WorldWideScience

Sample records for radiation safety design

  1. Comparison of Design and Practices for Radiation Safety among Five Synchrotron Radiation Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Liu, James C.; Rokni, Sayed H.; /SLAC; Asano, Yoshihiro; /JAERI-RIKEN, Hyogo; Casey, William R.; /Brookhaven; Donahue, Richard J.; /LBL, Berkeley

    2005-06-29

    There are more and more third-generation synchrotron radiation (SR) facilities in the world that utilize low emittance electron (or positron) beam circulating in a storage ring to generate synchrotron light for various types of experiments. A storage ring based SR facility consists of an injector, a storage ring, and many SR beamlines. When compared to other types of accelerator facilities, the design and practices for radiation safety of storage ring and SR beamlines are unique to SR facilities. Unlike many other accelerator facilities, the storage ring and beamlines of a SR facility are generally above ground with users and workers occupying the experimental floor frequently. The users are generally non-radiation workers and do not wear dosimeters, though basic facility safety training is required. Thus, the shielding design typically aims for an annual dose limit of 100 mrem over 2000 h without the need for administrative control for radiation hazards. On the other hand, for operational and cost considerations, the concrete ring wall (both lateral and ratchet walls) is often desired to be no more than a few feet thick (with an even thinner roof). Most SR facilities have similar operation modes and beam parameters (both injection and stored) for storage ring and SR beamlines. The facility typically operates almost full year with one-month start-up period, 10-month science program for experiments (with short accelerator physics studies and routine maintenance during the period of science program), and a month-long shutdown period. A typical operational mode for science program consists of long periods of circulating stored beam (which decays with a lifetime in tens of hours), interposed with short injection events (in minutes) to fill the stored current. The stored beam energy ranges from a few hundreds MeV to 10 GeV with a low injection beam power (generally less than 10 watts). The injection beam energy can be the same as, or lower than, the stored beam energy

  2. Design of the EURISOL multi-MW target assembly radiation and safety issues

    CERN Document Server

    Felcini, Marta; Kadi, Yacine; Otto, Thomas; Tecchio, L

    2006-01-01

    The multi-MW target proposed for the EURISOL facility will be based on fission of uranium (or thorium) compounds to produce rare isotopes far from stability. A two-step process is used for the isotope production. First, neutrons are generated in a liquid mercury target, irradiated by the 1 GeV proton or deuteron beam, provided by the EURISOL linac driver. Then, the neutrons induce fission in a surrounding assembly of uranium carbide. R&D projects on several aspects of the target assembly are ongoing. Key criteria for the target design are a maximum beam power capability of 4 MW, a remote handling system with minimum downtime and maximum reliability, as well as radiation safety, minimization of hazards and the classification of the facility. In the framework of the ongoing radiation characterization and safety studies, radiation transport simulations have been performed to calculate the prompt radiation dose in the target and surrounding materials, as well as to determine shielding material and angle-depen...

  3. Design of the EURISOL multi-MW target assembly: radiation and safety issues

    CERN Document Server

    Felcini, M; Kadi, Y; Otto, T; Tecchio, L; Otto, Th.

    2006-01-01

    The multi-MW target proposed for the EURISOL facility will be based on fission of uranium (or thorium) compounds to produce rare isotopes far from stability. A two-step process is used for the isotope production. First, neutrons are generated in a liquid mercury target, irradiated by the 1 GeV proton or deuteron beam, provided by the EURISOL linac driver. Then, the neutrons induce fission in a surrounding assembly of uranium carbide. R&D projects on several aspects of the target assembly are ongoing. Key criteria for the target design are a maximum beam power capability of 4 MW, a remote handling system with minimum downtime and maximum reliability, as well as radiation safety, minimization of hazards and the classification of the facility. In the framework of the ongoing radiation characterization and safety studies, radiation transport simulations have been performed to calculate the prompt radiation dose in the target and surrounding materials, as well as to determine shielding material and angle-depen...

  4. Radiation safety education for laboratory animal science.

    Science.gov (United States)

    Emrich, J; Lambert, K

    2000-08-01

    Students enrolled in the laboratory animal science graduate program at MCP Hahnemann University seek to gain entrance to veterinary school or to manage an animal facility within an academic institution, pharmaceutical or biotechnology company conducting biomedical research. Ongoing interaction between faculty in the radiation oncology, radiation safety, and lab animal science disciplines revealed an acute need for radiation safety education for laboratory animal science students who will likely interact with researchers either designing and writing protocols for animal studies using radiation or radioactive materials, or veterinary staff who will use sources of radiation to diagnose and/or treat possible animal injuries and diseases. A core course in the Radiation Sciences graduate program was modified to address the needs of these students, instructing them in radiation safety, detection and counting instrumentation, and radiation biology. These fundamental areas were integrated to help the students gain a sound, basic knowledge of radiation and radioactive materials used in biomedical research.

  5. Radiation Safety Aspects of Nanotechnology

    Energy Technology Data Exchange (ETDEWEB)

    Hoover, Mark [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Myers, David; Cash, Leigh Jackson [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Guilmette, Raymond [Ray Guilmette & Associates, LLC, Perry, ME (United States); Kreyling, Wolfgang [Helmholtz-Zentrum Munchen, (Germany); Oberdorster, Gunter [Univ. of Rochester, NY (United States); Smith, Rachel [Public Health England, Oxfordshire (United Kingdom). Centre for Radiation, Chemical and Environmental Hazards

    2017-03-27

    This Report is intended primarily for operational health physicists, radiation safety officers, and internal dosimetrists who are responsible for establishing and implementing radiation safety programs involving radioactive nanomaterials. It should also provide useful information for workers, managers and regulators who are either working directly with or have other responsibilities related to work with radioactive nanomaterials.

  6. Industrial irradiator radiation safety program assessments

    Science.gov (United States)

    Smith, Mark A.

    2000-03-01

    Considerable attention is typically given to radiation safety in the design of irradiators and initially establishing the program. However, one component that may not receive enough attention is applying the continuous improvement philosophy to the radiation safety program. Periodic total program assessments of radiation safety can ensure that the design and implementation of the program continues to be applicable to the operations. The first step in the process must be to determine what is to be covered in the program assessment. While regulatory compliance audits are a component, the most useful evaluation will extend beyond looking only at compliance and determine whether the radiation safety program is the most appropriate for the particular operation. Several aspects of the irradiator operation, not all of which may routinely be considered "radiation safety", per se, should be included: Design aspects of the irradiator and operating system, system controls, and maintenance procedures, as well as the more traditional radiation safety program components such as surveys, measurements and training.

  7. Radiation Safety in Pediatric Orthopaedics.

    Science.gov (United States)

    Caird, Michelle S

    2015-01-01

    Patients, surgeons, and staff are exposed to ionizing radiation in pediatric orthopaedic surgery from diagnostic studies and imaging associated with procedures. Estimating radiation dose to pediatric patients is based on complex algorithms and dose to surgeons and staff is based on dosimeter monitoring. Surgeons can decrease radiation exposure to patients with careful and thoughtful ordering of diagnostic studies and by minimizing exposure intraoperatively. Surgeon and staff radiation exposure can be minimized with educational programs, proper shielding and positioning intraoperatively, and prudent use of intraoperative imaging. Overall, better awareness among pediatric orthopaedic surgeons of our role in radiation exposure can lead to improvements in radiation safety.

  8. Integrated Safety in Design

    DEFF Research Database (Denmark)

    Schultz, Casper Siebken; Jørgensen, Kirsten

    2014-01-01

    a theoretical framework is developed from a combination of existing literature on health and safety and a mapping of existing practices based on interviews in all four companies. The interviews revealed that the basic knowledge on OHS among architects and engineers is limited. Also currently designers typically......An on-going research project investigates the inclusion of health and safety considerations in the design phase as a means to achieve a higher level of health and safety in the construction industry. Moreover, the approach is coupled to the overall quality efforts. Two architectural firms and two...... consider OHS in execution as a responsibility of the contractors. The output of this stage is a systematic and structured conceptual framework that couples OHS-risks in construction (health, safety and mental health) to the stages in the design and engineering processes. Moreover the framework includes...

  9. HRIBF Tandem Accelerator Radiation Safety System Upgrade

    Energy Technology Data Exchange (ETDEWEB)

    Blankenship, J.L.; Juras, R.C.

    1998-11-04

    The HRIBF Tandem Accelerator Radiation Safety System was designed to permit experimenters and operations staff controlled access to beam transport and experiment areas with accelerated beam present. Neutron-Gamma detectors are mounted in eaeh area at points of maximum dose rate and the resulting signals are integrated by redundan~ circuitry; beam is stopped if dose rate or integrated dose exceeds established limits. This paper will describe the system, in use for several vears at the HRIBF, and discuss changes recently made to modernize the system and to make the system compliant with DOE Order 5480.25 and related ORNL updated safety rules.

  10. Radiation safety in nuclear medicine procedures

    Energy Technology Data Exchange (ETDEWEB)

    Cho, Sang Geon; Kim, Ja Hae; Song, Ho Chun [Dept. of Nuclear Medicine, Medical Radiation Safety Research Center, Chonnam National University Hospital, Gwangju (Korea, Republic of)

    2017-03-15

    Since the nuclear disaster at the Fukushima Daiichi Nuclear Power Plant in 2011, radiation safety has become an important issue in nuclear medicine. Many structured guidelines or recommendations of various academic societies or international campaigns demonstrate important issues of radiation safety in nuclear medicine procedures. There are ongoing efforts to fulfill the basic principles of radiation protection in daily nuclear medicine practice. This article reviews important principles of radiation protection in nuclear medicine procedures. Useful references, important issues, future perspectives of the optimization of nuclear medicine procedures, and diagnostic reference level are also discussed.

  11. Radiation Safety in Nuclear Medicine Procedures.

    Science.gov (United States)

    Cho, Sang-Geon; Kim, Jahae; Song, Ho-Chun

    2017-03-01

    Since the nuclear disaster at the Fukushima Daiichi Nuclear Power Plant in 2011, radiation safety has become an important issue in nuclear medicine. Many structured guidelines or recommendations of various academic societies or international campaigns demonstrate important issues of radiation safety in nuclear medicine procedures. There are ongoing efforts to fulfill the basic principles of radiation protection in daily nuclear medicine practice. This article reviews important principles of radiation protection in nuclear medicine procedures. Useful references, important issues, future perspectives of the optimization of nuclear medicine procedures, and diagnostic reference level are also discussed.

  12. The Advanced Light Source (ALS) Radiation Safety System. Revised

    Energy Technology Data Exchange (ETDEWEB)

    Ritchie, A.L.; Oldfather, D.E.; Lindner, A.F.

    1993-08-01

    The Advanced Light Source (ALS) at the Lawrence Berkeley Laboratory (LBL) is a 1.5 Gev synchrotron light source facility consisting of a 120 kev electron gun, 50 Mev linear accelerator, 1.5 Gev booster synchrotron, 200 meter circumference electron storage ring, and many photon beamline transport systems for research. Figure 1. ALS floor plan. Pairs of neutron and gamma radiation monitors are shown as dots numbered from 1 to 12. The Radiation Safety System for the ALS has been designed and built with a primary goal of providing protection against inadvertent personnel exposure to gamma and neutron radiation and, secondarily, to enhance the electrical safety of select magnet power supplies.

  13. Radiation Engineering for Designers

    Science.gov (United States)

    Pellish, Jonathan A.

    2015-01-01

    This tutorial provides an overview of the natural space radiation environment, an introduction to radiation effect types, an overview of EEE parts selection, scrubbing, and radiation mitigation, and an introduction to radiation testing.

  14. Radiation Engineering for Designers

    Science.gov (United States)

    Pellish, Jonathan A.

    2015-01-01

    This tutorial provides an overview of the natural space radiation environment, an introduction to radiation effect types, an overview of EEE parts selection, scrubbing, and radiation mitigation, and an introduction to radiation testing.

  15. Safety design for medical robots.

    Science.gov (United States)

    Kazanzides, Peter

    2009-01-01

    The use of robots in medicine is increasing, leading to the call for specific safety standards. This is a challenging endeavor, however, because the patient must usually be placed in the robot's workspace and the medical staff must frequently interact with the robot. Although specific safety standards for medical robots do not yet exist, there are several medical device standards and well-established principles of risk analysis and safety design that can and should be applied. This paper presents a tutorial overview of safety design for medical robots, starting with a discussion of high-level safety requirements, followed by methods for risk assessment (or hazard analysis) and a brief discussion of some sample safety strategies.

  16. Radiation Safety Systems for Accelerator Facilities

    Energy Technology Data Exchange (ETDEWEB)

    James C. Liu; Jeffrey S. Bull; John Drozdoff; Robert May; Vaclav Vylet

    2001-10-01

    The Radiation Safety System (RSS) of an accelerator facility is used to protect people from prompt radiation hazards associated with accelerator operation. The RSS is a fully interlocked, engineered system with a combination of passive and active elements that are reliable, redundant, and fail-safe. The RSS consists of the Access Control System (ACS) and the Radiation Containment System (RCS). The ACS is to keep people away from the dangerous radiation inside the shielding enclosure. The RCS limits and contains the beam/radiation conditions to protect people from the prompt radiation hazards outside the shielding enclosure in both normal and abnormal operations. The complexity of a RSS depends on the accelerator and its operation, as well as associated hazard conditions. The approaches of RSS among different facilities can be different. This report gives a review of the RSS for accelerator facilities.

  17. Radiation Safety Systems for Accelerator Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Liu, James C

    2001-10-17

    The Radiation Safety System (RSS) of an accelerator facility is used to protect people from prompt radiation hazards associated with accelerator operation. The RSS is a fully interlocked, engineered system with a combination of passive and active elements that are reliable, redundant, and fail-safe. The RSS consists of the Access Control System (ACS) and the Radiation Containment System (RCS). The ACS is to keep people away from the dangerous radiation inside the shielding enclosure. The RCS limits and contains the beam/radiation conditions to protect people from the prompt radiation hazards outside the shielding enclosure in both normal and abnormal operations. The complexity of a RSS depends on the accelerator and its operation, as well as associated hazard conditions. The approaches of RSS among different facilities can be different. This report gives a review of the RSS for accelerator facilities.

  18. Radiation safety assessment and development of environmental radiation monitoring technology

    CERN Document Server

    Choi, B H; Kim, S G

    2002-01-01

    The Periodic Safety Review(PSR) of the existing nuclear power plants is required every ten years according to the recently revised atomic energy acts. The PSR of Kori unit 1 and Wolsong unit 1 that have been operating more than ten years is ongoing to comply the regulations. This research project started to develop the techniques necessary for the PSR. The project developed the following four techniques at the first stage for the environmental assessment of the existing plants. 1) Establishment of the assessment technology for contamination and accumulation trends of radionuclides, 2) alarm point setting of environmental radiation monitoring system, 3) Development of Radiation Safety Evaluation Factor for Korean NPP, and 4) the evaluation of radiation monitoring system performance and set-up of alarm/warn set point. A dynamic compartment model to derive a relationship between the release rates of gas phase radionuclides and the concentrations in the environmental samples. The model was validated by comparing ...

  19. Radiation safety considerations in proton aperture disposal.

    Science.gov (United States)

    Walker, Priscilla K; Edwards, Andrew C; Das, Indra J; Johnstone, Peter A S

    2014-04-01

    Beam shaping in scattered and uniform scanned proton beam therapy (PBT) is made commonly by brass apertures. Due to proton interactions, these devices become radioactive and could pose safety issues and radiation hazards. Nearly 2,000 patient-specific devices per year are used at Indiana University Cyclotron Operations (IUCO) and IU Health Proton Therapy Center (IUHPTC); these devices require proper guidelines for disposal. IUCO practice has been to store these apertures for at least 4 mo to allow for safe transfer to recycling contractors. The devices require decay in two staged secure locations, including at least 4 mo in a separate building, at which point half are ready for disposal. At 6 mo, 20-30% of apertures require further storage. This process requires significant space and manpower and should be considered in the design process for new clinical facilities. More widespread adoption of pencil beam or spot scanning nozzles may obviate this issue, as apertures then will no longer be necessary.

  20. Radiation protection and safety of radiation sources international basic safety standards

    CERN Document Server

    International Atomic Energy Agency. Vienna

    2014-01-01

    The Board of Governors of the IAEA first approved Basic Safety Standards in June 1962; they were published by the IAEA as IAEA Safety Series No. 9. A revised edition was issued in 1967. A third revision was published by the IAEA as the 1982 Edition of IAEA Safety Series No. 9 ; this edition was jointly sponsored by the IAEA, ILO, OECD/NEA and the WHO. The next edition was International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources, published by the IAEA as IAEA Safety Series No. 115 in February 1996, and jointly sponsored by the FAO, IAEA, ILO, OECD/NEA, PAHO and the WHO.

  1. A study on room design and radiation safety around room for Co-60 after loading HDR brachytherapy unit converted from room for Ir-192 after loading HDR brachytherapy unit

    Directory of Open Access Journals (Sweden)

    Om Prakash Gurjar

    2015-01-01

    Full Text Available Context: Use of Co-60 source in place of Ir-192 in high dose rate brachytherapy unit (HDR unit has come for discussion in recent publications. Co-60 based system has been advocated for centers which have fewer brachytherapy procedures as it has comparative economically and administrative advantage. This study has direct practical application for such institutions, which are at the cusp of moving from Ir-192 to Co-60 based brachytherapy. Aims: Conversion of Ir-192 HDR room to Co-60 HDR room and to analyze radiation safety around the room. Materials and Methods: Uniform thickness of 15 cm concrete was added to all walls (except one wall adjoining to linear accelerator bunker to convert existing room forIr-192 HDR unit to suitable room for Co-60 HDR unit. Radiation survey around room was done. Actual and calculated wall thicknesses were compared. Results: Radiation survey data indicates that modified room is suitable for Co-60 HDR unit and all values are in full conformity to annual dose limits mentioned in Safety Code for Radiation Therapy Sources (SCRTS, Atomic Energy Regulatory Body (AERB; the regulatory body in India. Also, modified wall thicknesses are appropriate for annual design dose limits mentioned in Safety Report Series No. 47 of International Atomic Energy Agency (IAEA. However, console wall thickness (0.45 m is less than the calculated thickness (0.53 m for instantaneous dose rate (IDR design dose limit (7.5 ΅Sv/h as perabove safety report of IAEA. Conclusions: The modified wall thicknesses are appropriate for annual design dose limits. However, console wall thickness is less than the required thickness for IDR design dose limit. It has been suggested to add 2.64 cm steel on console wall. It has been found that design dose limits should be considered while making room layout plan and regulatory body should add these constraints inSCRTS.

  2. 10 CFR 35.50 - Training for Radiation Safety Officer.

    Science.gov (United States)

    2010-01-01

    ...) of this section, and has achieved a level of radiation safety knowledge sufficient to function... 10 Energy 1 2010-01-01 2010-01-01 false Training for Radiation Safety Officer. 35.50 Section 35.50... Requirements § 35.50 Training for Radiation Safety Officer. Except as provided in § 35.57, the licensee...

  3. [Radiation safety of exploitation of radiation sources at the civil aviation airlines].

    Science.gov (United States)

    Afanas'ev, R V; Zuev, V G; Berezin, G I; Sereda, V N; Zasiad'ko, A K

    2004-01-01

    Radiation risks from isotope-containing equipment, and ionizing and unused X-ray radiation sources are characterized and relevant normative documents with safety requirements to radiation sources installation, radiation safety of aircraft servicing and repair, hand luggage control and heavy luggage registration, personal protection items, system of radiation monitoring at airlines and aircraft works, and liability for breach of performance guidelines are cited.

  4. Maintenance of radiation safety information system

    Energy Technology Data Exchange (ETDEWEB)

    Choi, Ho Sun [Korea Institute of Nuclear Safety, Taejon (Korea, Republic of); Park, Moon Il; Chung, Chong Kyu; Lim, Bock Soo; Kim, Hyung Uk; Chang, Kwang Il; Nam, Kwan Hyun; Cho, Hye Ryan [AD center incubation LAB, Taejon (Korea, Republic of)

    2001-12-15

    The objectives of radiation safety information system maintenance are to maintain the requirement of users, change of job process and upgrade of the system performance stably and effectively while system maintenance. We conduct the code of conduct recommended by IAEA, management of radioisotope inventory database systematically using analysis for the state of inventory database integrated in this system. This system and database will be support the regulatory guidance, rule making and information to the MOST, KINS, other regulatory related organization and general public optimizationally.

  5. Radiation protection and safety of workers

    Energy Technology Data Exchange (ETDEWEB)

    Lindhe, J.C. [Swedish Radiation Protection Inst. (Sweden)

    1997-10-01

    This section briefly reviews the principles applicable to radiation protection and safety of workers, and methods that could be used to minimise occupational exposure in reclamation work. In considering the clean up of areas shortly after an accident, a decision would have to be made whether to implement clean-up actions early and thus cause higher occupational doses, or wait until short-lived isotopes have decayed and/or weathering has reduced the radiation levels. For example, the decision may be to stabilise the contamination using sprays to prevent re-suspension followed by a delay before actual clean-up starts. The timing of such actions would depend on many factors, including weather conditions, the area involved, equipment available and the competence of the work force. Means of reducing occupational exposure while carrying out the tasks should, as far as possible, be clearly defined in `work procedures`. In general, reductions in occupational exposure during operational tasks can be accomplished by the use of shielding and limiting the time that workers spend exposed to radiation. (au). 10 refs.

  6. Addressing a radiation safety sentinel event alert: one state's experience.

    Science.gov (United States)

    Temme, James B; Lane, Thomas; Rutar, Frank; McGowan, Ann

    2012-01-01

    The Joint Commission issued a Sentinel Event Alert in August 2011 to address the radiation risks related to diagnostic medical imaging. The University of Nebraska Medical Center (UNMC) and Nebraska Coalition for Patient Safety (NCPS) sent a survey to Nebraska hospital radiology departments in May 2012 to solicit responses regarding radiation safety management practices. Survey results demonstrate that Nebraska hospitals perform well in many radiation safety efforts, but lack in others, as well as the need for additional research to track or compare progress. Nebraska's experience can serve as a model for other states to perform similar radiation safety management research.

  7. NCRP Program Area Committee 2: Operational Radiation Safety.

    Science.gov (United States)

    Goldin, Eric M; Pryor, Kathryn H

    2016-02-01

    Program Area Committee 2 of the National Council on Radiation Protection and Measurements provides guidance for radiation safety in occupational settings in a variety of industries and activities. The Committee completed three reports in recent years covering recommendations for the development and administration of radiation safety programs for smaller educational institutions, requirements for self-assessment programs that improve radiation safety and identify and correct deficiencies, and a comprehensive process for effective investigation of radiological incidents. Ongoing work includes a report on sealed radioactive source controls and oversight of a report on radioactive nanomaterials focusing on gaps within current radiation safety programs. Future efforts may deal with operational radiation safety programs in fields such as the safe use of handheld and portable x-ray fluorescence analyzers, occupational airborne radioactive contamination, unsealed radioactive sources, or industrial accelerators.

  8. NCRP Program Area Committee 2: Operational Radiation Safety

    Energy Technology Data Exchange (ETDEWEB)

    Pryor, Kathryn H.; Goldin, Eric M.

    2016-02-29

    Program Area Committee 2 of the National Council on Radiation Protection and Measurements provides guidance for radiation safety in occupational settings in a variety of industries and activities. The committee completed three reports in recent years covering recommendations for the development and administration of radiation safety programs for smaller educational institutions, requirements for self-assessment programs that improve radiation safety and identify and correct deficiencies, and a comprehensive process for effective investigation of radiological incidents. Ongoing work includes a report on sealed radioactive source controls and oversight of a report on radioactive nanomaterials focusing on gaps within current radiation safety programs. Future efforts may deal with operational radiation safety programs in fields such as the safe use of handheld and portable X-Ray fluorescence analyzers, occupational airborne radioactive contamination, unsealed radioactive sources, or industrial accelerators.

  9. Spacesuit Radiation Shield Design Methods

    Science.gov (United States)

    Wilson, John W.; Anderson, Brooke M.; Cucinotta, Francis A.; Ware, J.; Zeitlin, Cary J.

    2006-01-01

    Meeting radiation protection requirements during EVA is predominantly an operational issue with some potential considerations for temporary shelter. The issue of spacesuit shielding is mainly guided by the potential of accidental exposure when operational and temporary shelter considerations fail to maintain exposures within operational limits. In this case, very high exposure levels are possible which could result in observable health effects and even be life threatening. Under these assumptions, potential spacesuit radiation exposures have been studied using known historical solar particle events to gain insight on the usefulness of modification of spacesuit design in which the control of skin exposure is a critical design issue and reduction of blood forming organ exposure is desirable. Transition to a new spacesuit design including soft upper-torso and reconfigured life support hardware gives an opportunity to optimize the next generation spacesuit for reduced potential health effects during an accidental exposure.

  10. Controlling radiated emissions by design

    CERN Document Server

    Mardiguian, Michel

    2014-01-01

    The 3rd edition of Controlling Radiated Emissions by Design has been updated to reflect the latest changes in the field. New to this edition is material related to technical advances, specifically super-fast data rates on wire pairs, with no increase in RF interference. Throughout the book, details are given to control RF emissions using EMC design techniques. This book retains the step-by-step approach for incorporating EMC into every new design from the ground up. It describes the selection of quieter IC technologies, their implementation into a noise-free printed circuit layout, and the gathering of these into a low emissions package. Also included is how to design an I/O filter, along with connectors and cable considerations. All guidelines are supported throughout with comprehensive calculated examples. Design engineers, EMC specialists, and technicians will benefit from learning about the development of more efficient and economical control of emissions.

  11. Radiation safety and vascular access: attitudes among cardiologists worldwide

    Energy Technology Data Exchange (ETDEWEB)

    Vidovich, Mladen I., E-mail: miv@uic.edu [Department of Medicine, Division of Cardiology, University of Illinois at Chicago, Chicago, Illinois (United States); Khan, Asrar A. [Department of Medicine, Division of Cardiology, University of Illinois at Chicago, Chicago, Illinois (United States); Xie, Hui [Division of Epidemiology and Biostatistics and Cancer Center, University of Illinois at Chicago, Chicago, Illinois (United States); Shroff, Adhir R. [Department of Medicine, Division of Cardiology, University of Illinois at Chicago, Chicago, Illinois (United States)

    2015-03-15

    Objectives: To determine opinions and perceptions of interventional cardiologists on the topic of radiation and vascular access choice. Background: Transradial approach for cardiac catheterization has been increasing in popularity worldwide. There is evidence that transradial access (TRA) may be associated with increasing radiation doses compared to transfemoral access (TFA). Methods: We distributed a questionnaire to collect opinions of interventional cardiologists around the world. Results: Interventional cardiologists (n = 5332) were contacted by email to complete an on-line survey from September to October 2013. The response rate was 20% (n = 1084). TRA was used in 54% of percutaneous coronary interventions (PCIs). Most TRAs (80%) were performed with right radial access (RRA). Interventionalists perceived that TRA was associated with higher radiation exposure compared to TFA and that RRA was associated with higher radiation exposure that left radial access (LRA). Older interventionalists were more likely to use radiation protection equipment and those who underwent radiation safety training gave more importance to ALARA (as low as reasonably achievable). Nearly half the respondents stated they would perform more TRA if the radiation exposure was similar to TFA. While interventionalists in the United States placed less importance to certain radiation protective equipment, European operators were more concerned with physician and patient radiation. Conclusions: Interventionalists worldwide reported higher perceived radiation doses with TRA compared to TFA and RRA compared to LRA. Efforts should be directed toward encouraging consistent radiation safety training. Major investment and application of novel radiation protection tools and radiation dose reduction strategies should be pursued. - Highlights: • We examined radiation safety and arterial access practices among 1000 cardiologists. • Radial access is perceived as having higher radiation dose compared to

  12. Safety in the design of production lines

    DEFF Research Database (Denmark)

    Dyhrberg, Mette Bang; Broberg, Ole; Jacobsen, Peter

    2006-01-01

    This paper is a case study report on how safety considerations were handled in the process of redesigning a production line. The design process was characterized as a specification and negotiation process between engineers from the company and the supplier organization. The new production line...... became safer, but not as a result of any intentional plan to integrate safety aspects into the design process. Instead, the supplier’s design of a new piece of equipment had a higher built-in safety level. The engineering team in the company was aware of the importance of safety aspects neither...... a ‘history workshop’ with the engineering team. The workshop clarified the sequence of events and discussions that took place during the design process and opened for a discussion of the role of safety aspects. During the workshop new insights emerged into the question of how to integrate safety aspects...

  13. Characteristics of radiation safety for synchrotron radiation and X-ray free electron laser facilities.

    Science.gov (United States)

    Asano, Yoshihiro

    2011-07-01

    Radiation safety problems are discussed for typical electron accelerators, synchrotron radiation (SR) facilities and X-ray free electron laser (XFEL) facilities. The radiation sources at the beamline of the facilities are SR, including XFEL, gas bremsstrahlung and high-energy gamma ray and photo-neutrons due to electron beam loss. The radiation safety problems for each source are compared by using 8 GeV class SR and XFEL facilities as an example.

  14. Guidelines for engineering design for process safety

    National Research Council Canada - National Science Library

    2012-01-01

    .... Key areas to be enhanced in the new edition include inherently safer design, specifically concepts for design of inherently safer unit operations and Safety Instrumented Systems and Layer of Protection Analysis...

  15. Fire Safety Design of Wood Structures

    DEFF Research Database (Denmark)

    Hertz, Kristian Dahl

    2006-01-01

    Lecture Notes on Fire Safety Design of Wood Structures including charring of wood and load bearing capacity of beams, columns, and connections.......Lecture Notes on Fire Safety Design of Wood Structures including charring of wood and load bearing capacity of beams, columns, and connections....

  16. Neural Net Safety Monitor Design

    Science.gov (United States)

    Larson, Richard R.

    2007-01-01

    The National Aeronautics and Space Administration (NASA) at the Dryden Flight Research Center (DFRC) has been conducting flight-test research using an F-15 aircraft (figure 1). This aircraft has been specially modified to interface a neural net (NN) controller as part of a single-string Airborne Research Test System (ARTS) computer with the existing quad-redundant flight control system (FCC) shown in figure 2. The NN commands are passed to FCC channels 2 and 4 and are cross channel data linked (CCDL) to the other computers as shown. Numerous types of fault-detection monitors exist in the FCC when the NN mode is engaged; these monitors would cause an automatic disengagement of the NN in the event of a triggering fault. Unfortunately, these monitors still may not prevent a possible NN hard-over command from coming through to the control laws. Therefore, an additional and unique safety monitor was designed for a single-string source that allows authority at maximum actuator rates but protects the pilot and structural loads against excessive g-limits in the case of a NN hard-over command input. This additional monitor resides in the FCCs and is executed before the control laws are computed. This presentation describes a floating limiter (FL) concept1 that was developed and successfully test-flown for this program (figure 3). The FL computes the rate of change of the NN commands that are input to the FCC from the ARTS. A window is created with upper and lower boundaries, which is constantly floating and trying to stay centered as the NN command rates are changing. The limiter works by only allowing the window to move at a much slower rate than those of the NN commands. Anywhere within the window, however, full rates are allowed. If a rate persists in one direction, it will eventually hit the boundary and be rate-limited to the floating limiter rate. When this happens, a persistent counter begins and after a limit is reached, a NN disengage command is generated. The

  17. Army Programs: The Army Radiation Safety Program

    Science.gov (United States)

    2007-11-02

    area or very high radiation area. (For example, medical and dental diagnostic x-ray systems do not require an ARA.) However, commanders will...the testing of nuclear explosive devices or from past nuclear accidents such as Chernobyl that contribute to background radiation. Background radiation

  18. The architecture of safety: hospital design.

    Science.gov (United States)

    Joseph, Anjali; Rashid, Mahbub

    2007-12-01

    This paper reviews recent research literature reporting the effects of hospital design on patient safety. Features of hospital design that are linked to patient safety in the literature include noise, air quality, lighting conditions, patient room design, unit layout, and several other interior design features. Some of these features act as latent conditions for adverse events, and impact safety outcomes directly and indirectly by impacting staff working conditions. Others act as barriers to adverse events by providing hospital staff with opportunities for preventing accidents before they occur. Although the evidence linking hospital design to patient safety is growing, much is left to be done in this area of research. Nevertheless, the evidence reported in the literature may already be sufficient to have a positive impact on hospital design.

  19. Design of Fusion Safety Data Base

    Science.gov (United States)

    Aoki, Isao; Seki, Yasushi

    1994-03-01

    This report presents a data base architecture with its circumstance which is designed to be used for safety design and analysis studies. Design of Fusion Safety Data Base has been carried out to take into account a great number of published references on operation and control of fusion energy and engineering features to secure safety of fusion devices. Data Base of Fiscal Year 1993 - which has been established over an extended year - realized on PC (Personal Computer) peripherals is reported. The concept of data base architecture with its attributive issues and a manipulating way for users are also shown.

  20. What Parents Should Know about Medical Radiation Safety

    Science.gov (United States)

    ... 000 health care professionals in radiology, pediatrics, medical physics, and radiation safety. References Amis ES, Jr., Butler PF, Applegate KE, et al. American College of Radiology white paper on radiation dose in medicine. Journal of the American College of Radiology 2007; 4: ...

  1. Occupational safety in the fusion design process

    Energy Technology Data Exchange (ETDEWEB)

    Moshonas, K. E-mail: kmoshonas@sympatico.ca; Langman, V.J

    2001-04-01

    The radiological hazards associated with the operation and maintenance of fusion machines are cause for safety and regulatory concerns. Current experience in the nuclear industry, and at operating tokamaks confirm that a high level of occupational safety can be achieved through an effective planning process. For fusion facilities with increased hazard levels resulting from the introduction of large quantities of tritium, and higher neutron flux and fluence, a process must be implemented during the design phase to address both the worker safety and the regulatory requirements. Such a process has been developed and was used for the radiological occupational safety assessment of the International Thermonuclear Experimental Reactor (ITER). The purpose of this paper is to describe the approach used, including, the implementation of the as low as reasonably achievable (ALARA) principle for individual and collective doses in an evolving design, and the demonstration of adequate radiological occupational safety during the design process.

  2. Safety and Radiation Protection at Swedish Nuclear Power Plants 2005

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-05-15

    other things. Up-to-date and documented safety analyses must be prepared and actively be included in both the preventive safety work and in connection with plant modifications. The licensees have implemented design analysis projects for a long period of time and clarified and stringent regulations for safety analyses have entered into force in 2005. As a result, updated safety reports exist for many of the facilities and schedules exist for the supplementary work that remains to be done. SKI's reinforced supervision of Barsebaeck 2 continued until the closure of the reactor on May 31, 2005. In SKI's opinion, BKAB mainly handled the lengthy facility closure in a satisfactory manner. The handling of nuclear waste at the nuclear facilities has mainly functioned well. The same applies to the operation of the Repository for Low and Intermediate-level Operational Waste (SFR-1) and the Central Interim Storage Facility for Spent Nuclear Fuel (CLAB). The overall evaluation of the Swedish Radiation Protection Authority (SSI) is that radiation protection at Swedish nuclear power plants has functioned well in 2005. The total radiation dose to the personnel at Swedish nuclear power plants was 9.2 manSv, which agrees with the average value of the total radiation doses over the last five years (9 manSv). No-one received a radiation dose in excess of the established dose limits and the radiation levels in the facilities are largely unchanged compared with previous years. The radiation doses to the public from the Swedish nuclear power plants continue to be low. SSI considers that continuous work is also needed in the future at the facilities to further reduce radioactive releases by applying the best available technique (BAT) and other measures. The control measurements that SSI is conducting on environmental samples from around the nuclear power facilities as well as on radioactive releases to water show a good agreement with the licensees' own measurements.

  3. Spacecraft electronics design for radiation tolerance

    Science.gov (United States)

    Rasmussen, Robert D.

    1988-01-01

    Current design practices are described and future trends in spacecraft electronics which are likely to alter traditional approaches are discussed. A summary of radiation effects and radiation tolerance requirements typically levied on spacecraft designs is provided. Methods of dealing with radiation and testability issues are considered.

  4. Safety Sound interpretive site designation environmental assessment

    Data.gov (United States)

    US Fish and Wildlife Service, Department of the Interior — The purpose of this environmental assessment is to analyze the impacts of designating a 70 acre parcel of the Alaska Maritime National Wildlife Refuge as the Safety...

  5. Guidelines for engineering design for process safety

    National Research Council Canada - National Science Library

    2012-01-01

    "This updated version of one of the most popular and widely used CCPS books provides plant design engineers, facility operators, and safety professionals with key information on selected topics of interest...

  6. Radiation Safety of Sealed Radioactive Sources

    Energy Technology Data Exchange (ETDEWEB)

    Pryor, Kathryn H.

    2015-01-01

    Sealed radioactive sources are used in a wide variety of occupational settings and under differing regulatory/licensing structures. The definition of a sealed radioactive source varies between US regulatory authorities and standard-setting organizations. Potential problems with sealed sources cover a range of risks and impacts. The loss of control of high activity sealed sources can result in very high or even fatal doses to members of the public who come in contact with them. Sources that are not adequately sealed, and that fail, can cause spread of contamination and potential intake of radioactive material. There is also the possibility that sealed sources may be (or threatened to be) used for terrorist purposes and disruptive opportunities. Until fairly recently, generally-licensed sealed sources and devices received little, if any, regulatory oversight, and were often forgotten, lost or unaccounted for. Nonetheless, generally licensed devices can contain fairly significant quantities of radioactive material and there is some potential for exposure if a device is treated in a way that it was never designed. Industrial radiographers use and handle high activity and/or high-dose rate sealed sources in the field with a high degree of independence and minimal regulatory oversight. Failure to follow operational procedures and properly handle radiography sources can and has resulted in serious injuries and death. Industrial radiographers have experienced a disproportionately large fraction of incidents that result in unintended exposure to radiation. Sources do not have to contain significant quantities of radioactive material to cause problems in the event of their failure. A loss of integrity can cause the spread of contamination and potential exposure to workers and members of the public. The NCRP has previously provided recommendations on select aspects of sealed source programs. Future efforts to provide recommendations for sealed source programs are discussed.

  7. Construction safety and digital design: a review

    OpenAIRE

    Zhou, Wei; Whyte, Jennifer; Sacks, Rafael

    2012-01-01

    As digital technologies become widely used in designing buildings and infrastructure, questions arise about\\ud their impacts on construction safety. This review explores relationships between construction safety and\\ud digital design practices with the aim of fostering and directing further research. It surveys state-of-the-art\\ud research on databases, virtual reality, geographic information systems, 4D CAD, building information\\ud modeling and sensing technologies, finding various digital t...

  8. Radiation safety: what can happen in an accident.

    Science.gov (United States)

    Scully, C; de Almeida, O P

    1992-04-11

    Radiation hazards in dental practice have long been recognized, and the dangers from ionising radiation during dental radiography are discussed elsewhere. Continuing legislation will undoubtedly help reduce the risk of over-exposure and accidents. Nevertheless, it is of some concern that radiation safety is still ignored by some: for example, one recent survey in the UK showed that not all radiography sets conformed to modern safety standards. However, the profession also has reason to be concerned about more public radiation hazards that may affect them, and their families and others, and may, without denying the importance of dental radiation protection, have far greater effects on health. Well-known examples of domestic radon exposure occurred in the UK, particularly in the Lake District and the South West, and the nuclear reactor accidents--notably at Chernobyl in 1986.

  9. SAFETY

    CERN Document Server

    Niels Dupont

    2013-01-01

    CERN Safety rules and Radiation Protection at CMS The CERN Safety rules are defined by the Occupational Health & Safety and Environmental Protection Unit (HSE Unit), CERN’s institutional authority and central Safety organ attached to the Director General. In particular the Radiation Protection group (DGS-RP1) ensures that personnel on the CERN sites and the public are protected from potentially harmful effects of ionising radiation linked to CERN activities. The RP Group fulfils its mandate in collaboration with the CERN departments owning or operating sources of ionising radiation and having the responsibility for Radiation Safety of these sources. The specific responsibilities concerning "Radiation Safety" and "Radiation Protection" are delegated as follows: Radiation Safety is the responsibility of every CERN Department owning radiation sources or using radiation sources put at its disposition. These Departments are in charge of implementing the requi...

  10. Radiation protection, radiation safety and radiation shielding assessment of HIE-ISOLDE.

    Science.gov (United States)

    Romanets, Y; Bernardes, A P; Dorsival, A; Gonçalves, I F; Kadi, Y; di Maria, S; Vaz, P; Vlachoudis, V; Vollaire, J

    2013-07-01

    The high intensity and energy ISOLDE (HIE-ISOLDE) project is an upgrade to the existing ISOLDE facility at CERN. The foreseen increase in the nominal intensity and the energy of the primary proton beam of the existing ISOLDE facility aims at increasing the intensity of the produced radioactive ion beams (RIBs). The currently existing ISOLDE facility uses the proton beam from the proton-synchrotron booster with an energy of 1.4 GeV and an intensity up to 2 μA. After upgrade (final stage), the HIE-ISOLDE facility is supposed to run at an energy up to 2 GeV and an intensity up to 4 μA. The foreseen upgrade imposes constrains, from the radiation protection and the radiation safety point of view, to the existing experimental and supply areas. Taking into account the upgraded energy and intensity of the primary proton beam, a new assessment of the radiation protection and radiation safety of the HIE-ISOLDE facility is necessary. Special attention must be devoted to the shielding assessment of the beam dumps and of the experimental areas. In this work the state-of-the-art Monte Carlo particle transport simulation program FLUKA was used to perform the computation of the ambient dose equivalent rate distribution and of the particle fluxes in the projected HIE-ISOLDE facility (taking into account the upgrade nominal primary proton beam energy and intensity) and the shielding assessment of the facility, with the aim of identifying in the existing facility (ISOLDE) the critical areas and locations where new or reinforced shielding may be necessary. The consequences of the upgraded proton beam parameters on the operational radiation protection of the facility were studied.

  11. Radiation design criteria handbook. [design criteria for electronic parts applications

    Science.gov (United States)

    Stanley, A. G.; Martin, K. E.; Douglas, S.

    1976-01-01

    Radiation design criteria for electronic parts applications in space environments are provided. The data were compiled from the Mariner/Jupiter Saturn 1977 electronic parts radiation test program. Radiation sensitive device types were exposed to radiation environments compatible with the MJS'77 requirements under suitable bias conditions. A total of 189 integrated circuits, transistors, and other semiconductor device types were tested.

  12. Safety culture in design. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Macchi, L.; Pietikaeinen, E.; Liinasuo, M.; Savioja, P.; Reiman, T.; Wahlstroem, M. [VTT Technical Research Centre of Finland, Espoo (Finland); Kahlbom, U. [Risk Pilot AB, Stockholm (Sweden); Rollenhagen, C. [Vattenfall, Stockholm, (Sweden)

    2013-04-15

    In this report we approach design from a safety culture approach As this research area is new and understudied, we take a wide scope on the issue. Different theoretical perspectives that can be taken when improving safety of the design process are considered in this report. We suggest that in the design context the concept of safety culture should be expanded from an organizational level to the level of the network of organizations involved in the design activity. The implication of approaching the design process from a safety culture perspective are discussed and the results of the empirical part of the research are presented. In the interview study in Finland and Sweden we identified challenges and opportunities in the design process from safety culture perspective. Also, a small part of the interview study concentrated on state of the art human factors engineering (HFE) practices in Finland and the results relating to that are presented. This report provide a basis for future development of systematic good design practices and for providing guidelines that can lead to safe and robust technical solutions. (Author)

  13. MO-AB-201-00: Radiation Safety Officer Update

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2015-06-15

    The role of the Radiation Safety Officer at a medical facility can be complicated. The complexity of the position is based on the breadth of services provided at the institution and the nature of the radioactive materials license. Medical practices are constantly changing and the use of ionizing radiation continues to rise in this area. Some of the newer medical applications involving radiation have unique regulatory and safety issues that must be addressed. Oversight of the uses of radiation start at the local level (radiation safety officer, radiation safety committee) and are heavily impacted by outside agencies (i.e. Nuclear Regulatory Commission, State Radiologic Health, The Joint Commission (TJC), etc). This session will provide both an overview of regulatory oversight and essential compliance practices as well as practical ways to assess and introduce some of the new applications utilizing radioactive materials into your medical facility. Learning Objectives: Regulatory Compliance and Safety with New Radiotherapies: Spheres and Ra-223 (Lance Phillips) Understand the radioactive materials license amendment process to add new radiotherapies (i.e., SIR-Spheres, Therasphere, Xofigo). Understand the AU approval process for microspheres and Xofigo. Examine the training and handling requirements for new procedures. Understand the process involved with protocol development, SOP in order to define roles and responsibilities. The RSO and The RSC: Challenges and Opportunities (Colin Dimock) Understand how to form an effective Committee. Examine what the Committee does for the Program and the RSO. Understand the importance of Committee engagement. Discuss the balance of the complimentary roles of the RSO and the Committee. The Alphabet Soup of Regulatory Compliance: Being Prepared for Inspections (Linda Kroger) Recognize the various regulatory bodies and organizations with oversight or impact in Nuclear Medicine, Radiology and Radiation Oncology. Examine 10CFR35

  14. The increased use of radiation requires enhanced activities regarding radiation safety control

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Yun Jong; Lee, Jin Woo; Jeong, Gyo Seong [Korea Atomic Energy Research Institute, Jeongeup (Korea, Republic of)

    2015-05-15

    More recently, companies that have obtained permission to use radioactive materials or radiation device and registered radiation workers have increased by 10% and 4% respectively. The increased use of radiation could have an effect on radiation safety control. However, there is not nearly enough manpower and budget compared to the number of workers and facilities. This paper will suggest a counteroffer thought analyzing pending issues. The results of this paper indicate that there are 47 and 31.3 workers per radiation protection officer in educational and research institutes, respectively. There are 20.1 persons per RPO in hospitals, even though there are 2 RPOs appointed. Those with a special license as a radioisotope handler were ruled out as possible managers because medical doctors who have a special license for radioisotope handling normally have no experience with radiation safety. The number of staff members and budget have been insufficient for safety control at most educational and research institutes. It is necessary to build an optimized safety control system for effective Radiation Safety Control. This will reduce the risk factor of safety, and a few RPOs can be supplied for efficiency and convenience.

  15. EVALUATION OF BRACHYTHERAPY FACILITY SHIELDING STATUS IN KOREA OBTAINED FROM RADIATION SAFETY REPORTS

    Directory of Open Access Journals (Sweden)

    MI HYUN KEUM

    2013-10-01

    Full Text Available Thirty-eight radiation safety reports for brachytherapy equipment were evaluated to determine the current status of brachytherapy units in Korea and to assess how radiation oncology departments in Korea complete radiation safety reports. The following data was collected: radiation safety report publication year, brachytherapy unit manufacturer, type and activity of the source that was used, affiliation of the drafter, exposure rate constant, the treatment time used to calculate workload and the HVL values used to calculate shielding design goal values. A significant number of the reports (47.4% included the personal information of the drafter. The treatment time estimates varied widely from 12 to 2,400 min/week. There was acceptable variation in the exposure rate constant values (ranging between 0.469 and 0.592 (R-m2/Ci·hr, as well as in the HVLs of concrete, steel and lead for Iridium-192 sources that were used to calculate shielding design goal values. There is a need for standard guidelines for completing radiation safety reports that realistically reflect the current clinical situation of radiation oncology departments in Korea. The present study may be useful for formulating these guidelines.

  16. Approximate design calculation methods for radiation streaming in shield irregularities

    Energy Technology Data Exchange (ETDEWEB)

    Miura, Toshimasa; Hirao, Yoshihiro [Ship Research Inst., Mitaka, Tokyo (Japan); Yoritsune, Tsutomu

    1997-10-01

    Investigation and assessment are made for approximate design calculation methods of radiation streaming in shield irregularities. Investigation is made for (1) source, (2) definition of streaming radiation components, (3) calculation methods of streaming radiation, (4) streaming formulas for each irregularity, (5) difficulties in application of streaming formulas, etc. Furthermore, investigation is made for simple calculation codes and albedo data. As a result, it is clarified that streaming calculation formulas are not enough to cover various irregularities and their accuracy or application limit is not sufficiently clear. Accurate treatment is not made in the formulas with respect to the radiation behavior for slant incidence, bend part, offset etc., that results in too much safety factors in the design calculation and distrust of the streaming calculation. To overcome the state and improve the accuracy of the design calculation for shield irregularities, it is emphasized to assess existing formulas and develop better formulas based on systematic experimental studies. (author)

  17. Integrating Safety and Mission Assurance in Design

    Science.gov (United States)

    Cianciola, Chris; Crane, Kenneth

    2008-01-01

    This presentation describes how the Ares Projects are learning from the successes and failures of previous launch systems in order to maximize safety and reliability while maintaining fiscal responsibility. The Ares Projects are integrating Safety and Mission Assurance into design activities and embracing independent assessments by Quality experts in thorough reviews of designs and processes. Incorporating Lean thinking into the design process, Ares is also streamlining existing processes and future manufacturing flows which will yield savings during production. Understanding the value of early involvement of Quality experts, the Ares Projects are leading launch vehicle development into the 21st century.

  18. Preliminary safety design analysis of KALIMER

    Energy Technology Data Exchange (ETDEWEB)

    Suk, Soo Dong; Kwon, Y. M.; Kim, K. D. [Korea Atomic Energy Research Institute, Taejon (Korea)

    1999-03-01

    The national long-term R and D program updated in 1997 requires Korea Atomic Energy Research Institute(KAERI) to complete by the year 2006 the basic design of Korea Advanced Liquid Metal Reactor (KALIMER), along with supporting R and D work, with the capability of resolving the issue of spent fuel storage as well as with significantly enhanced safety. KALIMER is a 150 MWe pool-type sodium cooled prototype reactor that uses metallic fuel. The conceptual design is currently under way to establish a self consistent design meeting a set of the major safety design requirements for accident prevention. Some of current emphasis include those for inherent and passive means of negative reactivity insertion and decay heat removal, high shutdown reliability, prevention of and protection from sodium chemical reaction, and high seismic margin, among others. All of these requirements affect the reactor design significantly and involve supporting R and D programs of substance. This document first introduces a set of safety design requirements and accident evaluation criteria established for the conceptual design of KALIMER and then summarizes some of the preliminary results of engineering and design analyses performed for the safety of KALIMER. 19 refs., 19 figs., 6 tabs. (Author)

  19. Primary battery design and safety guidelines handbook

    Science.gov (United States)

    Bragg, Bobby J.; Casey, John E.; Trout, J. Barry

    1994-12-01

    This handbook provides engineers and safety personnel with guidelines for the safe design or selection and use of primary batteries in spaceflight programs. Types of primary batteries described are silver oxide zinc alkaline, carbon-zinc, zinc-air alkaline, manganese dioxide-zionc alkaline, mercuric oxide-zinc alkaline, and lithium anode cells. Along with typical applications, the discussions of the individual battery types include electrochemistry, construction, capacities and configurations, and appropriate safety measures. A chapter on general battery safety covers hazard sources and controls applicable to all battery types. Guidelines are given for qualification and acceptance testing that should precede space applications. Permissible failure levels for NASA applications are discussed.

  20. B190 computer controlled radiation monitoring and safety interlock system

    Energy Technology Data Exchange (ETDEWEB)

    Espinosa, D L; Fields, W F; Gittins, D E; Roberts, M L

    1998-08-01

    The Center for Accelerator Mass Spectrometry (CAMS) in the Earth and Environmental Sciences Directorate at Lawrence Livermore National Laboratory (LLNL) operates two accelerators and is in the process of installing two new additional accelerators in support of a variety of basic and applied measurement programs. To monitor the radiation environment in the facility in which these accelerators are located and to terminate accelerator operations if predetermined radiation levels are exceeded, an updated computer controlled radiation monitoring system has been installed. This new system also monitors various machine safety interlocks and again terminates accelerator operations if machine interlocks are broken. This new system replaces an older system that was originally installed in 1988. This paper describes the updated B190 computer controlled radiation monitoring and safety interlock system.

  1. Computer-based and web-based radiation safety training

    Energy Technology Data Exchange (ETDEWEB)

    Owen, C., LLNL

    1998-03-01

    The traditional approach to delivering radiation safety training has been to provide a stand-up lecture of the topic, with the possible aid of video, and to repeat the same material periodically. New approaches to meeting training requirements are needed to address the advent of flexible work hours and telecommuting, and to better accommodate individuals learning at their own pace. Computer- based and web-based radiation safety training can provide this alternative. Computer-based and web- based training is an interactive form of learning that the student controls, resulting in enhanced and focused learning at a time most often chosen by the student.

  2. New adventures in biomedical engineering: Radiation safety program management

    Energy Technology Data Exchange (ETDEWEB)

    Dickey, D.M. (Washington Hospital Center, DC (United States))

    1991-09-01

    As biomedical/clinical engineers expand their managerial expertise into nontraditional areas, it makes sense that they pursue areas where their formal training in physics and mathematics can be applied. Radiation safety requires having the educational background to understand atomic structure, the nature of radioactivity, mathematics, biology, chemistry, and instrumentation. Program management requires having the administrative experience to manage people, data, files, documentation, and budgets. Radiation safety program management also requires an understanding of how best to prepare for a surprise inspection, similar to but technically more specific than other inspections and surveys previously experienced by the BME/CE professional.

  3. Evaluation of radiation safety in 29 central Ohio veterinary practices

    Energy Technology Data Exchange (ETDEWEB)

    Moritz, S.A.; Wilkins, J.R. III; Hueston, W.D.

    1989-07-01

    A sample of 29 veterinary practices in Central Ohio were visited to assess radiation safety practices and observance of state regulations. Lead aprons and gloves were usually available, but gloves were not always worn. Protective thyroid collars and lead glasses were not available in any practice, lead shields in only five practices, and lead-lined walls and doors in only two practices. Eighteen practices had none of the required safety notices posted.

  4. DESIGN PACKAGE 1D SYSTEM SAFETY ANALYSIS

    Energy Technology Data Exchange (ETDEWEB)

    L.R. Eisler

    1995-02-02

    The purpose of this analysis is to systematically identify and evaluate hazards related to the Yucca Mountain Project Exploratory Studies Facility (ESF) Design Package 1D, Surface Facilities, (for a list of design items included in the package 1D system safety analysis see section 3). This process is an integral part of the systems engineering process; whereby safety is considered during planning, design, testing, and construction. A largely qualitative approach was used since a radiological System Safety analysis is not required. The risk assessment in this analysis characterizes the accident scenarios associated with the Design Package 1D structures/systems/components in terms of relative risk and includes recommendations for mitigating all identified risks. The priority for recommending and implementing mitigation control features is: (1) Incorporate measures to reduce risks and hazards into the structure/system/component (S/S/C) design, (2) add safety devices and capabilities to the designs that reduce risk, (3) provide devices that detect and warn personnel of hazardous conditions, and (4) develop procedures and conduct training to increase worker awareness of potential hazards, on methods to reduce exposure to hazards, and on the actions required to avoid accidents or correct hazardous conditions. The scope of this analysis is limited to the Design Package 1D structures/systems/components (S/S/Cs) during normal operations excluding hazards occurring during maintenance and ''off normal'' operations.

  5. Nuclear Safety Design Base for License Application

    Energy Technology Data Exchange (ETDEWEB)

    R.J. Garrett

    2005-09-29

    The purpose of this report is to identify and document the nuclear safety design requirements that are specific to structures, systems, and components (SSCs) of the repository that are important to safety (ITS) during the preclosure period and to support the preclosure safety analysis and the license application for the high-level radioactive waste (HLW) repository at Yucca Mountain, Nevada. The scope of this report includes the assignment of nuclear safety design requirements to SSCs that are ITS and does not include the assignment of design requirements to SSCs or natural or engineered barriers that are important to waste isolation (ITWI). These requirements are used as input for the design of the SSCs that are ITS such that the preclosure performance objectives of 10 CFR 63.111(b) [DIRS 173273] are met. The natural or engineered barriers that are important to meeting the postclosure performance objectives of 10 CFR 63.113(b) and (c) [DIRS 173273] are identified as ITWI. Although a structure, system, or component (SSC) that is ITS may also be ITWI, this report is only concerned with providing the nuclear safety requirements for SSCs that are ITS to prevent or mitigate event sequences during the repository preclosure period.

  6. DESIGN PACKAGE 1E SYSTEM SAFETY ANALYSIS

    Energy Technology Data Exchange (ETDEWEB)

    M. Salem

    1995-06-23

    The purpose of this analysis is to systematically identify and evaluate hazards related to the Yucca Mountain Project Exploratory Studies Facility (ESF) Design Package 1E, Surface Facilities, (for a list of design items included in the package 1E system safety analysis see section 3). This process is an integral part of the systems engineering process; whereby safety is considered during planning, design, testing, and construction. A largely qualitative approach was used since a radiological System Safety Analysis is not required. The risk assessment in this analysis characterizes the accident scenarios associated with the Design Package 1E structures/systems/components(S/S/Cs) in terms of relative risk and includes recommendations for mitigating all identified risks. The priority for recommending and implementing mitigation control features is: (1) Incorporate measures to reduce risks and hazards into the structure/system/component design, (2) add safety devices and capabilities to the designs that reduce risk, (3) provide devices that detect and warn personnel of hazardous conditions, and (4) develop procedures and conduct training to increase worker awareness of potential hazards, on methods to reduce exposure to hazards, and on the actions required to avoid accidents or correct hazardous conditions.

  7. Space Weather Nowcasting of Atmospheric Ionizing Radiation for Aviation Safety

    Science.gov (United States)

    Mertens, Christopher J.; Wilson, John W.; Blattnig, Steve R.; Solomon, Stan C.; Wiltberger, J.; Kunches, Joseph; Kress, Brian T.; Murray, John J.

    2007-01-01

    There is a growing concern for the health and safety of commercial aircrew and passengers due to their exposure to ionizing radiation with high linear energy transfer (LET), particularly at high latitudes. The International Commission of Radiobiological Protection (ICRP), the EPA, and the FAA consider the crews of commercial aircraft as radiation workers. During solar energetic particle (SEP) events, radiation exposure can exceed annual limits, and the number of serious health effects is expected to be quite high if precautions are not taken. There is a need for a capability to monitor the real-time, global background radiations levels, from galactic cosmic rays (GCR), at commercial airline altitudes and to provide analytical input for airline operations decisions for altering flight paths and altitudes for the mitigation and reduction of radiation exposure levels during a SEP event. The Nowcast of Atmospheric Ionizing Radiation for Aviation Safety (NAIRAS) model is new initiative to provide a global, real-time radiation dosimetry package for archiving and assessing the biologically harmful radiation exposure levels at commercial airline altitudes. The NAIRAS model brings to bear the best available suite of Sun-Earth observations and models for simulating the atmospheric ionizing radiation environment. Observations are utilized from ground (neutron monitors), from the atmosphere (the METO analysis), and from space (NASA/ACE and NOAA/GOES). Atmospheric observations provide the overhead shielding information and the ground- and space-based observations provide boundary conditions on the GCR and SEP energy flux distributions for transport and dosimetry simulations. Dose rates are calculated using the parametric AIR (Atmospheric Ionizing Radiation) model and the physics-based HZETRN (High Charge and Energy Transport) code. Empirical models of the near-Earth radiation environment (GCR/SEP energy flux distributions and geomagnetic cut-off rigidity) are benchmarked

  8. Radiation protection and radiation safety: CERN and its host states to sign a tripartite agreement.

    CERN Multimedia

    2010-01-01

    On 15 November CERN and its Host States will sign a tripartite agreement that replaces the existing bilateral agreements in matters of radiation protection and radiation safety at CERN. It will provide, for the first time, a single forum where the three parties will discuss how maximum overall safety can best be achieved in the specific CERN context.   CERN has always maintained close collaboration with its Host States in matters of safety. “The aim of this collaboration is especially to ensure best practice in the field of radiation protection and the safe operation of CERN’s facilities”, explains Ralf Trant, Head of the Occupational Health & Safety and Environmental Protection (HSE) Unit. Until today, CERN’s collaboration with its Host States was carried out under two sets of bilateral agreements: depending on which side of the French-Swiss border they were being carried out on, a different framework applied to the same activities. This approach has b...

  9. Corporate Functional Management Evaluation of the LLNL Radiation Safety Organization

    Energy Technology Data Exchange (ETDEWEB)

    Sygitowicz, L S

    2008-03-20

    A Corporate Assess, Improve, and Modernize review was conducted at Lawrence Livermore National Laboratory (LLNL) to evaluate the LLNL Radiation Safety Program and recommend actions to address the conditions identified in the Internal Assessment conducted July 23-25, 2007. This review confirms the findings of the Internal Assessment of the Institutional Radiation Safety Program (RSP) including the noted deficiencies and vulnerabilities to be valid. The actions recommended are a result of interviews with about 35 individuals representing senior management through the technician level. The deficiencies identified in the LLNL Internal Assessment of the Institutional Radiation Safety Program were discussed with Radiation Safety personnel team leads, customers of Radiation Safety Program, DOE Livermore site office, and senior ES&H management. There are significant issues with the RSP. LLNL RSP is not an integrated, cohesive, consistently implemented program with a single authority that has the clear roll and responsibility and authority to assure radiological operations at LLNL are conducted in a safe and compliant manner. There is no institutional commitment to address the deficiencies that are identified in the internal assessment. Some of these deficiencies have been previously identified and corrective actions have not been taken or are ineffective in addressing the issues. Serious funding and staffing issues have prevented addressing previously identified issues in the Radiation Calibration Laboratory, Internal Dosimetry, Bioassay Laboratory, and the Whole Body Counter. There is a lack of technical basis documentation for the Radiation Calibration Laboratory and an inadequate QA plan that does not specify standards of work. The Radiation Safety Program lack rigor and consistency across all supported programs. The implementation of DOE Standard 1098-99 Radiological Control can be used as a tool to establish this consistency across LLNL. The establishment of a site

  10. Safety and design in airplane construction

    Science.gov (United States)

    Teichmann, Alfred

    1934-01-01

    The author gives a survey of the principles of stress analysis and design of airplane structures, and discusses the fundamental strength specifications and their effect on the stress analysis as compared with the safety factors used in other branches of engineering.

  11. Concrete Strength for Fire Safety Design

    DEFF Research Database (Denmark)

    Hertz, Kristian Dahl

    2005-01-01

    Idealized data are derived for the compressive strength of a number of concretes for fire safety design. The data are derived from the authors own research including test series not published before and from more than 400 other test series comprising approximately 3000 specimens known from...

  12. Establishment of database for radiation exposure and safety assessment

    Energy Technology Data Exchange (ETDEWEB)

    Choi, G. S.; Kim, J. H. [Science Culture Research Institute, Seoul (Korea, Republic of)

    2005-12-15

    The nuclear electric energy in our country plays a major role for the national industrial development as well as for the secure living of the peoples. It is, however, considered as a socially dreadful elements because of the radiation materials exposed into the environment. In effect, the DB is intended to serve for the reference to the epidemical study upon the low-level radiation exposure involving the nuclear facilities, radio-isotope business enterprises, and the related workers at the radiation sites. In connection with the development of nuclear energy, the low-level radiation, associated with the radioisotope materials exposed into our environment out of nuclear facilities, is believed to possibly raise significant hazardous effects toward human persons. Therefor, it is necessary to take a positive counter measures by means of comprehensive quantitative estimates on its possibilities. In consequence, the low-level radiation effects do not bring about the immediate hazard cases, however, appear to possibly pose the lately caused diseases such as cancer cause, life reduction, and creation of mutation, etc. Therefore, it is intended to set up the social security with the secure safety, by conducting an advanced safety study on the low-level radiation.

  13. Safety design maps: an early evaluation of safety to support reactor design

    Energy Technology Data Exchange (ETDEWEB)

    Zanocco, P. E-mail: zanoccop@cab.cnea.gov.ar; Gimenez, M.; Delmastro, D

    2003-11-01

    A new tendency in nuclear reactor conceptual design is to include safety criteria through accident analysis to address the selection of the engineering solutions and the value of the main design parameters. In this work, the concept of design map is used to correlate reactor safety performance with the design parameters. The effect of different design parameters on characteristic safety variables, referred to as 'observable variables', extracted from reactor evolution during accidents, is analyzed, and the concept of 'safety design maps' is introduced. The sensitivity of these 'observables variables' regarding changes in design parameters is visualized. Several safety design maps are built from the performance of an integral type reactor during loss of heat sink (LOHS) and main steam line break sequences without SCRAM to show the technique potentiality. Maximum reactor pressure vessel (RPV) pressure and minimum departure from nucleate boiling ratio are chosen as 'observable variables' and their sensitivity to geometry-related parameters and reactivity coefficient is studied. Multiple-parameter single design maps and combined design maps for both accidental sequences are built as examples. The results show the usefulness of this technique to balance and optimize reactor design through an early engineering step. A computer code (HUARPE) has been developed in order to simulate these transients. The cooling circuit, the steam dome, the pressure vessel structures and core models are considered.

  14. Mars Radiation Risk Assessment and Shielding Design for Long-term Exposure to Ionizing Space Radiation

    Science.gov (United States)

    Tripathi, Ram K.; Nealy, John E.

    2007-01-01

    NASA is now focused on the agency's vision for space exploration encompassing a broad range of human and robotic missions including missions to Moon, Mars and beyond. As a result, there is a focus on long duration space missions. NASA is committed to the safety of the missions and the crew, and there is an overwhelming emphasis on the reliability issues for space missions and the habitat. The cost-effective design of the spacecraft demands a very stringent requirement on the optimization process. Exposure from the hazards of severe space radiation in deep space and/or long duration missions is a critical design constraint and a potential 'show stopper'. Thus, protection from the hazards of severe space radiation is of paramount importance to the agency's vision. It is envisioned to have long duration human presence on the Moon for deep space exploration. The exposures from ionizing radiation - galactic cosmic radiation and solar particle events - and optimized shield design for a swing-by and a long duration Mars mission have been investigated. It is found that the technology of today is inadequate for safe human missions to Mars, and revolutionary technologies need to be developed for long duration and/or deep space missions. The study will provide a guideline for radiation exposure and protection for long duration missions and career astronauts and their safety.

  15. Compendium of resources for radiation safety in medical imaging using ionizing radiation.

    Science.gov (United States)

    Minhas, Anum S; Frush, Donald P

    2013-05-01

    Diagnostic imaging, including ionizing radiation modalities, maintains a prominent role in the medical evaluation of patients. There is increasing awareness and need for information across varied sectors about low-level radiation and potential risks. Many medical and scientific organizations have resources discussing radiation risk and management. However, there is no single resource compiling this information. Websites, including those of national and international medical organizations, were reviewed for information on radiation dose, risk, justification, optimization, guidelines (including general information about improvement in quality and dose reduction without specific mention of optimization techniques), appropriateness criteria, and general principles of radiation safety for CT, fluoroscopy or angiography, and radiography. This information was organized into 8 tables, categorized by modality, and separated for adult and pediatric populations. Websites with training modules were noted as well. Twenty-nine websites were explored. Overall, less information is available about medical radiation safety in children compared with adults. Across both groups, most information is available on CT, then fluoroscopy, and finally radiography. Across all groups and modalities, there is no information available for patients or parents on optimization, appropriateness, or guidelines, with the exception of adult radiography, for which there are some guidelines. This compendium serves as a collective resource for communities including the public and regulatory organizations. Additionally, the compendium can be used to determine redundant or deficient areas, providing opportunities for more comprehensive resources and efficient efforts in accessing medical radiation patient safety information. Copyright © 2013 American College of Radiology. Published by Elsevier Inc. All rights reserved.

  16. Environmental radiation safety source term evaluation program

    Energy Technology Data Exchange (ETDEWEB)

    Moss, O.R.; Filipy, R.E.; Cannon, W.C.; Craig, D.K.

    1977-04-01

    Plutonium-238 is currently used in the form of a pure refractory oxide as a power source on a number of space vehicles that have already been or will be launched during the next few years. Although the sources are designed and built to withstand re-entry into the earth's atmosphere and impact with the earth's surface without releasing any plutonium, the possibility of such an event can never be absolutely excluded. Three separate tasks were undertaken in this study. The interactions between soils and /sup 238/PuO/sub 2/ aerosols which might be created in a space launch about environment were examined. Aging of the plutonium-soil mixture under a humid atmosphere showed a trend toward the slow coagulation of two dilute aerosols. Studies on marine animals were conducted to assess the response of /sup 238/PuO/sub 2/ pellets to conditions found 60 feet below the ocean surface. Ultrafilterability studies measured the solubility of /sup 238/PuO/sub 2/ as a function of time, temperature, suspension concentration and molality of solvent. (ACR)

  17. Update on radiation safety and dose reduction in pediatric neuroradiology.

    Science.gov (United States)

    Mahesh, Mahadevappa

    2015-09-01

    The number of medical X-ray imaging procedures is growing exponentially across the globe. Even though the overall benefit from medical X-ray imaging procedures far outweighs any associated risks, it is crucial to take all necessary steps to minimize radiation risks to children without jeopardizing image quality. Among the X-ray imaging studies, except for interventional fluoroscopy procedures, CT studies constitute higher dose and therefore draw considerable scrutiny. A number of technological advances have provided ways for better and safer CT imaging. This article provides an update on the radiation safety of patients and staff and discusses dose optimization in medical X-ray imaging within pediatric neuroradiology.

  18. Update on radiation safety and dose reduction in pediatric neuroradiology

    Energy Technology Data Exchange (ETDEWEB)

    Mahesh, Mahadevappa [Johns Hopkins University School of Medicine, The Russell H. Morgan Department of Radiology and Radiological Science, Baltimore, MD (United States)

    2015-09-15

    The number of medical X-ray imaging procedures is growing exponentially across the globe. Even though the overall benefit from medical X-ray imaging procedures far outweighs any associated risks, it is crucial to take all necessary steps to minimize radiation risks to children without jeopardizing image quality. Among the X-ray imaging studies, except for interventional fluoroscopy procedures, CT studies constitute higher dose and therefore draw considerable scrutiny. A number of technological advances have provided ways for better and safer CT imaging. This article provides an update on the radiation safety of patients and staff and discusses dose optimization in medical X-ray imaging within pediatric neuroradiology. (orig.)

  19. Delivering a radiation protection dividend: systemic capacity-building for the radiation safety profession in Africa

    Directory of Open Access Journals (Sweden)

    Julian Hilton

    2014-12-01

    Full Text Available Many African countries planning to enter the nuclear energy “family” have little or no experience of meeting associated radiation safety demands, whether operational or regulatory. Uses of radiation in medicine in the continent, whether for diagnostic or clinical purposes, are rapidly growing while the costs of equipment, and hence of access to services, are falling fast. In consequence, many patients and healthcare workers are facing a wide array of unfamiliar challenges, both operational and ethical, without any formal regulatory or professional framework for managing them safely. This, combined with heighted awareness of safety issues post Fukushima, means the already intense pressure on radiation safety professionals in such domains as NORM industries and security threatens to reach breaking point. A systematic competency-based capacity-building programme for RP professionals in Africa is required (Resolution of the Third AFRIRPA13 Regional Conference, Nairobi, September 2010. The goal is to meet recruitment and HR needs in the rapidly emerging radiation safety sector, while also addressing stakeholder concerns in respect of promoting and meeting professional and ethical standards. The desired outcome is an RP “dividend” to society as a whole. A curriculum model is presented, aligned to safety procedures and best practices such as Safety Integrity Level and Layer of Protection analysis; it emphasizes proactive risk communication both with direct and indirect stakeholders; and it outlines disciplinary options and procedures for managers and responsible persons for dealing with unsafe or dangerous behavior at work. This paper reports on progress to date. It presents a five-tier development pathway starting from a generic foundation course, suitable for all RP professionals, accompanied by specialist courses by domain, activity or industry. Delivery options are discussed. Part of the content has already been developed and delivered as

  20. Different design approaches to structural fire safety

    DEFF Research Database (Denmark)

    Giuliani, Luisa; Budny, I.

    2013-01-01

    Fire has always been a major threat for buildings and other structures, leadingto consequences that can affect both the safety of people and the usage or in some cases the very survival of constructions, due to collapse mechanisms induced by fire or fire effects.Aim of this paper is to highlight......-based fire design of the structure(PBFD), where safety goals are explicitly defined and a deeper knowledge of the structural response to fire effects can be achieved, for example with the avail of finite element analyses (FEA). On the other hand, designers can’t follow established procedures when undertaking...... with reference to one frame of the considered car park, outlining the most problematic aspects in the modelling and in the interpretation of the results and making a focus on the collapse mechanisms of steel frames such has catenary action and sway and non-sway collapse....

  1. Designing Radiation Resistance in Materials for Fusion Energy

    Science.gov (United States)

    Zinkle, S. J.; Snead, L. L.

    2014-07-01

    Proposed fusion and advanced (Generation IV) fission energy systems require high-performance materials capable of satisfactory operation up to neutron damage levels approaching 200 atomic displacements per atom with large amounts of transmutant hydrogen and helium isotopes. After a brief overview of fusion reactor concepts and radiation effects phenomena in structural and functional (nonstructural) materials, three fundamental options for designing radiation resistance are outlined: Utilize matrix phases with inherent radiation tolerance, select materials in which vacancies are immobile at the design operating temperatures, or engineer materials with high sink densities for point defect recombination. Environmental and safety considerations impose several additional restrictions on potential materials systems, but reduced-activation ferritic/martensitic steels (including thermomechanically treated and oxide dispersion-strengthened options) and silicon carbide ceramic composites emerge as robust structural materials options. Materials modeling (including computational thermodynamics) and advanced manufacturing methods are poised to exert a major impact in the next ten years.

  2. Preliminary Thermal Design of Cryogenic Radiation Shielding

    Science.gov (United States)

    Li, Xiaoyi; Mustafi, Shuvo; Boutte, Alvin

    2015-01-01

    Cryogenic Hydrogen Radiation Shielding (CHRS) is the most mass efficient material radiation shielding strategy for human spaceflight beyond low Earth orbit (LEO). Future human space flight, mission beyond LEO could exceed one year in duration. Previous radiation studies showed that in order to protect the astronauts from space radiation with an annual allowable radiation dose less than 500 mSv, 140 kgm2 of polyethylene is necessary. For a typical crew module that is 4 meter in diameter and 8 meter in length. The mass of polyethylene radiation shielding required would be more than 17,500 kg. The same radiation study found that the required hydrogen shielding for the same allowable radiation dose is 40 kgm2, and the mass of hydrogen required would be 5, 000 kg. Cryogenic hydrogen has higher densities and can be stored in relatively small containment vessels. However, the CHRS system needs a sophisticated thermal system which prevents the cryogenic hydrogen from evaporating during the mission. This study designed a cryogenic thermal system that protects the CHRS from hydrogen evaporation for one to up to three year mission. The design also includes a ground based cooling system that can subcool and freeze liquid hydrogen. The final results show that the CHRS with its required thermal protection system is nearly half of the mass of polyethylene radiation shielding.

  3. Radiation safety in sea transport of radioactive material in Japan

    Energy Technology Data Exchange (ETDEWEB)

    Odano, N. [National Maritime Research Inst., Tokyo (Japan); Yanagi, H. [Nuclear Fuel Transport Co., Ltd., Tokyo (Japan)

    2004-07-01

    Radiation safety for sea transport of radioactive material in Japan has been discussed based on records of the exposed dose of sea transport workers and measured data of dose rate equivalents distribution inboard exclusive radioactive material shipping vessels. Recent surveyed records of the exposed doses of workers who engaged in sea transport operation indicate that exposed doses of transport workers are significantly low. Measured distribution of the exposed dose equivalents inboard those vessels indicates that dose rate equivalents inside those vessels are lower than levels regulated by the transport regulations of Japan. These facts clarify that radiation safety of inboard environment and handling of transport casks in sea transport of radioactive material in Japan are assured.

  4. Creative Design of Double Safety Shoes Mechanisms

    Science.gov (United States)

    Cheng, Hong Yih

    This paper is to synthesize the double safety shoes mechanisms of elevators for prompting passenger's safety. A systematic design methodology including type synthesis and mechanism skeletons technology is also presented based on the design requirements and design constraints. The design requirements include to avoiding from collision between shoes, and shoe can be pulled out independently not to drag the door. The design constraints are proposed for assigning link types and kinematic relations. An existing mechanism, which is designed with six links and seven joints, is investigated by mechanism kinematics and structure sketch to establish the topological structure. According to the creative method, all of the possible kinematic chains with the numbers of the vertices and edges are enumerated. Then the linkage numbers are assigned skillfully to the edges, and one of the kinematic pairs, for example, revolute pair, prismatic pair, and rolling pair, is chosen for every vertices. So every kinematic chain can be stretched out several particularized chains. Several mechanism skeletons are also sketched.

  5. Radiation Safety Management Guidelines for PET-CT: Focus on Behavior and Environment

    Energy Technology Data Exchange (ETDEWEB)

    Jung, Jin Wook [Cancer Imaging Center, National University Cancer Hospital, Seoul (Korea, Republic of); Han, Eun Ok [Dept. of Radiological Technology, Daegu Health College, Seoul (Korea, Republic of)

    2011-09-15

    Our purpose is to specify behavior and environmental factors aimed at reducing the exposed dosage caused by PET-CT and to develop radiation safety management guidelines adequate for domestic circumstances. We have used a multistep-multimethod as the methodological approach to design and to carry out the research both in quality and quantity, including an analysis on previous studies, professional consultations and a survey. The survey includes responses from 139 practitioners in charged of 109 PET-CTs installed throughout Korea(reported by the Korean Society of Nuclear Medicine, 2010). The research use 156 questions using Cronbach's {alpha} (alpha) coefficients which were: 0.818 for 'the necessity of setting and installing the radiation protective environment'; 0.916 for 'the necessity of radiation protection', 'setting and installing the radiation protective environment'; and 0.885 for 'radiation protection'. The check list, derived from the radiation safety management guidelines focused on behavior and environment, was composed of 20 items for the radiation protective environment: including 5 items for the patient; 4 items for the guardian; 3 items for the radiologist; and 8 items applied to everyone involved; for a total of 26 items for the radiation protective behavior including: 12 items for the patient; 1 item for the guardian, 7 items for the radiologist; and 6 items applied to everyone involved. The specific check list is shown in (Table 5-6). Since our country has no safety management guidelines of its own to reduce the exposed dosage caused by PET-CTs, we believe the guidelines developed through this study means great deal to the field as it is not only appropriate for domestic circumstances, but also contains specific check lists for each target who may be exposed to radiation in regards to behavior and environment.

  6. Safety and Radiation Protection at Swedish Nuclear Power Plants 2007

    Energy Technology Data Exchange (ETDEWEB)

    2008-07-01

    The safety level of the plants is maintained at an acceptable level. SKI has in its regulatory supervision not found any known deficiencies in the barriers which could result in release of radioactive substances in excess of the permitted levels. SKI considers that improvements have been implemented during the year in the management, control and following up of safety work at the plants. In some cases, SKI has imposed requirements that improvements be made. Extensive measures are under way at the nuclear power plants to comply with the safety requirements in SKI's regulations, SKIFS 2004:2 concerning the design and construction of nuclear power reactors, and the stricter requirements regarding physical protection. Concurrently preparations are underway at eight of the ten units for thermal power increases. At the Forsmark plant considerable efforts have been during the year to correct the deficiencies in the safety culture and quality assurance system that became apparent in 2006. A programme to improve the execution of activities has been established in accordance with SKI's decision. SKI considers that the plant has developed in a positive direction but that there are further possibilities for improvement with regard to internal control. This is amongst other things concerns the areas internal auditing, independent safety review function, and working methods. SKI has had special supervision of the plant since 28 September, 2006. At the Oskarshamn plant work has been carried out to improve the organisation and routines in several areas. The plant has established routines which provide the basis to ensure that decisions are taken in a stringent manner. The quality assurance system has a clearer structure and there is a better defined division of work. Some measures remain to be dealt with in 2008. The Ringhals plant has also worked with attitudes to routines and internal control. SKI considers that the measures have good prerequisites to provide a

  7. Laser sources in dentistry and radiation safety regulations

    Science.gov (United States)

    De Luca, D.; Gaeta, G. M.; Lepore, M.

    2007-02-01

    Nowadays laser sources are largely adopted in dentistry due to their unique properties making them good candidates to substitute traditional scalpel and conventional diamond bur in the surgery of the soft and hard oral tissue, respectively. The large use of laser sources outside the research laboratories without the need of highly specialized personnel can ask for a widespread knowledge of safety issues related to this kind of equipment. The main hazard of accidental exposures regards eyes injury but increasing the power of the laser beam also skin can be involved. Safety legislations in Europe and U.S.A. take into account non ionizing radiations and laser radiation for the hazards for the health deriving from physical agents. Laser safety standards introduce 3 useful parameters for hazard characterization: "Accessible Emission Limit" (AEL), "Maximum Permissible Exposure" (MPE) and "Nominal Ocular Hazard Distance" (NOHD). We measured the MPE and NOHD for Er:YAG and other laser sources currently adopted in dentistry and we compared our results with data elaborated from standards in order to single out safe and comfortable working conditions. In fact an experimental assessment of the hazard parameters and the comparison with those of reference from safety standards turns out to be useful in order to estimate the residual hazard that can be still present after applying all the engineering protection and administrative rules.

  8. A study on radiation shielding and safety analysis for a synchrotron radiation beamline

    Energy Technology Data Exchange (ETDEWEB)

    Asano, Yoshihiro [Japan Atomic Energy Research Inst., Kansai Research Establishment, Synchrotron Radiation Research Center, Mikazuhi, Hyogo (Japan)

    2001-03-01

    Methods of shielding design and safety analysis are presented for a beam-line of synchrotron radiation. This paper consists of the shielding and safety study of synchrotron radiation with extremely intense and low energy photon below several hundreds keV, and the study for the behavior of remarkable high-energy photons up to 8 GeV, which can creep into beam-lines. A new shielding design code, STAC8 was developed to estimate the leakage dose outside the beam line hutch (an enclosure of the beam, optical elements or experimental instruments) easily and quickly with satisfactory accuracy. The code can calculate consistently from sources of synchrotron radiation to dose equivalent outside hutches with considering the build up effect and polarization effect. Validity of the code was verified by comparing its calculations with those of Monte Carlo simulations and measurement results of the doses inside the hutch of the BL14C of Photon Factory in the High Energy Accelerator Research Organization (KEK), showing good agreements. The shielding design calculations using STAC8 were carried out to apply to the practical beam-lines with the considering polarization effect and clarified the characteristics of the typical beam-line of the third generation synchrotron radiation facility, SPring-8. In addition, the shielding calculations were compared with the measurement outside the shield wall of the bending magnet beam-line of SPring-8, and showed fairly good agreement. The new shielding problems, which have usually been neglected in shielding designs for existing synchrotron radiation facilities, are clarified through the analysis of the beam-line shielding of SPring-8. The synchrotron radiation from the SPring-8 has such extremely high-intensity involving high energy photons that the scattered synchrotron radiation from the concrete floor of the hutch, the ground shine, causes a seriously high dose. The method of effective shielding is presented. For the estimation of the gas

  9. A Study on Enhancement of Understanding of Radiation and Safety Management

    Energy Technology Data Exchange (ETDEWEB)

    Yoo, Dong Han; Park, Ji Young; Lee, Jae Uk; Bae, Jun Woo; Kim, Hee Reyoung [Ulsan National Institute of Science and Technology, Ulsan (Korea, Republic of)

    2014-10-15

    Concerns for radiation exposure have been increased from small and big radiation works or experiments with radiation generator (RG) or radiation isotopes (RI) at institutions using radiation in Korea. Actually, due to radiation exposure occurred on the process of handling RI, etc., The exposure should be maintained as low as reasonably possible. To do this, above all, suitable training and establishment of safety culture have to be preceded. In this respect, an education institution is a place where people learn first about handling radiations in various specialties with purposes including academic research, and the first learned habits and practices acts as the basis for safety management of radiation when they continue to do radiation work after going into the society. Hereford, it is needed to establish the right safety culture on radiation for its safe managing. In the present study, the direction for the right understandings and safety improvement are suggested through the radiation survey on education institutions and preparation of safety guidances for users. The basic guidance at the radiation experiment was prepared for the right understanding of the radiation to prevent radiation accidents from careless handling by workers based on the surveyed results for education institutions. It is expected to be used as fundamentals for improvement for radiation safety management of workers and researchers and, further, safety policy for national nuclear energy and radiations.

  10. Reduction of adult fingers visualized on pediatric intensive care unit (PICU) chest radiographs after radiation technologist and PICU staff radiation safety education

    Energy Technology Data Exchange (ETDEWEB)

    Tynan, J.R.; Duncan, M.D.; Burbridge, B.E., E-mail: jentynan@hotmail.com [Univ. of Saskatchewan, Royal Univ. Hospital, Dept. of Medical Imaging, Saskatoon, Saskatchewan (Canada)

    2009-10-15

    A recent publication from our centre revealed a disturbing finding of a significant incidence of adult fingers seen on the pediatric intensive care unit (PICU) chest radiographs. This is inappropriate occupational exposure to diagnostic radiation. We hypothesized that the incidence of adult fingers on PICU chest radiographs would decline after radiation safety educational seminars were given to the medical radiation technologists and PICU staff. The present study's objectives were addressed by using a pretest-posttest design. Two cross-sectional PICU chest radiograph samples, taken before and after the administration of radiation safety education for our medical radiation technologists and PICU staff, were compared by using a {chi}{sup 2} test. There was a 61.2% and 76.9% reduction in extraneous adult fingers, directly exposed to the x-ray beam and those seen in the coned regions of the film, respectively, on PICU chest radiographs (66.7% reduction overall). This reduction was statistically significant ({chi}2 = 20.613, P < .001). Limiting unnecessary occupational radiation exposure is a critical issue in radiology. There was a statistically and clinically significant association between radiation safety education and the decreased number of adult fingers seen on PICU chest radiographs. This study provides preliminary evidence in favour of the benefit of radiation safety seminars. (author)

  11. Radiation safety analysis of the ISS bone densitometer

    Science.gov (United States)

    Todd, Paul; Vellinger, John C.; Barton, Kenneth; Faget, Paul

    A Bone Densitometer (BD) has been developed for installation on the International Space Station (ISS) with delivery by the Space-X Dragon spacecraft planned for mid 2014. After initial tests on orbit the BD will be used in longitudinal measurements of bone mineral density in experimental mice as a means of evaluating countermeasures to bone loss. The BD determines bone mineral density (and other radiographic parameters) by dual energy x-ray absorptiometry (DEXA). In a single mouse DEXA “scan” its 80 kV x-ray tube is operated for 15 seconds at 35 kV and 3 seconds at 80 kV in four repetitions, giving the subject a total dose of 2.5 mSv. The BD is a modification of a commercial mouse DEXA product known as PIXImus(TM). Before qualifying the BD for utilization on ISS it was necessary to evaluate its radiation safety features and any level of risk to ISS crew members. The BD design reorients the PIXImus so that it fits in an EXPRESS locker on ISS with the x-ray beam directed into the crew aisle. ISS regulation SSP 51700 considers the production of ionizing radiation to be a catastrophic-level hazard. Accidental exposure is prevented by three independent levels of on-off control as required for a catastrophic hazard. The ALARA (As Low as Reasonably Achievable) principle was applied to the BD hazard just as would be done on the ground, so deliberate exposure is limited by lead shielding according to ALARA. Hot spots around the BD were identified by environmental dosimetry using a Ludlum 9DP pressurized ionization chamber survey meter. Various thicknesses of lead were applied to the BD housing in areas where highest dose-per-scan readings were made. It was concluded that 0.4 mm of lead shielding at strategic locations, adding only a few kg of mass to the payload, would accomplish ALARA. With shielding in place the BD now exposes a crew member floating 40 cm away to less than 0.08 microSv per mouse scan. There is an upper limit of 20 scans per day, or 1.6 microSv per day

  12. Physics design of SSRF synchrotron radiation security

    Institute of Scientific and Technical Information of China (English)

    XU Yi; DAI Zhi-Min; LIU Gui-Min

    2009-01-01

    High brightness of SSRF brings about synchrotron radiation security problems,which will be solved in physics design.The main radiations are generated from bending magnets and insertion devices.Since the fact that radiation power and radiating area are different in these two kinds of synchrotron radiation,the arrangements of photon absorbers,diaphragms and other vacuum components need to be treated distinctively.In addition.SSRF interlock protection threshold is defined and the beam orbit in the straight line is limited.Hence.beam orbit in the bending magnets and IDs are also restricted by the threshold.The orbit restriction is calculated and helps us to arrange the vacuum components.In this paper,beam orbit distortion restricted by interlock protection threshold,radiation power,radiation angle and illuminating area are calculated.From the calculation results,the physics designs in manufacture and installation vacuum components are put forward.By commissioning,it is shown that physics requirements are met rigidly in the engineering process.

  13. Reinforcement Data for Fire Safety Design

    DEFF Research Database (Denmark)

    Hertz, Kristian Dahl

    2004-01-01

    for the deterioration of the materials when they are heated and cooled down. A simple expression is established for the description of deterioration curves for fire-exposed materials such as concrete and reinforcement by means of 5 parameters, which may be used as input data for structural fire safety calculations...... instead of the more troublesome application of curves or tables. This new idealized representation is compared with test data and with other idealized curves for the materials presented, and recommended design values are given. Warnings are given for misleading curves and expressions from the structural...

  14. Importance of Bladder Radioactivity for Radiation Safety in Nuclear Medicine

    Directory of Open Access Journals (Sweden)

    Salih Sinan Gültekin

    2013-12-01

    Full Text Available Objective: Most of the radiopharmaceuticals used in nuclear medicine are excreted via the urinary system. This study evaluated the importance of a reduction in bladder radioactivity for radiation safety. Methods: The study group of 135 patients underwent several organ scintigraphies [40/135; thyroid scintigraphy (TS, 30/135; whole body bone scintigraphy (WBS, 35/135; myocardial perfusion scintigraphy (MPS and 30/135; renal scintigraphy (RS] by a technologist within 1 month. In full and empty conditions, static bladder images and external dose rate measurements at 0.25, 0.50, 1, 1.5 and 2 m distances were obtained and decline ratios were calculated from these two data sets. Results: External radiation dose rates were highest in patients undergoing MPS. External dose rates at 0.25 m distance for TS, TKS, MPS and BS were measured to be 56, 106, 191 and 72 μSv h-1 for full bladder and 29, 55, 103 and 37 μSv h-1 for empty bladder, respectively. For TS, WBS, MPS and RS, respectively, average decline ratios were calculated to be 52%, 55%, 53% and 54% in the scintigraphic assessment and 49%, 51%, 49%, 50% and 50% in the assessment with Geiger counter. Conclusion: Decline in bladder radioactivity is important in terms of radiation safety. Patients should be encouraged for micturition after each scintigraphic test. Spending time together with radioactive patients at distances less than 1 m should be kept to a minimum where possible.

  15. A novel radiation hardened by design latch

    Institute of Scientific and Technical Information of China (English)

    Huang Zhengfeng; Liang Huaguo

    2009-01-01

    Due to aggressive technology scaling, radiation-induced soft errors have become a serious reliability concern in VLSI chip design. This paper presents a novel radiation hardened by design latch with high single-event-upset (SEU) immunity. The proposed latch can effectively mitigate SEU by internal dual interlocked scheme. The propagation delay, power dissipation and power delay product of the presented latch are evaluated by detailed SPICE simulations. Compared with previous SEU-hardening solutions such as TMR-Latch, the presented latch is more area efficient, delay and power efficient. Fault injection simulations also demonstrate the robustness of the presented latch even under high energy particle strikes.

  16. Shielding Design and Radiation Shielding Evaluation for LSDS System Facility

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Younggook; Kim, Jeongdong; Lee, Yongdeok [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-05-15

    As the system characteristics, the target in the spectrometer emits approximately 1012 neutrons/s. To efficiently shield the neutron, the shielding door designs are proposed for the LSDS system through a comparison of the direct shield and maze designs. Hence, to guarantee the radiation safety for the facility, the door design is a compulsory course of the development of the LSDS system. To improve the shielding rates, 250x250 covering structure was added as a subsidiary around the spectrometer. In this study, the evaluations of the suggested shielding designs were conducted using MCNP code. The suggested door design and covering structures can shield the neutron efficiently, thus all evaluations of all conditions are satisfied within the public dose limits. From the Monte Carlo code simulation, Resin(Indoor type) and Tungsten(Outdoor type) were selected as the shielding door materials. From a comparative evaluation of the door thickness, In and Out door thickness was selected 50 cm.

  17. An approach to radiation safety department benchmarking in academic and medical facilities.

    Science.gov (United States)

    Harvey, Richard P

    2015-02-01

    Based on anecdotal evidence and networking with colleagues at other facilities, it has become evident that some radiation safety departments are not adequately staffed and radiation safety professionals need to increase their staffing levels. Discussions with management regarding radiation safety department staffing often lead to similar conclusions. Management acknowledges the Radiation Safety Officer (RSO) or Director of Radiation Safety's concern but asks the RSO to provide benchmarking and justification for additional full-time equivalents (FTEs). The RSO must determine a method to benchmark and justify additional staffing needs while struggling to maintain a safe and compliant radiation safety program. Benchmarking and justification are extremely important tools that are commonly used to demonstrate the need for increased staffing in other disciplines and are tools that can be used by radiation safety professionals. Parameters that most RSOs would expect to be positive predictors of radiation safety staff size generally are and can be emphasized in benchmarking and justification report summaries. Facilities with large radiation safety departments tend to have large numbers of authorized users, be broad-scope programs, be subject to increased controls regulations, have large clinical operations, have significant numbers of academic radiation-producing machines, and have laser safety responsibilities.

  18. Design and Realization of the Safety Production Scheduling System

    Directory of Open Access Journals (Sweden)

    Qiang Fan

    2013-01-01

    Full Text Available In this study, we have a research of the design and realization of the Safety Production Scheduling System. Urged by the government departments as well as safety supervising institutions, many coal enterprises are embarking on designing and constructing an information system platform for safety production and scheduling. How to establish a systematic, comprehensive, standardized and scientific management platform for the safety production and scheduling has become a hot issue in the coal industry, which is also an important move to integrate various safety management measures in order to prevent major safety accidents and keep up with the international industry status. Taking a successful, large-scale safety production and scheduling system for example, this study elaborates on its overall design and construction. When the system is completed, it will play an important role in strengthening safety production of the coal mines, preventing accidents as well as increasing the overall safety level of the coal industry.

  19. Safety Analysis Report for Primary Capsule of Ir-192 Radiation Source

    Energy Technology Data Exchange (ETDEWEB)

    Lee, J. C.; Bang, K. S.; Choi, W. S.; Seo, K. S.; Son, K. J.; Park, W. J

    2008-12-15

    All of the source capsules to transport a special form radioactive material should be designed and fabricated in accordance with the design criteria prescribed in IAEA standards and domestic regulations. The objective of this project is to prove the safety of a primary capsule for Ir-192 radiation source which produced in the HANARO. The safety tests of primary capsules were carried out for the impact, percussion and heat conditions. And leakage tests were carried out before and after the each tests. The capsule showed slight scratches and their deformations were not found after each tests. It also met the allowable limits of leakage rate after each test. Therefore, it has been verified that the capsule was designed and fabricated to meet all requirements for the special form radioactive materials.

  20. Design considerations for a ceramic fabric radiator

    Energy Technology Data Exchange (ETDEWEB)

    Pauley, K.A.; Webb, B.J. (Pacific Northwest Lab., Richland, WA (USA)); Klein, A.C. (Oregon State Univ., Corvallis, OR (USA). Dept. of Nuclear Engineering)

    1990-04-01

    The design of an Advanced Ceramic Fabric (ACF) thermal management device for use in both interplanetary and near-earth space must consider several important aspects of the environment. First, the radiation field at various locations is dominated by a proton component which deposits its energy on the surface of the device. Second, the ACF materials, as well as pressure liner materials, must also be compatible with the working fluids selected for the system. Third, the fluid dynamics and heat transfer characteristics of this device should be adequately characterized. With the proper consideration of materials and operating conditions, the Bubble Membrane Radiator (BMR) may be utilized for several advanced space missions. 17 refs.

  1. Design of Safety Injection Tanks Using Axiomatic Design and TRIZ

    Energy Technology Data Exchange (ETDEWEB)

    Heo, Gyunyoung [Kyung Hee University, 1 Seocheon-dong, Giheung-gu, Yongin-si, Gyeonggi-do, 446-701 (Korea, Republic of); Jeong, Yong Hoon [Korea Advanced Institute of Science and Technology, 373-1 Guseong-dong, Yuseong-gu, Daejeon, 305-701 (Korea, Republic of)

    2008-07-01

    Design can be categorized into two steps: 'synthesis' and 'analysis'. While synthesis is the process of decision-making on design parameters, analysis is the process of optimizing the parameters selected. It is known from experience that the mistakes made in the synthesis process are hardly corrected in the analysis process. 'Systematic synthesis' is, therefore, easy to overlook but an important topic. 'Systematic' is interpreted as 'minimizing' uncertainty and subjectivity. This paper will introduce the design product achieved by using Axiomatic Design (AD) and TRIZ (Theory of Inventive Problem Solving romanized acronym for Russian), which is a new design of Safety Injection Tank (SIT). In designing a large-capacity SIT which should play an important role in mitigating the large break loss of coolant accidents, there are three issues: 1) the excessively large plenum for pressurized nitrogen gas; 2) the difficulties maintaining the high initial injection flow rate; and 3) the non-condensable nitrogen gas in the coolant. This study proposes a conceptual idea for SITs that are pressurized by the chemical reaction of solid propellants. The AD theory and the principles of TRIZ enable new approach in problem-solving for those three issues in an innovative way. The paper made an effort to clarify the systematic synthesis process to reach the final design solution. (authors)

  2. ENSURING RADIATION SAFETY AT THE XXVII WORLD SUMMER UNIVERSIADE IN KAZAN BY ROSPOTREBNADZOR BODIES AND ORGANIZATIONS. Сommunication 2. Ensuring radiation safety during the universiade

    Directory of Open Access Journals (Sweden)

    G. G. Onischenko

    2013-01-01

    Full Text Available In the second communication, the authors present and analyze in detail in chronological order all the activities performed in the course of providing radiation safety of the XXVII World Summer Universiade in Kazan. Special attention is given to assessing the effectiveness of the measures envisaged and implemented. Recommendations to improve the planning system have been developed, the list of measures ensuring radiation safety of the participants and guests to be held before and during large-scale events to ensure radiation safety was specified.

  3. Radiation and Nuclear Safety Authority (STUK) - History 1958-2008; Saeteilyturvakeskuksen historia 1958-2008

    Energy Technology Data Exchange (ETDEWEB)

    Hoffman, K.

    2008-07-01

    The publication is the 50th anniversary book of the Radiation and Nuclear Safety Authority (STUK). The organisation was founded in 1958 by the name Saeteilyfysiikan laitos (The Institute of Radiation Physics). The first duties were to inspect x-ray machines and machines used for radiation therapy in hospitals. The activities were started by six persons but were quickly widened and in the end of 1970's the institute employed more than 100 experts, who supervised nuclear power plants, radiation devices, radioactivity in the environment, and the radiation safety of miners. The present name Saeteilyturvakeskus - the Radiation and Nuclear Safety Authority (STUK) was given in 1984. Today STUK is the Finnish national regulatory authority in radiation and nuclear safety fields, research centre and organisation providing radiation related services. STUK employs about 350 experts

  4. Report for spreading culture of medical radiation safety in Korea: Mainly the activities of the Korean alliance for radiation safety and culture in medicine (KARSM)

    Energy Technology Data Exchange (ETDEWEB)

    Yoon, Yong Su; Kim, Jung Min; Kim, Ji Hyun; Choi, In Seok [Dept. of Radiologic Science, Korea University, Seoul (Korea, Republic of); Sung, Dong Wook [Dept. of Radiology, Kyunghee University Hospital, Seoul (Korea, Republic of); Do, Kyung Hyun [Dept. of Radiology, University of Ulsan College of Medicine, Asan Medical Center, Seoul (Korea, Republic of); Jung, Seung Eun [Dept. of Radiology, College of Medicine, The Catholic University of Korea, Seoul (Korea, Republic of); Kim, Hyung Soo [Dept. of Radiation Safety, National Institute of Food and Drug Safety Evaluation, Korea Food and Drug Administration, Seoul (Korea, Republic of)

    2013-09-15

    There are many concerns about radiation exposure in Korea after Fukushima Nuclear Plant Accident on 2011 in Japan. As some isotope materials are detected in Korea, people get worried about the radioactive material. In addition, the mass media create an air of anxiety that jump on the people’s fear instead of scientific approach. Therefore, for curbing this flow, health, medical institute from the world provide a variety of information about medical radiation safety and hold the campaign which can give people the image that medical radiation is safe. At this, the Korean Food and Drug Administration(KFDA) suggested that make the alliance of medical radiation safety and culture on August, 2011. Seven societies and institutions related medical radiation started to research and advertise the culture of medical radiation safety in Korea. In this report, mainly introduce the activities of the Korean Alliance for Radiation Safety and Culture in Medicine(KARSM) for spreading culture of medical radiation safety from 2011 to 2012.

  5. Radiation Safety Professional Certification Process in a Multi-Disciplinary Association

    Energy Technology Data Exchange (ETDEWEB)

    Wilson, G.; Jones, P.; Ilson, R.

    2004-07-01

    There is no one set of criteria that defines the radiation safety professional in Canada. The many varied positions, from university and medical to industry and mining, define different qualifications to manage radiation safety programs. The national regulatory body has to assess many different qualifications when determining if an individual is acceptable to be approved for the role of radiation safety officer under any given licence. Some professional organizations specify education requirements and work experience as a prerequisite to certification. The education component specifies a degree of some type but does not identify specific courses or competencies within that degree. This could result in individuals with varying levels of radiation safety experience and training. The Canadian Radiation Protection Association (CRPA), responding to a need identified by the membership of the association, has initiated a process where the varying levels of knowledge of radiation safety can be addressed for radiation safety professionals. By identifying a core level set of radiation safety competencies, the basic level of radiation safety officer for smaller organizations can be met. By adding specialty areas, education can be pursued to define the more complex needs of larger organizations. This competency based process meets the needs of licensees who do not require highly trained health physicists in order to meet the licensing requirements and at the same time provides a stepping stone for those who wish to pursue a more specialized health physics option. (Author) 8 refs.

  6. Safety and security aspects in design of digital safety I and C in nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Ding, Yongjian [University of Applied Sciences Magdeburg-Stendal, Magdeburg (Germany). Inst. of Electrical Engineering; Waedt, Karl [Areva GmbH, Erlangen (Germany). PEAS-G

    2016-05-15

    The paper describes a safety objective oriented systematic design approach of digital (computerized) safety I and C in modern nuclear power plants which considers the plant safety requirements as well as cybersecurity needs. The defence in depth philosophy is applied by using different defence lines in the I and C architecture and protection zones in the plant IT environment.

  7. Safety Issues for HIFU Transducer Design

    Science.gov (United States)

    Fleury, Gérard; Berriet, Rémi; Chapelon, Jean Yves; ter Haar, Gail; Lafon, Cyril; Le Baron, Olivier; Chupin, Laurent; Pichonnat, Fabrice; Lenormand, Jérôme

    2005-03-01

    In contrast with most ultrasound modalities for medical applications, (especially ultrasound imaging), High Intensity Focused Ultrasound (HIFU) involves technologies and procedures which may present risk to the patient. These risks, resulting from the high power levels required for effective therapy, should be taken into account at the earliest stages in the design of a system dedicated to HIFU treatment. An understanding of these risks must thus be shared amongst the many players in the field of therapy using high power ultrasound. Moreover, since the number of applications of HIFU has increased appreciably over recent years and the technology is ready to move from the research to the industrial level, it is worth now considering solutions that should be put in place to guarantee the safety of the patient during HIFU treatment. This paper reports thoughts on this, identifies some risks to the patient that must be taken into consideration in the design of HIFU transducers, and proposes some solutions that could prevent the deleterious consequences of transducer misuse or failure. For the main risks identified, such as exceeding the desired acoustic power or poor control of tissue targeting, a description of transducer performance that could potentially result in problems is systematically sought. This allows proposals for precautions to be taken during operation to be made. Parameters which should be monitored to ensure safe use are also suggested. This type of approach, which should be undertaken for the different components of a therapeutic system, highlights the challenges that must be faced in the immediate future for the development and safe exploitation of HIFU systems. The necessity for standard definitions of the parameters to be checked or monitored during HIFU treatments is crucial in this approach, as is the availability of reliable dedicated measurement devices. Co-ordinated action on these topics in the HIFU community would contribute to the

  8. Safety Evaluation for the Design of Non-Safety Class Diesel Generator in KJRR

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Hagtae; Kim, Jun-Yeon; Chae, Hee-Taek [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-10-15

    The power supply plan and safety evaluation for the safety systems of the KJRR is proposed in this paper to design the non-safety class DG. In the KJRR, there are several safety systems that need Class 1E power in accordance with the functional requirement. A Diesel Generator (DG) is an important emergency electrical system that supplies electrical power to essential non-uninterruptible loads. In the KIJANG Research Reactor (KJRR), the safety class DG is considered an emergency electrical system in the initial stage of the conceptual design, but is not applied due to the cost increase for the manufacturing and qualification of a new small capacity DG. A power supply plan for safety systems including Engineered Safety Features (ESF) is proposed, and the safety of the research reactor is evaluated in this paper to design the non-safety class DG for the KJRR. Among the emergency electrical systems of the KJRR, the power source for Class 1E power is only the safety class DC power supply and UPS system, because the DG is designed as a non-safety class. Therefore, safety systems receive Class 1E power from the DC power supply and UPS system. The capacity of the DC power supply and UPS system is determined to be 1 hour by considering the operating time of the SRHRS pump that operates for the longest time when a DBA including a LOEP happens. This means that the Class 1E power can be supplied to safety systems that need Class 1E power without the safety class DG. The results of this paper show that the non-safety class DG does not adversely affect the safety of the KJRR.

  9. Radiation safety issues in the water treatment plant - Indoor radon and gamma radiation

    Energy Technology Data Exchange (ETDEWEB)

    Jantsikene, A.; Kiisk, M.; Suursoo, S.; Koch, R. [University of Tartu, Institute of Physics (Estonia); Lumiste, L. [Tallinn University of Technology, Department of Chemical Engineering (Estonia)

    2014-07-01

    the second stage filters, classifying them as radioactive material. {sup 222}Rn activity generated in the filter columns was compared to {sup 222}Rn activity entering the plant with raw water; the latter was estimated via liquid scintillation technique. The results indicate that {sup 222}Rn inflow is insignificant compared to the {sup 222}Rn generation in the columns. The estimated difference is in six orders of magnitude. Six alpha-track detectors were placed inside the treatment plant (in filter hall and working rooms) for measuring {sup 220}Rn and {sup 222}Rn indoor air concentrations. The obtained results are above 200 Bq/m{sup 3}. According to the Estonian Standard EVS 840:2009 'Design of radon-safe buildings', the annual radon concentration in living-, rest- and workrooms should remain below 200 Bq/m{sup 3}. The implemented investigation presented in this paper reveals the importance of monitoring radiation safety of the workers of this water treatment plant. Document available in abstract form only. (authors)

  10. Developments of radiation safety requirements for the management of radiation devices

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Hee Seock [Pohang Accelerator Lab, Pohang (Korea, Republic of); Choi, Jin Ho [Gachun University of Medicine and science, Incheon (Korea, Republic of); Cheong, Yuon Young [Asan Medical Center, Seoul (Korea, Republic of)] (and others)

    2002-03-15

    The approach of the risk-informed regulatory options was studied to develop the radiation safety requirements for the managements for radiation devices. The task analysis, exposure, accident scenario development, risk analysis, and systematic approach for regulatory options was considered in full, based on the NRC report, 'NUREG/CR-6642', and the translation of its core part was conducted for ongoing research. In this methodology, the diamond tree that includes human factors, etc, additionally with normal event tree, was used. According to the analysis results of this approach, the risk analysis and the development of regulatory options were applied for the electron linear accelerators and the qualitative results were obtained. Because the field user groups were participated in this study could contribute to the basis establishment of the risk-informed regulation policy through securing consensus and inducing particle interests. It will make an important role of establishing the detail plan of ongoing research.

  11. Defining Design Limits of a Portable Radiation Dispersion Prevention System

    Energy Technology Data Exchange (ETDEWEB)

    Kang Seong Woo; Yim, Man Sung [KAIST, Daejeon (Korea, Republic of)

    2016-05-15

    To the eyes of the general public, however, reducing the chance of such accident is not enough. A typical engineer views a risk as a combination of both consequences and likelihoods, whereas an ordinary person may only consider consequences. The implementations of better regulations, improved human operator actions, and installations of extra safety systems may reduce the chance of having uncontrolled accident practically to zero, yet the public still fears having nuclear reactors. One such barrier system is a portable suction-based radiation dispersion prevention system, called Integrated Portable Suction-Centrifugal Filtration System (IPS-CFS). To design such systems, detailed information about the radioactive source term at the release point to the environment must be available to draw design limits. The preliminary design limits of the IPS-CFS are presented in this paper. It may seem challenging to design a comprehensive radioactive dispersion system that can successfully prevent such extreme accident conditions, especially due to the releases from high pressure. However, as more technologies develop and more realistic source term analyses are performed, it may be possible to develop such a public relief technology. With the development of such technology that can effectively prevent the dispersion of the uncontrolled radioactive releases in case of another Fukushima-like accident, it will result in increased safety of the nuclear power plants for both the public and the workers and may contribute to the increase in the public acceptance of nuclear energy.

  12. Innovative machine designs for radiation processing

    Science.gov (United States)

    Vroom, David

    2007-12-01

    In the 1990s Raychem Corporation established a program to investigate the commercialization of several promising applications involving the combined use of its core competencies in materials science, radiation chemistry and e-beam radiation technology. The applications investigated included those that would extend Raychem's well known heat recoverable polymer and wire and cable product lines as well as new potential applications such as remediation of contaminated aqueous streams. A central part of the program was the development of new accelerator technology designed to improve quality, lower processing costs and efficiently process conformable materials such at liquids. A major emphasis with this new irradiation technology was to look at the accelerator and product handling systems as one integrated, not as two complimentary systems.

  13. Occupant safety design approaches using physical testing and numerical simulation.

    NARCIS (Netherlands)

    Linzmaier, L.C.; Carvalho, J.R.; Benar, M.; Vilela, D.; Altamore, P.

    2001-01-01

    The vehicle design environment from a crashworthiness and safety perspective has become increasingly complex in recent years. New legal requirements imposed by the European Union (EU) and the United States National Highway Traffic Safety Administration (NHTSA) have created a design space of great

  14. Occupant safety design approaches using physical testing and numerical simulation.

    NARCIS (Netherlands)

    Linzmaier, L.C.; Carvalho, J.R.; Benar, M.; Vilela, D.; Altamore, P.

    2001-01-01

    The vehicle design environment from a crashworthiness and safety perspective has become increasingly complex in recent years. New legal requirements imposed by the European Union (EU) and the United States National Highway Traffic Safety Administration (NHTSA) have created a design space of great co

  15. Neuro-oncology update: radiation safety and nursing care during interstitial brachytherapy

    Energy Technology Data Exchange (ETDEWEB)

    Randall, T.M.; Drake, D.K.; Sewchand, W.

    1987-12-01

    Radiation control and safety are major considerations for nursing personnel during the care of patients receiving brachytherapy. Since the theory and practice of radiation applications are not part of the routine curriculum of nursing programs, the education of nurses and other health care professionals in radiation safety procedures is important. Regulatory agencies recommend that an annual safety course be given to all persons frequenting, using, or associated with patients containing radioactive materials. This article presents pertinent aspects of the principles and procedures of radiation safety, the role of personnel dose-monitoring devices, and the value of additional radiation control features, such as a lead cubicle, during interstitial brain implants. One institution's protocol and procedures for the care of high-intensity iridium-192 brain implants are discussed. Preoperative teaching guidelines and nursing interventions included in the protocol focus on radiation control principles.

  16. The knowledge, attitude and behavior on the radiation safety management for dental hygiene major students

    Energy Technology Data Exchange (ETDEWEB)

    Jeon, Yeo Reong; Cho, Pyong Kon; Kim, Yong Min [Dept. of Radiological Science, Daegu Catholic University, Daegu (Korea, Republic of); Han, Eun Ok [Korea Academy of Nuclear Safety, Seoul (Korea, Republic of); Jang, Hyon Chul [Dept. of Radiological Technology, Suseong College, Daegu (Korea, Republic of); Ko, Jong Kyung [Radiation Safety Management Commission, Daegu Health College, (Korea, Republic of)

    2015-12-15

    This study tries to find the educational basis based on the radiation safety knowledge, attitudes and behaviors to check the level of radiation safety behavior in domestic students who study dental hygiene. The students of 3rd and 4th grades in 83 universities which have registered on the Korean University Education Council were involved, and they were given a questionnaire for this study. The questionnaire was provided via visit with 20 copies to each university (total 1660 copies), mail by post and e-mail. Among them, we analyzed only 723 copies that we can trust. The data were analyzed with frequency, percentage, mean, standard deviation and Pearson’s correlation using the SPSS/WIN 15.0. As a result, there are correlations in the students’ knowledge, attitudes and behaviors regarding the radiation safety management. It means that the education which can improve the knowledge and attitudes should be applied to increase the action level of the radiation safety. In addition, the physical environment is the most closely correlated with the individual behavior, so it will be limited to improve the behavioral levels of the radiation safety if the physical environment is not prepared. Therefore, the physical environment should be supported to enhance the level of the radiation safety activity, and to increase the individual attitude level of radiation safety. The knowledge level of the radiation safety management is relatively lower than the attitudes level, and the behavior level is the lowest. Therefore, the education policy of the safety behavior must be enhanced. For domestic students, the educational intervention is necessary to improve their behavioral level of radiation safety management because they will be able to reduce the amount of radiation exposure of their patients in dental care after getting a job.

  17. Australian Radiation Protection and Nuclear Safety Act 1998. Act No 133

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-11-01

    A set of legislation consisting of three Acts in the field of radiation protection and nuclear safety was passed by both Houses of Parliament on 10 December 1998 and was proclaimed on 5 February 1999. Act No. 133 - Australian Radiation Protection and Nuclear Safety Act, which is a framework Law, established the Australian Radiation Protection and Nuclear Safety Agency (ARPANSA) as the regulatory body for radiation protection and nuclear safety, in place of the Nuclear Safety Bureau. The Chief Executive Officer of ARPANSA, who is appointed by the Governor-General for a term of up to 5 years, is obliged to submit annual and quarterly reports to the Minister on the operations of the Chief Executive Officer, ARPANSA, the Council, the Radiation Health Committee and the Nuclear Safety Committee. The Council is a consultative body which examines issues relating to radiation protection and nuclear safety and advises the Chief Executive Officer on these issues as well as on the adoption of recommendations, policies and codes. The Radiation Health Committee and the Nuclear Safety Committee are to be established as advisory committees to the Chief Executive Officer or the Council. Both committees should draft national policies, codes and standards in their respective fields and review their effectiveness periodically. The second in this series of legislation, Act No. 134, Australian Radiation Protection and Nuclear Safety (License Charges) Act requires holders of both facility and source licenses to pay an annual charge, to be prescribed by the regulations. The third, Act No. 135 , Australian Radiation Protection and Nuclear Safety (Consequential Amendments) Act repeals those provisions of the 1987 Australian Nuclear Science and Technology Organisation Act which concern the Nuclear Safety Bureau, and the 1978 Environment Protection Act as a whole

  18. Open Source Radiation Hardened by Design Technology

    Science.gov (United States)

    Shuler, Robert

    2016-01-01

    The proposed technology allows use of the latest microcircuit technology with lowest power and fastest speed, with minimal delay and engineering costs, through new Radiation Hardened by Design (RHBD) techniques that do not require extensive process characterization, technique evaluation and re-design at each Moore's Law generation. The separation of critical node groups is explicitly parameterized so it can be increased as microcircuit technologies shrink. The technology will be open access to radiation tolerant circuit vendors. INNOVATION: This technology would enhance computation intensive applications such as autonomy, robotics, advanced sensor and tracking processes, as well as low power applications such as wireless sensor networks. OUTCOME / RESULTS: 1) Simulation analysis indicates feasibility. 2)Compact voting latch 65 nanometer test chip designed and submitted for fabrication -7/2016. INFUSION FOR SPACE / EARTH: This technology may be used in any digital integrated circuit in which a high level of resistance to Single Event Upsets is desired, and has the greatest benefit outside low earth orbit where cosmic rays are numerous.

  19. Compliance of Bhabhatron-II telecobalt unit with IEC standard - Radiation safety.

    Science.gov (United States)

    Sahani, G; Kumar, Munish; Dash Sharma, P K; Sharma, D N; Chhokra, Kanta; Mishra, Bibekananda; Agarwal, S P; Kher, R K

    2009-04-28

    Bhabha Atomic Research Centre, Mumbai, India designed and developed a telecobalt unit, which was named as Bhabhatron-II. In this paper, the results pertaining to radiation safety of indigenously developed Bhabhatron-II telecobalt unit are reported. The various tests were carried out as per requirements of International Electrotechnical Commission standard and acceptance criteria developed nationally. Various devices such as CaSO4:Dy based thermoluminescent dosimeters, farmer type ionization chamber, water phantom and radiographic films were used. All the parameters pertaining to radiation leakage/transmission were within the tolerance limits as per IEC-60601-2-11 standard except the collimator transmission through X collimators (upper jaw), which marginally exceeds the tolerance limit.

  20. Radiation and Reason Why radiation at modest dose rates is quite harmless and current radiation safety regulations are flawed

    CERN Document Server

    CERN. Geneva

    2013-01-01

    Data on the impact of ionising radiation on life are examined in the light of evolutionary biology. This comparison confirms that fear of nuclear radiation is not justified by science itself; rather it originates in a failure of public trust in nuclear science, a relic of the international politics of the Cold War era. Current ionisation safety regulations appease this fear but without scientific support and they need fundamental reformulation. This should change the reaction to accidents like Fukushima, the cost of nuclear energy and the application of nuclear technology to the supply of food and fresh water. Such a boost to the world economy would require that more citizens study and appreciate the science involved – and then tell others -- not as much fun as the Higgs, perhaps, but no less important! www.radiationandreason.com

  1. Design for safety: theoretical framework of the safety aspect of BIM system to determine the safety index

    Directory of Open Access Journals (Sweden)

    Ai Lin Evelyn Teo

    2016-12-01

    Full Text Available Despite the safety improvement drive that has been implemented in the construction industry in Singapore for many years, the industry continues to report the highest number of workplace fatalities, compared to other industries. The purpose of this paper is to discuss the theoretical framework of the safety aspect of a proposed BIM System to determine a Safety Index. An online questionnaire survey was conducted to ascertain the current workplace safety and health situation in the construction industry and explore how BIM can be used to improve safety performance in the industry. A safety hazard library was developed based on the main contributors to fatal accidents in the construction industry, determined from the formal records and existing literature, and a series of discussions with representatives from the Workplace Safety and Health Institute (WSH Institute in Singapore. The results from the survey suggested that the majority of the firms have implemented the necessary policies, programmes and procedures on Workplace Safety and Health (WSH practices. However, BIM is still not widely applied or explored beyond the mandatory requirement that building plans should be submitted to the authorities for approval in BIM format. This paper presents a discussion of the safety aspect of the Intelligent Productivity and Safety System (IPASS developed in the study. IPASS is an intelligent system incorporating the buildable design concept, theory on the detection, prevention and control of hazards, and the Construction Safety Audit Scoring System (ConSASS. The system is based on the premise that safety should be considered at the design stage, and BIM can be an effective tool to facilitate the efforts to enhance safety performance. IPASS allows users to analyse and monitor key aspects of the safety performance of the project before the project starts and as the project progresses.

  2. Engineering Safety : With applications to fire safety design of buildings and road tunnels

    OpenAIRE

    Bjelland, Henrik

    2013-01-01

    A continuously changing and increasingly complex society leads to new challenges in safety design. Modern buildings and road tunnels are being packed with new technology that creates new failure modes, multiple subsystem interactions and tight couplings between different socio-technical systems. Meanwhile, safety is largely designed into these systems using prescriptive design rules that have evolved through reactions to accidents in systems with limited resemblance to moder...

  3. Study on development of education model and its evaluation system for radiation safety

    CERN Document Server

    Seo, K W; Nam, Y M

    2002-01-01

    As one of the detailed action strategy of multi object preparedness for strengthening of radiation safety management by MOST, this project was performed, in order to promote the safety culture for user and radiation worker through effective education program. For the prevention of radiological accident and effective implementation of radiation safety education and training, this project has been carried out the development of education model and its evaluation system on radiation safety. In the development of new education model, education course was classified; new and old radiation worker, temporary worker, lecturer and manager. The education model includes the contents of expanding the education opportunity and workplace training. In the development of evaluation system, the recognition criteria for commission-education institute and inside-education institute which should establish by law were suggested for evaluation program. The recognition criteria contains classification, student, method, facilities, ...

  4. 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

  5. Safety in passenger ships: The influence of environmental design characteristics on people's perception of safety.

    Science.gov (United States)

    Ahola, Markus; Mugge, Ruth

    2017-03-01

    Although objective safety is a widely studied topic in ergonomics, subjective safety has received far less research attention. Nevertheless, most of human decision-making and behavior depends on how we perceive our environment. This study investigates the effects of various environmental design characteristics on people's safety perception in a passenger ship context. Five different environmental design characteristics were manipulated to increase the openness of the space or to create more clear navigation, resulting in 20 different cabin corridors for a passenger ship. Ninety-seven respondents were asked to rate these corridors on the perceived safety in an experiment. The results showed that people feel more safe when the corridors have a curved ceiling, when the walls do not have a split-level design, and when there is a view to the outside. Designers can use these insights when designing future environments. Copyright © 2016 Elsevier Ltd. All rights reserved.

  6. Radiation safety issues in Y-90 microsphere selective hepatic radioembolization therapy: possible radiation exposure from the patients

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Young Chul; Kim, Yun Hwan; Uhm, Soon Ho; Seo, Yeon Seok; Park, Eun Kyung; Oh, Sun Young; Jeong, Eu Gene; Lee, Sin Ae; Choe, Jae Gol [Korea University Anam Hospital, Seoul (Korea, Republic of)

    2010-12-15

    The purpose of this study was to estimate the possible external radiation dose to other individuals from patients treated with Y-90 resin microspheres for unresectable hepatocellular carcinoma. We designed the study prospectively to estimate the possible radiation dose to other individuals from patients who had been treated with Y-90 microspheres for unresectable hepatocellular carcinoma. We estimated the total effective dose equivalent (TEDE) using two methods: 'theoretical' TEDEs according to the administered activity and 'measured' TEDE based on the 'measured' ambient radiation exposure rate. We compared the results from each method to determine when we can release patients from confinement at the earliest time complying with the patient release criteria. A total of 20 administrations of Y-90 resin microspheres were done in 18 patients. The average administered activity was 1.2{+-}0.77 (0.28-2.97) GBq. The 'theoretical' TEDEs were in the range of 0.8-10 {mu}Sv. The 'measured' TEDEs were in the range of 2.31-185 {mu}Sv. The measured TEDEs tend to be higher than the theoretical TEDEs. The values of theoretical and measured TEDE were both far less than 1 mSv, the upper limit at which the licensee can release a patient without any written documents. The effective dose equivalent caused by the Y-90 microsphere administered patient is very low. It is safe in terms of radiation safety to the other individuals when Y-90 microsphere radioembolization therapy is done with dose less than 3 GBq. Because the measured TEDE tends to be higher than the theoretical TEDE, it is recommended to use 'measured' TEDE for determining patient release

  7. Review of design criteria and safety analysis of safety class electric building for fuel test loop

    Energy Technology Data Exchange (ETDEWEB)

    Kim, J. Y.

    1998-02-01

    Steady state fuel test loop will be equipped in HANARO to obtain the development and betterment of advanced fuel and materials through the irradiation tests. HANARO fuel test loop was designed for CANDU and PWR fuel testing. Safety related system of Fuel Test Loop such as emergency cooling water system, component cooling water system, safety ventilation system, high energy line break mitigation system and remote control room was required 1E class electric supply to meet the safety operation in accordance with related code. Therefore, FTL electric building was designed to construction and install the related equipment based on seismic category I. The objective of this study is to review the design criteria and analysis the safety function of safety class electric building for fuel test loop, and this results will become guidance for the irradiation testing in future. (author). 10 refs., 6 tabs., 30 figs.

  8. Graphical symbols -- Safety colours and safety signs -- Part 1: Design principles for safety signs in workplaces and public areas

    CERN Document Server

    International Organization for Standardization. Geneva

    2002-01-01

    This International Standard establishes the safety identification colours and design principles for safety signs to be used in workplaces and in public areas for the purpose of accident prevention, fire protection, health hazard information and emergency evacuation. It also establishes the basic principles to be applied when developing standards containing safety signs. This part of ISO 3864 is applicable to workplaces and all locations and all sectors where safety-related questions may be posed. However, it is not applicable to the signalling used for guiding rail, road, river, maritime and air traffic and, generally speaking, to those sectors subject to a regulation which may differ.

  9. Safety effects of road design standards in Europe.

    NARCIS (Netherlands)

    Wegman, F.C.M. & Slop, M.

    2003-01-01

    This paper deals with the result of a study carried out for the European Commission by the SWOV Institute for Road Safety Research, in cooperation with a number of other European institutes, and which was reported in 1994. The title of the study is "Safety Effects of Road Design Standards." The aims

  10. Safety Considerations in the Design of Riot-Control Grenades

    Science.gov (United States)

    1982-08-01

    fuze design resulted in injuries to the user, because the user would not maintain the required pressure after removing the safety pin . The grenade...of the M25A2 grenade was the accidental functioning of the grenade with the safety pin intact. If the ferenade was dropped onto a hard surface

  11. Safety effects of road design standards in Europe.

    NARCIS (Netherlands)

    Wegman, F.C.M. & Slop, M.

    2003-01-01

    This paper deals with the result of a study carried out for the European Commission by the SWOV Institute for Road Safety Research, in cooperation with a number of other European institutes, and which was reported in 1994. The title of the study is "Safety Effects of Road Design Standards." The aims

  12. Design of Vertical Wall Caisson Breakwaters using Partial Safety Factors

    DEFF Research Database (Denmark)

    Burcharth, H. F.; Sørensen, John Dalsgaard

    1999-01-01

    The paper presents a new system for implementation of target reliability in caisson breakwater designs by means of partial safety factors. The development of the system is explained, and tables of partial safety factors are presented for important overall stability failure modes related to caisson...

  13. The implementation and assessment of a quality and safety culture education program in a large radiation oncology department.

    Science.gov (United States)

    Woodhouse, Kristina D; Volz, Edna; Bellerive, Marc; Bergendahl, Howard W; Gabriel, Peter E; Maity, Amit; Hahn, Stephen M; Vapiwala, Neha

    2016-01-01

    In 2010, the American Society for Radiation Oncology launched a national campaign to improve patient safety in radiation therapy. One recommendation included the expansion of educational programs dedicated to quality and safety. We subsequently implemented a quality and safety culture education program (Q-SCEP) in our large radiation oncology department. The purpose of this study is to describe the design, implementation, and impact of this Q-SCEP. In 2010, we instituted a comprehensive Q-SCEP, consisting of a longitudinal series of lectures, meetings, and interactive workshops. Participation was mandatory for all department members across all network locations. Electronic surveys were administered to assess employee engagement, knowledge retention, preferred learning styles, and the program's overall impact. The Agency for Healthcare Research and Quality (AHRQ) Survey on Patient Safety Culture was administered. Analysis of variance was used for statistical analysis. Between 2010 and 2015, 100% of targeted staff participated in Q-SCEP. Thirty-three percent (132 of 400) and 30% (136 of 450) responded to surveys in 2012 and 2014, respectively. Mean scores improved from 73% to 89% (P safety culture education was critical to performing their jobs well. Full course compliance was achieved despite the sizable number of personnel and treatment centers. Periodic assessments demonstrated high knowledge retention, which significantly improved over time in nearly all department divisions. Additionally, our AHRQ patient safety grade remains high and continues to improve. These results will be used to further enhance ongoing internal safety initiatives and to inform future innovative efforts. Copyright © 2016 American Society for Radiation Oncology. Published by Elsevier Inc. All rights reserved.

  14. Safety design integrated in the building delivery system

    DEFF Research Database (Denmark)

    Jørgensen, Kirsten

    2013-01-01

    . The purpose of this article is to demonstrate how safety and health can be integrated in the design phases integrated in the management delivery systems within construction, The method for the research was to go through the building delivery system step by step and create a normative description of what, when......In construction, it is important to view safety and health as an integrated part of the way that “designers” are working. The designers cowers architects, constructors, engineers and others who carry out their consulting services in the design phase of a construction project. The philosophy...... is simple, if the demands for safety and health are incorporated early on in the solving of a building assignment, then it becomes much easier to organise the executing phase in a responsible manner safety-wise. But, the problem is that very few of the designers have knowledge or experience of how to do so...

  15. A prediction model for the radiation safety management behavior of medical cyclotrons

    Energy Technology Data Exchange (ETDEWEB)

    Jung, Ji Hye; Han, Eun Ok [Daegu Health College, Daegu (Korea, Republic of); Kim, Ssang Tae [CareCamp Inc., Seoul (Korea, Republic of)

    2008-06-15

    This study attempted to provide reference materials for improving the behavior level in radiation safety managements by drawing a prediction model that affects the radiation safety management behavior because the radiation safety management of medical Cyclotrons, which can be used to produce radioisotopes, is an important factor that protects radiation caused diseases not only for radiological operators but average users. In addition, this study obtained follows results through the investigation applied from January 2 to January 30, 2008 for the radiation safety managers employed in 24 authorized organizations, which have already installed Cyclotrons, through applying a specific form of questionnaire in which the validity was guaranteed by reference study, site investigation, and focus discussion by related experts. The radiation safety management were configured as seven steps: step 1 is a production preparation step, step 2 is an RI production step, step 3 is a synthesis step, step 4 is a distribution step, step 5 is a quality control step, step 6 is a carriage container packing step, and step 7 is a transportation step. It was recognized that the distribution step was the most exposed as 15 subjects (62.5%), the items of 'the sanction and permission related works' and 'the guarantee of installation facilities and production equipment' were the most difficult as 9 subjects (37.5%), and in the trouble steps in such exposure, the item of 'the synthesis and distribution' steps were 4 times, respectively (30.8%). In the score of the behavior level in radiation safety managements, the minimum and maximum scores were 2.42 and 4.00, respectively, and the average score was 3.46 {+-} 0.47 out of 4. Prosperity and well-being programs in the behavior and job in radiation safety managements (r=0.529) represented a significant correlation statistically. In the drawing of a prediction model based on the factors that affected the behavior in

  16. Radiation safety awareness among medical interns: are EU guidelines being implemented?

    Science.gov (United States)

    Lee, A M; Lee, M J

    2016-11-14

    European recommendations suggest that medical students should be taught radiation safety before entering clinical practice. The aim of this study was to produce a summative assessment of radiation protection training in medical school in Ireland. A web-based questionnaire was distributed to the 2014 intern population (n = 683) via network intern-coordinators. The survey encompassed knowledge of radiation dose in X-ray investigations, laws governing the prescribing of radiation and complications of radiation exposure to staff and patients. Response rate was 14.2% (97/683) with all Irish medical schools represented. 64% of interns reported no formal training in radiation safety. 80% correctly identified MRI and 94% US as not posing a radiation risk. 54% identified CT PET as emitting the highest radiation dose to patients. Only 32% correctly identified one CT abdomen/pelvis as equivalent to the dose from 300 to 500 chest X-rays and 22% correctly identified the theoretical lifetime risk of cancer induction from CT abdomen/pelvis as 1 in 2000. While 71% thought it was very important that prescribers should be aware of patient radiation dose and 28% thought it was moderately important, 74% were not aware of any laws governing the prescribing of radiology investigations. Currently, there is little formal radiation safety training in Irish medical schools. Knowledge of radiation dose and the laws governing prescribing is limited among qualifying interns. Implementation of a formal radiation safety curriculum in Irish Medical Schools would adhere to EU guidelines and improve prescriber knowledge, patient, and personal radiation safety.

  17. Design an optimum safety policy for personnel safety management - A system dynamic approach

    Energy Technology Data Exchange (ETDEWEB)

    Balaji, P. [The Glocal University, Mirzapur Pole, Delhi- Yamuntori Highway, Saharanpur 2470001 (India)

    2014-10-06

    Personnel safety management (PSM) ensures that employee's work conditions are healthy and safe by various proactive and reactive approaches. Nowadays it is a complex phenomenon because of increasing dynamic nature of organisations which results in an increase of accidents. An important part of accident prevention is to understand the existing system properly and make safety strategies for that system. System dynamics modelling appears to be an appropriate methodology to explore and make strategy for PSM. Many system dynamics models of industrial systems have been built entirely for specific host firms. This thesis illustrates an alternative approach. The generic system dynamics model of Personnel safety management was developed and tested in a host firm. The model was undergone various structural, behavioural and policy tests. The utility and effectiveness of model was further explored through modelling a safety scenario. In order to create effective safety policy under resource constraint, DOE (Design of experiment) was used. DOE uses classic designs, namely, fractional factorials and central composite designs. It used to make second order regression equation which serve as an objective function. That function was optimized under budget constraint and optimum value used for safety policy which shown greatest improvement in overall PSM. The outcome of this research indicates that personnel safety management model has the capability for acting as instruction tool to improve understanding of safety management and also as an aid to policy making.

  18. What You Should Know About Pediatric Nuclear Medicine and Radiation Safety

    Science.gov (United States)

    What You Should Know About Pediatric Nuclear Medicine and Radiation Safety www.imagegently.org What is nuclear medicine? Nuclear medicine uses radioactive isotopes to create pictures of the human body. ...

  19. Reinforcement Data for Fire Safety Design

    DEFF Research Database (Denmark)

    Hertz, Kristian Dahl

    2004-01-01

    Idealized materials data are derived from a number of test series reported in the literature and made by the author. The data cover a variety of reinforcing steels from mild steel, deformed bars and cold worked bars to cold drawn prestressing steels. Processes are described, which are responsible...... for the deterioration of the materials when they are heated and cooled down. A simple expression is established for the description of deterioration curves for fire-exposed materials such as concrete and reinforcement by means of 5 parameters, which may be used as input data for structural fire safety calculations...

  20. Optimum design of cast iron finned radiator

    Institute of Scientific and Technical Information of China (English)

    赵立华; 张泓森; 董重成

    2003-01-01

    The height, thickness and spacing of fins have an impact on the thermal characteristics of a radiator.The calculation of heat output and metal thermal intensity for cast iron finned radiator are given by using heat transfer formula of vertical plate and parallel fins. Each factor having effect on the metal thermal intensity of a radiator is analyzed and the optimum structure parameters of a radiator are given in order to maximize metal thermal intensity.

  1. Beam dumps design and local radiation protection at TERA synchrotron.

    Science.gov (United States)

    Porta, A; Campi, F; Agosteo, S

    2005-01-01

    The realisation of the National Center of Hadrontherapy was funded by the Italian Government in 2002. The Centre will be built in the area of Pavia (Italy). The synchrotron designed in the framework of this programme will accelerate protons and carbon ions up to 250 MeV and 400 MeV u(-1), respectively. Some of the main aspects which were taken into account in the design of the acceleration system are the patient's safety and the beam control. From this point of view an important role is played by the beam dumps in the synchrotron ring and upstream of the extraction system. In particular, an horizontal and a vertical beam dump will be installed in the synchrotron ring: the former will be used for lowering the beam intensity and the latter for beam abortion. The dump at the extraction will absorb the particles during the mounting and the falling ramps of the synchrotron magnetic cycle, thus extracting only the flat top of the ion spill. Beam dumps can produce intense fields of secondary radiation (neutrons, charged light-hadrons and photons) and high rates of induced activity, since they can absorb the beam completely. Usually they have to be shielded to protect the electronics during machine operation and to attenuate the radiation dose below the limits imposed by the law when the personnel access to the synchrotron hall. The part of the shielding design of the beam dumps concerning with the acceleration of protons was made using Monte Carlo simulations with the FLUKA code. Both induced activity and secondary radiation were taken into account. The shields against secondary radiation produced by carbon ions were designed, referring only to secondary neutrons, taking double-differential distributions from the literature as sources for the FLUKA simulations. The induced activity from carbon ions interactions was estimated analytically, using the data generated by the EPAX 2 code. The dose-equivalent rates from the induced radionuclides were calculated at 1 m from the

  2. Epidemiological designs for vaccine safety assessment: methods and pitfalls.

    Science.gov (United States)

    Andrews, Nick

    2012-09-01

    Three commonly used designs for vaccine safety assessment post licensure are cohort, case-control and self-controlled case series. These methods are often used with routine health databases and immunisation registries. This paper considers the issues that may arise when designing an epidemiological study, such as understanding the vaccine safety question, case definition and finding, limitations of data sources, uncontrolled confounding, and pitfalls that apply to the individual designs. The example of MMR and autism, where all three designs have been used, is presented to help consider these issues.

  3. Rapidly design safety relief valve inlet piping systems

    Energy Technology Data Exchange (ETDEWEB)

    Westman, M.A.

    1997-03-01

    Safety relief valves (SRVs) used to protect against overpressure require well-designed inlet piping for proper operation. The engineer`s job is to produce these designs from a thorough understanding of the inlet piping as a key component in the safety relief system and the correct application of the governing fluid dynamics principles. This article will present a technique for analysis and design using classical ideal-gas adiabatic fluid flow principles. Also, it will discuss the advantages of using the personal computer (PC) to quickly arrive at accurate designs. This work applies to SRVs in which relief flows are limited by sonic conditions at their nozzles.

  4. Safety design integrated in the Building Delivery System

    DEFF Research Database (Denmark)

    Jørgensen, Kirsten

    2012-01-01

    of safety in each process. The group of participants who created the description had a high experience in a combination of research, safety and health in general and especial in construction and knowledge of the lean construction processes both from the clients perspective as well as from the designers...... phases of the building delivery system by using the principle of the lean construction modelling. The method for the research was to go through the lean construction building delivery system step by step and create a normative description of what to do, when to do and how to do to fully integration......It is important to see safety and health in construction as an integrated part of the way in which designers, architects, constructors, engineers and others carry out their consulting services. The purpose of this article is to demonstrate how safety and health can be integrated in the design...

  5. Preliminary Conceptual Design for Safety Parameter display System of PGSFR

    Energy Technology Data Exchange (ETDEWEB)

    Jo, Hyunju; Seong, Seunghwan; Kim, Wansu; Kim, Donghoon; Son, Kwangseop; Jang, Gwisook [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2014-05-15

    A PGSFR (prototype Gen-IV sodium-cooled fast reactor) is under development at KAERI. A safety parameter display system (SPDS) should be designed for licensing the PGSFR in order to cope with the TMI action plan requirements. Thus, a preliminary conceptual design for the SPDS of PGSFR including licensing requirements, intrinsic function, critical variables and alarm legs for the SPDS of the PGSFR is studied herein. At first, some documents issued by NRC related to install a SPDS include the following: - NUREG-0737, Clarification of TMI Action Plan Requirements - NUREG-0696, Functional Criteria for Emergency Response Facilities - NUREG-0835, Human Factors Acceptance Criteria for the Safety Parameter display System, Draft Report for Comment. The preliminary concept design for the SPDS of the PGSFR was studied. In designing of the PGSFR, the studied design concept will be refined and implemented through further studies to acquire the approval of a safety analysis report of the PGSFR.

  6. Designing Equipment for Use in Gamma Radiation Environments

    Energy Technology Data Exchange (ETDEWEB)

    Vandergriff, K.U.

    1990-01-01

    High levels of gamma radiation are known to cause degradation in a variety of materials and components. When designing systems to operate in a high radiation environment, special precautions and procedures should be followed. This report (1) outlines steps that should be followed in designing equipment and (2) explains the general effects of radiation on various engineering materials and components. Much information exists in the literature on radiation effects upon materials. However, very little information is available to give the designer a step-by-step process for designing systems that will be subject to high levels of gamma radiation, such as those found in a nuclear fuel reprocessing facility. In this report, many radiation effect references are relied upon to aid in the design of components and systems.

  7. Hypofractionated radiation therapy versus conventional radiation therapy in prostate cancer: A systematic review of its safety and efficacy.

    Science.gov (United States)

    Sánchez-Gómez, L M; Polo-deSantos, M; Rodríguez-Melcón, J I; Angulo, J C; Luengo-Matos, S

    2015-01-01

    New therapeutic alternatives can improve the safety and efficacy of prostate cancer treatment. To assess whether hypofractionated radiation therapy results in better safety and efficacy in the treatment of prostate cancer. Systematic review of the literature through searches on PubMed, Cochrane Library, CRD, ClinicalTrials and EuroScan, collecting indicators of safety and efficacy. We included 2 systematic reviews and a clinical trial. In terms of efficacy, there is considerable heterogeneity among the studies, and no conclusive results were found concerning the superiority of the hypofractionated option over the normal fractionated option. In terms of safety, there were no significant differences in the onset of acute genitourinary complications between the 2 treatments. However, one of the reviews found more acute gastrointestinal complications in patients treated with hypofractionated radiation therapy. There were no significant differences in long-term complications based on the type of radiation therapy used, although the studies did have limitations. To date, there are no conclusive results that show that hypofractionated radiation therapy is more effective or safer than normal fractionated radiation therapy in the treatment of localized prostate cancer. Copyright © 2014 AEU. Publicado por Elsevier España, S.L.U. All rights reserved.

  8. Preliminary safety analysis for key design features of KALIMER

    Energy Technology Data Exchange (ETDEWEB)

    Hahn, D. H.; Kwon, Y. M.; Chang, W. P.; Suk, S. D.; Lee, S. O.; Lee, Y. B.; Jeong, K. S

    2000-07-01

    KAERI is currently developing the conceptual design of a liquid metal reactor, KALIMER(Korea Advanced Liquid Metal Reactor) under the long-term nuclear R and D program. In this report, descriptions of the KALIMER safety design features and safety analyses results for selected ATWS accidents are presented. First, the basic approach to achieve the safety goal is introduced in chapter 1, and the safety evaluation procedure for the KALIMER design is described in chapter 2. It includes event selection, event categorization, description of design basis events, and beyond design basis events. In chapter 3, results of inherent safety evaluations for the KALIMER conceptual design are presented. The KALIMER core and plant system are designed to assure design performance during a selected set of events without either reactor control or protection system intervention. Safety analyses for the postulated anticipated transient without scram(ATWS) have been performed to investigate the KALIMER system response to the events. They are categorized as bounding events(BEs) because of their low probability of occurrence. In chapter 4, the design of the KALIMER containment dome and the results of its performance analysis are presented. The designs of the existing LMR containment and the KALIMER containment dome have been compared in this chapter. Procedure of the containment performance analysis and the analysis results are described along with the accident scenario and source terms. Finally, a simple methodology is introduced to investigate the core kinetics and hydraulic behavior during HCDA in chapter 5. Mathematical formulations have been developed in the framework of the modified bethe-tait method, and scoping analyses have been performed for the KALIMER core behavior during super-prompt critical excursions.

  9. Study on categorization of the safety design evaluation event

    Energy Technology Data Exchange (ETDEWEB)

    Kurisaka, Kenichi; Kani, Yoshio [Power Reactor and Nuclear Fuel Development Corp., Oarai, Ibaraki (Japan). Oarai Engineering Center

    1997-05-01

    In order to make a FBR practicable, it is important to make rational categorization of a safety design evaluation event. In this study, for the purpose of providing useful information into the event categorization, we developed the occurrence frequency data of various abnormal events, presented a proposal of the event categorization primarily based on the occurrence frequency and examined efficiency of the proposal. We researched and analyzed abnormal event instances of foreign and domestic FBR plants and of domestic light water reactor power plants. On the basis of the analysis, the failure occurrence frequency of the protection system (PS) in the FBR model plants with electric power production of 600MW and 1,000MW was quantified. Making use of results of probabilistic safety assessment study, loss-of-function probability of the mitigation system (MS) was quantified. Some of combinations of PS failure and loss of MS function were selected and their occurrence frequencies were quantified. We examined problems in the current categorization of the safety design evaluation event and presented a new proposal of the event categorization. Merits of the new proposal are to have divided the current category of `accident` into `small accident` and `rare accident`, explicitly to treat a multiple failure event not as a collateral analysis condition of supposing `a single failure` but as an event to be evaluated, and to have added a category for the event which is beyond design base, but should be supposed to evaluate depth of the safety design in terms of defense-in-depth. Some candidates of the safety design evaluation event were identified and applied to the new proposal. In comparison with the current categorization, we obtained perspective that it was possible to evaluate the safety design more in detail and effectively, especially depth of the safety design such as backup reactor shutdown system, decay heat removal function in a natural circulation mode etc. (J.P.N.)

  10. Radiation safety control on Ulchin NPP Unit 1 s/g sleeving

    Energy Technology Data Exchange (ETDEWEB)

    Kim, S. T.; Jang, Y. S. [KEPCO Ulchin Nuclear Power Plant Units 1, 2, Kyongsangbukdo (Korea, Republic of)

    1999-07-01

    Ulchin NPP unit 1 has been entered its tenth operation year. As the operation years went by, S/G tubes' defects have been reported, which was analyzed mainly due to PWSCC through ECT and various studies. In the ninth overhaul, technical staffs of Ulchin unit 1 decided to do sleeve installation for defected tubes. This sleeve installation was a second experience on our plant in KEPCO. The sleeving tubes were estimated to 600 pieces, but increased to 987 pieces by ECT results. As the sleeve installation was performed in high radiation level, we have considered various radiation safety, i e. protection of radiation source and internal exposure. The collective radiation exposure dose was recorded to 142.32 man-mSv and no internal exposed person was discovered. But there are some requirements to improve radiation safety for reducing exposure dose to radiation. PWSCC : Primary Water Side Stress Corrosion Crack (author)

  11. ENSURING RADIATION SAFETY AT THE XXVII WORLD SUMMER UNIVERSIADE IN KAZAN BY ROSPOTREBNADZOR BODIES AND ORGANIZATIONS Communication 1. Ensuring radiation safety at the preparatory phase

    Directory of Open Access Journals (Sweden)

    G. G. Onischenko

    2013-01-01

    Full Text Available After the terrorist attack at theBostonMarathon, Federal and Republican executive bodies took increased security measures during the XXVII World Summer Universiade inKazan. Bodies and Organizations of the Federal Service for Surveillance on Consumer Rights Protection and Human Well-being (Rospotrebnadzor were participants of all preparatory activities and directly provided security of the Student Games inKazan. This report analyzes the experience of providing radiation safety by Rospotrebnadzor experts at the stage of preparation for the Universiade. So far, Rospotrebnadzor organizations had no experience of providing radiation safety of such large-scale events. Analysis of the performed work with account for both positive and negative experiences is especially important in the context of preparations for the safety providing of the Olympic Winter Games inSochiin 2014. 

  12. Radiation effects in power converters: Design of a radiation hardened integrated switching DC/DC converter

    Science.gov (United States)

    Adell, Philippe

    When electronic devices are used in space and military systems, they may be exposed to various types of radiation, including photons, electrons, protons, neutrons, and heavy ions. The effects of radiation on the semiconductor devices within the systems range from gradual degradation to catastrophic failure. In order to design and produce reliable systems for space or military applications, it is necessary to understand the device-level effects of radiation and develop appropriate strategies for reducing system susceptibility. This research focuses on understanding radiation effects in power converters for space and military applications. We show that power converters are very sensitive to radiation (total-dose, single event effects and displacement damage) and that their radiation response is dependent on input bias conditions and load conditions. We compared the radiation hardness of various power converter topologies using experiments and simulations. Evaluation of these designs under different modes of operation is demonstrated to be critical for determining radiation hardness. We emphasize the correlation between radiation effects and the role of the dynamic response of these topologies. For instance, total dose exposure has been found to degrade loop gain and affect regulation in some converters. We propose several radiation-hardening solutions to improve the radiation response of these designs. For instance, we demonstrate the design of a digitally controlled boost converter suitable for space applications based on an SRAM FPGA. A design hardening solution has been developed and successfully applied through VHDL simulations and experiments to assure the continuous operation of the converter in the presence of SEES (more precisely SEFIs). This research led to the design of a digitally controlled radiation hardened integrated switching buck converter. The proposed design is suitable for micro-satellite applications and is based on a high-voltage/CMOS process

  13. 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)

  14. Advanced analysis and design for fire safety of steel structures

    CERN Document Server

    Li, Guoqiang

    2013-01-01

    Advanced Analysis and Design for Fire Safety of Steel Structures systematically presents the latest findings on behaviours of steel structural components in a fire, such as the catenary actions of restrained steel beams, the design methods for restrained steel columns, and the membrane actions of concrete floor slabs with steel decks. Using a systematic description of structural fire safety engineering principles, the authors illustrate the important difference between behaviours of an isolated structural element and the restrained component in a complete structure under fire conditions. The book will be an essential resource for structural engineers who wish to improve their understanding of steel buildings exposed to fires. It is also an ideal textbook for introductory courses in fire safety for master’s degree programs in structural engineering, and is excellent reading material for final-year undergraduate students in civil engineering and fire safety engineering. Furthermore, it successfully bridges th...

  15. Summary of Prometheus Radiation Shielding Nuclear Design Analysis

    Energy Technology Data Exchange (ETDEWEB)

    J. Stephens

    2006-01-13

    This report transmits a summary of radiation shielding nuclear design studies performed to support the Prometheus project. Together, the enclosures and references associated with this document describe NRPCT (KAPL & Bettis) shielding nuclear design analyses done for the project.

  16. Radiation safety during remediation of the SevRAO facilities: 10 years of regulatory experience.

    Science.gov (United States)

    Sneve, M K; Shandala, N; Kiselev, S; Simakov, A; Titov, A; Seregin, V; Kryuchkov, V; Shcheblanov, V; Bogdanova, L; Grachev, M; Smith, G M

    2015-09-01

    In compliance with the fundamentals of the government's policy in the field of nuclear and radiation safety approved by the President of the Russian Federation, Russia has developed a national program for decommissioning of its nuclear legacy. Under this program, the State Atomic Energy Corporation 'Rosatom' is carrying out remediation of a Site for Temporary Storage of spent nuclear fuel (SNF) and radioactive waste (RW) at Andreeva Bay located in Northwest Russia. The short term plan includes implementation of the most critical stage of remediation, which involves the recovery of SNF from what have historically been poorly maintained storage facilities. SNF and RW are stored in non-standard conditions in tanks designed in some cases for other purposes. It is planned to transport recovered SNF to PA 'Mayak' in the southern Urals. This article analyses the current state of the radiation safety supervision of workers and the public in terms of the regulatory preparedness to implement effective supervision of radiation safety during radiation-hazardous operations. It presents the results of long-term radiation monitoring, which serve as informative indicators of the effectiveness of the site remediation and describes the evolving radiation situation. The state of radiation protection and health care service support for emergency preparedness is characterized by the need to further study the issues of the regulator-operator interactions to prevent and mitigate consequences of a radiological accident at the facility. Having in mind the continuing intensification of practical management activities related to SNF and RW in the whole of northwest Russia, it is reasonable to coordinate the activities of the supervision bodies within a strategic master plan. Arrangements for this master plan are discussed, including a proposed programme of actions to enhance the regulatory supervision in order to support accelerated mitigation of threats related to the nuclear legacy in the

  17. Web design and development for centralize area radiation monitoring system in Malaysian Nuclear Agency

    Science.gov (United States)

    Ibrahim, Maslina Mohd; Yussup, Nolida; Haris, Mohd Fauzi; Soh @ Shaari, Syirrazie Che; Azman, Azraf; Razalim, Faizal Azrin B. Abdul; Yapp, Raymond; Hasim, Harzawardi; Aslan, Mohd Dzul Aiman

    2017-01-01

    One of the applications for radiation detector is area monitoring which is crucial for safety especially at a place where radiation source is involved. An environmental radiation monitoring system is a professional system that combines flexibility and ease of use for data collection and monitoring. Nowadays, with the growth of technology, devices and equipment can be connected to the network and Internet to enable online data acquisition. This technology enables data from the area monitoring devices to be transmitted to any place and location directly and faster. In Nuclear Malaysia, area radiation monitor devices are located at several selective locations such as laboratories and radiation facility. This system utilizes an Ethernet as a communication media for data acquisition of the area radiation levels from radiation detectors and stores the data at a server for recording and analysis. This paper discusses on the design and development of website that enable all user in Nuclear Malaysia to access and monitor the radiation level for each radiation detectors at real time online. The web design also included a query feature for history data from various locations online. The communication between the server's software and web server is discussed in detail in this paper.

  18. Designing and developing management systems for environmental, health and safety

    Energy Technology Data Exchange (ETDEWEB)

    Holdsworth, Rodger D.; Franklyn-Alderman, Christy [Risk, Reliability and Safety Engineering, Houston, TX (United States)

    2000-07-01

    The introduction of Quality, Risk, Safety and Environmental management philosophies has significantly changed industry view of company organization and controlling processes entering the new millennium. Quality, Risk, Health and Environmental programs and systems, such as ISO/Q S 9000, ISO 14000, Process Safety, risk management are impacting the way industry meet the challenges of safety and environmental risks and the needs of the customer. A wealth of knowledge can be extracted from practical application, which might otherwise be unobtainable without years of management systems experience related to management systems design, development, implementation and control. (author)

  19. Design review report for modifications to RMCS safety class equipment

    Energy Technology Data Exchange (ETDEWEB)

    Corbett, J.E.

    1997-05-30

    This report documents the completion of the formal design review for modifications to the Rotary Mode Core Sampling (RMCS) safety class equipment. These modifications are intended to support core sampling operations in waste tanks requiring flammable gas controls. The objective of this review was to approve the Engineering Change Notices affecting safety class equipment used in the RMCS system. The conclusion reached by the review committee was that these changes are acceptable.

  20. Radon in the Workplace: the Occupational Safety and Health Administration (OSHA) Ionizing Radiation Standard.

    Science.gov (United States)

    Lewis, Robert K

    2016-10-01

    On 29 December 1970, the Occupational Safety and Health Act of 1970 established the Occupational Safety and Health Administration (OSHA). This article on OSHA, Title 29, Part 1910.1096 Ionizing Radiation standard was written to increase awareness of the employer, the workforce, state and federal governments, and those in the radon industry who perform radon testing and radon mitigation of the existence of these regulations, particularly the radon relevant aspect of the regulations. This review paper was also written to try to explain what can sometimes be complicated regulations. As the author works within the Radon Division of the Pennsylvania Department of Environmental Protection, Bureau of Radiation Protection, the exclusive focus of the article is on radon. The 1910.1096 standard obviously covers many other aspects of radiation and radiation safety in the work place.

  1. Preliminary safety analysis for key design features of KALIMER-600

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Y. B.; Chang, W. P.; Suk, S. D.; Ha, K. S.; Jeong, H. Y.; Heo, S

    2004-03-01

    KAERI is developing the conceptual design of a Liquid Metal Reactor, KALIMER-600 (Korea Advanced LIquid MEtal Reactor) under the Long-term Nuclear R and D Program. KALIMER-600 addresses key issues regarding future nuclear power plants such as plant safety, economics, proliferation, and waste. In this report, key safety design features are described and safety analyses results for typical ATWS accidents in the KALIMER design with breakeven core are presented. First, the basic approach to achieve the safety goal is introduced in Chapter 1, and the event categorization and acceptance criteria for the KALIMER-600 safety analysis are described in Chapter 2. In Chapter 3, results of inherent safety evaluations for the KALIMER-600 conceptual design are presented. The KALIMER-600 core and plant system are designed to assure benign performance during a selected set of events without either reactor control or protection system intervention. Safety analyses for the postulated Anticipated Transient Without Scram (ATWS) have been performed using the SSC-K code to investigate the KALIMER-600 system response to the events. They are categorized as Bounding Events (BEs) because of their low probability of occurrence. In Chapter 4, the analysis of flow blockage for KALIMER-600 with the MATRA-LMR-FB code, which has been developed for the internal flow blockage in a LMR subassembly. The cases with a blockage of 6-subchannel, 24-subchannel, and 54-subchannel are analyzed.The performance analysis of the KALIMER-600 containment and some evaluations for the behaviors during HCDA will be performed later.

  2. Assessment of radiation safety awareness among nuclear medicine nurses: a pilot study

    Science.gov (United States)

    Yunus, N. A.; Abdullah, M. H. R. O.; Said, M. A.; Ch'ng, P. E.

    2014-11-01

    All nuclear medicine nurses need to have some knowledge and awareness on radiation safety. At present, there is no study to address this issue in Malaysia. The aims of this study were (1) to determine the level of knowledge and awareness on radiation safety among nuclear medicine nurses at Putrajaya Hospital in Malaysia and (2) to assess the effectiveness of a training program provided by the hospital to increase the knowledge and awareness of the nuclear medicine nurses. A total of 27 respondents attending a training program on radiation safety were asked to complete a questionnaire. The questionnaire consists 16 items and were categorized into two main areas, namely general radiation knowledge and radiation safety. Survey data were collected before and after the training and were analyzed using descriptive statistics and paired sample t-test. Respondents were scored out of a total of 16 marks with 8 marks for each area. The findings showed that the range of total scores obtained by the nuclear medicine nurses before and after the training were 6-14 (with a mean score of 11.19) and 13-16 marks (with a mean score of 14.85), respectively. Findings also revealed that the mean score for the area of general radiation knowledge (7.59) was higher than that of the radiation safety (7.26). Currently, the knowledge and awareness on radiation safety among the nuclear medicine nurses are at the moderate level. It is recommended that a national study be conducted to assess and increase the level of knowledge and awareness among all nuclear medicine nurses in Malaysia.

  3. Radio Frequency Radiation of Millimeter Wave Length: An Evaluation of Potential Occupational Safety Issues Relating to Surface Heating

    Science.gov (United States)

    2016-06-14

    Radio frequency radiation of millimeter wave length: An evaluation of potential occupational safety issues. 5a. CONTRACT NUMBER 5b. GRANT NUMBER...Paper------------------------------- RADIO FREQUENCY RADIATION OF MILLIMETER WAVE LENGTH: POTENTIAL OCCUPATIONAL...cancer. Health Phys. 78(2):170-181; 2000 Key words: cancer; radiation , nonionizing; occupational safety; radiofrequency INTRODUCTION THE RADIO

  4. Integrating Safeguards and Security with Safety into Design

    Energy Technology Data Exchange (ETDEWEB)

    Robert S. Bean; John W. Hockert; David J. Hebditch

    2009-05-01

    There is a need to minimize security risks, proliferation hazards, and safety risks in the design of new nuclear facilities in a global environment of nuclear power expansion, while improving the synergy of major design features and raising operational efficiency. In 2008, the U.S. Department of Energy (DOE), National Nuclear Security Administration (NNSA) launched the Next Generation Safeguards Initiative (NGSI) covering many safeguards areas. One of these, launched by NNSA with support of the DOE Office of Nuclear Energy, was a multi-laboratory project, led by the Idaho National Laboratory (INL), to develop safeguards by design. The proposed Safeguards-by-Design (SBD) process has been developed as a structured approach to ensure the timely, efficient, and cost effective integration of international safeguards and other nonproliferation barriers with national material control and accountability, physical security, and safety objectives into the overall design process for the nuclear facility lifecycle. A graded, iterative process was developed to integrate these areas throughout the project phases. It identified activities, deliverables, interfaces, and hold points covering both domestic regulatory requirements and international safeguards using the DOE regulatory environment as exemplar to provide a framework and guidance for project management and integration of safety with security during design. Further work, reported in this paper, created a generalized SBD process which could also be employed within the licensed nuclear industry and internationally for design of new facilities. Several tools for integrating safeguards, safety, and security into design are discussed here. SBD appears complementary to the EFCOG TROSSI process for security and safety integration created in 2006, which focuses on standardized upgrades to enable existing DOE facilities to meet a more severe design basis threat. A collaborative approach is suggested.

  5. SP-100 design, safety, and testing

    Energy Technology Data Exchange (ETDEWEB)

    Smith, G.L.; Cox, C.M.; Mahaffey, M.K.

    1990-07-01

    The SP-100 Program is developing a nuclear reactor power system that can enhance and/or enable future civilian and military space missions. The program is directed to develop space reactor technology to provide electrical power in the range of tens to hundreds of kilowatts. The major nuclear assembly test is to be conducted at the Hanford Site near Richland, Washington, and is designed to validate the performance of the 2.4-MWt nuclear and heat transport assembly. 10 refs., 5 figs.

  6. Participatory design of a preliminary safety checklist for general practice.

    Science.gov (United States)

    Bowie, Paul; Ferguson, Julie; MacLeod, Marion; Kennedy, Susan; de Wet, Carl; McNab, Duncan; Kelly, Moya; McKay, John; Atkinson, Sarah

    2015-05-01

    The use of checklists to minimise errors is well established in high reliability, safety-critical industries. In health care there is growing interest in checklists to standardise checking processes and ensure task completion, and so provide further systemic defences against error and patient harm. However, in UK general practice there is limited experience of safety checklist use. To identify workplace hazards that impact on safety, health and wellbeing, and performance, and codesign a standardised checklist process. Application of mixed methods to identify system hazards in Scottish general practices and develop a safety checklist based on human factors design principles. A multiprofessional 'expert' group (n = 7) and experienced front-line GPs, nurses, and practice managers (n = 18) identified system hazards and developed and validated a preliminary checklist using a combination of literature review, documentation review, consensus building workshops using a mini-Delphi process, and completion of content validity index exercise. A prototype safety checklist was developed and validated consisting of six safety domains (for example, medicines management), 22 sub-categories (for example, emergency drug supplies) and 78 related items (for example, stock balancing, secure drug storage, and cold chain temperature recording). Hazards in the general practice work system were prioritised that can potentially impact on the safety, health and wellbeing of patients, GP team members, and practice performance, and a necessary safety checklist prototype was designed. However, checklist efficacy in improving safety processes and outcomes is dependent on user commitment, and support from leaders and promotional champions. Although further usability development and testing is necessary, the concept should be of interest in the UK and internationally. © British Journal of General Practice 2015.

  7. Automated Radiation Measurements for Aviation Safety (ARMAS) Project

    Data.gov (United States)

    National Aeronautics and Space Administration — Commercial aircrew members and frequent flyers face radiation hazards from the effects of cosmic rays and solar energetic particles. During significant solar events,...

  8. Automated Radiation Measurements for Aviation Safety (ARMAS) Project

    Data.gov (United States)

    National Aeronautics and Space Administration — The existing state-of-the-art for physics-based, data-driven, climatological specification of the global radiation environment is the capability embodied by Nowcast...

  9. Radiation safety knowledge and practices among Irish orthopaedic trainees.

    LENUS (Irish Health Repository)

    Nugent, M

    2014-04-23

    Fluoroscopy is frequently used in orthopaedic surgery, particularly in a trauma setting. Exposure of patients and staff to ionising radiation has been studied extensively; however, little work has been done to evaluate current knowledge and practices among orthopaedic trainees.

  10. Nanotoxicology and nanoparticle safety in biomedical designs

    Directory of Open Access Journals (Sweden)

    Ai J

    2011-05-01

    Full Text Available Jafar Ai1, Esmaeil Biazar2, Mostafa Jafarpour3, Mohamad Montazeri4, Ali Majdi5, Saba Aminifard5, Mandana Zafari5, Hanie Akbari R6, Hadi Rad Gh71Department of Tissue Engineering, Faculty of Advanced Technologies, Tehran University of Medical Sciences, Tehran; 2Department of Chemistry, Islamic Azad University – Tonekabon Branch, Mazandaran; 3Department of Microbiology, Faculty of Science, Islamic Azad University – Tonekabon Branch, Mazandaran; 4Faculty of Medical Sciences, Babol University of Medical Sciences; 5Young Researchers Club – Islamic Azad University, Tonekabon Branch, Mazandaran; 6Faculty of Medical Sciences, Islamic Azad University – North branch, Tehran; 7Faculty of Medical Sciences, Islamic Azad University – Tonekabon Branch, Mazandaran, IranAbstract: Nanotechnology has wide applications in many fields, especially in the biological sciences and medicine. Nanomaterials are applied as coating materials or in treatment and diagnosis. Nanoparticles such as titania, zirconia, silver, diamonds, iron oxides, carbon nanotubes, and biodegradable polymers have been studied in diagnosis and treatment. Many of these nanoparticles may have toxic effects on cells. Many factors such as size, inherent properties, and surface chemistry may cause nanoparticle toxicity. There are methods for improving the performance and reducing toxicity of nanoparticles in medical design, such as biocompatible coating materials or biodegradable/biocompatible nanoparticles. Most metal oxide nanoparticles show toxic effects, but no toxic effects have been observed with biocompatible coatings. Biodegradable nanoparticles are also used in the efficient design of medical materials, which will be reviewed in this article.Keywords: nanotechnology, nanotoxicology, nanomaterials, nanobiomaterials

  11. Design of SJ-10 Space Radiation Detector Prototype

    CERN Document Server

    Liu, Yaqing; Cui, Xingzhu; Peng, Wenxi; Fan, Ruirui; Gao, Xiaohua Liang Ming; Zhang, Yunlong; Zhang, Chengmo; Zhang, Jiayu; Yang, Jiawei; Wang, Jinzhou; Dong, Fei Zhang Yifan; Guo, Dongya; Zhou, Dawei

    2014-01-01

    The space radiation detector is a space apparatus for detecting the outer-space particles and monitoring the radiation environment. Though identifying the particles and acquiring the biological experimental data, we can learn about the space radiation impacts on the human body and defend the space radiation damage. This paper designed a prototype of the space radiation detector for SJ-10 and evaluated the performance by the system simulation. More specifically, the space radiation impacts on the human body were analyzed including the different particles, the radiation flux and the energy channels. Then the detector system based on analysis results were built by the Monte Carlo simulation. Finally, the detection algorithms of incident energy range were proposed to identify the outer-space particles and provide the reliable radiation environment data for biological experimental apparatus.

  12. Attitude of the Korean dentists towards radiation safety and selection criteria

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Byung Do [Dept. of Oral and Maxillofacial Radiology and Wonkwang Dental Research Institute, College of Dentistry, Wonkwang University, Iksan (Korea, Republic of); Ludlow, John B. [Graduate Program in Oral and Maxillofacial Radiology, School of Dentistry, University of North Carolina, Chapel Hill (United States)

    2013-09-15

    X-ray exposure should be clinically justified and each exposure should be expected to give patients benefits. Since dental radiographic examination is one of the most frequent radiological procedures, radiation hazard becomes an important public health concern. The purpose of this study was to investigate the attitude of Korean dentists about radiation safety and use of criteria for selecting the frequency and type of radiographic examinations. The study included 267 Korean dentists. Five questions related to radiation safety were asked of each of them. These questions were about factors associated with radiation protection of patients and operators including the use of radiographic selection criteria for intraoral radiographic procedures. The frequency of prescription of routine radiographic examination (an example is a panoramic radiograph for screening process for occult disease) was 34.1%, while that of selective radiography was 64.0%. Dentists' discussion of radiation risk and benefit with patients was infrequent. More than half of the operators held the image receptor by themselves during intraoral radiographic examinations. Lead apron/thyroid collars for patient protection were used by fewer than 22% of dental offices. Rectangular collimation was utilized by fewer than 15% of dental offices. The majority of Korean dentists in the study did not practice radiation protection procedures which would be required to minimize exposure to unnecessary radiation for patients and dental professionals. Mandatory continuing professional education in radiation safety and development of Korean radiographic selection criteria is recommended.

  13. Attitude of the Korean dentists towards radiation safety and selection criteria.

    Science.gov (United States)

    Lee, Byung-Do; Ludlow, John B

    2013-09-01

    X-ray exposure should be clinically justified and each exposure should be expected to give patients benefits. Since dental radiographic examination is one of the most frequent radiological procedures, radiation hazard becomes an important public health concern. The purpose of this study was to investigate the attitude of Korean dentists about radiation safety and use of criteria for selecting the frequency and type of radiographic examinations. The study included 267 Korean dentists. Five questions related to radiation safety were asked of each of them. These questions were about factors associated with radiation protection of patients and operators including the use of radiographic selection criteria for intraoral radiographic procedures. The frequency of prescription of routine radiographic examination (an example is a panoramic radiograph for screening process for occult disease) was 34.1%, while that of selective radiography was 64.0%. Dentists' discussion of radiation risk and benefit with patients was infrequent. More than half of the operators held the image receptor by themselves during intraoral radiographic examinations. Lead apron/thyroid collars for patient protection were used by fewer than 22% of dental offices. Rectangular collimation was utilized by fewer than 15% of dental offices. The majority of Korean dentists in the study did not practice radiation protection procedures which would be required to minimize exposure to unnecessary radiation for patients and dental professionals. Mandatory continuing professional education in radiation safety and development of Korean radiographic selection criteria is recommended.

  14. Safety assessment in plant layout design using indexing approach: implementing inherent safety perspective. Part 1 - guideword applicability and method description.

    Science.gov (United States)

    Tugnoli, Alessandro; Khan, Faisal; Amyotte, Paul; Cozzani, Valerio

    2008-12-15

    Layout planning plays a key role in the inherent safety performance of process plants since this design feature controls the possibility of accidental chain-events and the magnitude of possible consequences. A lack of suitable methods to promote the effective implementation of inherent safety in layout design calls for the development of new techniques and methods. In the present paper, a safety assessment approach suitable for layout design in the critical early phase is proposed. The concept of inherent safety is implemented within this safety assessment; the approach is based on an integrated assessment of inherent safety guideword applicability within the constraints typically present in layout design. Application of these guidewords is evaluated along with unit hazards and control devices to quantitatively map the safety performance of different layout options. Moreover, the economic aspects related to safety and inherent safety are evaluated by the method. Specific sub-indices are developed within the integrated safety assessment system to analyze and quantify the hazard related to domino effects. The proposed approach is quick in application, auditable and shares a common framework applicable in other phases of the design lifecycle (e.g. process design). The present work is divided in two parts: Part 1 (current paper) presents the application of inherent safety guidelines in layout design and the index method for safety assessment; Part 2 (accompanying paper) describes the domino hazard sub-index and demonstrates the proposed approach with a case study, thus evidencing the introduction of inherent safety features in layout design.

  15. AMTV headway sensor and safety design

    Science.gov (United States)

    Johnston, A. R.; Nelson, M.; Cassell, P.; Herridge, J. T.

    1980-01-01

    A headway sensing system for an automated mixed traffic vehicle (AMTV) employing an array of optical proximity sensor elements is described, and its performance is presented in terms of object detection profiles. The problem of sensing in turns is explored experimentally and requirements for future turn sensors are discussed. A recommended headway sensor configuration, employing multiple source elements in the focal plane of one lens operating together with a similar detector unit, is described. Alternative concepts including laser radar, ultrasonic sensing, imaging techniques, and radar are compared to the present proximity sensor approach. Design concepts for an AMTV body which will minimize the probability of injury to pedestrians or passengers in the event of a collision are presented.

  16. Modeling Programs Increase Aircraft Design Safety

    Science.gov (United States)

    2012-01-01

    Flutter may sound like a benign word when associated with a flag in a breeze, a butterfly, or seaweed in an ocean current. When used in the context of aerodynamics, however, it describes a highly dangerous, potentially deadly condition. Consider the case of the Lockheed L-188 Electra Turboprop, an airliner that first took to the skies in 1957. Two years later, an Electra plummeted to the ground en route from Houston to Dallas. Within another year, a second Electra crashed. In both cases, all crew and passengers died. Lockheed engineers were at a loss as to why the planes wings were tearing off in midair. For an answer, the company turned to NASA s Transonic Dynamics Tunnel (TDT) at Langley Research Center. At the time, the newly renovated wind tunnel offered engineers the capability of testing aeroelastic qualities in aircraft flying at transonic speeds near or just below the speed of sound. (Aeroelasticity is the interaction between aerodynamic forces and the structural dynamics of an aircraft or other structure.) Through round-the-clock testing in the TDT, NASA and industry researchers discovered the cause: flutter. Flutter occurs when aerodynamic forces acting on a wing cause it to vibrate. As the aircraft moves faster, certain conditions can cause that vibration to multiply and feed off itself, building to greater amplitudes until the flutter causes severe damage or even the destruction of the aircraft. Flutter can impact other structures as well. Famous film footage of the Tacoma Narrows Bridge in Washington in 1940 shows the main span of the bridge collapsing after strong winds generated powerful flutter forces. In the Electra s case, faulty engine mounts allowed a type of flutter known as whirl flutter, generated by the spinning propellers, to transfer to the wings, causing them to vibrate violently enough to tear off. Thanks to the NASA testing, Lockheed was able to correct the Electra s design flaws that led to the flutter conditions and return the

  17. Laser safety in design of near-infrared scanning LIDARs

    Science.gov (United States)

    Zhu, X.; Elgin, D.

    2015-05-01

    3D LIDARs (Light Detection and Ranging) with 1.5μm nanosecond pulse lasers have been increasingly used in different applications. The main reason for their popularity is that these LIDARs have high performance while at the same time can be made eye-safe. Because the laser hazard effect on eyes or skin at this wavelength region (mining applications. We have incorporated the laser safety requirements in the LIDAR design and conducted laser safety analysis for different operational scenarios. While 1.5μm is normally said to be the eye-safe wavelength, in reality a high performance 3D LIDAR needs high pulse energy, small beam size and high pulse repetition frequency (PRF) to achieve long range, high resolution and high density images. The resulting radiant exposure of its stationary beam could be many times higher than the limit for a Class 1 laser device. Without carefully choosing laser and scanning parameters, including field-of-view, scan speed and pattern, a scanning LIDAR can't be eye- or skin-safe based only on its wavelength. This paper discusses the laser safety considerations in the design of eye-safe scanning LIDARs, including laser pulse energy, PRF, beam size and scanning parameters in two basic designs of scanning mechanisms, i.e. galvanometer based scanner and Risley prism based scanner. The laser safety is discussed in terms of device classification, nominal ocular hazard distance (NOHD) and safety glasses optical density (OD).

  18. Safety Analysis for Key Design Features of KALIMER-600 Design Concept

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Yong Bum; Kwon, Y. M.; Kim, E. K.; Suk, S. D.; Chang, W. P.; Jeong, H. Y.; Ha, K. S

    2007-02-15

    This report contains the safety analyses of the KALIMER-600 conceptual design which KAERI has been developing under the Long-term Nuclear R and D Program. The analyses have been performed reflecting the design developments during the second year of the 4th design phase in the program. The specific presentations are the key design features with the safety principles for achieving the safety objectives, the event categorization and safety criteria, and results on the safety analyses for the DBAs and ATWS events, the containment performance, and the channel blockages. The safety analyses for both the DBAs and ATWS events have been performed using SSC-K version 1.3., and the results have shown the fulfillment of the safety criteria for DBAs with conservative assumptions. The safety margins as well as the inherent safety also have been confirmed for the ATWS events. For the containment performance analysis, ORIGEN-2.1 and CONTAIN-LMR have been used. In results, the structural integrity has been acceptable and the evaluated exposure dose rate has been complied with 10 CFR 100 and PAG limits. The analysis results for flow blockages of 6-subchannels, 24-subchannels, and 54- subchannels with the MATRA-LMR-FB code, have assured the integrity of subassemblies.

  19. 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.

  20. Radiation Belt Storm Probes (RBSP) Payload Safety Introduction Briefing

    Science.gov (United States)

    Loftin, Chuck; Lampert, Dianna; Herrburger, Eric; Smith, Clay; Hill, Stuart; VonMehlem, Judi

    2008-01-01

    Mission of the Geospace Radiation Belt Storm Probes (RBSP) is: Gain s cientific understanding (to the point of predictability) of how populations of relativistic electrons and ions in space form or change in response to changes in solar activity and the solar wind.

  1. Design strength evaluation of RC beams under radiation environments for nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Kang, Won-Hee [Institute for Infrastructure Engineering, University of Western Sydney, Penrith, NSW 2751 (Australia); Kwon, Tae-Hyun [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Kim, Hyeong-Tae [Department of Civil and Environmental Engineering, Yonsei University, Seoul 120-749 (Korea, Republic of); Park, Kyoungsoo, E-mail: k-park@yonsei.ac.kr [Department of Civil and Environmental Engineering, Yonsei University, Seoul 120-749 (Korea, Republic of)

    2016-05-15

    Neutron irradiation changes the behavior of construction materials such as strength and ductility, and thus structural design equations or their safety margins should accordingly be updated for the design of nuclear power plants (NPP) under irradiation. However, current design codes do not account for such changes in material strength. In this study, a framework is proposed to evaluate the change of the safety margins in design equations of reinforced concrete (RC) flexural members under radiation environments. Material strength changes are approximated on the basis of a collected test database, and the design strengths of RC beams are evaluated considering these material strength changes. The evaluation results demonstrate that the design strength of an under-reinforced flexural member can increase while the design strength of an over-reinforced member generally decreases. These results are associated with the material strength changes such that the yield strength of steel increases and the compressive strength of concrete decreases with the fluence of neutron radiation. Current NPP design codes need to further consider this un-conservative design possibility due to the design strength reduction of flexural members under irradiation.

  2. Systems Engineering and Safety Issues in Scientific Facilities Subject to Ionizing Radiations

    Directory of Open Access Journals (Sweden)

    Pierre Bonnal

    2013-10-01

    Full Text Available The conception and development of large- scale scientific facilities emitting ionizing radiations rely more on project management practices in use in the process industry than on systems engineering practices. This paper aims to highlight possible reasons for this present situation and to propose some ways to enhance systems engineering so that the specific radiation safety requirements are considered and integrated in the approach. To do so, we have reviewed lessons learned from the management of large-scale scientific projects and more specifically that of the Large Hadron Collider project at CERN. It is shown that project management and systems engineering practices are complementary and can beneficially be assembled in an integrated and lean managerial framework that grants the appropriate amount of focus to safety and radiation safety aspects.

  3. Systems Engineering and Safety Issues in Scientific Facilities Subject to Ionizing Radiations

    Directory of Open Access Journals (Sweden)

    Pierre Bonnal

    2013-10-01

    Full Text Available The conception and development of large-scale scientific facilities emitting ionizing radiations rely more on project management practices in use in the process industry than on systems engineering practices. This paper aims to highlight possible reasons for this present situation and to propose some ways to enhance systems engineering so that the specific radiation safety requirements are considered and integrated in the approach. To do so, we have reviewed lessons learned from the management of large-scale scientific projects and more specifically that of the Large Hadron Collider project at CERN. It is shown that project management and systems engineering practices are complementary and can beneficially be assembled in an integrated and lean managerial framework that grants the appropriate amount of focus to safety and radiation safety aspects.

  4. Partial Safety Factors for Fatigue Design of Wind Turbine Blades

    DEFF Research Database (Denmark)

    Toft, Henrik Stensgaard; Sørensen, John Dalsgaard

    2010-01-01

    In the present paper calibration of partial safety factors for fatigue design of wind turbine blades is considered. The stochastic models for the physical uncertainties on the material properties are based on constant amplitude fatigue tests and the uncertainty on Miners rule for linear damage...

  5. Food Safety Monitoring System Design Based on WIA-PA

    Directory of Open Access Journals (Sweden)

    Lin Tang

    2015-05-01

    Full Text Available The study designed a food safety monitoring network system which is composed of the wireless sensor network and MCU based on the emerging wireless communication technology. Tests indicate that the system runs well with small consumption and good mobility and the data can be uploaded to host computer for real-time display and record.

  6. Information about robustness, reliability and safety in early design phases

    DEFF Research Database (Denmark)

    Marini, Vinicius Kaster

    This thesis is motivated by the need for support in considerations of robustness, reliability and safety during early design phases. The thesis deals with the question of how to codify and communicate failures and hazards, and devises measures against these. Current methods to robustness, reliabi......This thesis is motivated by the need for support in considerations of robustness, reliability and safety during early design phases. The thesis deals with the question of how to codify and communicate failures and hazards, and devises measures against these. Current methods to robustness......, reliability and safety reviewed have shortcomings including the complexity of using them and dependence on expert input for mitigating uncertainty and ambiguity among solution alternatives. This research is carried out using case studies: a pilot case to assess information requirements from reliability...... methods, and an industrial case to assess how the use of information about robustness, reliability and safety as practised by current methods influences concept development. Current methods cannot be used in early design phases due to their dependence on detailed design information for the identification...

  7. Using partial safety factors in wind turbine design and testing

    Energy Technology Data Exchange (ETDEWEB)

    Musial, W.D. [National Renewable Energy Lab., Golden, CO (United States)

    1997-12-31

    This paper describes the relationship between wind turbine design and testing in terms of the certification process. An overview of the current status of international certification is given along with a description of limit-state design basics. Wind turbine rotor blades are used to illustrate the principles discussed. These concepts are related to both International Electrotechnical Commission and Germanischer Lloyd design standards, and are covered using schematic representations of statistical load and material strength distributions. Wherever possible, interpretations of the partial safety factors are given with descriptions of their intended meaning. Under some circumstances, the authors` interpretations may be subjective. Next, the test-load factors are described in concept and then related to the design factors. Using technical arguments, it is shown that some of the design factors for both load and materials must be used in the test loading, but some should not be used. In addition, some test factors not used in the design may be necessary for an accurate test of the design. The results show that if the design assumptions do not clearly state the effects and uncertainties that are covered by the design`s partial safety factors, outside parties such as test labs or certification agencies could impose their own meaning on these factors.

  8. Design and Implementation of the HJ-1-C Satellite SAR Full-power Radiation Test

    OpenAIRE

    Zhang Hua-chun; Tao Xin; Ni Jiang; Yu Wei-dong

    2014-01-01

    In this paper, the HJ-1-C SAR full-power radiation test design is presented. For the new problems caused by SAR high-power concentrated emissions, the radar-receiving channel-leakage power test is proposed to ensure the safety of the radar-receiving path, and the transceiver channel closed-loop radar system test is discussed. The experimental results show that the proposed HJ-1-C SAR full-power radiation test scheme is reasonable and feasible, with the desired outcome.

  9. Design and Implementation of the HJ-1-C Satellite SAR Full-power Radiation Test

    Directory of Open Access Journals (Sweden)

    Zhang Hua-chun

    2014-06-01

    Full Text Available In this paper, the HJ-1-C SAR full-power radiation test design is presented. For the new problems caused by SAR high-power concentrated emissions, the radar-receiving channel-leakage power test is proposed to ensure the safety of the radar-receiving path, and the transceiver channel closed-loop radar system test is discussed. The experimental results show that the proposed HJ-1-C SAR full-power radiation test scheme is reasonable and feasible, with the desired outcome.

  10. Evaluation of a Radiation Worker Safety Training Program at a nuclear facility

    Energy Technology Data Exchange (ETDEWEB)

    Lindsey, J.E.

    1993-05-01

    A radiation safety course was evaluated using the Kirkpatrick criteria of training evaluation as a guide. Thirty-nine employees were given the two-day training course and were compared with 15 employees in a control group who did not receive the training. Cognitive results show an immediate gain in knowledge, and substantial retention at 6 months. Implications of the results are discussed in terms of applications to current radiation safety training was well as follow-on training research and development requirements.

  11. Electromagnetic Radiation Measurements and Safety Issues of some Cellular

    Directory of Open Access Journals (Sweden)

    A. Mousa

    2011-01-01

    Full Text Available As the mobile telecommunication systems are tremendously growing allover the world then the numbers of handheld andbase stations are also rapidly growing and it became very popular to see these base stations distributed everywhere in theneighborhood and on roof tops which has caused a considerable amount of panic to the public in Palestine concerning witherthe radiated electromagnetic field from these base stations may cause any health effect or hazard. This paper focuses on theradiated electromagnetic energy from some typical mobile base stations around the city of Nablus. The exposure levels dueto these stations were measured and compared to some international standard guidelines like ICNIRP and FCC to see if itmeets these standards, this is in order to answer some of the public fear and concern. The results are presented and somecomments are made on the other sources of electromagnetic radiation in the 200 kHz to 3 GHz range.

  12. Attitude of the Korean dentists towards radiation safety and selection criteria

    OpenAIRE

    Lee, Byung-Do; Ludlow, John B.

    2013-01-01

    Purpose X-ray exposure should be clinically justified and each exposure should be expected to give patients benefits. Since dental radiographic examination is one of the most frequent radiological procedures, radiation hazard becomes an important public health concern. The purpose of this study was to investigate the attitude of Korean dentists about radiation safety and use of criteria for selecting the frequency and type of radiographic examinations. Materials and Methods The study included...

  13. Australian radiation protection and nuclear safety (consequential amendments) Bill 1998. Explanatory memorandum

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-12-31

    The purpose of this Bill is to make consequential changes to the Australian Nuclear Science and Technology Organisation Act 1987 (the ANSTO Act) and to provide for transitional arrangements to cover the operation of controlled facilities and the handling of radiation sources while applications for licences to cover these facilities and activities are being made under the proposed Australian Radiation Protection and Nuclear Safety Act 1998 (the ARPANS Act) For this purpose, the Bill: (a) repeals Parts VI and VII A of the ANSTO Act under which, respectively, the Safety Review Committee and the Nuclear Safety Bureau are established, as the functions of the Committee and Bureau will be transferred to the CEO of the Australian Radiation Protection and Nuclear Safety Agency, established under the ARPANS Act; (b) makes transitional arrangements for the transfer of the assets and liabilities of the Nuclear Safety Bureau to the Commonwealth, and confers on the CEO of ARPANSA the powers of the Director of the Nuclear Safety Bureau in relation to the Australian Nuclear Science and Technology Organisation during the transitional period before the offenses provisions commence to operate under the ARPANS Act; (c) repeals the Environment Protection (Nuclear Codes) Act 1978. That Act provides for the development and endorsement of Codes of Practice which will be undertaken under the auspices of ARPANSA; (d) provides that Commonwealth entities have a transition period of 6 months after the ARPANS Act commences to apply for a licence to authorize specified activities under that Act

  14. Parametric study for the fire safety design of steel structures

    DEFF Research Database (Denmark)

    Aiuti, Riccardo; Giuliani, Luisa

    2013-01-01

    and find out the basic collapse mechanisms of structural elements in fire conditions, considering the rest of the construction with appropriate constraints. The analysis is carried out taking into account material and geometrical nonlinearities as well as the degradation of steel properties at high......Despite the increasing knowledge on the behaviour of structures in fire and the development of new design tools for fire safety, current prescriptive regulations and design procedures present several shortcomings. These are mostly due to an oversimplification of the problem, in order to allow...... for a simple integration of the fire design procedures in the common practice. In this view, the structural fire safety of a building can be accomplished by verifying that single elements can resist a standard fire exposure for a required time, without taking into consideration the effect of restrained...

  15. The design and safety features of the IRIS reactor

    Energy Technology Data Exchange (ETDEWEB)

    Carelli, Mario D. E-mail: carellmd@westinghouse.com; Conway, L.E.; Oriani, L.; Petrovic, B.; Lombardi, C.V.; Ricotti, M.E.; Barroso, A.C.O.; Collado, J.M.; Cinotti, L.; Todreas, N.E.; Grgic, D.; Moraes, M.M.; Boroughs, R.D.; Ninokata, H.; Ingersoll, D.T.; Oriolo, F

    2004-05-01

    Salient features of the International Reactor Innovative and Secure (IRIS) are presented here. IRIS, an integral, modular, medium size (335 MWe) PWR, has been under development since the turn of the century by an international consortium led by Westinghouse and including over 20 organizations from nine countries. Described here are the features of the integral design which includes steam generators, pumps and pressurizer inside the vessel, together with the core, control rods, and neutron reflector/shield. A brief summary is provided of the IRIS approach to extended maintenance over a 48-month schedule. The unique IRIS safety-by-design approach is discussed, which, by eliminating accidents, at the design stage, or decreasing their consequences/probabilities when outright elimination is not possible, provides a very powerful first level of defense in depth. The safety-by-design allows a significant reduction and simplification of the passive safety systems, which are presented here, together with an assessment of the IRIS response to transients and postulated accidents.

  16. Radiation Safety Issues in High Altitude Commercial Aircraft

    Science.gov (United States)

    Wilson, John W.; Cucinotta, Francis A.; Shinn, Judy L.

    1995-01-01

    The development of a global economy makes the outlook for high speed commercial intercontinental flight feasible, and the development of various configurations operating from 20 to 30 km have been proposed. In addition to the still unresolved issues relating to current commercial operations (12-16 km), the higher dose rates associated with the higher operating altitudes makes il imperative that the uncertainties in the atmospheric radiation environment and the associated health risks be re-examined. Atmospheric radiation associated with the galactic cosmic rays forms a background level which may, under some circumstances, exceed newly recommended allowable exposure limits proposed on the basis of recent evaluations of the A -bomb survivor data (due to increased risk coefficients). These larger risk coefficients, within the context of the methodology for estimating exposure limits, are resulting in exceedingly low estimated allowable exposure limits which may impact even present day flight operations and was the reason for the CEC workshop in Luxembourg (1990). At higher operating altitudes, solar particles events can produce exposures many orders of magnitude above background levels and pose significant health risks to the most sensitive individuals (such as during pregnancy). In this case the appropriate quality factors are undefined, and some evidence exists which indicates that the quality factor for stochastic effects is a substantial underestimate.

  17. CURRENT TRENDS OF THE PROVISION FOR RADIATION SAFETY OF THE POPULATION OF THE RUSSIAN FEDERATION

    Directory of Open Access Journals (Sweden)

    G. G. Onishenko

    2014-01-01

    Full Text Available P.V.Ramzaev”The article is devoted to the actual issues ofRussian Federationpopulation radiation safety providing at the present stage. The important role of radiation-hygienic passportization is underlined in the process of the obtaining of objective information of radiation situation in the country, of population exposure doses from the all sources: artificial and natural, from the use of ionizing irradiation sources in medicine. The leading role is shown of the natural ionizing irradiation sources in the level of the country population exposure. The main directions of activities are stated aimed on the decreasing of population exposure doses from the natural sources. The brief characteristics is given of the radiation situation on the territories radioactively contaminated after the accident on the Chernobyl NPP, in the Pacific Ocean basin after the accident on the “Fukushima-1”NPP, of the main measures for radiation protection providing and for counteraction to radiation terrorism during the period of international sports and mass actions which were carried out in Russia in the last years (XXVII World Summer Universiade in2013 inKazan, XXII Olympic and XI Winter Paralympics Games in2014 inSochi. The most important tasks are defined for the improvement ofRussian Federationpopulation radiation safety at the present stage.

  18. Strategies for Navigating Common Ethical Dilemmas Encountered by Operational Radiation Safety Professionals.

    Science.gov (United States)

    Emery, Robert J; Rios, Janelle

    2016-02-01

    Because operational radiation safety professionals can encounter ethical dilemmas in the course of their work, codes of ethics and professional standards of conduct are maintained by the Health Physics Society (HPS) and the American Academy of Health Physics (AAHP). While these works provide valuable guidance, they do not operationalize the types of ethical dilemmas radiation safety practitioners might encounter. For example, consider the ethical conundrum of “dual loyalty,” defined as the situation in which an individual holds simultaneous obligations to two or more parties. In the case of radiation safety, practicing professionals hold obligations to the workers being protected and to the leaders of the organization. If these obligations are in conflict, serious difficulties can arise. The conundrum of dual loyalty is described and a strategy for reducing its effect is discussed. Two other common ethical issues; “confidentiality” and “organizational dissent” are similarly presented. A foundation from which to launch an ongoing dialogue about ethical issues within the radiation safety profession is also proposed.

  19. Strategies for Navigating Common Ethical Dilemmas Encountered by Operational Radiation Safety Professionals

    Science.gov (United States)

    Emery, RJ; Rios, J

    2017-01-01

    Because operational radiation safety professionals can encounter ethical dilemmas in the course of their work, codes of ethics and professional standards of conduct are maintained by the Health Physics Society (HPS) and the American Academy of Health Physics (AAHP). While these works provide valuable guidance, they do not operationalize the types of ethical dilemmas radiation safety practitioners might encounter. For example, consider the ethical conundrum of “dual loyalty”, defined as the situation in which an individual holds simultaneous obligations to two or more parties. In the case of radiation safety, practicing professionals hold obligations to the workers being protected and to the leaders of the organization. If these obligations are in conflict, serious difficulties can arise. The conundrum of dual loyalty is described and a strategy for reducing its effect is discussed. Two other common ethical issues; “confidentiality” and “organizational dissent” are similarly presented. A foundation from which to launch an ongoing dialogue about ethical issues within the radiation safety profession is also proposed. PMID:26710164

  20. Evaluation of safety, an unavoidable requirement in the applications of ionizing radiations; La evaluacion de la seguridad un requisito de seguridad insoslayable en las aplicaciones de las radiaciones ionizantes

    Energy Technology Data Exchange (ETDEWEB)

    Jova Sed, Luis Andres, E-mail: jovaluis@gmail.com [Centro Nacional de Seguridad Nuclear (CNSN), La Habana (Cuba)

    2013-07-01

    The safety assessments should be conducted as a means to evaluate compliance with safety requirements (and thus the application of fundamental safety principles) for all facilities and activities in order to determine the measures to be taken to ensure safety. It is an essential tool in decision making. For long time we have linked the safety assessment to nuclear facilities and not to all practices involving the use of ionizing radiation in daily life. However, the main purpose of the safety assessment is to determine if it has reached an appropriate level of safety for an installation or activity and if it has fulfilled the objectives of safety and basic safety criteria set by the designer, operating organization and the regulatory body under the protection and safety requirements set out in the International Basic safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources. This paper presents some criteria and personal experiences with the new international recommendations on this subject and its practical application in the region and demonstrates the importance of this requirement. Reflects the need to train personnel of the operator and the regulatory body in the proportional application of this requirement in practice with ionizing radiation.

  1. Current global and Korean issues in radiation safety of nuclear medicine procedures.

    Science.gov (United States)

    Song, H C

    2016-06-01

    In recent years, the management of patient doses in medical imaging has evolved as concern about radiation exposure has increased. Efforts and techniques to reduce radiation doses are focussed not only on the basis of patient safety, but also on the fundamentals of justification and optimisation in cooperation with international organisations such as the International Commission on Radiological Protection, the International Atomic Energy Agency, and the World Health Organization. The Image Gently campaign in children and Image Wisely campaign in adults to lower radiation doses have been initiated in the USA. The European Association of Nuclear Medicine paediatric dosage card, North American consensus guidelines, and Nuclear Medicine Global Initiative have recommended the activities of radiopharmaceuticals that should be administered in children. Diagnostic reference levels (DRLs), developed predominantly in Europe, may be an important tool to manage patient doses. In Korea, overexposure to radiation, even from the use of medical imaging, has become a public issue, particularly since the accident at the Fukushima nuclear power plant. As a result, the Korean Nuclear Safety and Security Commission revised the technical standards for radiation safety management in medical fields. In parallel, DRLs for nuclear medicine procedures have been collected on a nationwide scale. Notice of total effective dose from positron emission tomography-computed tomography for cancer screening has been mandatory since mid-November 2014.

  2. Relationship between knowledge, attitude, behavior, and self-efficacy on the radiation safety on dental hygienist

    Energy Technology Data Exchange (ETDEWEB)

    Han, Eun Ok; Jun, Sung Hee [Daegu Health College, Daegu (Korea, Republic of)

    2008-11-15

    The objective of this study is to draw an educational plant for reducing the probability of troubles caused by radiation for dental hygienists who are the major applicants of radiation equipments used in dental offices. This study investigated the knowledge and self-efficacy, which is the major variable that affects the attitude and behavior, on the radiation safety that is an educational approach. Also, this study obtained following results from a survey for 25 days from June 15, 2008 that was applied for 225 dental hygienists worked at dental offices and clinics in the area of Youngnam in order to verify the relationship between such variables. The average scores for the knowledge, attitude, and behavior were 54.28±16.33, 87.93±9.75, and 59.85±14.76, respectively. Also, the average score of the self-efficacy was 72.88±8.60. In the knowledge level for the radiation safety, ‘a case that prepares personal dosimeters’, ‘a case that establishes protection facilities’, ‘a case that presents 6⁓10 dental hygienists’, ‘a case that presents radiological technologists’, and ‘a case that is a general hospital’ represented high values. In the attitude level for the radiation safety, ‘a case who is a married person’, ‘a case that prepares personal dosimeters’, and ‘a case that is a general hospital’ showed high values. In the behavior level for the radiation safety, ‘a case that shows a career in dental hygienist or radiographic for 6⁓10 years’, ‘a case that attends radiation safety education’, ‘a case that establishes protection facilities’ showed high values. Also, in the self-efficacy level, ‘a case that who has a high education level more than graduate school education’ and ‘a case that establishes protection facilities’ represented high values. In the relationship between the knowledge, attitude, behavior, and self-efficacy for the radiation safety, it showed statistically significant differences in this

  3. Radiological protection, safety and security issues in the industrial and medical applications of radiation sources

    Science.gov (United States)

    Vaz, Pedro

    2015-11-01

    The use of radiation sources, namely radioactive sealed or unsealed sources and particle accelerators and beams is ubiquitous in the industrial and medical applications of ionizing radiation. Besides radiological protection of the workers, members of the public and patients in routine situations, the use of radiation sources involves several aspects associated to the mitigation of radiological or nuclear accidents and associated emergency situations. On the other hand, during the last decade security issues became burning issues due to the potential malevolent uses of radioactive sources for the perpetration of terrorist acts using RDD (Radiological Dispersal Devices), RED (Radiation Exposure Devices) or IND (Improvised Nuclear Devices). A stringent set of international legally and non-legally binding instruments, regulations, conventions and treaties regulate nowadays the use of radioactive sources. In this paper, a review of the radiological protection issues associated to the use of radiation sources in the industrial and medical applications of ionizing radiation is performed. The associated radiation safety issues and the prevention and mitigation of incidents and accidents are discussed. A comprehensive discussion of the security issues associated to the global use of radiation sources for the aforementioned applications and the inherent radiation detection requirements will be presented. Scientific, technical, legal, ethical, socio-economic issues are put forward and discussed.

  4. Progress and Status on the Development of NASA's Nowcast of Atmospheric Ionizing Radiation for Aviation Safety (NAIRAS) model

    Science.gov (United States)

    Mertens, C. J.; Tobiska, W. K.; Blattnig, S. R.; Kress, B. T.; Wiltberger, M. J.; Solomon, S. C.; Kunches, J.; Murray, J. J.

    2008-12-01

    The NASA Applied Sciences Program recently selected a project for funding through the Research Opportunities in Space and Earth Sciences (ROSES) solicitation. The project objective is to develop a nowcast prediction of air-crew radiation exposure from both background galactic cosmic rays (GCR) and solar energetic particle events (SEP) that may accompany solar storms. The new air-crew radiation exposure model is called the Nowcast of Atmospheric Ionizing Radiation for Aviation Safety (NAIRAS) model. NAIRAS will provide global, data-driven, real-time radiation dose predictions of biologically harmful radiation at commercial airline altitudes. Observations are utilized from the ground (neutron monitors), from the atmosphere (the NCEP reanalysis), and from space (NASA/ACE and NOAA/GOES). Atmospheric observations provide the overhead shielding information and the ground- and space-based observations provide boundary conditions on the incident GCR and SEP particle flux distributions for transport and dosimetry simulations. Dose rates are calculated using the parametric AIR (Atmospheric Ionizing Radiation) model and the physics-based HZETRN (High Charge and Energy Transport) code. In this paper we discuss the concept and design of the NAIRAS model, and present recent progress in the implementation and give examples of the model results. Specifically, we show predictions of representative annual background exposure levels and radiation exposure levels for selected SEP events during solar cycle 23, with emphasis on the high-latitude and polar region. We also characterize the suppression of the geomagnetic cutoff rigidity during these storm periods and their subsequent influence on atmospheric radiation exposure. We discuss the key uncertainties and areas that need improvement in both model and data, the timeline for project completion, and access to model results.

  5. Partial Safety Factors for Fatigue Design of Wind Turbine Blades

    DEFF Research Database (Denmark)

    Toft, Henrik Stensgaard; Sørensen, John Dalsgaard

    In the present paper calibration of partial safety factors for fatigue design of wind turbine blades is considered. The stochastic models for the physical uncertainties on the material properties are based on constant amplitude fatigue tests and the uncertainty on Miners rule for linear damage...... from rainflow-counting of simulated time series for a 5MW reference wind turbine [1]. A possible influence of a complex stress state in the blade is not taken into account and only longitudinal stresses are considered....

  6. ALWR safety approaches and trends. Implementation of passive safety features in the design

    Energy Technology Data Exchange (ETDEWEB)

    Ignatiev, V.

    1995-11-01

    Reactor vendors world-wide are examining various advanced light water reactors (ALWR) options to reach utility goals. The amount of information available about each design varies essentially depending on its maturity. Some advanced reactor designs are the evolutionary results of combining old structures, systems and components in new ways, others use innovative solutions. A summary review is given for better understanding of new ALWR design trends and approaches in different countries and subsequent R and D activities. An attempt was made to describe and assess specific innovative and passive features implemented in the leading ALWR designs for further plant design safety improvements. The advantages and disadvantages of these innovations in obtaining reliable systems have been considered. Also, this report indicates the importance of uncertainties remaining and identifies the additional work needed. 51 refs, 27 figs, 7 tabs.

  7. Approaches to enhancing radiation safety in cardiovascular imaging: a scientific statement from the American Heart Association.

    Science.gov (United States)

    Fazel, Reza; Gerber, Thomas C; Balter, Stephen; Brenner, David J; Carr, J Jeffrey; Cerqueira, Manuel D; Chen, Jersey; Einstein, Andrew J; Krumholz, Harlan M; Mahesh, Mahadevappa; McCollough, Cynthia H; Min, James K; Morin, Richard L; Nallamothu, Brahmajee K; Nasir, Khurram; Redberg, Rita F; Shaw, Leslee J

    2014-11-01

    Education, justification, and optimization are the cornerstones to enhancing the radiation safety of medical imaging. Education regarding the benefits and risks of imaging and the principles of radiation safety is required for all clinicians in order for them to be able to use imaging optimally. Empowering patients with knowledge of the benefits and risks of imaging will facilitate their meaningful participation in decisions related to their health care, which is necessary to achieve patient-centered care. Limiting the use of imaging to appropriate clinical indications can ensure that the benefits of imaging outweigh any potential risks. Finally, the continually expanding repertoire of techniques that allow high-quality imaging with lower radiation exposure should be used when available to achieve safer imaging. The implementation of these strategies in practice is necessary to achieve high-quality, patient-centered imaging and will require a shared effort and investment by all stakeholders, including physicians, patients, national scientific and educational organizations, politicians, and industry.

  8. A design thinking approach to effective vaccine safety communication.

    Science.gov (United States)

    Seeber, Lea; Michl, Bettina; Rundblad, Gabriella; Trusko, Brett; Schnjakin, Maxim; Meinel, Christoph; Weinberg, Ulrich; Gaedicke, Gerhard; Rath, Barbara

    2015-01-01

    The highly complex and controversial topic of vaccine safety communication warrants innovative, user-centered solutions that would start with gaining mutual respect while taking into account the needs, concerns and underlying motives of patients, parents and physicians. To this end, a non-profit collaborative project was conducted by The Vienna Vaccine Safety Initiative, an international think tank aiming to promote vaccine safety research and communication, and the School of Design Thinking in Potsdam, Germany, the first school for innovation in Europe. The revolutionary concept of the Design Thinking approach is to group students in small multi-disciplinary teams. As a result they can generate ground-breaking ideas by combining their expertise and different points of view. The team agreed to address the following design challenge question: "How might we enable physicians to encourage parents and children to prevent infectious diseases?" The current article describes, step-by step, the ideation and innovation process as well as first tangible outcomes of the project.

  9. Safety analysis for key design features of KALIMER-600 design concept

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Yong-Bum; Kwon, Y. M.; Kim, E. K.; Suk, S. D.; Chang, W. P.; Joeng, H. Y.; Ha, K. S.; Heo, S

    2005-03-01

    KAERI is developing the conceptual design of a Liquid Metal Reactor, KALIMER-600 (Korea Advanced LIquid MEtal Reactor) under the Long-term Nuclear R and D Program. KALIMER-600 addresses key issues regarding future nuclear power plants such as plant safety, economics, proliferation, and waste. In this report, key safety design features are described and safety analyses results for typical ATWS accidents, containment design basis accidents, and flow blockages in the KALIMER design are presented. First, the basic approach to achieve the safety goal and main design features of KALIMER-600 are introduced in Chapter 1, and the event categorization and acceptance criteria for the KALIMER-600 safety analysis are described in Chapter 2, In Chapter 3, results of inherent safety evaluations for the KALIMER-600 conceptual design are presented. The KALIMER-600 core and plant system are designed to assure benign performance during a selected set of events without either reactor control or protection system intervention. Safety analyses for the postulated anticipated transient without scram (ATWS) have been performed using the SSC-K code to investigate the KALIMER-600 system response to the events. The objectives of Chapter 4, are to assess the response of KALIMER-600 containment to the design basis accidents and to evaluate whether the consequences are acceptable or not in the aspect of structural integrity and the exposure dose rate. In Chapter 5, the analysis of flow blockage for KALIMER-600 with the MATRA-LMR-FB code, which has been developed for the internal flow blockage in a LMR subassembly, are described. The cases with a blockage of 6-subchannel, 24-subchannel, and 54-subchannel are analyzed.

  10. Enhancing VHTR Passive Safety and Economy with Thermal Radiation Based Direct Reactor Auxiliary Cooling System

    Energy Technology Data Exchange (ETDEWEB)

    Haihua Zhao; Hongbin Zhang; Ling Zou; Xiaodong Sun

    2012-06-01

    One of the most important requirements for Gen. IV Very High Temperature Reactor (VHTR) is passive safety. Currently all the gas cooled version of VHTR designs use Reactor Vessel Auxiliary Cooling System (RVACS) for passive decay heat removal. The decay heat first is transferred to the core barrel by conduction and radiation, and then to the reactor vessel by thermal radiation and convection; finally the decay heat is transferred to natural circulated air or water systems. RVACS can be characterized as a surface based decay heat removal system. The RVACS is especially suitable for smaller power reactors since small systems have relatively larger surface area to volume ratio. However, RVACS limits the maximum achievable power level for modular VHTRs due to the mismatch between the reactor power (proportional to volume) and decay heat removal capability (proportional to surface area). When the relative decay heat removal capability decreases, the peak fuel temperature increases, even close to the design limit. Annular core designs with inner graphite reflector can mitigate this effect; therefore can further increase the reactor power. Another way to increase the reactor power is to increase power density. However, the reactor power is also limited by the decay heat removal capability. Besides the safety considerations, VHTRs also need to be economical in order to compete with other reactor concepts and other types of energy sources. The limit of decay heat removal capability set by using RVACS has affected the economy of VHTRs. A potential alternative solution is to use a volume-based passive decay heat removal system, called Direct Reactor Auxiliary Cooling Systems (DRACS), to remove or mitigate the limitation on decay heat removal capability. DRACS composes of natural circulation loops with two sets of heat exchangers, one on the reactor side and another on the environment side. For the reactor side, cooling pipes will be inserted into holes made in the outer or

  11. PROVIDING INDUSTRIAL SAFETY IN THE DESIGN OF CHEMICAL FACILITIES

    Directory of Open Access Journals (Sweden)

    S. V. Danilova

    2015-01-01

    Full Text Available Designing of chemical destination requires developers’ particular, careful approach, as malfunctions are dangerous for the whole area in which the facility is located. Efficient and uninterrupted operation of a chemical entity assumes certain tasks, and at the design stage, and during the construction, reconstruction, repair, and maintenance. When designing a crucial question: placing equipment in the technological scheme (nature and the order and connection of separate devices; determine the input parameters of raw materials; establishment of technological parameters of the system; determine the structural characteristics of the devices of the system; selection of process parameters in devices that affect the speed of the process, output and product quality. The main document containing the requirements of industrial safety, chemical and other dangerous objects is the Federal Law of July 21, 1997 № 116-FZ "On industrial safety of hazardous production facilities", as amended on December 31, 2014. It defines and regulates the framework for ensuring the safe operation of hazardous production facilities. The most important part in the development and design of hazardous chemicals is the examination of industrial safety, which is held on the basis of the principles of independence, objectivity, comprehensiveness and completeness of the research carried out by using modern science and technology. Design of chemical facilities is a complex, multifactorial and time-consuming process, which should be regarded as a series of socio-organizational and engineering stages. It is a systematic approach to solving design problems and control of all stages of the life cycle of chemical facilities will provide a high level of safe operation of industrial facilities.

  12. Flight Hardware Packaging Design for Stringent EMC Radiated Emission Requirements

    Science.gov (United States)

    Lortz, Charlene L.; Huang, Chi-Chien N.; Ravich, Joshua A.; Steiner, Carl N.

    2013-01-01

    This packaging design approach can help heritage hardware meet a flight project's stringent EMC radiated emissions requirement. The approach requires only minor modifications to a hardware's chassis and mainly concentrates on its connector interfaces. The solution is to raise the surface area where the connector is mounted by a few millimeters using a pedestal, and then wrapping with conductive tape from the cable backshell down to the surface-mounted connector. This design approach has been applied to JPL flight project subsystems. The EMC radiated emissions requirements for flight projects can vary from benign to mission critical. If the project's EMC requirements are stringent, the best approach to meet EMC requirements would be to design an EMC control program for the project early on and implement EMC design techniques starting with the circuit board layout. This is the ideal scenario for hardware that is built from scratch. Implementation of EMC radiated emissions mitigation techniques can mature as the design progresses, with minimal impact to the design cycle. The real challenge exists for hardware that is planned to be flown following a built-to-print approach, in which heritage hardware from a past project with a different set of requirements is expected to perform satisfactorily for a new project. With acceptance of heritage, the design would already be established (circuit board layout and components have already been pre-determined), and hence any radiated emissions mitigation techniques would only be applicable at the packaging level. The key is to take a heritage design with its known radiated emissions spectrum and repackage, or modify its chassis design so that it would have a better chance of meeting the new project s radiated emissions requirements.

  13. The safety relief valve handbook design and use of process safety valves to ASME and International codes and standards

    CERN Document Server

    Hellemans, Marc

    2009-01-01

    The Safety Valve Handbook is a professional reference for design, process, instrumentation, plant and maintenance engineers who work with fluid flow and transportation systems in the process industries, which covers the chemical, oil and gas, water, paper and pulp, food and bio products and energy sectors. It meets the need of engineers who have responsibilities for specifying, installing, inspecting or maintaining safety valves and flow control systems. It will also be an important reference for process safety and loss prevention engineers, environmental engineers, and plant and process designers who need to understand the operation of safety valves in a wider equipment or plant design context. . No other publication is dedicated to safety valves or to the extensive codes and standards that govern their installation and use. A single source means users save time in searching for specific information about safety valves. . The Safety Valve Handbook contains all of the vital technical and standards informat...

  14. Development of a Quality and Safety Competency Curriculum for Radiation Oncology Residency: An International Delphi Study.

    Science.gov (United States)

    Adleman, Jenna; Gillan, Caitlin; Caissie, Amanda; Davis, Carol-Anne; Liszewski, Brian; McNiven, Andrea; Giuliani, Meredith

    2017-06-01

    To develop an entry-to-practice quality and safety competency profile for radiation oncology residency. A comprehensive list of potential quality and safety competency items was generated from public and professional resources and interprofessional focus groups. Redundant or out-of-scope items were eliminated through investigator consensus. Remaining items were subjected to an international 2-round modified Delphi process involving experts in radiation oncology, radiation therapy, and medical physics. During Round 1, each item was scored independently on a 9-point Likert scale indicating appropriateness for inclusion in the competency profile. Items indistinctly ranked for inclusion or exclusion were re-evaluated through web conference discussion and reranked in Round 2. An initial 1211 items were compiled from 32 international sources and distilled to 105 unique potential quality and safety competency items. Fifteen of the 50 invited experts participated in round 1: 10 radiation oncologists, 4 radiation therapists, and 1 medical physicist from 13 centers in 5 countries. Round 1 rankings resulted in 80 items included, 1 item excluded, and 24 items indeterminate. Two areas emerged more prominently within the latter group: change management and human factors. Web conference with 5 participants resulted in 9 of these 24 items edited for content or clarity. In Round 2, 12 participants rescored all indeterminate items resulting in 10 items ranked for inclusion. The final 90 enabling competency items were organized into thematic groups consisting of 18 key competencies under headings adapted from Deming's System of Profound Knowledge. This quality and safety competency profile may inform minimum training standards for radiation oncology residency programs. Copyright © 2017 Elsevier Inc. All rights reserved.

  15. European Workshop Industrical Computer Science Systems approach to design for safety

    Science.gov (United States)

    Zalewski, Janusz

    1992-01-01

    This paper presents guidelines on designing systems for safety, developed by the Technical Committee 7 on Reliability and Safety of the European Workshop on Industrial Computer Systems. The focus is on complementing the traditional development process by adding the following four steps: (1) overall safety analysis; (2) analysis of the functional specifications; (3) designing for safety; (4) validation of design. Quantitative assessment of safety is possible by means of a modular questionnaire covering various aspects of the major stages of system development.

  16. Radiation safety of handheld mobile phones and base stations

    Energy Technology Data Exchange (ETDEWEB)

    Jokela, K.; Leszczynski, D.; Paile, W.; Salomaa, S.; Puranen, L.; Hyysalo, P

    1999-01-01

    The recent expansion of personal telecommunications has led to a rapid increase in the exposure of people to the radio-frequency (RF) radiation. Although the mobile phones are low power devices, the antenna is so close to the head that the local exposure may slightly exceed 2 W/kg, the current exposure limit for the local specific absorption rate SAR for the general public. The increase in the temperature is, however, too small to have any physiological significance. On the basis of experiments with cell cultures it is possible that other biological effects caused by some unknown non-thermal mechanism exist, but thus far there is no conclusive biological or epidemiological evidence to suggest any diseases or adverse physiological changes below the thermal threshold. The use of a mobile phone by a person wearing a pace-maker, is not recommended, if the immunity of the pace-maker has not been assured. The exposure caused by the base stations is in all practical cases well below the power density limits for general public. (author) 118 refs.

  17. Instructor qualification for radiation safety training at a national laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Trinoskey, P.A.

    1994-10-01

    Prior to 1993, Health Physics Training (HPT) was conducted by the Lawrence Livermore National Laboratory (LLNL) health physics group. The job requirements specified a Masters Degree and experience. In fact, the majority of Health Physicists in the group were certified by the American Board of Health Physics. Under those circumstances, it was assumed that individuals in the group were technically qualified and the HPT instructor qualification stated that. In late 1993, the Health Physics Group at the LLNL was restructured and the training function was assigned to the training group. Additional requirements for training were mandated by the Department of Energy (DOE), which would necessitate increasing the existing training staff. With the need to hire, and the policy of reassignment of employees during downsizing, it was imperative that formal qualification standards be developed for technical knowledge. Qualification standards were in place for instructional capability. In drafting the new training qualifications for instructors, the requirements of a Certified Health Physicists had to be modified due to supply and demand. Additionally, for many of the performance-based training courses, registration by the National Registry of Radiation Protection Technologists is more desirable. Flexibility in qualification requirements has been incorporated to meet the reality of ongoing training and the compensation for desirable skills of individuals who may not meet all the criteria. The qualification requirements for an instructor rely on entry-level requirements and emphasis on goals (preferred) and continuing development of technical and instructional capabilities.

  18. Global real-time dose measurements using the Automated Radiation Measurements for Aerospace Safety (ARMAS) system

    Science.gov (United States)

    Tobiska, W. Kent; Bouwer, D.; Smart, D.; Shea, M.; Bailey, J.; Didkovsky, L.; Judge, K.; Garrett, H.; Atwell, W.; Gersey, B.; Wilkins, R.; Rice, D.; Schunk, R.; Bell, D.; Mertens, C.; Xu, X.; Wiltberger, M.; Wiley, S.; Teets, E.; Jones, B.; Hong, S.; Yoon, K.

    2016-11-01

    The Automated Radiation Measurements for Aerospace Safety (ARMAS) program has successfully deployed a fleet of six instruments measuring the ambient radiation environment at commercial aircraft altitudes. ARMAS transmits real-time data to the ground and provides quality, tissue-relevant ambient dose equivalent rates with 5 min latency for dose rates on 213 flights up to 17.3 km (56,700 ft). We show five cases from different aircraft; the source particles are dominated by galactic cosmic rays but include particle fluxes for minor radiation periods and geomagnetically disturbed conditions. The measurements from 2013 to 2016 do not cover a period of time to quantify galactic cosmic rays' dependence on solar cycle variation and their effect on aviation radiation. However, we report on small radiation "clouds" in specific magnetic latitude regions and note that active geomagnetic, variable space weather conditions may sufficiently modify the magnetospheric magnetic field that can enhance the radiation environment, particularly at high altitudes and middle to high latitudes. When there is no significant space weather, high-latitude flights produce a dose rate analogous to a chest X-ray every 12.5 h, every 25 h for midlatitudes, and every 100 h for equatorial latitudes at typical commercial flight altitudes of 37,000 ft ( 11 km). The dose rate doubles every 2 km altitude increase, suggesting a radiation event management strategy for pilots or air traffic control; i.e., where event-driven radiation regions can be identified, they can be treated like volcanic ash clouds to achieve radiation safety goals with slightly lower flight altitudes or more equatorial flight paths.

  19. Standardized Radiation Shield Design Methods: 2005 HZETRN

    Science.gov (United States)

    Wilson, John W.; Tripathi, Ram K.; Badavi, Francis F.; Cucinotta, Francis A.

    2006-01-01

    Research committed by the Langley Research Center through 1995 resulting in the HZETRN code provides the current basis for shield design methods according to NASA STD-3000 (2005). With this new prominence, the database, basic numerical procedures, and algorithms are being re-examined with new methods of verification and validation being implemented to capture a well defined algorithm for engineering design processes to be used in this early development phase of the Bush initiative. This process provides the methodology to transform the 1995 HZETRN research code into the 2005 HZETRN engineering code to be available for these early design processes. In this paper, we will review the basic derivations including new corrections to the codes to insure improved numerical stability and provide benchmarks for code verification.

  20. Sequential circuit design for radiation hardened multiple voltage integrated circuits

    Science.gov (United States)

    Clark, Lawrence T.; McIver, III, John K.

    2009-11-24

    The present invention includes a radiation hardened sequential circuit, such as a bistable circuit, flip-flop or other suitable design that presents substantial immunity to ionizing radiation while simultaneously maintaining a low operating voltage. In one embodiment, the circuit includes a plurality of logic elements that operate on relatively low voltage, and a master and slave latches each having storage elements that operate on a relatively high voltage.

  1. [Systemic approach to ecologic safety at objects with radiation jeopardy, involved into localization of low and medium radioactive waste].

    Science.gov (United States)

    Veselov, E I

    2011-01-01

    The article deals with specifying systemic approach to ecologic safety of objects with radiation jeopardy. The authors presented stages of work and algorithm of decisions on preserving reliability of storage for radiation jeopardy waste. Findings are that providing ecologic safety can cover 3 approaches: complete exemption of radiation jeopardy waste, removal of more dangerous waste from present buildings and increasing reliability of prolonged localization of radiation jeopardy waste at the initial place. The systemic approach presented could be realized at various radiation jeopardy objects.

  2. Key Performance Indicators in the Evaluation of the Quality of Radiation Safety Programs.

    Science.gov (United States)

    Schultz, Cheryl Culver; Shaffer, Sheila; Fink-Bennett, Darlene; Winokur, Kay

    2016-08-01

    Beaumont is a multiple hospital health care system with a centralized radiation safety department. The health system operates under a broad scope Nuclear Regulatory Commission license but also maintains several other limited use NRC licenses in off-site facilities and clinics. The hospital-based program is expansive including diagnostic radiology and nuclear medicine (molecular imaging), interventional radiology, a comprehensive cardiovascular program, multiple forms of radiation therapy (low dose rate brachytherapy, high dose rate brachytherapy, external beam radiotherapy, and gamma knife), and the Research Institute (including basic bench top, human and animal). Each year, in the annual report, data is analyzed and then tracked and trended. While any summary report will, by nature, include items such as the number of pieces of equipment, inspections performed, staff monitored and educated and other similar parameters, not all include an objective review of the quality and effectiveness of the program. Through objective numerical data Beaumont adopted seven key performance indicators. The assertion made is that key performance indicators can be used to establish benchmarks for evaluation and comparison of the effectiveness and quality of radiation safety programs. Based on over a decade of data collection, and adoption of key performance indicators, this paper demonstrates one way to establish objective benchmarking for radiation safety programs in the health care environment.

  3. Are we failing to communicate? Internet-based patient education materials and radiation safety

    Energy Technology Data Exchange (ETDEWEB)

    Hansberry, David R., E-mail: hansbedr@njms.rutgers.edu; Ramchand, Tekchand, E-mail: ramchate@njms.rutgers.edu; Patel, Shyam, E-mail: patel288@njms.rutgers.edu; Kraus, Carl, E-mail: krauscf@njms.rutgers.edu; Jung, Jin, E-mail: jungjk@njms.rutgers.edu; Agarwal, Nitin, E-mail: nitin.agarwal@rutgers.edu; Gonzales, Sharon F., E-mail: gonzalsh@njms.rutgers.edu; Baker, Stephen R., E-mail: bakersr@njms.rutgers.edu

    2014-09-15

    Introduction: Patients frequently turn to the Internet when seeking answers to healthcare related inquiries including questions about the effects of radiation when undergoing radiologic studies. We investigate the readability of online patient education materials concerning radiation safety from multiple Internet resources. Methods: Patient education material regarding radiation safety was downloaded from 8 different websites encompassing: (1) the Centers for Disease Control and Prevention, (2) the Environmental Protection Agency, (3) the European Society of Radiology, (4) the Food and Drug Administration, (5) the Mayo Clinic, (6) MedlinePlus, (7) the Nuclear Regulatory Commission, and (8) the Society of Pediatric Radiology. From these 8 resources, a total of 45 articles were analyzed for their level of readability using 10 different readability scales. Results: The 45 articles had a level of readability ranging from 9.4 to the 17.2 grade level. Only 3/45 (6.7%) were written below the 10th grade level. No statistical difference was seen between the readability level of the 8 different websites. Conclusions: All 45 articles from all 8 websites failed to meet the recommendations set forth by the National Institutes of Health and American Medical Association that patient education resources be written between the 3rd and 7th grade level. Rewriting the patient education resources on radiation safety from each of these 8 websites would help many consumers of healthcare information adequately comprehend such material.

  4. Review and Analysis of Development of "Safety by Design" Requirements

    Energy Technology Data Exchange (ETDEWEB)

    Vance, Scott A.; Hockert, John

    2009-10-20

    This report, the deliverable for Task 4 of the NA-243 Safeguards by Design Work Plan for Fiscal Year 2009, develops the lessons to be learned for the institutionalization of Safeguards By Design (SBD) from the Department of Energy (DOE) experience developing and implementing DOE-STD-1189, Integration of Safety into the Design Process. This experience was selected for study because of the similarity of the challenges of integrating safety and safeguards into the design process. Development of DOE-STD-1189 began in January 2006 and the standard was issued for implementation in March 2008. The process was much more time consuming than originally anticipated and might not have come to fruition had senior DOE management been less committed to its success. Potentially valuable lessons can be learned from both the content and presentation of the integration approach in DOE-STD-1189 and from the DOE experience in developing and implementing DOE-STD-1189. These lessons are important because the instutionalization of SBD does not yet appear to have the level of senior management commitment afforded development and implementation of DOE-STD-1189.

  5. PGSFR Core Thermal Design Procedure to Evaluate the Safety Margin

    Energy Technology Data Exchange (ETDEWEB)

    Choi, Sun Rock; Kim, Sang-Ji [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2014-10-15

    The Korea Atomic Energy Research Institute (KAERI) has performed a SFR design with the final goal of constructing a prototype plant by 2028. The main objective of the SFR prototype plant is to verify the TRU metal fuel performance, reactor operation, and transmutation ability of high-level wastes. The core thermal design is to ensure the safe fuel performance during the whole plant operation. Compared to the critical heat flux in typical light water reactors, nuclear fuel damage in SFR subassemblies arises from a creep induced failure. The creep limit is evaluated based on the maximum cladding temperature, power, neutron flux, and uncertainties in the design parameters, as shown in Fig. 1. In this work, the core thermal design procedures are compared to verify the present PGSFR methodology based on the nuclear plant design criteria/guidelines and previous SFR thermal design methods. The PGSFR core thermal design procedure is verified based on the nuclear plant design criteria/guidelines and previous methods in LWRs and SFRs. The present method aims to directly evaluate the fuel cladding failure and to assure more safety margin. The 2 uncertainty is similar to 95% one-side tolerance limit of 1.96 in LWRs. The HCFs, ITDP, and MCM reveal similar uncertainty propagation for cladding midwall temperature for typical SFR conditions. The present HCFs are mainly employed from the CRBR except the fuel-related uncertainty such as an incorrect fuel distribution. Preliminary PGSFR specific HCFs will be developed by the end of 2015.

  6. Conceptual Design of Passive Safety System for Lead-Bismuth Cooled Fast Reactor

    Science.gov (United States)

    Abdullah, A. G.; Nandiyanto, A. B. D.

    2016-04-01

    This paper presents the results of the conceptual design of passive safety systems for reactor power 225 MWth using Pb-Bi coolant. Main purpose of this research is to design of heat removal system from the reactor wall. The heat from the reactor wall is removed by RVACS system using the natural circulation from the atmosphere around the reactor at steady state. The calculation is performed numerically using Newton-Raphson method. The analysis involves the heat transfer systems in a radiation, conduction and natural convection. Heat transfer calculations is performed on the elements of the reactor vessel, outer wall of guard vessel and the separator plate. The simulation results conclude that the conceptual design is able to remove heat 1.33% to 4.67% from the thermal reactor power. It’s can be hypothesized if the reactor had an accident, the system can still overcome the heat due to decay.

  7. Computer aided microbial safety design of food processes.

    Science.gov (United States)

    Schellekens, M; Martens, T; Roberts, T A; Mackey, B M; Nicolaï, B M; Van Impe, J F; De Baerdemaeker, J

    1994-12-01

    To reduce the time required for product development, to avoid expensive experimental tests, and to quantify safety risks for fresh products and the consequence of processing there is a growing interest in computer aided food process design. This paper discusses the application of hybrid object-oriented and rule-based expert system technology to represent the data and knowledge of microbial experts and food engineers. Finite element models for heat transfer calculation routines, microbial growth and inactivation models and texture kinetics are combined with food composition data, thermophysical properties, process steps and expert knowledge on type and quantity of microbial contamination. A prototype system has been developed to evaluate changes in food composition, process steps and process parameters on microbiological safety and textual quality of foods.

  8. Code conversion for system design and safety analysis of NSSS

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Hae Cho; Kim, Young Tae; Choi, Young Gil; Kim, Hee Kyung [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1996-01-01

    This report describes overall project works related to conversion, installation and validation of computer codes which are used in NSSS design and safety analysis of nuclear power plants. Domain/os computer codes for system safety analysis are installed and validated on Apollo DN10000, and then Apollo version are converted and installed again on HP9000/700 series with appropriate validation. Also, COOLII and COAST which are cyber version computer codes are converted into versions of Apollo DN10000 and HP9000/700, and installed with validation. This report details whole processes of work involved in the computer code conversion and installation, as well as software verification and validation results which are attached to this report. 12 refs., 8 figs. (author)

  9. Cascade Distillation System Design for Safety and Mission Assurance

    Science.gov (United States)

    Sarguisingh, Miriam; Callahan, Michael R.; Okon, Shira

    2015-01-01

    Per the NASA Human Health, Life Support and Habitation System Technology Area 06 report "crewed missions venturing beyond Low-Earth Orbit (LEO) will require technologies with improved reliability, reduced mass, self-sufficiency, and minimal logistical needs as an emergency or quick-return option will not be feasible".1 To meet this need, the development team of the second generation Cascade Distillation System (CDS 2.0) chose a development approach that explicitly incorporate consideration of safety, mission assurance, and autonomy. The CDS 2.0 preliminary design focused on establishing a functional baseline that meets the CDS core capabilities and performance. The critical design phase is now focused on incorporating features through a deliberative process of establishing the systems failure modes and effects, identifying mitigation strategies, and evaluating the merit of the proposed actions through analysis and test. This paper details results of this effort on the CDS 2.0 design.

  10. A framework for quality improvement and patient safety education in radiation oncology residency programs.

    Science.gov (United States)

    Yeung, Anamaria; Greenwalt, Julie

    2015-01-01

    In training future radiation oncologists, we must begin to focus on training future QI specialists. Our patients are demanding better quality and safer care, and accrediting bodies are requiring it. We must equip radiation oncology trainees to be leaders in this new world. To that end, a QI/PS educational program should contain 2 components: a didactic portion focused on teaching basic QI tools as well as an overview of the quality and safety goals of the institution, and an experiential component, ideally a resident-led QI project mentored by an expert faculty member and that is linked to the department's and institution's goals.

  11. Fire safety design of atria. Valokatteisten tilojen palotekniikkaa

    Energy Technology Data Exchange (ETDEWEB)

    Keski-Rahkonen, O.; Bjoerkman, J. (eds.) (Technical Research Centre of Finland, Espoo (Finland). Fire Technology Lab.)

    1992-01-01

    Atria, halls and other large size glass buildings have recently become very popular in public buildings in Finland. Atria are large rooms, and constructed from new type of construction parts which present high demands on their fire protection. This publication consists of three parts. The first parts deals with design of atria according to Finnish and foreign building codes. Especially safety of egress, active fire protection, smoke venting as well as materials and structures are discussed. The second part deals detailed with smoke venting applying a recent NFPA Guide on atrium inside an office building. Additionally, the same object is simulated numerically using a zone model code BRI2. The third part deals with thermal load of structural members of an atrium inside a big office building applying numerical fire simulation using zone model code BRI2. The simulation yields hot layer temperature and smoke layer height inside the building. The report is a review on the fire protection design principles starting from the simple traditional prescriptive calculation rules. The examples of utilization of numerical fire simulation for solving special problems in fire safety design are included.

  12. Safety Culture in activities involving ionising radiation-education project

    Energy Technology Data Exchange (ETDEWEB)

    Sahyun, A.; Sordi, G. M.; Sanches, M. P.; Levy, P. J.; Levy, D. S.

    2004-07-01

    The Brazilian National Commission of Nuclear Energy (CNEN) requires a Radiological Protection Plan for all installations authorized to work with radioactive material and a qualified Radiological Protection Supervisor. The CNEN requires the certification of practical experience in the area plus a qualification exam, applied by them. ATOMO, has opted to develop on-line courses, using multimedia resources, available at the time this congress takes place. OMICCRON, a multimedia enterprise, is in charge of the program and design. First, the research and brochures have to be adapted for the electronic language, through links, hot words and icons, especially developed for additional information. Besides the images and graphs from the original brochures, Omiccron developed, in graphic computing, specific animation explaining the procedures in more details, illustrating and simplifying the comprehension of the more complex subjects. The CD ROM presentation was enhanced with some slide displays, automatically changing the pictures, as the explanations are given. For practical visualization of these complex and important procedures, the CD also shows some technical videos. At the end of each unit covering a specific subject, the students will be submitted to self-evaluation tests, for more profitable results. This CD is not only an electronic brochure, but mainly an on-line course with weekly Internet support via e-mail or chat site, where the learners will access the instructors and a frequent questions database, useful links and related sites, permanently upgraded. Before going to the following module, the learner has to pass a written test prepared by ATOMO, via Internet. At the end of the course, a certificate will be given. The control will be made through the use of a password, provided for the authorized company and /or users. The instructors will evaluate the learners' advancement by Internet. In the case of companies, this tool will be equally offered, by using

  13. [Use of system of radiation and hygienic certification of territories for ensuring supervision of radiation safety of the population at the regional level].

    Science.gov (United States)

    Rakitin, I A; Gorsky, G A

    2013-01-01

    In article the experience of Department of Federal Service for Supervision of Consumer Rights Protection and Human Welfare in St. Petersburg, related with performing of radiation and hygienic certification of the organizations and territories is considered. The annual assessment of individual and collective risks of emergence of stochastic effects for the population and the personnel of radiation objects shows the significance of radiation and hygienic certification for hygienic justification of the measures directed on a decrease in radiation exposure of the population from technogenic, natural and medical sources of ionizing radiation. The long-term analysis of the structure and dynamics of annual individual and collective effective doses of radiation of the population within the framework of radiation and hygienic certification and the Universal state system for control and accounting for individual doses of radiation of citizens allows to estimate efficiency of address target programs for the solution of actual problems of radiation safety at the regional level.

  14. Design data and safety features of commerical nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Heddleson, F.A.

    1976-06-01

    Design data, safety features, and site characteristics are summarized for 34 nuclear power units in 17 power stations in the United States. Six pages of data are presented for each plant, consisting of thermal-hydraulic and nuclear factors, containment features, emergency-core-cooling systems, site features, circulating water system data, and miscellaneous factors. An aerial perspective is also presented for each plant. This volume covers Light Water Reactors (LWRs) with dockets 50-508 through 50-549, four HTGRs--50-171, 50-267, 50-450/451, 50-463/464, the Atlantic Floating Station 50-477/478, and the Clinch River Breeder 50-537.

  15. RESILIENT INTERFACE DESIGN FOR SAFETY-CRITICAL EMBEDDED AUTOMOTIVE SOFTWARE

    Directory of Open Access Journals (Sweden)

    Harald Sporer

    2016-01-01

    Full Text Available The replacement of the former, purely mechanical, functionality with mechatronics-based solutions, the introduction of new propulsion technologies, and the connection of cars to their environment are just a few reasons for the continuously increasing electrical and/or electronic system (E/E system complexity in modern passenger cars. Smart methodologies and techniques have been introduced in system development to cope with these new challenges. A topic that is often neglected is the definition of the interface between the hardware and software subsystems. However, during the development of safety-critical E/E systems, according to the automotive functional safety standard ISO 26262, an unambiguous definition of the hardware-software interface (HSI has become vital. This paper presents a domain-specific modelling approach for mechatronic systems with an integrated hardware-software interface definition feature. The newly developed model-based domain-specific language is tailored to the needs of mechatronic system engineers and supports the system’s architectural design including the interface definition, with a special focus on safety-criticality.

  16. EURISOL-DS Multi‐MW Target: Radiological Protection, Radiation Safety and Shielding Aspects

    CERN Document Server

    Y. Romanets and R. Luís (ITN)

    The objective of this work was to carry out a detailed study and analysis of all aspects related toradioprotection and radiation safety of the spallation target area and the whole spaces reservedfor the fission targets and spallation target maintenance. Operational and no‐operationalconditions were considered for an evaluation of the radiation safety conditions.An analysis of the proposed shielding dimensions and configuration was performed for thesystem during operation time. Parameters as activation, dose rate, energy deposition, etc. aremore important for the no‐operation period, in order to evaluate the hazard level anddetermine the staff access type to the maintenance areas (direct or remote control).Such elements as the fission targets and the whole structure involved on it were studied in moredetail because of the disposal issues, after operation. Activation, dose rate and residual nuclideswere studied for each element of the assembly. All parameters were analyzed according to their...

  17. To control the nuclear safety and the radiation protection; Controler la surete nucleaire et la radioprotection

    Energy Technology Data Exchange (ETDEWEB)

    Lacoste, A.C. [Direction Generale de la Surete Nucleaire et de la Radioprotection, 75 - Paris (France); Bordarier, Ph. [Autorite de Surete Nucleaire (ASN), 75 - Paris (France); Saint-Raymond, Ph. [Conseil General des Mines, 75 - Paris (France); Repussard, J. [Institut de Radioprotection et de Surete Nucleaire (IRSN), 92 - Clamart (France); Gouze, J.R. [Apave Groupe, 75 - Paris (France); Degos, L. [Haute Autorite de Sante, 93 - Saint-Denis La Plaine (France); Massart, S.; Wiroth, P.; Thezee, Ch.; Petit, G. [Electricite de France (EDF), 75 - Paris (France); Cahen, B.; Hubert, I.; Wiroth, P.; Thezee, Ch.; Petit, G. [Ministere de l' Ecologie et du Developpement Durable, Direction de la Prevention des Pollutions et des Risques (DPPR), 75 - Paris (France); Kaufer, B. [Organisation for Economic Co-Operation and Development, Nuclear Energy Agency (AEN/OCDE), 75 - Paris (France); Taniguchi, T. [Agence Internationale de l' Energie Atomique (AIEA), Vienna (Austria); Revol, H. [Office Parlementaire d' Evaluation des Choix Scientifiques et Technologiques (OPECST), 75 - Paris (France)

    2005-10-15

    Publishing this dossier, the aim is to present the principles and the variety of issues linked to nuclear safety and radiation protection supervision, and the main strategic choices made to use efficiently and effectively A.S.N. supervision means. A.S.N. is responsible for nuclear safety and radiation protection supervision. A.S.N. has to be itself evaluated and supervised by external bodies. The Parliament Office for Evaluation of Scientific and Technological Options (O.P.E.C.S.T.) supervises it; the foreign peers watch and A.S.N. has to be the object of an international audit conducted by its peers under the leadership of I.A.E.A. by the beginning of 2007. (N.C.)

  18. Public information and education on radiation safety and protection in Indonesia

    Energy Technology Data Exchange (ETDEWEB)

    Djaloeis, Azhar [National Atomic Energy Agency, Jalan KH Abdul Rohim, Mampang Prapatan, Jakarta (Indonesia)

    1999-09-01

    This paper presents a brief overview of public information and education concerning nuclear science and technology in general and radiation safety and protection in particular in Indonesia from the perspective of promoting the development and utilization of nuclear science and technology in the country. The role of nuclear science and technology in Indonesia is first introduced, followed by an overview of the nuclear activities in the country. Basic considerations, major objectives of the public information and education program on radiation safety and protection as well as basic and operational strategies to achieve those objectives are then presented. Major programs including highlights of the past and present activities as well as prospect on future course of actions are discussed. (author)

  19. Level of knowledge among the population of radiation safety basic issues

    Directory of Open Access Journals (Sweden)

    S. A. Zelencova

    2015-01-01

    Full Text Available The goal of research was to determine the level of knowledge among the population on issues like sources of ionising radiation, methods of ionising radiation measurement, measures of self-protection in case of threating or actual radioactive pollution in the district, and to study self-estimation by the population of their knowledge of radiation safety issues. Research was carried out using the method of questioning of population groups in three regions close to the places of previous peaceful nuclear explosions (Arkhangelsk, Murmansk and Tyumen regions, and in five Far East regions of the Russian Federation (Kamchatka, Khabarovsk, Primorsky, Magadan and South-Sakhalin regions after radiation accident in Japan at "Fukushima-1" NPP. This research included processing of 243 questionnaires from the regions close to places of previous peaceful nuclear explosions and 216 questionnaires from the Far East regions.The analysis of obtained questioning results enabled to make the following conclusions: the level of knowledge among the population about the basic concepts of radiation safety appeared to be generally low among respondents of all eight territories. Considerable number of respondents in seven groups correctly mentioned the x-ray device as a source of ionising radiation (from 71 to 88 % of answers. In Murmansk region – only 52 % of the answers. Respondents of the same seven groups often correctly answered the question on how to detect ionising radiation (only with devices – from 68 to 98 % in different groups. The smallest number of correct answers to this question (42 % is also noted among respondents from the Murmansk region.Level of knowledge on self-protection measures at threating or actual radioactive pollution of the places of residence appeared a little higher among the Far East region population, who had actual concerns regarding the threat of radioactive pollution at the present time. However, in all eight investigated groups

  20. Sweden's Co-operation with Eastern Europe in Radiation Safety 2011

    Energy Technology Data Exchange (ETDEWEB)

    Dassen, Lars van; Andersson, Sarmite; Bejarano, Gabriela; Chirman, Inessa; Delalic, Zlatan; Ekblad, Christer; Karlberg, Olof; Klasen, Haakan; Olsson, Kjell; Sandberg, Viviana; Stenberg, Tor; Turner, Roland; Wickman, Barbro

    2012-11-01

    In 2011, the Swedish Radiation Safety Authority implemented co-operation projects in Russia, Ukraine, Georgia, Lithuania and Moldova, based on instructions from the Swedish Government and agreements with the European Union and the Swedish International Development Co-operation Agency, SIDA. The projects aim at achieving a net contribution to radiation safety (including nuclear safety, nuclear security, waste management, nonproliferation as well as radiation protection and emergency preparedness) for the benefit of the host countries and the international community as well as Sweden. This report gives an overview of all the projects implemented in 2011. The project managers from SSM are the cornerstones of our successful work, but all the efforts and dedication by staff members of the facilities and authorities in the mentioned countries are indispensable for the long-term positive outcomes. This report is meant to serve as a detailed account regarding SSM's efforts as part of the Swedish international activities, on which Sweden will report to the Nuclear Security Summit in Seoul. The parties to the G-8 Global Partnership have in June 2011 extended the Global Partnership for ten more years, till 2022. Other international frameworks, such as the UNSC Resolution 1540, remain a vibrant instrument by which UN Member States can exchange information on security concerns and request assistance from each other. The projects that SSM implements in Moldova and Georgia have a reference to the aims and purposes of the UNSC Resolution 1540. Much work has been done in the fields of nuclear security and safety, but there are still lots of issues that need to be taken care of. As such, SSM will continue to do its part for nuclear safety and security at the international level, along the lines and priorities set by our Government.

  1. A Radiation Hardened by Design CMOS ASIC for Thermopile Readouts

    Science.gov (United States)

    Quilligan, G.; Aslam, S.; DuMonthier, J.

    2012-01-01

    A radiation hardened by design (RHBD) mixed-signal application specific integrated circuit (ASIC) has been designed for a thermopile readout for operation in the harsh Jovian orbital environment. The multi-channel digitizer (MCD) ASIC includes 18 low noise amplifier channels which have tunable gain/filtering coefficients, a 16-bit sigma-delta analog-digital converter (SDADC) and an on-chip controller. The 18 channels, SDADC and controller were designed to operate with immunity to single event latchup (SEL) and to at least 10 Mrad total ionizing dose (TID). The ASIC also contains a radiation tolerant 16-bit 20 MHz Nyquist ADC for general purpose instrumentation digitizer needs. The ASIC is currently undergoing fabrication in a commercial 180 nm CMOS process. Although this ASIC was designed specifically for the harsh radiation environment of the NASA led JEO mission it is suitable for integration into instrumentation payloads 011 the ESA JUICE mission where the radiation hardness requirements are slightly less stringent.

  2. Unified methodology for fire safety assessment and optimal design

    Energy Technology Data Exchange (ETDEWEB)

    Shetty, N.K.; Deaves, D.M.; Gierlinski, J.T. [WS Atkins Consultants Ltd., Epsom (United Kingdom); Dogliani, M. [Registro Italiano Navale, Genova (Italy)

    1996-12-31

    The paper presents a unified, fully-probabilistic approach to fire safety assessment and optimal design of fire protection on offshore topside structures. The methodology has been developed by integrating Quantitative Risk Analysis (QRA) techniques with the modern methods of Structural System Reliability Analysis (SRA) and Reliability Based Design Optimization (RBDO). The integration has been achieved by using platform-specific extended event-trees which model in detail the escalation paths leading to the failure of Temporary Refuge (TR), Escape, Evacuation and Rescue (EER) systems or structural collapse of the topside. Probabilities of events for which historical data are not generally available are calculated using structural reliability methods. The optimization of fire protection is performed such that the total expected cost of the protection system and the cost of failure of the platform (loss of life, loss of asset, environmental damage) is minimized while satisfying reliability constraints.

  3. ON NEW RECOMMENDATIONS OF THE INTERNATIONAL COMMISSION ON RADIOLOGICAL PROTECTION (ICRP PART 1: RADIATION SAFETY BASIS.

    Directory of Open Access Journals (Sweden)

    I. K. Romanovich

    2008-01-01

    Full Text Available ICRP Publication 103 was issued in November, 2007.  The new approaches of ICRP to maintenance radiation protection are formulated in this publication. These recommendations are the further development of the previous document - the ICRP 60 Publication. The new data, allowing to specify or reconsider quantitative protection criteria have appeared after 1990. ICRP suggests to use a number of new ideas and concepts as base principles of radiation protection maintenance. Taking into account that the standard of radiating safety of Russia (RSSR [3] which is used in Russian Federation since 1999 have been developed in a view of the 60 publication and other international publications, and also in a view of national experience of radiation safety maintenance. It is very important to study and comprehend innovations of ICRP, and also to estimate an opportunity and an acceptability of their realization by development of new edition of RSSR. In the first and second parts of present article the review of the new ICRP Recommendations and some judgments concerning an opportunity of the refraction of Publication ICRP positions in the future RSSR is given.

  4. Radiation safety and protection in U.S. dental hygiene programs.

    Science.gov (United States)

    Farman, A G; Hunter, N; Grammer, S

    1986-07-01

    A survey of radiation safety and protection measures used by programs teaching dental hygiene indicated some areas for concern. No barriers or radiation shieldings were used between operator and patient in four programs. Radiation monitoring devices were not worn by faculty operators in 16% of the programs. Fewer than half of the programs used thyroid shields for patients on a routine basis. Insufficient filtration for the kilovolt peak employed was used by 14% of the programs, and for 19% more the filtration was unknown or unspecified. Three programs used closed cones. Rectangular collimation was not used at all by 63% of the programs, and only 20% used E speed film routinely. Quality assurance for equipment maintenance and for film processing were in place at only 54% and 49% of the programs, respectively.

  5. The cohort of the atomic bomb survivors major basis of radiation safety regulations

    CERN Document Server

    Rühm, W; Nekolla, E A

    2006-01-01

    Since 1950 about 87 000 A-bomb survivors from Hiroshima and Nagasaki have been monitored within the framework of the Life Span Study, to quantify radiation-induced late effects. In terms of incidence and mortality, a statistically significant excess was found for leukemia and solid tumors. In another major international effort, neutron and gamma radiation doses were estimated, for those survivors (Dosimetry System DS02). Both studies combined allow the deduction of risk coefficients that serve as a basis for international safety regulations. As an example, current results on all solid tumors combined suggest an excess relative risk of 0.47 per Sievert for an attained age of 70 years, for those who were exposed at an age of 30 years. After exposure to an effective dose of one Sievert the solid tumor mortality would thus be about 50% larger than that expected for a similar cohort not exposed to any ionizing radiation from the bombs.

  6. Radiation Authority and Nuclear Safety in Finland (STUK); La autoridad de Radiacion y Seguridad Nuclear de Finlandia (STUK)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-07-01

    Created in 1958 as an institute in charge of inspecting radioactive equipment used in hospitals, STUK is nowadays a specialised organisation whose functions cover all fields for applying radiation and nuclear safety. (Author)

  7. Acoustic design sensitivity analysis of structural sound radiation

    Institute of Scientific and Technical Information of China (English)

    许智生

    2009-01-01

    This paper presents an acoustic design sensitivity(ADS)analysis on sound radiation of structures by using the boundary element method(BEM).We calculated the velocity distribution of the thin plate by analytical method and the surface sound pressure by Rayleigh integral,and expressed the sound radiation power of the structure in a positive definite quadratic form of the Hermitian with an impedance matrix.The ADS analysis of the plate was thus translated into the analysis of structure dynamic sensitivity and ...

  8. Thin film design for advanced thermochromic smart radiator devices

    Institute of Scientific and Technical Information of China (English)

    Feng Yu-Dong; Wang Zhi-Min; Ma Ya-Li; Zhang Fu-Jia

    2007-01-01

    This paper describes the research on the materials and design methods for advanced smart radiator devices (SRDs) on large-area flexible substrates utilized on spacecraft. The functional material is thermochromic vanadium dioxide. The coating design of 3RD is similar to the design of broadband filter coatings in a mid-infrared region. The multilayer coatings have complex structures. Coating materials must be highly transparent in a required spectrum region and also mechanically robust enough to endure the influence from the rigorous environments of outer space. The number of layers must be very small, suitable for the deposition on large-area flexible substrates. All the coatings are designed initially based on optical calculation and practical experience, and then optimized by the TFCALC software. Several designs are described and compared with each other. The results show that the emittance variability of the designed SRDs is great than 400%, more advanced than the reported ones.

  9. Design and development of a portable gamma radiation monitor

    Energy Technology Data Exchange (ETDEWEB)

    Munir, M.; Khalid, M. [Health Physics Division, Directorate of Systems and Services, Pakistan Institute of Nuclear Science and Technology (PINSTECH), Nilore, Islamabad 45650 (Pakistan); Ahmad, N.; Sohail, S.; Naveed, R. A.; Rafiq, M. Q. [Pakistan Institute of Engineering and Applied Sciences (PIEAS), P. O. Nilore, Islamabad 45650 (Pakistan)

    2009-07-15

    A portable gamma radiation monitor has been designed and developed. The monitor can be used effectively in the dose range from 0.07 to 500 mGy/h due to gamma rays of energy greater than 65 keV. The monitor overestimated radiation doses and the uncertainty in the measured dose rate has been found to be {<=}30%. The response of the monitor can be considered isotropic within an acceptable error of {+-}30%. Provision has also been added to use the monitor as an installed radiation monitor. In installed mode, it can be operated from a remote location up to 1 km and the timing history can be stored on a personal computer.

  10. Laparoscopic ovarian transposition before pelvic radiation in rectal cancer patient: safety and feasibility

    Directory of Open Access Journals (Sweden)

    Al-Asari Sami

    2012-09-01

    Full Text Available Abstract Background Infertility due to pelvic radiation for advanced rectal cancer treatment is a major concern particularly in young patients. Pre-radiation laparoscopic ovarian transposition may offer preservation of ovarian function during the treatment however its use is limited. Aim The study investigates the safety, feasibility and effectiveness of pre-radiation laparoscopic ovarian transposition and its effect on ovarian function in the treatment o locally advanced rectal cancer. Methods Charts review of all young female patients diagnosed with locally advanced rectal cancer, underwent laparoscopic ovarian transposition, then received preoperative radiotherapy at king Faisal Specialist Hospital and Research Centre between 2003–2007. Results During the period studied three single patients age between 21–27 years underwent pre-radiation laparoscopic ovarian transposition for advanced rectal cancer. All required pretreatment laparoscopic diversion stoma due to rectal stricture secondary to tumor that was performed at the same time. One patient died of metastatic disease during treatment. The ovarian hormonal levels (FSH and LH were normal in two patients. One has had normal menstrual period and other had amenorrhoea after 4 months follow-up however her ovarian hormonal level were within normal limits. Conclusions Laparoscopic ovarian transposition before pelvic radiation in advanced rectal cancer treatment is an effective and feasible way of preservation of ovarian function in young patients at risk of radiotherapy induced ovarian failure. However, this procedure is still under used and it is advisable to discuss and propose it to suitable patients.

  11. Safeguard By Design Lessons Learned from DOE Experience Integrating Safety into Design

    Energy Technology Data Exchange (ETDEWEB)

    Hockert, John; Burbank, Roberta L.

    2010-04-13

    This paper identifies the lessons to be learned for the institutionalization of Safeguards by Design (SBD) from the Department of Energy (DOE) experience developing and implementing DOE-STD-1189-2008, Integration of Safety into the Design Process. The experience is valuable because of the similarity of the challenges of integrating safety and safeguards into the design process. The paper reviews the content and development of DOE-STD-1189-2008 from its initial concept in January 2006 to its issuance in March 2008. Lessons learned are identified in the areas of the development and structure of requirements for the SBD process; the target audience for SBD requirements and guidance, the need for a graded approach to SBD, and a possible strategy for development and implementation of SBD within DOE.

  12. Design Methodologies and to Combat Radiation Induced Corruption in FPGAs and SoCs Project

    Data.gov (United States)

    National Aeronautics and Space Administration — Traditional radiation hardened by process (RHBP) and radiation hardened by design (RHBD) techniques have seen success in mitigating the effects of radiation induced...

  13. Vector Design for Improved DNA Vaccine Efficacy, Safety and Production

    Directory of Open Access Journals (Sweden)

    James A. Williams

    2013-06-01

    Full Text Available DNA vaccination is a disruptive technology that offers the promise of a new rapidly deployed vaccination platform to treat human and animal disease with gene-based materials. Innovations such as electroporation, needle free jet delivery and lipid-based carriers increase transgene expression and immunogenicity through more effective gene delivery. This review summarizes complementary vector design innovations that, when combined with leading delivery platforms, further enhance DNA vaccine performance. These next generation vectors also address potential safety issues such as antibiotic selection, and increase plasmid manufacturing quality and yield in exemplary fermentation production processes. Application of optimized constructs in combination with improved delivery platforms tangibly improves the prospect of successful application of DNA vaccination as prophylactic vaccines for diverse human infectious disease targets or as therapeutic vaccines for cancer and allergy.

  14. Beyond Implications and Applications: the Story of 'Safety by Design'

    Science.gov (United States)

    M Kelty, Christopher

    2009-08-01

    Using long-term anthropological observations at the Center for Biological and Environmental Nanotechnology in Houston, Texas, the article demonstrates in detail the creation of new objects, new venues and new modes of veridiction which have reoriented the disciplines of materials chemistry and nanotoxicology. Beginning with the confusion surrounding the meaning of 'implications' and 'applications' the article explores the creation of new venues (CBEN and its offshoot the International Council on Nanotechnology); it then demonstrates how the demands for a responsible, safe or ethical science were translated into new research and experiment in and through these venues. Finally it shows how 'safety by design' emerged as a way to go beyond implications and applications, even as it introduced a whole new array of controversies concerning its viability, validity and legitimacy.

  15. Design of 3D simulation engine for oilfield safety training

    Science.gov (United States)

    Li, Hua-Ming; Kang, Bao-Sheng

    2015-03-01

    Aiming at the demand for rapid custom development of 3D simulation system for oilfield safety training, this paper designs and implements a 3D simulation engine based on script-driven method, multi-layer structure, pre-defined entity objects and high-level tools such as scene editor, script editor, program loader. A scripting language been defined to control the system's progress, events and operating results. Training teacher can use this engine to edit 3D virtual scenes, set the properties of entity objects, define the logic script of task, and produce a 3D simulation training system without any skills of programming. Through expanding entity class, this engine can be quickly applied to other virtual training areas.

  16. Design, Operations, and Safety Report for the MERIT Target System

    Energy Technology Data Exchange (ETDEWEB)

    Graves, Van B [ORNL; Spampinato, Philip Thomas [ORNL

    2007-09-01

    The Mercury Intense Target Project (MERIT) is a proof-of-principal experiment to determine the feasibility of using a free-jet of Hg as a spallation target in a Neutrino Factory or a Muon Collider facility. The 1-cm-diameter, 20-m/sec jet will be generated inside a 15-Tesla magnetic field, and high-speed optical diagnostics will be used to photograph the interaction between the Hg jet and a 24-GeV proton beam.The experiment is scheduled to be conducted at CERN in 2007. ORNL is responsible for the design, fabrication, and testing of a system to deliver the Hg jet within the confines of the 15-cm magnet bore. This report documents the functional and safety requirements of the Hg system along with descriptions of its interfaces to the other experimental equipment.

  17. Design of laboratory experiments to study radiation-driven implosions

    Science.gov (United States)

    Keiter, P. A.; Trantham, M.; Malamud, G.; Klein, S. R.; Davis, J.; VanDervort, R.; Shvarts, D.; Drake, R. P.; Stone, J. M.; Fraenkel, M.; Frank, Y.; Raicher, E.

    2017-03-01

    The interstellar medium is heterogeneous with dense clouds amid an ambient medium. Radiation from young OB stars asymmetrically irradiate the dense clouds. Bertoldi (1989) developed analytic formulae to describe possible outcomes of these clouds when irradiated by hot, young stars. One of the critical parameters that determines the cloud's fate is the number of photon mean free paths in the cloud. For the extreme cases where the cloud size is either much greater than or much less than one mean free path, the radiation transport should be well understood. However, as one transitions between these limits, the radiation transport is much more complex and is a challenge to solve with many of the current radiation transport models implemented in codes. We present the design of laboratory experiments that use a thermal source of x-rays to asymmetrically irradiate a low-density plastic foam sphere. The experiment will vary the density and hence the number of mean free paths of the sphere to study the radiation transport in different regimes. We have developed dimensionless parameters to relate the laboratory experiment to the astrophysical system and we show that we can perform the experiment in the same transport regime.

  18. Synchrotron radiation shielding design and ICRP radiological protection quantities.

    Science.gov (United States)

    Bassey, Bassey; Moreno, Beatriz; Chapman, Dean

    2015-06-01

    Protection and operational quantities as defined by the International Commission on Radiological Protection (ICRP) and the International Commission on Radiation Units and Measurements (ICRU) are the two sets of quantities recommended for use in radiological protection for external radiation. Since the '80s, the protection quantities have evolved from the concept of dose equivalent to effective dose equivalent to effective dose, and the associated conversion coefficients have undergone changes. In this work, the influence of three different versions of ICRP photon dose conversion coefficients in the synchrotron radiation shielding calculations of an experimental enclosure has been examined. The versions are effective dose equivalent (ICRP Publication 51), effective dose (ICRP Publication 74), and effective dose (ICRP Publication 116) conversion coefficients. The sources of the synchrotron radiation white beam into the enclosure were a bending magnet, an undulator and a wiggler. The ranges of photons energy from these sources were 10-200 keV for the bending magnet and undulator, and 10-500 keV for the wiggler. The design criterion aimed a radiation leakage less than 0.5 µSv h(-1) from the enclosure. As expected, larger conversion coefficients in ICRP Publication 51 lead to higher calculated dose rates. However, the percentage differences among the calculated dose rates get smaller once shielding is added, and the choice of conversion coefficients set did not affect the final shielding decision.

  19. Interface design of VSOP'94 computer code for safety analysis

    Science.gov (United States)

    Natsir, Khairina; Yazid, Putranto Ilham; Andiwijayakusuma, D.; Wahanani, Nursinta Adi

    2014-09-01

    Today, most software applications, also in the nuclear field, come with a graphical user interface. VSOP'94 (Very Superior Old Program), was designed to simplify the process of performing reactor simulation. VSOP is a integrated code system to simulate the life history of a nuclear reactor that is devoted in education and research. One advantage of VSOP program is its ability to calculate the neutron spectrum estimation, fuel cycle, 2-D diffusion, resonance integral, estimation of reactors fuel costs, and integrated thermal hydraulics. VSOP also can be used to comparative studies and simulation of reactor safety. However, existing VSOP is a conventional program, which was developed using Fortran 65 and have several problems in using it, for example, it is only operated on Dec Alpha mainframe platforms and provide text-based output, difficult to use, especially in data preparation and interpretation of results. We develop a GUI-VSOP, which is an interface program to facilitate the preparation of data, run the VSOP code and read the results in a more user friendly way and useable on the Personal 'Computer (PC). Modifications include the development of interfaces on preprocessing, processing and postprocessing. GUI-based interface for preprocessing aims to provide a convenience way in preparing data. Processing interface is intended to provide convenience in configuring input files and libraries and do compiling VSOP code. Postprocessing interface designed to visualized the VSOP output in table and graphic forms. GUI-VSOP expected to be useful to simplify and speed up the process and analysis of safety aspects.

  20. Probabilistic Structural Evaluation of Uncertainties in Radiator Sandwich Panel Design

    Science.gov (United States)

    Kuguoglu, Latife; Ludwiczak, Damian

    2006-01-01

    The Jupiter Icy Moons Orbiter (JIMO) Space System is part of the NASA's Prometheus Program. As part of the JIMO engineering team at NASA Glenn Research Center, the structural design of the JIMO Heat Rejection Subsystem (HRS) is evaluated. An initial goal of this study was to perform sensitivity analyses to determine the relative importance of the input variables on the structural responses of the radiator panel. The desire was to let the sensitivity analysis information identify the important parameters. The probabilistic analysis methods illustrated here support this objective. The probabilistic structural performance evaluation of a HRS radiator sandwich panel was performed. The radiator panel structural performance was assessed in the presence of uncertainties in the loading, fabrication process variables, and material properties. The stress and displacement contours of the deterministic structural analysis at mean probability was performed and results presented. It is followed by a probabilistic evaluation to determine the effect of the primitive variables on the radiator panel structural performance. Based on uncertainties in material properties, structural geometry and loading, the results of the displacement and stress analysis are used as an input file for the probabilistic analysis of the panel. The sensitivity of the structural responses, such as maximum displacement and maximum tensile and compressive stresses of the facesheet in x and y directions and maximum VonMises stresses of the tube, to the loading and design variables is determined under the boundary condition where all edges of the radiator panel are pinned. Based on this study, design critical material and geometric parameters of the considered sandwich panel are identified.

  1. Evaluation of radiation safety for storage o high integrity container in Yonggwang NPP

    Energy Technology Data Exchange (ETDEWEB)

    Kwak, Sang Soo; Park, Seung Chil; Ha, Jong Hyun; Kim, Byung Tae [Nuclear Environment Technology Institute, KEPCO, Taejon (Korea, Republic of)

    1999-07-01

    In order to reduce the generation of radioactive waste in Yonggwang NPP, the spent resin dry system(SRDS) will be used for treatment of spent resin. According to operation of SRD, a different container will be required for containment of spent resin instead of DOT-17H drum. Therefore, the high integrity container (HIC) which is manufactured for disposal will be used for containment of spent resin generated from SRDS. Because the HIC contained with spent resin as high radioactivity and high radiation dose rate, a special attention in handling of HIC and storage of HIC in radioactive waste storage building should be paid. Accordingly, it is necessary to prepare the program for safe storage of HIC. Several options on storage of HIC into the radioactive waste storage building in Yonggwang NPP were established. Depending on the field conditions, it can be of help to the choice of pertinent method for safe and effective storage of HIC. In this report, the radiation safety of each option on the storage of HIC was evaluated and it shows that any option can be adapted as an effective storage method for Younggwang NPP if some problems appeared through the radiation safety evaluation are resolved. (author)

  2. Analysis and conceptual design of a lunar radiator parabolic shade

    Science.gov (United States)

    Ewert, Michael K.; Clark, Craig S.

    1991-01-01

    On the moon, the available heat sink temperature for a vertical unshaded radiator at the equator is 322 K. A method of reducing this heat sink temperature using a parabolic trough shading device was investigated. A steady state heat balance was performed to predict the available heat sink temperature. The effect of optical surface properties on system performance was investigated. Various geometric configurations were also evaluated. A flexible shade conceptual design is presented which greatly reduces the weight and stowed volume of the system. The concept makes use of the natural catenary shape assumed by a flexible material when supported at two points. The catenary shape is very near parabolic. The lunar radiator parabolic shade design presented integrates the energy collection and rejection of a solar dynamic power cycle with the moderate temperature waste heat rejection of a lunar habitat.

  3. 77 FR 74196 - Draft Guidance for Industry on Safety Considerations for Product Design To Minimize Medication...

    Science.gov (United States)

    2012-12-13

    ... Product Design To Minimize Medication Errors; Availability AGENCY: Food and Drug Administration, HHS... guidance for industry entitled ``Safety Considerations for Product Design to Minimize Medication Errors... using a systems approach to minimize medication errors relating to product design. The draft...

  4. High-voltage safety fuses for the transition-radiation tracking detector in the ATLAS experiment

    NARCIS (Netherlands)

    Voronov, SA; Voronov, YA; Onishchenko, EM; Simakov, AB; Sosnovtsev, VV; Suchkov, SI; Sugrobova, TA

    2004-01-01

    A safety fuse has been designed for the electrical protection of gas-filled detectors in the ATLAS experiment at CERN (Geneva, Switzerland). The fuse is a polished lithium niobate plate with a titanium strip of 91-kOmega resistance deposited by the photolithographic technique. The forced blow-out ti

  5. 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

  6. HIGH COOLING WATER TEMPERATURE EFFECTS ON DESIGN AND OPERATIONAL SAFETY OF NPPS IN THE GULF REGION

    Directory of Open Access Journals (Sweden)

    BYUNG KOO KIM

    2013-12-01

    Full Text Available The Arabian Gulf region has one of the highest ocean temperatures, reaching above 35 degrees and ambient temperatures over 50 degrees in the summer. Two nuclear power plants (NPP are being introduced in the region for the first time, one at Bushehr (1,000 MWe PWR plant from Russia, and a much larger one at Barakah (4X1,400 MWe PWR from Korea. Both plants take seawater from the Gulf for condenser cooling, having to modify the secondary/tertiary side cooling systems design by increasing the heat transfer surface area from the country of origin. This paper analyses the secondary side of a typical PWR plant operating under the Rankine cycle with a simplified thermal-hydraulic model. Parametric study of ocean cooling temperatures is conducted to estimate thermal efficiency variations and its associated design changes for the secondary side. Operational safety is reviewed to deliver rated power output with acceptable safety margins in line with technical specifications, mainly in the auxiliary systems together with the cooling water temperature. Impact on the Gulf seawater as the ultimate heat sink is considered negligible, affecting only the adjacent water near the NPP site, when compared to the solar radiation on the sea surface.

  7. TH-E-19A-01: Quality and Safety in Radiation Therapy

    Energy Technology Data Exchange (ETDEWEB)

    Ford, E [University of Washington, Seattle, WA (United States); Ezzell, G [Mayo Clinic Arizona, Phoenix, AZ (United States); Miller, B [Henry Ford Health System, Clinton Township, MI (United States); Yorke, E [Memorial Sloan-Kettering Cancer Center, New York, NY (United States)

    2014-06-15

    Clinical radiotherapy data clearly demonstrate the link between the quality and safety of radiation treatments and the outcome for patients. The medical physicist plays an essential role in this process. To ensure the highest quality treatments, the medical physicist must understand and employ modern quality improvement techniques. This extends well beyond the duties traditionally associated with prescriptive QA measures. This session will review the current best practices for improving quality and safety in radiation therapy. General elements of quality management will be reviewed including: what makes a good quality management structure, the use of prospective risk analysis such as FMEA, and the use of incident learning. All of these practices are recommended in society-level documents and are incorporated into the new Practice Accreditation program developed by ASTRO. To be effective, however, these techniques must be practical in a resource-limited environment. This session will therefore focus on practical tools such as the newly-released radiation oncology incident learning system, RO-ILS, supported by AAPM and ASTRO. With these general constructs in mind, a case study will be presented of quality management in an SBRT service. An example FMEA risk assessment will be presented along with incident learning examples including root cause analysis. As the physicist's role as “quality officer” continues to evolve it will be essential to understand and employ the most effective techniques for quality improvement. This session will provide a concrete overview of the fundamentals in quality and safety. Learning Objectives: Recognize the essential elements of a good quality management system in radiotherapy. Understand the value of incident learning and the AAPM/ASTRO ROILS incident learning system. Appreciate failure mode and effects analysis as a risk assessment tool and its use in resource-limited environments. Understand the fundamental principles of good

  8. Incident learning and failure-mode-and-effects-analysis guided safety initiatives in radiation medicine

    Directory of Open Access Journals (Sweden)

    Ajay eKapur

    2013-12-01

    Full Text Available By combining incident learning and process failure-mode-and-effects-analysis in a structure-process-outcome framework we have created a risk profile for our radiation medicine practice and implemented evidence-based risk mitigation initiatives focused on patient safety. Based on reactive reviews of incidents reported in our departmental incident-reporting system and proactive failure-mode-and-effects-analysis, high safety-risk procedures in our paperless radiation medicine process and latent risk factors were identified. Six initiatives aimed at the mitigation of associated severity, likelihood of occurrence and detectability risks were implemented. These were the standardization of care pathways and toxicity grading, pre-treatment-planning peer review, a policy to thwart delay-rushed processes, an electronic whiteboard to enhance coordination and the use of six-sigma metrics to monitor operational efficiencies. The effectiveness of these initiatives over a three year period was assessed using process and outcome specific metrics within the framework of the department structure. There has been a 47% increase in incident reporting, with no increase in adverse events. Care pathways have been used with greater than 97% clinical compliance rate. The implementation of peer review prior to treatment planning and use of the whiteboard have provided opportunities for proactive detection and correction of errors. There has been a twofold drop in the occurrence of high-risk procedural delays. Patient treatment start delays are routinely enforced on cases that would have historically been rushed. Z-scores for high risk procedures have steadily improved from 1.78 to 2.35. The initiatives resulted in sustained reductions of failure-mode risks as measured by a set of evidence-based metrics over a three year period. These augment or incorporate many of the published recommendations for patient safety in radiation medicine by translating them to clinical

  9. Evaluation of experimental methods for assessing safety for ultrasound radiation force elastography.

    Science.gov (United States)

    Skurczynski, M J; Duck, F A; Shipley, J A; Bamber, J C; Melodelima, D

    2009-08-01

    Standard test tools have been evaluated for the assessment of safety associated with a prototype transducer intended for a novel radiation force elastographic imaging system. In particular, safety has been evaluated by direct measurement of temperature rise, using a standard thermal test object, and detection of inertial cavitation from acoustic emission. These direct measurements have been compared with values of the thermal index and mechanical index, calculated from acoustic measurements in water using standard formulae. It is concluded that measurements using a thermal test object can be an effective alternative to the calculation of thermal index for evaluating thermal hazard. Measurement of the threshold for cavitation was subject to considerable variability, and it is concluded that the mechanical index still remains the preferred standard means for assessing cavitation hazard.

  10. Research projects of the Finnish Centre for Radiation and Nuclear Safety 1996-1997; Saeteilyturvakeskuksen tutkimushankkeet 1996-1997

    Energy Technology Data Exchange (ETDEWEB)

    Mustonen, R.; Koponen, H. [eds.

    1996-02-01

    The research activities of the Finnish Centre for Radiation and Nuclear Safety (STUK) are based on the Centre`s primary task of preventing and restricting adverse effects of radiation. As a rule, studies concerning nuclear safety (part 1 of the publication) are studies originating from the regulatory function of STUK; these are directed and funded by the Centre but the Centre does not carry them out itself. In contrast, studies dealing with radiation exposure and health risks (part 2 of the publication) are conducted by the Centre itself, often in cooperation with some other research institute or university. Results of these studies are published in open scientific literature.

  11. Engineered and Administrative Safety Systems for the Control of Prompt Radiation Hazards at Accelerator Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Liu, James C.; /SLAC; Vylet, Vashek; /Duke U.; Walker, Lawrence S.; /SLAC

    2007-12-17

    The ANSI N43.1 Standard, currently in revision (ANSI 2007), sets forth the requirements for accelerator facilities to provide adequate protection for the workers, the public and the environment from the hazards of ionizing radiation produced during and from accelerator operations. The Standard also recommends good practices that, when followed, provide a level of radiation protection consistent with those established for the accelerator communities. The N43.1 Standard is suitable for all accelerator facilities (using electron, positron, proton, or ion particle beams) capable of producing radiation, subject to federal or state regulations. The requirements (see word 'shall') and recommended practices (see word 'should') are prescribed in a graded approach that are commensurate with the complexity and hazard levels of the accelerator facility. Chapters 4, 5 and 6 of the N43.1 Standard address specially the Radiation Safety System (RSS), both engineered and administrative systems, to mitigate and control the prompt radiation hazards from accelerator operations. The RSS includes the Access Control System (ACS) and Radiation Control System (RCS). The main requirements and recommendations of the N43.1 Standard regarding the management, technical and operational aspects of the RSS are described and condensed in this report. Clearly some aspects of the RSS policies and practices at different facilities may differ in order to meet the practical needs for field implementation. A previous report (Liu et al. 2001a), which reviews and summarizes the RSS at five North American high-energy accelerator facilities, as well as the RSS references for the 5 labs (Drozdoff 2001; Gallegos 1996; Ipe and Liu 1992; Liu 1999; Liu 2001b; Rokni 1996; TJNAF 1994; Yotam et al. 1991), can be consulted for the actual RSS implementation at various laboratories. A comprehensive report describing the RSS at the Stanford Linear Accelerator Center (SLAC 2006) can also serve as a

  12. Overview of Design, Lifecycle, and Safety for Computer-Based Systems

    Science.gov (United States)

    Torres-Pomales, Wilfredo

    2015-01-01

    This document describes the need and justification for the development of a design guide for safety-relevant computer-based systems. This document also makes a contribution toward the design guide by presenting an overview of computer-based systems design, lifecycle, and safety.

  13. Six sigma tools for a patient safety-oriented, quality-checklist driven radiation medicine department.

    Science.gov (United States)

    Kapur, Ajay; Potters, Louis

    2012-01-01

    The purpose of this work was to develop and implement six sigma practices toward the enhancement of patient safety in an electronic, quality checklist-driven, multicenter, paperless radiation medicine department. A quality checklist process map (QPM), stratified into consultation through treatment-completion stages was incorporated into an oncology information systems platform. A cross-functional quality management team conducted quality-function-deployment and define-measure-analyze-improve-control (DMAIC) six sigma exercises with a focus on patient safety. QPM procedures were Pareto-sorted in order of decreasing patient safety risk with failure mode and effects analysis (FMEA). Quantitative metrics for a grouped set of highest risk procedures were established. These included procedural delays, associated standard deviations and six sigma Z scores. Baseline performance of the QPM was established over the previous year of usage. Data-driven analysis led to simplification, standardization, and refinement of the QPM with standard deviation, slip-day reduction, and Z-score enhancement goals. A no-fly policy (NFP) for patient safety was introduced at the improve-control DMAIC phase, with a process map interlock imposed on treatment initiation in the event of FMEA-identified high-risk tasks being delayed or not completed. The NFP was introduced in a pilot phase with specific stopping rules and the same metrics used for performance assessments. A custom root-cause analysis database was deployed to monitor patient safety events. Relative to the baseline period, average slip days and standard deviations for the risk-enhanced QPM procedures improved by over threefold factors in the NFP period. The Z scores improved by approximately 20%. A trend for proactive delays instead of reactive hard stops was observed with no adverse effects of the NFP. The number of computed potential no-fly delays per month dropped from 60 to 20 over a total of 520 cases. The fraction of computed

  14. Chalcogenide Glass Radiation Sensor; Materials Development, Design and Device Testing

    Energy Technology Data Exchange (ETDEWEB)

    Mitkova, Maria; Butt, Darryl; Kozicki, Michael; Barnaby, Hugo

    2013-04-30

    studied the effect of x-rays and γ-rays, on thin film chalcogenide glasses and applied them in conjunction with film incorporating a silver source in a new type of radiation sensor for which we have an US patent application [3]. In this report, we give data about our studies regarding our designed radiation sensor along with the testing and performance at various radiation doses. These studies have been preceded by materials characterization research related to the compositional and structural characteristics of the active materials used in the radiation sensor design. During the work on the project, we collected a large volume of material since every experiment was repeated many times to verify the results. We conducted a comprehensive material research, analysis and discussion with the aim to understand the nature of the occurring effects, design different structures to harness these effects, generated models to aid in the understanding the effects, built different device structures and collected data to quantify device performance. These various aspects of our investigation have been detailed in previous quarterly reports. In this report, we present our main results and emphasize on the results pertaining to the core project goals materials development, sensor design and testing and with an emphasis on classifying the appropriate material and design for the optimal application. The report has three main parts: (i) Presentation of the main data; (ii) Bulleted summary of the most important results; (iii) List of the patent, journal publications, conference proceedings and conferences participation, occurring as a result of working on the project.

  15. Highway Safety Program Manual: Volume 12: Highway Design, Construction and Maintenance.

    Science.gov (United States)

    National Highway Traffic Safety Administration (DOT), Washington, DC.

    Volume 12 of the 19-volume Highway Safety Program Manual (which provides guidance to State and local governments on preferred highway safety practices) focuses on highway design, construction and maintenance. The purpose and specific objectives of such a program are described. Federal authority in the area of highway safety and policies regarding…

  16. Radiation safety and quality control assurance in X-ray diagnostics 1998; Saeteilyturvallisuus ja laadunvarmistus roentgendiagnostiikassa 1998

    Energy Technology Data Exchange (ETDEWEB)

    Servomaa, A. [ed.

    1998-03-01

    The report is based on a seminar course of lectures `Radiation safety and quality assurance in X-ray diagnostics 1998` organized by the Radiation and Nuclear Safety Authority (STUK) in Finland. The lectures included actual information on X-ray examinations: methods of quality assurance, methods of measuring and calculating patient doses, examination frequencies, patient doses, occupational doses, and radiation risks. Paediatric X-ray examinations and interventional procedures were the most specific topics. The new Council Directive 97/43/Euratom on medical exposure, and the European Guidelines on quality criteria for diagnostic radiographic images, were discussed in several lectures. Lectures on general radiation threats and preparedness, examples of radiation accidents, and emergency preparedness in hospitals were also included. (editor)

  17. Self-shielded electron linear accelerators designed for radiation technologies

    Science.gov (United States)

    Belugin, V. M.; Rozanov, N. E.; Pirozhenko, V. M.

    2009-09-01

    This paper describes self-shielded high-intensity electron linear accelerators designed for radiation technologies. The specific property of the accelerators is that they do not apply an external magnetic field; acceleration and focusing of electron beams are performed by radio-frequency fields in the accelerating structures. The main characteristics of the accelerators are high current and beam power, but also reliable operation and a long service life. To obtain these characteristics, a number of problems have been solved, including a particular optimization of the accelerator components and the application of a variety of specific means. The paper describes features of the electron beam dynamics, accelerating structure, and radio-frequency power supply. Several compact self-shielded accelerators for radiation sterilization and x-ray cargo inspection have been created. The introduced methods made it possible to obtain a high intensity of the electron beam and good performance of the accelerators.

  18. The basis and safety of food irradiation. Advantages of radiation treatment for food sanitation and storage

    Energy Technology Data Exchange (ETDEWEB)

    Ito, Hitoshi [Japan Atomic Energy Research Inst., Takasaki, Gunma (Japan). Takasaki Radiation Chemistry Research Establishment

    2001-09-01

    The food irradiation has the history of more than 60 years in its development. However, its commercial application has not been promoted well in Japan even though the safety of irradiated foods was confirmed. Recently, relevant authorities in 52 countries have given clearance to many commodities, and irradiated foods are commercially distributed in USA and EU countries. The international situation makes some unavoidable circumstances which can not close the commercialization of food irradiation in Japan. The present report contains the basis and application of food irradiation, and history of development in the World and Japan. Moreover, the safety of irradiated foods are demonstrated from many evidences of researches in animal feeding tests, in analysis of radiolytic products, in nutritional evaluations and in microbiological studies of irradiated foods. Especially, it makes obvious from the results of many researches that unique radiolytic products can not be produced by irradiation of foods. Because main radiation effects are induced by oxidation degradation of food components as similar to natural oxidation by heating or UV light. Radiation engineering for commercial process and identification methods of irradiated foods are also presented. (author)

  19. An oil-free compact X-pinch plasma radiation source: Design and radiation performance

    Science.gov (United States)

    Shapovalov, Roman V.; Spielman, Rick B.; Imel, George R.

    2017-06-01

    This paper describes a new, high-current, X-pinch radiation source recently developed and tested at Idaho State University. Our design is based on two linear transformer driver (LTD) bricks arranged in side-by-side geometry and directly coupled with an X-pinch load. The salient features of our 2-LTD-bricks are its simplicity, compactness, and portability: there is no oil, no water, and no SF6. It can be easily relocated to any place where a compact X-pinch radiation source is wanted. The driver can store up to 2.8 kJ of initial energy and can deliver more than 200-kA peak-current with less than 200-ns, 10%-90%, rise time into a short-circuit load. When the driver is coupled with an X-pinch load, it generates a very fast and bright radiation pulse. Source size measurements indicate that this radiation originates from a very small dense plasma, known as a "hot spot."

  20. An integrated design methodology for the safety and security of nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Joung, S. Y.; Chang, S. H. [Korea Advanced Institute of Science and Technology, Daejeon (Korea, Republic of)

    2012-03-15

    After Fukushima nuclear power plant accident, safety of nuclear power plant was issued. In Fukushima accident, one of main reason is location of emergency diesel power generators stop which locate under the sea water level when tsunami occurred. In view of security, emergency diesel generator location under reactor building design is good because for example to escape air strike but is not good for safety for example Fukushima accident. Sometimes safety and security design looks conflicting but nuclear safety and nuclear security share the goal of protecting but nuclear safety and nuclear power plants operate at acceptable risk levels. The purpose of this paper is to introduce safety and security integrated design for nuclear power plant in special emergency diesel generator and control room with simple probabilistic safety assessment analysis.

  1. Design and Radiation Assessment of Optoelectronic Transceiver Circuits for ITER

    CERN Document Server

    Leroux, P; Van Uffelen, M; Steyaert, M

    2008-01-01

    The presented work describes the design and characterization results of different electronic building blocks for a MGy gamma radiation tolerant optoelectronic transceiver aiming at ITER applications. The circuits are implemented using the 70GHz fT SiGe HBT in a 0.35μm BiCMOS technology. A VCSEL driver circuit has been designed and measured up to a TID of 1.6 MGy and up to a bit rate of 622Mbps. No significant degradation is seen in the eye opening of the output signal. On the receiver side, both a 1GHz, 3kΩ transimpedance and a 5GHz Cherry-Hooper amplifier with over 20dB voltage gain have been designed.

  2. Improving efficiency and safety in external beam radiation therapy treatment delivery using a Kaizen approach.

    Science.gov (United States)

    Kapur, Ajay; Adair, Nilda; O'Brien, Mildred; Naparstek, Nikoleta; Cangelosi, Thomas; Zuvic, Petrina; Joseph, Sherin; Meier, Jason; Bloom, Beatrice; Potters, Louis

    2017-06-29

    Modern external beam radiation therapy treatment delivery processes potentially increase the number of tasks to be performed by therapists and thus opportunities for errors, yet the need to treat a large number of patients daily requires a balanced allocation of time per treatment slot. The goal of this work was to streamline the underlying workflow in such time-interval constrained processes to enhance both execution efficiency and active safety surveillance using a Kaizen approach. A Kaizen project was initiated by mapping the workflow within each treatment slot for 3 Varian TrueBeam linear accelerators. More than 90 steps were identified, and average execution times for each were measured. The time-consuming steps were stratified into a 2 × 2 matrix arranged by potential workflow improvement versus the level of corrective effort required. A work plan was created to launch initiatives with high potential for workflow improvement but modest effort to implement. Time spent on safety surveillance and average durations of treatment slots were used to assess corresponding workflow improvements. Three initiatives were implemented to mitigate unnecessary therapist motion, overprocessing of data, and wait time for data transfer defects, respectively. A fourth initiative was implemented to make the division of labor by treating therapists as well as peer review more explicit. The average duration of treatment slots reduced by 6.7% in the 9 months following implementation of the initiatives (P = .001). A reduction of 21% in duration of treatment slots was observed on 1 of the machines (P Kaizen approach has the potential to improve operational efficiency and safety with quick turnaround in radiation therapy practice by addressing non-value-adding steps characteristic of individual department workflows. Higher effort opportunities are identified to guide continual downstream quality improvements. Copyright © 2017. Published by Elsevier Inc.

  3. Radiation shielding design of the PAL-XFEL

    Science.gov (United States)

    Jung, Nam-Suk; Lee, Hee-Seock; Oh, Joo-Hee; Kim, Bum-Jong

    2015-02-01

    The construction of the Pohang Accelerator Laboratory X-ray Free Electron Laser (PAL-XFEL) started in 2011. The PAL-XFEL is designed to generate X-rays using 10 GeV, 0.2 nC electron beams. For the radiation shielding design, a beam-loss scenario suitable for the PAL-XFEL should be established. The beam-loss scenario was determined and categorized as normal or accidental. The electron beam will be shut down automatically when accidental beam-loss occurs. Using this scenario, the thickness of the accelerator and undulator tunnel of the PAL-XFEL was calculated by using the SHIELD11 code, and complicated tunnel structures such as maze entrances, sliding doors, trenches, sleeves, and ducts, were determined under the assumption of a thick iron target by using the FLUKA code. A detailed design of the main beam dump was established, and shielding structures at the front end for suppression of the radiation dose at the experimental area under the accidental beam-loss scenario were considered. The muon production was estimated by using the FLUKA code.

  4. Radiation Shielding Design for ISOL System Beam Line

    Institute of Scientific and Technical Information of China (English)

    WANG; Feng; QIN; Jiu-chang

    2013-01-01

    The beam line of the ISOL system passes through the shielding wall and connects the HI-13 tandem accelerator.Neutron produced by tandem accelerator will affect the area of BRIF through the beam line.To protect the staff in BRIF area from radiation a shielding design of the beam line is carried out.The neutron source in the vault of tandem accelerator is the H.E Faraday cup of HI-13 tandem accelerator as showed in Fig.1.The Faraday cup is consisted of 1 mm molybdenum sheet and 10 mm

  5. Towards the Design of Safety-Critical Software

    Directory of Open Access Journals (Sweden)

    R. Rafeh

    2013-10-01

    Full Text Available Safety is the most important factor when developing software for safety-critical systems. Traditional approaches attempted to achieve safety through testing the software. However, there might be some bugs in the software not revealed in the test procedure. Formal verification is a new trend in developing safe software. In this paper, we propose a multi-phase formal approach for safety management in safety-critical software. We use timed transition Petri-net as a formal means to specify the properties of the model and their relations in each component of the software. In addition, we use the Z language to specify textual and mathematical specifications of the model, as a representative model to evaluate the proposed approach; we chose continuous infusion insulin pump (CIIP.

  6. Design considerations to enhance the safety of patient compartments in ambulance transporters.

    Science.gov (United States)

    Byran, Eyal; Gilad, Issachar

    2012-01-01

    The safety of the interior of ambulances is dubious and, in the event of sudden impact during emergency transport, potentially perilous to patients they carry. The workplace ergonomics of the interior of the passenger cabin is lacking. This article discusses an improved ergonomic interior design based on study findings, observations and subjective perception. It suggests design aspects and safety concepts aimed at increasing the safety of patients and paramedic staff inside the ambulance as a mobile workstation.

  7. National Ignition Facility sub-system design requirements integrated safety systems SSDR 1.5.4

    Energy Technology Data Exchange (ETDEWEB)

    Reed, R.; VanArsdall, P.; Bliss, E.

    1996-09-01

    This System Design Requirement document establishes the performance, design, development, and test requirements for the Integrated Safety System, which is part of the NIF Integrated Computer Control System (ICCS).

  8. On the Safety of Stage Machinery from the Design Perspective(Outline)

    Institute of Scientific and Technical Information of China (English)

    CHEN Wei

    2015-01-01

    In this paper, domestic and international safety standards and speciifcations related to the design were introduced, as well as the safety design of general theater audience, stage, electrical control system and special equipment. In addition, it was illustrated by speciifc examples.

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

    NARCIS (Netherlands)

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

    2014-01-01

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

  10. Verification of Overall Safety Factors In Deterministic Design Of Model Tested Breakwaters

    DEFF Research Database (Denmark)

    Burcharth, H. F.

    2001-01-01

    The paper deals with concepts of safety implementation in design. An overall safety factor concept is evaluated on the basis of a reliability analysis of a model tested rubble mound breakwater with monolithic super structure. Also discussed are design load identification and failure mode limit st...

  11. Design of the NSLS-II Top-Off Safety System

    Energy Technology Data Exchange (ETDEWEB)

    Fliller, III R. [Brookhaven National Lab. (BNL), Upton, NY (United States). National Synchrotron Light Source; Doom, L. [Brookhaven National Lab. (BNL), Upton, NY (United States). National Synchrotron Light Source; Ganetis, G. [Brookhaven National Lab. (BNL), Upton, NY (United States). National Synchrotron Light Source; Hetzel, C. [Brookhaven National Lab. (BNL), Upton, NY (United States). National Synchrotron Light Source; Job, P. K. [Brookhaven National Lab. (BNL), Upton, NY (United States). National Synchrotron Light Source; Li, Y. [Brookhaven National Lab. (BNL), Upton, NY (United States). National Synchrotron Light Source; Shaftan, T. [Brookhaven National Lab. (BNL), Upton, NY (United States). National Synchrotron Light Source; Sharma, S. [Brookhaven National Lab. (BNL), Upton, NY (United States). National Synchrotron Light Source; Singh, O. [Brookhaven National Lab. (BNL), Upton, NY (United States). National Synchrotron Light Source; Wang, G. M. [Brookhaven National Lab. (BNL), Upton, NY (United States). National Synchrotron Light Source; Xia, Z. [Brookhaven National Lab. (BNL), Upton, NY (United States). National Synchrotron Light Source

    2015-05-03

    The NSLS-II accelerators finished commissioning in the fall of 2014, with beamline commissioning underway. Part of the design for the NSLS-II is to operate in top off mode. The Top Off Safety System (TOSS) is presently being installed. In this report we discuss the Top Off Safety System design and implementation, along with the necessary tracking results and radiological calculations.

  12. The Gas-Cooled Fast Reactor: Report on Safety System Design for Decay Heat Removal

    Energy Technology Data Exchange (ETDEWEB)

    K. D. Weaver; T. Marshall; T. Y. C. Wei; E. E. Feldman; M. J. Driscoll; H. Ludewig

    2003-09-01

    The gas-cooled fast reactor (GFR) was chosen as one of the Generation IV nuclear reactor systems to be developed based on its excellent potential for sustainability through reduction of the volume and radiotoxicity of both its own fuel and other spent nuclear fuel, and for extending/utilizing uranium resources orders of magnitude beyond what the current open fuel cycle can realize. In addition, energy conversion at high thermal efficiency is possible with the current designs being considered, thus increasing the economic benefit of the GFR. However, research and development challenges include the ability to use passive decay heat removal systems during accident conditions, survivability of fuels and in-core materials under extreme temperatures and radiation, and economical and efficient fuel cycle processes. This report addresses/discusses the decay heat removal options available to the GFR, and the current solutions. While it is possible to design a GFR with complete passive safety (i.e., reliance solely on conductive and radiative heat transfer for decay heat removal), it has been shown that the low power density results in unacceptable fuel cycle costs for the GFR. However, increasing power density results in higher decay heat rates, and the attendant temperature increase in the fuel and core. Use of active movers, or blowers/fans, is possible during accident conditions, which only requires 3% of nominal flow to remove the decay heat. Unfortunately, this requires reliance on active systems. In order to incorporate passive systems, innovative designs have been studied, and a mix of passive and active systems appears to meet the requirements for decay heat removal during accident conditions.

  13. VISRAD, 3-D Target Design and Radiation Simulation Code

    Science.gov (United States)

    Golovkin, Igor; Macfarlane, Joseph; Golovkina, Viktoriya

    2016-10-01

    The 3-D view factor code VISRAD is widely used in designing HEDP experiments at major laser and pulsed-power facilities, including NIF, OMEGA, OMEGA-EP, ORION, LMJ, Z, and PLX. It simulates target designs by generating a 3-D grid of surface elements, utilizing a variety of 3-D primitives and surface removal algorithms, and can be used to compute the radiation flux throughout the surface element grid by computing element-to-element view factors and solving power balance equations. Target set-up and beam pointing are facilitated by allowing users to specify positions and angular orientations using a variety of coordinates systems (e.g., that of any laser beam, target component, or diagnostic port). Analytic modeling for laser beam spatial profiles for OMEGA DPPs and NIF CPPs is used to compute laser intensity profiles throughout the grid of surface elements. We will discuss recent improvements to the software package and plans for future developments.

  14. Radiation safety protocol for high dose 131I therapy of thyroid carcinoma in patients on hemodialysis for chronic renal failure.

    Science.gov (United States)

    Modarresifar, Homayoun; Almodovar, Samuel; Bass, William B; Ojha, Buddhiwardhan

    2007-02-01

    Iodine ablation therapy for thyroid cancer on patients receiving dialysis poses unique radiation safety challenges. Exposure to gamma and beta negative particles by the hemodialysis (HD) staff is a concern that has not been well studied. A 53-y-old male patient on HD for chronic renal failure was scheduled for 131I high dose therapy as treatment for thyroid papillary carcinoma. The patient was on HD every other day, prior to ablation. A high dose of 131I (3,607.5 MBq) was required. The patient was admitted for 131I therapy, and continued HD. Thyroid cancer ablation therapy was administered according to our institutional protocol. New radiation safety measures were developed and implemented in order to give the patient an optimal treatment dose, reduce radiation to the patient (critical organs and whole body), and to protect the HD personnel. This included placing two lead shields between the patient and the HD nurse, and HD monitoring by two alternating nurses to reduce their radiation exposure. Film badges were used to measure radiation exposure to the nursing staff. Dosimetry calculations were obtained to determine radiation absorbed doses by the optic lens, skin, and whole body. Quality control verification for this shielding arrangement proved to be effective in protecting the HD staff against gamma and beta negative radiation from recent 131I high dose therapy. Implementation of this model proved to be an effective and adequate radiation safety protocol for limiting radiation exposure to the HD staff. The patient was given 3607.5 MBq for optimal treatment after HD. Hemodialysis was repeated after approximately 48 and 96 h to remove excess 131I and reduce radiation to the patient.

  15. Dismantlement of nuclear facilities decommissioned from the Russian navy: Enhancing regulatory supervision of nuclear and radiation safety

    Energy Technology Data Exchange (ETDEWEB)

    Sneve, M.K.

    2013-03-01

    The availability of up to date regulatory norms and standards for nuclear and radiation safety, relevant to the management of nuclear legacy situations, combined with effective and efficient regulatory procedures for licensing and monitoring compliance, are considered to be extremely important. Accordingly the NRPA has set up regulatory cooperation programs with corresponding authorities in the Russian Federation. Cooperation began with the civilian regulatory authorities and was more recently extended to include the military authority and this joint cooperation supposed to develop the regulatory documents to improve supervision over nuclear and radiation safety while managing the nuclear military legacy facilities in Northwest Russia and other regions of the country. (Author)

  16. A study on the necessity of medical facilities safety design adoption.

    Science.gov (United States)

    Park, Bora; Yang, Yeongae; Yang, Dongjoo; Shin, Joong-Il; Park, Sujong; Park, Soohee; Park, Yunhee

    2013-07-01

    [Purpose] The purpose of this study was to investigate the requirements of the introduction of a safety design and certification system for medical facilities. [Subjects] A survey was carried out of one hundred nurses, physical therapists, occupational therapists, speech and language therapists from May to August in 2012. [Methods] The survey was conducted after giving subjects some information about safety design. [Results] The participants were aware of the need for establishing a safety design certification system. Total responses to services, facilities and space were analyzed in order to evaluate the priorities of safety, user characteristics, functionality, convenience and aesthetics. Regarding the application of a safety design certification system to services, items were prioritized in the order of children's items, household supplies and hospital supplies. For facilities, the priorities were, living space, social welfare and medical facilities; space, they were public and transportation-related places. The requirements for operating a safety design system were in order development of: highly skilled manpower, the legal system, educational promotion and qualifying facilities. [Conclusion] In conclusion, in order to implement safety design in medical facilities, a safety design certification system should be introduced first, and to do this a systematic and comprehensive study is needed.

  17. An initial radiation safety needs assessment of Costa Rica: the South Texas Chapter of the Health Physics Society's strategic planning appraisal for participation in the "Radiation Safety Without Borders" initiative.

    Science.gov (United States)

    Emery, Robert J; Felknor, S A

    2002-05-01

    In response to the Health Physics Society's recent 'radiation safety without borders" initiative, the South Texas Chapter of the Health Physics Society selected Costa Rica as its partner country of choice. To develop an understanding of the radiation safety needs of this country, the fall 2001 University of Texas Health Science Center at Houston School of Public Health Environmental Radiation and Radioactivity class was tasked with the assignment of assessing the possible radiation safety needs and concerns for this country. The assignment culminated in a class presentation to the membership of the South Texas Chapter during its annual fall meeting. Using library and web based resources, tile students reviewed a number of public health and radiation-related topics. Life expectancies were found to be equivalent to the United States, even though significant differences in per capita health expenditures were noted. Costa Rica exhibited lower population mortality rates from major causes such as cardiovascular diseases, neoplasms, and external sources. Maternal and infant mortality rates were found to be much higher in Costa Rica than in the United States. Naturally occurring radiation sources such as uranium deposits were not identified as apparent major radiation issues of concern, although ultraviolet radiation exposures are consistently high. Several recent events in the country and the region involving patient overexposures suggest that concerns are likely focused on ensuring the proper use and maintenance of healing arts radiation equipment. The lack of available information on radioactive waste disposal suggests that waste handling also may be an issue warranting attention. The exercise proved to be very educational for the students, and the information gathered will serve to focus the Chapter's efforts when technical exchanges are initiated. The importance of linking this initiative to other existing programs within the country is also discussed.

  18. Optimal Design of Safety Instrumented Systems for Pressure Control of Methanol Separation Columns in the Bisphenol a Manufacturing Process

    Directory of Open Access Journals (Sweden)

    In-Bok Lee

    2016-12-01

    Full Text Available A bisphenol A production plant possesses considerable potential risks in the top of the methanol separation column, as pressurized acetone, methanol, and water are processed at an elevated temperature, especially in the event of an abnormal pressure increase due to a sudden power outage. This study assesses the potential risks in the methanol separation column through hazard and operability assessments and evaluates the damages in the case of fire and explosion accident scenarios. The study chooses three leakage scenarios: a 5-mm puncture on the methanol separation column, a 50-mm diameter fracture of a discharge pipe and a catastrophic rupture, and, simulated using Phast (Ver. 6.531, the concentration distribution of scattered methanol, thermal radiation distribution of fires, and overpressure distribution of vapor cloud explosions. Implementation of a safety-instrumented system equipped with two-out-of-three voting as a safety measure can detect overpressure at the top of the column and shut down the main control valve and the emergency shutoff valve simultaneously. By applying a safety integrity level of three, the maximal release volume of the safety relief valve can be reduced and, therefore, the design capacity of the flare stack can also be reduced. Such integration will lead to improved safety at a reduced cost.

  19. Application of an informatics-based decision-making framework and process to the assessment of radiation safety in nanotechnology.

    Science.gov (United States)

    Hoover, Mark D; Myers, David S; Cash, Leigh J; Guilmette, Raymond A; Kreyling, Wolfgang G; Oberdörster, Günter; Smith, Rachel; Cassata, James R; Boecker, Bruce B; Grissom, Michael P

    2015-02-01

    The National Council on Radiation Protection and Measurements (NCRP) established NCRP Scientific Committee 2-6 to develop a report on the current state of knowledge and guidance for radiation safety programs involved with nanotechnology. Nanotechnology is the understanding and control of matter at the nanoscale, at dimensions between ∼1 and 100 nm, where unique phenomena enable novel applications. While the full report is in preparation, this paper presents and applies an informatics-based decision-making framework and process through which the radiation protection community can anticipate that nano-enabled applications, processes, nanomaterials, and nanoparticles are likely to become present or are already present in radiation-related activities; recognize specific situations where environmental and worker safety, health, well-being, and productivity may be affected by nano-related activities; evaluate how radiation protection practices may need to be altered to improve protection; control information, interpretations, assumptions, and conclusions to implement scientifically sound decisions and actions; and confirm that desired protection outcomes have been achieved. This generally applicable framework and supporting process can be continuously applied to achieve health and safety at the convergence of nanotechnology and radiation-related activities.

  20. A comparison between prescriptive- and performance-based approaches in fire safety design of structures

    DEFF Research Database (Denmark)

    Budny, Iwona; Giuliani, Luisa

    2010-01-01

    is therefore of interest. Furthermore, the method based on prescriptive procedures is not free of design limitations and does not provide detailed information about the structure’s performance under high temperature, which is often crucial if a disproportionate collapse must be avoided. The more advanced......A provision of an adequate consideration of both the people and structure safety is a crucial goal in a rational fire design. However, only a partial agreement concerning the general structural fire safety approach exists, and several meaningful discrepancies concerning the design and verification...... approach of performance-based fire design (PBFD) becomes therefore more and more popular. A higher design flexibility based on performance objectives constitutes a beneficial and competitive concept within the structural fire safety engineering, ensuring a higher safety level of a design choice. The aim...

  1. 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.

  2. Use of information technologies to contribute for optimizing the safety radiation management in Cuba; Uso de las tecnologias de la informacion, para contribuir a la optimizacion de la gestion de la seguridad radiologica en Cuba

    Energy Technology Data Exchange (ETDEWEB)

    Valdes Ramos, M.; Prendes Alonso, M.; Hernandez Saiz, A.; Manzano de Armas, J., E-mail: zury@cphr.edu.cu [Agencia de Energia Nuclear y Tecnologias de Avanzada (CPHR/AENTA), La Habana (Cuba). Centro de Proteccion e Higiene de las Radiaciones

    2013-11-01

    This paper presents the results achieved in Cuba, with the development of a group of information management tools to implement radiation safety systemic and proactive approaches to safety and ICT supported. These tools were designed for different organisms with responsibility for the security at the country level, to the regulatory authority, for user entities, for individual monitoring services and other radiation protection services. It describes the philosophy of information management model used, the characteristics of the developed tools and their integration, the work performed for the homogenization of information available and the ability to capture and deliver data at different levels in decision making. The tools developed are based on the use of variables and indicators of importance to the safety and the systemic approach adopted allows to facilitate the optimization process for supervision of safety practices as well as contribute to the management of knowledge in radiation safety, through a synergistic combination of process data, information, information management systems, and the creative and innovative radiation safety experts.

  3. Improvement of microbiological safety of sous-vide meals by gamma radiation

    Energy Technology Data Exchange (ETDEWEB)

    Farkas, J. E-mail: huto@omega.kee.hu; Polyak-Feher, K.; Andrassy, E.; Meszaros, L

    2002-03-01

    Experimental batches of smoked-cured pork in stewed beans sauce were inoculated with spores of psychrotrophic Bacillus cereus, more heat and radiation resistant than spores of non-proteolytic C. botulinum. After vacuum packaging, the meals were treated with combinations of pasteurizing heat treatments and gamma irradiation of 5 kGy. Prior and after treatments, and periodically during storage at 10 deg. C, total aerobic and total anerobic viable cell counts, and selectively, the viable cell counts of B. cereus and sulphite-reducing clostridia have been determined. The effects of the treatment order as well as addition of nisin to enhance the preservative efficiency of the physical treatments were also studied. Heat-sensitization of bacterial spores surviving irradiation occurred. The quality-friendly sous-vide cooking in combination with this medium dose gamma irradiation and/or nisin addition increased considerably the microbiological safety and the keeping quality of the meals studied. However, approx. 40% loss of thiamin content occurred as an effect of combination treatments, and adverse sensorial effects may also limit the feasible radiation doses or the usable concentrations of nisin.

  4. Radiation safety aspects in application of isotopes for industrial radiography in Bangladesh

    Energy Technology Data Exchange (ETDEWEB)

    Bakht, D. [Titas Gas Transmission and Distribution Company, Dhaka (Bangladesh)

    1997-10-01

    Industrial Radiography arose out of the widespread applications of X-rays pioneered by Roentgen about 100 years back. It is routinely used in studying the integrity of structural materials and like most countries in the world, its use in Bangladesh is increasing at a faster rate. This is because Bangladesh is a developing country of 3rd world and in the backdrop of agrarian poverty ridden economy, its population may exceed 125 millions by 2000 AD, leaving some 12 millions people unemployed. To support them, therefore, immense activities are activated in different sectors. Accordingly, increasing importance on NDT is given and in most cases particular application of Gamma radiography is preferred using Iridium Isotope Ir-192. Consequently the points of implications of isotopes are in Open Field and Inservice Inspection Radiography, Handling of Radiation Emergencies, Safe Transport of Radioactive Materials and Hazardous Effects and Risk of Ionizing Radiation, etc. Accordingly over exposure of Ir-192 Radionuclides, Accidents and Unusual Occurrences: Case Studies, Training Courses on Safety and Regulation of Sealed Sources, Licenses for Radiography Operation including Safe Disposal of Isotopes are the salient issues to be viewed in appropriate perspectives. The role played by Bangladesh Atomic Energy Commission and Bangladesh Society for NDT in collaboration with other members of the international committee for NDT are furthering the safe industrialization process

  5. Improvement of microbiological safety of sous-vide meals by gamma radiation

    Science.gov (United States)

    Farkas, J.; Polyák-Fehér, K.; Andrássy, É.; Mészáros, L.

    2002-03-01

    Experimental batches of smoked-cured pork in stewed beans sauce were inoculated with spores of psychrotrophic Bacillus cereus, more heat and radiation resistant than spores of non-proteolytic C. botulinum. After vacuum packaging, the meals were treated with combinations of pasteurizing heat treatments and gamma irradiation of 5 kGy. Prior and after treatments, and periodically during storage at 10°C, total aerobic and total anerobic viable cell counts, and selectively, the viable cell counts of B. cereus and sulphite-reducing clostridia have been determined. The effects of the treatment order as well as addition of nisin to enhance the preservative efficiency of the physical treatments were also studied. Heat-sensitization of bacterial spores surviving irradiation occurred. The quality-friendly sous-vide cooking in combination with this medium dose gamma irradiation and/or nisin addition increased considerably the microbiological safety and the keeping quality of the meals studied. However, approx. 40% loss of thiamin content occurred as an effect of combination treatments, and adverse sensorial effects may also limit the feasible radiation doses or the usable concentrations of nisin.

  6. Efficacy and safety of polaprezinc as a preventive drug for radiation-induced stomatitis

    Energy Technology Data Exchange (ETDEWEB)

    Fujiwara, Masayuki; Kamikonya, Norihiko; Tsuboi, Keita; Nakao, Norio [Hyogo Coll. of Medicine, Nishinomiya (Japan); Irie, Miwa [Takarazuka Municipal Hospital, Hyogo (Japan); Izumi, Masayuki [Minamiosaka Total Health Care Center, Osaka (Japan); Irie, Toshihiko; Fujisawa, Hiromi; Muro, Chikaaki [Hyogo Coll. of Medicine, Nishinomiya (Japan). Hospital

    2002-03-01

    Radiation-induced stomatitis is one of the adverse effects of total body irradiation (TBI). We examined the usefulness of oral polaprezinc as a preventive drug for stomatitis. The present study was conducted with 19 patients who were diagnosed with hematologic malignancy and who underwent TBI as pretreatment for bone marrow transplantation, peripheral blood stem transplantation, or cord blood stem cell transplantation. Eleven patients ingested the suspension of polaprezinc and 2% carmellose sodium (carboxymethylcellulose sodium: CMC) beginning the day before TBI (P-CMC group), while the other eight patients did not ingest P-CMC (control group). The severity of stomatitis was assessed in each group during a four-weeks period. Stomatitis (Grade:{>=}3) developed in one of 11 patients in the polaprezinc group and in 4 of 8 patients in the control group (P=0.046). The times at which stomatitis development ranged between weeks 1 and 2 after the onset of TBI in the two groups. No adverse reaction owing to the ingestion of P-CMC was observed. These results suggested the efficacy and safety of polaprezinc as a preventive drug for radiation-induced stomatitis. (author)

  7. Efficacy and safety of far infrared radiation in lymphedema treatment: clinical evaluation and laboratory analysis.

    Science.gov (United States)

    Li, Ke; Zhang, Zheng; Liu, Ning Fei; Feng, Shao Qing; Tong, Yun; Zhang, Ju Fang; Constantinides, Joannis; Lazzeri, Davide; Grassetti, Luca; Nicoli, Fabio; Zhang, Yi Xin

    2017-01-26

    Swelling is the most common symptom of extremities lymphedema. Clinical evaluation and laboratory analysis were conducted after far infrared radiation (FIR) treatment on the main four components of lymphedema: fluid, fat, protein, and hyaluronan. Far infrared radiation is a kind of hyperthermia therapy with several and additional benefits as well as promoting microcirculation flow and improving collateral lymph circumfluence. Although FIR therapy has been applied for several years on thousands of lymphedema patients, there are still few studies that have reported the biological effects of FIR on lymphatic tissue. In this research, we investigate the effects of far infrared rays on the major components of lymphatic tissue. Then, we explore the effectiveness and safety of FIR as a promising treatment modality of lymphedema. A total of 32 patients affected by lymphedema in stage II and III were treated between January 2015 and January 2016 at our department. After therapy, a significant decrease of limb circumference measurements was noted and improving of quality of life was registered. Laboratory examination showed the treatment can also decrease the deposition of fluid, fat, hyaluronan, and protein, improving the swelling condition. We believe FIR treatment could be considered as both an alternative monotherapy and a useful adjunctive to the conservative or surgical lymphedema procedures. Furthermore, the real and significant biological effects of FIR represent possible future applications in wide range of the medical field.

  8. Fear patterns: a new approach to designing road safety advertisements.

    Science.gov (United States)

    Algie, Jennifer; Rossiter, John R

    2010-01-01

    This research studies fear patterns within fear appeal anti-speeding television commercials. A pattern of fear is the sequence of fear arousal and fear reduction, if any, that is felt by the viewing audience when exposed to a fear appeal advertisement. Many road safety advertisers use fear appeals, such as "shock" advertising, that result in fear arousal, leaving the viewer feeling extremely tense. The moment-to-moment reactions of young drivers to 12 road safety commercials are gauged using a dynamic, temporal measure of fear. The fear patterns generated from each ad are analyzed and a new perspective on creating fear appeal road safety advertisements, with an emphasis on fear-relief, fear-partial relief, and fear-only patterns, is discussed.

  9. Design of Traceability System for Pork Safety Production

    Institute of Scientific and Technical Information of China (English)

    2009-01-01

    With the development of society and the improvement of living standards,consumers’demand for high quality meat products is constantly increasing.Traceability for livestock products is widely recognized to be an effective measure for any modern and integrated food safety control system.The quality tracing and traceability system of production’s entire processes is an important technology tool to protect pork safety.This paper proposes a RFID-enabled traceability system for pork supply chain.By adopting SQL Server 2000 databases and intelligent identification technology,a tracing system suitable to Chinese situation for monitoring and controlling quality of pork is constructed,and it manages to realize information traceability for entire pork production.The study indicates that the traceability system is valuable for practical reference and feasible.It can help consumers to confide in pork safety and encourage the pork industry developing.

  10. Applications of radiation processing in combination with conventional treatments to assure food safety: New development

    Energy Technology Data Exchange (ETDEWEB)

    Lacroix, M. [Canadian Irradiation Center, Research Laboratory in Sciences Applied to Food, INRS-Institut Armand-Frappier, 531 Boulevard des Prairies, Laval, Quebec (Canada)], E-mail: monique.lacroix@iaf.inrs.ca; Turgis, M. [Canadian Irradiation Center, Research Laboratory in Sciences Applied to Food, INRS-Institut Armand-Frappier, 531 Boulevard des Prairies, Laval, Quebec (Canada); Borsa, J. [MDS Nordion, 447 March Road, Kanata, Ontario, K2K 2P7 (Canada); Millette, M.; Salmieri, S.; Caillet, S. [Canadian Irradiation Center, Research Laboratory in Sciences Applied to Food, INRS-Institut Armand-Frappier, 531 Boulevard des Prairies, Laval, Quebec (Canada); Han, J. [Sungkyunkwan University, Department of Food Science and Biotechnology, Suwon 440-746 (Korea, Republic of)

    2009-11-15

    Spice extracts under the form of essential oils (Eos) were tested for their efficiency to increase the relative bacterial radiosensitivity (RBR) of Listeria monocytogenes, Escherichia coli and Salmonellatyphi in culture media under different atmospheric conditions. The selected Eos were tested for their ability to reduce the dose necessary to eliminate E. coli and S.typhi in medium fat ground beef (23% fat) and Listeria in ready-to-eat carrots when packed under air or under atmosphere rich in oxygen (MAP). Results have demonstrated that depending of the compound added and the combined treatment used, the RBR increased from 2 to 4 times. In order to evaluate the industrial feasibility, EOs were added in ground beef at a concentration which does not affect the taste and treated at a dose of 1.5 kGy. The content of total mesophilic aerobic, E. coli, Salmonella, total coliform, lactic acid bacteria, and Pseudomonas was determined during 28 days. The results showed that the combined treatment (radiation and EOs) can eliminate Salmonella and E. coli when done under air. When done under MAP, Pseudomonas could be eliminated and a shelf life of more than 28 days was observed. An active edible coating containing EOs was also developed and sprayed on ready-to-eat carrots before radiation treatment and Listeria was evaluated. A complete inhibition of Listeria was obtained at a dose of 0.5 kGy when applied under MAP. Our results have shown that the combination of an edible coating, MAP, and radiation can be used to maintain the safety of meat and vegetables.

  11. Applications of radiation processing in combination with conventional treatments to assure food safety: New development

    Science.gov (United States)

    Lacroix, M.; Turgis, M.; Borsa, J.; Millette, M.; Salmieri, S.; Caillet, S.; Han, J.

    2009-11-01

    Spice extracts under the form of essential oils (Eos) were tested for their efficiency to increase the relative bacterial radiosensitivity (RBR) of Listeria monocytogenes, Escherichia coli and Salmonellatyphi in culture media under different atmospheric conditions. The selected Eos were tested for their ability to reduce the dose necessary to eliminate E. coli and S.typhi in medium fat ground beef (23% fat) and Listeria in ready-to-eat carrots when packed under air or under atmosphere rich in oxygen (MAP). Results have demonstrated that depending of the compound added and the combined treatment used, the RBR increased from 2 to 4 times. In order to evaluate the industrial feasibility, EOs were added in ground beef at a concentration which does not affect the taste and treated at a dose of 1.5 kGy. The content of total mesophilic aerobic, E. coli, Salmonella, total coliform, lactic acid bacteria, and Pseudomonas was determined during 28 days. The results showed that the combined treatment (radiation and EOs) can eliminate Salmonella and E. coli when done under air. When done under MAP, Pseudomonas could be eliminated and a shelf life of more than 28 days was observed. An active edible coating containing EOs was also developed and sprayed on ready-to-eat carrots before radiation treatment and Listeria was evaluated. A complete inhibition of Listeria was obtained at a dose of 0.5 kGy when applied under MAP. Our results have shown that the combination of an edible coating, MAP, and radiation can be used to maintain the safety of meat and vegetables.

  12. Radiation Constraints in the Design and Conception of LHC Control Systems

    CERN Document Server

    Pignard, Christian; Rausch, R; Tsoulou, A; Wijnands, Thijs

    2003-01-01

    The radiation constraint for the design and conception of LHC controls systems is described. One of the criteria when selecting electronic components is their radiation tolerance. Complete control systems are designed to operate reliable even when data is occasionally being corrupted by high energetic particles. Radiation also has an impact on the architecture, layout and integration of a control system. Finally, development costs, system functionality, reliability and the overall life span of a radiation tolerant control system are discussed.

  13. Physical design correlates of efficiency and safety in emergency departments: a qualitative examination.

    Science.gov (United States)

    Pati, Debajyoti; Harvey, Thomas E; Pati, Sipra

    2014-01-01

    The objective of this study was to explore and identify physical design correlates of safety and efficiency in emergency department (ED) operations. This study adopted an exploratory, multimeasure approach to (1) examine the interactions between ED operations and physical design at 4 sites and (2) identify domains of physical design decision-making that potentially influence efficiency and safety. Multidisciplinary gaming and semistructured interviews were conducted with stakeholders at each site. Study data suggest that 16 domains of physical design decisions influence safety, efficiency, or both. These include (1) entrance and patient waiting, (2) traffic management, (3) subwaiting or internal waiting areas, (4) triage, (5) examination/treatment area configuration, (6) examination/treatment area centralization versus decentralization, (7) examination/treatment room standardization, (8) adequate space, (9) nurse work space, (10) physician work space, (11) adjacencies and access, (12) equipment room, (13) psych room, (14) staff de-stressing room, (15) hallway width, and (16) results waiting area. Safety and efficiency from a physical environment perspective in ED design are mutually reinforcing concepts--enhancing efficiency bears positive implications for safety. Furthermore, safety and security emerged as correlated concepts, with security issues bearing implications for safety, thereby suggesting important associations between safety, security, and efficiency.

  14. 78 FR 51754 - Request To Modify License by Replacing Security Plan With New Radiation Safety Plan; U.S...

    Science.gov (United States)

    2013-08-21

    ..., requesting to replace its security plan with a new radiation safety plan. DATES: Submit comments by September... authorizes the licensee to possess depleted uranium. The proposed change is to modify License Condition No... entities participating under 10 CFR 2.315(c), must be filed in accordance with the NRC E-Filing rule (72...

  15. Environmental Modelling for Radiation Safety (EMRAS) — A Summary Report of the Results of the EMRAS Programme (2003-2007)

    DEFF Research Database (Denmark)

    Arkhipov, A.; Charnock, T.W.; Gaschak, S.

    This publication provides a detailed overview of the results and achievements of the IAEA programme called EMRAS (Environmental Modelling for Radiation Safety), which ran from 2003 to 2007. The activities of the various working groups focused on the compilation of a handbook of parameter values f...

  16. Nuclear Safety Functions of ITER Gas Injection System Instrumentation and Control and the Concept Design

    Science.gov (United States)

    Yang, Yu; Maruyama, S.; Fossen, A.; Villers, F.; Kiss, G.; Zhang, Bo; Li, Bo; Jiang, Tao; Huang, Xiangmei

    2016-08-01

    The ITER Gas Injection System (GIS) plays an important role on fueling, wall conditioning and distribution for plasma operation. Besides that, to support the safety function of ITER, GIS needs to implement three nuclear safety Instrumentation and Control (I&C) functions. In this paper, these three functions are introduced with the emphasis on their latest safety classifications. The nuclear I&C design concept is briefly discussed at the end.

  17. Modelling of Safety Factors in the Design of GRP Composite Products

    DEFF Research Database (Denmark)

    Babu, B.J.C.; Prabhakaran, R.T. Durai; Lystrup, Aage

    2010-01-01

    An attempt has been made in this paper to arrive at the safety factor design of glass fibre reinforced polymer (GRP) composite products using graph theoretic model. In the conventional design and recommendations of the standards, these design factors affecting properties have been considered as i...... that the proposed overall factor of safety is an appropriate and comprehensive measure of factor of safety. The proposed methodology is illustrated for a typical resin transfer moulded (RTM) fume hood. The concept can easily be extended for other applications....

  18. Brazed Joints Design and Allowables: Discuss Margins of Safety in Critical Brazed Structures

    Science.gov (United States)

    FLom, Yury

    2009-01-01

    This slide presentation tutorial discusses margins of safety in critical brazed structures. It reviews: (1) the present situation (2) definition of strength (3) margins of safety (4) design allowables (5) mechanical testing (6) failure criteria (7) design flowchart (8) braze gap (9) residual stresses and (10) delayed failures. This presentation addresses the strength of the brazed joints, the methods of mechanical testing, and our ability to evaluate the margins of safety of the brazed joints as it applies to the design of critical and expensive brazed assemblies.

  19. High-voltage safety fuses for the transition-radiation tracking detector in the ATLAS experiment

    CERN Document Server

    Voronov, S A; Onishchenko, E M; Simakov, A B; Sosnovtsev, V V; Suchkov, S; Sugrobova, T A

    2004-01-01

    A safety fuse has been designed for the electrical protection of gas- filled detectors in the ATLAS experiment at CERN (Geneva, Switzerland). The fuse is a polished lithium niobate plate with a titanium strip of 91-kOmega resistance deposited by the photolithographic technique. The forced blowout time of the fuse is 10-50 ms; whereupon the leakage current through it is less than 1 nA at a 2-kV voltage. The resistance of the fuse case is greater than or equivalent equal' greater than 10**1**2 Omega. Its overall dimensions are 5.8 multiplied by 3.8 multiplied by 2 mm.

  20. Design for sustainable development : environmental management and safety and health

    NARCIS (Netherlands)

    Zwetsloot, G.; Bos, J.

    1998-01-01

    This is a report on the EU's environmental management and audit scheme and its interaction with the management of safety and health. The focus is on the interactions at company and at policy level. To illustrate the relevance of the interactions at company level, the Annex includes five case studies

  1. Electronics system design techniques for safety critical applications

    CERN Document Server

    Sterpone, Luca

    2008-01-01

    Addresses the development of techniques for the evaluation and the hardening of designs implemented on SRAM-based Field Programmable Gate Arrays. This title presents a design methodology solving industrial designer''s needs for implementing electronic systems using SRAM-based FPGAs in critical environments, like the space or avionic ones.

  2. Nuclear Safety and Radiation Protection in Europe - a common approach; Surete nucleaire et radioprotection en Europe - une approche commune

    Energy Technology Data Exchange (ETDEWEB)

    McGarry, Ann [Institut irlandais de protection radiologique - RPII (Ireland)

    2010-11-15

    In Europe, the European Union has adopted directives and implemented other measures which form the basis of a common approach to nuclear safety and radiation protection across all Member States. In particular, there are EU directives setting out radiation protection standards and establishing a Community framework for the nuclear safety of nuclear installations. There are also arrangements in place to provide for an effective response to nuclear emergencies and to facilitate high quality research into nuclear and radiation protection related topics. Inevitably the stage of development in each area is somewhat different, but generally progress is ongoing in each area. From the point of view of a small country like Ireland, the development of common standards and arrangements across Europe is beneficial as they are based on the best available knowledge and expertise; they provide for greater transparency; they facilitate public confidence and make best use of the available resources. However, there are some areas in which common approaches could be further advanced. For example, the medical exposure of patients is increasingly of concern across Europe and the further development of common approaches in this area would be helpful. It would also be useful to develop a more integrated approach to nuclear safety and radiation protection regulation and to better integrate nuclear and radiation issues with other public health and environment concerns. (author)

  3. Safety learning and imagination versus safety bureaucracy in design of the traffic sector.

    NARCIS (Netherlands)

    Jagtman, H.M. & Hale, A.R.

    2007-01-01

    This paper deals with the processes of evaluating the possible safety eVects of measures introduced either in the road infrastructure or in the electronic and information systems in cars. It uses speed control measures (speed bumps and the Intelligent Speed Adapter [ISA]) as cases to describe and

  4. Safety concerns and suggested design approaches to the HTGR Reformer process concept

    Energy Technology Data Exchange (ETDEWEB)

    Green, R.C.

    1981-09-01

    This report is a safety review of the High Temperature Gas-Cooled Reactor Reformer Application Study prepared by Gas-Cooled Reactor Associates (GCRA) of La Jolla, California. The objective of this review was to identify safety concerns and suggests design approaches to minimize risk in the High Temperature Gas-Cooled Reactor Reformer (HTGR-R) process concept.

  5. The Designing Bus for Nuclear Safety Class Controller

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Dongil; Lee, Myeongkyun; Yun, Donghwa [PONUTech Co,. Ltd., Research Institute, Ulsan (Korea, Republic of); Ryoo, Kwangki [Hanbat National Univ., Daejeon (Korea, Republic of)

    2013-10-15

    EtherCAT (Ethernet for Control Automation Technology) is based on the IEEE 802.3 standard as one of the communication which is the I/O (Input/Output), sensors and communication function of PLC (Programmable Logic Controller) in industry and factory environment use is increasing. The Nuclear Safety Class Controller implemented by the EtherCAT applied bus can be shown the improving performance of data transmission in the controller.

  6. Safety

    CERN Multimedia

    2003-01-01

    Please note that the safety codes A9, A10 AND A11 (ex annexes of SAPOCO/42) entitled respectively "Safety responsibilities in the divisions" "The safety policy committee (SAPOCO) and safety officers' committees" and "Administrative procedure following a serious accident or incident" are available on the web at the following URLs: Code A9: http://edms.cern.ch/document/337016/LAST_RELEASED Code A10: http://edms.cern.ch/document/337019/LAST_RELEASED Code A11: http://edms.cern.ch/document/337026/LAST_RELEASED Paper copies can also be obtained from the TIS divisional secretariat, e-mail: tis.secretariat@cern.ch. TIS Secretariat

  7. Modeling safety in a distributed technology management environment for more cost-effective conceptual design of chemical process plants

    NARCIS (Netherlands)

    Schupp, B.A.; Lemkowitz, S.M.; Goossens, L.H.J.; Hale, A.R.; Pasman, H.J.

    2002-01-01

    Profitability of the CPI can improve by better integrating safety into the design process. At present, conceptual desgners lack means to design safety. This paper discusses a methodology, Design for Safety (DFS), that strives to provide these. It consists of two major concepts. A technology

  8. Modeling safety in a distributed technology management environment for more cost-effective conceptual design of chemical process plants

    NARCIS (Netherlands)

    Schupp, B.A.; Lemkowitz, S.M.; Goossens, L.H.J.; Hale, A.R.; Pasman, H.J.

    2002-01-01

    Profitability of the CPI can improve by better integrating safety into the design process. At present, conceptual desgners lack means to design safety. This paper discusses a methodology, Design for Safety (DFS), that strives to provide these. It consists of two major concepts. A technology manageme

  9. 48 CFR 52.250-4 - SAFETY Act Pre-qualification Designation Notice.

    Science.gov (United States)

    2010-10-01

    ...) Definitions. As used in this provision— Act of terrorism means any act determined to have met the following... which pricing or any other terms or conditions are offered contingent upon SAFETY Act designation...

  10. 48 CFR 52.250-3 - SAFETY Act Block Designation/Certification.

    Science.gov (United States)

    2010-10-01

    ...), insert the following provision: Safety Act Block Designation/Certification (FEB 2009) (a) Definitions. As... of Homeland Security, Washington, DC 20528. (f) Proposals in which pricing or any other terms...

  11. Safety factors for structural design-history and developments

    NARCIS (Netherlands)

    Straalen, IJ.J. van

    2000-01-01

    The design of structures is concemed with the generation of solutions and the verification of the reliability. potential design solutions are a result of a process of problem formulation, definition of objeciive functions, conceptual design and optimization. To control this process, many strategies

  12. The nuclear safety and the radiation protection in France in 2003; La surete nucleaire et la radioprotection en France en 2003

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-03-15

    Nine points are reviewed: the law project relative to the safety and openness in nuclear field, the safety of the European PWR type Reactor, the priorities in radiation protection, inspection of radiation protection, the surveillance of patients exposure to ionizing radiations, the hot days and dryness of summer 2003 and the functioning of nuclear power plant, the national planning of radioactive waste management, the becoming of high level and years living radioactive waste, the European nuclear policy. (N.C.)

  13. Physics Design of Criticality Assembly in Experimental Research About Criticality Safety in Spent Fuel Dissolver

    Institute of Scientific and Technical Information of China (English)

    ZHOU; Qi

    2012-01-01

    <正>In order to meet the experimental demand of criticality safety research in the spent fuel dissolver, we need to design a suitable criticality assembly. The key problem of the design work is the core design because there are many limits for it such as the number of fuel rods loaded, fissile materials existed in the solution, reactivity control, core size and etc.

  14. Managing NIF safety equipment in a high neutron and gamma radiation environment.

    Science.gov (United States)

    Datte, Philip; Eckart, Mark; Jackson, Mark; Khater, Hesham; Manuel, Stacie; Newton, Mark

    2013-06-01

    The National Ignition Facility (NIF) is a 192 laser beam facility that supports the Inertial Confinement Fusion program. During the ignition experimental campaign, the NIF is expected to perform shots with varying fusion yield producing 14 MeV neutrons up to 20 MJ or 7.1 × 10(18) neutrons per shot and a maximum annual yield of 1,200 MJ. Several infrastructure support systems will be exposed to varying high yield shots over the facility's 30-y life span. In response to this potential exposure, analysis and testing of several facility safety systems have been conducted. A detailed MCNP (Monte Carlo N-Particle Transport Code) model has been developed for the NIF facility, and it includes most of the major structures inside the Target Bay. The model has been used in the simulation of expected neutron and gamma fluences throughout the Target Bay. Radiation susceptible components were identified and tested to fluences greater than 10(13) (n cm(-2)) for 14 MeV neutrons and γ-ray equivalent. The testing includes component irradiation using a 60Co gamma source and accelerator-based irradiation using 4- and 14- MeV neutron sources. The subsystem implementation in the facility is based on the fluence estimates after shielding and survivability guidelines derived from the dose maps and component tests results. This paper reports on the evaluation and implementation of mitigations for several infrastructure safety support systems, including video, oxygen monitoring, pressure monitors, water sensing systems, and access control interfaces found at the NIF.

  15. Recommendations for the Design and Construction of Safety Related User Programs

    DEFF Research Database (Denmark)

    Ehrenberger, W. D.; Taylor, J. R.

    1977-01-01

    Summarises that state of the art in writing programs for process computers, which have to meet safety requirements and therefore must be licensed. The principles of such programs are given as well as more detailed recommendations for their design and construction.......Summarises that state of the art in writing programs for process computers, which have to meet safety requirements and therefore must be licensed. The principles of such programs are given as well as more detailed recommendations for their design and construction....

  16. Design and safety analysis of the helium cooled solid breeder blanket for CFETR

    Energy Technology Data Exchange (ETDEWEB)

    Wang, Shuai; Zhou, Guangming; Lv, Zhongliang; Jin, Cheng; Chen, Hongli [University of Science and Technology of China, Anhui (China). School of Nuclear Science and Technology

    2016-05-15

    This paper reports the design and safety analysis results of the helium cooled solid breeder blanket of the Chinese Fusion Engineering Test Reactor (CFETR). Materials selection and basic structure of the blanket have been presented. Performance analysis including neutronics analysis and thermo-mechanical analysis has shown good results. And the safety analysis of the blanket under Loss Of Coolant Accident (LOCA) conditions has been described. Results showed the current design can deal well with the selected accident scenarios.

  17. Design for Safety - The Ares Launch Vehicles Paradigm Change

    Science.gov (United States)

    Safie, Fayssal M.; Maggio, Gaspare

    2010-01-01

    The lessons learned from the S&MA early involvement in the Ares I launch vehicle design phases proved that performing an in-line function jointly with engineering is critical for S&MA to have an effective role in supporting the system, element, and component design. These lessons learned were used to effectively support the Ares V conceptual design phase and planning for post conceptual design phases. The Top level Conceptual LOM assessment for Ares V performed by the S&MA community jointly with the engineering Advanced Concept Office (ACO) was influential in the final selection of the Ares V system configuration. Post conceptual phase, extensive reliability effort should be planned to support future Heavy Lift Launch Vehicles (HLLV) design. In-depth reliability analysis involving the design, manufacturing, and system engineering communities is critical to understand design and process uncertainties and system integrated failures.

  18. Viimsi water treatment plant for Ra removal: NORM residue/waste generation, radiation safety issues, and regulatory response

    Energy Technology Data Exchange (ETDEWEB)

    Kiisk, M.; Suursoo, S.; Realo, E.; Jantsikene, A.; Lumiste, L.; Vaeaer, K.; Isakar, K.; Koch, R. [University of Tartu (Estonia)

    2014-07-01

    In early 2012, the first large-scale water treatment plant, specifically designed to remove Ra-isotopes from groundwater, was commissioned in Viimsi parish, North-Estonia. The plant serves approximately 15 000 consumers with maximum production capacity of 6000 m{sup 3}/d. The chosen water treatment technology is chemical free and is based on co-precipitation and adsorption with Fe(OH){sub 3} and MnO{sub 2} flocks, and adsorption of residual Ra onto zeolite sand. The chosen technology is a complex approach and is designed to reduce high Fe and Mn concentrations as well as dissolved gases along with Ra isotopes. It is proved to be well adapted with hydro-chemical conditions of the groundwater feeding the plant. As the novel technology has been applied for the first time on a large scale, the plant was taken under long-term investigation when commissioned. The latter focuses on three areas: Ra removal efficiency and its dynamics, build-up of radioactive waste, and radiation safety. The average Ra-226 and Ra-228 activity concentrations in raw water feeding the plant are approximately 0.5 Bq/L and 0.6 Bq/L, respectively, resulting in total indicative dose of 0.4 mSv/y. Operating conditions of the plant are restricted by the established indicative value of 0.1 mSv/y for drinking water, i.e. a minimum 75% removal efficiency for Ra is required. Results of the studies show that the plant operates at Ra-removal efficiency of 98% or higher without the need of regeneration or replacement of filtering materials within the first two years. Measurements confirm that ∼90% of Ra accumulates in the solid filter media, 8-9% is washed out by backwash system as liquid effluent and 1-2% is fed on to the consumer distribution network. It has been calculated that at the level of current production capacity (below 3000 m{sup 3}/d) the yearly accumulation rate in the plant is approximately 300 and 400 MBq/y for Ra-226 and Ra-228, respectively. These values strongly exceed the exemption

  19. Lower oil prices, safety influence offshore design trends

    Energy Technology Data Exchange (ETDEWEB)

    Dino, G.M. (Fluor Daniel Inc., Sugar Land, TX (US))

    1989-08-07

    Current international design trends offshore are towards bigger topsides facilities, deeper water gravity support structures, cheaper facility and structure construction technology, and safer platform equipment/module layouts and process design. There are international examples that typify these four design trends. Offshore oil and gas development has grown steadily in size, water depth, cost, complexity, and technology since the first offshore field out of sight of land was found in 1947 in the Gulf of Mexico. Design trends in the offshore industry have also evolved to meet the technological challenges of the day.

  20. Accelerator and radiation physics

    CERN Document Server

    Basu, Samita; Nandy, Maitreyee

    2013-01-01

    "Accelerator and radiation physics" encompasses radiation shielding design and strategies for hadron therapy accelerators, neutron facilities and laser based accelerators. A fascinating article describes detailed transport theory and its application to radiation transport. Detailed information on planning and design of a very high energy proton accelerator can be obtained from the article on radiological safety of J-PARC. Besides safety for proton accelerators, the book provides information on radiological safety issues for electron synchrotron and prevention and preparedness for radiological emergencies. Different methods for neutron dosimetry including LET based monitoring, time of flight spectrometry, track detectors are documented alongwith newly measured experimental data on radiation interaction with dyes, polymers, bones and other materials. Design of deuteron accelerator, shielding in beam line hutches in synchrotron and 14 MeV neutron generator, various radiation detection methods, their characteriza...

  1. Preliminary safety analysis for key design features of KALIMER with breakeven core

    Energy Technology Data Exchange (ETDEWEB)

    Hahn, Do Hee; Kwon, Y. M.; Chang, W. P.; Suk, S. D.; Lee, Y. B.; Jeong, K. S

    2001-06-01

    KAERI is currently developing the conceptual design of a Liquid Metal Reactor, KALIMER (Korea Advanced Liquid MEtal Reactor) under the Long-term Nuclear R and D Program. KALIMER addresses key issues regarding future nuclear power plants such as plant safety, economics, proliferation, and waste. In this report, descriptions of safety design features and safety analyses results for selected ATWS accidents for the breakeven core KALIMER are presented. First, the basic approach to achieve the safety goal is introduced in Chapter 1, and the safety evaluation procedure for the KALIMER design is described in Chapter 2. It includes event selection, event categorization, description of design basis events, and beyond design basis events.In Chapter 3, results of inherent safety evaluations for the KALIMER conceptual design are presented. The KALIMER core and plant system are designed to assure benign performance during a selected set of events without either reactor control or protection system intervention. Safety analyses for the postulated anticipated transient without scram (ATWS) have been performed to investigate the KALIMER system response to the events. In Chapter 4, the design of the KALIMER containment dome and the results of its performance analyses are presented. The design of the existing containment and the KALIMER containment dome are compared in this chapter. Procedure of the containment performance analysis and the analysis results are described along with the accident scenario and source terms. Finally, a simple methodology is introduced to investigate the core energetics behavior during HCDA in Chapter 5. Sensitivity analyses have been performed for the KALIMER core behavior during super-prompt critical excursions, using mathematical formulations developed in the framework of the Modified Bethe-Tait method. Work energy potential was then calculated based on the isentropic fuel expansion model.

  2. Safety and Efficacy of Ultrasound-Guided Fiducial Marker Implantation for CyberKnife Radiation Therapy

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Jae Hyun; Hong, Seong; Sook; Kim, Jung Hoon; Park, Hyun Jeong; Chang, Yun Woo; Chang, A Ram [Soonchunhyang University Seoul Hospital, Seoul (Korea, Republic of); Kwon, Seok Beom [Hallym University College of Medicine, Chuncheon (Korea, Republic of)

    2012-06-15

    To evaluate the safety and technical success rate of an ultrasound-guided fiducial marker implantation in preparation for CyberKnife radiation therapy. We retrospectively reviewed 270 percutaneous ultrasound-guided fiducial marker implantations in 77 patients, which were performed from June 2008 through March 2011. Of 270 implantations, 104 were implanted in metastatic lymph nodes, 96 were in the liver, 39 were in the pancreas, and 31 were in the prostate. During and after the implantation, major and minor procedure-related complications were documented. We defined technical success as the implantation enabling adequate treatment planning and CT simulation. The major and minor complication rates were 1% and 21%, respectively. One patient who had an implantation in the liver suffered severe abdominal pain, biloma, and pleural effusion, which were considered as major complication. Abdominal pain was the most common complication in 11 patients (14%). Among nine patients who had markers inserted in the prostate, one had transient hematuria for less than 24 hours, and the other experienced transient voiding difficulty. Of the 270 implantations, 261 were successful (97%). The reasons for unsuccessful implantations included migration of fiducial markers (five implantations, 2%) and failure to discriminate the fiducial markers (three implantations, 1%). Among the unsuccessful implantation cases, six patients required additional procedures (8%). The symptomatic complications following ultrasound-guided percutaneous implantation of fiducial markers are relatively low. However, careful consideration of the relatively higher rate of migration and discrimination failure is needed when performing ultrasound-guided percutaneous implantations of fiducial markers.

  3. Radiation prevulcanized natural rubber latex: Cytotoxicity and safety evaluation on animal

    Science.gov (United States)

    Keong, C. C.; Zin, W. M. Wan; Ibrahim, P.; Ibrahim, S.

    2010-05-01

    Radiation prevulcanized natural rubber latex (RVNRL) was claimed to be more user friendly than natural rubber latex prevulcanized by sulphur curing system. The absence of Type IV allergy inducing chemicals in RVNRL make it a suitable material for manufacturing of many kinds of latex products, especially those come into direct contact with users. This paper reveals and discusses the findings of cytotoxicity test and safety evaluation on animal for RVNRL. The test was done on RVNRL films prepared by coagulant dipping method and RVNRL dipped products produced by latex dipped product manufacturers. Cytotocixity test was carried out on mammalian cell culture American Type Culture Collection CCL 81, Vero. Results indicated that no cytotoxic effect from RVNRL films and products was found on the cell culture. Two animal studies, namely dermal sensitization study and primary skin irritation study, were done on gloves made from RVNRL. Albino white guinea pigs were used as test subjects in dermal sensitization study and results showed no sensitization induced by the application of test material in the guinea pigs. Primary skin irritation study was done on New Zealand white rabbits and results showed that the product tested was not corrosive and was not a primary irritant

  4. Safety of Redo Hepatectomy for Colorectal Liver Metastases after Selective Interarterial Radiation Therapy: A Case Report

    Directory of Open Access Journals (Sweden)

    Kyriakos Neofytou

    2014-01-01

    Full Text Available Surgical resection is the only potentially curative strategy in the treatment of patients with colorectal liver metastases (CLM. Unfortunately, only about 10%–15% of patients are candidates for resection. Preoperative chemotherapy aims to increase the number of patients that may be eligible for liver resection by downsizing liver metastases. For patients with unresectable, chemotherapy refractory CLM the available treatment options are limited. Selective interarterial radiation therapy (SIRT is one of the most promising treatment options for this group of patients. Although only a small number of these patients have been reported as becoming candidates for potentially curative hepatic resection following sufficient reduction in the volume of liver metastases, the question arises regarding the safety of liver resection in these patients. We report a case of a patient who presented unresectable liver relapse of CLM after previous right hepatectomy. He underwent SIRT which resulted in downsizing of the liver metastases making the patient candidate for left lateral sectionectomy. He underwent the redo hepatectomy without any complications. To the best of our knowledge, this is the first reported case of redo hepatectomy after SIRT for CLM.

  5. Radiation prevulcanized natural rubber latex: Cytotoxicity and safety evaluation on animal

    Energy Technology Data Exchange (ETDEWEB)

    Keong, C C; Zin, W M Wan; Ibrahim, P; Ibrahim, S, E-mail: chai@nuclearmalaysia.gov.my [Malaysian Nuclear Agency, Bangi, 43000 Kajang, Selangor (Malaysia)

    2010-05-15

    Radiation prevulcanized natural rubber latex (RVNRL) was claimed to be more user friendly than natural rubber latex prevulcanized by sulphur curing system. The absence of Type IV allergy inducing chemicals in RVNRL make it a suitable material for manufacturing of many kinds of latex products, especially those come into direct contact with users. This paper reveals and discusses the findings of cytotoxicity test and safety evaluation on animal for RVNRL. The test was done on RVNRL films prepared by coagulant dipping method and RVNRL dipped products produced by latex dipped product manufacturers. Cytotocixity test was carried out on mammalian cell culture American Type Culture Collection CCL 81, Vero. Results indicated that no cytotoxic effect from RVNRL films and products was found on the cell culture. Two animal studies, namely dermal sensitization study and primary skin irritation study, were done on gloves made from RVNRL. Albino white guinea pigs were used as test subjects in dermal sensitization study and results showed no sensitization induced by the application of test material in the guinea pigs. Primary skin irritation study was done on New Zealand white rabbits and results showed that the product tested was not corrosive and was not a primary irritant

  6. Design concept of radiation control system for the high intensity proton accelerator facility

    CERN Document Server

    Miyamoto, Y; Harada, Y; Ikeno, K

    2002-01-01

    Description is given for the characteristic radiation environment for the High Intensity Proton Accelerator Facility and the design concept of the radiation control system of it. The facility is a large scale accelerator complex consisting of high energy proton accelerators carrying the highest beam intensity in the world and the related experimental facilities and therefore provides various issues relevant to the radiation environment. The present report describes the specifications for the radiation control system for the facility, determined in consideration of these characteristics.

  7. Ethical issues in engineering design safety and sustainability

    NARCIS (Netherlands)

    Van Gorp, A.C.

    2005-01-01

    The goal of this research is to obtain insight in how engineers deal with ethical issues in daily engineering design practice. It is reasonable to assume that ethical issues and the way engineers deal with them depend on characteristics of the design process. I have made use of Vincentis dimensions

  8. Solar radiation data sources, applications, and network design

    Energy Technology Data Exchange (ETDEWEB)

    None

    1978-04-01

    A prerequisite to considering solar energy projects is to determine the requirements for information about solar radiation to apply to possible projects. This report offers techniques to help the reader specify requirements in terms of solar radiation data and information currently available, describes the past and present programs to record and present information to be used for most requirements, presents courses of action to help the user meet his needs for information, lists sources of solar radiation data and presents the problems, costs, benefits and responsibilities of programs to acquire additional solar radiation data. Extensive background information is provided about solar radiation data and its use. Specialized information about recording, collecting, processing, storing and disseminating solar radiation data is given. Several Appendices are included which provide reference material for special situations.

  9. Safety Design Strategy for the Remote Handled Low-Level Waste Disposal Project

    Energy Technology Data Exchange (ETDEWEB)

    Boyd D. Chirstensen

    2015-03-01

    In accordance with the requirements of U.S. Department of Energy (DOE) Order 413.3A, “Program and Project Management for the Acquisition of Capital Assets,” safety must be integrated into the design process for new or major modifications to DOE Hazard Category 1, 2, and 3 nuclear facilities. The intended purpose of this requirement involves the handling of hazardous materials, both radiological and chemical, in a way that provides adequate protection to the public, workers, and the environment. Requirements provided in DOE Order 413.3A and DOE Order 420.1C, “Facility Safety,” and the expectations of DOE-STD-1189-2008, “Integration of Safety into the Design Process,” provide for identification of hazards early in the project and use of an integrated team approach to design safety into the facility. This safety design strategy provides the basic safety-in-design principles and concepts that will be used for the Remote-Handled Low-Level Waste Disposal Project.

  10. Occupational health and safety: Designing and building with MACBETH a value risk-matrix for evaluating health and safety risks

    Science.gov (United States)

    Lopes, D. F.; Oliveira, M. D.; Costa, C. A. Bana e.

    2015-05-01

    Risk matrices (RMs) are commonly used to evaluate health and safety risks. Nonetheless, they violate some theoretical principles that compromise their feasibility and use. This study describes how multiple criteria decision analysis methods have been used to improve the design and the deployment of RMs to evaluate health and safety risks at the Occupational Health and Safety Unit (OHSU) of the Regional Health Administration of Lisbon and Tagus Valley. ‘Value risk-matrices’ (VRMs) are built with the MACBETH approach in four modelling steps: a) structuring risk impacts, involving the construction of descriptors of impact that link risk events with health impacts and are informed by scientific evidence; b) generating a value measurement scale of risk impacts, by applying the MACBETH-Choquet procedure; c) building a system for eliciting subjective probabilities that makes use of a numerical probability scale that was constructed with MACBETH qualitative judgments on likelihood; d) and defining a classification colouring scheme for the VRM. A VRM built with OHSU members was implemented in a decision support system which will be used by OHSU members to evaluate health and safety risks and to identify risk mitigation actions.

  11. Designing Serious Games for Safety Education: "Learn to Brace" versus Traditional Pictorials for Aircraft Passengers.

    Science.gov (United States)

    Chittaro, Luca

    2016-05-01

    Serious games for safety education (SGSE) are a novel tool for preparing people to prevent and\\or handle risky situations. Although several SGSE have been developed, design and evaluation methods for SGSE need to be better grounded in and guided by safety-relevant psychological theories. In particular, this paper focuses on threat appeals and the assessment of variables, such as safety locus of control, that influence human behavior in real risky situations. It illustrates how we took into account such models in the design and evaluation of "Learn to Brace", a first-of-its-kind serious game that deals with a major problem in aviation safety, i.e. the scarce effectiveness of the safety cards used by airlines. The study considered a sample of 48 users: half of them received instructions about the brace position through the serious game, the other half through a traditional safety card pictorial. Results showed that the serious game was much more effective than the traditional instructions both in terms of learning and of changing safety-relevant perceptions, especially safety locus of control and recommendation perception.

  12. Assessment of Offshore Wind System Design, Safety, and Operation Standards

    Energy Technology Data Exchange (ETDEWEB)

    Sirnivas, S.; Musial, W.; Bailey, B.; Filippelli, M.

    2014-01-01

    This report is a deliverable for a project sponsored by the U.S. Department of Energy (DOE) entitled National Offshore Wind Energy Resource and Design Data Campaign -- Analysis and Collaboration (contract number DE-EE0005372; prime contractor -- AWS Truepower). The project objective is to supplement, facilitate, and enhance ongoing multiagency efforts to develop an integrated national offshore wind energy data network. The results of this initiative are intended to 1) produce a comprehensive definition of relevant met-ocean resource assets and needs and design standards, and 2) provide a basis for recommendations for meeting offshore wind energy industry data and design certification requirements.

  13. Impact of Passive Safety on FHR Instrumentation Systems Design and Classification

    Energy Technology Data Exchange (ETDEWEB)

    Holcomb, David Eugene [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

    2015-01-01

    Fluoride salt-cooled high-temperature reactors (FHRs) will rely more extensively on passive safety than earlier reactor classes. 10CFR50 Appendix A, General Design Criteria for Nuclear Power Plants, establishes minimum design requirements to provide reasonable assurance of adequate safety. 10CFR50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors, provides guidance on how the safety significance of systems, structures, and components (SSCs) should be reflected in their regulatory treatment. The Nuclear Energy Institute (NEI) has provided 10 CFR 50.69 SSC Categorization Guideline (NEI-00-04) that factors in probabilistic risk assessment (PRA) model insights, as well as deterministic insights, through an integrated decision-making panel. Employing the PRA to inform deterministic requirements enables an appropriately balanced, technically sound categorization to be established. No FHR currently has an adequate PRA or set of design basis accidents to enable establishing the safety classification of its SSCs. While all SSCs used to comply with the general design criteria (GDCs) will be safety related, the intent is to limit the instrumentation risk significance through effective design and reliance on inherent passive safety characteristics. For example, FHRs have no safety-significant temperature threshold phenomena, thus enabling the primary and reserve reactivity control systems required by GDC 26 to be passively, thermally triggered at temperatures well below those for which core or primary coolant boundary damage would occur. Moreover, the passive thermal triggering of the primary and reserve shutdown systems may relegate the control rod drive motors to the control system, substantially decreasing the amount of safety-significant wiring needed. Similarly, FHR decay heat removal systems are intended to be running continuously to minimize the amount of safety-significant instrumentation needed to initiate

  14. Operational design for safety of minimum operators; Shoninka no tameno opereshon anzen sekkei

    Energy Technology Data Exchange (ETDEWEB)

    Yamamuro, N. [Nippon Zeon Co., Ltd., Tokyo (Japan)

    2000-07-05

    One of the keywords of the chemical plant in the twenty-first century is the minimum operators. It requires the plant with the more advanced reliability it maintains the safe level along the convention in little personnel. Here, it limits the target to automation and computerization design, which are a key point of minimum operators plant design, and on the design strategy of new operation safety design, it introduces the outline. (NEDO)

  15. Design of a transition radiation detector for cosmic rays

    Science.gov (United States)

    Hartmann, G.; Mueller, D.; Prince, T.

    1975-01-01

    Transition radiation detectors consisting of sandwiches of plastic foam radiators and multiwire proportional chambers can be used to identify cosmic ray particles with energies gamma ? E/mc-squared is greater than 10 to the 3rd and to measure their energy in the region gamma is roughly equal to 10 to the 3rd

  16. Role of experience, leadership and individual protection in cath lab. A multicenter questionnaire and workshop on radiation safety

    Energy Technology Data Exchange (ETDEWEB)

    Kuon, E. [Klinik Fraenkische Schweiz, Ebermannstadt (Germany). Div. of Cardiology; Weitmann, K.; Hoffmann, W. [University Medicine, Greifswald (Germany). Inst. for Community Medicine; Doerr, M.; Hummel, A.; Busch, M.C.; Felix, S.B.; Empen, K. [University Medicine, Greifswald (Germany). Div. of Internal Medicine

    2015-10-15

    Radiation exposure in invasive cardiology remains considerable. We evaluated the acceptance of radiation protective devices and the role of operator experience, team leadership, and technical equipment in radiation safety efforts in the clinical routine. Cardiologists (115 from 27 centers) answered a questionnaire and documented radiation parameters for 10 coronary angiographies (CA), before and 3.1 months after a 90-min. mini-course in radiation-reducing techniques. Mini-course participants achieved significant median decreases in patient dose area products (DAP: from 26.6 to 13.0 Gy x cm{sup 2}), number of radiographic frames (- 29 %) and runs (- 18 %), radiographic DAP/frame (- 32 %), fluoroscopic DAP/s (- 39 %), and fluoroscopy time (- 16 %). Multilevel analysis revealed lower DAPs with decreasing body mass index (- 1.4 Gy x cm{sup 2} per kg/m2), age (- 1.2 Gy x cm{sup 2}/decade), female sex (- 5.9 Gy x cm{sup 2}), participation of the team leader (- 9.4 Gy x cm{sup 2}), the mini-course itself (- 16.1 Gy x cm{sup 2}), experience (- 0.7 Gy x cm{sup 2}/1000 CAs throughout the interventionalist's professional life), and use of older catheterization systems (- 6.6 Gy x cm{sup 2}). Lead protection included apron (100 %), glass sheet (95 %), lengthwise (94 %) and crosswise (69 %) undercouch sheet, collar (89 %), glasses (28 %), cover around the patients' thighs (19 %), foot switch shield (7 %), gloves (3 %), and cap (1 %). Radiation-protection devices are employed less than optimally in the clinical routine. Cardiologists with a great variety of interventional experience profited from our radiation safety workshop - to an even greater extent if the interventional team leader also participated.

  17. Predicting the effectiveness of road safety campaigns through alternative research designs.

    Science.gov (United States)

    Adamos, Giannis; Nathanail, Eftihia

    2016-12-01

    A large number of road safety communication campaigns have been designed and implemented in the recent years; however their explicit impact on driving behavior and road accident rates has been estimated in a rather low proportion. Based on the findings of the evaluation of three road safety communication campaigns addressing the issues of drinking and driving, seat belt usage, and driving fatigue, this paper applies different types of research designs (i.e., experimental, quasi-experimental, and non-experimental designs), when estimating the effectiveness of road safety campaigns, implements a cross-design assessment, and conducts a cross-campaign evaluation. An integrated evaluation plan was developed, taking into account the structure of evaluation questions, the definition of measurable variables, the separation of the target audience into intervention (exposed to the campaign) and control (not exposed to the campaign) groups, the selection of alternative research designs, and the appropriate data collection methods and techniques. Evaluating the implementation of different research designs in estimating the effectiveness of road safety campaigns, results showed that the separate pre-post samples design demonstrated better predictability than other designs, especially in data obtained from the intervention group after the realization of the campaign. The more constructs that were added to the independent variables, the higher the values of the predictability were. The construct that most affects behavior is intention, whereas the rest of the constructs have a lower impact on behavior. This is particularly significant in the Health Belief Model (HBM). On the other hand, behavioral beliefs, normative beliefs, and descriptive norms, are significant parameters for predicting intention according to the Theory of Planned Behavior (TPB). The theoretical and applied implications of alternative research designs and their applicability in the evaluation of road safety

  18. 1972 preliminary safety analysis report based on a conceptual design of a proposed repository in Kansas

    Energy Technology Data Exchange (ETDEWEB)

    Blomeke, J.O.

    1977-08-01

    This preliminary safety analysis report is based on a proposed Federal Repository at Lyons, Kansas, for receiving, handling, and depositing radioactive solid wastes in bedded salt during the remainder of this century. The safety analysis applies to a hypothetical site in central Kansas identical to the Lyons site, except that it is free of nearby salt solution-mining operations and bore holes that cannot be plugged to Repository specifications. This PSAR contains much information that also appears in the conceptual design report. Much of the geological-hydrological information was gathered in the Lyons area. This report is organized in 16 sections: considerations leading to the proposed Repository, design requirements and criteria, a description of the Lyons site and its environs, land improvements, support facilities, utilities, different impacts of Repository operations, safety analysis, design confirmation program, operational management, requirements for eventually decommissioning the facility, design criteria for protection from severe natural events, and the proposed program of experimental investigations. (DLC)

  19. Invited review: study design considerations for clinical research in veterinary radiology and radiation oncology.

    Science.gov (United States)

    Scrivani, Peter V; Erb, Hollis N

    2013-01-01

    High quality clinical research is essential for advancing knowledge in the areas of veterinary radiology and radiation oncology. Types of clinical research studies may include experimental studies, method-comparison studies, and patient-based studies. Experimental studies explore issues relative to pathophysiology, patient safety, and treatment efficacy. Method-comparison studies evaluate agreement between techniques or between observers. Patient-based studies investigate naturally acquired disease and focus on questions asked in clinical practice that relate to individuals or populations (e.g., risk, accuracy, or prognosis). Careful preplanning and study design are essential in order to achieve valid results. A key point to planning studies is ensuring that the design is tailored to the study objectives. Good design includes a comprehensive literature review, asking suitable questions, selecting the proper sample population, collecting the appropriate data, performing the correct statistical analyses, and drawing conclusions supported by the available evidence. Most study designs are classified by whether they are experimental or observational, longitudinal or cross-sectional, and prospective or retrospective. Additional features (e.g., controlled, randomized, or blinded) may be described that address bias. Two related challenging aspects of study design are defining an important research question and selecting an appropriate sample population. The sample population should represent the target population as much as possible. Furthermore, when comparing groups, it is important that the groups are as alike to each other as possible except for the variables of interest. Medical images are well suited for clinical research because imaging signs are categorical or numerical variables that might be predictors or outcomes of diseases or treatments. © 2013 Veterinary Radiology & Ultrasound.

  20. Rationalization of safety factors for breakwater design in hurricane-prone areas

    NARCIS (Netherlands)

    Tsimopoulou, V.; Kanning, W.; Verhagen, H.J.; Vrijling, J.K.

    2011-01-01

    This paper presents the development of a semi-probabilistic method for armour layer design of rubble mound breakwaters, which is based on the use of safety factors. The objective is to introduce an approach that is both attractive to designers and sufficiently reliable when a high degree of uncertai

  1. Rationalization of safety factors for breakwater design in hurricane-prone areas

    NARCIS (Netherlands)

    Tsimopoulou, V.; Kanning, W.; Verhagen, H.J.; Vrijling, J.K.

    2011-01-01

    This paper presents the development of a semi-probabilistic method for armour layer design of rubble mound breakwaters, which is based on the use of safety factors. The objective is to introduce an approach that is both attractive to designers and sufficiently reliable when a high degree of uncertai

  2. Design of a total-dose radiation hardened monolithic CMOS DC-DC boost converter

    Energy Technology Data Exchange (ETDEWEB)

    Liu Zhi; Yu Hongbo; Liu Youbao [Xi' an Institute of Microelectronics Technology, Xi' an 710054 (China); Ning Hongying, E-mail: liuzhi6048@126.com [Xi' an University of Technology, Xi' an 710048 (China)

    2011-07-15

    This paper presents the design and implementation of a monolithic CMOS DC-DC boost converter that is hardened for total dose radiation. In order to improve its radiation tolerant abilities, circuit-level and device-level RHBD (radiation-hardening by design) techniques were employed. Adaptive slope compensation was used to improve the inherent instability. The H-gate MOS transistors, annular gate MOS transistors and guard rings were applied to reduce the impact of total ionizing dose. A boost converter was fabricated by a standard commercial 0.35 {mu}m CMOS process. The hardened design converter can work properly in a wide range of total dose radiation environments, with increasing total dose radiation. The efficiency is not as strongly affected by the total dose radiation and so does the leakage performance. (semiconductor integrated circuits)

  3. Design and Modeling of a Variable Heat Rejection Radiator

    Science.gov (United States)

    Miller, Jennifer R.; Birur, Gajanana C.; Ganapathi, Gani B.; Sunada, Eric T.; Berisford, Daniel F.; Stephan, Ryan

    2011-01-01

    Variable Heat Rejection Radiator technology needed for future NASA human rated & robotic missions Primary objective is to enable a single loop architecture for human-rated missions (1) Radiators are typically sized for maximum heat load in the warmest continuous environment resulting in a large panel area (2) Large radiator area results in fluid being susceptible to freezing at low load in cold environment and typically results in a two-loop system (3) Dual loop architecture is approximately 18% heavier than single loop architecture (based on Orion thermal control system mass) (4) Single loop architecture requires adaptability to varying environments and heat loads

  4. Workflow Enhancement (WE) Improves Safety in Radiation Oncology: Putting the WE and Team Together

    Energy Technology Data Exchange (ETDEWEB)

    Chao, Samuel T., E-mail: chaos@ccf.org [Department of Radiation Oncology, Taussig Cancer Institute, Cleveland Clinic, Cleveland, Ohio (United States); Rose Ella Burkhardt Brain Tumor and Neuro-oncology Center, Cleveland Clinic, Cleveland, Ohio (United States); Meier, Tim; Hugebeck, Brian; Reddy, Chandana A.; Godley, Andrew; Kolar, Matt [Department of Radiation Oncology, Taussig Cancer Institute, Cleveland Clinic, Cleveland, Ohio (United States); Suh, John H. [Department of Radiation Oncology, Taussig Cancer Institute, Cleveland Clinic, Cleveland, Ohio (United States); Rose Ella Burkhardt Brain Tumor and Neuro-oncology Center, Cleveland Clinic, Cleveland, Ohio (United States)

    2014-07-15

    Purpose: To review the impact of a workflow enhancement (WE) team in reducing treatment errors that reach patients within radiation oncology. Methods and Materials: It was determined that flaws in our workflow and processes resulted in errors reaching the patient. The process improvement team (PIT) was developed in 2010 to reduce errors and was later modified in 2012 into the current WE team. Workflow issues and solutions were discussed in PIT and WE team meetings. Due to tensions within PIT that resulted in employee dissatisfaction, there was a 6-month hiatus between the end of PIT and initiation of the renamed/redesigned WE team. In addition to the PIT/WE team forms, the department had separate incident forms to document treatment errors reaching the patient. These incident forms are rapidly reviewed and monitored by our departmental and institutional quality and safety groups, reflecting how seriously these forms are treated. The number of these incident forms was compared before and after instituting the WE team. Results: When PIT was disbanded, a number of errors seemed to occur in succession, requiring reinstitution and redesign of this team, rebranded the WE team. Interestingly, the number of incident forms per patient visits did not change when comparing 6 months during the PIT, 6 months during the hiatus, and the first 6 months after instituting the WE team (P=.85). However, 6 to 12 months after instituting the WE team, the number of incident forms per patient visits decreased (P=.028). After the WE team, employee satisfaction and commitment to quality increased as demonstrated by Gallup surveys, suggesting a correlation to the WE team. Conclusions: A team focused on addressing workflow and improving processes can reduce the number of errors reaching the patient. Time is necessary before a reduction in errors reaching patients will be seen.

  5. Analysis of radiation environmental safety for China's Spallation Neutron Source (CSNS)

    Science.gov (United States)

    Wang, Qing-Bin; Wu, Qing-Biao; Ma, Zhong-Jian; Zhang, Qing-Jiang; Li, Nan; Wu, Jing-Min; Liu, Jian; Zhang, Gang

    2010-07-01

    The China Spallation Neutron Source (CSNS) is going to be located in Dalang Town, Dongguan City in the Guangdong Province. In this paper we report the results of the parameters related with environment safety based on experiential calculations and Monte Carlo simulations. The main project of the accelerator is an under ground construction. On top there is a 0.5 m concrete and 5.0 m soil covering for shielding, which can reduce the dose out of the tunnel's top down to 0.2 μSv/h. For the residents on the boundary of the CSNS, the dose produced by skyshine, which is caused by the penetrated radiation leaking from the top of the accelerator, is no more than 0.68 μSv/a. When CSNS is operating normally, the maximal annual effective dose due to the emission of gas from the tunnel is 2.40×10-3 mSv/a to the public adult, and 2.29×10-3 mSv/a to a child, both values are two orders of magnitude less than the limiting value for control and management. CSNS may give rise to an activation of the soil and groundwater in the nearest tunnels, where the main productions are 3H, 7Be, 22Na, 54Mn, etc. But the specific activity is less than the exempt specific activity in the national standard GB13376-92. So it is safe to say that the environmental impact caused by the activation of soil and groundwater is insignificant. To sum up, for CSNS, as a powerful neutron source device, driven by a high-energy high-current proton accelerator, a lot of potential factors affecting the environment exist. However, as long as effective shieldings for protection are adopted and strict rules are drafted, the environmental impact can be kept under control within the limits of the national standard.

  6. Contract-Based Design of Embedded Systems Integrating Nominal Behavior and Safety

    Directory of Open Access Journals (Sweden)

    Bernhard Kaiser

    2015-10-01

    Full Text Available The distributed design process for safety-critical embedded systems has become an increasingly difficult challenge: Electronic Control Units (ECUs in vehicles, for instance, participate in many vehicle functions, while each vehicle function, in turn, is spread across several ECUs. Many suppliers participate in systems design and many partial functions are reused from past projects, not always knowing the assumptions at the time of their development. In particular, efficient allocation of safety mechanisms and a sound safety case are difficult tasks for original equipment manufacturers (OEMs. Contract-based development has gained popularity as an approach for supporting distributed development by explicitly annotating assumptions and guarantees to components, but an integrated process covering specification of nominal behavior and safety has not been described so far. We present such an integrated development approach that encompasses the systematic breakdown of nominal system behavior using contracts, the consistent derivation of safety analysis by interpreting several types of contract violations as a specification for failure modes, and the subsequent integration of safety mechanisms that cover these failure modes through safety contracts. The approach equally fits hardware and software and is therefore applicable on the system level. We demonstrate it by an electric drive example. The extensibility of our approach towards Cyber Physical Systems, which compose themselves at runtime, is briefly outlined at the end of the article.

  7. Innovation in patient safety: a new task design in reducing patient falls.

    Science.gov (United States)

    Tzeng, Huey-Ming; Yin, Chang-Yi

    2008-01-01

    This novel study used a human factor engineering approach to improve patient safety and prevent patient falls. We compared the safety levels of 2 task designs to help patients get out of hospital beds: the traditional sitting-standing position and the prone position. It is assumed that when patients' conditions are comparable, using the prone position is safer. When the prone position is used, if patients lose their balance, they will fall back to the surface of beds.

  8. The creation of IRSN Institute of radiation protection and nuclear safety; La creation de l'IRSN Institut de Radioprotection et de Surete Nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-03-01

    The creation of the Institute of Radiation Protection and Nuclear Safety (I.R.S.N.) answers to the government will to modify the organisation of safety and radiation protection, in order to separate the functions of expert, monitor and operator. The I.R.S.N. has for missions to realize expertise by giving to the government advice on nuclear risks; to conduct researches in order to improve the knowledge; to work towards radiation monitoring of environment and workers as well as exposure sources to radiations. (N.C.)

  9. Design of safety mechanism for an industrial manipulator based on passive compliance

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Hwi Su; Park, Jung Jun; Song, Jae Bok [Korea University, Seoul (Korea, Republic of); Kyung, Jin Ho [Korea Institute of Machinery and Materials, Daejeon (Korea, Republic of)

    2010-11-15

    In recent years, collision safety between humans and robots has drawn much attention since human-robot cooperation is increasingly needed in various fields. Since positioning accuracy and collision safety are both important, an industrial manipulator should maintain very high stiffness for positioning accuracy in a normal situation, but exhibit very low stiffness when subjected to a collision force greater than the tolerance for human injury. To satisfy these requirements, we proposed in our previous research a safety mechanism composed of a linear spring and a double-slider mechanism for a service robot with a small payload. We modified this device to meet more stringent requirements for an industrial manipulator which usually has a payload higher than a service robot. Several experiments on static and dynamic collisions showed high stiffness of the safety mechanism in response to an external torque that was less than a predetermined threshold torque, but low stiffness that enabled absorption of the collision force when the external torque exceeded the threshold. Thus, positioning accuracy and collision safety were improved using the proposed design. Furthermore, a new safety criterion is suggested to verify the collision safety of a manipulator that uses the proposed safety mechanism

  10. Resolution of thermal-hydraulic safety and licensing issues for the system 80+{sup {trademark}} design

    Energy Technology Data Exchange (ETDEWEB)

    Carpentino, S.E.; Ritterbusch, S.E.; Schneider, R.E. [ABB-Combustion Engineering, Windsor, CT (United States)] [and others

    1995-09-01

    The System 80+{sup {trademark}} Standard Design is an evolutionary Advanced Light Water Reactor (ALWR) with a generating capacity of 3931 MWt (1350 MWe). The Final Design Approval (FDA) for this design was issued by the Nuclear Regulatory Commission (NRC) in July 1994. The design certification by the NRC is anticipated by the end of 1995 or early 1996. NRC review of the System 80+ design has involved several new safety issues never before addressed in a regulatory atmosphere. In addition, conformance with the Electric Power Research Institute (EPRI) ALWR Utility Requirements Document (URD) required that the System 80+ plant address nuclear industry concerns with regard to design, construction, operation and maintenance of nuclear power plants. A large number of these issues/concerns deals with previously unresolved generic thermal-hydraulic safety issues and severe accident prevention and mitigation. This paper discusses the thermal-hydraulic analyses and evaluations performed for the System 80+ design to resolve safety and licensing issues relevant to both the Nuclear Stream Supply System (NSSS) and containment designs. For the NSSS design, the Safety Depressurization System mitigation capability and resolution of the boron dilution concern are described. Examples of containment design issues dealing with containment shell strength, robustness of the reactor cavity walls and hydrogen mixing under severe accident conditions are also provided. Finally, the overall approach used in the application of NRC`s new (NUREG-1465) radiological source term for System 80+ evaluation is described. The robustness of the System 80+ containment design to withstand severe accident consequences was demonstrated through detailed thermal-hydraulic analyses and evaluations. This advanced design to shown to meet NRC severe accident policy goals and ALWR URD requirements without any special design features and unnecessary costs.

  11. Safety regulation for the design approval of special form radioactive sources

    Energy Technology Data Exchange (ETDEWEB)

    Cho, Woon-Kap [Korea Institute of Nuclear Safety (KINS), Guseong-dong 19, Yuseong, Daejeon 305-338 (Korea, Republic of)], E-mail: wkcho@kins.re.kr

    2009-07-15

    Several kinds of special form radioactive sources for industrial, medical applications are being produced in Korea. Special form radioactive sources should meet strict safety requirements specified in the domestic safety regulations and the design of the sources should be certified by the regulatory authority, the Ministry of Education, Science and Technology (MEST). Several safety tests such as impact, percussion, heating, and leak tests are performed on the sources according to the domestic regulations and the international safety standards such as ANSI N542-1977 and ISO 2919-1999(E). As a regulatory expert body, Korea Institute of Nuclear Safety (KINS) assesses various types of application documents, such as safety analysis report, quality assurance program, and other documents evidencing fulfillment of requirements for design approval of the special form radioactive sources, submitted by a legal person who intends to produce special form radioactive sources and then reports the assessment result to MEST. A design approval certificate is issued to the applicant by MEST on the basis of a technical evaluation report presented by KINS.

  12. Statistical issues in the design, conduct and analysis of two large safety studies.

    Science.gov (United States)

    Gaffney, Michael

    2016-10-01

    The emergence, post approval, of serious medical events, which may be associated with the use of a particular drug or class of drugs, is an important public health and regulatory issue. The best method to address this issue is through a large, rigorously designed safety study. Therefore, it is important to elucidate the statistical issues involved in these large safety studies. Two such studies are PRECISION and EAGLES. PRECISION is the primary focus of this article. PRECISION is a non-inferiority design with a clinically relevant non-inferiority margin. Statistical issues in the design, conduct and analysis of PRECISION are discussed. Quantitative and clinical aspects of the selection of the composite primary endpoint, the determination and role of the non-inferiority margin in a large safety study and the intent-to-treat and modified intent-to-treat analyses in a non-inferiority safety study are shown. Protocol changes that were necessary during the conduct of PRECISION are discussed from a statistical perspective. Issues regarding the complex analysis and interpretation of the results of PRECISION are outlined. EAGLES is presented as a large, rigorously designed safety study when a non-inferiority margin was not able to be determined by a strong clinical/scientific method. In general, when a non-inferiority margin is not able to be determined, the width of the 95% confidence interval is a way to size the study and to assess the cost-benefit of relative trial size. A non-inferiority margin, when able to be determined by a strong scientific method, should be included in a large safety study. Although these studies could not be called "pragmatic," they are examples of best real-world designs to address safety and regulatory concerns. © The Author(s) 2016.

  13. Human Factors engineering criteria and design for the Hanford Waste Vitrification Plant preliminary safety analysis report

    Energy Technology Data Exchange (ETDEWEB)

    Wise, J.A.; Schur, A.; Stitzel, J.C.L.

    1993-09-01

    This report provides a rationale and systematic methodology for bringing Human Factors into the safety design and operations of the Hanford Waste Vitrification Plant (HWVP). Human Factors focuses on how people perform work with tools and machine systems in designed settings. When the design of machine systems and settings take into account the capabilities and limitations of the individuals who use them, human performance can be enhanced while protecting against susceptibility to human error. The inclusion of Human Factors in the safety design of the HWVP is an essential ingredient to safe operation of the facility. The HWVP is a new construction, nonreactor nuclear facility designed to process radioactive wastes held in underground storage tanks into glass logs for permanent disposal. Its design and mission offer new opposites for implementing Human Factors while requiring some means for ensuring that the Human Factors assessments are sound, comprehensive, and appropriately directed.

  14. The reactor accident in Fukushima Daiichi. The consequence of design deficiencies and inadequate safety engineering; Der Reaktorunfall in Fukushima Daiichi. Folge fehlerhafter Auslegung und unzureichender Sicherheitstechnik

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2015-03-15

    The reactor accident in Fukushima Daiichi is discussed in the frame of design deficiencies and inadequate safety engineering. The progress of the accident as consequence of the earthquake and the tsunami is described. The radiological situation for the public is supposed to be blow the dose limit of 20 mSv/year. The WHO and UNSCEAR (United Nations Scientific Committee on the Effects of Atomic radiation) did not observe acute radiation injuries. The Japanese authorities have classified the accident to 7 of the INES scale. The German Atomforum e.V. considers the safety engineering of German NPPs to be superior to the Japanese situation due to higher emergency energy supply, extensive measures to reduce the hydrogen accumulation and mitigating measures for the accident management. German NPPS are considered highly robust as the EU stress tests have shown.

  15. Lessons learned from Fukushima Daiichi nuclear power plant accident: efficient education items of radiation safety for general public.

    Science.gov (United States)

    Ohno, K; Endo, K

    2015-07-01

    The Fukushima Daiichi nuclear power plant (FNP-1) accident, while as tragic as the tsunami, was a man-made disaster created by the ignorance of the effects of radiation and radioactive materials. Therefore, it is important that all specialists in radiation protection in medicine sympathize with the anxiety of the general public regarding the harmful effects of radiation and advise people accordingly. All questions and answers were collected related to inquiries from the general public that were posted to reliable websites, including those of the government and radiation-related organizations, from March 2011 to November 2012. The questions were summarized and classified by similarity of content. (1) The total number of questions is 372. The content was broadly classified into three categories: inquiries for radiation-related knowledge and about health effects and foods. The questions asked to obtain radiation-related knowledge were the most common, accounting for 38 %. Thirty-six percentage of the questions were related to health effects, and 26 % involved foods, whereas 18 % of the questions were related to children and pregnancy. (2) The change over time was investigated in 290 questions for which the time of inquiry was known. Directly after the earthquake, the questions were primarily from people seeking radiation-related knowledge. Later, questions related to health effects increased. The anxiety experienced by residents following the nuclear accident was caused primarily by insufficient knowledge related to radiation, concerns about health effects and uncertainties about food and water safety. The development of educational materials focusing on such content will be important for risk communication with the general public in countries with nuclear power plants. Physicians and medical physicist should possess the ability to respond to questions such as these and should continue with medical examinations and treatments in a safe and appropriate manner.

  16. The European space suit, a design for productivity and crew safety

    Science.gov (United States)

    Skoog, A. Ingemar; Berthier, S.; Ollivier, Y.

    In order to fulfil the two major mission objectives, i.e. support planned and unplanned external servicing of the COLUMBUS FFL and support the HERMES vehicle for safety critical operations and emergencies, the European Space Suit System baseline configuration incorporates a number of design features, which shall enhance the productivity and the crew safety of EVA astronauts. The work in EVA is today - and will be for several years - a manual work. Consequently, to improve productivity, the first challenge is to design a suit enclosure which minimizes movement restrictions and crew fatigue. It is covered by the "ergonomic" aspect of the suit design. Furthermore, it is also necessary to help the EVA crewmember in his work, by giving him the right information at the right time. Many solutions exist in this field of Man-Machine Interface, from a very simple system, based on cuff check lists, up to advanced systems, including Head-Up Displays. The design concept for improved productivity encompasses following features: • easy donning/doffing thru rear entry, • suit ergonomy optimisation, • display of operational information in alpha-numerical and graphical from, and • voice processing for operations and safety critical information. Concerning crew safety the major design features are: • a lower R-factor for emergency EVA operations thru incressed suit pressure, • zero prebreath conditions for normal operations, • visual and voice processing of all safety critical functions, and • an autonomous life support system to permit unrestricted operations around HERMES and the CFFL. The paper analyses crew safety and productivity criteria and describes how these features are being built into the design of the European Space Suit System.

  17. Radiation hardness by design for mixed signal infrared readout circuit applications

    Science.gov (United States)

    Gaalema, Stephen; Gates, James; Dobyns, David; Pauls, Greg; Wall, Bruce

    2013-09-01

    Readout integrated circuits (ROICs) to support space-based infrared detection applications often have severe radiation tolerance requirements. Radiation hardness-by-design (RHBD) significantly enhances the radiation tolerance of commercially available CMOS and custom radiation hardened fabrication techniques are not required. The combination of application specific design techniques, enclosed gate architecture nFETs and intrinsic thin oxide radiation hardness of 180 nm process node commercial CMOS allows realization of high performance mixed signal circuits. Black Forest Engineering has used RHBD techniques to develop ROICs with integrated A/D conversion that operate over a wide range of temperatures (40K-300K) to support infrared detection. ROIC radiation tolerance capability for 256x256 LWIR area arrays and 1x128 thermopile linear arrays is presented. The use of 130 nm CMOS for future ROIC RHBD applications is discussed.

  18. Design and implementation of automatic shading device for diffuse radiation measurement

    Institute of Scientific and Technical Information of China (English)

    LYU; Wenhua; BIAN; Zeqiang; CHONG; Wei

    2015-01-01

    Considering the problem of too large area the shading disc covered,complex shadow band coefficients and too big diffuse radiation measurement bias,an automatic shading device for diffuse radiometer is designed and realized. Set a shading ball on the automatic sun tracker,drive linkage parallelogram structure with the declination axis arm,the shading ball can rotate synchronously with the motion of the sun and shade beam radiation measured with pyranometer,thus shading beam radiation and measuring diffuse radiation can be realized automatically. The comparison test results show that the automatic shading device can realize diffuse radiation measurement automatically,the accuracy of diffuse radiation readings can get a 18. 7% improvement compared with traditional measure system,greatly improves the reliability and accuracy of the diffuse radiation measurement.

  19. Design and calibration of a novel transient radiative heat flux meter for a spacecraft thermal test

    Science.gov (United States)

    Sheng, Chunchen; Hu, Peng; Cheng, Xiaofang

    2016-06-01

    Radiative heat flux measurement is significantly important for a spacecraft thermal test. To satisfy the requirements of both high accuracy and fast response, a novel transient radiative heat flux meter was developed. Its thermal receiver consists of a central thermal receiver and two thermal guarded annular plates, which ensure the temperature distribution of the central thermal receiver to be uniform enough for reasonably applying lumped heat capacity method in a transient radiative heat flux measurement. This novel transient radiative heat flux meter design can also take accurate measurements regardless of spacecraft surface temperature and incident radiation spectrum. The measurement principle was elaborated and the coefficients were calibrated. Experimental results from testing a blackbody furnace and an Xenon lamp show that this novel transient radiative heat flux meter can be used to measure transient radiative heat flux up to 1400 W/m2 with high accuracy and the response time of less than 10 s.

  20. Safety effectiveness of pavement design treatment at intersections: Left turning vehicles and pedestrians on crosswalks

    Directory of Open Access Journals (Sweden)

    Hasina Iasmin

    2016-07-01

    Full Text Available Pedestrians are the most vulnerable road users as they are more exposed than other road users. Pedestrian safety at road intersections still remains the most vital and yet unsolved issue. One of the critical points in pedestrian safety is the occurrence of accidents between left-turning vehicle and pedestrians on crosswalks at signalized intersections. A crosswalk is a place designated for pedestrians and cyclists to cross vehicular roads safely. Drivers are expected to give priority to pedestrians or cyclists during interactions between them on the crosswalk. If a driver exhibits non-yielding behavior, the interaction will turn into a collision. This study examined the safety effect of three crosswalks designed with different materials such as red-colored material or brick pavement based on a safety performance study. The safety performance study considered left-turning driver's gap acceptance behavior and the severity of traffic conflict events between left-turning vehicles and pedestrians. The results of the study indicates that using brick pavement on a crosswalk increases the safety level of the crosswalk. Drivers at such crosswalks are more acquiescent to the priority rule.

  1. Design of CMOS logic gates for TID radiation

    Science.gov (United States)

    Attia, John Okyere; Sasabo, Maria L.

    1993-01-01

    The rise time, fall time and propagation delay of the logic gates were derived. The effects of total ionizing dose (TID) radiation on the fall and rise times of CMOS logic gates were obtained using C program calculations and PSPICE simulations. The variations of mobility and threshold voltage on MOSFET transistors when subjected to TID radiation were used to determine the dependence of switching times on TID. The results of this work indicate that by increasing the size of P-channel transistor with respect to the N-channel transistors of the CMOS gates, the propagation delay of CMOS logic gate can be made to decrease with, or be independent of an increase in TID radiation.

  2. Safety analysis and lay-out aspects of shieldings against particle radiation at the example of spallation facilities in the megawatt range; Sicherheitstechnische Analyse und Auslegungsaspekte von Abschirmungen gegen Teilchenstrahlung am Beispiel von Spallationsanlagen im Megawatt Bereich

    Energy Technology Data Exchange (ETDEWEB)

    Hanslik, R.

    2006-08-15

    This paper discusses the shielding of particle radiation from high current accelerators, spallation neutron sources and so called ADS-facilities (Accelerator Driven Systems). ADS-facilities are expected to gain importance in the future for transmutation of long-lived isotopes from fission reactors as well as for energy production. In this paper physical properties of the radiation as well as safety relevant requirements and corresponding shielding concepts are discussed. New concepts for the layout and design of such shielding are presented. Focal point of this work will be the fundamental difference between conventional fission reactor shielding and the safety relevant issues of shielding from high-energy radiation. Key point of this paper is the safety assessment of shielding issues of high current accelerators, spallation targets and ADS-blanket systems as well as neutron scattering instruments at spallation neutron sources. Safety relevant shielding requirements are presented and discussed. For the layout and design of the shielding for spallation sources computer base calculations methods are used. A discussion and comparison of the most important methods like semi-empirical, deterministic and stochastic codes are presented. Another key point within the presented paper is the discussion of shielding materials and their shielding efficiency concerning different types of radiation. The use of recycling material, as a cost efficient solution, is discussed. Based on the conducted analysis, flowcharts for a systematic layout and design of adequate shielding for targets and accelerators have been developed and are discussed in this paper. By use of these flowcharts layout and engineering design of future ADS-facilities can be performed. (orig.)

  3. Safety analysis and lay-out aspects of shieldings against particle radiation at the example of spallation facilities in the megawatt range; Sicherheitstechnische Analyse und Auslegungsaspekte von Abschirmungen gegen Teilchenstrahlung am Beispiel von Spallationsanlagen im Megawatt Bereich

    Energy Technology Data Exchange (ETDEWEB)

    Hanslik, R.

    2006-08-15

    This paper discusses the shielding of particle radiation from high current accelerators, spallation neutron sources and so called ADS-facilities (Accelerator Driven Systems). ADS-facilities are expected to gain importance in the future for transmutation of long-lived isotopes from fission reactors as well as for energy production. In this paper physical properties of the radiation as well as safety relevant requirements and corresponding shielding concepts are discussed. New concepts for the layout and design of such shielding are presented. Focal point of this work will be the fundamental difference between conventional fission reactor shielding and the safety relevant issues of shielding from high-energy radiation. Key point of this paper is the safety assessment of shielding issues of high current accelerators, spallation targets and ADS-blanket systems as well as neutron scattering instruments at spallation neutron sources. Safety relevant shielding requirements are presented and discussed. For the layout and design of the shielding for spallation sources computer base calculations methods are used. A discussion and comparison of the most important methods like semi-empirical, deterministic and stochastic codes are presented. Another key point within the presented paper is the discussion of shielding materials and their shielding efficiency concerning different types of radiation. The use of recycling material, as a cost efficient solution, is discussed. Based on the conducted analysis, flowcharts for a systematic layout and design of adequate shielding for targets and accelerators have been developed and are discussed in this paper. By use of these flowcharts layout and engineering design of future ADS-facilities can be performed. (orig.)

  4. Overview of traffic safety aspects and design in road tunnels

    Directory of Open Access Journals (Sweden)

    Shy Bassan

    2016-07-01

    Drivers in road tunnels generally reduce their speed and increase their lateral position from the right tunnel wall while driving. In shorter tunnels, with reduced driving speed, driver vigilance may be more robust without being hindered by dull driving, which is more common in longer tunnels. Still, in spite of driver alertness, crash rates in tunnels occur due to the tunnel's unusual driving environment. Crash rates are lower in the tunnel inner zone due to driver alertness, especially after passing the transition zone and acclimating to the tunnel environment. The number of crashes, however, is higher along zone 4 (tunnel inner zone, which is the principal zone, as it covers longer driving distance. According to most studies, short tunnels were found to exhibit higher crash rates than long tunnels because the entrance zones incorporate higher crash rates, compared with the midzones; nonetheless, longer unidirectional (freeway and multilane tunnels with higher design speed, entail lower driver alertness and diminished concentration due to relatively monotonous driving in spite of a tunnel's closed environment.

  5. SKIRT: the design of a suite of input models for Monte Carlo radiative transfer simulations

    CERN Document Server

    Baes, Maarten

    2015-01-01

    The Monte Carlo method is the most popular technique to perform radiative transfer simulations in a general 3D geometry. The algorithms behind and acceleration techniques for Monte Carlo radiative transfer are discussed extensively in the literature, and many different Monte Carlo codes are publicly available. On the contrary, the design of a suite of components that can be used for the distribution of sources and sinks in radiative transfer codes has received very little attention. The availability of such models, with different degrees of complexity, has many benefits. For example, they can serve as toy models to test new physical ingredients, or as parameterised models for inverse radiative transfer fitting. For 3D Monte Carlo codes, this requires algorithms to efficiently generate random positions from 3D density distributions. We describe the design of a flexible suite of components for the Monte Carlo radiative transfer code SKIRT. The design is based on a combination of basic building blocks (which can...

  6. Antisideslip and Antirollover Safety Speed Controller Design for Vehicle on Curved Road

    Directory of Open Access Journals (Sweden)

    Guo Lie

    2014-01-01

    Full Text Available When the drivers cannot be aware of the existing of forthcoming curved roads and fail to regulate their safety speeds accordingly, sideslip or rollover may occur with high probability. The antisideslip and antirollover control of vehicle on curved road in automatic highway systems is studied. The safety speed warning system is set before entering the curved road firstly. The speed adhesion control is adopted to shorten the braking distance while decelerating and to guarantee the safety speed. The velocity controller when decelerating on the straight path and the posture controller when driving on curved road are designed, respectively, utilizing integral backstepping technology. Simulation results demonstrate that this control system is characterized by quick and precise tracking and global stability. Consequently, it is able to avoid the dangerous operating conditions, such as sideslip and rollover, and guarantee the safety and directional stability when driving on curved road.

  7. Emergency relief system design: The DIERS users group safety relief valve example problem

    Energy Technology Data Exchange (ETDEWEB)

    Fisher, H.G. [Union Carbide Corp., South Charleston, WV (United States)

    1995-12-31

    Emergency relief system design involving two-phase flow is an evolving and complex technology. Aspects of alternative design techniques have been published. Well-documented, comprehensive design methods for safety relief valves, rupture disks and breather vents, however, are not readily available and example problems supported by data do not exist. Design Institute for Emergency Relief Systems (DIERS) Users Group members recently completed an example rating problem consisting of a safety relief valve mounted in a typical industrial configuration. Participants were asked to compute the flow through the device and to calculate the inlet pipe irreversible pressure loss and discharge pipe back pressure. Case studies involving various flows and physical conditions were formulated. A {open_quotes}Modified Delphi{close_quotes} technique was used to encourage participants to work until the {open_quotes}consensus{close_quotes} result was achieved. The exercise served to educate participants in the complexities and subtleties of emergency relief system design involving safety relief installations as compared to ideal nozzle calculations. All learned from the various calculation techniques used by others to solve the problem. Participants corrected parts of their computer codes and/or added procedures to address aspects of the problem. The present example problem is not supported by data. Available safety relief valve two-phase flow data suggest complexity not presently included in problem solutions. Future modification of the results may be required as additional considerations are incorporated into existing analytical methods and computer codes. 20 refs., 21 tabs.

  8. Multi-dimensional database design and implementation of dam safety monitoring system

    Directory of Open Access Journals (Sweden)

    Er-feng ZHAO

    2008-09-01

    Full Text Available To improve the effectiveness of dam safety monitoring database systems, the development process of a multi-dimensional conceptual data model was analyzed and a logic design was achieved in multi-dimensional database mode. The optimal data model was confirmed by identifying data objects, defining relations and reviewing entities. The conversion of relations among entities to external keys and entities and physical attributes to tables and fields was interpreted completely. On this basis, a multi-dimensional database that reflects the management and analysis of a dam safety monitoring system on monitoring data information has been established, for which factual tables and dimensional tables have been designed. Finally, based on service design and user interface design, the dam safety monitoring system has been developed with Delphi as the development tool. This development project shows that the multi-dimensional database can simplify the development process and minimize hidden dangers in the database structure design. It is superior to other dam safety monitoring system development models and can provide a new research direction for system developers.

  9. Multi-dimensional database design and implementation of dam safety monitoring system

    Institute of Scientific and Technical Information of China (English)

    Zhao Erfeng; Wang Yachao; Jiang Yufeng; Zhang Lei; Yu Hong

    2008-01-01

    To improve the effectiveness of dam safety monitoring database systems, the development process of a multi-dimensional conceptual data model was analyzed and a logic design was achieved in multi-dimensional database mode. The optimal data model was confirmed by identifying data objects, defining relations and reviewing entities. The conversion of relations among entities to external keys and entities and physical attributes to tables and fields was interpreted completely. On this basis, a multi-dimensional database that reflects the management and analysis of a dam safety monitoring system on monitoring data information has been established, for which factual tables and dimensional tables have been designed. Finally, based on service design and user interface design, the dam safety monitoring system has been developed with Delphi as the development tool. This development project shows that the multi-dimensional database can simplify the development process and minimize hidden dangers in the database structure design. It is superior to other dam safety monitoring system development models and can provide a new research direction for system developers.

  10. Radiation Tolerant Design with 0.18-micron CMOS Technology

    CERN Document Server

    Chen, Li; Durdle , Nelson G.

    This thesis discusse s th e issues r elated to the us e of enclosed-gate layou t trans isto rs and guard rings in a 0.18 μ m CMOS technology in order to im prove the radiation tolerance of ASICs. The thin gate oxides of subm icron technologies ar e inherently m ore radiation tole rant tha n the thick er oxides present in less advanced technologies. Using a commercial deep subm icron technology to bu ild up radiation-ha rdened circuits introduces several advantages com pared to a dedicated radiation-ha rd technology, such as speed, power, area, stability, and expense. Som e novel aspects related to the use of encl osed-gate layout transist ors are presented in this th esis. A m odel to calculate the aspect ratio is introduced and verified. Some im portant electrica l par ameters of the tran sistors such as threshold voltage, leakage current, subthreshold slope, and transconducta nce are studied before and afte...

  11. Effects of auditing patient safety in hospital care: design of a mixed-method evaluation.

    Science.gov (United States)

    Hanskamp-Sebregts, Mirelle; Zegers, Marieke; Boeijen, Wilma; Westert, Gert P; van Gurp, Petra J; Wollersheim, Hub

    2013-06-22

    Auditing of patient safety aims at early detection of risks of adverse events and is intended to encourage the continuous improvement of patient safety. The auditing should be an independent, objective assurance and consulting system. Auditing helps an organisation accomplish its objectives by bringing a systematic, disciplined approach to evaluating and improving the effectiveness of risk management, control, and governance. Audits are broadly conducted in hospitals, but little is known about their effects on the behaviour of healthcare professionals and patient safety outcomes. This study was initiated to evaluate the effects of patient safety auditing in hospital care and to explore the processes and mechanisms underlying these effects. Our study aims to evaluate an audit system to monitor and improve patient safety in a hospital setting. We are using a mixed-method evaluation with a before-and-after study design in eight departments of one university hospital in the period October 2011-July 2014. We measure several outcomes 3 months before the audit and 15 months after the audit. The primary outcomes are adverse events and complications. The secondary outcomes are experiences of patients, the standardised mortality ratio, prolonged hospital stay, patient safety culture, and team climate. We use medical record reviews, questionnaires, hospital administrative data, and observations to assess the outcomes. A process evaluation will be used to find out which components of internal auditing determine the effects. We report a study protocol of an effect and process evaluation to determine whether auditing improves patient safety in hospital care. Because auditing is a complex intervention targeted on several levels, we are using a combination of methods to collect qualitative and quantitative data about patient safety at the patient, professional, and department levels. This study is relevant for hospitals that want to early detect unsafe care and improve patient

  12. Design of Hack-Resistant Diabetes Devices and Disclosure of Their Cyber Safety.

    Science.gov (United States)

    Sackner-Bernstein, Jonathan

    2017-03-01

    The focus of the medical device industry and regulatory bodies on cyber security parallels that in other industries, primarily on risk assessment and user education as well as the recognition and response to infiltration. However, transparency of the safety of marketed devices is lacking and developers are not embracing optimal design practices with new devices. Achieving cyber safe diabetes devices: To improve understanding of cyber safety by clinicians and patients, and inform decision making on use practices of medical devices requires disclosure by device manufacturers of the results of their cyber security testing. Furthermore, developers should immediately shift their design processes to deliver better cyber safety, exemplified by use of state of the art encryption, secure operating systems, and memory protections from malware.

  13. Safety analysis for key design features of KALIMER with breakeven core

    Energy Technology Data Exchange (ETDEWEB)

    Hahn, Do Hee; Kwon, Y. M.; Chang, W. P.; Suk, S. D.; Lee, Y. B.; Jeong, K. S

    2002-04-01

    KAERI is currently developing the conceptual design of a liquid metal reactor, KALIMER (Korea Advanced Liquid MEtal Reactor) under the Long-term nuclear R and D Program. In this report, key safety design features are described and safety analyses results for typical ATWS accidents in the KALIMER design with breakeven core are presented. First, the basic approach to achieve the safety goal is introduced in chapter 1, and the event categorization and acceptance criteria for the KALIMER safety analysis are described in chapter 2. In chapter 3, results of inherent safety evaluations for the KALIMER conceptual design are presented. Safety analyses for the postulated anticipated transient without scram (ATWS) have been performed using the SSC-K code to investigate the KALIMER system response to the events. They are categorized as Bounding Events (BEs) because of their low probability of occurrence. In chapter 4, the performance analysis results of the KALIMER containment dome are described along with the HCDA accident scenario and source terms. The major containment parameters of peak pressure and peak temperature have been calculated using the CONTAIN-LMR code. Radiological consequence has been evaluated by the MACCS code. Finally, a simple methodology is introduced to investigate the core energetics behavior during HCDA in chapter 5. Sensitivity analyses have been performed for the KALIMER core behavior during super-prompt critical excursions, using SCHAMBETA code developed in the framework of the modified bethe-tait method. Work energy potentials based arising from the sodium expansion as well as the isentropic fuel expansion are then calculated to evaluate the structural integrity of the reactor vessel, reactor internals and primary coolant system of KALIMER.

  14. Radiation Belt Modeling for Spacecraft Design: Model Comparisons for Common Orbits

    Science.gov (United States)

    Lauenstein, J.-M.; Barth, J. L.

    2005-01-01

    We present the current status of radiation belt modeling, providing model details and comparisons with AP-8 and AE-8 for commonly used orbits. Improved modeling of the particle environment enables smarter space system design.

  15. A comparison between prescriptive- and performance-based approaches in fire safety design of structures

    DEFF Research Database (Denmark)

    Budny, Iwona; Giuliani, Luisa

    2010-01-01

    approach of performance-based fire design (PBFD) becomes therefore more and more popular. A higher design flexibility based on performance objectives constitutes a beneficial and competitive concept within the structural fire safety engineering, ensuring a higher safety level of a design choice. The aim...... of this paper is to present the diversity in fundamentals, procedures and solutions of the two foregoing approaches. The aim is primarily accomplished through the detailed case-study analysis of an open car-park in compliance with the European and Scandinavian prescriptive regulations. Furthermore, the advanced...... methodology of the performance-based fire design approach is considered, with the avail of computer-aided simulations of the main frame of the car-park. Nonlinear analyses, with respect to thermally induced effects and emphasis laid to the collapse modality, are carried out on a frame of the considered...

  16. Design optimization of radiation shielding structure for lead slowing-down spectrometer system

    Directory of Open Access Journals (Sweden)

    Jeong Dong Kim

    2015-04-01

    Full Text Available A lead slowing-down spectrometer (LSDS system is a promising nondestructive assay technique that enables a quantitative measurement of the isotopic contents of major fissile isotopes in spent nuclear fuel and its pyroprocessing counterparts, such as 235U, 239Pu, 241Pu, and, potentially, minor actinides. The LSDS system currently under development at the Korea Atomic Energy Research Institute (Daejeon, Korea is planned to utilize a high-flux (>1012 n/cm2·s neutron source comprised of a high-energy (30 MeV/high-current (∼2 A electron beam and a heavy metal target, which results in a very intense and complex radiation field for the facility, thus demanding structural shielding to guarantee the safety. Optimization of the structural shielding design was conducted using MCNPX for neutron dose rate evaluation of several representative hypothetical designs. In order to satisfy the construction cost and neutron attenuation capability of the facility, while simultaneously achieving the aimed dose rate limit (<0.06 μSv/h, a few shielding materials [high-density polyethylene (HDPE–Borax, B4C, and Li2CO3] were considered for the main neutron absorber layer, which is encapsulated within the double-sided concrete wall. The MCNP simulation indicated that HDPE-Borax is the most efficient among the aforementioned candidate materials, and the combined thickness of the shielding layers should exceed 100 cm to satisfy the dose limit on the outside surface of the shielding wall of the facility when limiting the thickness of the HDPE-Borax intermediate layer to below 5 cm. However, the shielding wall must include the instrumentation and installation holes for the LSDS system. The radiation leakage through the holes was substantially mitigated by adopting a zigzag-shape with concrete covers on both sides. The suggested optimized design of the shielding structure satisfies the dose rate limit and can be used for the construction of a facility in the near

  17. Design optimization of radiation shielding structure for lead slowing-down spectrometer system

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Jeong Dong; Ahn, Sang Joon; Lee, Yong Deok [Nonproliferation System Research Division, Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Park, Chang Je [Dept. of Nuclear Engineering, Sejong University, Seoul (Korea, Republic of)

    2015-04-15

    A lead slowing-down spectrometer (LSDS) system is a promising nondestructive assay technique that enables a quantitative measurement of the isotopic contents of major fissile isotopes in spent nuclear fuel and its pyroprocessing counterparts, such as 235U, 239Pu, 241Pu, and, potentially, minor actinides. The LSDS system currently under development at the Korea Atomic Energy Research Institute (Daejeon, Korea) is planned to utilize a high-flux (>101{sup 2n}/cm{sup 2}·s) neutron source comprised of a high-energy (30 MeV)/high-current (∼2 A) electron beam and a heavy metal target, which results in a very intense and complex radiation field for the facility, thus demanding structural shielding to guarantee the safety. Optimization of the structural shielding design was conducted using MCNPX for neutron dose rate evaluation of several representative hypothetical designs. In order to satisfy the construction cost and neutron attenuation capability of the facility, while simultaneously achieving the aimed dose rate limit (<0.06 μSv/h), a few shielding materials [high-density polyethylene (HDPE)–Borax, B{sub 4}C, and Li{sub 2}CO{sub 3}] were considered for the main neutron absorber layer, which is encapsulated within the double-sided concrete wall. The MCNP simulation indicated that HDPE-Borax is the most efficient among the aforementioned candidate materials, and the combined thickness of the shielding layers should exceed 100 cm to satisfy the dose limit on the outside surface of the shielding wall of the facility when limiting the thickness of the HDPE-Borax intermediate layer to below 5 cm. However, the shielding wall must include the instrumentation and installation holes for the LSDS system. The radiation leakage through the holes was substantially mitigated by adopting a zigzag-shape with concrete covers on both sides. The suggested optimized design of the shielding structure satisfies the dose rate limit and can be used for the construction of a facility in

  18. Safety and environmental process for the design and construction of the National Ignition Facility

    Energy Technology Data Exchange (ETDEWEB)

    Brereton, S.J., LLNL

    1998-05-27

    The National Ignition Facility (NIF) is a U.S. Department of Energy (DOE) laser fusion experimental facility currently under construction at the Lawrence Livermore National Laboratory (LLNL). This paper describes the safety and environmental processes followed by NIF during the design and construction activities.

  19. A Survey of a System of Methods for Fire Safety Design of Traditional Concrete Constructions

    DEFF Research Database (Denmark)

    Hertz, Kristian

    2000-01-01

    During the years since 1978 the author has been developing a series of calculation methods and sup-porting test methods for the fire safety design of concrete constructions. The basic methods have been adopted in the fire chapters of the Eurocode ENV1992-1-2 and the Danish code for concrete const...

  20. Design optimization for security-and safety-critical distributed real-time applications

    DEFF Research Database (Denmark)

    Jiang, Wei; Pop, Paul; Jiang, Ke

    2016-01-01

    In this paper, we are interested in the design of real-time applications with security, safety, timing, and energy requirements. The applications are scheduled with cyclic scheduling, and are mapped on distributed heterogeneous architectures. Cryptographic services are deployed to satisfy securit...

  1. PreScan, madymo and vehil design and evaluation tools for integrated safety systems

    NARCIS (Netherlands)

    Lupker, H.; Lemmen, P.; Ploeg, J.

    2006-01-01

    Pre-Crash Systems (PCS) use environment sensors and electronic control functions to improve the effectiveness of passive safety devices by activating them before a collision occurs. In view of the autonomous character and high demands on reliability, dedicated design tools and methodologies are requ

  2. Improving fuel cycle design and safety characteristics of a gas cooled fast reactor

    NARCIS (Netherlands)

    van Rooijen, W.F.G.

    2006-01-01

    This research concerns the fuel cycle and safety aspects of a Gas Cooled Fast Reactor, one of the so-called "Generation IV" nuclear reactor designs. The Generation IV Gas Cooled Fast Reactor uses helium as coolant at high temperature. The goal of the GCFR is to obtain a "closed nuclear fuel cycle",

  3. Improving fuel cycle design and safety characteristics of a gas cooled fast reactor

    NARCIS (Netherlands)

    van Rooijen, W.F.G.

    2006-01-01

    This research concerns the fuel cycle and safety aspects of a Gas Cooled Fast Reactor, one of the so-called "Generation IV" nuclear reactor designs. The Generation IV Gas Cooled Fast Reactor uses helium as coolant at high temperature. The goal of the GCFR is to obtain a "closed nuclear fuel cycle",

  4. Context factors affecting design and operation of Food Safety Management Systems in the fresh produce chain

    NARCIS (Netherlands)

    Kirezieva, K.K.; Nanyunja, J.; Jacxsens, L.; Vorst, van der J.G.A.J.; Uyttendaele, M.; Luning, P.A.

    2013-01-01

    Recent food-borne outbreaks and cases of non-compliances to maximum residue limits of pesticides, indicated that food safety management systems (FSMS) in fresh produce chain are not yet performing in a satisfactory manner. However, the system output is not only dependent on the system design and ope

  5. Structural safety: Study into critical factors in the design and construction process

    NARCIS (Netherlands)

    Terwel, K.C.

    2014-01-01

    Failure investigations show that 80-85% of the structural failures are caused by inadequacies in the design and construction process, related to human and organizational factors. This study showed that safety culture, allocation of responsibilities control, communication and collaboration and knowl

  6. K Basin sludge packaging design criteria (PDC) and safety analysis report for packaging (SARP) approval plan

    Energy Technology Data Exchange (ETDEWEB)

    Brisbin, S.A.

    1996-03-06

    This document delineates the plan for preparation, review, and approval of the Packaging Design Crieteria for the K Basin Sludge Transportation System and the Associated on-site Safety Analysis Report for Packaging. The transportation system addressed in the subject documents will be used to transport sludge from the K Basins using bulk packaging.

  7. Optimum Safety Levels and Design Rules for the Icelandic Type Berm Breakwater

    DEFF Research Database (Denmark)

    Sigurdarson, Sigurdur; van der Meer, Jentsje W.; Burcharth, Hans F.;

    2007-01-01

    Guidance on selection of breakwater types and related design safety levels for breakwaters are almost non-existent, which is the reason that PIANC has initiated working group 47 on this subject. This paper presents ongoing work particulary on the Icelandic type berm breakwater within the PIANC wo...

  8. Optimum Safety Levels and Design Rules for the Icelandic-Type Berm Breakwater

    DEFF Research Database (Denmark)

    Sigurdarson, Sigurdur; van der Meer, Jentsje W.; Burcharth, Hans F.

    2009-01-01

    This paper gives first an elaboration of berm recession equations for berm breakwaters and then new deterministic design rules for the Icelandic-type berm breakwater. Safety optimization calculations have been performed for a mild depth limited wave climate and for a situation a deep water. Repair...

  9. Design characteristics for pressurized water small modular nuclear power reactors with focus on safety

    Energy Technology Data Exchange (ETDEWEB)

    Kani, Iraj Mahmoudzadeh [Tehran Univ. (Iran, Islamic Republic of). Civil Faculty; Zandieh, Mehdi [Tehran Univ. (Iran, Islamic Republic of). Civil Faculty; International Univ. of Imam Khomeini (Iran, Islamic Republic of). Architecture Faculty; Abadi, Saeed Kheirollahi Hossein [International Univ. of Imam Khomeini (Iran, Islamic Republic of). Architecture Faculty

    2016-05-15

    Small Modular Reactors (SMRs) are a technology, attracting attention. Light water SMR possess an upgraded design case and emphasize the significance of integral models. Beside of these advantages, SMRs has faced numerous challenges, e.g. licensing, cost/investment, safety and security observation, social and environmental issues in building new plants.

  10. Design concept of radiation control system for the high intensity proton accelerator facility

    Energy Technology Data Exchange (ETDEWEB)

    Miyamoto, Yukihiro; Ikeno, Koichi; Akiyama, Shigenori; Harada, Yasunori [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    2002-11-01

    Description is given for the characteristic radiation environment for the High Intensity Proton Accelerator Facility and the design concept of the radiation control system of it. The facility is a large scale accelerator complex consisting of high energy proton accelerators carrying the highest beam intensity in the world and the related experimental facilities and therefore provides various issues relevant to the radiation environment. The present report describes the specifications for the radiation control system for the facility, determined in consideration of these characteristics. (author)

  11. Implementation of European Directive on Optical Radiation Safety takes place in May 2010

    NARCIS (Netherlands)

    Wieringa, F.P.

    2009-01-01

    At the latest by May 10th 2010, Directive 2006/25/EC regarding the exposure of workers to risks arising from artificial optical radiation must be implemented by all EU-member states, thus legally adopting ICNIRP limit values for ultraviolet, visible and infrared radiation. For IUVA-members the

  12. Design and Transient Analysis of Passive Safety Cooling Systems for Advanced Nuclear Reactors

    OpenAIRE

    Galvez, Cristhian

    2011-01-01

    The Pebble Bed Advanced High Temperature Reactor (PB-AHTR) is a pebble fueled, liquid salt cooled, high temperature nuclear reactor design that can be used for electricity generation or other applications requiring the availability of heat at elevated temperatures. A stage in the design evolution of this plant requires the analysis of the plant during a variety of potential transients to understand the primary and safety cooling system response. This study focuses on the performance of the pa...

  13. SAFETY

    CERN Multimedia

    M. Plagge, C. Schaefer and N. Dupont

    2013-01-01

    Fire Safety – Essential for a particle detector The CMS detector is a marvel of high technology, one of the most precise particle measurement devices we have built until now. Of course it has to be protected from external and internal incidents like the ones that can occur from fires. Due to the fire load, the permanent availability of oxygen and the presence of various ignition sources mostly based on electricity this has to be addressed. Starting from the beam pipe towards the magnet coil, the detector is protected by flooding it with pure gaseous nitrogen during operation. The outer shell of CMS, namely the yoke and the muon chambers are then covered by an emergency inertion system also based on nitrogen. To ensure maximum fire safety, all materials used comply with the CERN regulations IS 23 and IS 41 with only a few exceptions. Every piece of the 30-tonne polyethylene shielding is high-density material, borated, boxed within steel and coated with intumescent (a paint that creates a thick co...

  14. SAFETY

    CERN Multimedia

    C. Schaefer and N. Dupont

    2013-01-01

      “Safety is the highest priority”: this statement from CERN is endorsed by the CMS management. An interpretation of this statement may bring you to the conclusion that you should stop working in order to avoid risks. If the safety is the priority, work is not! This would be a misunderstanding and misinterpretation. One should understand that “working safely” or “operating safely” is the priority at CERN. CERN personnel are exposed to different hazards on many levels on a daily basis. However, risk analyses and assessments are done in order to limit the number and the gravity of accidents. For example, this process takes place each time you cross the road. The hazard is the moving vehicle, the stake is you and the risk might be the risk of collision between both. The same principle has to be applied during our daily work. In particular, keeping in mind the general principles of prevention defined in the late 1980s. These principles wer...

  15. Radiation safety and quality in diagnostic x-ray imaging 2001; Saeteilyturvallisuus ja laatu roentgendiagnostiikassa 2001

    Energy Technology Data Exchange (ETDEWEB)

    Servomaa, A.; Parviainen, T. (eds.)

    2001-05-01

    The obligations of the medical exposure directive (97/43/Euratom) for hospitals dominate the current activities in radiation protection in medical radiology. The directive gives special emphasis to radiation exposure of children, to examinations with high radiation doses and to radiation exposure in health screening programmes. The most important examinations with high doses are radiological interventions, where even acute skin effects are possible, and the computed tomography where the number of CT examinations makes only about 5% from the total number of x-ray examinations but the collective effective dose about 40% from the combined collective effective dose of all x-ray examinations. In the research projects financed by the European Commission, radiation exposures to paediatric patients have been measured in radiography, fluoroscopy and CT, and various dose assessment methods have been compared to develop a method for national follow-up of patients' radiation dose. The newest research project is focused on dosimetry and quality assurance in interventional radiology and digital imaging. Other actual topics are the development of radiation protection regulations and quality systems, education and training programmes, and clinical audits. This report deals with new radiation protection guides and recommendations and the education and training of radiological staff in radiation protection. One important topic is the development of national follow-up method of radiation exposure to patients and comparison of various dose assessment methods. Quality assurance in health care and in paediatric radiology, and the acceptance test and quality assurance measurements of radiological equipment are also described. (orig.)

  16. Waterways structural optimum design of electric car radiator

    Institute of Scientific and Technical Information of China (English)

    FAN Bailin; CHEN hua; ZHANG Pei; DOU Jinping

    2012-01-01

    Thermal resistance was composed by thermal resistance of Aluminum substrate, thermal resistance of convective heat transfer and the thermal resistance of the cooling liquid. The change rule was studied through the calculation on Aluminum plate thermal resistance, thermal resistance of convective heat transfer and the thermal resistance of the cooling liquid. Its change regular- ity was simulated by toolbox In the MATLAB, and it was found that thermal resistance of convective heat transfer effect on the effi- ciency was most obvious in a certain amount of the heat and flow for thermal resistance of the Pin-fin radiator under the premise. The structural parameters of radiator were related to the size of thermal resistance.

  17. Designation of Ray Detector Shielding Box for Radiation Imaging

    Institute of Scientific and Technical Information of China (English)

    CHUCheng-jie; XINGJian-sheng; JIAOChuan-rong

    2003-01-01

    The technology of radiation imaging plays an important role in the area of no-bug diagnosis. The principle is that the absorbed dose amount is different when rays go through objects with different material or thickness. According to the through ray intensity, we can get the characteristic picture of diagnostic objects. For this subject, the ray is from a 60Co point irradiation source.

  18. Designation of Ray Detector Shielding Box for Radiation Imaging

    Institute of Scientific and Technical Information of China (English)

    CHUCheng-jie; XINGJian-sheng; JIAOChuan-rong

    2003-01-01

    The technology of radiation imaging plays an important role in the area of no-bug diagnosis. The principle is that the absorbed dose is different when the rays go through objects with different material or thickness. According to the through ray intensity, we can get the characteristic picture of diagnostic objects. For this subject, the ray is from a 60Co point irradiation source.

  19. Study of rationalized safety design based on the seismic PSA for an LMFBR

    Energy Technology Data Exchange (ETDEWEB)

    Nakai, Ryodai; Yamaguchi, Akira

    1998-12-01

    Seismic PSA was carried out for a typical liquid metal cooled fast breeder reactor (LMFBR) in order to study the rationalized seismic design, maintaining and/or improving safety during seismic event. The seismic sequence quantification identifies the dominant structures, systems and components (SSCs) to the seismic core damage frequency (CDF). The sensitivity analyses by reducing or increasing the seismic capacity for SSCs are used to examine the optimized seismic design in view of safety and economical aspects. The LMFBR-specific risk-significant SSCs are reactor coolant boundary, decay heat removal coolant path and reactor control rod, which are different from those of light water reactors (LWRs). The electrical power supply system has a minor contribution to the seismic CDF. The sensitivity study shows that passive safety features of LMFBRs are important to maintain and/or enhance seismic capacity. The passive safety includes the decay heat removal capability via natural circulation and safety measures without depending on the support systems such as alternating current (AC) electrical power, for example. On the course of seismic sequence quantification, a methodology to evaluate the probability of seismic-induced multiple failure has been developed and applied to the decay heat removal function. The results suggest the multiplicity of the triply redundant system is to be considered for the significant components such as the decay heat removal path when one considers the difference in the seismic response.

  20. [The control of radiation protection in the field of radiotherapy by the French Nuclear Safety Authority (ASN)].

    Science.gov (United States)

    Godet, J-L

    2007-11-01

    During the last months, several incidents at radiotherapy services occurred in France; one of these accidents led to the death of several patients or required further heavy surgical acts. In this context, ASN (Autorité de sûreté nucléaire) issued an experimental guide for the notification of radiation protection events and achieved, in dialogue with professional organisations, a new scale intended to facilitate public information on radiotherapy incidents. ASN is also fully involved in the preparation of the action plan managed by the Health ministry in order to improve the safety of treatment in radiotherapy.

  1. Initial experience with an 11 MeV self-shielded medical cyclotron on operation and radiation safety

    Directory of Open Access Journals (Sweden)

    Pant G

    2007-01-01

    Full Text Available A self-shielded medical cyclotron (11 MeV was commissioned at our center, to produce positron emitters, namely, 18 F, 15 O, 13 N and 11 C for positron emission tomography (PET imaging. Presently the cyclotron has been exclusively used for the production of 18 F - for 18 F-FDG imaging. The operational parameters which influence the yield of 18 F - production were monitored. The radiation levels in the cyclotron and radiochemistry laboratory were also monitored to assess the radiation safety status in the facility. The target material, 18 O water, is bombarded with proton beam from the cyclotron to produce 18 F - ion that is used for the synthesis of 18 F-FDG. The operational parameters which influence the yield of 18 F - were observed during 292 production runs out of a total of more than 400 runs. The radiation dose levels were also measured in the facility at various locations during cyclotron production runs and in the radiochemistry laboratory during 18 F-FDG syntheses. It was observed that rinsing the target after delivery increased the number of production runs in a given target, as well as resulted in a better correlation between the duration of bombardment and the end of bombardment 18 F - activity with absolutely clean target after being rebuilt. The radiation levels in the cyclotron and radiochemistry laboratory were observed to be well within prescribed limits with safe work practice.

  2. EICT Based Diagnostic Tool and Monitoring System for EMF Radiation to Sustain Environmental Safety

    Directory of Open Access Journals (Sweden)

    K Parandham

    2013-10-01

    Full Text Available the adverse effects of electromagnetic radiation from mobile phones and communication towers on health issues are being well documented today. However, exact correlation between radiation of communication towers and their radiation levels, are not monitored. Aim of this paper is to study, analyze, apply networking and data mining technologies to develop an EICT based Diagnostic tool and Monitoring system for electromagnetic radiation levels into environment. This system is to network all mobile towers of each service provider as a single entity and then connect all service providers to a central monitoring agency online for continuous monitoring. Since very large numbers of mobile towers exist in India, each state can have its own regional network which is further networked with national central network. This can be enlarged to entire world for monitoring the EMF radiation levels near every mobile tower. For these regional national and international networks the connectivity is to be instituted by the respective service provider. In this paper an attempt is made to logically apply Data Mining and networking technologies to develop a central EICT based diagnostic tool and monitoring system for EMF radiation from each transmission tower. With this system regional, national and international agencies/authorities can monitor the EMF radiation at each and every transmission tower area continuously and verify them with exposure standards. It is proposed to display this information using Integrated Display System in front of monitoring authority at appropriate levels.

  3. Design and Implementation of the Harvard Fellowship in Patient Safety and Quality.

    Science.gov (United States)

    Gandhi, Tejal K; Abookire, Susan A; Kachalia, Allen; Sands, Kenneth; Mort, Elizabeth; Bommarito, Grace; Gagne, Jane; Sato, Luke; Weingart, Saul N

    2016-01-01

    The Harvard Fellowship in Patient Safety and Quality is a 2-year physician-oriented training program with a strong operational orientation, embedding trainees in the quality departments of participating hospitals. It also integrates didactic and experiential learning and offers the option of obtaining a master's degree in public health. The program focuses on methodologically rigorous improvement and measurement, with an emphasis on the development and implementation of innovative practice. The operational orientation is intended to foster the professional development of future quality and safety leaders. The purpose of this article is to describe the design and development of the fellowship.

  4. Probabilistic safety assessment of the design of a tall buildings under the extreme load

    Science.gov (United States)

    Králik, Juraj

    2016-06-01

    The paper describes some experiences from the deterministic and probabilistic analysis of the safety of the tall building structure. There are presented the methods and requirements of Eurocode EN 1990, standard ISO 2394 and JCSS. The uncertainties of the model and resistance of the structures are considered using the simulation methods. The MONTE CARLO, LHS and RSM probabilistic methods are compared with the deterministic results. On the example of the probability analysis of the safety of the tall buildings is demonstrated the effectiveness of the probability design of structures using Finite Element Methods.

  5. Research on vaccines during pregnancy: protocol design and assessment of safety.

    Science.gov (United States)

    Munoz, Flor M; Sheffield, Jeanne S; Beigi, Richard H; Read, Jennifer S; Swamy, Geeta K; Jevaji, Indira; Rasmussen, Sonja A; Edwards, Kathryn M; Fortner, Kimberly B; Patel, Shital M; Spong, Catherine Y; Ault, Kevin; Heine, R Philips; Nesin, Mirjana

    2013-09-13

    The Division of Microbiology and Infectious Diseases at the National Institute of Allergy and Infectious Diseases, National Institutes of Health organized a series of conferences, entitled "Enrolling Pregnant Women in Clinical Trials of Vaccines and Therapeutics", to discuss study design and the assessment of safety in clinical trials conducted in pregnant women. A panel of experts was charged with developing guiding principles for the design of clinical trials and the assessment of safety of vaccines during pregnancy. Definitions and a grading system to evaluate local and systemic reactogenicity, adverse events, and other events associated with pregnancy and delivery were developed. The purpose of this report is to provide investigators interested in vaccine research in pregnancy with a basic set of tools to design and implement maternal immunization studies which may be conducted more efficiently using consistent definitions and grading of adverse events to allow the comparison of safety reports from different trials. These guidelines and safety assessment tools may be modified to meet the needs of each particular protocol based on evidence collected as investigators use them in clinical trials in different settings and share their findings and expertise.

  6. Standardization Safety Management of Nuclear and Radiation Safety Supervision in Colleges and Universities%高校核与辐射安全监管规范化研究

    Institute of Scientific and Technical Information of China (English)

    陈洪霞; 刘朋; 陈永清

    2016-01-01

    针对目前高校核与辐射安全监管方面存在的问题,以苏州大学核与辐射安全监管为研究对象,对高校核与辐射安全监管进行探索与实践。规范化核与辐射的安全监管可以促进大学的安全监管水平。%It has the important meaning to formulate university related safety administrative regulations and security standard, specially regarding standardized safety supervision of the nuclear and radiation, It can promote the university security supervision being scientiifc, standardized normative, and raise the university safety supervision being level. In view of the problems which exist in present university safety supervision on nuclear and radiation, taking the actual situation of Suzhou University safety supervision on nuclear and radiation as an example, it has been explored about the safety supervision on nuclear and radiation.

  7. Cooperation in Nuclear Waste Management, Radiation Protection, Emergency Preparedness, Reactor Safety and Nuclear Non-Proliferation in Eastern Europe

    Energy Technology Data Exchange (ETDEWEB)

    Dassen, Lars van; Delalic, Zlatan; Ekblad, Christer; Keyser, Peter; Turner, Roland; Rosengaard, Ulf; German, Olga; Grapengiesser, Sten; Andersson, Sarmite; Sandberg, Viviana; Olsson, Kjell; Stenberg, Tor

    2009-10-15

    The Swedish Radiation Safety Authority (SSM) is trusted with the task of implementing Sweden's bilateral assistance to Russia, Ukraine, Georgia, Belarus and Armenia in the fields of reactor safety, nuclear waste management, nuclear non-proliferation as well as radiation protection and emergency preparedness. In these fields, SSM also participates in various projects financed by the European Union. The purpose of this project-oriented report is to provide the Swedish Government and other funding agencies as well as other interested audiences in Sweden and abroad with an encompassing understanding of our work and in particular the work performed during 2008. the activities are divided into four subfields: Nuclear waste management; Reactor safety; Radiation safety and emergency preparedness; and, Nuclear non-proliferation. SSM implements projects in the field of spent nuclear fuel and radioactive waste management in Russia. The problems in this field also exist in other countries, yet the concentration of nuclear and radioactive materials are nowhere higher than in north-west Russia. And given the fact that most of these materials stem from the Cold War era and remain stored under conditions that vary from 'possibly acceptable' to 'wildly appalling' it is obvious that Sweden's first priority in the field of managing nuclear spent fuel and radioactive waste lies in this part of Russia. The prioritisation and selection of projects in reactor safety are established following thorough discussions with the partners in Russia and Ukraine. For specific guidance on safety and recommended safety improvements at RBMK and VVER reactors, SSM relies on analyses and handbooks established by the IAEA in the 1990s. In 2008, there were 16 projects in reactor safety. SSM implements a large number of projects in the field of radiation protection and emergency preparedness. The activities are at a first glance at some distance from the activities covered and

  8. Completion plug design provides improved operational efficiency and safety while minimizing environmental risks

    Energy Technology Data Exchange (ETDEWEB)

    Dum, Frank [T.D. Williamson, Inc., Tulsa, OK (United States)

    2012-07-01

    Pipeline repair standards have been raised with recent improvements for completion plugs when used with a brand new setting tool, resulting in lower environmental risks, improved operational efficiency and safety. The design changes were originally made to serve in an offshore environment in order to minimize the diver's time in the water and simplify steps by the diver to execute pipeline repair operations in cold, dark conditions. Enhancements in the design include fewer number of fittings, plugs, o-rings and gaskets isolating the pipeline product found inside the pipe. The new design is a step toward meeting strict operational and safety standards demanded in the field of pipeline maintenance and repair. (author)

  9. System Guidelines for EMC Safety-Critical Circuits: Design, Selection, and Margin Demonstration

    Science.gov (United States)

    Lawton, R. M.

    1996-01-01

    Demonstration of required safety margins on critical electrical/electronic circuits in large complex systems has become an implementation and cost problem. These margins are the difference between the activation level of the circuit and the electrical noise on the circuit in the actual operating environment. This document discusses the origin of the requirement and gives a detailed process flow for the identification of the system electromagnetic compatibility (EMC) critical circuit list. The process flow discusses the roles of engineering disciplines such as systems engineering, safety, and EMC. Design and analysis guidelines are provided to assist the designer in assuring the system design has a high probability of meeting the margin requirements. Examples of approaches used on actual programs (Skylab and Space Shuttle Solid Rocket Booster) are provided to show how variations of the approach can be used successfully.

  10. The interaction between design and occupier behaviour in the safety of new homes.

    Science.gov (United States)

    McDermott, Hilary; Haslam, Roger; Gibb, Alistair

    2007-03-01

    The design of new homes includes many safety features intended to protect occupiers from injury or ill health within the home, however the effectiveness of these primary intervention measures is likely to be affected by user behaviour. This study examined the interaction between user activity and dwelling design and how this might affect health and safety. It aimed to identify how people use features within new homes and how this may limit the protection afforded by building design, codes and regulations. Forty, home-based, semi-structured, in-depth interviews and home inspections were conducted with individuals recently inhabiting a new home. A range of behaviours were reported in relation to building features including fire doors, pipes and cables, and loft access, which may lead to increased risk of injury or ill-health. For example, occupiers described interfering with the self-closing mechanisms on fire doors and drilling into walls without considering the location of services. They also reported knowingly engaging in unsafe behaviour when accessing the loft, increasing their risk of falls. The accounts suggest that designers and builders need to give greater consideration to how occupier behaviour interacts with building features so that improvements in both design and occupier education can lead to improved health and safety.

  11. The Role of Probabilistic Design Analysis Methods in Safety and Affordability

    Science.gov (United States)

    Safie, Fayssal M.

    2016-01-01

    For the last several years, NASA and its contractors have been working together to build space launch systems to commercialize space. Developing commercial affordable and safe launch systems becomes very important and requires a paradigm shift. This paradigm shift enforces the need for an integrated systems engineering environment where cost, safety, reliability, and performance need to be considered to optimize the launch system design. In such an environment, rule based and deterministic engineering design practices alone may not be sufficient to optimize margins and fault tolerance to reduce cost. As a result, introduction of Probabilistic Design Analysis (PDA) methods to support the current deterministic engineering design practices becomes a necessity to reduce cost without compromising reliability and safety. This paper discusses the importance of PDA methods in NASA's new commercial environment, their applications, and the key role they can play in designing reliable, safe, and affordable launch systems. More specifically, this paper discusses: 1) The involvement of NASA in PDA 2) Why PDA is needed 3) A PDA model structure 4) A PDA example application 5) PDA link to safety and affordability.

  12. US Food and Drug Administration Regulation of Medical Devices and Radiation Oncology: Can Reform Improve Safety?

    OpenAIRE

    Hattangadi, Jona A.; O'Reilly, James T.; Recht, Abram

    2011-01-01

    A review of the issues involved in medical device regulation in radiation oncology, including a general review of federal medical device regulation and explanations of the legal and regulatory framework.

  13. Influence of ergonomic design on trackless mining machines on the health and safety of the operators, drivers and workers.

    CSIR Research Space (South Africa)

    Mason, S

    1998-07-01

    Full Text Available The project has produced information and methodologies for use by designers, mine managers and engineers to improve the health and safety associated with the use of trackless vehicles in mines. The project deliverables focus on assisting; designers...

  14. Mathematical Optimization Techniques for Multi-Phase Radiation Treatment Design

    OpenAIRE

    Sonderman, David

    1983-01-01

    A mathematical model for optimal external beam radiotherapy treatment design over multiple treatment phases is presented. The solution procedure is discussed and illustrated on a case of boost treatment for lung cancer. The models are integrated with current radiobiological software to produce an optimal design over both phases of treatment displayed by means of computer graphics.

  15. Internal Charging Design Environments for the Earths Radiation Belts

    Science.gov (United States)

    Minow, Joseph I.; Edwards, David L.

    2009-01-01

    Relativistic electrons in the Earth's radiation belts are a widely recognized threat to spacecraft because they penetrate lightly shielded vehicle hulls and deep into insulating materials where they accumulate to sufficient levels to produce electrostatic discharges. Strategies for evaluating the magnitude of the relativistic electron flux environment and its potential for producing ESD events are varied. Simple "rule of thumb" estimates such as the widely used 10(exp 10) e-/sq cm fluence within 10 hour threshold for the onset of pulsing in dielectric materials provide a quick estimate of when to expect charging issues. More sophisticated strategies based on models of the trapped electron flux within the Earth s magnetic field provide time dependent estimates of electron flux along spacecraft orbits and orbit integrate electron flux. Finally, measurements of electron flux can be used to demonstrate mean and extreme relativistic electron environments. This presentation will evaluate strategies used to specify energetic electron flux and fluence environments along spacecraft trajectories in the Earth s radiation belts.

  16. Involving the elderly in the design process: a participatory design model for usability, safety and attractiveness

    OpenAIRE

    Demirbilek, Oya

    1999-01-01

    Ankara : Institute of Economics and Social Sciences of Bilkent University, 1999. Thesis (Ph.D.) -- Bilkent University, 1999 Includes bibliographical references leaves 113-131 This work presents a conceptual model involving the elderly users into the design process by means of participatory design sessions, where the expertise of designers and the real requirements and opinions of elderly end-users, related to how objects, environments and equipment should be designed to allow ageing ...

  17. The European nuclear safety and radiation protection area: steps and prospects; L'Europe de la surete nucleaire et de la radioprotection: grandes etapes et perspectives

    Energy Technology Data Exchange (ETDEWEB)

    Gillet, G. [Autorite de Surete Nucleaire, Dir. des relations internationales 75 - Paris (France)

    2010-11-15

    Launched with enthusiasm and determination in 1957, The European Atomic Energy Community (EAEC - EURATOM), which aimed to promote the development of a 'powerful nuclear industry' in Europe, has not ultimately fulfilled the wishes of its founding fathers. Rapidly, and on a topic as strategic as the peaceful use of the atom, national reflexes prevailed. The Chernobyl disaster, in 1986, also substantially slowed down the use of nuclear energy in Europe. Nuclear safety and radiation protection have followed two different paths. Backed by Chapter III of the EURATOM treaty, over time the EAEC has developed a substantial legislative corpus on radiation protection. Meanwhile, and strange as it may seem, nuclear safety has remained the poor relation, on the grounds that the treaty does not grant EURATOM competence in the area. It is true that legislation was adopted in reaction to Chernobyl, but for a long time there was no specific regulation of nuclear safety in the EU. The European nuclear safety and radiation protection area owes its construction to Community mechanisms as well as to informal initiatives by safety authorities. Today, more than ever, this centre provides consistency, an overall balance which should both strengthen it and impose it as an international reference. Progress can now be expected on waste management, radiation protection and the safety objectives of new reactors. (author)

  18. Some Challenges in the Design of Human-Automation Interaction for Safety-Critical Systems

    Science.gov (United States)

    Feary, Michael S.; Roth, Emilie

    2014-01-01

    Increasing amounts of automation are being introduced to safety-critical domains. While the introduction of automation has led to an overall increase in reliability and improved safety, it has also introduced a class of failure modes, and new challenges in risk assessment for the new systems, particularly in the assessment of rare events resulting from complex inter-related factors. Designing successful human-automation systems is challenging, and the challenges go beyond good interface development (e.g., Roth, Malin, & Schreckenghost 1997; Christoffersen & Woods, 2002). Human-automation design is particularly challenging when the underlying automation technology generates behavior that is difficult for the user to anticipate or understand. These challenges have been recognized in several safety-critical domains, and have resulted in increased efforts to develop training, procedures, regulations and guidance material (CAST, 2008, IAEA, 2001, FAA, 2013, ICAO, 2012). This paper points to the continuing need for new methods to describe and characterize the operational environment within which new automation concepts are being presented. We will describe challenges to the successful development and evaluation of human-automation systems in safety-critical domains, and describe some approaches that could be used to address these challenges. We will draw from experience with the aviation, spaceflight and nuclear power domains.

  19. Analysis and design of a flat central finned-tube radiator

    Science.gov (United States)

    Auer, B. M.; Haller, H. C.; Krebs, R. P.

    1971-01-01

    Computer program based on fixed conductance parameter yields minimum weight design. Second program employs variable conductance parameter and variable ratio of fin length to tube outside radius, and is used for radiator designs with geometric limitations. Major outputs of the two programs are given.

  20. Using Space Weather Variability in Evaluating the Radiation Environment Design Specifications for NASA's Constellation Program

    Science.gov (United States)

    Coffey, Victoria N.; Blackwell, William C.; Minow, Joseph I.; Bruce, Margaret B.; Howard, James W.

    2007-01-01

    NASA's Constellation program, initiated to fulfill the Vision for Space Exploration, will create a new generation of vehicles for servicing low Earth orbit, the Moon, and beyond. Space radiation specifications for space system hardware are necessarily conservative to assure system robustness for a wide range of space environments. Spectral models of solar particle events and trapped radiation belt environments are used to develop the design requirements for estimating total ionizing radiation dose, displacement damage, and single event effects for Constellation hardware. We first describe the rationale using the spectra chosen to establish the total dose and single event design environmental specifications for Constellation systems. We then compare variability of the space environment to the spectral design models to evaluate their applicability as conservative design environments and potential vulnerabilities to extreme space weather events

  1. Radiation-Suppressed plasmonic open resonators designed by nonmagnetic transformation optics

    Science.gov (United States)

    Xu, Hongyi; Wang, Xingjue; Yu, Tianyuan; Sun, Handong; Zhang, Baile

    2012-01-01

    How to confine light energy associated with surface plasmon polaritons (SPPs) in a physical space with minimal radiation loss whereas creating maximum interacting section with surrounding environment is of particular interest in plasmonic optics. By virtue of transformation optics, we propose a design method of forming a polygonal surface-plasmonic resonator in fully open structures by applying the nonmagnetic affine transformation optics strategy. The radiation loss can be suppressed because SPPs that propagate in the designed open structures will be deceived as if they were propagating on a flat metal/dielectric interface without radiation. Because of the nonmagnetic nature of the transformation strategy, this design can be implemented with dielectric materials available in nature. An experimentally verifiable model is subsequently proposed for future experimental demonstration. Our design may find potential applications in omnidirectional sensing, light harvesting, energy storage and plasmonic lasing. PMID:23136641

  2. Optimization of a conical antenna for pulse radiation - An efficient design using resistive loading

    Science.gov (United States)

    Maloney, James G.; Smith, Glenn S.

    1993-07-01

    The conical monopole antenna with a section of continuous resistive loading is considered as a radiator for temporally short, broad-bandwidth pulses. The geometrical details of the coaxial feed and the resistive loading are varied to optimize this structure for pulse radiation. Compared with the perfectly conducting cone, the optimized resistive cone radiates a better reproduction of the pulse excitation with no loss in amplitude, and has internal reflections that are much smaller in amplitude. Graphical displays of the field surrounding the antenna are used to give insight into the physical processes for transient radiation from this antenna. Experimental models were constructed to verify the optimization and demonstrate the practicality of the design. Measurements of both the reflected voltage in the feed line and the time-varying radiated field are in excellent agreement with the theoretical calculations.

  3. Status of research on biological effects and safety of electromagnetic radiation: telecommunications frequencies

    Energy Technology Data Exchange (ETDEWEB)

    Barnett, S.B.

    1994-06-01

    The possible adverse effects on human health of exposure to radiofrequency (RF) and microwave electromagnetic fields and radiation are of public concern. As the ambient electromagnetic environment continues to intensify (e.g. cellular and portable phones, wireless communications, LANs, PCNs) the effects of exposure from cumulative sources and prolonged exposure to low levels needs to be addressed. This review considers RF and microwave radiation above 100 kHz. It is acknowledged that there are several possible areas of biological interaction which have health implications and about which current knowledge is limited. Advice is based on the assessment of risks to health resulting from these exposures as derived from studies on the effects of RF radiation on animals and volunteers and from epidemiological studies of exposed populations. 360 refs., 9 tabs., 1 fig.

  4. Safety standards for express roads : research in the framework of the European research project Safety Standards for Road Design and Redesign SAFESTAR, Workpackages 3.4.

    NARCIS (Netherlands)

    Hummel, T.

    1999-01-01

    The objective of the SAFESTAR project is the formulation of design standards or recommendations exclusively based on safety arguments. Workpackage 3 (WP3) of SAFESTAR, of which this report is the concluding report, should result in design recommendations for single and dual-carriageway express roads

  5. A hybrid multi-objective imperialist competitive algorithm and Monte Carlo method for robust safety design of a rail vehicle

    Science.gov (United States)

    Nejlaoui, Mohamed; Houidi, Ajmi; Affi, Zouhaier; Romdhane, Lotfi

    2017-10-01

    This paper deals with the robust safety design optimization of a rail vehicle system moving in short radius curved tracks. A combined multi-objective imperialist competitive algorithm and Monte Carlo method is developed and used for the robust multi-objective optimization of the rail vehicle system. This robust optimization of rail vehicle safety considers simultaneously the derailment angle and its standard deviation where the design parameters uncertainties are considered. The obtained results showed that the robust design reduces significantly the sensitivity of the rail vehicle safety to the design parameters uncertainties compared to the determinist one and to the literature results.

  6. Ecological interface design and system safety: One facet of Rasmussen's legacy.

    Science.gov (United States)

    Bennett, Kevin B

    2017-03-01

    The focus of this manuscript is on cognitive systems engineering/ecological interface design (CSE/EID) and the role that this framework may play in improving system safety. First, the decision making and problem solving literatures are reviewed with an eye towards informational needs that are required to support these activities. The utility of two of Rasmussen's analytical tools (i.e., the abstraction and aggregation hierarchies) in conducting work domain analyses to identify associated information (i.e., categories and relationships) is discussed. The importance of designing ecological displays and interfaces that span the informational categories in the abstraction hierarchy is described and concrete examples are provided. The potential role that ecological interfaces can play in providing effective decision making (i.e., preventing accidents) and problem solving (i.e., dealing with accidents) support, thereby improving the safety of our socio-technical systems, is explored. Copyright © 2015 Elsevier Ltd. All rights reserved.

  7. Influence of geometric design characteristics on safety under heterogeneous traffic flow

    Directory of Open Access Journals (Sweden)

    Praveen Vayalamkuzhi

    2016-12-01

    Full Text Available This paper focuses on analysing the influence of geometric design characteristics on traffic safety using bi-directional data on a divided roadway operated under heterogeneous traffic conditions in India. The study was carried out on a four lane divided inter-city highway in plain and rolling terrain. Statistical modelling approach by Poisson regression and Negative binomial regression were used to assess the safety performance as occurrence of crashes are random events and to identify the influence of the geometric design variables on the crash frequency. Negative binomial regression model was found to be more suitable to identify the variables contributing to road crashes. The study enabled better understanding of the factors related to road geometrics that influence road crash frequency. The study also established that operating speed has a significant contribution to the total number of crashes. Negative binomial models are found to be appropriate to predict road crashes on divided roadways under heterogeneous traffic conditions.

  8. External Beam Radiation Therapy and Abiraterone in Men With Localized Prostate Cancer: Safety and Effect on Tissue Androgens

    Energy Technology Data Exchange (ETDEWEB)

    Cho, Eunpi [University of Washington School of Medicine, Seattle, Washington (United States); Fred Hutchinson Cancer Research Center, Seattle, Washington (United States); Mostaghel, Elahe A. [Fred Hutchinson Cancer Research Center, Seattle, Washington (United States); Russell, Kenneth J.; Liao, Jay J.; Konodi, Mark A. [University of Washington School of Medicine, Seattle, Washington (United States); Kurland, Brenda F. [University of Pittsburgh, Pittsburgh, Pennsylvania (United States); Marck, Brett T. [Veterans Affairs Puget Sound Health Care System, Seattle, Washington (United States); Matsumoto, Alvin M. [University of Washington School of Medicine, Seattle, Washington (United States); Veterans Affairs Puget Sound Health Care System, Seattle, Washington (United States); Dalkin, Bruce L. [University of Washington School of Medicine, Seattle, Washington (United States); Montgomery, R. Bruce, E-mail: rbmontgo@uw.edu [University of Washington School of Medicine, Seattle, Washington (United States)

    2015-06-01

    Purpose: Optimizing androgen suppression may provide better control of localized prostate cancer (PCa). Numerous trials have supported the benefit of combining androgen deprivation therapy with definitive radiation therapy in men with locally advanced or high-grade disease. Addition of abiraterone to luteinizing hormone-releasing hormone agonist (LHRHa) with radiation has not been reported. We examined the safety of this combination as well as its impact on androgen suppression. Methods and Materials: A prospective, phase 2 study was conducted in men with localized PCa treated with 6 months of neoadjuvant and concurrent abiraterone with LHRHa and radiation. Duration of adjuvant LHRHa was at the discretion of the treating clinician. Prostate biopsy assays were obtained prior to the start of therapy and prior to radiation. Sera and tissue androgen levels were measured by liquid chromatography-tandem mass spectrometry. Results: A total of 22 men with intermediate- (n=3) and high-risk PCa (n=19) received study therapy. Sixteen men completed the intended course of abiraterone, and 19 men completed planned radiation to 77.4 to 81 Gy. Radiation to pelvic nodes was administered in 20 men. The following grade 3 toxicities were reported: lymphopenia (14 patients), fatigue (1 patient), transaminitis (2 patients), hypertension (2 patients), and hypokalemia (1 patient). There were no grade 4 toxicities. All 21 men who complied with at least 3 months of abiraterone therapy had a preradiation prostate-specific antigen (PSA) concentration nadir of <0.3 ng/mL. Median levels of tissue androgen downstream of CYP17A were significantly suppressed after treatment with abiraterone, and upstream steroids were increased. At median follow-up of 21 months (range: 3-37 months), only 1 patient (who had discontinued abiraterone at 3 months) had biochemical relapse. Conclusions: Addition of abiraterone to LHRHa with radiation is safe and achieves effective prostatic androgen suppression

  9. Radiation protection at synchrotron radiation facilities.

    Science.gov (United States)

    Liu, J C; Vylet, V

    2001-01-01

    A synchrotron radiation (SR) facility typically consists of an injector, a storage ring, and SR beamlines. The latter two features are unique to SR facilities, when compared to other types of accelerator facilities. The SR facilities have the characteristics of low injection beam power, but high stored beam power. The storage ring is generally above ground with people occupying the experimental floor around a normally thin concrete ring wall. This paper addresses the radiation issues, in particular the shielding design, associated with the storage ring and SR beamlines. Normal and abnormal beam losses for injection and stored beams, as well as typical storage ring operation, are described. Ring shielding design for photons and neutrons from beam losses in the ring is discussed. Radiation safety issues and shielding design for SR beamlines, considering gas bremsstrahlung and synchrotron radiation, are reviewed. Radiation source terms and the methodologies for shielding calculations are presented.

  10. The Design and Safety Review for a Creep Capsule With Four Specimens

    Energy Technology Data Exchange (ETDEWEB)

    Cho, M. S.; Seo, C. G.; Choi, M. H.; Choo, K. N.; Sohn, J. M.; Kang, Y. H.; Kim, B. G. [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    2006-07-01

    To review the safety in the irradiation test of a creep capsule with 4 specimens, the design analysis for the incore creep test in the normal and abnormal operation condition was performed. In the normal operation condition, the reactivity effect was estimated and the analysis on the stress and temperature was performed. In the abnormal operation condition, the effect exerted on the capsule body by a leakage or breakage of the stress loading unit was analyzed.

  11. Design of compact system with wide electron beam for radiation technologies

    CERN Document Server

    Korolyov, A N; Pirozhenko, Vitaly M

    2001-01-01

    Design of a compact system for radiation processing of products and materials has been developed. The system provides two modes of irradiation, i.e. irradiation of continuously moving tapes and fixed samples. The irradiation is performed in a hermetically sealed chamber filled by nitrogen. This ecologically pure system includes the radiation protection,autonomous water cooling system and automated PC-control. It can be placed in any production or clinical room.

  12. Modified blackbody radiation spectrum of a selective emitter with application to incandescent light source design.

    Science.gov (United States)

    Matsumoto, Takahiro; Tomita, Makoto

    2010-06-21

    Using a selective emitter with high emissivity in the visible wavelength region and low emissivity in the infrared wavelength region, we reduced the infrared contribution to the blackbody radiation spectrum and shifted the peak emission to shorter wavelengths. We made precise measurements of thermal radiation loss. The conversion efficiency from input electric power to visible light radiation was quantitatively evaluated with high accuracy. Using the proposed selective emitter, the conversion efficiencies in excess of 95% could be produced. Our conclusions pave the way for the design of incandescent lamps with luminous efficiencies exceeding 400 lm/W.

  13. Safety assessment in plant layout design using indexing approach: implementing inherent safety perspective. Part 2-Domino Hazard Index and case study.

    Science.gov (United States)

    Tugnoli, Alessandro; Khan, Faisal; Amyotte, Paul; Cozzani, Valerio

    2008-12-15

    The design of layout plans requires adequate assessment tools for the quantification of safety performance. The general focus of the present work is to introduce an inherent safety perspective at different points of the layout design process. In particular, index approaches for safety assessment and decision-making in the early stages of layout design are developed and discussed in this two-part contribution. Part 1 (accompanying paper) of the current work presents an integrated index approach for safety assessment of early plant layout. In the present paper (Part 2), an index for evaluation of the hazard related to the potential of domino effects is developed. The index considers the actual consequences of possible escalation scenarios and scores or ranks the subsequent accident propagation potential. The effects of inherent and passive protection measures are also assessed. The result is a rapid quantification of domino hazard potential that can provide substantial support for choices in the early stages of layout design. Additionally, a case study concerning selection among various layout options is presented and analyzed. The case study demonstrates the use and applicability of the indices developed in both parts of the current work and highlights the value of introducing inherent safety features early in layout design.

  14. Radiation safety assessment and development of environmental radiation monitoring technology; standardization of input parameters for the calculation of annual dose from routine releases from commercial reactor effluents

    Energy Technology Data Exchange (ETDEWEB)

    Rhee, I. H.; Cho, D.; Youn, S. H.; Kim, H. S.; Lee, S. J.; Ahn, H. K. [Soonchunhyang University, Ahsan (Korea)

    2002-04-01

    This research is to develop a standard methodology for determining the input parameters that impose a substantial impact on radiation doses of residential individuals in the vicinity of four nuclear power plants in Korea. We have selected critical nuclei, pathways and organs related to the human exposure via simulated estimation with K-DOSE 60 based on the updated ICRP-60 and sensitivity analyses. From the results, we found that 1) the critical nuclides were found to be {sup 3}H, {sup 133}Xe, {sup 60}Co for Kori plants and {sup 14}C, {sup 41}Ar for Wolsong plants. The most critical pathway was 'vegetable intake' for adults and 'milk intake' for infants. However, there was no preference in the effective organs, and 2) sensitivity analyses showed that the chemical composition in a nuclide much more influenced upon the radiation dose than any other input parameters such as food intake, radiation discharge, and transfer/concentration coefficients by more than 102 factor. The effect of transfer/concentration coefficients on the radiation dose was negligible. All input parameters showed highly estimated correlation with the radiation dose, approximated to 1.0, except for food intake in Wolsong power plant (partial correlation coefficient (PCC)=0.877). Consequently, we suggest that a prediction model or scenarios for food intake reflecting the current living trend and a formal publications including details of chemical components in the critical nuclei from each plant are needed. Also, standardized domestic values of the parameters used in the calculation must replace the values of the existed or default-set imported factors via properly designed experiments and/or modelling such as transport of liquid discharge in waters nearby the plants, exposure tests on corps and plants so on. 4 figs., 576 tabs. (Author)

  15. Cornell Alliance for Science Evaluation of Consensus on Genetically Modified Food Safety: Weaknesses in Study Design.

    Science.gov (United States)

    Antoniou, Michael N; Robinson, Claire J

    2017-01-01

    Cornell Alliance for Science has launched an initiative in which "citizen scientists" are called upon to evaluate studies on health risks of genetically modified (GM) crops and foods. The purpose is to establish whether the consensus on GM food safety claimed by the American Association for the Advancement of Science (AAAS) is supported by a review of the scientific literature. The Alliance's citizen scientists are examining more than 12,000 publication abstracts to quantify how far the scientific literature supports the AAAS's statement. We identify a number of fundamental weaknesses in the Alliance's study design, including evaluation is based only on information provided in the publication abstract; there is a lack of clarity as to what material is included in the 12,000 study abstracts to be reviewed, since the number of appropriately designed investigations addressing GM food safety are few; there is uncertainty as to whether studies of toxic effects arising from GM crop-associated pesticides will be included; there is a lack of clarity regarding whether divergent yet equally valid interpretations of the same study will be taken into account; and there is no definition of the cutoff point for consensus or non-consensus on GM food safety. In addition, vital industry proprietary biosafety data on GM crops and associated pesticides are not publicly available and is thus cannot inform this project. Based on these weaknesses in the study design, we believe it is questionable as to whether any objective or meaningful conclusion can be drawn from the Alliance's initiative.

  16. Design and reliability, availability, maintainability, and safety analysis of a high availability quadruple vital computer system

    Institute of Scientific and Technical Information of China (English)

    Ping TAN; Wei-ting HE; Jia LIN; Hong-ming ZHAO; Jian CHU

    2011-01-01

    With the development of high-speed railways in China,more than 2000 high-speed trains will be put into use.Safety and efficiency of railway transportation is increasingly important.We have designed a high availability quadruple vital computer (HAQVC) system based on the analysis of the architecture of the traditional double 2-out-of-2 system and 2-out-of-3 system.The HAQVC system is a system with high availability and safety,with prominent characteristics such as fire-new internal architecture,high efficiency,reliable data interaction mechanism,and operation state change mechanism.The hardware of the vital CPU is based on ARM7 with the real-time embedded safe operation system (ES-OS).The Markov modeling method is designed to evaluate the reliability,availability,maintainability,and safety (RAMS) of the system.In this paper,we demonstrate that the HAQVC system is more reliable than the all voting triple modular redundancy (AVTMR) system and double 2-out-of-2 system.Thus,the design can be used for a specific application system,such as an airplane or high-speed railway system.

  17. Comprehension of safety signs for construction workers: comparison of existing and newly designed signs.

    Science.gov (United States)

    Arphorn, Sara; Augsornpeug, Naiphaporn; Srisorrachatr, Suwat; Pruktharathikul, Vichai

    2003-12-01

    The comprehension of safety signs for construction workers was compared among existing and improved designs. Safety signs considered were existing signs, existing signs improved by adding text, existing signs improved by adding/changing pictorials, and existing signs improved by adding/changing pictorials and text. Three hundred and eighty-four construction workers were randomized for assignments into four groups. They were working on nine constructions work sites randomly selected from work sites located in Bangkok, Thailand. The number of workers in each work site was calculated for the proportion of the sample size and then they were randomized so that equal numbers of workers were included in the four groups. The four types of safety signs and an interview form were used to test their comprehension of safety signs. For data analysis, percentages, means, standard deviations, the chi-square test, the one-way ANOVA and LSD tests were applied. The results showed that the mean comprehension scores of the existing signs improved by adding text, the existing signs improved by adding/changing pictorials, and the existing signs improved by adding/changing pictorials and text were significantly higher than those of the existing signs. In addition, the mean comprehension scores of the existing signs improved by adding text and the existing signs improved by adding/changing pictorials and text were significantly higher than those of the existing signs improved by adding/changing pictorials. The highest mean comprehension score of safety signs for the construction workers was found in the existing signs improved by adding/changing pictorials and text. These results indicated that for construction workers, the comprehension of safety signs with pictorials and explanatory text was better than that of the existing signs.

  18. Design and implementation of an identification system in construction site safety for proactive accident prevention.

    Science.gov (United States)

    Yang, Huanjia; Chew, David A S; Wu, Weiwei; Zhou, Zhipeng; Li, Qiming

    2012-09-01

    Identifying accident precursors using real-time identity information has great potential to improve safety performance in construction industry, which is still suffering from day to day records of accident fatality and injury. Based on the requirements analysis for identifying precursor and the discussion of enabling technology solutions for acquiring and sharing real-time automatic identification information on construction site, this paper proposes an identification system design for proactive accident prevention to improve construction site safety. Firstly, a case study is conducted to analyze the automatic identification requirements for identifying accident precursors in construction site. Results show that it mainly consists of three aspects, namely access control, training and inspection information and operation authority. The system is then designed to fulfill these requirements based on ZigBee enabled wireless sensor network (WSN), radio frequency identification (RFID) technology and an integrated ZigBee RFID sensor network structure. At the same time, an information database is also designed and implemented, which includes 15 tables, 54 queries and several reports and forms. In the end, a demonstration system based on the proposed system design is developed as a proof of concept prototype. The contributions of this study include the requirement analysis and technical design of a real-time identity information tracking solution for proactive accident prevention on construction sites. The technical solution proposed in this paper has a significant importance in improving safety performance on construction sites. Moreover, this study can serve as a reference design for future system integrations where more functions, such as environment monitoring and location tracking, can be added.

  19. Compassionate containment? Balancing technical safety and therapy in the design of psychiatric wards.

    Science.gov (United States)

    Curtis, Sarah; Gesler, Wilbert; Wood, Victoria; Spencer, Ian; Mason, James; Close, Helen; Reilly, Joseph

    2013-11-01

    This paper contributes to the international literature examining design of inpatient settings for mental health care. Theoretically, it elaborates the connections between conceptual frameworks from different strands of literature relating to therapeutic landscapes, social control and the social construction of risk. It does so through a discussion of the substantive example of research to evaluate the design of a purpose built inpatient psychiatric health care facility, opened in 2010 as part of the National Health Service (NHS) in England. Findings are reported from interviews or discussion groups with staff, patients and their family and friends. This paper demonstrates a strong, and often critical awareness among members of staff and other participants about how responsibilities for risk governance of 'persons' are exercised through 'technical safety' measures and the implications for therapeutic settings. Our participants often emphasised how responsibility for technical safety was being invested in the physical infrastructure of certain 'places' within the hospital where risks are seen to be 'located'. This illuminates how the spatial dimensions of social constructions of risk are incorporated into understandings about therapeutic landscapes. There were also more subtle implications, partly relating to 'Panopticist' theories about how the institution uses technical safety to supervise its own mechanisms, through the observation of staff behaviour as well as patients and visitors. Furthermore, staff seemed to feel that in relying on technical safety measures they were, to a degree, divesting themselves of human responsibility for risks they are required to manage. However, their critical assessment showed their concerns about how this might conflict with a more therapeutic approach and they contemplated ways that they might be able to engage more effectively with patients without the imposition of technical safety measures. These findings advance our thinking

  20. Prevention by Design: Construction and Renovation of Health Care Facilities for Patient Safety and Infection Prevention.

    Science.gov (United States)

    Olmsted, Russell N

    2016-09-01

    The built environment supports the safe care of patients in health care facilities. Infection preventionists and health care epidemiologists have expertise in prevention and control of health care-associated infections (HAIs) and assist with designing and constructing facilities to prevent HAIs. However, design elements are often missing from initial concepts. In addition, there is a large body of evidence that implicates construction and renovation as being associated with clusters of HAIs, many of which are life threatening for select patient populations. This article summarizes known risks and prevention strategies within a framework for patient safety.

  1. First wall and blanket module safety enhancement by material selection and design decision

    Energy Technology Data Exchange (ETDEWEB)

    Merrill, B.J.

    1980-01-01

    A thermal/mechanical study has been performed which illustrates the behavior of a fusion reactor first wall and blanket module during a loss of coolant flow event. The relative safety advantages of various material and design options were determined. A generalized first wall-blanket concept was developed to provide the flexibility to vary the structural material (stainless steel vs titanium), coolant (helium vs water), and breeder material (liquid lithium vs solid lithium aluminate). In addition, independent vs common first wall-blanket cooling and coupled adjacent module cooling design options were included in the study. The comparative analyses were performed using a modified thermal analysis code to handle phase change problems.

  2. Behavior and awareness of thyroid cancer patients in Korea having non-hospitalized low-dose radioiodine treatment with regard to radiation safety

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Seog Gyun; Paeng, Jin Chul; Eo, Jae Seon; Shim, Hye Kyung; Kang, Keon Wook; Chung, June Key; Lee, Myung Chul; Lee, Dong Soo [College of Medicine, Seoul National University, Seoul (Korea, Republic of)

    2010-12-15

    With the recent increase in incidence of thyroid cancer, non-hospitalized low-dose (NH-LD) radioiodine treatment (RIT) has also increased rapidly. The radioactivity limit that is allowed to be administered without hospitalization depends on individual calculation, based partly on patients' behavior. In this study, Korean patients' behavior in relation to radiation safety in NHLD RIT was surveyed. A total of 218 patients who underwent NH-LD RIT of 1.1 GBq {sup 131}I in a single center were surveyed. The patients underwent RIT with a standard protocol and the survey was performed by interview when they visited subsequently for a whole-body scan. The survey questionnaire included three parts of questions: general information, behavior relating to isolation during RIT, and awareness of radiation safety. After administration of radioiodine, 40% of patients who returned home used mass transportation, and another 47% went home by taxi or in car driven by another person. Isolation at home was generally sufficient. However, 7% of patients did not stay in a separate room. Among the 218 patients, 34% did not go home and chose self-isolation away from home, mostly due to concerns about radiation safety of family members. However, the places were mostly public places, including hotels, resorts, and hospitals. About half of the patients replied that access to radiation safety information was not easy and their awareness of radiation safety was not satisfactory. As a result, 45% of patients wanted hospitalized RIT. In many countries, including Korea, RIT is continuously increasing. Considering the radiation safety of patients' family members or the public and the convenience of patients, the pretreatment education of patients should be enhanced. In addition, the hospitalization of patients having low-dose therapy is recommended to be seriously considered and expanded, with the expansion of dedicated treatment facilities

  3. Final safety analysis report for the Galileo Mission: Volume 1, Reference design document

    Energy Technology Data Exchange (ETDEWEB)

    1988-05-01

    The Galileo mission uses nuclear power sources called Radioisotope Thermoelectric Generators (RTGs) to provide the spacecraft's primary electrical power. Because these generators contain nuclear material, a Safety Analysis Report (SAR) is required. A preliminary SAR and an updated SAR were previously issued that provided an evolving status report on the safety analysis. As a result of the Challenger accident, the launch dates for both Galileo and Ulysses missions were later rescheduled for November 1989 and October 1990, respectively. The decision was made by agreement between the DOE and the NASA to have a revised safety evaluation and report (FSAR) prepared on the basis of these revised vehicle accidents and environments. The results of this latest revised safety evaluation are presented in this document (Galileo FSAR). Volume I, this document, provides the background design information required to understand the analyses presented in Volumes II and III. It contains descriptions of the RTGs, the Galileo spacecraft, the Space Shuttle, the Inertial Upper Stage (IUS), the trajectory and flight characteristics including flight contingency modes, and the launch site. There are two appendices in Volume I which provide detailed material properties for the RTG.

  4. Preliminary safety calculations to improve the design of Molten Salt Fast Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Brovchenko, M.; Heuer, D.; Merle-Lucotte, E.; Allibert, M.; Capellan, N.; Ghetta, V.; Laureau, A. [LPSC, CNRS/IN2P3, Grenoble INP, 53,rue des Martyrs, 38026 Grenoble Cedex (France)

    2012-07-01

    Molten salt reactors are liquid fuel reactors so that they are flexible in operation but very different in the safety approach from solid fuel reactors. This study bears on the specific concept named Molten Salt Fast Reactor (MSFR). Since this new nuclear technology is in development, safety is an essential point to be considered all along the R and D studies. This paper presents the first step of the safety approach: the systematic description of the MSFR, limited here to the main systems surrounding the core. This systematic description is the basis on which we will be able to devise accidental scenarios. Thanks to the negative reactivity feedback coefficient, most accidental scenarios lead to reactor shut down. Because of the decay heat generated in the fuel salt, it must be cooled. After the description of the tools developed to calculate the residual heat, the different contributions are discussed in this study. The decay heat of fission products in the MSFR is evaluated to be low (3% of nominal power), mainly due to the reprocessing that transfers the fission products to the gas reprocessing unit. As a result, the contribution of the actinides is significant (0.5% of nominal power). The unprotected loss of heat sink transients are studied in this paper. It appears that slow transients are favorable (> 1 min) to minimize the temperature increase of the fuel salt. This work will be the basis of further safety studies as well as an essential parameter for the design of the draining system. (authors)

  5. 10 CFR 36.39 - Design requirements.

    Science.gov (United States)

    2010-01-01

    ... concrete and design the walls, wall penetrations, and entranceways to meet the radiation shielding... licensee shall design the reinforced concrete radiation shields to retain their integrity in the event of... REGULATORY COMMISSION LICENSES AND RADIATION SAFETY REQUIREMENTS FOR IRRADIATORS Design and...

  6. Safety effects of road design standards in Europe. Contribution to the International Symposium on Highway Geometric Design Practices, Session on Safety and Human Factors Considerations, Boston, Massachusetts, August 30 - September 1, 1995.

    NARCIS (Netherlands)

    Wegman, F.C.M. & Slop, M.

    1996-01-01

    This paper deals with the result of a study carried out for the European Commission by the SWOV Institute for Road Safety Research, in co-operation with a number of other European institutes, and which was reported in 1994. The title of the study is "Safety Effects of Road Design Standards." The aim

  7. Safety effects of road design standards in Europe. Contribution to the International Symposium on Highway Geometric Design Practices, Session on Safety and Human Factors Considerations, Boston, Massachusetts, August 30 - September 1, 1995.

    NARCIS (Netherlands)

    Wegman, F.C.M. & Slop, M.

    1996-01-01

    This paper deals with the result of a study carried out for the European Commission by the SWOV Institute for Road Safety Research, in co-operation with a number of other European institutes, and which was reported in 1994. The title of the study is "Safety Effects of Road Design Standards." The aim

  8. Integrating Safety, Operations, Security, and Safeguards (ISOSS) into the design of small modular reactors : a handbook.

    Energy Technology Data Exchange (ETDEWEB)

    Middleton, Bobby D.; Mendez, Carmen Margarita

    2013-10-01

    The existing regulatory environment for nuclear reactors impacts both the facility design and the cost of operations once the facility is built. Delaying the consideration of regulatory requirements until late in the facility design - or worse, until after construction has begun - can result in costly retrofitting as well as increased operational costs to fulfill safety, security, safeguards, and emergency readiness requirements. Considering the scale and scope, as well as the latest design trends in the next generation of nuclear facilities, there is an opportunity to evaluate the regulatory requirements and optimize the design process for Small Modular Reactors (SMRs), as compared to current Light Water Reactors (LWRs). To this end, Sandia has embarked on an initiative to evaluate the interactions of regulations and operations as an approach to optimizing the design of SMR facilities, supporting operational efficiencies, as well as regulatory requirements. The early stages of this initiative consider two focus areas. The first focus area, reported by LaChance, et al. (2007), identifies the regulatory requirements established for the current fleet of LWR facilities regarding Safety, Security, Operations, Safeguards, and Emergency Planning, and evaluates the technical bases for these requirements. The second focus area, developed in this report, documents the foundations for an innovative approach that supports a design framework for SMR facilities that incorporates the regulatory environment, as well as the continued operation of the facility, into the early design stages, eliminating the need for costly retrofitting and additional operating personnel to fulfill regulatory requirements. The work considers a technique known as Integrated Safety, Operations, Security and Safeguards (ISOSS) (Darby, et al., 2007). In coordination with the best practices of industrial operations, the goal of this effort is to develop a design framework that outlines how ISOSS

  9. A study on the radiation and environment safety -Development of technology for biological dosimetry-

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Kang Suk; Kim, Kook Chan; Kim, In Kyoo; Kim, Jin Kyoo; Chun Kee Jung; Park, Hyo Kook; Kim, Sang Bok; Park Sun Yung [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1995-07-01

    Adult rats were treated a single, whole body exposure to a dose of 0.1, 0.5, 1.0, 2.0, 3.0 Gy. The animals were sacrificed 6, 24, 48, 72, 96 hours following exposure. The amount of serum acute phase proteins(haptoglobin, ceruloplasmin, C-reactive protein, alpha-1 antitrypsin, alpha-1 acid glycoprotein, transferrin) were measured by competitive ELISA. In the 0.1 Gy irradiated rats, serum haptoglobin, C-reactive protein and alpha-1 antitrypsin were 400% higher and serum transferrin was 50% lower as compared to controls, 96 hours after irradiation. Ceruloplasmin increased by 400%, 24 hours after irradiation, but 96 hours after irradiation, the concentration of this protein in rat returned to normal level. On the other hand, no changes were observed in the case of alpha-1 acid glycoprotein. In the group of the 3.0 Gy irradiated rats, transferrin increased by 200%, 96 hours after irradiation. These biochemical responses to radiation did not show dose-dependent relation, but the sensitivity of the indicators was high enough to detect absorbed dose of 0.1 Gy. The above results can be applied to the measurements of acute phase reactants in human serum for the assessment of exposure doses in radiation workers and patients under radiation therapy. 39 figs, 72 refs. (Author).

  10. Efficient runner safety assessment during early design phase and root cause analysis

    Science.gov (United States)

    Liang, Q. W.; Lais, S.; Gentner, C.; Braun, O.

    2012-11-01

    Fatigue related problems in Francis turbines, especially high head Francis turbines, have been published several times in the last years. During operation the runner is exposed to various steady and unsteady hydraulic loads. Therefore the analysis of forced response of the runner structure requires a combined approach of fluid dynamics and structural dynamics. Due to the high complexity of the phenomena and due to the limitation of computer power, the numerical prediction was in the past too expensive and not feasible for the use as standard design tool. However, due to continuous improvement of the knowledge and the simulation tools such complex analysis has become part of the design procedure in ANDRITZ HYDRO. This article describes the application of most advanced analysis techniques in runner safety check (RSC), including steady state CFD analysis, transient CFD analysis considering rotor stator interaction (RSI), static FE analysis and modal analysis in water considering the added mass effect, in the early design phase. This procedure allows a very efficient interaction between the hydraulic designer and the mechanical designer during the design phase, such that a risk of failure can be detected and avoided in an early design stage.The RSC procedure can also be applied to a root cause analysis (RCA) both to find out the cause of failure and to quickly define a technical solution to meet the safety criteria. An efficient application to a RCA of cracks in a Francis runner is quoted in this article as an example. The results of the RCA are presented together with an efficient and inexpensive solution whose effectiveness could be proven again by applying the described RSC technics. It is shown that, with the RSC procedure developed and applied as standard procedure in ANDRITZ HYDRO such a failure is excluded in an early design phase. Moreover, the RSC procedure is compatible with different commercial and open source codes and can be easily adapted to apply for

  11. Design of autotrack detecting instrument for solar UV radiation

    Science.gov (United States)

    Xia, Jiangtao; Mao, Xiaoli; Zhao, Jing

    2009-11-01

    In order to autotrack the object and detect the solar UV index, a reliable real-time high-precise instrument is proposed in this paper. This instrument involves two subsystems: the autotrack and detecting modules. The autotrack module consists of four-quadrant photo detector, multi-channel signal processing circuit and precise stepping system. The detecting module designed for dada measurement and acquisition is made up of the ultraviolet sensor UV460 and high precision A/D converter MAX1162. The key component of the entire instrument is ultralow-power microprocessor MSP430 which is used for entire system controlling and data processing. The lower system of autotracking and measurement is communicated with upper PC computer by RS232 module. In the experiment, the tracking precision of two-dimensional motion revolving stage is calibrated to be less than 0.05°. Experimental results indicate that the system designed could realize the precise autotracking and detecting function well, and the measure precision of system has reached the desirable target.

  12. Nuclear safety and radiation protection report of the Fessenheim nuclear facilities - 2010; Rapport sur la surete nucleaire et la radioprotection des installations nucleaires de Fessenheim - 2010

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-06-15

    This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Fessenheim nuclear power plant (INB 75, Haut-Rhin, 68 (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2010, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

  13. Role of fire safety design in building design%防火疏散设计在建筑设计中的作用

    Institute of Scientific and Technical Information of China (English)

    贾江美

    2011-01-01

    结合建筑规范中条文总结了高层建筑与商业建筑的防火疏散设计应注意的问题,阐述了防火疏散设计理念,并指出多层商业建筑及高层建筑防火疏散设计应注意事项,以期提高人们对建筑设计中防火疏散设计意识。%Integrating with building norms,it summarizes the matters needing attention in fire safety design for high-rise building and commercial buildings,describes fire safety design concept,and points out matters needing attention in multi-layer commercial building and high-rise building fire safety design,with a view to improve people's fire safety design consciousness in building design.

  14. Safety techniques in the change of nuclear systems. Radiation protection at spallation neutron sources and transmutation facilities; Sicherheitstechnik im Wandel Nuklearer Systeme. Strahlenschutz bei Spallationsneutronenquellen und Transmutationsanlagen

    Energy Technology Data Exchange (ETDEWEB)

    Nuenighoff, Kay

    2009-07-01

    : production of secondary particles, induced radiotoxicity, energy deposition, and the moderation of neutrons and their transport through neutron guides. All these topics are discussed, and numerical solutions are presented. To answer questions concerning the radiation protection of such facilities complex numerical simulations are mandatory. Especially the strong interest in the field of basic research in cold neutron beams requires not only the study of the interaction of high energetic particles with matter, but furthermore the investigation of the influence of neutron optical phenomenons. The presented numerical methods allow the engineer responsible for radiation protection to analyse radiological hazards during the design phase of a project and the early and cheap implementation of technical solutions improving safety. Quoted as an example spallation neutron sources as well as energy amplifiers are discussed. At the end the philosophy of the safety of high power accelerator driven systems are discussed from the point of view of a safety scientist. (orig.)

  15. Environmental Modelling for Radiation Safety (EMRAS) — A Summary Report of the Results of the EMRAS Programme (2003-2007)

    DEFF Research Database (Denmark)

    Arkhipov, A.; Charnock, T.W.; Gaschak, S.;

    This publication provides a detailed overview of the results and achievements of the IAEA programme called EMRAS (Environmental Modelling for Radiation Safety), which ran from 2003 to 2007. The activities of the various working groups focused on the compilation of a handbook of parameter values...... for the prediction of radionuclide transfer in temperate environments, on the test and comparison of models to assess the transfer of tritium and 14C to biota and humans, on the validation of models for dose reconstruction due to 131I after the Chernobyl accident, on modelling the transfer of radionuclides...... in aquatic systems, on remediation of rural and urban sites with radioactive residues, and on the impact of environmental radioactivity on non-human species. The book concludes with a summary of the outcomes of the EMRAS programme and is accompanied by a CD-ROM which provides details of the work...

  16. Framework for Integrating Safety, Operations, Security, and Safeguards in the Design and Operation of Nuclear Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Darby, John L. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Horak, Karl Emanuel [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); LaChance, Jeffrey L. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Tolk, Keith Michael [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Whitehead, Donnie Wayne [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2007-10-01

    The US is currently on the brink of a nuclear renaissance that will result in near-term construction of new nuclear power plants. In addition, the Department of Energy’s (DOE) ambitious new Global Nuclear Energy Partnership (GNEP) program includes facilities for reprocessing spent nuclear fuel and reactors for transmuting safeguards material. The use of nuclear power and material has inherent safety, security, and safeguards (SSS) concerns that can impact the operation of the facilities. Recent concern over terrorist attacks and nuclear proliferation led to an increased emphasis on security and safeguard issues as well as the more traditional safety emphasis. To meet both domestic and international requirements, nuclear facilities include specific SSS measures that are identified and evaluated through the use of detailed analysis techniques. In the past, these individual assessments have not been integrated, which led to inefficient and costly design and operational requirements. This report provides a framework for a new paradigm where safety, operations, security, and safeguards (SOSS) are integrated into the design and operation of a new facility to decrease cost and increase effectiveness. Although the focus of this framework is on new nuclear facilities, most of the concepts could be applied to any new, high-risk facility.

  17. Design Issues for Using Magnetic Materials in Radiation Environments at Elevated Temperature

    Science.gov (United States)

    Bowman, Cheryl L.

    2013-01-01

    One of the challenges of designing motors and alternators for use in nuclear powered space missions is accounting for the effects of radiation. Terrestrial reactor power plants use distance and shielding to minimize radiation damage but space missions must economize volume and mass. Past studies have shown that sufficiently high radiation levels can affect the magnetic response of hard and soft magnetic materials. Theoretical models explaining the radiation-induced degradation have been proposed but not verified. This paper reviews the literature and explains the cumulative effects of temperature, magnetic-load, and radiation-level on the magnetic properties of component materials. Magnetic property degradation is very specific to alloy choice and processing history, since magnetic properties are very much entwined with specific chemistry and microstructural features. However, there is basic theoretical as well as supportive experimental evidence that the negative impact to magnetic properties will be minimal if the bulk temperature of the material is less than fifty percent of the Curie temperature, the radiation flux is low, and the demagnetization field is small. Keywords: Magnets, Permanent Magnets, Power Converters, Nuclear Electric Power Generation, Radiation Tolerance.

  18. Design considerations for the coherent radiator, FEL, in the MAX IV proposal

    CERN Document Server

    Werin, Sverker; Brandin, Mathias; Eriksson, Mikael; Hansen, T N; Larsson, Jörgen; Lindgren, L J; Tarawneh, Hamed

    2004-01-01

    The MAX IV proposal is a project for the next Swedish synchrotron radiation source. Currently a design study is produced with funding from the Swedish research council (VR). One half of the project will be a double storage ring (at 3 and 1.5 GeV respectively) but the other half will be a coherent radiator, FEL, based on the 3 GeV injector. The basic FEL solution will consist of a normal conducting linac at 3 GeV which feeds three seeded cascaded optical klystrons and a radiator undulator to produce radiation down to 1.5-3 nm at GW powers. To assure synchronisation the gun laser and the seed laser share initial laser and amplifier. This basic system can be enhanced in various ways which will be discussed .

  19. Design of two digital radiation tolerant integrated circuits for high energy physics experiments data readout

    CERN Document Server

    Bonacini, Sandro

    2003-01-01

    High Energy Physics research (HEP) involves the design of readout electron- ics for its experiments, which generate a high radiation ¯eld in the detectors. The several integrated circuits placed in the future Large Hadron Collider (LHC) experiments' environment have to resist the radiation and carry out their normal operation. In this thesis I will describe in detail what, during my 10-months partic- ipation in the digital section of the Microelectronics group at CERN, I had the possibility to work on: - The design of a radiation-tolerant data readout digital integrated cir- cuit in a 0.25 ¹m CMOS technology, called \\the Kchip", for the CMS preshower front-end system. This will be described in Chapter 3. - The design of a radiation-tolerant SRAM integrated circuit in a 0.13 ¹m CMOS technology, for technology radiation testing purposes and fu- ture applications in the HEP ¯eld. The SRAM will be described in Chapter 4. All the work has carried out under the supervision and with the help of Dr. Kostas Klouki...

  20. Single Line of Sight CMOS radiation tolerant camera system design overview

    Science.gov (United States)

    Carpenter, A. C.; Dayton, M.; Kimbrough, J.; Datte, P.; Macaraeg, C.; Funsten, B.; Gardner, P.; Kittle, D.; Charron, K.; Bell, P.; Celeste, J.; Sanchez, M.; Mitchell, B.; Claus, L.; Robertson, G.; Porter, J.; Sims, G.; Hilsabeck, T.

    2016-09-01

    This paper covers the preliminary design of a radiation tolerant nanosecond-gated multi-frame CMOS camera system for use in the NIF. Electrical component performance data from 14 MeV neutron and cobalt 60 radiation testing will be discussed. The recent development of nanosecond-gated multi-frame hybrid-CMOS (hCMOS) focal plane arrays by the Ultrafast X-ray Imaging (UXI) group at Sandia National Lab has generated a need for custom camera electronics to operate in the pulsed radiation environment of the NIF target chamber. Design requirements and performance data for the prototype camera system will be discussed. The design and testing approach for the radiation tolerant camera system will be covered along with the evaluation of commercial off the shelf (COTS) electronic component such as FPGAs, voltage regulators, ADCs, DACs, optical transceivers, and other electronic components. Performance changes from radiation exposure on select components will be discussed. Integration considerations for x-ray imaging diagnostics on the NIF will also be covered.

  1. The Westinghouse AP1000 plant design: a generation III+ reactor with unique proven passive safety technology

    Energy Technology Data Exchange (ETDEWEB)

    Demetri, K. J.; Leipner, C. I.; Marshall, M. L., E-mail: demetrkj@westinghouse.com [Westinghouse Electric Company, 1000 Westinghouse Drive, Cranberry Township, PA 16066 (United States)

    2015-09-15

    The AP1000 plant is an 1100-M We pressurized water reactor with passive safety features and extensive plant simplifications and standardization that simplify construction, operation, maintenance, safety, and cost. The AP1000 plant is based on proven pressurized water reactor (PWR) technology, with an emphasis on safety features that rely solely on natural forces. These passive safety features are combined with simple, active, defense-in-depth systems used during normal plant operations which also provide the first level of defense against more probable events. This paper focuses on specific safety and licensing topics: the AP1000 plant robustness to be prepared for extreme events that may lead to catastrophic loss of infrastructure, such as the Fukushima Dai-ichi event, and the AP1000 plant compliance with the safety objectives for new plants. The first deployment of the AP1000 plant formally began in July 2007 when Westinghouse Electric Company and its consortium partner, the Shaw Group, signed contracts for four AP1000 units on coastal sites of Sanmen and Haiyang, China. Both sites have the planned ability to accommodate at least six AP1000 units; construction is largely concurrent for all four units. Additionally, the United States (U.S.) Nuclear Regulatory Commission (NRC) issued combined licenses (COLs) to allow Southern Nuclear Operating Company (SNC) and South Carolina Electric and Gas Company (SCE and G) to construct and operate AP1000 plants. Within this paper, the various factors that contribute to an unparalleled level of design, construction, delivery, and licensing certainty for any new AP1000 plant projects are described. These include: 1) How the AP1000 plant design development and reviews undertaken in the United States, China and Europe increase licensing certainty. 2) How the AP1000 passive plant robustness against extreme events that result in large loss of infrastructure further contributes to the licensing certainty in a post

  2. Training in nuclear and radiation safety in Latin American and Caribbean; Capacitacion en seguridad nuclear y radiologica en America Latina y el Caribe

    Energy Technology Data Exchange (ETDEWEB)

    Papadopulos, S.; Diaz, O.; Larcher, A.; Echenique, L.; Nicolas, R., E-mail: spapadopulos@arn.gob.ar, E-mail: odiaz@arn.gob.ar, E-mail: alarcher@arn.gob.ar, E-mail: lechenique@arn.gob.ar, E-mail: rnicolas@arn.gob.ar [Autoridad Regulatoria Nuclear (ARN), Buenos Aires (Argentina); Lombardi, R.; Quintana, G., E-mail: alombar@fi.uba, E-mail: quinta@fi.uba.ar [Universidad de Buenos Aires (FI/UBA), (Argentina). Facultad de Ingenieria

    2013-07-01

    From thirty-three years, Argentina has taken the commitment to train professionals in the field of nuclear and radiation safety for the care and protection of workers and public in general. Sponsored by the IAEA and supported by the Faculty of Engineering of the University of Buenos Aires (FIUBA), an undertaking was made to encourage the training of scientists and experts in the countries of the region in order to establish a strong safety culture in radiation in individuals and maintaining high standards of safety practices using ionizing radiation. In 2012, the Graduate Course in Radiation Protection and Safety of Radiation Sources has acquired the status of 'Specialization' of the FIUBA, a category that further hierarchies skills training in the subject. This is a highly anticipated achievement by the implications for academic institutions, national and regional level, contributing to the strengthening of the Regional Training Center for Latin America and the Caribbean, acknowledged in a long-term agreement between the IAEA and Argentina in September 2008. Due to increased demand for nuclear activity, it is important to continue and deepen further training in radiological and nuclear areas. In order to satisfy both national and regional needs a process of increase on training offer training is being carried out, under the jurisdiction frame of the Nuclear Regulatory Authority. This paper presents the achievements of the country so far as regards training of human resource in radiation protection and nuclear safety in the region and highlights the challenges ahead for the extension of the offer in education and training. (author)

  3. Value of public health and safety actions and radiation dose avoided

    Energy Technology Data Exchange (ETDEWEB)

    Baum, J.W. [Brookhaven National Lab., Upton, NY (United States)

    1994-05-01

    The values judged best to reflect the willingness of society to pay for the avoidance or reduction of risk were deduced from studies of costs of health care, transportation safety, consumer product safety, government agency actions, wage-risk compensation, consumer behavior (market) studies, and willingness-to-pay surveys. The results ranged from $1,400,000 to $2,700,000 per life saved. Applying the mean of these values ($2,100,000) and the latest risk per unit dose coefficients used by the ICRP (1991), which take into account risks to the general public, including genetic effects and nonfatal cancers, yields a value of dose avoided of $750 to $1,500 per person-cSv for public exposures. The lower value applies if adjustments are made for years of life lost per fatality. A nominal value of $1,000 per person-cSv seems appropriate in light of the many uncertainties involved in deducing these values. These values are consistent with values recommended by several European countries for individual doses in the region of 1 mSv/y (100 mrem/y). Below this dose rate, most countries have values a factor of 7 to 10 lower, based on the assumption that society is less concerned with fatality risks below about 10{sup {minus}4}/y.

  4. Monitoring human factor risk characteristics at nuclear legacy sites in northwest Russia in support of radiation safety regulation.

    Science.gov (United States)

    Scheblanov, V Y; Sneve, M K; Bobrov, A F

    2012-12-01

    This paper describes research aimed at improving regulatory supervision of radiation safety during work associated with the management of spent nuclear fuel and radioactive waste at legacy sites in northwest Russia through timely identification of employees presenting unfavourable human factor risk characteristics. The legacy sites of interest include sites of temporary storage now operated by SevRAO on behalf of Rosatom. The sites were previously operational bases for servicing nuclear powered submarines and are now subject to major remediation activities. These activities include hazardous operations for recovery of spent nuclear fuel and radioactive waste from sub-optimal storage conditions. The paper describes the results of analysis of methods, procedures, techniques and informational issues leading to the development of an expert-diagnostic information system for monitoring of workers involved in carrying out the most hazardous operations. The system serves as a tool for human factor and professional reliability risk monitoring and has been tested in practical working environments and implemented as part of regulatory supervision. The work has been carried out by the Burnasyan Federal Medical Biophysical Center, within the framework of the regulatory cooperation programme between the Federal Medical-Biological Agency of Russia and the Norwegian Radiation Protection Authority.

  5. Factors Associated With Radiation Treatment Compliance for Women With Cervical Cancer in a Safety Net Health System.

    Science.gov (United States)

    Echeverria, Alfredo; Manley, Haley; OʼDonnell, Barrett; Asper, Joshua; Bonnen, Mark; Ludwig, Michelle

    2017-09-01

    The aim of the study was to determine whether patient characteristics are associated with radiation treatment noncompliance. We retrospectively studied 244 patients with cervical cancer treated with chemoradiation between May 2006 and August 2015 at a safety net health center. Compliance with treatment was defined as missing less than 2 days of scheduled radiation. Treatment records revealed a compliance rate of 50.8% in this population. Factors associated with noncompliance were younger age (hazard ratio [HR], 1.037; P = 0.004), presence of psychiatric diagnosis (HR, 0.581; P = 0.044), and having insurance (HR, 0.484; P = 0.022). Noncompliance was associated with a decrease in disease-free survival (HR, 0.555; P = 0.042) but was not associated with overall survival. International Federation of Gynecology and Obstetrics stage was associated with detriment in overall survival on multivariate analysis (HR, 2.034; P = 0.001). Younger patients, those with psychiatric illness, and those with insurance define a group that is more likely to be noncompliant with treatment and hence may require up-front intervention to improve outcomes.

  6. Establish the Foundation of Environmental Assessment Technique in ROK via the International Environmental Modelling for Radiation Safety Managed by IAEA

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Han Soo; Choi, Y. H.; Keum, D. K.; Kang, H. S.; Ahn, S. S.; Chung, Y. S.; Lee, C. W.; Hwang, W. T.; Seo, K. S

    2005-08-15

    Tritiated water (HTO) released from the nuclear facilities can easily be absorbed by plants via their stomata and incorporated into organics by metabolic processes such as photosynthesis. Organically bound tritium (OBT) in plant cells is mostly inexchangeable and remains at harvest to contribute some to the ingestion radiation dose (Barry et al., 1999). In assessing the ingestion dose due to an accidental release of HTO, a dynamic model simulating its environmental behaviors is needed. Various types of dynamic HTO models have been developed in many different countries. Joint international researches have been conducted many times for model comparisons and validations (BIOMOVS II, 1996a, 1996b). In 2003, however, with the understanding of an insufficiency in the validation test, the IAEA started on a joint international research program for the validation of environmental models (EMRAS : Environmental Modelling for Radiation Safety) as a successor to the BIOMASS (2001). The KAERI submitted 'a scenario of an acute soybean exposure to HTO' to the Tritium Working Group (Theme 1) in the EMRAS program. It was accepted as Task 2 of the working group. This report is the result of a joint research for the KAERI scenario carried out by the EMRAS tritium working group with the KAERI playing a role of a coordinator.

  7. Progress report: nuclear safety and radiation protection in France in 2005; Rapport annuel: la surete nucleaire et la radioprotection en France en 2005

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-07-01

    The Asn (Nuclear safety authority) considers that 2005 was a satisfactory year in terms of nuclear safety and radiation protection. However, further progress can and must be made. 2005 was a year of great progress for the Asn as it consolidated its organisation and working methods, in accordance with the 2005-2007 strategic plan it set for itself. The Asn continued progress in the field of radiation protection has given rise to various new regulations to improve the legislative and regulatory framework in this area. 2005 was marked by significant progress in the process of harmonizing national nuclear safety policies Against a backdrop of the preparation of a bill on management of radioactive materials and waste, to be presented to Parliament in March 2006, 2005 was a year of important milestones. The Asn control activities encompass the following seven areas: development of general regulations for nuclear safety and radiation protection; management of individual authorization requests and receipt of declarations; inspection of nuclear activities; organisation of radiological surveillance of individuals and of the environment; preparation for management of emergency situations and implementation if necessary; contribution to public information on nuclear safety and radiation protection; determination of the French position within international community. Main topics in 2005: government bill on transparency and security in the nuclear field; the challenges and ambitions of the Asn; controlling exposure to radon; EPR Reactor Project Safety; working towards a law on radioactive waste in 2006; I.R.R.T.: an international audit of Asn in 2006; harmonization of nuclear safety in Europe; Chernobyl: what has been achieved over the past 20 years; informing the Public; internal authorizations. (N.C.)

  8. The Radiation Tolerant Electronics for the LHC Cryogenic Controls: Basic Design and First Operational Experience

    CERN Document Server

    Casas-Cubillos, J; Rodríguez-Ruiz, M A

    2008-01-01

    The LHC optics is based in the extensive use of superconducting magnets covering 23 km inside the tunnel. The associated cryogenic system for keeping the magnets in nominal conditions is hence distributed all around the 27 km LHC tunnel and the cryogenic instrumentation submitted to the LHC radiation environment is composed of about 18’000 sensors and actuators. Radiation Tolerant (RadTol) electronics was designed and procured in order to keep the signals integrity against electromagnetic interference and to reduce cabling costs required in case of sending the analog signals into the 30 radiation protected areas. This paper presents the basic design, the qualification of the main RadTol components and the first operational results.

  9. Design of Pass Band Filter in Hybrid Architecture Planar/Non-Radiative Dielectric Waveguide Integration Technology

    Directory of Open Access Journals (Sweden)

    Harizi Hanen

    2012-01-01

    Full Text Available Problem statement: The expansion of RF, microwave and millimeter devices has revolutionized today’s ommunication and sensor systems. Low-cost, high-performance and mass producible millimeter wave technologies are vital for commercial broadband systems. Challenging issues are commonly faced in the design of low-loss integrated circuits for example high-Q band pass filter, which the planar technique is fundamentally limited in performance. Approach: In this study, we present a design of a nonradiative dielectric waveguide band pass filter based on hybrid architecture of micro strip line and non-radiative dielectric waveguide. Results: The simulation with High Frequency Structure Simulator (HFSS three dimensional analyses is presented. Conclusion: The non radiative dielectric resolves most of the drawbacks of dielectric waveguide in connection with the radiation loss."

  10. Load assumption for fatigue design of structures and components counting methods, safety aspects, practical application

    CERN Document Server

    Köhler, Michael; Pötter, Kurt; Zenner, Harald

    2017-01-01

    Understanding the fatigue behaviour of structural components under variable load amplitude is an essential prerequisite for safe and reliable light-weight design. For designing and dimensioning, the expected stress (load) is compared with the capacity to withstand loads (fatigue strength). In this process, the safety necessary for each particular application must be ensured. A prerequisite for ensuring the required fatigue strength is a reliable load assumption. The authors describe the transformation of the stress- and load-time functions which have been measured under operational conditions to spectra or matrices with the application of counting methods. The aspects which must be considered for ensuring a reliable load assumption for designing and dimensioning are discussed in detail. Furthermore, the theoretical background for estimating the fatigue life of structural components is explained, and the procedures are discussed for numerous applications in practice. One of the prime intentions of the authors ...

  11. Design, development, fabrication, and safety-of-flight testing of a panoramic night vision goggle

    Science.gov (United States)

    Jackson, Timothy W.; Craig, Jeffrey L.

    1999-07-01

    A novel approach to significantly increasing the field of view (FOV) of night vision goggles (NVGs) has been developed. This approach uses four image intensifier tubes instead of the usual two to produce a 100 degree wide FOV. A conceptual demonstrator device was fabricated in November 1995 and limited flight evaluations were performed. Further development of this approach continues with eleven advanced technology demonstrators delivered in March 1999 that feature five different design configurations. Some of the units will be earmarked for ejection seat equipped aircraft due to their low profile design allowing the goggle to be retained safely during and after ejection. Other deliverables will be more traditional in design approach and lends itself to transport and helicopter aircraft as well as ground personnel. Extensive safety-of-flight testing has been accomplished as a precursor to the F-15C operational utility evaluation flight testing at Nellis AFB that began in March 1999.

  12. Feasibility and safety of outpatient brachytherapy in 37 patients with brain tumors using the GliaSite Radiation Therapy System.

    Science.gov (United States)

    Chino, Kazumi; Silvain, Daniel; Grace, Ana; Stubbs, James; Stea, Baldassarre

    2008-07-01

    Temporary, low dose rate brachytherapy to the margins of resected brain tumors, using a balloon catheter system (GliaSite Radiation Therapy System) and liquid I-125 radiation source (Iotrex), began in 2002 at the University of Arizona Medical Center. Initially, all patients were treated on an inpatient basis. For patient convenience, we converted to outpatient therapy. In this article we review the exposure data and safety history for the 37 patients treated as outpatients. Proper patient selection and instruction is crucial to having a successful outpatient brachytherapy program. A set of evaluation criteria and patient instructions were developed in compliance with the U.S. Nuclear Regulatory Commission's document NUREG-1556 Volume 9 (Appendix U) and Arizona State Nuclear regulatory guidelines, which specify acceptable exposure rates for outpatient release in this setting. Of the 37 patients monitored, 26 patients were treated for recurrent glioblastoma multiforme (GBM), six for primary GBM, and five for metastatic brain tumors. All 37 patients and their primary caregivers gave signed agreement to follow a specific set of instructions and were released for the duration of brachytherapy (3-7 days). The typical prescription dose was 60 Gy delivered at 0.5 cm from the balloon surface. Afterloaded activities in these patients ranged from 90.9 to 750.0 mCi and measured exposure rates at 1 m from the head were less than 14 mR/h. The mean exposure to the caretaker measured by personal radiation Landauer Luxel + whole body dosimeters for 25 caretakers was found to be 9.6 mR, which was significantly less than the mean calculated exposure of 136.8 mR. For properly selected patients, outpatient brachytherapy is simple and can be performed within established regulatory guidelines.

  13. Design and Fabrication of a Composite Morphing Radiator Panel Using High Conductivity Fibers

    Science.gov (United States)

    Wescott, Matthew T.; McQuien, J. Scott; Bertagne, Christopher L.; Whitcomb, John D.; Hart, Darren J.; Erickson, Lisa R.

    2017-01-01

    Upcoming crewed space missions will involve large internal and external heat loads and require advanced thermal control systems to maintain a desired internal environment temperature. Radiators with at least 12:1 turndown ratios (the ratio between the maximum and minimum heat rejection rates) will be needed. However, current technologies are only able to achieve turndown ratios of approximately 3:1. A morphing radiator capable of altering shape could significantly increase turndown capabilities. Shape memory alloys offer qualities that may be well suited for this endeavor; their temperature-dependent phase changes could offer radiators the ability to passively control heat rejection. In 2015, a morphing radiator prototype was constructed and tested in a thermal vacuum environment, where it successfully demonstrated the morphing behavior and variable heat rejection. Newer composite prototypes have since been designed and manufactured using two distinct types of SMA materials. These models underwent temperature cycling tests in a thermal vacuum chamber and a series of fatigue tests to characterize the lifespan of these designs. The focus of this paper is to present the design approach and testing of the morphing composite facesheet. The discussion includes: an overall description of the project background, definition of performance requirements, composite materials selection, use of analytic and numerical design tools, facesheet fabrication, and finally fatigue testing with accompanying results.

  14. Low-cost cadmium zinc telluride radiation detectors based on electron-transport-only designs

    Energy Technology Data Exchange (ETDEWEB)

    B. A. Brunett; J. C. Lund; J. M. Van Scyoc; N. R. Hilton; E. Y. Lee; R. B. James

    1999-01-01

    The goal of this project was to utilize a novel device design to build a compact, high resolution, room temperature operated semiconductor gamma ray sensor. This sensor was constructed from a cadmium zinc telluride (CZT) crystal. It was able to both detect total radiation intensity and perform spectroscopy on the detected radiation. CZT detectors produced today have excellent electron charge carrier collection, but suffer from poor hole collection. For conventional gamma-ray spectrometers, both the electrons and holes must be collected with high efficiency to preserve energy resolution. The requirement to collect the hole carriers, which have relatively low lifetimes, limits the efficiency and performance of existing experimental devices. By implementing novel device designs such that the devices rely only on the electron signal for energy information, the sensitivity of the sensors for detecting radiation can be increased substantially. In this report the authors describe a project to develop a new type of electron-only CZT detector. They report on their successful efforts to design, implement and test these new radiation detectors. In addition to the design and construction of the sensors the authors also report, in considerable detail, on the electrical characteristics of the CZT crystals used to make their detectors.

  15. Preliminary Safety Design Report for Remote Handled Low-Level Waste Disposal Facility

    Energy Technology Data Exchange (ETDEWEB)

    Timothy Solack; Carol Mason

    2012-03-01

    A new onsite, remote-handled low-level waste disposal facility has been identified as the highest ranked alternative for providing continued, uninterrupted remote-handled low-level waste disposal for remote-handled low-level waste from the Idaho National Laboratory and for nuclear fuel processing activities at the Naval Reactors Facility. Historically, this type of waste has been disposed of at the Radioactive Waste Management Complex. Disposal of remote-handled low-level waste in concrete disposal vaults at the Radioactive Waste Management Complex will continue until the facility is full or until it must be closed in preparation for final remediation of the Subsurface Disposal Area (approximately at the end of Fiscal Year 2017). This preliminary safety design report supports the design of a proposed onsite remote-handled low-level waste disposal facility by providing an initial nuclear facility hazard categorization, by discussing site characteristics that impact accident analysis, by providing the facility and process information necessary to support the hazard analysis, by identifying and evaluating potential hazards for processes associated with onsite handling and disposal of remote-handled low-level waste, and by discussing the need for safety features that will become part of the facility design.

  16. Conceptual Safety Design Report for the Remote Handled Low-Level Waste Disposal Facility

    Energy Technology Data Exchange (ETDEWEB)

    Boyd D. Christensen

    2010-02-01

    A new onsite, remote-handled LLW disposal facility has been identified as the highest ranked alternative for providing continued, uninterrupted remote-handled LLW disposal for remote-handled LLW from the Idaho National Laboratory and for spent nuclear fuel processing activities at the Naval Reactors Facility. Historically, this type of waste has been disposed of at the Radioactive Waste Management Complex. Disposal of remote-handled LLW in concrete disposal vaults at the Radioactive Waste Management Complex will continue until the facility is full or until it must be closed in preparation for final remediation of the Subsurface Disposal Area (approximately at the end of Fiscal Year 2017). This conceptual safety design report supports the design of a proposed onsite remote-handled LLW disposal facility by providing an initial nuclear facility hazard categorization, by identifying potential hazards for processes associated with onsite handling and disposal of remote-handled LLW, by evaluating consequences of postulated accidents, and by discussing the need for safety features that will become part of the facility design.

  17. New geometric design consistency model based on operating speed profiles for road safety evaluation.

    Science.gov (United States)

    Camacho-Torregrosa, Francisco J; Pérez-Zuriaga, Ana M; Campoy-Ungría, J Manuel; García-García, Alfredo

    2013-12-01

    To assist in the on-going effort to reduce road fatalities as much as possible, this paper presents a new methodology to evaluate road safety in both the design and redesign stages of two-lane rural highways. This methodology is based on the analysis of road geometric design consistency, a value which will be a surrogate measure of the safety level of the two-lane rural road segment. The consistency model presented in this paper is based on the consideration of continuous operating speed profiles. The models used for their construction were obtained by using an innovative GPS-data collection method that is based on continuous operating speed profiles recorded from individual drivers. This new methodology allowed the researchers to observe the actual behavior of drivers and to develop more accurate operating speed models than was previously possible with spot-speed data collection, thereby enabling a more accurate approximation to the real phenomenon and thus a better consistency measurement. Operating speed profiles were built for 33 Spanish two-lane rural road segments, and several consistency measurements based on the global and local operating speed were checked. The final consistency model takes into account not only the global dispersion of the operating speed, but also some indexes that consider both local speed decelerations and speeds over posted speeds as well. For the development of the consistency model, the crash frequency for each study site was considered, which allowed estimating the number of crashes on a road segment by means of the calculation of its geometric design consistency. Consequently, the presented consistency evaluation method is a promising innovative tool that can be used as a surrogate measure to estimate the safety of a road segment.

  18. Training Programs on Radiological Safety for users of Ionizing Radiations in Peru; Programas de formacion en proteccion radiologica para usuarios de radiaciones ionizantes en el Peru

    Energy Technology Data Exchange (ETDEWEB)

    Medina Gironzini, E.

    2003-07-01

    In Peru, people who work with ionizing radiations must have an authorization (Individual License) as established in the Radiological Safety Regulations, which are the mandatory rules. The Technical Office of the National Authority (OTAN), which is the technical organ of the Peruvian Institute of Nuclear Energy (IPEN) in charge of controlling radiations within the country, grants the authorization after the candidate demonstrates that he/she knows the specific use of the technique using radiations, as well as the aspects related to safety and radiological protection. Since it was created in 1972, the Superior Center of Nuclear Studies (VSEN) from IPEN has carried out different training courses so that people can work safety with ionizing radiations in medicine, industry and investigation. The analysis of the radiological safety programs carried out by CSEN during the last 30 years, which allowed the training of more than 2200 people in the country and, at the same time, made possible the securing of the respective Individual License, is presented in this work. The courses, nuclear medicine, radiotherapy, industrial radiography, nuclear gauges gamma irradiator, etc..., are part of the continuous education program of CSEN. (Author)

  19. An evaluation of two conducted electrical weapons and two probe designs using a swine comparative cardiac safety model.

    Science.gov (United States)

    Dawes, Donald Murray; Ho, Jeffrey D; Moore, Johanna C; Miner, James R

    2013-09-01

    Despite human laboratory and field studies that have demonstrated a reasonable safety profile for TASER brand conducted electrical weapons (CEW), the results of some swine studies and arrest related deaths temporal to the use of the CEWs continue to raise questions regarding cardiac safety. TASER International, Inc., has released a new CEW, the TASER X2, touted to have a better safety profile than its long-standing predecessor, the TASER X26. We have developed a model to assess the relative cardiac safety of CEWs and used it to compare the TASER X2 and the TASER X26. This safety model was also used to assess the relative safety of an experimental probe design as compared to the standard steel probe. Our results suggest that the TASER X2 has an improved safety margin over the TASER X26. The new probe design also has promise for enhanced cardiac safety, although may have some disadvantages when compared to the existing design which would make field use impractical.

  20. ASN annual report 2007 - ASN report abstracts on the state of Nuclear Safety and Radiation Protection in France in 2007; ASN rapport annuel 2007

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2008-07-01

    The 2007 annual report of the French nuclear safety authority (ASN) presents the highlights of the year in the domain of nuclear safety and radiation protection in France. The year 2007 was marked by the implementation of a new legislative and regulatory framework created by the 13 June 2006 Act on transparency and security in the nuclear field (TSN) and the 28 June Act on the sustainable management of radioactive materials and wastes. As in the previous two years, the year was relatively satisfactory from the nuclear safety viewpoint and slightly less so with regard to small-scale nuclear activities. For two years now, the medical field has been marked by the declaration to ASN of a number of serious radiotherapy accidents which have led to several deaths or the need for extensive surgery. The following main topics are reviewed in the document: 1 - the decrees implementing the 'TSN' act and the 'Waste' act; 2 - the new ASN, one year on; 3 - ASN regulatory actions in the field of radiotherapy; 4 - regulation of new installations; 5 - the key issues for regulation of existing installations; 6 - nuclear safety and radiation protection research; 7 - policy for management of the post-accident phase of a radiological emergency; 8 - sites and soils polluted by radioactive materials; 9 - international harmonization of nuclear safety and radiation protection.