort System

Science.gov (United States)

Schaible, Dawn M.; Yuchnovicz, Daniel E.

2011-01-01

The National Aeronautics and Space Administration (NASA) Engineering and Safety Center (NESC) was tasked to develop an alternate, tower-less launch abort system (LAS) as risk mitigation for the Orion Project. The successful pad abort flight demonstration test in July 2009 of the "Max" launch abort system (MLAS) provided data critical to the design of future LASs, while demonstrating the Agency s ability to rapidly design, build and fly full-scale hardware at minimal cost in a "virtual" work environment. Limited funding and an aggressive schedule presented a challenge for testing of the complex MLAS system. The successful pad abort flight demonstration test was attributed to the project s systems engineering and integration process, which included: a concise definition of, and an adherence to, flight test objectives; a solid operational concept; well defined performance requirements, and a test program tailored to reducing the highest flight test risks. The testing ranged from wind tunnel validation of computational fluid dynamic simulations to component ground tests of the highest risk subsystems. This paper provides an overview of the testing/risk management approach and methodologies used to understand and reduce the areas of highest risk - resulting in a successful flight demonstration test.

Autonomous Aerobraking Development Software: Phase 2 Summary

Science.gov (United States)

Cianciolo, Alicia D.; Maddock, Robert W.; Prince, Jill L.; Bowes, Angela; Powell, Richard W.; White, Joseph P.; Tolson, Robert; O'Shaughnessy, Daniel; Carrelli, David

2013-01-01

NASA has used aerobraking at Mars and Venus to reduce the fuel required to deliver a spacecraft into a desired orbit compared to an all-propulsive solution. Although aerobraking reduces the propellant, it does so at the expense of mission duration, large staff, and DSN coverage. These factors make aerobraking a significant cost element in the mission design. By moving on-board the current ground-based tasks of ephemeris determination, atmospheric density estimation, and maneuver sizing and execution, a flight project would realize significant cost savings. The NASA Engineering and Safety Center (NESC) sponsored Phase 1 and 2 of the Autonomous Aerobraking Development Software (AADS) study, which demonstrated the initial feasibility of moving these current ground-based functions to the spacecraft. This paper highlights key state-of-the-art advancements made in the Phase 2 effort to verify that the AADS algorithms are accurate, robust and ready to be considered for application on future missions that utilize aerobraking. The advancements discussed herein include both model updates and simulation and benchmark testing. Rigorous testing using observed flight atmospheres, operational environments and statistical analysis characterized the AADS operability in a perturbed environment.

Volpe Center Annual Accomplishments: Advancing Transportation Innovation for the Public Good - January 2018

Science.gov (United States)

2018-01-01

The Volpe Centers Annual Accomplishments highlights our best work of 2017 and illustrates the sustained impact of the Volpe Center in supporting the U.S. DOTs top priorities and strategic goals: safety, infrastructure, innovation, and accountab...

National HTGR safety program

International Nuclear Information System (INIS)

Davis, D.E.; Kelley, A.P. Jr.

1982-01-01

This paper presents an overview of the National HTGR Program in the US with emphasis on the safety and licensing strategy being pursued. This strategy centers upon the development of an integrated approach to organizing and classifying the functions needed to produce safe and economical nuclear power production. At the highest level, four plant goals are defined - Normal Operation, Core and Plant Protection, Containment Integrity and Emergency Preparedness. The HTGR features which support the attainment of each goal are described and finally a brief summary is provided of the current status of the principal safety development program supporting the validation of the four plant goals

Annual report 1985 of the KfK Central Safety Department

International Nuclear Information System (INIS)

Kiefer, H.; Koelzer, W.; Koenig, L.A.

1986-04-01

The Central Safety Department is responsible for handling all problems of radiation protection, safety and security of the institutes and departments of the Karlsruhe Nuclear Research Center, for waste water activity measurements and environmental monitoring of the whole area of the Center, and for research and development work mainly focusing on nuclear safety and radiation protection measures. The r+d work concentrates on the following aspects: physical and chemical behavior of biologically particularly active radionuclides, behavior of HT in the air/plant/soil system, biophysics of multicellular systems, improvement in radiation protection measurement and personnel dosimetry. This report gives details of the different duties, indicates the results of 1985 routine tasks and reports about results of investigations and developments of the working groups of the Department. The reader is referred to the English translation of the Table of Contents and of Chapter 1 describing the duties and organization of the Central Safety Department. (orig./HP) [de

The maintenance training center of the paks nuclear power plant - past, present and future

International Nuclear Information System (INIS)

Kiss, I.

2001-01-01

The safety of the Paks nuclear power plant (Paks NPP) is a political-economic factor with general influence on the stability of the Hungarian economy. Since the beginning of the 1990s, the plant management has been taking significant efforts to learn about the factors that define plant safety and to reveal areas where safety can be further improved. Major emphasis is also placed on the provision of resources and creation of conditions necessary for the preservation of staff competence. In 1997 a separate, maintenance-specific facility was erected. The Maintenance Training Center of the Paks NPP is a worldwide major unique center. (orig.) [de

Designing a Safety Reporting Smartphone Application to Improve Patient Safety After Total Hip Arthroplasty.

Science.gov (United States)

Krumsvik, Ole Andreas; Babic, Ankica

2017-01-01

This paper presents a safety reporting smartphone application which is expected to reduce the occurrence of postoperative adverse events after total hip arthroplasty (THA). A user-centered design approach was utilized to facilitate optimal user experience. Two main implemented functionalities capture patient pain levels and well-being, the two dimensions of patient status that are intuitive and commonly checked. For these and other functionalities, mobile technology could enable timely safety reporting and collection of patient data out of a hospital setting. The HCI expert, and healthcare professionals from the Haukeland University Hospital in Bergen have assessed the design with respect to the interaction flow, information content, and self-reporting functionalities. They have found it to be practical, intuitive, sufficient and simple for users. Patient self-reporting could help recognizing safety issues and adverse events.

Karlsruhe nuclear research center. Main activities

International Nuclear Information System (INIS)

The article reports on problems of securing the fuel supply for nuclear power generation, on reprocessing and ultimate storage of radioactive material, on the safety of nuclear facilities, on new technologies and basic research, and on the infrastructure of the Karlsruhe nuclear research center, as well as finance and administration. (HK) [de

Are Immigrants More Physically Active Than Native-Born Australians and Does it Changes Over Time? Evidence From a Nationally Representative Longitudinal Survey.

Science.gov (United States)

Joshi, Suresh; Jatrana, Santosh; Paradies, Yin

2017-02-01

We investigated the differences and over time changes in recommended physical activity among foreign-born (FB) from English speaking countries (ESC) and non-English speaking countries (NESC) relative to native-born (NB) Australians, and whether the association between nativity and duration of residence (DoR) and physical activity is mediated by English language proficiency, socioeconomic status and social engagement/membership. This study applies multilevel group-meancentered mixed (hybrid) logistic regression models to 12 waves of longitudinal data (12,634 individuals) from the Household, Income and Labor Dynamics in Australia survey with engagement in physical activities for more than 3 times a week as the outcome variable. Immigrants from ESC had higher odds of physical activity, while immigrants from NESC had significantly lower odds of physical activity than NB Australians, after adjusting for covariates. There was no evidence that these differences changed by DoR among immigrants from NESC, whereas ESC immigrants had higher odds of physical activity when their DoR was more than 20 years. We also found a mediating role of English language proficiency on immigrants physical activities. Appropriate health promotion interventions should be implemented to foster physical activities among NESC immigrants, considering English language proficiency as an important factor in designing interventions.

Safety and environmental health handbook

Science.gov (United States)

,

1989-01-01

This Safety Handbook (445-1-H.) supplements the Geological Survey Safety Management Program objectives set forth in Survey Manual 445.1. Specifically, it provides a compact source of basic information to assist management and employees in preventing motor vehicle accidents, personal injuries, occupational diseases, fire, and other property damage or loss. All work situations incidental to the Geological Survey cannot be discussed in a handbook, and such complete coverage is not intended in this document. However, a wide range of subjects are covered in which a "common sense" approach to safety has been expressed. These subjects have been organized such that Chapters 1-5 address administrative issues, Chapters 6-12 address activities usually conducted within a facility, and Chapters 13-20 address field activities. No information contained in the Handbook is intended to alter any provision of any Federal law or executive order, Department of the Interior or Survey directive, or collective bargaining agreement. Questions or suggestions regarding the content of the Safety Handbook may be directed to the Survey Safety Manager, Administrative Division, Office of Facilities and Management Services, National Center, Reston, Virginia, Mail Stop 246. The previous edition of the Safety Handbook is superseded.

77 FR 43090 - Safety and Occupational Health Study Section: Notice of Charter Renewal

Science.gov (United States)

2012-07-23

... Committee Act (Pub. L. 92-463) of October 6, 1972, that the Safety and Occupational Health Study Section... Secretary, Safety and Occupational Health Study Section, Department of Health and Human Services, 1600... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Safety and...

75 FR 42455 - Safety and Occupational Health Study Section: Notice of Charter Renewal

Science.gov (United States)

2010-07-21

... Committee Act (Pub. L. 92-463) of October 6, 1972, that the Safety and Occupational Health Study Section... Secretary, Safety and Occupational Health Study Section, Department of Health and Human Services, 1600... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Safety and...

Electric Power Research Institute: Environmental Technology Control Center, report to the Steering committee. Final technical report

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-04-01

This report describes test for air pollution control of flue gas and mercury as a result of coal combustion. The NYSEG Kintigh Station provided flue gas to the Center 100% of the time during this performance period. As the Kintigh Station operated with a variety of coals, fluctuations in the Center`s inlet SO{sub 2} concentrations were experienced. Safety training for the month was conducted by the O&M Superintendent, Maintenance Supervisor and Shift Supervisors. {open_quotes}Personal Protective Equipment{close_quotes} was the topic of the month. Inspections of the ECTC Facility and safety equipment (SCR air-packs, fire extinguishers, etc.) were completed and recorded this month. All systems were found to be in good condition. By continuing to emphasize safe work habits at the Center, we have raised the total number of days without a lost time injury to 1426 as of 4/30/96. The monthly safety meeting with the NYSEG Kintigh Station was held on April 30, 1996 with both NYSEG and ECTC representatives. The topics of discussion included an overview of NYSEG`s upcoming alternate fuel burn, an update on plant staffing changes, and a discussion of future safety training activities.

76 FR 23810 - Public Safety and Homeland Security Bureau; Federal Advisory Committee Act; Emergency Response...

Science.gov (United States)

2011-04-28

... FEDERAL COMMUNICATIONS COMMISSION Public Safety and Homeland Security Bureau; Federal Advisory Committee Act; Emergency Response Interoperability Center Public Safety Advisory Committee Meeting AGENCY... Fullano, Associate Chief, Public Safety and Homeland Security Bureau, Federal Communications Commission...

Implementing and measuring safety goals and safety culture. 4. Utility's Activities for Better Safety Culture After the JCO Accident

International Nuclear Information System (INIS)

Omoto, Akira

2001-01-01

The criticality accident at the JCO plant prompted the Government to enact a law for nuclear emergency preparedness. The nuclear industry established NSnet to facilitate opportunities for peer review among its members. This paper describes the activities by NSnet and TEPCO's Kashiwazaki-Kariwa nuclear power station (NPS) for a better safety culture. Created as a voluntary organization by the nuclear industry in 1999, NSnet has 35 members and is assisted by CRIEPI and NUPEC for its activities relevant to human factors. Given the fact that nuclear facility operators not belonging to WANO had no institutional system available for exchange of experiences and good practices for better safety among themselves, NSnet's activities focus on peer review by member organizations and onsite seminars. Starting April 2000 with visits to three fuel fabricators, NSnet intends to have 23 peer-review visits in 2 yr (Ref. 1). The six-member review team stays on-site for 4 days, during which time they review-using guidelines available from WANO and IAEA-OSART-six areas: organization/management, emergency preparedness, education/training, operation/ maintenance, protection against occupational radiation exposure, and prevention of accidents. A series of on-site seminars is held at members' nuclear facilities, to which NSnet dispatches experts for lectures. NSnet plans to hold such seminars twice per month. Other activities include information-sharing through a newsletter, a Web site (www. nsnet.gr.jp), and others. Although considerable differences exist in the design and the practices in operation/maintenance between power reactors and JCO, utilities can extract lessons from the accident that will be worth consideration for their own facilities in the areas of safety culture, education and training, and interface between design and operation. This thinking prompted the Nuclear Safety Promotion Center at Kashiwazaki-Kariwa NPS, to which the author belonged at that time, to launch the

Implementation of Information Management System for Radiation Safety of Personnel at the Russian Northwest Center for Radioactive Waste Management 'SevRAO' - 13131

Energy Technology Data Exchange (ETDEWEB)

Chizhov, K.; Simakov, A.; Seregin, V.; Kudrin, I.; Shandala, N.; Tsovyanov, A.; Kryuchkov, V. [Burnasyan Federal Medical Biophysical Center of Federal Medical Biological Agency, RF Ministry of Health and Social Development. 46, Zhivopisnaya St., Moscow, 123182 (Russian Federation); Krasnoschekov, A.; Kosnikov, A. [Northwest Center for Radioactive Waste Management ' SevRAO' - a branch of the Federal State Unitary Enterprise ' Enterprise for Radioactive Waste Management' ' RosRAO' 183017, Murmansk, Lobova st., 100 (Russian Federation); Kemsky, I. [Regional management - 120 of the Federal Medical-Biological Agency, 184682, Snezhnogorsk, Valentina Biryukova St., 5/1 (Russian Federation); Sneve, M. [Norwegian Radiation Protection Authority, Postboks 55, 1332 Oesteraas (Norway)

2013-07-01

The report is an overview of the information-analytical system designed to assure radiation safety of workers. The system was implemented in the Northwest Radioactive Waste Management Center 'SevRAO' (which is a branch of the Federal State Unitary Enterprise 'Radioactive Waste Management Enterprise RosRAO'). The center is located in the Northwest Russia. In respect to 'SevRAO', the Federal Medical-Biological Agency is the regulatory body, which deals with issues of radiation control. The main document to regulate radiation control is 'Reference levels of radiation factors in radioactive wastes management center'. This document contains about 250 parameters. We have developed a software tool to simplify control of these parameters. The software includes: input interface, the database, dose calculating module and analytical block. Input interface is used to enter radiation environment data. Dose calculating module calculates the dose on the route. Analytical block optimizes and analyzes radiation situation maps. Much attention is paid to the GUI and graphical representation of results. The operator can enter the route at the industrial site or watch the fluctuations of the dose rate field on the map. Most of the results are presented in a visual form. Here we present some analytical tasks, such as comparison of the dose rate in some point with control levels at this point, to be solved for the purpose of radiation safety control. The program helps to identify points making the largest contribution to the collective dose of the personnel. The tool can automatically calculate the route with the lowest dose, compare and choose the best route. The program uses several options to visualize the radiation environment at the industrial site. This system will be useful for radiation monitoring services during the operation, planning of works and development of scenarios. The paper presents some applications of this system on real data

78 FR 12065 - National Institute for Occupational Safety and Health Personal Protective Technology for...

Science.gov (United States)

2013-02-21

... Institute for Occupational Safety and Health Personal Protective Technology for Pesticide Handlers: Stakeholder Meeting AGENCY: The National Institute for Occupational Safety and Health (NIOSH) of the Centers...: Notice of public meeting. SUMMARY: The National Institute for Occupational Safety and Health (NIOSH) of...

Safety management of a complex R and D ground operating system

Science.gov (United States)

Connors, J. F.; Maurer, R. A.

1975-01-01

A perspective on safety program management was developed for a complex R&D operating system, such as the NASA-Lewis Research Center. Using a systems approach, hazardous operations are subjected to third-party reviews by designated-area safety committees and are maintained under safety permit controls. To insure personnel alertness, emergency containment forces and employees are trained in dry-run emergency simulation exercises. The keys to real safety effectiveness are top management support and visibility of residual risks.

Patient safety trilogy: perspectives from clinical engineering.

Science.gov (United States)

Gieras, Izabella; Sherman, Paul; Minsent, Dennis

2013-01-01

This article examines the role a clinical engineering or healthcare technology management (HTM) department can play in promoting patient safety from three different perspectives: a community hospital, a national government health system, and an academic medical center. After a general overview, Izabella Gieras from Huntington Hospital in Pasadena, CA, leads off by examining the growing role of human factors in healthcare technology, and describing how her facility uses clinical simulations in medical equipment evaluations. A section by Paul Sherman follows, examining patient safety initiatives from the perspective of the Veterans Health Administration with a focus on hazard alerts and recalls. Dennis Minsent from Oregon Health & Science University writes about patient safety from an academic healthcare perspective, and details how clinical engineers can engage in multidisciplinary safety opportunities.

CMS penalizes 758 hospitals for safety incidents

Directory of Open Access Journals (Sweden)

Robbins RA

2015-12-01

Full Text Available No abstract available. Article truncated after 150 words. The Centers for Medicare and Medicaid Services (CMS is penalizing 758 hospitals with higher rates of patient safety incidents, and more than half of those were also fined last year, as reported by Kaiser Health News (1. Among the hospitals being financially punished are some well-known institutions, including Yale New Haven Hospital, Medstar Washington Hospital Center in DC, Grady Memorial Hospital, Northwestern Memorial Hospital in Chicago, Indiana University Health, Brigham and Womens Hospital, Tufts Medical Center, University of North Carolina Hospital, the Cleveland Clinic, Hospital of the University of Pennsylvania, Parkland Health and Hospital, and the University of Virginia Medical Center (Complete List of Hospitals Penalized 2016. In the Southwest the list includes Banner University Medical Center in Tucson, Ronald Reagan UCLA Medical Center, Stanford Health Care, Denver Health Medical Center and the University of New Mexico Medical Center (for list of Southwest hospitals see Appendix 1. In total, CMS ...

Progress of nuclear safety research. 2003

International Nuclear Information System (INIS)

Anoda, Yoshinari; Amagai, Masaki; Tobita, Tohru

2004-03-01

JAERI is conducting nuclear safety research primarily at the Nuclear Safety Research Center in close cooperation with the related departments in accordance with the Long Term Plan for Development and Utilization of Nuclear Energy and Annual Plan for Safety Research issued by the Japanese government. The fields of conducting safety research at JAERI are the engineering safety of nuclear power plants and nuclear fuel cycle facilities, and radioactive waste management as well as advanced technology for safety improvement or assessment. Also, JAERI has conducted international collaboration to share the information on common global issues of nuclear safety and to supplement own research. Moreover, when accidents occurred at nuclear facilities, JAERI has taken a responsible role by providing technical experts and investigation for assistance to the government or local public body. This report summarizes the nuclear safety research activities of JAERI from April 2001 through March 2003 and utilized facilities. This report also summarizes the examination of the ruptured pipe performed for assistance to the Nuclear and Industrial Safety Agency (NISA) for investigation of the accident at the Hamaoka Nuclear Power Station Unit-1 on November, 2001, and the integrity evaluation of cracked core shroud of BWRs of the Tokyo Electric Power Company performed for assistance to the Nuclear Safety Commission in reviewing the evaluation reports by the licensees. (author)

Nuclear energy research in Germany 2008. Research centers and universities

International Nuclear Information System (INIS)

Tromm, Walter

2009-01-01

This summary report presents nuclear energy research at research centers and universities in Germany in 2008. Activities are explained on the basis of examples of research projects and a description of the situation of research and teaching in general. Participants are the - Karlsruhe Research Center, - Juelich Research Center (FZJ), - Dresden-Rossendorf Research Center (FZD), - Verein fuer Kernverfahrenstechnik und Analytik Rossendorf e.V. (VKTA), - Technical University of Dresden, - University of Applied Sciences, Zittau/Goerlitz, - Institute for Nuclear Energy and Energy Systems (IKE) at the University of Stuttgart, - Reactor Simulation and Reactor Safety Working Group at the Bochum Ruhr University. (orig.)

Camping Safety--Bring 'Em Back Alive.

Science.gov (United States)

Schmidt, Ernest F.

1980-01-01

A "prioritized" list of dangers of the woods is discussed and suggestions for safety in organized camping are listed. Available from: Center for Environmental, Camping and Outdoor Education; University of North Carolina at Greensboro; Pine Lake Field Campus; 4016 Blumenthal Road; Greensboro, NC, 27406. (AN)

Evaluation and review of the safety management system implementation in the Royal Thai Air Force

Science.gov (United States)

Chaiwan, Sakkarin

This study was designed to determine situation and effectiveness of the safety management system currently implemented in the Royal Thai Air Force. Reviewing the ICAO's SMS and the RTAF's SMS was conducted to identify similarities and differences between the two safety management systems. Later, the researcher acquired safety statistics from the RTAF Safety Center to investigate effectiveness of its safety system. The researcher also collected data to identify other factors affecting effectiveness of the safety system during conducting in-depth interviews. Findings and Conclusions: The study shows that the Royal Thai Air Force has never applied the International Civil Aviation Organization's Safety management System to its safety system. However, the RTAF's SMS and the ICAO's SMS have been developed based on the same concepts. These concepts are from Richard H. Woods's book, Aviation safety programs: A management handbook. However, the effectiveness of the Royal Thai Air Force's safety system is in good stance. An accident rate has been decreasing regularly but there are no known factors to describe the increasing rate, according to the participants' opinion. The participants have informed that there are many issues to be resolved to improve the RTAF's safety system. Those issues are cooperation among safety center's staffs, attitude toward safety of the RTAF senior commanders, and safety standards.

SCALE criticality safety verification and validation package

International Nuclear Information System (INIS)

Bowman, S.M.; Emmett, M.B.; Jordan, W.C.

1998-01-01

Verification and validation (V and V) are essential elements of software quality assurance (QA) for computer codes that are used for performing scientific calculations. V and V provides a means to ensure the reliability and accuracy of such software. As part of the SCALE QA and V and V plans, a general V and V package for the SCALE criticality safety codes has been assembled, tested and documented. The SCALE criticality safety V and V package is being made available to SCALE users through the Radiation Safety Information Computational Center (RSICC) to assist them in performing adequate V and V for their SCALE applications

RSAS: a Reactor Safety Assessment System

International Nuclear Information System (INIS)

Sebo, D.E.; Dixon, B.W.; Bray, M.A.

1985-01-01

The Reactor Safety Assessment System (RSAS) is an expert system under development for the United States Nuclear Regulatory Commission (NRC). RSAS is being developed for use at the NRC's Operations Center in the event of a serious incident at a licensed nuclear power plant. The system generates situation assessments for the NRC Reactor Safety Team based on a limited number of plant parameters, known operator actions, and plant status data. The RSAS rule base currently covers one reactor type. The extension of the rule base to other reactor types is also discussed

Perspectives on reactor safety. Revision 1

International Nuclear Information System (INIS)

Haskin, F.E.; Hodge, S.A.

1997-11-01

The US Nuclear Regulatory Commission (NRC) maintains a technical training center at Chattanooga, Tennessee to provide appropriate training to both new and experienced NRC employees. This document describes a one-week course in reactor safety concepts. The course consists of five modules: (1) the development of safety concepts; (2) severe accident perspectives; (3) accident progression in the reactor vessel; (4) containment characteristics and design bases; and (5) source terms and offsite consequences. The course text is accompanied by slides and videos during the actual presentation of the course

Perspectives on reactor safety. Revision 1

Energy Technology Data Exchange (ETDEWEB)

Haskin, F.E. [New Mexico Univ., Albuquerque, NM (United States). Dept. of Chemical and Nuclear Engineering; Camp, A.L. [Sandia National Labs., Albuquerque, NM (United States); Hodge, S.A. [Oak Ridge National Lab., TN (United States). Engineering Technology Div.

1997-11-01

The US Nuclear Regulatory Commission (NRC) maintains a technical training center at Chattanooga, Tennessee to provide appropriate training to both new and experienced NRC employees. This document describes a one-week course in reactor safety concepts. The course consists of five modules: (1) the development of safety concepts; (2) severe accident perspectives; (3) accident progression in the reactor vessel; (4) containment characteristics and design bases; and (5) source terms and offsite consequences. The course text is accompanied by slides and videos during the actual presentation of the course.

Management concepts and safety applications for nuclear fuel facilities

International Nuclear Information System (INIS)

Eisner, H.; Scotti, R.S.

1995-05-01

This report presents an overview of effectiveness of management control of safety. It reviews several modern management control theories as well as the general functions of management and relates them to safety issues at the corporate and at the process safety management (PSM) program level. Following these discussions, structured technique for assessing management of the safety function is suggested. Seven modern management control theories are summarized, including business process reengineering, the learning organization, capability maturity, total quality management, quality assurance and control, reliability centered maintenance, and industrial process safety. Each of these theories is examined for-its principal characteristics and implications for safety management. The five general management functions of planning, organizing, directing, monitoring, and integrating, which together provide control over all company operations, are discussed. Under the broad categories of Safety Culture, Leadership and Commitment, and Operating Excellence, key corporate safety elements and their subelements are examined. The three categories under which PSM program-level safety issues are described are Technology, Personnel, and Facilities

Management concepts and safety applications for nuclear fuel facilities

Energy Technology Data Exchange (ETDEWEB)

Eisner, H.; Scotti, R.S. [George Washington Univ., Washington, DC (United States). School of Engineering and Applied Science; Delicate, W.S. [KEVRIC Co., Inc., Silver Spring, MD (United States)

1995-05-01

This report presents an overview of effectiveness of management control of safety. It reviews several modern management control theories as well as the general functions of management and relates them to safety issues at the corporate and at the process safety management (PSM) program level. Following these discussions, structured technique for assessing management of the safety function is suggested. Seven modern management control theories are summarized, including business process reengineering, the learning organization, capability maturity, total quality management, quality assurance and control, reliability centered maintenance, and industrial process safety. Each of these theories is examined for-its principal characteristics and implications for safety management. The five general management functions of planning, organizing, directing, monitoring, and integrating, which together provide control over all company operations, are discussed. Under the broad categories of Safety Culture, Leadership and Commitment, and Operating Excellence, key corporate safety elements and their subelements are examined. The three categories under which PSM program-level safety issues are described are Technology, Personnel, and Facilities.

The ethical leadership challenge: creating a culture of patient- and family-centered care in the hospital setting.

Science.gov (United States)

Piper, Llewellyn E

2011-01-01

The growing number of medical errors and resulting preventable deaths in hospitals presents an ethical dilemma that must be addressed by health care leaders and managers. These medical errors and deaths raise questions about safety and quality issues resulting in rising public mistrust and patient dissatisfaction. Many of these medical errors and deaths could have been avoided by including the patient and family in the care. The ethical challenge for leadership is creating a culture of patient- and family-centered care as a means to improve quality, safety, patient satisfaction, and public trust. This article addresses ways to improve safety, quality, patient satisfaction, and cost and thereby reduce medical errors and deaths by implementing a patient- and family-centered care culture. The first critical step for improvement is for hospital leaders and managers to answer the ethical call to create a culture centered on patient- and family-centered care in the hospital setting.

77 FR 66855 - Center for Scientific Review; Notice of Closed Meetings

Science.gov (United States)

2012-11-07

... personal privacy. Name of Committee: Center for Scientific Review Special Emphasis Panel; Gene Discover...-HIV Diagnostics, Food Safety, Sterilization/Disinfection and Bioremediation. Date: November 15-16...

76 FR 59143 - Joint Meeting of the Advisory Committee for Reproductive Health Drugs and the Drug Safety and...

Science.gov (United States)

2011-09-23

...] Joint Meeting of the Advisory Committee for Reproductive Health Drugs and the Drug Safety and Risk... Reproductive Health Drugs and the Drug Safety and Risk Management Advisory Committee. General Function of the..., Adelphi, MD. The conference center telephone number is 301-985-7300. Contact Person: Kalyani Bhatt, Center...

Ethics Review of Pediatric Multi-Center Drug Trials

NARCIS (Netherlands)

Needham, Allison C.; Kapadia, Mufiza Z.; Offringa, Martin

2015-01-01

The assessment of safety and efficacy of therapeutics for children and adolescents requires the use of multi-centered designs. However, the need to obtain ethical approval from multiple independent research ethics boards (REBs) presents as a challenge to investigators and sponsors who must consider

Aviation safety/automation program overview

Science.gov (United States)

Morello, Samuel A.

1990-01-01

The goal is to provide a technology base leading to improved safety of the national airspace system through the development and integration of human-centered automation technologies for aircraft crews and air traffic controllers. Information on the problems, specific objectives, human-automation interaction, intelligent error-tolerant systems, and air traffic control/cockpit integration is given in viewgraph form.

A study of adopting maintenance rule under the periodic safety review and reliability centered maintenance program

International Nuclear Information System (INIS)

Kilyoo, Kim

2001-01-01

U.S Maintenance Rule (MR) has three main functions. One is to monitor the performance changes of SSCs (Structure, System, and Component) caused by risk informed applications. Periodic Safety Review (PSR) program is widely adopted in Europe while it is not adopted in U. S. A where MR and new oversight program are instead used. Recently, in Korea, it was determined to adopt PSR, and the first PSR program has started this year for Kori unit 1 as a pilot plant. Also, a traditional Reliability Centered Maintenance (RCM) has been performed for 4 systems of YGN unit 1 and 2 and it will be applied to the other nuclear power plants in Korea. However, since MR is adopting many useful concept of RCM, traditional RCM could not be further performed without being associated with MR. Thus, MR, RCM and PSR have recently become hot issue policies which should be well associated each other in Korea, and this paper suggests a desirable new maintenance process which would embrace the concepts of the three policies, and also discusses whether U.S. MR is necessary even though a PSR program is already adopted, and if necessary, then how cost-effectively it can be introduced to. (author)

Safety after extended repeated use of ulipristal acetate for uterine fibroids

DEFF Research Database (Denmark)

Fauser, Bart C J M; Donnez, Jacques; Bouchard, Philippe

2017-01-01

OBJECTIVE: To assess long term safety of extended repeated 3-month courses of ulipristal acetate (UPA) 10 mg/day, for up to 8 courses, with focus on endometrial and laboratory safety parameters. METHODS: This long-term, multi-center, open-label cohort, follow up study consisted of up to 8 consecu...

CNC Turning Center Advanced Operations. Computer Numerical Control Operator/Programmer. 444-332.

Science.gov (United States)

Skowronski, Steven D.; Tatum, Kenneth

This student guide provides materials for a course designed to introduce the student to the operations and functions of a two-axis computer numerical control (CNC) turning center. The course consists of seven units. Unit 1 presents course expectations and syllabus, covers safety precautions, and describes the CNC turning center components, CNC…

Amarillo National Resource Center for Plutonium. Quarterly technical progress report, May 1, 1997--July 31, 1997

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-09-01

Progress summaries are provided from the Amarillo National Center for Plutonium. Programs include the plutonium information resource center, environment, public health, and safety, education and training, nuclear and other material studies.

77 FR 67658 - Navigation Safety Advisory Council

Science.gov (United States)

2012-11-13

... DEPARTMENT OF HOMELAND SECURITY Coast Guard [Docket No. USCG-2012-0212] Navigation Safety Advisory.../en/hotels/florida/embassy-suites-tampa-downtown-convention-center-TPAESES/index.html . For... possible. To facilitate public participation, we are inviting public comment on the issues to be considered...

Radiation safety program in a high dose rate brachytherapy facility

International Nuclear Information System (INIS)

Rodriguez, L.V.; Hermoso, T.M.; Solis, R.C.

2001-01-01

The use of remote afterloading equipment has been developed to improve radiation safety in the delivery of treatment in brachytherapy. Several accidents, however, have been reported involving high dose-rate brachytherapy system. These events, together with the desire to address the concerns of radiation workers, and the anticipated adoption of the International Basic Safety Standards for Protection Against Ionizing Radiation (IAEA, 1996), led to the development of the radiation safety program at the Department of Radiotherapy, Jose R. Reyes Memorial Medical Center and at the Division of Radiation Oncology, St. Luke's Medical Center. The radiation safety program covers five major aspects: quality control/quality assurance, radiation monitoring, preventive maintenance, administrative measures and quality audit. Measures for evaluation of effectiveness of the program include decreased unnecessary exposures of patients and staff, improved accuracy in treatment delivery and increased department efficiency due to the development of staff vigilance and decreased anxiety. The success in the implementation required the participation and cooperation of all the personnel involved in the procedures and strong management support. This paper will discuss the radiation safety program for a high dose rate brachytherapy facility developed at these two institutes which may serve as a guideline for other hospitals intending to install a similar facility. (author)

Increasing NASA SSC Range Safety by Developing the Framework to Monitor Airspace and Enforce Restrictions

Data.gov (United States)

National Aeronautics and Space Administration — The NASA John C. Stennis Space Center (SSC) Office of Safety and Mission Assurance (SMA) has a safety concern associated with unauthorized aircraft entering...

Transformational Leadership: The Chief Nursing Officer Role in Leading Quality and Patient Safety.

Science.gov (United States)

Jones, Pam; Polancich, Shea; Steaban, Robin; Feistritzer, Nancye; Poe, Terri

This department column highlights leadership perspectives of quality and patient safety practice. The purpose of this article is to provide strategic direction for transformational quality and safety leadership as the chief nursing officer (CNO) within the academic medical center environment.

Proceeding of Radiation Safety and Environment; Prosiding Presentasi Ilmiah Keselamatan Radiasi dan Lingkungan

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-07-01

Scientific Presentation of Radiation Safety and Environment was held on 20-21 august 1996 at Center of Research Atomic Energy Pasar Jum'at, Jakarta, Indonesia. Have presented 50 papers about Radiation Safety, dosimetry and standardization, environment protection and radiation effect.

Application of reliability centered maintenance to Embalse NPP

International Nuclear Information System (INIS)

Torres, Antonio; Perdomo, Manuel; Fornero, Damian; Corchera, Roberto

2010-01-01

One of the most recent applications of Probabilistic Safety Analysis to Embalse NPP is the Safety Oriented Maintenance Program developed through the Reliability Centered Maintenance (RCM) methodology. Such an application was carried out by a cooperated effort between the staff of nuclear safety department of NPP and experts from Instituto Superior de Tecnologias y Ciencias Aplicadas of Cuba. So far 6 technological systems have been analyzed with important results regarding the optimization of preventive and predictive maintenance program of those systems. Any tasks of RCM were automated via MOSEG code. The results of this study were focused on the elaboration and modification of the Preventive Program, prioritization of stocks, reorientation of predictive techniques and modification in the time parameters of maintenance. (author)

Beamline for Schools Safety Awareness Day

CERN Multimedia

Photo Service, CERN

2014-01-01

The first two teams to participate in CERN's Beamline for Schools project spent their first day at CERN at the Safety Training Center in Prévessin. They covered amongst others radiation protection, cryogenics and fire-fighting. The teams will spend the rest of the week at the T9 beamline.

Progress report of Cekmece Nuclear Research and Training Center for 1981

International Nuclear Information System (INIS)

1982-01-01

Presented are the research works carried out in 1981 in Energy, Radiological Safety, Radioisotope, Application of Nuclear Techniques and Basic Research of Cekmece Nuclear Research and Training Center. (author)

Report transparency and nuclear safety 2007 CEA Saclay

International Nuclear Information System (INIS)

2007-01-01

This report presents the activities of the CEA Center of Saclay for the year 2007. The actions concerning the safety, the radiation protection, the significant events, the release control and the environmental impacts and the wastes stored on the center are discussed. More especially two public consultation on release authorizations and the Neurospin installations, the dismantling of the 49 nuclear installation, the shutdown of the learning reactor ULYSSE are detailed. (A.L.B.)

The company's management puts priority on safety

International Nuclear Information System (INIS)

Tomek, J.

2006-01-01

On 29-30 June, 2006, the training for workers of the Slovenske elektrarne, a. s. was organized to explain the most important management safety aspects on leadership awareness (Nuclear Leadership Awareness Course). The course was held at the regional consultation center in Jaslovske Bohunice. (author)

Safety concerns with the Centers for Disease Control opioid calculator

Directory of Open Access Journals (Sweden)

Fudin J

2017-12-01

Full Text Available Jeffrey Fudin,1–4 Mena Raouf,2 Erica L Wegrzyn,2–4 Michael E Schatman5,61Scientific and Clinical Affairs, Remitigate, LLC, Delmar, NY, USA; 2Stratton VA Medical Center, Albany, NY, USA; 3Western New England University College of Pharmacy, Springfield, MA, USA; 4Albany College of Pharmacy & Health Sciences, Albany, NY, USA; 5Research and Network Development, Boston Pain Care, Waltham, MA, USA; 6Department of Public Health & Community Medicine, Tufts University School of Medicine, Boston, MA, USAMorphine milligram equivalence (MME and other comparable acronyms have been employed in federal pain guidelines and used by policy makers to limit opioid prescribing.1–5 On March 18, 2016, the Centers for Disease Control (CDC released its Guideline for Prescribing Opioids for Chronic Pain.1 The guidelines provided 12 recommendations for “primary care clinicians prescribing opioids for chronic pain outside of active cancer treatment, palliative care, and end-of-life care”. One of the CDC recommendations states that clinicians “should avoid increasing dosage to ≥90 MME/day or carefully justify a decision to titrate dosage to ≥90 MME/day”.1

The safety characteristics of the HTR 500 reactor plant

International Nuclear Information System (INIS)

Wachholz, W.

1987-01-01

The HTR is a reactor having a passive safety. It is equipped with the usual active engineered safety systems in simplified form. Due to its inherent safety characteristics and the burst-safe prestressed concrete reactor vessel activity containment is ensured even without the effect of active safety systems. Even in the event of extremely hypothetical accidents the effect on the environment is low enough so that evacuation or relocation of the population is not required. Therefore large-scale damage of agricultural land and industrially used areas is safely ruled out. Thus the site selection for this type of reactor is not restricted i.e. an HTR can be constructed near industrial and urban center. (author)

Violence against health workers in Family Medicine Centers.

Science.gov (United States)

Al-Turki, Nouf; Afify, Ayman Am; AlAteeq, Mohammed

2016-01-01

Health care violence is a significant worldwide problem with negative consequences on both the safety and well-being of health care workers as well as workplace activities. Reports examining health care violence in Saudi Arabia are limited and the results are conflicting. To estimate the prevalence and determine the demographic and occupational characteristics associated with workplace violence in primary care centers in Riyadh, Saudi Arabia. A cross-sectional study included 270 health care workers in 12 family medicine centers in Riyadh during November and December 2014. A structured self-administered questionnaire was used to estimate the frequency, timing, causes, reactions, and consequences of workplace violence plus participants' demographic and occupational data. A total 123 health care workers (45.6%) experienced some kind of violence over 12 months prior to the study. These included physical (6.5%) and nonphysical violence (99.2%), including verbal violence (94.3%) and intimidation (22.0%). Offenders were patients (71.5%) in the majority of cases, companions (20.3%), or both (3.3%). Almost half (48.0%) of health care workers who experienced violence did nothing, 38.2% actively reported the event, and 13.8% consulted a colleague. A significant association of workplace violence was found with working multiple shifts, evening or night shift, and lack of an encouraging environment to report violence. Workplace violence is still a significant problem in primary care centers. The high frequency of violence together with underreporting may indicate the inefficiency of the current safety program. More safety programs and training activities for health care workers, efficient reporting system, and zero tolerance policies need to be implemented to minimize workplace violence against health workers.

THE FLUORBOARD A STATISTICALLY BASED DASHBOARD METHOD FOR IMPROVING SAFETY

International Nuclear Information System (INIS)

PREVETTE, S.S.

2005-01-01

The FluorBoard is a statistically based dashboard method for improving safety. Fluor Hanford has achieved significant safety improvements--including more than a 80% reduction in OSHA cases per 200,000 hours, during its work at the US Department of Energy's Hanford Site in Washington state. The massive project on the former nuclear materials production site is considered one of the largest environmental cleanup projects in the world. Fluor Hanford's safety improvements were achieved by a committed partnering of workers, managers, and statistical methodology. Safety achievements at the site have been due to a systematic approach to safety. This includes excellent cooperation between the field workers, the safety professionals, and management through OSHA Voluntary Protection Program principles. Fluor corporate values are centered around safety, and safety excellence is important for every manager in every project. In addition, Fluor Hanford has utilized a rigorous approach to using its safety statistics, based upon Dr. Shewhart's control charts, and Dr. Deming's management and quality methods

Requirement and prospect of nuclear data activities for nuclear safety

International Nuclear Information System (INIS)

Kimura, Itsuro

2000-01-01

Owing to continuous efforts by the members of JNDC (Japanese Nuclear Data Committee) and Nuclear Data Center in JAERI (Japan Atomic Energy Research Institute), several superb evaluated nuclear data files, such as JENDL, FP (fission product) yields and decay heat, have been compiled in Japan and opened to the world. However, they are seldom adopted in safety design and safety evaluation of light water reactors and are hardly found in related safety regulatory guidelines and standards except the decay heat. In this report, shown are a few examples of presently used nuclear data in the safety design and the safety evaluation of PWRs (pressurized water reactors) and so forth. And then, several procedures are recommended in order to enhance more utilization of Japanese evaluated nuclear data files for nuclear safety. (author)

76 FR 13638 - Ensuring the Safety of Imported Foods and Animal Feed: Comparability of Food Safety Systems and...

Science.gov (United States)

2011-03-14

... DEPARTMENT OF HEALTH AND HUMAN SERVICES Food and Drug Administration [Docket No. FDA-2011-N-0135..., to request onsite parking, or to submit the full text, comprehensive outline, or summary of an oral presentation: Juanita Yates, Center for Food Safety and Applied Nutrition, Food and Drug Administation, 5100...

Safety Case for Service Contracts

Energy Technology Data Exchange (ETDEWEB)

Martinez, Israel L.

2014-07-01

Safety cases developed for the Facilities Management and Operations Center (FMOC) are based on the requirements in MN471021, Work Planning and Control Criteria for Safe Design and Operations. The FMOC performs maintenance activities in various locations at Sandia National Laboratories, New Mexico (SNL/NM). SNL/NM consists of more than 6,000,000 square feet of buildings, structures, and site infrastructure on approximately 13,000 acres of land. The FMOC performs approximately 7500 service contract work orders a year to assist with operations and maintenance at the SNL/NM site and facilities. As part of the continual improvement process, this Safety Case will be reviewed and updated, as needed, or at a minimum every three years.

Fuel safety research 2000

Energy Technology Data Exchange (ETDEWEB)

Uetsuka, Hiroshi (ed.) [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

2001-03-01

In April 1999, the Fuel Safety Research Laboratory was newly established as a part of reorganization of the Nuclear Safety Research Center, JAERI. The new laboratory was organized by combining three pre-existing laboratories, Reactivity Accident Laboratory, Fuel Reliability Laboratory, and a part of Severe Accident Research Laboratory. The Fuel Safety Research Laboratory becomes to be in charge of all fuel safety research in JAERI. Various experimental and analytical researches are conducted in the laboratory by using the unique facilities such as the Nuclear Safety Research Reactor (NSRR), the Japan Material Testing Reactor (JMTR), the Japan Research Reactor 3 (JRR-3) and hot cells in JAERI. The laboratory consists of following five research groups corresponding to each research fields; (a) Research group of fuel behavior under the reactivity initiated accident conditions (RIA group). (b) Research group of fuel behavior under the loss-of-coolant accident conditions (LOCA group). (c) Research group of fuel behavior under the normal operation conditions (JMTR/BOCA group). (d) Research group of fuel behavior analysis (FEMAXI group). (e) Research group of FP release/transport behavior from irradiated fuel (VEGA group). The research activities in year 2000 produced many important data and information. They are, for example, failure of high burnup BWR fuel rod under RIA conditions, data on the behavior of hydrided Zircaloy cladding under LOCA conditions and FP release data from VEGA experiments at very high temperature/pressure condition. This report summarizes the outline of research activities and major outcomes of the research executed in 2000 in the Fuel Safety Research Laboratory. (author)

Report of transparency and nuclear safety 2007 CEA Fontenay aux Roses

International Nuclear Information System (INIS)

2007-01-01

This report presents the activities of the CEA Center of Fontenay aux roses for the year 2007. After many years of decommissioning and dismantling of nuclear installations, the Center is now devoted (since 2005) to the development of research programmes on biology and biomedical technologies. The actions concerning the safety, the radiation protection, the significant events, the release control and the environmental impacts and the wastes stored on the center are discussed. (A.L.B.)

FFTF Work Control Center

International Nuclear Information System (INIS)

Talbot, M.D.

1986-01-01

A centralized Work Control Center (WCC) is responsible for assuring that maintenance and modification of the Fast Flux Test Facility (FFTF) is performed in accordance with written procedures that ensure design integrity, personnel and public safety, and equipment and system availability for the computerized Master Information Data Acquisition System (MIDAS). Each maintenance task is logged into MIDAS from a Work Request from that has been reviewed and prioritized by the WCC. Thereafter, MIDAS is used to track schedule, manpower and material requirements; authorize field work; and close out the maintenance activity

Report transparency and nuclear safety 2007 CEA Cadarache

International Nuclear Information System (INIS)

2007-01-01

This report presents the activities of the CEA Center of Cadarache for the year 2007. The actions concerning the safety, the radiation protection, the significant events, the release control and the environmental impacts and the wastes stored on the center are discussed. More especially the report discusses the beginning of the RJH reactor construction, the fourth generation reactors research programs, the implementing of la Rotonde the new radioactive wastes management installation, the renovation of the LECA. (A.L.B.)

Summary of fuel safety research meeting 2005

International Nuclear Information System (INIS)

Fuketa, Toyoshi; Nakamura, Takehiko; Nagase, Fumihisa; Nakamura, Jinichi; Suzuki, Motoe; Sasajima, Hideo; Sugiyama, Tomoyuki; Amaya, Masaki; Kudo, Tamotsu; Chuto, Toshinori; Tomiyasu, Kunihiko; Udagawa, Yutaka; Ikehata, Hisashi; Kida, Mitsuko; Ikatsu, Nobuhiko; Hosoyamada, Ryuji; Hamanishi, Eizou; Iwasaki, Ryo; Ozawa, Masaaki

2006-03-01

Fuel Safety Research Meeting 2005, which was organized by the Japan Atomic Energy Agency (Establishment of the new organization in Oct. 1, 2005 integrated of JAERI and JNC) was held on March 2-3, 2005 at Toshi Center Hotel, Tokyo. The purposes of the meeting are to present and discuss the results of experiments and analyses on reactor fuel safety and to exchange views and experiences among the participants. The technical topics of the meting covered the status of fuel safety research activities, fuel behavior under Reactivity Initiated Accident (RIA) and Loss of coolant accident (LOCA) conditions, high fuel behavior, and radionuclide release under severe accident conditions. This summary contains all the abstracts and sheets of viewgraph presented in the meeting. (author)

Staff roster for 1979: National Center for Analysis of Energy Systems

Energy Technology Data Exchange (ETDEWEB)

1980-01-01

This publication is a compilation of resumes from the current staff of the National Center for Analysis of Energy Systems. The Center, founded in January 1976, is one of four areas within the Department of Energy and Environment at Brookhaven National Laboratory. The emphasis of programs at the Center is on energy policy and planning studies at the regional, national, and international levels, involving quantitative, interdisciplinary studies of the technological, economic, social, and environmental aspects of energy systems. To perform these studies the Center has assembled a staff of experts in the areas of science, technology, economics planning, health and safety, information systems, and quantitative analysis.

Patient safety: break the silence.

Science.gov (United States)

Johnson, Hope L; Kimsey, Diane

2012-05-01

A culture of patient safety requires commitment and full participation from all staff members. In 2008, results of a culture of patient safety survey conducted in the perioperative division of the Lehigh Valley Health Network in Pennsylvania revealed a lack of patient-centered focus, teamwork, and positive communication. As a result, perioperative leaders assembled a multidisciplinary team that designed a safety training program focusing on Crew Resource Management, TeamSTEPPS, and communication techniques. The team used video vignettes and an audience response system to engage learners and promote participation. Topics included using preprocedural briefings and postprocedural debriefings, conflict resolution, and assertiveness techniques. Postcourse evaluations showed that the majority of respondents believed they were better able to question the decisions or actions of someone with more authority. The facility has experienced a marked decrease in the number of incidents requiring a root cause analysis since the program was conducted. Copyright © 2012 AORN, Inc. Published by Elsevier Inc. All rights reserved.

Proceedings of the First Seminar on Radiation Safety Technology and Nuclear Biomedicine

International Nuclear Information System (INIS)

Suprihadi, Topo

2003-01-01

The First Seminar on Radiation Safety Technology and Nuclear Biomedicine was held on 10-11 April 2001 at the Center for Research and Development of Radiation Safety and Nuclear Biomedicine have presented 19 papers about upgrading manpower resources, researcher, investigator, manager, and user of nuclear facilities, to go out against free market era

The Competence Promoting by NNSA for Keeping High Level Nuclear Safety: The Corner Stone of the Nuclear Safety Regulation Edifice

International Nuclear Information System (INIS)

Hu, L.

2016-01-01

Facing the fast development of the nuclear power industry and the application of radioactive sources, The MEP(NNSA) is endeavoured to promoting its competency, including: complementing the law system, training and recruiting staff to keep a capable team, constructing the R&D base to keep the basic capability, promoting safety culture both for the industry and the regulator. After the Fukushima nuclear accident, the MEP(NNSA) planned to construct R&D base, in which the Platform Nuclear Safety Monitoring and Emergency Responding, the Platform of Safety Technology of PWR Testing, the Laboratory of Safety Management Technology of Nuclear Waste Verification, the Laboratory of Environmental Radiation Monitoring and the Center of International Cooperation are included. On the other hand, the MEP(NNSA) issued Chinese nuclear safety culture policy declaration in 2014, and carried out a large scale Specialized Action for Nuclear Safety Promotion to promote the nuclear safety culture both for the industry and herself. For the nuclear regulator, It is essential to conduct the competence promoting by both “hardware” and “software”, the former is the material foundation of regulation authority, which will be effectively functioning under the facilitating of the latter. (author)

Restaurant manager and worker food safety certification and knowledge.

Science.gov (United States)

Brown, Laura G; Le, Brenda; Wong, Melissa R; Reimann, David; Nicholas, David; Faw, Brenda; Davis, Ernestine; Selman, Carol A

2014-11-01

Over half of foodborne illness outbreaks occur in restaurants. To combat these outbreaks, many public health agencies require food safety certification for restaurant managers, and sometimes workers. Certification entails passing a food safety knowledge examination, which is typically preceded by food safety training. Current certification efforts are based on the assumption that certification leads to greater food safety knowledge. The Centers for Disease Control and Prevention conducted this study to examine the relationship between food safety knowledge and certification. We also examined the relationships between food safety knowledge and restaurant, manager, and worker characteristics. We interviewed managers (N=387) and workers (N=365) about their characteristics and assessed their food safety knowledge. Analyses showed that certified managers and workers had greater food safety knowledge than noncertified managers and workers. Additionally, managers and workers whose primary language was English had greater food safety knowledge than those whose primary language was not English. Other factors associated with greater food safety knowledge included working in a chain restaurant, working in a larger restaurant, having more experience, and having more duties. These findings indicate that certification improves food safety knowledge, and that complex relationships exist among restaurant, manager, and worker characteristics and food safety knowledge.

Restaurant Manager and Worker Food Safety Certification and Knowledge

Science.gov (United States)

Brown, Laura G.; Le, Brenda; Wong, Melissa R.; Reimann, David; Nicholas, David; Faw, Brenda; Davis, Ernestine; Selman, Carol A.

2017-01-01

Over half of foodborne illness outbreaks occur in restaurants. To combat these outbreaks, many public health agencies require food safety certification for restaurant managers, and sometimes workers. Certification entails passing a food safety knowledge examination, which is typically preceded by food safety training. Current certification efforts are based on the assumption that certification leads to greater food safety knowledge. The Centers for Disease Control and Prevention conducted this study to examine the relationship between food safety knowledge and certification. We also examined the relationships between food safety knowledge and restaurant, manager, and worker characteristics. We interviewed managers (N = 387) and workers (N = 365) about their characteristics and assessed their food safety knowledge. Analyses showed that certified managers and workers had greater food safety knowledge than noncertified managers and workers. Additionally, managers and workers whose primary language was English had greater food safety knowledge than those whose primary language was not English. Other factors associated with greater food safety knowledge included working in a chain restaurant, working in a larger restaurant, having more experience, and having more duties. These findings indicate that certification improves food safety knowledge, and that complex relationships exist among restaurant, manager, and worker characteristics and food safety knowledge. PMID:25361386

Industrial center of gathering, warehousing and storage. Annual report 2015

International Nuclear Information System (INIS)

2016-01-01

This report first presents the installations of the Cires (industrial center for regrouping, warehousing and storage), its equipment and buildings, its activities (storage of very-low-activity wastes, regrouping and warehousing of non-electronuclear wastes). It reviews the arrangements regarding safety and radiation protection: radioactive waste storage safety, safety of non-electronuclear waste regrouping and warehousing, relationship with the regional directorate of environment, planning and housing (DREAL), quality audits, staff safety, and radiation protection. It addresses the actions undertaken for the monitoring of the environment and of releases by the installations: radiological control in various locations (measurements in soils, waters, underground waters, and atmospheric releases), physical and chemical controls. The next part reports actions regarding transparency and information (visits, conferences, exhibitions, relationship with the local information and control commission)

Industrial center of gathering, warehousing and storage. Annual report 2016

International Nuclear Information System (INIS)

2016-01-01

This report first presents the installations of the Cires (industrial center for regrouping, warehousing and storage), its equipment and buildings, its activities (storage of very-low-activity wastes, regrouping and warehousing of non-electronuclear wastes). It reviews the arrangements regarding safety and radiation protection: radioactive waste storage safety, safety of non-electronuclear waste regrouping and warehousing, relationship with the regional directorate of environment, planning and housing (DREAL), quality audits, staff safety, and radiation protection. It addresses the actions undertaken for the monitoring of the environment and of releases by the installations: radiological control in various locations (measurements in soils, waters, underground waters, and atmospheric releases), physical and chemical controls. The next part reports actions regarding transparency and information (visits, conferences, exhibitions, relationship with the local information and control commission)

78 FR 47419 - Requirements for the OSHA Training Institute Education Centers Program and the OSHA Outreach...

Science.gov (United States)

2013-08-05

... DEPARTMENT OF LABOR Occupational Safety and Health Administration [Docket No. OSHA-2009-0022] Requirements for the OSHA Training Institute Education Centers Program and the OSHA Outreach Training Program...) Requirements AGENCY: Occupational Safety and Health Administration (OSHA), U.S. Department of Labor. ACTION...

Center for Nuclear Safety in Central and Eastern Europe: a platform for co-operation

International Nuclear Information System (INIS)

Tomik, L.; Kichev, E.

2003-01-01

The paper presents a summary of the current status and the activities of the Centre of Nuclear Safety in Central and Eastern Europe (CENS). The CENS is a non-profit and independent association supported by the Swiss and Slovak Governments. The main mission of the CENS is to provide an independent platform for technical co-operation between the regulatory authorities of the Western and Eastern countries. The key partners of the CENS are the Swiss Federal Nuclear Safety Inspectorate (HSK), the International Atomic Energy Agency (IAEA), the US Department of Energy (US DOE), the Nuclear Regulatory Authority of the Slovak Republic (UJD), the Gesellschaft fuer Anlagen-und Reaktorsicherheit mbH (GRS), Germany and the Institute of Radiation Protection and Nuclear Safety (IRSN), France. The CENS programs for 2003-2004 are presented. It can be considered as a complement to the IAEA activities in the area of short-term and event urgent planning. CENS projects as an example are presented. CENS proposals for co-operation with the Bulgarian institutions are made in connection with the topics of the forum round table discussions

Safety of remifentanil in transsphenoidal surgery: A single-center analysis of 540 patients.

Science.gov (United States)

Cote, David J; Burke, William T; Castlen, Joseph P; King, Chih H; Zaidi, Hasan A; Smith, Timothy R; Laws, Edward R; Aglio, Linda S

2017-04-01

Although some studies have examined the efficacy and safety of remifentanil in patients undergoing neurosurgical procedures, none has examined its safety in transsphenoidal operations specifically. In this study, all transsphenoidal operations performed by a single author from 2008 to 2015 were retrospectively reviewed to evaluate the safety of remifentanil in a consecutive series of patients. During the study period, 540 transsphenoidal operations were identified. Of these, 443 (82.0%) patients received remifentanil intra-operatively; 97 (18.0%) did not. The two groups were well-matched with regard to demographic categories, comorbidities, and pre-operative medications (p>0.05), except pre-operative tobacco use (p=0.021). Patients were also well-matched with regard to radiographic features and surgical techniques. Patients who received remifentanil were more likely to harbor a macroadenoma (78.1% vs. 67.0%, p=0.025), and had slightly longer anesthesia time on average (269.2minvs. 239.4min, p=0.024). All pathologic diagnoses were well-matched between the two groups, except that patients receiving remifentanil were more likely to harbor a non-functioning adenoma (46.5% vs. 26.8%, ptranssphenoidal surgery, remifentanil was found to be a safe anesthetic adjunct. There were no significant differences in post-operative hospital course or complications in patients who did and did not receive intra-operative remifentanil. Copyright © 2016 Elsevier Ltd. All rights reserved.

Federal Radiological Monitoring and Assessment Center Health and Safety Manual

Energy Technology Data Exchange (ETDEWEB)

FRMAC Health and Safety Working Group

2012-03-20

This manual is a tool to provide information to all responders and emergency planners and is suggested as a starting point for all organizations that provide personnel/assets for radiological emergency response. It defines the safety requirements for the protection of all emergency responders. The intent is to comply with appropriate regulations or provide an equal level of protection when the situation makes it necessary to deviate. In the event a situation arises which is not addressed in the manual, an appropriate management-level expert will define alternate requirements based on the specifics of the emergency situation. This manual is not intended to pertain to the general public.

Implementation of probabilistic safety concepts in international codes

International Nuclear Information System (INIS)

Borges, J.F.

1977-01-01

Recent progress in the implementation of safety concepts in international structure codes is briefly presented. Special attention is paid to the work of the Joint-Committee on Structural Safety. The discussion is centered on some problems such as: safety differentiation, definition and combination of actions, spaces for checking safety and non-linear structural behaviour. When discussing safety differentiation it should be considered that the total probability of failure derives from a theoretical probability of failure and a probability of failure due to error and gross negligence. Optimization of design criteria should take into account both causes of failure. The quantification of reliability implies a probabilistic idealization of all basic variables. Steps taken to obtain an improved definition of different types of actions and rules for their combination are described. Safety checking can be carried out in terms of basic variables, action-effects, or any other suitable variable. However, the advantages and disadvantages of the different types of formulation should be discussed, particularly in the case of non-linear structural behaviour. (orig.) [de

A relational leadership perspective on unit-level safety climate.

Science.gov (United States)

Thompson, Debra N; Hoffman, Leslie A; Sereika, Susan M; Lorenz, Holly L; Wolf, Gail A; Burns, Helen K; Minnier, Tamra E; Ramanujam, Rangaraj

2011-11-01

This study compared nursing staff perceptions of safety climate in clinical units characterized by high and low ratings of leader-member exchange (LMX) and explored characteristics that might account for differences. Frontline nursing leaders' actions are critical to ensure patient safety. Specific leadership behaviors to achieve this goal are underexamined. The LMX perspective has shown promise in nonhealthcare settings as a means to explain safety climate perceptions. Cross-sectional survey of staff (n = 711) and unit directors from 34 inpatient units in an academic medical center was conducted. Significant differences were found between high and low LMX scoring units on supervisor safety expectations, organizational learning-continuous improvement, total communication, feedback and communication about errors, and nonpunitive response to errors. The LMX perspective can be used to identify differences in perceptions of safety climate among nursing staff. Future studies are needed to identify strategies to improve staff safety attitudes and behaviors. Copyright © 2011 Wolters Kluwer Health | Lippincott Williams & Wilkins

30 CFR 75.812-2 - High-voltage power centers and transformers; record of examination.

Science.gov (United States)

2010-07-01

... 30 Mineral Resources 1 2010-07-01 2010-07-01 false High-voltage power centers and transformers; record of examination. 75.812-2 Section 75.812-2 Mineral Resources MINE SAFETY AND HEALTH ADMINISTRATION... High-Voltage Distribution § 75.812-2 High-voltage power centers and transformers; record of examination...

Violence against health workers in Family Medicine Centers

Science.gov (United States)

Al-Turki, Nouf; Afify, Ayman AM; AlAteeq, Mohammed

2016-01-01

Background Health care violence is a significant worldwide problem with negative consequences on both the safety and well-being of health care workers as well as workplace activities. Reports examining health care violence in Saudi Arabia are limited and the results are conflicting. Objective To estimate the prevalence and determine the demographic and occupational characteristics associated with workplace violence in primary care centers in Riyadh, Saudi Arabia. Methods A cross-sectional study included 270 health care workers in 12 family medicine centers in Riyadh during November and December 2014. A structured self-administered questionnaire was used to estimate the frequency, timing, causes, reactions, and consequences of workplace violence plus participants’ demographic and occupational data. Results A total 123 health care workers (45.6%) experienced some kind of violence over 12 months prior to the study. These included physical (6.5%) and nonphysical violence (99.2%), including verbal violence (94.3%) and intimidation (22.0%). Offenders were patients (71.5%) in the majority of cases, companions (20.3%), or both (3.3%). Almost half (48.0%) of health care workers who experienced violence did nothing, 38.2% actively reported the event, and 13.8% consulted a colleague. A significant association of workplace violence was found with working multiple shifts, evening or night shift, and lack of an encouraging environment to report violence. Conclusion Workplace violence is still a significant problem in primary care centers. The high frequency of violence together with underreporting may indicate the inefficiency of the current safety program. More safety programs and training activities for health care workers, efficient reporting system, and zero tolerance policies need to be implemented to minimize workplace violence against health workers. PMID:27330300

Safety research program of NUCEF

International Nuclear Information System (INIS)

Naito, Y.

1996-01-01

To contribute the safety and establishment of advanced technologies in the area of nuclear fuel cycle, Japan Atomic Energy Research Institute (JAERI) has constructed a new research facility NUCEF (Nuclear Fuel Cycle Safety Engineering Research Facility) as the center for the research and development, particularly on the reprocessing technology and transuranium (TRU) waste management. NUCEF consist of three buildings, administration building, experiment building A and B. Building A has two experiment facilities STACY (Static Experiment Critical Facility) and TRACY (Transient Experiment Critical Facility). The experiment building B is referred to as BECKY (Back-end Fuel Cycle Key Elements Research Facility). Researches on the reprocessing and the waste management are carried out with spent fuels, high-level liquid waste, TRU etc. in the α γ cell and glove boxes. NUCEF was constructed with the following aims. Using STACY and TRACY, are aimed, (1) research on advanced technology for criticality safety control, (2) reconfirmation of criticality safety margin of the Rokkasho reprocessing plant. Using BECKY, are aimed, (1) research on advanced technology of reprocessing process, (2) contribution to develop the scenario for TRU waste disposal, (3) development of new technology for TRU partitioning and volume reduction of radioactive waste. To realize the above aims, following 5 research subjects are settled in NUCEF, (1) Criticality safety research, (2) Research on safety and advanced technology of fuel reprocessing, (3) Research on TRU waste management, (4) Fundamental research on TRU chemistry, (5) Key technology development for TRU processing. (author)

Alpha waste management at the Valduc Research Center

International Nuclear Information System (INIS)

Jouan, A.; Cartier, R.; Durec, J.P.; Flament, T.

1995-01-01

Operation of the reprocessing facilities at the Valduc Research Center of the French Atomic Energy Commission (CEA) generates waste with a variety of characteristics. The waste compatible with surface storage requirements is transferred to the French Radioactive Waste Management Agency (ANDRA); rest is reprocessed under a program which enables storage in compliance with the requirements of permits issued by safety Authorities. The waste reprocessing program provides for the construction of an incinerator capable of handling nearly all of the combustible waste generated by the Center and vitrification facility for treating liquid waste generated by the plutonium handling plant. (authors)

Field studies of safety security rescue technologies through training and response activities

Science.gov (United States)

Murphy, Robin R.; Stover, Sam

2006-05-01

This paper describes the field-oriented philosophy of the Institute for Safety Security Rescue Technology (iSSRT) and summarizes the activities and lessons learned during calendar year 2005 of its two centers: the Center for Robot-Assisted Search and Rescue and the NSF Safety Security Rescue industry/university cooperative research center. In 2005, iSSRT participated in four responses (La Conchita, CA, Mudslides, Hurricane Dennis, Hurricane Katrina, Hurricane Wilma) and conducted three field experiments (NJTF-1, Camp Hurricane, Richmond, MO). The lessons learned covered mobility, operator control units, wireless communications, and general reliability. The work has collectively identified six emerging issues for future work. Based on these studies, a 10-hour, 1 continuing education unit credit course on rescue robotics has been created and is available. Rescue robots and sensors are available for loan upon request.

Probabilistic Fracture Mechanics Analysis of the Orbiter's LH2 Feedline Flowliner

Science.gov (United States)

Bonacuse, Peter J. (Technical Monitor); Hudak, Stephen J., Jr.; Huyse, Luc; Chell, Graham; Lee, Yi-Der; Riha, David S.; Thacker, Ben; McClung, Craig; Gardner, Brian; Leverant, Gerald R.;

The storage center of very-low level radioactive wastes

International Nuclear Information System (INIS)

2008-01-01

The low level radioactive wastes have a radioactivity level as same as the natural radioactivity. This wastes category and their storage has been taken into account by the french legislation. This document presents the storage principles of the site, containment, safety and the Center organization. (A.L.B.)

Design and safety aspects of nuclear district heating reactors

International Nuclear Information System (INIS)

Brogli, R.; Mathews, D.; Pelloni, S.

1989-01-01

Extensive studies on the rationale, the potential and the technology of nuclear district heating have been performed in Switzerland. Beside economics the safety aspects were of primary importance. Due to the high costs to transport heat the heating reactor tend to be small and therefore, minimally staffed and located close to population centers. Stringed safety rules are therefore applying. Gas cooled reactors are well suited as district heating reactors since they have due to their characteristics several inherent features, significant safety margins and a remarkable radioactivity retention potential. Some ways to mitigate the effects of water ingress and graphite corrosion are under investigation. (author). 5 refs, 3 figs

Transition from metal-ligand bonding to halogen bonding involving a metal as halogen acceptor a study of Cu, Ag, Au, Pt, and Hg complexes

Science.gov (United States)

Oliveira, Vytor; Cremer, Dieter

2017-08-01

Utilizing all-electron Dirac-exact relativistic calculations with the Normalized Elimination of the Small Component (NESC) method and the local vibrational mode approach, the transition from metal-halide to metal halogen bonding is determined for Au-complexes interacting with halogen-donors. The local stretching force constants of the metal-halogen interactions reveal a smooth transition from weak non-covalent halogen bonding to non-classical 3-center-4-electron bonding and finally covalent metal-halide bonding. The strongest halogen bonds are found for dialkylaurates interacting with Cl2 or FCl. Differing trends in the intrinsic halogen-metal bond strength, the binding energy, and the electrostatic potential are explained.

Determination of an Ergonomically Sound Glovebox Glove Port Center Line

Energy Technology Data Exchange (ETDEWEB)

Christman, Marissa St John [Los Alamos National Laboratory

2016-11-30

Determine an ergonomic glovebox glove port center line location which will be used for standardization in new designs, thus allowing for predictable human work performance, reduced worker exposure to radiation and musculoskeletal injury risks, and improved worker comfort, efficiency, health, and safety.

Determination of an Ergonomically Sound Glovebox Glove Port Center Line

International Nuclear Information System (INIS)

Christman, Marissa St; Land, Whitney Morgan

2016-01-01

Determine an ergonomic glovebox glove port center line location which will be used for standardization in new designs, thus allowing for predictable human work performance, reduced worker exposure to radiation and musculoskeletal injury risks, and improved worker comfort, efficiency, health, and safety.

University building safety index measurement using risk and implementation matrix

Science.gov (United States)

Rahman, A.; Arumsari, F.; Maryani, A.

2018-04-01

Many high rise building constructed in several universities in Indonesia. The high-rise building management must provide the safety planning and proper safety equipment in each part of the building. Unfortunately, most of the university in Indonesia have not been applying safety policy yet and less awareness on treating safety facilities. Several fire accidents in university showed that some significant risk should be managed by the building management. This research developed a framework for measuring the high rise building safety index in university The framework is not only assessed the risk magnitude but also designed modular building safety checklist for measuring the safety implementation level. The safety checklist has been developed for 8 types of the university rooms, i.e.: office, classroom, 4 type of laboratories, canteen, and library. University building safety index determined using risk-implementation matrix by measuring the risk magnitude and assessing the safety implementation level. Building Safety Index measurement has been applied in 4 high rise buildings in ITS Campus. The building assessment showed that the rectorate building in secure condition and chemical department building in beware condition. While the library and administration center building was in less secure condition.

Quality Management Procedures Influence the Food Safety Practices at Childcare Centers

Science.gov (United States)

Enke, Allison A.; Briley, Margaret E.; Curtis, Suzanne R.; Greninger, Sue A.; Staskel, Deanna M.

2007-01-01

Childcare in the United States (US) has become a necessary part of life for most working parents with the increased use of center-based childcare over the past three decades. Approximately 13 million preschoolers attend some form of childcare. Literature indicates the main predictors of quality childcare programs are adequate experience and…

Guidelines for implementation of RCM on safety systems

International Nuclear Information System (INIS)

Kim, Tae Woon; Brijendra Singh.

1996-04-01

Reliability Centered Maintenance (RCM) methodology was originally developed by the commercial airlines industry in the early 1960s for identifying applicable and effective preventive maintenance tasks and as currently used in nuclear power industry. Effective maintenance of the systems at a nuclear power plant (NPP) is essential for its safe and reliable operation. Reliability Centered Maintenance at NPP is the program to assure that plant systems remain within an original design criteria and are not adversely affected during the plant life time. The aim of this report is to provide the guidelines to implement the RCM approach on NPP safety systems. Safety systems are usually standby and therefore, we need to periodically detect and repair failures that may have occurred since the previous activation or inspection the equipment. The RCM guidelines are intended to help identify the failure modes and related root causes and then decide the maintenance policies to achieve the high level of safety and reliability. The RCM is intended to improve or maintain high levels of system reliability and plant availability. Since the reliability of plant systems will be improved, the plant safety correspondingly will be increased. Another goal of RCM is to optimize the maintenance and surveillance tasks such that the overall level of resources required to accomplish essential tasks is kept to minimum. RCM also strives to eliminate unnecessary corrective maintenance and to select yet most cost-effective approach to maintenance, testing and inspection for system components. 9 refs. (Author) .new

Plutonium research and related activities at the Amarillo National Resource Center for Plutonium

International Nuclear Information System (INIS)

Hartley, R.S.; Beard, C.A.; Barnes, D.L.

1998-01-01

With the end of the Cold War, the US and Russia are reducing their nuclear weapons stockpiles. What to do with the materials from thousands of excess nuclear weapons is an important international challenge. How to handle the remaining US stockpile to ensure safe storage and reliability, in light of the aging support infrastructure, is an important national challenge. To help address these challenges and related issues, the Amarillo National Resource Center for Plutonium is working on behalf of the State of Texas with the US Department of Energy (DOE). The center directs three major programs that address the key aspects of the plutonium management issue: (1) the Communications, Education, Training and Community Involvement Program, which focuses on informing the public about plutonium and providing technical education at all levels; (2) the Environmental, Safety, and Health (ES and H) Program, which investigates the key ES and H impacts of activities related to the DOE weapons complex in Texas; and (3) the Nuclear and Other Materials Program, which is aimed at minimizing safety and proliferation risks by helping to develop and advocate safe stewardship, storage, and disposition of nuclear weapons materials. This paper provides an overview of the center's nuclear activities described in four broad categories of international activities, materials safety, plutonium storage, and plutonium disposition

Assessment of Patient Safety Culture in Primary Health Care Settings in Kuwait

Directory of Open Access Journals (Sweden)

Maha Mohamed Ghobashi

2014-01-01

Full Text Available Background Patient safety is critical component of health care quality. We aimed to assess the awareness of primary healthcare staff members about patient safety culture and explore the areas of deficiency and opportunities for improvement concerning this issue.Methods: This descriptive cross sectional study surveyed 369 staff members in four primary healthcare centers in Kuwait using self-administered “Hospital Survey on Patient Safety Culture” adopted questionnaire. The total number of respondents was 276 participants (response rate = 74.79%.Results: Five safety dimensions with lowest positivity (less than 50% were identified and these are; the non – punitive response to errors, frequency of event reporting, staffing, communication openness, center handoffs and transitions with the following percentages of positivity 24%, 32%, 41%, 45% and 47% respectively. The dimensions of highest positivity were teamwork within the center’s units (82% and organizational learning (75%.Conclusion: Patient safety culture in primary healthcare settings in Kuwait is not as strong as improvements for the provision of safe health care. Well-designed patient safety initiatives are needed to be integrated with organizational policies, particularly the pressing need to address the bioethical component of medical errors and their disclosure, communication openness and emotional issues related to them and investing the bright areas of skillful organizational learning and strong team working attitudes.    

An innovative approach to interdisciplinary occupational safety and health education.

Science.gov (United States)

Rosen, Mitchel A; Caravanos, Jack; Milek, Debra; Udasin, Iris

2011-07-01

The New York and New Jersey Education and Research Center (ERC) provides a range of graduate continuing education for occupational safety and health (OSH) professionals in training. A key element of the education is to provide interdisciplinary training to industrial hygienists, ergonomists, occupational medicine physicians and other health and safety trainees to prepare them for the collaboration required to solve the complex occupational health and safety problems they will face in their careers. This center has developed an innovative interdisciplinary training approach that provides an historical aspect, while allowing the graduate students to identify solutions to occupational issues from a multi-disciplinary approach. The ERC developed a tour that brings students to sites of historical and/or contemporary significance in the occupational safety and health and environmental fields. The ERC has conducted five tours, and has included 85 students and residents as participants. 80% of participants rated the tour as providing a high amount of OSH knowledge gained. 98% of the participants felt the goal of providing interdisciplinary education was achieved. This tour has been successful in bridging the OSH fields to better understand how occupational and environmental exposures have occurred, in order to prevent future exposures so that workplace conditions and health can be improved. Copyright © 2011 Wiley-Liss, Inc.

Amarillo National Resource Center for Plutonium 1999 plan

Energy Technology Data Exchange (ETDEWEB)

NONE

1999-01-30

The purpose of the Amarillo National Resource Center for Plutonium is to serve the Texas Panhandle, the State of Texas and the US Department of Energy by: conducting scientific and technical research; advising decision makers; and providing information on nuclear weapons materials and related environment, safety, health, and nonproliferation issues while building academic excellence in science and technology. This paper describes the electronic resource library which provides the national archives of technical, policy, historical, and educational information on plutonium. Research projects related to the following topics are described: Environmental restoration and protection; Safety and health; Waste management; Education; Training; Instrumentation development; Materials science; Plutonium processing and handling; and Storage.

Amarillo National Resource Center for Plutonium 1999 plan

International Nuclear Information System (INIS)

1999-01-01

The purpose of the Amarillo National Resource Center for Plutonium is to serve the Texas Panhandle, the State of Texas and the US Department of Energy by: conducting scientific and technical research; advising decision makers; and providing information on nuclear weapons materials and related environment, safety, health, and nonproliferation issues while building academic excellence in science and technology. This paper describes the electronic resource library which provides the national archives of technical, policy, historical, and educational information on plutonium. Research projects related to the following topics are described: Environmental restoration and protection; Safety and health; Waste management; Education; Training; Instrumentation development; Materials science; Plutonium processing and handling; and Storage

Developing the Safety of Atrial Fibrillation Ablation Registry Initiative (SAFARI) as a collaborative pan-stakeholder critical path registry model: a Cardiac Safety Research Consortium "Incubator" Think Tank.

Science.gov (United States)

Al-Khatib, Sana M; Calkins, Hugh; Eloff, Benjamin C; Kowey, Peter; Hammill, Stephen C; Ellenbogen, Kenneth A; Marinac-Dabic, Danica; Waldo, Albert L; Brindis, Ralph G; Wilbur, David J; Jackman, Warren M; Yaross, Marcia S; Russo, Andrea M; Prystowsky, Eric; Varosy, Paul D; Gross, Thomas; Pinnow, Ellen; Turakhia, Mintu P; Krucoff, Mitchell W

2010-10-01

Although several randomized clinical trials have demonstrated the safety and efficacy of catheter ablation of atrial fibrillation (AF) in experienced centers, the outcomes of this procedure in routine clinical practice and in patients with persistent and long-standing persistent AF remain uncertain. Brisk adoption of this therapy by physicians with diverse training and experience highlights potential concerns regarding the safety and effectiveness of this procedure. Some of these concerns could be addressed by a national registry of AF ablation procedures such as the Safety of Atrial Fibrillation Ablation Registry Initiative that was initially proposed at a Cardiac Safety Research Consortium Think Tank meeting in April 2009. In January 2010, the Cardiac Safety Research Consortium, in collaboration with the Duke Clinical Research Institute, the US Food and Drug Administration, the American College of Cardiology, and the Heart Rhythm Society, held a follow-up meeting of experts in the field to review the construct and progress to date. Other participants included the National Heart, Lung, and Blood Institute; the Centers for Medicare and Medicaid Services; the Agency for Healthcare Research and Quality; the AdvaMed AF working group; and additional industry representatives. This article summarizes the discussions that occurred at the meeting of the state of the Safety of Atrial Fibrillation Ablation Registry Initiative, the identification of a clear pathway for its implementation, and the exploration of solutions to potential issues in the execution of this registry. Copyright © 2010 Mosby, Inc. All rights reserved.

Trends in safety objectives for nuclear district heating plants

Energy Technology Data Exchange (ETDEWEB)

Brogli, R [Paul Scherrer Inst., Villigen (Switzerland)

1997-09-01

Safety objectives for dedicated nuclear heating plants are strongly influenced on the one hand by what is accepted for electricity nuclear stations, and on the other hand by the requirement that for economical reasons heating reactors have to be located close to population centers. The paper discusses the related trends and comes to the conclusion that on account of the specific technical characteristics of nuclear heating plants adequate safety can be provided even for highly populated sites. (author). 8 refs.

The specific tasks of RF TSO - FSUE VO 'Safety', related with Implementation of obligations under the Convention on Nuclear Safety

International Nuclear Information System (INIS)

Potapov, V.; Kuznetsov, M.; Kapralov, E.

2010-01-01

It was more than 20 years ago that IAEA discussed the issue pertaining to the need in scientific and engineering support to the regulatory body. The Convention on Nuclear Safety being the keystone in assurance of the global nuclear safety and security regime was adopted in 1994. It is pointed out that two independent organizations supervised by Rostechnadzor have been established within the Russian TSO system, FSUE VO 'Safety' being one of them. The tasks of the organization comprise obligatory certification of equipment as well as acceptance of equipment before its delivery to the NPP both in Russia and in the countries constructing the power units based on the Russian designs. The acceptance procedure has been set forth in the new Russian document at the level of the federal rules and regulations for nuclear safety assurance. As far as its implementation decision is concerned, a task for selection and training of personnel has been set and allocated on the Training and Methodological Center of Nuclear and Radiation Safety established with the support of FSUE VO 'Safety', which provides training programmes and specific lecture courses in the wide range of the relevant topics. (author)

Estimation of the ripple effects on a regional community of the formation of the nuclear energy science complex in Gyeongju

Energy Technology Data Exchange (ETDEWEB)

Lee, Byung-Sik [Dankook Univ., Chungnam (Korea, Republic of). Dept. of Nuclear Engineering; Moon, Joo Hyun [Dongguk Univ. Gyeongju, Gyeongbuk (Korea, Republic of). Dept. of Nuclear Energy Engineering

2017-05-15

Korea has developed advanced nuclear technologies, including those for future nuclear energy systems and the safe management of spent nuclear fuel, and is about to make a decision as to whether to make a massive investment in the development R and D for commercialization of them. There is no area large enough to accommodate all the development R and D-related facilities together at Korea Atomic Energy Research Institute (KAERI) to perform the development R and Ds. KAERI seeks solutions to the space problem, which includes the construction of a nuclear energy science complex (NESC). Gyeongju is one of the potential sites. This study estimated the ripple effects on the regional community if the NESC is to be formed in Gyeongju using inter-regional input-output analysis. The estimation shows that the ripple effects to the regional community of the formation of the NESC in Gyeongju would be 1,086,633 billion Korean Won (KRW) for regional production inducement, 455,299 billion KRW for value-added inducement, and 9,592 persons for employment inducement.

Safety research for LWR type reactors

International Nuclear Information System (INIS)

1989-07-01

The current R and D activities are to be seen in connection with the LWR risk assessment studies. Two trends are emerging, of which the one concentrates more on BWR-specific problems, and the other on the efficiency or safety-related assessment of accident management activities. This annual report of 1988 reviews the progress of work done by the institutes and departments of the Karlsruhe Nuclear Research Center, (KfK), or on behalf of KfK by external institutions, in the field of safety research. The papers of this report present the state of work at the end of the year 1988. They are written in German, with an abstract in English. (orig./HP) [de

The safety net medical home initiative: transforming care for vulnerable populations.

Science.gov (United States)

Sugarman, Jonathan R; Phillips, Kathryn E; Wagner, Edward H; Coleman, Katie; Abrams, Melinda K

2014-11-01

Despite findings that medical homes may reduce or eliminate health care disparities among underserved and minority populations, most previous medical home pilot and demonstration projects have focused on health care delivery systems serving commercially insured patients and Medicare beneficiaries. To develop a replicable approach to support medical home transformation among diverse practices serving vulnerable and underserved populations. Facilitated by a national program team, convening organizations in 5 states provided coaching and learning community support to safety net practices over a 4-year period. To guide transformation, we developed a framework of change concepts aligned with supporting tools including implementation guides, activity checklists, and measurement instruments. Sixty-five health centers, homeless clinics, private practices, residency training centers, and other safety net practices in Colorado, Idaho, Massachusetts, Oregon, and Pennsylvania. We evaluated implementation of the change concepts using the Patient-Centered Medical Home-Assessment, and conducted a survey of participating practices to assess perceptions of the impact of the technical assistance. All practices implemented key features of the medical home model, and nearly half (47.6%) implemented the 33 identified key changes to a substantial degree as evidenced by level A Patient-Centered Medical Home-Assessment scores. Two thirds of practices that achieved substantial implementation did so only after participating in the initiative for >2 years. By the end of the initiative, 83.1% of sites achieved external recognition as medical homes. Despite resource constraints and high-need populations, safety net clinics made considerable progress toward medical home implementation when provided robust, multimodal support over a 4-year period.

Technical Excellence and Communication: The Cornerstones for Successful Safety and Mission Assurance Programs

Science.gov (United States)

Malone, Roy W.; Livingston, John M.

2010-01-01

The paper describes the role of technical excellence and communication in the development and maintenance of safety and mission assurance programs. The Marshall Space Flight Center (MSFC) Safety and Mission Assurance (S&MA) organization is used to illustrate philosophies and techniques that strengthen safety and mission assurance efforts and that contribute to healthy and effective organizational cultures. The events and conditions leading to the development of the MSFC S&MA organization are reviewed. Historic issues and concerns are identified. The adverse effects of resource limitations and risk assessment roles are discussed. The structure and functions of the core safety, reliability, and quality assurance functions are presented. The current organization s mission and vision commitments serve as the starting points for the description of the current organization. The goals and objectives are presented that address the criticisms of the predecessor organizations. Additional improvements are presented that address the development of technical excellence and the steps taken to improve communication within the Center, with program customers, and with other Agency S&MA organizations.

Technical Excellence and Communication, the Cornerstones for Successful Safety and Mission Assurance Programs

Science.gov (United States)

Malone, Roy W.; Livingston, John M.

2010-09-01

The paper describes the role of technical excellence and communication in the development and maintenance of safety and mission assurance programs. The Marshall Space Flight Center(MSFC) Safety and Mission Assurance(S&MA) organization is used to illustrate philosophies and techniques that strengthen safety and mission assurance efforts and that contribute to healthy and effective organizational cultures. The events and conditions leading to the development of the MSFC S&MA organization are reviewed. Historic issues and concerns are identified. The adverse effects of resource limitations and risk assessment roles are discussed. The structure and functions of the core safety, reliability, and quality assurance functions are presented. The current organization’s mission and vision commitments serve as the starting points for the description of the current organization. The goals and objectives are presented that address the criticisms of the predecessor organizations. Additional improvements are presented that address the development of technical excellence and the steps taken to improve communication within the Center, with program customers, and with other Agency S&MA organizations.

Perspective of Nurses toward the Patient Safety Culture in Neonatal Intensive Care Units

Directory of Open Access Journals (Sweden)

Saba Farzi

2017-12-01

Conclusion: According to the results, adherence to the dimensions of the patient safety culture was poor in the studied hospitals. Therefore, the patient safety culture requires special attention by providing proper facilities, adequate staff, developing checklists for handoffs and transitions, and surveillance and continuous monitoring by healthcare centers. Furthermore, a system-based approach should be implemented to deal with errors, while a persuasive reporting approach is needed to promote the patient safety culture in the NICUs of these hospitals.

Safety regulation: The lessons of workplace safety rule management for managing the regulatory burden

OpenAIRE

Hale, A.R.; Borys, D.; Adams, M.

2012-01-01

There is a strong political consensus in a number of countries that occupational safety and health regulation is stifling industrial innovation and development and is feeding a culture of damaging risk aversion and petty bureaucracy. In a number of countries this has led to proposals to repeal regulations and reduce the regulatory burden. The authors were commissioned to prepare a discussion paper on this issue by the Mercatus Center of George Mason University in Arlington, Virginia, aimed pa...

Safer Systems: A NextGen Aviation Safety Strategic Goal

Science.gov (United States)

Darr, Stephen T.; Ricks, Wendell R.; Lemos, Katherine A.

2008-01-01

The Joint Planning and Development Office (JPDO), is charged by Congress with developing the concepts and plans for the Next Generation Air Transportation System (NextGen). The National Aviation Safety Strategic Plan (NASSP), developed by the Safety Working Group of the JPDO, focuses on establishing the goals, objectives, and strategies needed to realize the safety objectives of the NextGen Integrated Plan. The three goal areas of the NASSP are Safer Practices, Safer Systems, and Safer Worldwide. Safer Practices emphasizes an integrated, systematic approach to safety risk management through implementation of formalized Safety Management Systems (SMS) that incorporate safety data analysis processes, and the enhancement of methods for ensuring safety is an inherent characteristic of NextGen. Safer Systems emphasizes implementation of safety-enhancing technologies, which will improve safety for human-centered interfaces and enhance the safety of airborne and ground-based systems. Safer Worldwide encourages coordinating the adoption of the safer practices and safer systems technologies, policies and procedures worldwide, such that the maximum level of safety is achieved across air transportation system boundaries. This paper introduces the NASSP and its development, and focuses on the Safer Systems elements of the NASSP, which incorporates three objectives for NextGen systems: 1) provide risk reducing system interfaces, 2) provide safety enhancements for airborne systems, and 3) provide safety enhancements for ground-based systems. The goal of this paper is to expose avionics and air traffic management system developers to NASSP objectives and Safer Systems strategies.

Manche storage Centre. Information report on nuclear safety and radiation protection 2015

International Nuclear Information System (INIS)

2016-01-01

After a presentation of the Manche Storage Centre (CSM), the first French center of surface storage of low- and intermediate-level radioactive wastes, of its history, its buildings and activities, of the multi-layer cover, of the water management system (installation, controls, sampling), this report then describes the measures related to nuclear safety, the management of conventional and nuclear wastes produced by the Centre, the other impacts, the control, maintenance and follow-up of installations, the radiation protection and security of the center, the incidents and accidents that occurred at the facility, and the public information and communication actions. Recommendations of the Health and safety Committee (CHSCT) are reported at the end

78 FR 37228 - Cooperative Agreement To Support the Western Center for Food Safety

Science.gov (United States)

2013-06-20

... FSMA activities. FDA regards the development and strengthening of public-private partnerships to be a... agricultural producers, along with other public and private stakeholders. This established UC Davis network... study the agro- ecological differences that may impact food safety in the agricultural sector. WCFS has...

Activity of safety review for the facilities using nuclear material (2). Safety review results and maintenance experiences for hot laboratories

International Nuclear Information System (INIS)

Amagai, Tomio; Fujishima, Tadatsune; Mizukoshi, Yasutaka; Sakamoto, Naoki; Ohmori, Tsuyoshi

2009-01-01

In the site of O-arai Research and Development Center of Japan Atomic Energy Agency (JAEA), five hot laboratories for post-irradiation examination and development of plutonium fuels are operated more than 30 years. A safety review method for preventive maintenance on these hot laboratories includes test facilities and devices are established in 2003. After that, the safety review of these facilities and devices are done and taken the necessary maintenance based on the results in each year. In 2008, 372 test facilities and devices in these hot laboratories were checked and reviewed by this method. As a results of the safety review, repair issues of 38 facilities of above 372 facilities were resolved. This report shows the review results and maintenance experiences based on the results. (author)

Perspectives on reactor safety

Energy Technology Data Exchange (ETDEWEB)

Haskin, F.E. [New Mexico Univ., Albuquerque, NM (United States). Dept. of Chemical and Nuclear Engineering; Camp, A.L. [Sandia National Labs., Albuquerque, NM (United States)

1994-03-01

The US Nuclear Regulatory Commission (NRC) maintains a technical training center at Chattanooga, Tennessee to provide appropriate training to both new and experienced NRC employees. This document describes a one-week course in reactor, safety concepts. The course consists of five modules: (1) historical perspective; (2) accident sequences; (3) accident progression in the reactor vessel; (4) containment characteristics and design bases; and (5) source terms and offsite consequences. The course text is accompanied by slides and videos during the actual presentation of the course.

Perspectives on reactor safety

International Nuclear Information System (INIS)

Haskin, F.E.

1994-03-01

The US Nuclear Regulatory Commission (NRC) maintains a technical training center at Chattanooga, Tennessee to provide appropriate training to both new and experienced NRC employees. This document describes a one-week course in reactor, safety concepts. The course consists of five modules: (1) historical perspective; (2) accident sequences; (3) accident progression in the reactor vessel; (4) containment characteristics and design bases; and (5) source terms and offsite consequences. The course text is accompanied by slides and videos during the actual presentation of the course

Development and Validation of a Short-Form Safety Net Medical Home Scale.

Science.gov (United States)

Nocon, Robert S; Gunter, Kathryn E; Gao, Yue; Lee, Sang Mee; Chin, Marshall H

2017-12-01

To develop a short-form Safety Net Medical Home Scale (SNMHS) for assessing patient-centered medical home (PCMH) capability in safety net clinics. National surveys of federally qualified health centers (FQHCs). Interviews with FQHC directors. We constructed three short-form SNMHS versions and examined correlations with full SNMHS and related primary care assessments. We tested usability with FQHC directors and reviewed scale development with an advisory group. Federally qualified health center surveys were administered in 2009 and 2013, by mail and online. Usability testing was conducted through telephone interviews with FQHC directors in 2013. Six-, 12-, and 18-question short-form SNMHS versions had Pearson correlations with full scale of 0.84, 0.92, and 0.96, respectively. All versions showed a level of convergent validity with other primary care assessment scales comparable to the full SNMHS. User testers found short forms to be low-burden, though missing some PCMH concepts. Advisory group members expressed caution over missing concepts and appropriate use of short-form self-assessments. Short-form versions of SNMHS showed strong correlations with full scale and may be useful for brief assessment of safety net PCMH capability. Each short-form SNMHS version may be appropriate for different research, quality improvement, and assessment purposes. © Health Research and Educational Trust.

Medical Waste Management in Community Health Centers.

Science.gov (United States)

Tabrizi, Jafar Sadegh; Rezapour, Ramin; Saadati, Mohammad; Seifi, Samira; Amini, Behnam; Varmazyar, Farahnaz

2018-02-01

Non-standard management of medical waste leads to irreparable side effects. This issue is of double importance in health care centers in a city which are the most extensive system for providing Primary Health Care (PHC) across Iran cities. This study investigated the medical waste management standards observation in Tabriz community health care centers, northwestern Iran. In this triangulated cross-sectional study (qualitative-quantitative), data collecting tool was a valid checklist of waste management process developed based on Iranian medical waste management standards. The data were collected in 2015 through process observation and interviews with the health center's staff. The average rate of waste management standards observance in Tabriz community health centers, Tabriz, Iran was 29.8%. This case was 22.8% in dimension of management and training, 27.3% in separating and collecting, 31.2% in transport and temporary storage, and 42.9% in sterilization and disposal. Lack of principal separation of wastes, inappropriate collecting and disposal cycle of waste and disregarding safety tips (fertilizer device performance monitoring, microbial cultures and so on) were among the observed defects in health care centers supported by quantitative data. Medical waste management was not in a desirable situation in Tabriz community health centers. The expansion of community health centers in different regions and non-observance of standards could predispose to incidence the risks resulted from medical wastes. So it is necessary to adopt appropriate policies to promote waste management situation.

Nursing perception of the impact of medication carts on patient safety and ergonomics in a teaching health care center.

Science.gov (United States)

Rochais, Élise; Atkinson, Suzanne; Bussières, Jean-François

2013-04-01

In our Quebec (Canada) University Hospital Center, 68 medication carts have been implemented as part of a nationally funded project on drug distribution technologies. There are limited data published about the impact of medication carts in point-of-care units. Our main objective was to assess nursing staff's perception and satisfaction of medication carts on patient safety and ergonomics. Quantitative and qualitative cross-sectional study. Data were gathered from a printed questionnaire administered to nurses and an organized focus group composed of nurses and pharmacists. A total of 195 nurses completed the questionnaire. Eighty percent of the nurses agreed that medication carts made health care staff's work easier and 64% agreed that it helped to reduce medication incidents/accidents. Only 27% and 43% agreed that carts' location reduces the risk of patients' interruptions and colleagues' interruptions, respectively. A total of 17 suggestions were extracted from the focus group (n = 7 nurses; n = 3 pharmacist) and will be implemented in the next year. This descriptive study confirms the positive perception and satisfaction of nurses exposed to medication carts. However, interruptions are a major concern and source of dissatisfaction. The focus group has revealed many issues which will be improved.

Failure mode and effects analysis based risk profile assessment for stereotactic radiosurgery programs at three cancer centers in Brazil

Energy Technology Data Exchange (ETDEWEB)

Teixeira, Flavia C., E-mail: flavitiz@gmail.com [CNEN—Comissao Nacional de Energia Nuclear, Rio de Janeiro, RJ 22290-901, Brazil and LCR/UERJ—Laboratorio de Ciencias Radiologicas/Universidade do Estado do Rio de Janeiro, Rio de Janeiro, RJ 20550-013 (Brazil); Almeida, Carlos E. de [LCR/UERJ—Laboratorio de Ciencias Radiologicas/Universidade do Estado do Rio de Janeiro, Rio de Janeiro, RJ 20550-013 (Brazil); Saiful Huq, M. [Department of Radiation Oncology, University of Pittsburgh Cancer Institute and UPMC Cancer Center, Pittsburgh, Pennsylvania 15232 (United States)

2016-01-15

Purpose: The goal of this study was to evaluate the safety and quality management program for stereotactic radiosurgery (SRS) treatment processes at three radiotherapy centers in Brazil by using three industrial engineering tools (1) process mapping, (2) failure modes and effects analysis (FMEA), and (3) fault tree analysis. Methods: The recommendations of Task Group 100 of American Association of Physicists in Medicine were followed to apply the three tools described above to create a process tree for SRS procedure for each radiotherapy center and then FMEA was performed. Failure modes were identified for all process steps and values of risk priority number (RPN) were calculated from O, S, and D (RPN = O × S × D) values assigned by a professional team responsible for patient care. Results: The subprocess treatment planning was presented with the highest number of failure modes for all centers. The total number of failure modes were 135, 104, and 131 for centers I, II, and III, respectively. The highest RPN value for each center is as follows: center I (204), center II (372), and center III (370). Failure modes with RPN ≥ 100: center I (22), center II (115), and center III (110). Failure modes characterized by S ≥ 7, represented 68% of the failure modes for center III, 62% for center II, and 45% for center I. Failure modes with RPNs values ≥100 and S ≥ 7, D ≥ 5, and O ≥ 5 were considered as high priority in this study. Conclusions: The results of the present study show that the safety risk profiles for the same stereotactic radiotherapy process are different at three radiotherapy centers in Brazil. Although this is the same treatment process, this present study showed that the risk priority is different and it will lead to implementation of different safety interventions among the centers. Therefore, the current practice of applying universal device-centric QA is not adequate to address all possible failures in clinical processes at different

Failure mode and effects analysis based risk profile assessment for stereotactic radiosurgery programs at three cancer centers in Brazil

International Nuclear Information System (INIS)

Teixeira, Flavia C.; Almeida, Carlos E. de; Saiful Huq, M.

2016-01-01

Purpose: The goal of this study was to evaluate the safety and quality management program for stereotactic radiosurgery (SRS) treatment processes at three radiotherapy centers in Brazil by using three industrial engineering tools (1) process mapping, (2) failure modes and effects analysis (FMEA), and (3) fault tree analysis. Methods: The recommendations of Task Group 100 of American Association of Physicists in Medicine were followed to apply the three tools described above to create a process tree for SRS procedure for each radiotherapy center and then FMEA was performed. Failure modes were identified for all process steps and values of risk priority number (RPN) were calculated from O, S, and D (RPN = O × S × D) values assigned by a professional team responsible for patient care. Results: The subprocess treatment planning was presented with the highest number of failure modes for all centers. The total number of failure modes were 135, 104, and 131 for centers I, II, and III, respectively. The highest RPN value for each center is as follows: center I (204), center II (372), and center III (370). Failure modes with RPN ≥ 100: center I (22), center II (115), and center III (110). Failure modes characterized by S ≥ 7, represented 68% of the failure modes for center III, 62% for center II, and 45% for center I. Failure modes with RPNs values ≥100 and S ≥ 7, D ≥ 5, and O ≥ 5 were considered as high priority in this study. Conclusions: The results of the present study show that the safety risk profiles for the same stereotactic radiotherapy process are different at three radiotherapy centers in Brazil. Although this is the same treatment process, this present study showed that the risk priority is different and it will lead to implementation of different safety interventions among the centers. Therefore, the current practice of applying universal device-centric QA is not adequate to address all possible failures in clinical processes at different

Computational methods for criticality safety analysis within the scale system

International Nuclear Information System (INIS)

Parks, C.V.; Petrie, L.M.; Landers, N.F.; Bucholz, J.A.

1986-01-01

The criticality safety analysis capabilities within the SCALE system are centered around the Monte Carlo codes KENO IV and KENO V.a, which are both included in SCALE as functional modules. The XSDRNPM-S module is also an important tool within SCALE for obtaining multiplication factors for one-dimensional system models. This paper reviews the features and modeling capabilities of these codes along with their implementation within the Criticality Safety Analysis Sequences (CSAS) of SCALE. The CSAS modules provide automated cross-section processing and user-friendly input that allow criticality safety analyses to be done in an efficient and accurate manner. 14 refs., 2 figs., 3 tabs

76 FR 66075 - Center for Scientific Review; Notice of Closed Meetings

Science.gov (United States)

2011-10-25

...: Non-HIV Diagnostics, Food Safety, Sterilization/Disinfection and Bioremediation. Date: November 17-18... Hotel, 4300 Military Road, NW., Washington, DC 20015. Contact Person: Gagan Pandya, PhD, Scientific... applications. Place: Legacy Hotel and Meeting Center, 1775 Rockville Pike, Rockville, MD 20852. Contact Person...

1986 international meeting of nuclear reactor safety committees

International Nuclear Information System (INIS)

Moeller, D.W.

1987-01-01

During the week of Oct. 20-23, 1986, nuclear power-plant safety representatives from the Federal Republic of Germany (FRG), France, Japan, and the US assembled to discuss subjects of mutual interest. The meeting, the first of its kind, was organized under the leadership and direction of David A. Ward, Chairman, Advisory Committee on Reactor Safeguards, US Nuclear Regulatory Commission (NRC), and held at the Wingspread Conference Center of the Johnson Foundation in Racine, Wis. Approximately 40 representatives of the several countries attended. Discussions were candid and provided the participants an opportunity to share thoughts and information on nuclear safety concerns and solutions

NASA's Software Safety Standard

Science.gov (United States)

Ramsay, Christopher M.

2007-01-01

NASA relies more and more on software to control, monitor, and verify its safety critical systems, facilities and operations. Since the 1960's there has hardly been a spacecraft launched that does not have a computer on board that will provide command and control services. There have been recent incidents where software has played a role in high-profile mission failures and hazardous incidents. For example, the Mars Orbiter, Mars Polar Lander, the DART (Demonstration of Autonomous Rendezvous Technology), and MER (Mars Exploration Rover) Spirit anomalies were all caused or contributed to by software. The Mission Control Centers for the Shuttle, ISS, and unmanned programs are highly dependant on software for data displays, analysis, and mission planning. Despite this growing dependence on software control and monitoring, there has been little to no consistent application of software safety practices and methodology to NASA's projects with safety critical software. Meanwhile, academia and private industry have been stepping forward with procedures and standards for safety critical systems and software, for example Dr. Nancy Leveson's book Safeware: System Safety and Computers. The NASA Software Safety Standard, originally published in 1997, was widely ignored due to its complexity and poor organization. It also focused on concepts rather than definite procedural requirements organized around a software project lifecycle. Led by NASA Headquarters Office of Safety and Mission Assurance, the NASA Software Safety Standard has recently undergone a significant update. This new standard provides the procedures and guidelines for evaluating a project for safety criticality and then lays out the minimum project lifecycle requirements to assure the software is created, operated, and maintained in the safest possible manner. This update of the standard clearly delineates the minimum set of software safety requirements for a project without detailing the implementation for those

MORT: a safety management program developed for ERDA

International Nuclear Information System (INIS)

1977-03-01

ERDA's System Safety Development Center (SSDC) is located at the Idaho National Engineering Laboratory under the EG and G Idaho, Inc., contract administered by the Idaho Operations Office. The SSDC performs a variety of tasks for ERDA's Division of Safety, Standards, and Compliance, for the purpose of improvement and application of safety program elements. Primary among these tasks are development and demonstration of new methodologies, training, consultation, and technical writing. This information package (ERDA 77-38) is an example of the later task, aimed at communicating to a general audience the nature and purpose of major features of the Management Oversight and Risk Tree (MORT) program. The SSDC also originates a guideline series of monographs (the ERDA 76-45 series) for individuals who desire more specific explanations of the MORT program

Design, operation, and safety of single-room interventional MRI suites: practical experience from two centers.

Science.gov (United States)

White, Mark J; Thornton, John S; Hawkes, David J; Hill, Derek L G; Kitchen, Neil; Mancini, Laura; McEvoy, Andrew W; Razavi, Reza; Wilson, Sally; Yousry, Tarek; Keevil, Stephen F

2015-01-01

The design and operation of a facility in which a magnetic resonance imaging (MRI) scanner is incorporated into a room used for surgical or endovascular cardiac interventions presents several challenges. MR safety must be maintained in the presence of a much wider variety of equipment than is found in a diagnostic unit, and of staff unfamiliar with the MRI environment, without compromising the safety and practicality of the interventional procedure. Both the MR-guided cardiac interventional unit at Kings College London and the intraoperative imaging suite at the National Hospital for Neurology and Neurosurgery are single-room interventional facilities incorporating 1.5 T cylindrical-bore MRI scanners. The two units employ similar strategies to maintain MR safety, both in original design and day-to-day operational workflows, and between them over a decade of incident-free practice has been accumulated. This article outlines these strategies, highlighting both similarities and differences between the units, as well as some lessons learned and resulting procedural changes made in both units since installation. © 2014 Wiley Periodicals, Inc.

Forging successful academic-community partnerships with community health centers: the California statewide Area Health Education Center (AHEC) experience.

Science.gov (United States)

Fowkes, Virginia; Blossom, H John; Mitchell, Brenda; Herrera-Mata, Lydia

2014-01-01

Increased access to insurance under the Affordable Care Act will increase demands for clinical services in community health centers (CHCs). CHCs also have an increasingly important educational role to train clinicians who will remain to practice in community clinics. CHCs and Area Health Education Centers (AHECs) are logical partners to prepare the health workforce for the future. Both are sponsored by the Health Resources and Services Administration, and they share a mission to improve quality of care in medically underserved communities. AHECs emphasize the educational side of the mission, and CHCs the service side. Building stronger partnerships between them can facilitate a balance between education and service needs.From 2004 to 2011, the California Statewide AHEC program and its 12 community AHECs (centers) reorganized to align training with CHC workforce priorities. Eight centers merged into CHC consortia; others established close partnerships with CHCs in their respective regions. The authors discuss issues considered and approaches taken to make these changes. Collaborative innovative processes with program leadership, staff, and center directors revised the program mission, developed common training objectives with an evaluation plan, and defined organizational, functional, and impact characteristics for successful AHECs in California. During this planning, centers gained confidence as educational arms for the safety net and began collaborations with statewide programs as well as among themselves. The AHEC reorganization and the processes used to develop, strengthen, and identify standards for centers forged the development of new partnerships and established academic-community trust in planning and implementing programs with CHCs.

Aube storage center for very-low-level radioactive wastes. Annual report 2010

International Nuclear Information System (INIS)

2011-09-01

The National Radioactive Waste Management Agency (Andra), was established by the December 1991 Waste Act as a public body in charge of the long-term management of all radioactive waste, under the supervision of the Ministry of Ecology, Energy, Sustainable Development and the Sea (formerly the Ministry of Industry and the Ministry of Environment), and the Ministry of Research. The Andra operates two storage centers in the Aube region (France): the center for short-lived low- and intermediate-level wastes, and the center for very-low-level radioactive wastes. This document is the 2010 activity report of the center for very-low-level radioactive wastes. It presents a review of the activities of the center: presentation of the installations, safety, security and radiation protection, environmental monitoring and effluents, public information and communication

Radiation Protection and Safety Department - annual report 1977

International Nuclear Information System (INIS)

Kiefer, H.; Koelzer, W.

1978-03-01

The duties cover tasks relative to radiation protection and safety on behalf of the institutes and departments of Kernforschungszentrum Karlsruhe and environmental monitoring for the whole Nuclear Research Center as well as own research and development work, mainly performed under the Nuclear Research Center and the Nuclear Safeguards Project. The centers of interest of R and D activities were: investigation of the atmospheric diffusion in the micro- and meso-scale, study of the radiological consequences of accidents in reactors under probabilistic aspects, implementation of nuclear fuel safeguarding systems, improvements in radiation protection measurement technology. This report gives details of the different duties, indicates the results of 1977 routine measurements, and reports about new results of investigations and developments of the working groups of the department. (orig.) [de

A conceptual framework for patient-centered fertility treatment.

Science.gov (United States)

Duthie, Elizabeth A; Cooper, Alexandra; Davis, Joseph B; Schoyer, Katherine D; Sandlow, Jay; Strawn, Estil Y; Flynn, Kathryn E

2017-09-07

Patient-centered care is a pillar of quality health care and is important to patients experiencing infertility. In this study we used empirical, in-depth data on couples' experiences of infertility treatment decision making to inform and revise a conceptual framework for patient-centered fertility treatment that was developed based on health care professionals' conceptualizations of fertility treatment, covering effectiveness, burden, safety, and costs. In this prospective, longitudinal mixed methods study, we collected data from both members (separately) of 37 couples who scheduled an initial consult with a reproductive specialist. Data collection occurred 1 week before the initial consultation, 1 week after the initial consultation, and then roughly 2, 4, 8, and 12 months later. Data collection included semi-structured qualitative interviews, self-reported questionnaires, and medical record review. Interviews were recorded, transcribed, and content analyzed in NVivo. A single coder analyzed all transcripts, with > 25% of transcripts coded by a second coder to ensure quality control and consistency. Content analysis of the interview transcripts revealed 6 treatment dimensions: effectiveness, physical and emotional burden, time, cost, potential risks, and genetic parentage. Thus, the revised framework for patient-centered fertility treatment retains much from the original framework, with modification to one dimension (from safety to potential risks) and the addition of two dimensions (time and genetic parentage). For patients and their partners making fertility treatment decisions, tradeoffs are explicitly considered across dimensions as opposed to each dimension being considered on its own. Patient-centered fertility treatment should account for the dimensions of treatment that patients and their partners weigh when making decisions about how to add a child to their family. Based on the lived experiences of couples seeking specialist medical care for

JICST Factual DatabaseJICST Chemical Substance Safety Regulation Database

Science.gov (United States)

Abe, Atsushi; Sohma, Tohru

JICST Chemical Substance Safety Regulation Database is based on the Database of Safety Laws for Chemical Compounds constructed by Japan Chemical Industry Ecology-Toxicology & Information Center (JETOC) sponsored by the Sience and Technology Agency in 1987. JICST has modified JETOC database system, added data and started the online service through JOlS-F (JICST Online Information Service-Factual database) in January 1990. JICST database comprises eighty-three laws and fourteen hundred compounds. The authors outline the database, data items, files and search commands. An example of online session is presented.

Safety of nuclear operation and maintenance

International Nuclear Information System (INIS)

Mori, M.; Nitta, T.; Sakai, K.

1994-01-01

The Kansai Electric Power Co. Inc.(Kansai EPC) aims to pursue a high quality and highly reliable operation in nuclear power generation in order to ensure safety by reducing the risk of accidents and win the confidence from the society and the public. It is emphasised that in order to realize this aim manufacturers and contractors cooperate with each other in performing high quality maintenance through plant lifetime maintenance system. TQC (Total Quality Control) activity enhances the motivation for each individual to have a quality-oriented mind and cultivate the safety culture. Under the lifetime employment practice, Kansai EPC and maintenance contractors can conduct systematic education and training, and the Maintenance Training Center helps to make it effective. 6 figs

Radiation safety system (RSS) backbones: Design, engineering, fabrication and installation

International Nuclear Information System (INIS)

Wilmarth, J.E.; Sturrock, J.C.; Gallegos, F.R.

1998-01-01

The Radiation Safety System (RSS) Backbones are part of an electrical/electronic/mechanical system insuring safe access and exclusion of personnel to areas at the Los Alamos Neutron Science Center (LANSCE) accelerator. The RSS Backbones control the safety fusible beam plugs which terminate transmission of accelerated ion beams in response to predefined conditions. Any beam or access fault of the backbone inputs will cause insertion of the beam plugs in the low energy beam transport. The Backbones serve the function of tying the beam plugs to the access control systems, beam spill monitoring systems and current-level limiting systems. In some ways the Backbones may be thought of as a spinal column with beam plugs at the head and nerve centers along the spinal column. The two Linac Backbone segments and experimental area segments form a continuous cable plant over 3,500 feet from beam plugs to the tip on the longest tail. The Backbones were installed in compliance with current safety standards, such as installation of the two segments in separate conduits or tray. Monitoring for ground-faults and input wiring verification was an added enhancement to the system. The system has the capability to be tested remotely

Application of the SEIPS Model to Analyze Medication Safety in a Crisis Residential Center.

Science.gov (United States)

Steele, Maria L; Talley, Brenda; Frith, Karen H

2018-02-01

Medication safety and error reduction has been studied in acute and long-term care settings, but little research is found in the literature regarding mental health settings. Because mental health settings are complex, medication administration is vulnerable to a variety of errors from transcription to administration. The purpose of this study was to analyze critical factors related to a mental health work system structure and processes that threaten safe medication administration practices. The Systems Engineering Initiative for Patient Safety (SEIPS) model provides a framework to analyze factors affecting medication safety. The model approach analyzes the work system concepts of technology, tasks, persons, environment, and organization to guide the collection of data. In the study, the Lean methodology tools were used to identify vulnerabilities in the system that could be targeted later for improvement activities. The project director completed face-to-face interviews, asked nurses to record disruptions in a log, and administered a questionnaire to nursing staff. The project director also conducted medication chart reviews and recorded medication errors using a standardized taxonomy for errors that allowed categorization of the prevalent types of medication errors. Results of the study revealed disruptions during the medication process, pharmacology training needs, and documentation processes as the primary opportunities for improvement. The project engaged nurses to identify sustainable quality improvement strategies to improve patient safety. The mental health setting carries challenges for safe medication administration practices. Through analysis of the structure, process, and outcomes of medication administration, opportunities for quality improvement and sustainable interventions were identified, including minimizing the number of distractions during medication administration, training nurses on psychotropic medications, and improving the documentation

Quantitative security and safety analysis with attack-fault trees

NARCIS (Netherlands)

Kumar, Rajesh; Stoelinga, Mariëlle Ida Antoinette

2017-01-01

Cyber physical systems, like power plants, medical devices and data centers have to meet high standards, both in terms of safety (i.e. absence of unintentional failures) and security (i.e. no disruptions due to malicious attacks). This paper presents attack fault trees (AFTs), a formalism that

Violence against health workers in Family Medicine Centers

Directory of Open Access Journals (Sweden)

Al-Turki N

2016-05-01

Full Text Available Nouf Al-Turki,1 Ayman AM Afify,1 Mohammed AlAteeq2 1Family Medicine Department, Prince Sultan Military Medical City, 2Department of Family Medicine and PHC, King Abdul-Aziz Medical City, National Guard Health Affairs, Riyadh, Kingdom of Saudi Arabia Background: Health care violence is a significant worldwide problem with negative consequences on both the safety and well-being of health care workers as well as workplace activities. Reports examining health care violence in Saudi Arabia are limited and the results are conflicting.Objective: To estimate the prevalence and determine the demographic and occupational characteristics associated with workplace violence in primary care centers in Riyadh, Saudi Arabia.Methods: A cross-sectional study included 270 health care workers in 12 family medicine centers in Riyadh during November and December 2014. A structured self-administered questionnaire was used to estimate the frequency, timing, causes, reactions, and consequences of workplace violence plus participants’ demographic and occupational data.Results: A total 123 health care workers (45.6% experienced some kind of violence over 12 months prior to the study. These included physical (6.5% and nonphysical violence (99.2%, including verbal violence (94.3% and intimidation (22.0%. Offenders were patients (71.5% in the majority of cases, companions (20.3%, or both (3.3%. Almost half (48.0% of health care workers who experienced violence did nothing, 38.2% actively reported the event, and 13.8% consulted a colleague. A significant association of workplace violence was found with working multiple shifts, evening or night shift, and lack of an encouraging environment to report violence.Conclusion: Workplace violence is still a significant problem in primary care centers. The high frequency of violence together with underreporting may indicate the inefficiency of the current safety program. More safety programs and training activities for health care

report transparency and nuclear safety 2007- CISBIO

International Nuclear Information System (INIS)

2007-01-01

This report presents the activities of CISBIO, nuclear base installation, for the year 2007. CISBIO realizes at Saclay most of the radiopharmaceuticals and drugs distributed in France for the nuclear medicine. The actions concerning the safety, the radiation protection, the significant events, the release control and the environmental impacts and the wastes stored on the center are discussed. (A.L.B.)

Functioning of the IPSN Crisis Technical Center (CTC) inside the Crisis National Organisation

International Nuclear Information System (INIS)

Cernes, A.

1995-01-01

A forethought about the organization and counter-actions to follow in case of reactor accident crisis has been carried out by the French nuclear partners (operators and public authorities). This forethought has led to the creation of a Crisis National Organization which determines the responsibilities and missions of each partner. Inside this organization, the IPSN (Institute for Nuclear Protection and Safety) plays the role of technical support and expert for the Safety Authority. To carry out these missions, a Crisis Technical Center has been installed for ten years in Fontenay-aux-Roses CEA center. This document is a presentation of the CTC activities and evolutions in the framework of the existing National Organization. The main axes along which this activity will evolve in the future are summarized. (J.S.). 3 figs

Food safety and consumer behaviour

DEFF Research Database (Denmark)

Frewer, Lynn; Fischer, Arnout; Scholderer, Joachim

2005-01-01

, consumers may not pay enough attention to some types of food safety issue, such as the risk of food poisoning from microbial contamination, which may at best be debilitating, and at worst fatal (Center for Disease Control and Prevention, 1994). This risk is certainly largely avoidable through taking......Food safety is a priority for many consumers, and there is an expectation throughout society that the food supplied for human consumption is safe and nutritious to eat. Understanding technical risk estimates alone, however, will not explain the risk-related behaviours of consumers. On the one hand...... appropriate risk mitigation measures through the food chain, not least in the domestic kitchen. However, factors related to consumer psychology may increase the risks to consumers as they produce barriers to self-protective behaviours (Frewer & Fischer, in press; Worsfold & Griffith, 1997). In contrast...

Food safety and consumer behaviour

DEFF Research Database (Denmark)

Frewer, Lynn; Fischer, Arnout; Scholderer, Joachim

2005-01-01

Food safety is a priority for many consumers, and there is an expectation throughout society that the food supplied for human consumption is safe and nutritious to eat. Understanding technical risk estimates alone, however, will not explain the risk-related behaviours of consumers. On the one hand......, consumers may not pay enough attention to some types of food safety issue, such as the risk of food poisoning from microbial contamination, which may at best be debilitating, and at worst fatal (Center for Disease Control and Prevention, 1994). This risk is certainly largely avoidable through taking...... appropriate risk mitigation measures through the food chain, not least in the domestic kitchen. However, factors related to consumer psychology may increase the risks to consumers as they produce barriers to self-protective behaviours (Frewer & Fischer, in press; Worsfold & Griffith, 1997). In contrast...

Simulation of the shopping center 'Zona I' evacuation

Directory of Open Access Journals (Sweden)

Jevtić Radoje B.

2014-01-01

Full Text Available One of the most important and the most complex tasks in human protection and human safety in objects is the projecting of the object evacuation. There are many factors that could effect on the opportune living of object such as object assignment, arrangement of rooms, arrangement of furniture, arrangement of exits, occupant speed and many other that human lives and material properties depend on. This is very important for objects with great number of humans, such as high residential objects, shopping centers, schools, hospitals etc. This paper has written to show the possible evacuation situations and calculate minimal time for evacuation in case of the shopping center 'Zona I' in Niš.

NASA-Langley Research Center's Aircraft Condition Analysis and Management System Implementation

Science.gov (United States)

Frye, Mark W.; Bailey, Roger M.; Jessup, Artie D.

2004-01-01

This document describes the hardware implementation design and architecture of Aeronautical Radio Incorporated (ARINC)'s Aircraft Condition Analysis and Management System (ACAMS), which was developed at NASA-Langley Research Center (LaRC) for use in its Airborne Research Integrated Experiments System (ARIES) Laboratory. This activity is part of NASA's Aviation Safety Program (AvSP), the Single Aircraft Accident Prevention (SAAP) project to develop safety-enabling technologies for aircraft and airborne systems. The fundamental intent of these technologies is to allow timely intervention or remediation to improve unsafe conditions before they become life threatening.

Obtaining laser safety at a synchrotron radiation user facility: The Advanced Light Source

International Nuclear Information System (INIS)

Barat, K.

1996-01-01

The Advanced Light Source (ALS) is a US national facility for scientific research and development located at the Lawrence Berkeley National Laboratory in California. The ALS delivers the world's brightest synchrotron radiation in the far ultraviolet and soft X-ray regions of the spectrum. As a user facility it is available to researchers from industry, academia, and laboratories from around the world. Subsequently, a wide range of safety concerns become involved. This article relates not only to synchrotron facilities but to any user facility. A growing number of US centers are attracting organizations and individuals to use the equipment on site, for a fee. This includes synchrotron radiation and/or free electron facilities, specialty research centers, and laser job shops. Personnel coming to such a facility bring with them a broad spectrum of safety cultures. Upon entering, the guests must accommodate to the host facility safety procedures. This article describes a successful method to deal with that responsibility

Large-scale fuel cycle centers

International Nuclear Information System (INIS)

Smiley, S.H.; Black, K.M.

1977-01-01

The United States Nuclear Regulatory Commission (NRC) has considered the nuclear energy center concept for fuel cycle plants in the Nuclear Energy Center Site Survey - 1975 (NECSS-75) -- an important study mandated by the U.S. Congress in the Energy Reorganization Act of 1974 which created the NRC. For the study, NRC defined fuel cycle centers to consist of fuel reprocessing and mixed oxide fuel fabrication plants, and optional high-level waste and transuranic waste management facilities. A range of fuel cycle center sizes corresponded to the fuel throughput of power plants with a total capacity of 50,000 - 300,000 MWe. The types of fuel cycle facilities located at the fuel cycle center permit the assessment of the role of fuel cycle centers in enhancing safeguarding of strategic special nuclear materials -- plutonium and mixed oxides. Siting of fuel cycle centers presents a considerably smaller problem than the siting of reactors. A single reprocessing plant of the scale projected for use in the United States (1500-2000 MT/yr) can reprocess the fuel from reactors producing 50,000-65,000 MWe. Only two or three fuel cycle centers of the upper limit size considered in the NECSS-75 would be required in the United States by the year 2000 . The NECSS-75 fuel cycle center evaluations showed that large scale fuel cycle centers present no real technical difficulties in siting from a radiological effluent and safety standpoint. Some construction economies may be attainable with fuel cycle centers; such centers offer opportunities for improved waste management systems. Combined centers consisting of reactors and fuel reprocessing and mixed oxide fuel fabrication plants were also studied in the NECSS. Such centers can eliminate not only shipment of plutonium, but also mixed oxide fuel. Increased fuel cycle costs result from implementation of combined centers unless the fuel reprocessing plants are commercial-sized. Development of plutonium-burning reactors could reduce any

MP-Division health and safety reference handbook

International Nuclear Information System (INIS)

Putnam, T.M.

1987-09-01

This report presents the objectives, organization, policies, and essential rules and procedures that have been adopted by MP Division and that form the basis of the Health and Safety Program of the Clinton P. Anderson Meson Physics Facility (LAMPF). The facility includes the beam-delivery systems for the Los Alamos Neutron Scattering Center and the Weapons Neutron Research Facility (LANSCE/WNR). The program is designed not only to assure the health and safety of all personnel, including users, in their work at LAMPF, and of MP-Division staff in their work on the LANSCE/WNR beam lines, but also to protect the facility (buildings and equipment) and the environment. 33 refs., 18 figs., 2 tabs

[Does simulator-based team training improve patient safety?].

Science.gov (United States)

Trentzsch, H; Urban, B; Sandmeyer, B; Hammer, T; Strohm, P C; Lazarovici, M

2013-10-01

Patient safety became paramount in medicine as well as in emergency medicine after it was recognized that preventable, adverse events significantly contributed to morbidity and mortality during hospital stay. The underlying errors cannot usually be explained by medical technical inadequacies only but are more due to difficulties in the transition of theoretical knowledge into tasks under the conditions of clinical reality. Crew Resource Management and Human Factors which determine safety and efficiency of humans in complex situations are suitable to control such sources of error. Simulation significantly improved safety in high reliability organizations, such as the aerospace industry.Thus, simulator-based team training has also been proposed for medical areas. As such training is consuming in cost, time and human resources, the question of the cost-benefit ratio obviously arises. This review outlines the effects of simulator-based team training on patient safety. Such course formats are not only capable of creating awareness and improvements in safety culture but also improve technical team performance and emphasize team performance as a clinical competence. A few studies even indicated improvement of patient-centered outcome, such as a reduced rate of adverse events but further studies are required in this respect. In summary, simulator-based team training should be accepted as a suitable strategy to improve patient safety.

Safety implications of diesel generator aging management

International Nuclear Information System (INIS)

Hoopingarner, K.R.

1989-01-01

Significant safety improvements can be achieved in diesel-generator management related to aging, testing, and other important regulatory concerns. This paper reports on the progress of aging research related to nuclear service diesel generators, which developed data and information supporting the recommended safety improvements. The key to diesel-generator safety improvements is the development of a new balanced approach where testing, inspections, monitoring and trending, training, and maintenance all have appropriate importance. Safety improvement is projected in a management program that concurrently achieves three goals: first, the reduction of the fast-start stressor by regulatory and utility actions; second, the establishment of more appropriate testing and trending procedures; third, the adoption and use of reliability-centered maintenance activities. This paper describes the recommended safety improvements and the positive role of utility management in the process and outlines a new recommended regulatory approach. Diesel generator aging and wear is the subject of research sponsored by the Nuclear Plant Aging Research (NPAR) Program under the US Nuclear Regulatory Commission (NRC). Office of Nuclear Regulatory Research. The research was conducted by Pacific Northwest Laboratory (PNL), which is operated for the US Department of Energy by Battelle Memorial Institute. 4 refs., 1 fig., 1 tab

Engineering and Safety Partnership Enhances Safety of the Space Shuttle Program (SSP)

Science.gov (United States)

Duarte, Alberto

2007-01-01

Project Management must use the risk assessment documents (RADs) as tools to support their decision making process. Therefore, these documents have to be initiated, developed, and evolved parallel to the life of the project. Technical preparation and safety compliance of these documents require a great deal of resources. Updating these documents after-the-fact not only requires substantial increase in resources - Project Cost -, but this task is also not useful and perhaps an unnecessary expense. Hazard Reports (HRs), Failure Modes and Effects Analysis (FMEAs), Critical Item Lists (CILs), Risk Management process are, among others, within this category. A positive action resulting from a strong partnership between interested parties is one way to get these documents and related processes and requirements, released and updated in useful time. The Space Shuttle Program (SSP) at the Marshall Space Flight Center has implemented a process which is having positive results and gaining acceptance within the Agency. A hybrid Panel, with equal interest and responsibilities for the two larger organizations, Safety and Engineering, is the focal point of this process. Called the Marshall Safety and Engineering Review Panel (MSERP), its charter (Space Shuttle Program Directive 110 F, April 15, 2005), and its Operating Control Plan emphasizes the technical and safety responsibilities over the program risk documents: HRs; FMEA/CILs; Engineering Changes; anomalies/problem resolutions and corrective action implementations, and trend analysis. The MSERP has undertaken its responsibilities with objectivity, assertiveness, dedication, has operated with focus, and has shown significant results and promising perspectives. The MSERP has been deeply involved in propulsion systems and integration, real time technical issues and other relevant reviews, since its conception. These activities have transformed the propulsion MSERP in a truly participative and value added panel, making a

On the status of the EFR Euro-Breeder and its passive safety features

International Nuclear Information System (INIS)

Marth, W.

1992-01-01

The Project of the EFR, the European Fast Reactor, is characterized by close European cooperation among power utilities, plant vendors, and research centers. In the present phase up until 1993 a consistent design of the nuclear part of the plant is being elaborated with the inclusion of a site-independent safety report. The most important design features, especially those in the field of passive safety, must be backed up by reliable R and D findings. These findings will enable the ad hoc Safety Club, a body of European safety experts, to pass its vote on the general licensability of the plant concept. (orig.) [de

Patient safety: Safety culture and patient safety ethics

DEFF Research Database (Denmark)

Madsen, Marlene Dyrløv

2006-01-01

,demonstrating significant, consistent and sometimes large differences in terms of safety culture factors across the units participating in the survey. Paper 5 is the results of a study of the relation between safety culture, occupational health andpatient safety using a safety culture questionnaire survey......Patient safety - the prevention of medical error and adverse events - and the initiative of developing safety cultures to assure patients from harm have become one of the central concerns in quality improvement in healthcare both nationally andinternationally. This subject raises numerous...... challenging issues of systemic, organisational, cultural and ethical relevance, which this dissertation seeks to address through the application of different disciplinary approaches. The main focus of researchis safety culture; through empirical and theoretical studies to comprehend the phenomenon, address...

Assessment of safety culture in the Iranian nuclear installations

International Nuclear Information System (INIS)

Farahani, H.F.; Davilu, H.; Sepanloo, K.

2005-01-01

The deficient safety culture (S.C) is the center of safety issues of nuclear industry. To benefit from the advantages of nuclear technology and considering the fact of potential hazards of accidents in nuclear installations it is essential to view safety as the highest priority. S.C is an amalgamation of values, standards, morals and norms of acceptable behavior. Organizations having effective S.C show constant commitment to safety as a top level priority. Furthermore, the personnel of a nuclear facility shall recognize the safety significance of their tasks. Many people even those who work in the field of safety do not have a correct understanding of what S.C looks like in practical sense. In this study, by conducting a survey according to IAEA-TECDOC-1329 in some nuclear facilities, the S.C within the Iranian nuclear facilities is assessed. The human and organizational factors in Tehran Research Reactor are evaluated using a questionnaire method with active participation of the reactor operators. The results sho w that the operators are pretty aware of the subject. Also it has been identified some areas of improvement. (authors)

Lessons learned from process incident databases and the process safety incident database (PSID) approach sponsored by the Center for Chemical Process Safety

International Nuclear Information System (INIS)

Sepeda, Adrian L.

2006-01-01

Learning from the experiences of others has long been recognized as a valued and relatively painless process. In the world of process safety, this learning method is an essential tool since industry has neither the time and resources nor the willingness to experience an incident before taking corrective or preventative steps. This paper examines the need for and value of process safety incident databases that collect incidents of high learning value and structure them so that needed information can be easily and quickly extracted. It also explores how they might be used to prevent incidents by increasing awareness and by being a tool for conducting PHAs and incident investigations. The paper then discusses how the CCPS PSID meets those requirements, how PSID is structured and managed, and its attributes and features

NASA Goddard Space Flight Center Supply Chain Management Program

Science.gov (United States)

Kelly, Michael P.

2011-01-01

This slide presentation reviews the working of the Supplier Assessment Program at NASA Goddard Space Flight Center. The program supports many GSFC projects to ensure suppliers are aware of and are following the contractual requirements, to provide an independent assessment of the suppliers' processes, and provide suppliers' safety and mission assurance organizations information to make the changes within their organization.

Changing the Safety and Mission Assurance (S and MA) Paradigm

Science.gov (United States)

Malone, Roy W.; Safie, Fayssal M.

2010-01-01

This slide presentation reviews the change in the work and impact of the Safety and Mission Assurance directorate at Marshall Space Flight Center. It reviews the background and the reasons given for a strong Safety & Mission Assurance presence in all planning for space flight. This was pointed out by the Rogers Commission Report after the Space Challenger accident, by the Columbia Accident Investigation Board (CAIB) and by a 2006 NASA Exploration Safety Study (NESS) Team. The overall objective of the work in this area was to improve and maintain S&MA expertise and skills. Training for this work was improved and the S&MA organization was reorganized. This has resulted in a paradigm shift for NASA's safety efforts, which is described. The presentation then reviews the impact of the new S&MA work in the Ares I design and development.

The CABRI facility: Implementation of a pressurized water loop and related safety review

International Nuclear Information System (INIS)

Cabrillat, J.C.; Maegey, M.; Bourguignon, D.; Miachon, G.; Forestier, F.; Coulon, J.P.; Faury, M.

2003-01-01

The CABRI reactor operated by CEA at the CADARACHE Nuclear Center in France provided the condition for safety studies on nuclear fuel. Initially designed to support investigations on Fast Reactor fuel, large modifications are underway to provide representative conditions for studies on Light Water Fuel types. A general overview of these modifications, the related safety review and supporting studies are described in the paper. (author)

Prospective, Randomized, Multi-centered Clinical Trial Assessing Safety and Efficacy of a Synthetic Cartilage Implant Versus First Metatarsophalangeal Arthrodesis in Advanced Hallux Rigidus.

Science.gov (United States)

Baumhauer, Judith F; Singh, Dishan; Glazebrook, Mark; Blundell, Chris; De Vries, Gwyneth; Le, Ian L D; Nielsen, Dominic; Pedersen, M Elizabeth; Sakellariou, Anthony; Solan, Matthew; Wansbrough, Guy; Younger, Alastair S E; Daniels, Timothy

2016-05-01

Although a variety of great toe implants have been tried in an attempt to maintain toe motion, the majority have failed with loosening, malalignment/dislocation, implant fragmentation and bone loss. In these cases, salvage to arthrodesis is more complicated and results in shortening of the ray or requires structural bone graft to reestablish length. This prospective study compared the efficacy and safety of this small (8/10 mm) hydrogel implant to the gold standard of a great toe arthrodesis for advanced-stage hallux rigidus. In this prospective, randomized non-inferiority study, patients from 12 centers in Canada and the United Kingdom were randomized (2:1) to a synthetic cartilage implant or first metatarsophalangeal (MTP) joint arthrodesis. VAS pain scale, validated outcome measures (Foot and Ankle Ability Measure [FAAM] sport scale), great toe active dorsiflexion motion, secondary procedures, radiographic assessment, and safety parameters were evaluated. Analysis was performed using intent-to-treat (ITT) and modified ITT (mITT) methodology. The primary endpoint for the study consisted of a single composite endpoint using the 3 primary study outcomes (pain, function, and safety). The individual subject's outcome was considered a success if all of the following criteria were met: (1) improvement (decrease) from baseline in VAS pain of ≥30% at 12 months; (2) maintenance of function from baseline in FAAM sports subscore at 12 months; and (3) absence of major safety events at 2 years. The proportion of successes in each group was determined and 1-sided 95% confidence interval for the difference between treatment groups was calculated. Noninferiority of the implant to arthrodesis was considered statistically significant if the 1-sided 95% lower confidence interval was greater than the equivalence limit (sports and activity of daily living subscores improved significantly at 12 and 24 months in both groups. First MTP active dorsiflexion motion improvement was 6

Nuclear Fuel Recovery and Recycling Center. License application, PSAR, volume 1

International Nuclear Information System (INIS)

1976-01-01

A summary of the location and major design features of the proposed Nuclear Fuel Recovery and Recycling Center is presented. The safety aspects of the proposed facilities and operations are summarized, taking into account possible normal and abnormal operating and environmental conditions. A chapter on site characteristics is included

AMDIS Case Conference: Intrusive Medication Safety Alerts.

Science.gov (United States)

Graham, J; Levick, D; Schreiber, R

2010-01-01

Clinical decision support that provides enhanced patient safety at the point of care frequently encounters significant pushback from clinicians who find the process intrusive or time-consuming. We present a hypothetical medical center's dilemma about its allergy alerting system and discuss similar problems faced by real hospitals. We then share some lessons learned and best practices for institutions who wish to implement these tools themselves.

EC6 safety design improvements

Energy Technology Data Exchange (ETDEWEB)

Yu, S.; Lee, A.G.; Soulard, M. [Candu Energy Inc., Mississauga, ON (Canada)

2014-07-01

The Enhanced CANDU 6 (EC6) builds on the proven high performance design such as the Qinshan CANDU 6 reactor, and has made improvements to safety, operational performance, and has incorporated extensive operational feedback. Completion of all three phases of the pre-licensing design review by the Canadian Regulator - the Canadian Nuclear Safety Commission has provided a higher level of assurance that the EC6 reference design has taken modern regulatory requirements and expectations into account and further confirmed that there are no fundamental barriers to licensing the EC6 design in Canada. The EC6 design is based on the defence-in-depth principles in INSAG-10 and provides further safety features that address the lessons learned from Fukushima. With these safety features, the EC6 design has strengthened accident prevention as the first priority in the defence-in-depth strategy, as outlined in INSAG-10. As well, the EC6 design has incorporated further mitigation measures to provide additional protection of the public and the environment if the preventive measures fail. The EC6 design has an appropriate combination of inherent, passive safety characteristics, engineered features and administrative safety measures to effectively prevent and mitigate severe accident progressions. A strong contributor to the robustness and redundancy of CANDU design is the two-group separation philosophy. This ensures a high degree of independence between safety systems as well as physical separation and functional independence in how fundamental safety functions are provided. This paper will describe the following safety features based on the application of defence-in-depth and design approach to prevent beyond design basis events progressing to severe accidents and to mitigate the consequences if it occurs: Improved steam generator heat sink via a more reliable emergency heat removal system; Increased time before manual field actions are required via enhanced capacity of

FMCSA safety program effectiveness measurement : Roadside Intervention Effectiveness Model, fiscal year 2012.

Science.gov (United States)

2016-02-01

The Federal Motor Carrier Safety Administration (FMCSA), in cooperation with the John A. Volpe National : Transportation Systems Center, has developed an analytic model to measure the effectiveness of roadside : inspections and traffic enforcements i...

Pacific Northwest Laboratory annual report for 1989 to the Assistant Secretary for Environment, Safety, and Health - Part 5: Environment, Safety, Health, and Quality Assurance

Energy Technology Data Exchange (ETDEWEB)

Faust, L.G.; Doctor, P.G.; Selby, J.M.

1990-04-01

Part 5 of the 1989 Annual Report to the US Department of Energy's Assistant Secretary for Environment, Safety, and Health presents Pacific Northwest Laboratory's progress on work performed for the Office of Environmental Guidance and Compliance, the Office of Environmental Audit, the Office of National Environmental Policy Act Project Assistance, the Office of Nuclear Safety, the Office of Safety Compliance, and the Office of Policy and Standards. For each project, as identified by the Field Work Proposal, there is an article describing progress made during fiscal year 1989. Authors of these articles represent a broad spectrum of capabilities derived from five of the seven technical centers of the Laboratory, reflecting the interdisciplinary nature of the work. 35 refs., 1 fig.

Handbook of safety assessment of nanomaterials from toxicological testing to personalized medicine

CERN Document Server

Fadeel, Bengt

2014-01-01

"The Handbook of Safety Assessment of Nanomaterials: From Toxicological Testing to Personalized Medicine provides a comprehensive overview of the state of the art of nanotoxicology and is a unique resource that fills up many knowledge gaps in the toxicity issue of nanomaterials in medical applications. The book is distinguished by up-to-date insights into creating a science-based framework for safety assessment of nanomedicines." -Prof. Yuliang Zhao, National Center for Nanosciences and Technology, China.

Evaluation of the safety culture in the regulatory activity in Camaguey province

International Nuclear Information System (INIS)

Naranjo Lopez, A.M.; Barreras Caballero, A.; Damera Martinez, A.

1999-01-01

Previous studied accomplished in the country have permitted to evaluate the activity of the regulatory body in nuclear safety matter in part of the national territory. These studies did not encompass the Camaguey province. In the work are shown the results of the study in this part of the territory, accomplished as of the survey elaborated by the National Nuclear Safety Center using guides it ASCOT and other documents of the IAEA

Artificial Neural Network Test Support Development for the Space Shuttle PRCS Thrusters

Science.gov (United States)

Lehr, Mark E.

2005-01-01

A significant anomaly, Fuel Valve Pilot Seal Extrusion, is affecting the Shuttle Primary Reaction Control System (PRCS) Thrusters, and has caused 79 to fail. To help address this problem, a Shuttle PRCS Thruster Process Evaluation Team (TPET) was formed. The White Sands Test Facility (WSTF) and Boeing members of the TPET have identified many discrete valve current trace characteristics that are predictive of the problem. However, these are difficult and time consuming to identify and trend by manual analysis. Based on this exhaustive analysis over months, 22 thrusters previously delivered by the Depot were identified as high risk for flight failures. Although these had only recently been installed, they had to be removed from Shuttles OV103 and OV104 for reprocessing, by directive of the Shuttle Project Office. The resulting impact of the thruster removal, replacement, and valve replacement was significant (months of work and hundreds of thousands of dollars). Much of this could have been saved had the proposed Neural Network (NN) tool described in this paper been in place. In addition to the significant benefits to the Shuttle indicated above, the development and implementation of this type of testing will be the genesis for potential Quality improvements across many areas of WSTF test data analysis and will be shared with other NASA centers. Future tests can be designed to incorporate engineering experience via Artificial Neural Nets (ANN) into depot level acceptance of hardware. Additionally, results were shared with a NASA Engineering and Safety Center (NESC) Super Problem Response Team (SPRT). There was extensive interest voiced among many different personnel from several centers. There are potential spin-offs of this effort that can be directly applied to other data acquisition systems as well as vehicle health management for current and future flight vehicles.

Evolution of International Space Station Program Safety Review Processes and Tools

Science.gov (United States)

Ratterman, Christian D.; Green, Collin; Guibert, Matt R.; McCracken, Kristle I.; Sang, Anthony C.; Sharpe, Matthew D.; Tollinger, Irene V.

2013-01-01

The International Space Station Program at NASA is constantly seeking to improve the processes and systems that support safe space operations. To that end, the ISS Program decided to upgrade their Safety and Hazard data systems with 3 goals: make safety and hazard data more accessible; better support the interconnection of different types of safety data; and increase the efficiency (and compliance) of safety-related processes. These goals are accomplished by moving data into a web-based structured data system that includes strong process support and supports integration with other information systems. Along with the data systems, ISS is evolving its submission requirements and safety process requirements to support the improved model. In contrast to existing operations (where paper processes and electronic file repositories are used for safety data management) the web-based solution provides the program with dramatically faster access to records, the ability to search for and reference specific data within records, reduced workload for hazard updates and approval, and process support including digital signatures and controlled record workflow. In addition, integration with other key data systems provides assistance with assessments of flight readiness, more efficient review and approval of operational controls and better tracking of international safety certifications. This approach will also provide new opportunities to streamline the sharing of data with ISS international partners while maintaining compliance with applicable laws and respecting restrictions on proprietary data. One goal of this paper is to outline the approach taken by the ISS Progrm to determine requirements for the new system and to devise a practical and efficient implementation strategy. From conception through implementation, ISS and NASA partners utilized a user-centered software development approach focused on user research and iterative design methods. The user-centered approach used on

Relationship between knowledge, attitude, behavior, and self-efficacy on the radiation safety management of radiation workers in medical institutions

International Nuclear Information System (INIS)

Han, Eun Ok

2007-01-01

Radiation safety managements in medical institutions are needed to protect certain radiation damages as a part of National Coalition. This study investigates the characteristics of self-efficacy that become the major factor on the knowledge, attitude, and behavior on the radiation safety management of radiation workers as an approach of educational aspects and analyzes the relationship between such factors to provide basic materials for improving the activity level of radiation safety managements. In order to implement the goal of this study, a survey was performed for 1,200 workers who were engaged in radiation treatments in medical centers, such as general hospital, university hospital, private hospital, and public health center for 42 days from July 23, 2006. Then, the results of the analysis can be summarized as follows: 1. Average scores on knowledge, attitude, and behavior in the radiation safety management were presented as 75.76±11.20, 90.55±8.59, 80.58±11.70, respectively. Also, the average score of self-efficacy was recorded as 73.55±9.82. 2. Knowledge levels in the radiation safety management showed significant differences according to the sex, age, marriage, education, and experience. Also, males of married, older, highly educated, and largely experienced represented high knowledge levels. Attitude levels in the radiation safety management showed certain significant differences according to the type of medical centers in which private hospitals showed a relatively low level compared to that of high levels in university hospitals. Behavior levels in the radiation safety management also represented significant differences according to the age, marriage, education, experience, and types of medical centers. Factors in married, general hospital, older, highly educated, and largely experienced showed high behavior levels. In addition, the self-efficacy showed certain differences according to the marriage and types of medical centers. Factors in married

Relationship between knowledge, attitude, behavior, and self-efficacy on the radiation safety management of radiation workers in medical institutions

Energy Technology Data Exchange (ETDEWEB)

Han, Eun Ok [Daegu Health College, Daegu (Korea, Republic of)

2007-06-15

Radiation safety managements in medical institutions are needed to protect certain radiation damages as a part of National Coalition. This study investigates the characteristics of self-efficacy that become the major factor on the knowledge, attitude, and behavior on the radiation safety management of radiation workers as an approach of educational aspects and analyzes the relationship between such factors to provide basic materials for improving the activity level of radiation safety managements. In order to implement the goal of this study, a survey was performed for 1,200 workers who were engaged in radiation treatments in medical centers, such as general hospital, university hospital, private hospital, and public health center for 42 days from July 23, 2006. Then, the results of the analysis can be summarized as follows: 1. Average scores on knowledge, attitude, and behavior in the radiation safety management were presented as 75.76{+-}11.20, 90.55{+-}8.59, 80.58{+-}11.70, respectively. Also, the average score of self-efficacy was recorded as 73.55{+-}9.82. 2. Knowledge levels in the radiation safety management showed significant differences according to the sex, age, marriage, education, and experience. Also, males of married, older, highly educated, and largely experienced represented high knowledge levels. Attitude levels in the radiation safety management showed certain significant differences according to the type of medical centers in which private hospitals showed a relatively low level compared to that of high levels in university hospitals. Behavior levels in the radiation safety management also represented significant differences according to the age, marriage, education, experience, and types of medical centers. Factors in married, general hospital, older, highly educated, and largely experienced showed high behavior levels. In addition, the self-efficacy showed certain differences according to the marriage and types of medical centers. Factors in

[Learning from errors: applying aviation safety concepts to medicine].

Science.gov (United States)

Sommer, K-J

2012-11-01

Health care safety levels range below other complex industries. Civil aviation has throughout its history developed methods and concepts that have made the airplane into one of the safest means of mass transport. Key elements are accident investigations that focus on cause instead of blame, human-centered design of machinery and processes, continuous training of all personnel and a shared safety culture. These methods and concepts can basically be applied to medicine which has successfully been achieved in certain areas, however, a comprehensive implementation remains to be completed. This applies particularly to including the topic of safety into relevant curricula. Physicians are obliged by the oath"primum nil nocere" to act, but economic as well as political pressure will eventually confine professional freedom if initiative is not taken soon.

Proceedings of KURRI symposium on criticality safety

International Nuclear Information System (INIS)

Nishina, Kojiro; Kanda, Keiji

1984-01-01

On August 8, 1984, at the Reactor Application Center of the Research Reactor Institute, Kyoto University, the symposium on criticality safety was held, and 81 participants from various fields of reactor physics, nuclear fuel cycle engineering, reactor chemistry, nuclear chemistry, health physics and so on discussed the problem. The gists of the presentation are collected in this report. The contents are the techniques of evaluating criticality safety in respective fuel facilities, the system of control and its concept, the course and plan of the research on criticality safety in Japan and foreign countries, the techniques of determining multiplication factor and so on, and the review of present status, the pointing-out of problems and the report of new techniques were made. The measures coping with criticality safety have been mostly to meet urgent demand, but its fundamental examination and long term research should be carried out. This symposium was planned as the preparation for such research project, and favorable comment was given by the participants. In the next symposium, it is considered better to limit the themes and to allot more time to respective lectures. (Kako, I.)

FMCSA safety program effectiveness measurement : Roadside Intervention Effectiveness Model, fiscal year 2010.

Science.gov (United States)

2014-11-01

The Federal Motor Carrier Safety Administration (FMCSA), in cooperation with the John A. Volpe National Transportation Systems Center, has developed an analytic model to measure the effectiveness of roadside inspections and traffic enforcements in te...

FMCSA safety program effectiveness measurement : roadside intervention effectiveness model fiscal year 2011.

Science.gov (United States)

2015-06-01

The Federal Motor Carrier Safety Administration (FMCSA), in cooperation with the John A. Volpe National Transportation Systems Center, has developed an analytic model to measure the effectiveness of roadside inspections and traffic enforcements in te...

FMCSA safety program effectiveness measurement : roadside intervention effectiveness model, fiscal year 2013.

Science.gov (United States)

2017-08-01

The Federal Motor Carrier Safety Administration (FMCSA), in cooperation with the John A. Volpe National Transportation Systems Center, has developed an analytic model to measure the effectiveness of roadside inspections and traffic enforcements in te...

Annual report 2007 Manche center; Rapport annuel 2007 Centre Manche

Energy Technology Data Exchange (ETDEWEB)

NONE

2007-07-01

The National Agency for the Radioactive Wastes Management (ANDRA), is public company, with an industrial and commercial status. This document presents the activities of the year 2007 for the Manche center. It details the installations, the safety and radiation protection policy, the main events of the tear, the radioactive wastes management and the public information mission. (A.L.B.)

Annual report 2007 Aube center; Rapport annuel 2007 Centre Aube

Energy Technology Data Exchange (ETDEWEB)

NONE

2007-07-01

The National Agency for the Radioactive Wastes Management (ANDRA), is public company, with an industrial and commercial status. This document presents the activities of the year 2007 for the Aube center. It details the installations, the safety and radiation protection policy, the main events of the tear, the radioactive wastes management and the public information mission. (A.L.B.)

Semi-annual report of Nuclear Technology and Development Center (CDTN) - July to December 1988

International Nuclear Information System (INIS)

1989-01-01

The main activities developed by the several divisions of Nuclear Technology Development Center (CDTN) are described, including areas of reactor tecnologies, fuel cycle, materials and component, nuclear safety and tecnical substructure. (C.G.C.) [pt

Radiation safety training for industrial irradiators: What are we trying to accomplish?

International Nuclear Information System (INIS)

Smith, M.A.

1998-01-01

Radiation safety training at an industrial irradiator facility takes a different approach than the traditional methods and topics used at other facilities. Where the more routine industrial radiation users focus on standard training topics of contamination control, area surveys, and the traditional dogma of time, distance, and shielding, radiation safety in an industrial irradiation facility must be centered on preventing accidents. Because the primary methods for accomplishing that goal are engineering approaches such as safety system interlocks, training provided to facility personnel should address system operation and emergency actions. This presents challenges in delivering radiation safety training to an audience of varied educational and technical background where little to no commercially available training material specific to this type of operation exists

Catching crime: detection of public safety incidents using social media

CSIR Research Space (South Africa)

Marivate, Vukosi

2016-11-01

Full Text Available The increasing prevalence of Social Media platform use has brought with it an explosion of new user generated public data. This data is centered around many, diverse topics. One theme of interest is how one can tap into the public safety and crime...

The development of two-phase flow instrumentation at PNC O-arai Engineering Center

International Nuclear Information System (INIS)

Obata, T.; Kobori, T.; Hayamizu, Y.

1975-10-01

This paper reviews development works on the two-phase flow instrumentation carried out at PNC Oarai Engineering Center for FUGEN safety test. The paper describes heater surface temperature measurement, four types of void meters and two steam quality meters. (auth.)

In-Space Manufacturing at NASA Marshall Space Flight Center: Enabling Technologies for Exploration

Science.gov (United States)

Bean, Quincy; Johnston, Mallory; Ordonez, Erick; Ryan, Rick; Prater, Tracie; Werkeiser, Niki

2015-01-01

NASA Marshall Space Flight Center is currently engaged in a number of in-space manufacturing(ISM)activities that have the potential to reduce launch costs, enhance crew safety, and provide the capabilities needed to undertake long duration spaceflight safely and sustainably.

SRTC criticality safety technical review: Nuclear Criticality Safety Evaluation 93-04 enriched uranium receipt

International Nuclear Information System (INIS)

Rathbun, R.

1993-01-01

Review of NMP-NCS-930087, open-quotes Nuclear Criticality Safety Evaluation 93-04 Enriched Uranium Receipt (U), July 30, 1993, close quotes was requested of SRTC (Savannah River Technology Center) Applied Physics Group. The NCSE is a criticality assessment to determine the mass limit for Engineered Low Level Trench (ELLT) waste uranium burial. The intent is to bury uranium in pits that would be separated by a specified amount of undisturbed soil. The scope of the technical review, documented in this report, consisted of (1) an independent check of the methods and models employed, (2) independent HRXN/KENO-V.a calculations of alternate configurations, (3) application of ANSI/ANS 8.1, and (4) verification of WSRC Nuclear Criticality Safety Manual procedures. The NCSE under review concludes that a 500 gram limit per burial position is acceptable to ensure the burial site remains in a critically safe configuration for all normal and single credible abnormal conditions. This reviewer agrees with that conclusion

Workers safety in public psychiatric services: problems, laws and protections.

Science.gov (United States)

Carabellese, F; Urbano, M; Coluccia, A; Gualtieri, G

2017-01-01

The dramatic case of murder of a psychiatrist during her service in her public office (Centro di Salute Mentale of Bari-Libertà) has led the authors to reflect on the safety of workplaces, in detail of public psychiatric services. It is in the light of current legislation, represented by the Legislative Decree of April 9th, 2008 no. 81, which states the implementing rules of Law 123/2007. In particular, the Authors analyzed the criticalities of the application of this Law, with the aim of safeguarding the health and safety of the workers in all psychiatric services (nursing departments, outpatient clinics, community centers, day care centers, etc.). The Authors suggest the need to set up an articulated specific organizational system of risk assessment of psychiatric services, that can prevent and protect the workers from identified risks, and finally to ensure their active participation in prevention and protection activities, in absence of which specific profiles of responsibility would be opened up to the employers.

The Armstrong Institute: An Academic Institute for Patient Safety and Quality Improvement, Research, Training, and Practice.

Science.gov (United States)

Pronovost, Peter J; Holzmueller, Christine G; Molello, Nancy E; Paine, Lori; Winner, Laura; Marsteller, Jill A; Berenholtz, Sean M; Aboumatar, Hanan J; Demski, Renee; Armstrong, C Michael

2015-10-01

Academic medical centers (AMCs) could advance the science of health care delivery, improve patient safety and quality improvement, and enhance value, but many centers have fragmented efforts with little accountability. Johns Hopkins Medicine, the AMC under which the Johns Hopkins University School of Medicine and the Johns Hopkins Health System are organized, experienced similar challenges, with operational patient safety and quality leadership separate from safety and quality-related research efforts. To unite efforts and establish accountability, the Armstrong Institute for Patient Safety and Quality was created in 2011.The authors describe the development, purpose, governance, function, and challenges of the institute to help other AMCs replicate it and accelerate safety and quality improvement. The purpose is to partner with patients, their loved ones, and all interested parties to end preventable harm, continuously improve patient outcomes and experience, and eliminate waste in health care. A governance structure was created, with care mapped into seven categories, to oversee the quality and safety of all patients treated at a Johns Hopkins Medicine entity. The governance has a Patient Safety and Quality Board Committee that sets strategic goals, and the institute communicates these goals throughout the health system and supports personnel in meeting these goals. The institute is organized into 13 functional councils reflecting their behaviors and purpose. The institute works daily to build the capacity of clinicians trained in safety and quality through established programs, advance improvement science, and implement and evaluate interventions to improve the quality of care and safety of patients.

Applying reliability centered maintenance analysis principles to inservice testing

International Nuclear Information System (INIS)

Flude, J.W.

1994-01-01

Federal regulations require nuclear power plants to use inservice test (IST) programs to ensure the operability of safety-related equipment. IST programs are based on American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code requirements. Many of these plants also use Reliability Centered Maintenance (RCM) to optimize system maintenance. ASME Code requirements are hard to change. The process for requesting authority to use an alternate strategy is long and expensive. The difficulties of obtaining this authority make the use of RCM method on safety-related systems not cost effective. An ASME research task force on Risk Based Inservice Testing is investigating changing the Code. The change will allow plants to apply RCM methods to the problem of maintenance strategy selection for safety-related systems. The research task force is working closely with the Codes and Standards sections to develop a process related to the RCM process. Some day plants will be able to use this process to develop more efficient and safer maintenance strategies

WE-G-BRA-01: Patient Safety and Treatment Quality Improvement Through Incident Learning: Experience of a Non-Academic Proton Therapy Center

Energy Technology Data Exchange (ETDEWEB)

Zheng, Y; Johnson, R; Zhao, L; Ramirez, E; Rana, S; Singh, H; Chacko, M [Procure Proton Therapy Center, Oklahoma City, OK (United States)

2015-06-15

Purpose: Incident learning has been proven to improve patient safety and treatment quality in conventional radiation therapy. However, its application in proton therapy has not been reported yet to our knowledge. In this study, we report our experience in developing and implementation of an in-house incident learning system. Methods: An incident learning system was developed based on published principles and tailored for our clinical practice and available resource about 18 months ago. The system includes four layers of error detection and report: 1) dosimetry peer review; 2) physicist plan quality assurance (QA); 3) treatment delivery issue on call and record; and 4) other incident report. The first two layers of QA and report were mandatory for each treatment plan through easy-to-use spreadsheets that are only accessible by the dosimetry and physicist departments. The treatment delivery issues were recorded case by case by the on call physicist. All other incidents were reported through an online incident report system, which can be anonymous. The incident report includes near misses on planning and delivery, process deviation, machine issues, work flow and documentation. Periodic incident reviews were performed. Results: In total, about 116 errors were reported through dosimetry review, 137 errors through plan QA, 83 treatment issues through physics on call record, and 30 through the online incident report. Only 8 incidents (2.2%) were considered to have a clinical impact to patients, and the rest of errors were either detected before reaching patients or had negligible dosimetric impact (<5% dose variance). Personnel training & process improvements were implemented upon periodic incident review. Conclusion: An incident learning system can be helpful in personnel training, error reduction, and patient safety and treatment quality improvement. The system needs to be catered for each clinic’s practice and available resources. Incident and knowledge sharing among

Safety and efficacy of thromboprophylaxis with fondaparinux in elderly acutely ill medical patients with renal impairment: a retrospective single center study

Directory of Open Access Journals (Sweden)

Federico Silvestri

2013-12-01

Full Text Available The majority of acutely ill medical patients are elderly with some degree of renal impairment. In this setting, venous thromboembolism (VTE is one of the leading causes of morbidity and mortality and, to reduce this risk, a correct thromboprophylaxis is needed. The aim of this single center retrospective study was to assess the safety and efficacy of fondaparinux in elderly acutely ill medical patients with renal impairment. All patients aged 60 years or over, bedridden for at least four days, with a creatinine clearance (CrCl of 50 mL/min or under, and who had received fondaparinux during hospitalization were evaluated and followed for up to 90 days after discharge. A total of 125 patients were evaluated (34.4% males; median age was 83.0 years. Median duration of thromboprophylaxis was 9.0 days. Forty-one (32.8% patients were treated with fondaparinux 1.5 mg daily, 84 (67.2% with 2.5 mg daily. Inappropriately high doses of fondaparinux were used in 77 patients with CrCl 20-50 mL/min, in 12 patients with CrCl below 20 mL/min, in 14 patients with prothrombin time (PT ratio over 1.2, in 8 patients with PT ratio over 1.5, and in 3 patients with thrombocytopenia. No episodes of VTE or of major bleeding were recorded while there were 6 episodes (2.4% of minor bleeding. Both dosages of fondaparinux showed similar safety and efficacy. Twenty-six patients (20.8% died; no cause of death was related to fondaparinux. In conclusion, in elderly acutely ill hospitalized medical patients with renal impairment, prophylaxis with fondaparinux 2.5 or 1.5 mg daily is safe and effective in preventing VTE without increasing bleeding risk.

WE-G-BRA-01: Patient Safety and Treatment Quality Improvement Through Incident Learning: Experience of a Non-Academic Proton Therapy Center

International Nuclear Information System (INIS)

Zheng, Y; Johnson, R; Zhao, L; Ramirez, E; Rana, S; Singh, H; Chacko, M

2015-01-01

Purpose: Incident learning has been proven to improve patient safety and treatment quality in conventional radiation therapy. However, its application in proton therapy has not been reported yet to our knowledge. In this study, we report our experience in developing and implementation of an in-house incident learning system. Methods: An incident learning system was developed based on published principles and tailored for our clinical practice and available resource about 18 months ago. The system includes four layers of error detection and report: 1) dosimetry peer review; 2) physicist plan quality assurance (QA); 3) treatment delivery issue on call and record; and 4) other incident report. The first two layers of QA and report were mandatory for each treatment plan through easy-to-use spreadsheets that are only accessible by the dosimetry and physicist departments. The treatment delivery issues were recorded case by case by the on call physicist. All other incidents were reported through an online incident report system, which can be anonymous. The incident report includes near misses on planning and delivery, process deviation, machine issues, work flow and documentation. Periodic incident reviews were performed. Results: In total, about 116 errors were reported through dosimetry review, 137 errors through plan QA, 83 treatment issues through physics on call record, and 30 through the online incident report. Only 8 incidents (2.2%) were considered to have a clinical impact to patients, and the rest of errors were either detected before reaching patients or had negligible dosimetric impact (<5% dose variance). Personnel training & process improvements were implemented upon periodic incident review. Conclusion: An incident learning system can be helpful in personnel training, error reduction, and patient safety and treatment quality improvement. The system needs to be catered for each clinic’s practice and available resources. Incident and knowledge sharing among

The French nuclear safety authority's experience with radioactive transport inspection

International Nuclear Information System (INIS)

Jacob, E.; Aguilar, J.

2004-01-01

About 300,000 radioactive material packages are transported annually in France. Most consist of radioisotopes for medical, pharmaceutical or industrial use. On the other hand, the nuclear industry deals with the transport of fuel cycle materials (uranium, fuel assemblies, etc.) and waste from power plants, reprocessing plants and research centers. France is also a transit country for shipments such as spent fuel packages from Switzerland or Germany, which are bound for Sellafield in Great Britain. The French nuclear safety authority (DGSNR: Directorate General for Nuclear Safety and Radioprotection) has been responsible since 1997 for the safety of radioactive material transport. This paper presents DGNSR's experience with transport inspection: a feedback of key points based on 300 inspections achieved during the past five years is given

Importance of the documentation of the manual of quality and procedures handbook in the nuclear technology center

International Nuclear Information System (INIS)

Domech More, J.; Bolanos Hernandez, R.; Quitero Rosello, R.; Fernandez Rondon, M.; Milian Lorenzo, D.; Rodriguez Gual, M.

1997-01-01

In the present work is presented the methodology used for the elaboration of manual of quality of the Nuclear Technology Center and the technical Procedures Handbook for the execution of Preliminary Safety report of the Juragua Nuclear Power Plant, as well as the importance that has this documentation for the work of the center

Security for safety critical space borne systems

Science.gov (United States)

Legrand, Sue

1987-01-01

The Space Station contains safety critical computer software components in systems that can affect life and vital property. These components require a multilevel secure system that provides dynamic access control of the data and processes involved. A study is under way to define requirements for a security model providing access control through level B3 of the Orange Book. The model will be prototyped at NASA-Johnson Space Center.

Development of reliability centered maintenance methods and tools

International Nuclear Information System (INIS)

Jacquot, J.P.; Dubreuil-Chambardel, A.; Lannoy, A.; Monnier, B.

1992-12-01

This paper recalls the development of the RCM (Reliability Centered Maintenance) approach in the nuclear industry and describes the trial study implemented by EDF in the context of the OMF (RCM) Project. The approach developed is currently being applied to about thirty systems (Industrial Project). On a parallel, R and D efforts are being maintained to improve the selectivity of the analysis methods. These methods use Probabilistic Safety Study models, thereby guaranteeing better selectivity in the identification of safety critical elements and enhancing consistency between Maintenance and Safety studies. They also offer more detailed analysis of operation feedback, invoking for example Bayes' methods combining expert judgement and feedback data. Finally, they propose a functional and material representation of the plant. This dual representation describes both the functions assured by maintenance provisions and the material elements required for their implementation. In the final chapter, the targets of the future OMF workstation are summarized and the latter's insertion in the EDF information system is briefly described. (authors). 5 figs., 2 tabs., 7 refs

Quantifying Pilot Contribution to Flight Safety During an In-Flight Airspeed Failure

Science.gov (United States)

Etherington, Timothy J.; Kramer, Lynda J.; Bailey, Randall E.; Kennedey, Kellie D.

2017-01-01

Accident statistics cite the flight crew as a causal factor in over 60% of large transport fatal accidents. Yet a well-trained and well-qualified crew is acknowledged as the critical center point of aircraft systems safety and an integral component of the entire commercial aviation system. A human-in-the-loop test was conducted using a Level D certified Boeing 737-800 simulator to evaluate the pilot's contribution to safety-of-flight during routine air carrier flight operations and in response to system failures. To quantify the human's contribution, crew complement was used as an independent variable in a between-subjects design. This paper details the crew's actions and responses while dealing with an in-flight airspeed failure. Accident statistics often cite flight crew error (Baker, 2001) as the primary contributor in accidents and incidents in transport category aircraft. However, the Air Line Pilots Association (2011) suggests "a well-trained and well-qualified pilot is acknowledged as the critical center point of the aircraft systems safety and an integral safety component of the entire commercial aviation system." This is generally acknowledged but cannot be verified because little or no quantitative data exists on how or how many accidents/incidents are averted by crew actions. Anecdotal evidence suggest crews handle failures on a daily basis and Aviation Safety Action Program data generally supports this assertion, even if the data is not released to the public. However without hard evidence, the contribution and means by which pilots achieve safety of flight is difficult to define. Thus, ways to improve the human ability to contribute or overcome deficiencies are ill-defined.

Automated system for the management of the radiological safety in a radiopharmaceutical and labelled compounds production center; Sistema automatizado para la gestion de la seguridad radiologica un centro de produccion de radiofarmacos y compuestos marcados