STAMINA OF A GASKETED BOLTED FLANGED PIPE JOINT UNDER DYNAMIC LOADING

Directory of Open Access Journals (Sweden)

Muhammad Abid

2016-11-01

Full Text Available Gasketed bolted flange joints are the most critical components in pipelines for their sealing and strength under operating conditions. Most of the work available in literature is under static loading, whereas in industry, cyclic loads are applied due to the vibrating machinery such as motors, pumps, sloshing in offshore applications and in the ships etc. In this study a three dimensional finite element analysis of a gasketed joint is carried out using a spiral wound gasket under bolt up and dynamic operating conditions (internal pressure, axial and bending singly and in combination. The cyclic axial loads are concluded relatively more challenging for both the sealing and strength of the joint. Higher magnitudes of loads and frequencies are also observed more challenging to the joints performance.

A 3D regression surface for the room temperature tightness gasket data reduction and bolt load design

International Nuclear Information System (INIS)

Jolly, Pascal; Marchand, Luc

2008-01-01

The purpose of the present work is to propose a new approach for modelling the tightness behaviour of the gaskets used in bolted flange joints. This new approach consists of developing a mathematical model for a three-dimensional (3D) representation of the gasket tightness performance. Rather than considering a 2D graph for characterizing the complete gasket behaviour, a third axis is added to the S g vs. Tp plot to dissociate the unloading cycles from initial gasket tightening. This leads to the definition of a surface that is represented by a simple polynomial equation that contains six coefficients that are determined by a simple regression calculation. In the first part of the paper, the new approach is tested through a database of 406 room temperature tightness (ROTT) tests performed on different gasket styles. Then, a statistical analysis of the predictions made with the new model demonstrates its ability to predict gasket leak rates much more accurately than it was previously possible with the gasket constants derived from the ROTT Draft 9 or 10 methods. It is also demonstrated that the new approach can be used to model successfully complex gasket behaviours such as the tightness hardening phenomenon. Secondly, the effect of gas pressure change on the leak rate is analysed. It turns out that at high gasket stresses, the actual scheme of the ROTT tests may not allow enough time for reaching a stabilized leak rate value because of a transitory time effect in the porous structure of gaskets. Then, in order to evaluate the characteristic waiting period (dwell time) before a stabilized flow rate is achieved following a change in the gas pressure level, a simple phenomenological analysis of the flow is performed

Acid Aging Effects on Surfaces of PTFE Gaskets Investigated by Fourier Transform Infrared Spectroscopy

Directory of Open Access Journals (Sweden)

L. Giorgini

2016-09-01

Full Text Available This paper investigates the effect of a prolonged acid and thermal attack, on the surface of PTFE by Fourier Transform Infrared Micro-Spectroscopy (FT-IR. The materials are commercialized by two alternative producers in form of Teflon tapes. These tapes are installed in process plants where tires moulds are cleaned inside a multistage ultrasonic process. In these cases, Teflon tapes, having a role of gaskets, show inexplicably phenomena of degradation in relatively short operation periods. Even considering that these gaskets are exposed to the combined effect of ultrasonic waves, temperature, humidity and acid attack, the PTFE properties of resistance nominally exclude the possibility of these severe erosion phenomena. An interesting explanation can be related to the potential presence in the cleaning solution, mainly based on sulfamic acid, of highly reactive chemical compounds, as chlorides and fluorides, originated by the disaggregation of elements from the tire composition and/or additives used as processing aids and/or by catalytic effect generated by fluorine produced by PTFE degradation. In general, up to 300 different chemical elements, both organic and inorganic, natural and synthetic, are merged in a tire. Since this composition is practically unknown, especially regarding additives and “unusual elements”, representing a secrecy of each tire manufactures, it is really complex to define the chemical composition of the cleaning solution with an appropriate precision. As a consequence, the gaskets have been treated with different mixtures of acids in the way to combine a larger range of possibilities. Thus, the FT-IR experimental characterization of PTFE surface properties followed an appropriate accelerated aging, aiming at actuating the specific mechanics of wearing as in industrial use. The different acid treatments adopted for accelerating the aging of gaskets have highlighted the different behaviour of the PTFE matrix, but

The comparison of System 1000 analysis and type testing for neoprene gasket environmental qualification

International Nuclear Information System (INIS)

Park, Kyung Heum; Kim, Jong Seok; Jeong, Sun Chul; Jang, Kyung Nam; Hwang, Sung Phil

2010-01-01

The typical environmental qualification is to ensure that equipment will operate on demand to meet system performance requirements during normal and abnormal service conditions. There are four environmental qualification methods, type testing, operating experience, analysis and combined method. Generally, the American EQ do not contain the mechanical equipment like pumps and valves in their EQ equipment list because their EQ standard 10CFR50.49 limits EQ equipment as electrical equipment. On the other hand, Canadian EQ contain the mechanical equipment like pumps and valves in their EQ components list, Canadians usually call American 'equipment' as 'components', because their EQ standard CSA N290.13-05 do not limits EQ equipment as electrical equipment. System 1000 program is typical Canadian EQ analysis method using mathematical modeling and comparison with established engineering information and manufacturers' data. Most of Canadian nuclear power utilities like NB Power, Hydro Quebec and OPG use the System 1000 program to evaluate the design life for their EQ components. To qualify a pump, I had to list all the non-metallic parts in the pump and found there are lots of gaskets made by neoprene material. I tried to qualify these neoprene gaskets by analysis using System 1000 program and by type testing. In this paper, I'd like to introduce the qualification results of neoprene gasket both type testing and analysis using System 1000 program

The safe transport of radioactive materials

CERN Document Server

Gibson, R

1966-01-01

The Safe Transport of Radioactive Materials is a handbook that details the safety guidelines in transporting radioactive materials. The title covers the various regulations and policies, along with the safety measures and procedures of radioactive material transport. The text first details the 1963 version of the IAEA regulation for the safe transport of radioactive materials; the regulation covers the classification of radionuclides for transport purposes and the control of external radiation hazards during the transport of radioactive materials. The next chapter deals with concerns in the im

Non-linear finite element modelling and analysis of the effect of gasket creep-relaxation on circular bolted flange connections

International Nuclear Information System (INIS)

Luyt, P.C.B.; Theron, N.J.; Pietra, F.

2017-01-01

It is well known that gasket creep-relaxation results in a reduction of contact pressure between the surface of a gasket and the face of a flange over an extended period of time. This reduction may result in the subsequent failure of the circular bolted flange connection due to leakage. In this paper a pair of flat and raised face integral flanges, PN 10 DN 50 (in accordance with the European EN 1092-1 standard), with non-asbestos compressed fibre ring gaskets with aramid and a nitrile rubber binder were considered. Finite element modelling and analyses were done, for both the circular bolted flange configurations, during the seating condition. The results of the finite element analyses were experimentally validated. It was found that the number of bolt tightening increments as well as the time between the bolt tightening increments had a significant impact on the effect which gasket creep-relaxation had after the seating condition. An increase in either the number of bolting increments or the time between the bolting increments will reduce the effect which gasket creep-relaxation has once the bolts had been fastened. Based on these results it is possible to develop an optimisation scheme to minimize the effect which gasket creep-relaxation has on the contact pressure between the face of the flange and the gasket, after seating, by either increasing or decreasing the number of bolt tightening increments or the time between the bolt tightening increments. - Highlights: • Number of bolt tightening increments and time between bolt tightening increments had significant impact on effect of gasket creep-relaxation after the seating condition. • Impact of gasket creep-relaxation during seating and operating phases investigated by means of finite element analysis and experimentally verified. • Possible to develop optimisation scheme to minimize effect ofh gasket creep-relaxation on contact pressure between flange face and gasket. • Knowing the contact pressure is

Relaxation behaviour of gasketed joints during assembly using finite ...

Indian Academy of Sciences (India)

Faculty of Mechanical Engineering, Ghulam Ishaq Khan (GIK) Institute of ... Bolt scatter, bolt bending, joint relaxation and gasket stress variation are concluded the main .... In the present work, following two ..... American Society of Mech.

Description of gasket failure in a 7 cell PEMFC stack

Energy Technology Data Exchange (ETDEWEB)

Husar, Attila; Serra, Maria [Institut de Robotica i Informatica Industrial, Parc Tecnologic de Barcelona, Edifici U, C. Llorens i Artigas, 4-6, 2a Planta, 08028 Barcelona (Spain); Kunusch, Cristian [Laboratorio de Electronica Industrial Control e Instrumentacion, Facultad de Ingenieria, UNLP (Argentina)

2007-06-10

This article presents the data and the description of a fuel cell stack that failed due to gasket degradation. The fuel cell under study is a 7 cell stack. The unexpected change in several variables such as temperature, pressure and voltage indicated the possible failure of the stack. The stack was monitored over a 6 h period in which data was collected and consequently analyzed to conclude that the fuel cell stack failed due to a crossover leak on the anode inlet port located on the cathode side gasket of cell 2. This stack failure analysis revealed a series of indicators that could be used by a super visional controller in order to initiate a shutdown procedure. (author)

Nuclear power plant accident simulations of gasket materials under simultaneous radiation plus thermal plus mechanical stress conditions

International Nuclear Information System (INIS)

Gillen, K.T.; Malone, G.M.

1997-07-01

In order to probe the response of silicone door gasket materials to a postulated severe accident in an Italian nuclear power plant, compression stress relaxation (CSR) and compression set (CS) measurements were conducted under combined radiation (approximately 6 kGy/h) and temperature (up to 230 degrees C) conditions. By making some reasonable initial assumptions, simplified constant temperature and dose rates were derived that should do a reasonable job of simulating the complex environments for worst-case severe events that combine overall aging plus accidents. Further simplification coupled with thermal-only experiments allowed us to derive thermal-only conditions that can be used to achieve CSR and CS responses similar to those expected from the combined environments that are more difficult to simulate. Although the thermal-only simulations should lead to sealing forces similar to those expected during a severe accident, modulus and density results indicate that significant differences in underlying chemistry are expected for the thermal-only and the combined environment simulations. 15 refs., 31 figs., 15 tabs

Replacement of thermal column elastomeric gasket in pool type research reactors based on ageing and radiation degradation

International Nuclear Information System (INIS)

Garai, S.K.

2006-01-01

Pool type research reactors are designed with Thermal column facilities to irradiate samples at different flux levels of thermal neutrons. The sealing of demineralised pool water between stainless steel lined pool wall and the Aluminium Thermal column plate is achieved by an elastomeric gasket. The gasket joint is subjected to pool water temperature ranging from 25degC to 45degC and radiation field of the order of 104 -106 R/hr. The gasket loses its sealing properties due to ageing and radiation degradation after a few years, leading to the leakage and loss of the pool water. Though degradation of the gasket is, generally, predictable, some amount of uncertainty always remains in the leakage rate. The paper describes the study of a few elastomers in radiation environment and replacement of the Thermal column gasket of a swimming pool type research reactor. It includes the details of features like planning and scheduling, the actual sequential execution of the job, various problems encountered and corrective measures applied, engineering and radiological safety measures adopted, development of remote tools, disassembly and reassembly procedure and finally satisfactory completion of the site job in high radiation environment with minimum time and man rem consumption. (author)

Safe transport of radioactive material

International Nuclear Information System (INIS)

1994-01-01

Delivering radioactive material to where it is needed is a vital service to industry and medicine. Millions of packages are shipped all over the world by all modes of transport. The shipments pass through public places and must meet stringent safety requirements. This video explains how radioactive material is safely transported and describes the rules that carriers and handlers must follow

Assessment of airborne asbestos exposure during the servicing and handling of automobile asbestos-containing gaskets.

Science.gov (United States)

Blake, Charles L; Dotson, G Scott; Harbison, Raymond D

2006-07-01

Five test sessions were conducted to assess asbestos exposure during the removal or installation of asbestos-containing gaskets on vehicles. All testing took place within an operative automotive repair facility involving passenger cars and a pickup truck ranging in vintage from late 1960s through 1970s. A professional mechanic performed all shop work including engine disassembly and reassembly, gasket manipulation and parts cleaning. Bulk sample analysis of removed gaskets through polarized light microscopy (PLM) revealed asbestos fiber concentrations ranging between 0 and 75%. Personal and area air samples were collected and analyzed using National Institute of Occupational Safety Health (NIOSH) methods 7400 [phase contrast microscopy (PCM)] and 7402 [transmission electron microscopy (TEM)]. Among all air samples collected, approximately 21% (n = 11) contained chrysotile fibers. The mean PCM and phase contrast microscopy equivalent (PCME) 8-h time weighted average (TWA) concentrations for these samples were 0.0031 fibers/cubic centimeters (f/cc) and 0.0017 f/cc, respectively. Based on these findings, automobile mechanics who worked with asbestos-containing gaskets may have been exposed to concentrations of airborne asbestos concentrations approximately 100 times lower than the current Occupational Safety and Health Administration (OSHA) Permissible Exposure Limit (PEL) of 0.1 f/cc.

An evaluation of the ENDF/GASKET model for thermal neutron scattering in heavy water

International Nuclear Information System (INIS)

Abbate, M.J.; Antunez, H.M.

1977-06-01

The ENDF/GASKET model for computing thermal neutron scattering was selected for studies undertaken with the purpose of getting thoroughly acquainted with the behavior of the heavy water as a moderator. As a first step in its evaluation, the scattering law S(α,β) was computed with ENDF/GASKET. A comparison of the values so obtained with others previously measured or computed showed that the model is not completely satisfactory in this respect. This is attributed to coherent scattering not included in the model and to the need of improving its frequency spectrum. Any way, the experimental values show serious descrepancies and it is difficult to reach definitive conclusions. The Legendre moments of the double differential cross section and its microscopic values were also computed. As it was found by other authors, the incoherent approximation of ENDF/GASKET results in a drastic departure from the measured total cross section below 0,006 eV. In addition, the discrepancies between measured and calculated average μ, might also imply that the coherence effects are appreciable at higher energies. Also decay constance and diffusion parameters were computed for D 2 O (100%), and these agree well with values of other sources. The measurement and computation of neutron spectra in heavy water is presently intented for the sake of completing evaluation. So far two alternatives are foreseen for further work: the improvement of ENDF/GASKET, or the evaluation of the more recent Jarvis model. (author) [es

Procedures for the Safe Transport of Radioactive Material

Energy Technology Data Exchange (ETDEWEB)

Kim, Jang Lyul; Chung, K. K.; Lee, J. I.; Chang, S. Y.; Lee, T. Y

2007-11-15

This technical report describes the procedure and work responsibility along with the regulation and standard necessary for the safe transport of radioactive or contaminated materials. This report, therefore, can be effectively used to secure the public safety as well as to prevent the disastrous event which might be resulted from the transport process of radioactive materials by establishing a procedure and method on the safe packing, handling and transport of radioactive materials.

Functional properties of poly(tetrafluoroethylene) (PTFE) gasket working in nuclear reactor conditions

Science.gov (United States)

Wyszkowska, Edyta; Leśniak, Magdalena; Kurpaska, Lukasz; Prokopowicz, Rafal; Jozwik, Iwona; Sitarz, Maciej; Jagielski, Jacek

2018-04-01

In this study structural and nanomechanical properties of polytetrafluoroethylene (PTFE) used as a gasket in the nuclear reactor have been deeply investigated. In order to reveal structural changes caused by long-term pressure, temperature and irradiation (possibly neutron and gamma), methods such as SEM, X-ray diffraction and Raman Spectroscopy have been used. Nanomechanical properties such as Young Modulus and hardness were investigated by means of the nanoindentation technique. Presented study confirmed the influence of working (radiative) environment on the functional properties of PTFE. The results of Raman spectroscopy and X-ray diffraction techniques revealed shift of the major band positions and band intensities increase. Moreover, changes of hardness and Young Modulus values of the irradiated material with respect to the virgin specimen have been recorded. This phenomenon can be attributed to the modifications in crystallinity of the material. Presented work suggest that morphology of the irradiated material altered from well-ordered parallel fibers to more dense and thicker ones.

Safe transport of radioactive material

International Nuclear Information System (INIS)

1990-01-01

Recently the Agency redefined its policy for education and training in radiation safety. The emphasis is now on long-term strategic planning of general education and training programmes. In line with this general policy the Agency's Standing Advisory Group for the Safe Transport of Radioactive Material (SAGSTRAM) in its 7th meeting (April 1989) agreed that increased training activity should be deployed in the area of transport. SAGSTRAM specifically recommended the development of a standard training programme on this subject area, including audio-visual aids, in order to assist Member States in the implementation of the Agency's Regulations for the Safe Transport of Radioactive Material. This training programme should be substantiated by a biennial training course which is thought to be held either as an Interregional or a Regional Course depending on demand. This training manual, issued as a first publication in the Training Course Series, represents the basic text material for future training courses in transport safety. The topic areas covered by this training manual and most of the texts have been developed from the course material used for the 1987 Bristol Interregional Course on Transport Safety. The training manual is intended to give guidance to the lecturers of a course and will be provided to the participants for retention. Refs, figs and tabs

Regulations for the safe transport of radioactive material

International Nuclear Information System (INIS)

1995-01-01

Regulations and rules for the safe transport of radioactive materials by all kinds of conveyance are offered. Different types of packages and the conditions associated with the methods of safe packaging are given

DEVELOPMENT OF REMOTE HANFORD CONNECTOR GASKET REPLACEMENT TOOLING FOR THE SAVANNAH RIVER SITE'S DEFENSE WASTE PROCESSING FACILITY

International Nuclear Information System (INIS)

Krementz, D

2007-01-01

The Savannah River Site's (SRS) Defense Waste Processing Facility (DWPF) requested development of tooling for remote replacement of gaskets in mechanical Hanford connectors. The facility has compressed air supply, two master-slave manipulators (MSM's) and a lightweight robotic arm for operation of the remote tools. The Savannah River National Laboratory (SRNL) developed and tested multiple tools to perform the gasket replacement tasks. Separate pneumatic snap-ring removal tools that use the connector skirt as a reaction surface were developed for removal of the snap ring and spent gasket on both vertical and horizontal Hanford connectors. A pneumatic tool that clamps and centers on the jumper pipe ID was developed to simultaneously install the new gasket and snap ring. A pneumatic snap-ring-loading tool was developed that compresses the snap ring and places it in a groove in the installation tool. All of the tools are located on a custom work table with a pneumatic valve station that directs compressed air to the desired tool and vents the tools as needed. The entire system has been successfully tested using MSM's to manipulate the various tools. Deployment of the entire system is expected during FY08. The Hanford connector gasket replacement tooling has been successfully tested using MSM's to manipulate the various tools. Nitric acid is used in many of the decontamination processes performed in the REDC, where the tooling will be deployed. Although most of the tool components were fabricated/purchased with nitric acid and radioactive service in mind, some of the prototype parts must be replaced with parts that are more compatible with nitric acid/radioactive service. Several modifications to the various tools are needed to facilitate maintenance and replacement of failed components. Development of installation tools for replacement of 1-inch, 2-inch and multi-hole gaskets is being considered. Deployment of the existing system in the DWPF REDC is expected during FY

Safe transport of radioactive materials in Egypt

International Nuclear Information System (INIS)

El-Shinawy, R.M.K.

1994-01-01

In Egypt the national regulations for safe transport of radioactive materials (RAM) are based on the International Atomic Energy Agency (IAEA) regulations. In addition, regulations for the safe transport of these materials through the Suez Canal (SC) were laid down by the Egyptian Atomic Energy Authority (EAEA) and the Suez Canal Authority (SCA). They are continuously updated to meet the increased knowledge and the gained experience. The technical and protective measures taken during transport of RAM through SC are mentioned. Assessment of the impact of transporting radioactive materials through the Suez Canal using the INTERTRAN computer code was carried out in cooperation with IAEA. The transported activities and empty containers, the number of vessels carrying RAM through the canal from 1963 and 1991 and their nationalities are also discussed. The protective measures are mentioned. A review of the present situation of the radioactive wastes storage facilities at the Atomic Energy site at Inshas is given along with the regulation for safe transportation and disposal of radioactive wastes. (Author)

Safe transport of radioactive material. Second edition

International Nuclear Information System (INIS)

1991-01-01

The transport of radioactive material embraces the carriage of radioisotopes for industrial, medical and research uses, and the movement of waste, in addition to consignments of nuclear fuel cycle material. It has been estimated that between eighteen and thirty-eight million package shipments take place each year. On the recommendation of the Standing Advisory Group on the Safe Transport of Radioactive Material (SAGSTRAM), which enjoys wide representations from the Agency's Member States and international organizations, the Secretariat is preparing a training kit comprising this training manual and complementary visual aids. The kit is intended to be the basis for an extensive course on the subject and can be used in whole or in part for inter-regional, regional and even national training purposes. Member States can thus benefit from the material either through training courses sponsored by the Agency, or, alternatively, organized by themselves. As a step towards achieving that goal, the current training manual was compiled using material from the first Inter-Regional Training Course on the Safe Transport of Radioactive material that was held in co-operation with the Nuclear Power Training Centre of the then Central Electricity Generating Board at Bristol, United Kingdom. This Manual was initially published in 1990. On the recommendation of the Agency's Standing Advisory Group on the Safe Transport of Radioactive Material (SAGSTRAM), the Manual has since been expanded and updated in time for the second Inter-Regional Training Course, that will in 1991 similarly be held in Bristol. Refs, figs, tabs

The safe transport of radioactive materials

International Nuclear Information System (INIS)

Messenger, W. de L.M.

1979-02-01

The hazards of radioactive materials in transport are surveyed. The system whereby they are safely transported between nuclear establishments in the United Kingdom and overseas is outlined. Several popular misconceptions are dealt with. (author)

effect of gasket of varying thickness on spark ignition engines

African Journals Online (AJOL)

DJFLEX

In the study of Toyota, In-line, 4 cylinders, spark ignition engine using gaskets of varying thicknesses. (1.75mm, 3.5mm, 5.25mm, 7mm and 8.75mm) between the cylinder head and the engine block, the performance characteristics of the engine was investigated via the effect of engine speed on brake power, brake thermal ...

75 FR 38168 - Hazardous Materials: International Regulations for the Safe Transport of Radioactive Material (TS...

Science.gov (United States)

2010-07-01

... may also provide contact information, such as a telephone number and/or e-mail address. PHMSA and the.... PHMSA-2010-0130 (Notice No.10-2)] Hazardous Materials: International Regulations for the Safe Transport... (IAEA) ``Regulations for the Safe Transport of Radioactive Material'' (TS-R-1), which is scheduled for...

Safe Transport of Radioactive Material, Philosophy and Overview

Energy Technology Data Exchange (ETDEWEB)

EL-Shinawy, R M.K. [Radiation Protection Dept., Nuclear Rasearch Center, Atomic Energy Authority, Cairo (Egypt)

2008-07-01

Safe transport of radioactive material regulations issued by IAEA since 1961, provide standards for insuring a high level of safety of people,transport workers, property and environment against radiation, contamination and criticality hazards as well as thermal effects associated with the transport of the radioactive wastes and material. The history ,development, philosophy and scope of these international and national regulations were mentioned as well as the different supporting documents to the regulations for safe transport of radioactive material were identified.The first supporting document , namely TS - G-1.1(ST-2) ,Advisory material is also issued by the IAEA.It contains both the advisory and explanatory materials previously published in safety series Nos 7and 37 and therefore TS-G-1.1 (ST-2) will supersede safety series Nos 7 and 37. The second supporting document namely TS-G-1.2 (ST-3), planning and preparing for emergency response to transport accidents involving radioactive material ,which will supersede safety series No 87. In addition to quality assurance (SS no.113), compliance assurance (SS no. 112), the training manual and others.

Safe Transport of Radioactive Material, Philosophy and Overview

International Nuclear Information System (INIS)

EL-Shinawy, R.M.K.

2008-01-01

Safe transport of radioactive material regulations issued by IAEA since 1961, provide standards for insuring a high level of safety of people,transport workers, property and environment against radiation, contamination and criticality hazards as well as thermal effects associated with the transport of the radioactive wastes and material. The history ,development, philosophy and scope of these international and national regulations were mentioned as well as the different supporting documents to the regulations for safe transport of radioactive material were identified.The first supporting document , namely TS - G-1.1(ST-2) ,Advisory material is also issued by the IAEA.It contains both the advisory and explanatory materials previously published in safety series Nos 7and 37 and therefore TS-G-1.1 (ST-2) will supersede safety series Nos 7 and 37. The second supporting document namely TS-G-1.2 (ST-3), planning and preparing for emergency response to transport accidents involving radioactive material ,which will supersede safety series No 87. In addition to quality assurance (SS no.113), compliance assurance (SS no. 112), the training manual and others

Effect of gasket of varying thickness on spark ignition engines | Ajayi ...

African Journals Online (AJOL)

In the study of Toyota, In-line, 4 cylinders, spark ignition engine using gaskets of varying thicknesses (1.75mm, 3.5mm, 5.25mm, 7mm and 8.75mm) between the cylinder head and the engine block, the performance characteristics of the engine was investigated via the effect of engine speed on brake power, brake thermal ...

Regulatory requirements on management of radioactive material safe transport in China

International Nuclear Information System (INIS)

Chu, C.

2016-01-01

Since 1980s, the IAEA Regulation for safe transport of radioactive material was introduced into China; the regulatory system of China began with international standards, and walked towards the institutionalized. In 2003 the National People’s Congress (NPC) promulgated “the Act on the Prevention of Radioactive Pollution of the People's Republic of China”. In 2009 “Regulation for the Safe Transport of Radioactive Material” (Referred to “Regulation”) was promulgated by the State Council. Subsequently, the National Nuclear Safety Administration (NNSA) began to formulate executive detailed department rules, regulations guidelines and standards. The present system of acts, regulations and standards on management of safe transport of radioactive material in China and future planning were introduced in this paper. Meanwhile, the paper described the specific administration requirements of the Regulation on classification management of radioactive materials, license management of transport packaging including design, manufacture and use, licensing management of transport activities and the provisions of illegal behaviors arising in safe transport of radioactive material. (author)

Seal performance of thermal aged metal gasket of dual purpose metal cask for interim spent fuel storage after external impact load

International Nuclear Information System (INIS)

Takeshi Yokoyama; Masami Kato; Satoshi Itooka

2005-01-01

As for interim storage for spent nuclear fuels using dual purpose dry metal cask in Japan, we recognize one of the important technical issues that there is a possibility for the cask with degraded metal gasket during storage to apply to transportation. In our study until 2003 focused on degradation of important components for the cask safety performance during storage and application to transportation, for metal gasket, we conducted property tests for degradation and influence of lid movement on seal performance, and furthermore verification tests. From the results, we developed the method to evaluate leak rate from lid with degraded metal gasket at accidents during transportation and in addition, we found as follows: Lid would hardly move and leak rate would not increase seriously during fire event. Leak rate from lid with degraded metal gasket could be evaluated by using results of leak rate trend depending on horizontal displacement of lid by external impact load. So, with regard to influence of lid movement on seal performance, we conducted additional test for extending horizontal displacement in lid moving in 2004. In addition, seal performance was discussed from the results, both previous and latest test. (authors)

Nonlinear stochastic interacting dynamics and complexity of financial gasket fractal-like lattice percolation

Science.gov (United States)

Zhang, Wei; Wang, Jun

2018-05-01

A novel nonlinear stochastic interacting price dynamics is proposed and investigated by the bond percolation on Sierpinski gasket fractal-like lattice, aim to make a new approach to reproduce and study the complexity dynamics of real security markets. Fractal-like lattices correspond to finite graphs with vertices and edges, which are similar to fractals, and Sierpinski gasket is a well-known example of fractals. Fractional ordinal array entropy and fractional ordinal array complexity are introduced to analyze the complexity behaviors of financial signals. To deeper comprehend the fluctuation characteristics of the stochastic price evolution, the complexity analysis of random logarithmic returns and volatility are preformed, including power-law distribution, fractional sample entropy and fractional ordinal array complexity. For further verifying the rationality and validity of the developed stochastic price evolution, the actual security market dataset are also studied with the same statistical methods for comparison. The empirical results show that this stochastic price dynamics can reconstruct complexity behaviors of the actual security markets to some extent.

Safe transport of radioactive material. 3. ed

Energy Technology Data Exchange (ETDEWEB)

NONE

2002-12-01

The IAEA has developed a standardized approach to transport safety training as a means of helping Member States to implement the Transport Regulations. The training manual is an anchor of this standardized approach to training: it contains all the topics presented in the sequential order recommended by the IAEA for the student to gain a thorough understanding of the body of knowledge that is needed to ensure that radioactive material ranked as Class 7 in the United Nations' nomenclature for dangerous goods - is transported safely. The explanations in the text refer, where needed, to the appropriate requirements in the IAEA's Transport Regulations; additional useful information is also provided. Thus, the training manual in addition to the Transport Regulations and their supporting documents is used by the IAEA as the basis for delivering all of its training courses on the safe transport of radioactive material. Enclosed with the training manual is a CD-ROM that contains the text of the manual as well as the visual aids that are used at the IAEA's training courses. The following topics are covered: review of radioactivity and radiation; review of radiation protection principles; regulatory terminology; basic safety concepts: materials and packages; activity limits and material restrictions; selection of optimal package type; test procedures: material and packages; requirements for transport; control of material in transport; fissile material: regulatory requirements and operational aspects; quality assurance; national competent authority; additional regulatory constraints for transport; international liability and insurance; emergency planning and preparedness; training; services provided by the IAEA.

Safe transport of radioactive material. 3. ed

International Nuclear Information System (INIS)

2002-01-01

The IAEA has developed a standardized approach to transport safety training as a means of helping Member States to implement the Transport Regulations. The training manual is an anchor of this standardized approach to training: it contains all the topics presented in the sequential order recommended by the IAEA for the student to gain a thorough understanding of the body of knowledge that is needed to ensure that radioactive material ranked as Class 7 in the United Nations' nomenclature for dangerous goods - is transported safely. The explanations in the text refer, where needed, to the appropriate requirements in the IAEA's Transport Regulations; additional useful information is also provided. Thus, the training manual in addition to the Transport Regulations and their supporting documents is used by the IAEA as the basis for delivering all of its training courses on the safe transport of radioactive material. Enclosed with the training manual is a CD-ROM that contains the text of the manual as well as the visual aids that are used at the IAEA's training courses. The following topics are covered: review of radioactivity and radiation; review of radiation protection principles; regulatory terminology; basic safety concepts: materials and packages; activity limits and material restrictions; selection of optimal package type; test procedures: material and packages; requirements for transport; control of material in transport; fissile material: regulatory requirements and operational aspects; quality assurance; national competent authority; additional regulatory constraints for transport; international liability and insurance; emergency planning and preparedness; training; services provided by the IAEA

AC properties of 3d Sierpinski gaskets: rigorous results

International Nuclear Information System (INIS)

Burioni, R; Cassi, D; Neri, F M

2005-01-01

The problem of the decimation of a network of impedances on the three-dimensional Sierpinski gasket is solved: the exact map M is given and its asymptotic behaviours are studied. The most significant invariant subspaces of M and the associated submaps are considered. This also allows us to address the problem of small-size phenomena, such as oscillating asymptotic behaviour, on this kind of fractal. The set of the resonances of the system and the frequency dependence of the total impedance are studied both in the thermodynamic limit and in mesoscopic systems

Endurance test report of rubber sealing materials for the containment vessel

International Nuclear Information System (INIS)

Yamamoto, R.; Watanabe, K.; Hanashima, K.

2015-01-01

In the event of a nuclear power plant accident such as a core meltdown and a cooling system failure, the containment contains radioactive materials released from the reactor pressure vessel to reduce the activity of the radioactive materials and the effects of radiation in the vicinity of the plant. Since high sealing performance and high pressure resistance are required of the containment, a silicone or EPDM rubber gasket with high heat and radiation resistance is used for the sealing of the sealing boundary of the containment. In recent years, it has been shown that a large amount of steam is released into the containment in the case of a severe accident. Consequently, radiation resistance at high temperature as well as steam resistance is required of the rubber gasket placed at the sealing boundary. However, the steam resistance of silicone rubber is not necessarily as good as that of EPDM rubber. Therefore, it is necessary to evaluate the sealing characteristics of rubber gaskets in such a degrading environment in a severe accident. O. Kato et al. [1] conducted a study on the degradation status of rubber gaskets and their application limits at high temperature. However, few studies have evaluated rubber gaskets in high-temperature radiation and steam environments. In this study, we degraded silicone rubber and EPDM rubber used for the containment in the high-temperature radiation and steam environments expected to occur in a severe accident and evaluated the useful life of the rubber as a sealing material by estimating the change in its performance as a sealing material from the change in permanent compressive strain in the rubber. (author)

Storage containers for radioactive material

International Nuclear Information System (INIS)

Cassidy, D.A.; Dates, L.R.; Groh, E.F.

1981-01-01

A radioactive material storage system is disclosed for use in the laboratory. This system is composed of the following: a flat base plate with a groove in one surface thereof and a hollow pedestal extending perpendicularly away from the other surface thereof; a sealing gasket in the groove, a cover having a filter therein and an outwardly extending flange which fits over the plate; the groove and the gasket, and a clamp for maintaining the cover and the plate are sealed together, whereby the plate and the cover and the clamp cooperate to provide a storage area for radioactive material readily accessible for use or inventory. Wall mounts are provided to prevent accidental formation of critical masses during storage

The safe transport of radioactive material in South Africa

International Nuclear Information System (INIS)

Jutle, K.K.

1997-01-01

An overview is presented of the activities related to the transport of radioactive material in South Africa. In particular, the applicable legislation, the scope of authority and regulatory functions of the Competent Authority are discussed. The categories of radioactive materials transported and the packaging requirements for the safe transport of these radioactive materials are also described. (Author)

The safe transport of radioactive material in South Africa

International Nuclear Information System (INIS)

Jutle, K.K.

2000-01-01

An overview is presented of the activities related to the transport of radioactive material in South Africa. In particular, the applicable legislation, the scope of authority and the regulatory functions of the Competent Authority are discussed. The categories of radioactive materials transported and the packaging requirements for the safe transport of these radioactive materials are also described. (author)

Mathematical model for choosing the nuclear safe matrix compositions for fissile material immobilization

International Nuclear Information System (INIS)

Gorshtein, A.I.; Matyunin, Yu.I.; Poluehktov, P.P.

2000-01-01

A mathematical model is proposed for preliminary choice of the nuclear safe matrix compositions for fissile material immobilization. The IBM PC computer software for nuclear safe matrix composition calculations is developed. The limiting concentration of fissile materials in the some used and perspective nuclear safe matrix compositions for radioactive waste immobilization is calculated [ru

Working safely with radioactive materials

International Nuclear Information System (INIS)

Davies, Wynne

1993-01-01

In common with exposure to many other laboratory chemicals, exposure to ionising radiations and to radioactive materials carries a small risk of causing harm. Because of this, there are legal limits to the amount of exposure to ionising radiations at work and special rules for working with radioactive materials. Although radiation protection is a complex subject it is possible to simplify to 10 basic things you should do -the Golden Rules. They are: 1) understand the nature of the hazard and get practical training; 2) plan ahead to minimise time spent handling radioactivity; 3) distance yourself appropriately from sources of radiation; 4) use appropriate shielding for the radiation; 5) contain radioactive materials in defined work areas; 6) wear appropriate protective clothing and dosimeters; 7) monitor the work area frequently for contamination control; 8) follow the local rules and safe ways of working; 9) minimise accumulation of waste and dispose of it by appropriate routes, and 10) after completion of work, monitor, wash, and monitor yourself again. These rules are expanded in this article. (author)

The Safe Transportation of Radioactive Materials

International Nuclear Information System (INIS)

Megrahi, Abdulhafeed; Abu-Ali, Giuma; Enhaba; Ahmed

2008-01-01

In this paper, we present the essential conditions that should be required for transporting the radioactive materials. We demonstrate the procedure for transporting the radioactive iodine-131 from the Centre of Renewable Energies and Desalination of Water in Tajoura, Libya to Tripoli Medical Center. The safe measures were taken during the process of the transportation of the isotope produced in the centre including dosimetry analysis and the thickness of the container. (author)

Calculations on safe storage and transportation of radioactive materials

Energy Technology Data Exchange (ETDEWEB)

Hathout, A M; El-Messiry, A M; Amin, E [National Center for Nuclear Safety and Radiation Control and AEA, Cairo (Egypt)

1997-12-31

In this work the safe storage and transportation of fresh fuel as a radioactive material studied. Egypt planned ET RR 2 reactor which is of relatively high power and would require adequate handling and transportation. Therefore, the present work is initiated to develop a procedure for safe handling and transportation of radioactive materials. The possibility of reducing the magnitude of radiation transmitted on the exterior of the packages is investigated. Neutron absorbers are used to decrease the neutron flux. Criticality calculations are carried out to ensure the achievement of subcriticality so that the inherent safety can be verified. The discrete ordinate transport code ANISN was used. The results show good agreement with other techniques. 2 figs., 2 tabs.

Safe and secure: transportation of radioactive materials

International Nuclear Information System (INIS)

Howe, D.

2015-01-01

Western Waste Management Facility is Central Transportation Facility for Low and Intermediate waste materials. Transportation support for Stations: Reactor inspection tools and heavy water between stations and reactor components and single bundles of irradiated fuel to AECL-Chalk River for examination. Safety Track Record: 3.2 million kilometres safely travelled and no transportation accident - resulting in a radioactive release.

Physical and chemical test results of electrostatic safe flooring materials

Science.gov (United States)

Gompf, R. H.

1988-01-01

This test program was initiated because a need existed at the Kennedy Space Center (KSC) to have this information readily available to the engineer who must make the choice of which electrostatic safe floor to use in a specific application. The information, however, should be of value throughout both the government and private industry in the selection of a floor covering material. Included are the test results of 18 floor covering materials which by test evaluation at KSC are considered electrostatically safe. Tests were done and/or the data compiled in the following areas: electrostatics, flammability, hypergolic compatibility, outgassing, floor type, material thickness, and available colors. Each section contains the test method used to gather the data and the test results.

Materials for Nuclear Plants From Safe Design to Residual Life Assessments

CERN Document Server

Hoffelner, Wolfgang

2013-01-01

The clamor for non-carbon dioxide emitting energy production has directly  impacted on the development of nuclear energy. As new nuclear plants are built, plans and designs are continually being developed to manage the range of challenging requirement and problems that nuclear plants face especially when managing the greatly increased operating temperatures, irradiation doses and extended design life spans. Materials for Nuclear Plants: From Safe Design to Residual Life Assessments  provides a comprehensive treatment of the structural materials for nuclear power plants with emphasis on advanced design concepts.   Materials for Nuclear Plants: From Safe Design to Residual Life Assessments approaches structural materials with a systemic approach. Important components and materials currently in use as well as those which can be considered in future designs are detailed, whilst the damage mechanisms responsible for plant ageing are discussed and explained. Methodologies for materials characterization, material...

Quality assurance for the safe transport of radioactive material

International Nuclear Information System (INIS)

1994-01-01

All activities related to the safe transport of radioactive material should be covered by a quality assurance programme. This publication recognizes that a single transport operation often involves several different organizations, each having specific responsibilities. Hence, it is unlikely that the operation will be covered by a single quality assurance programme. Each quality assurance programme should be tailored to the specific organizational structure for which the programme is prepared, with account taken of the particular transport activities of that organization and the interfaces with other organizations. The aim of this publication is to give a detailed interpretation of what must be done by whom to produce a quality assurance programme for radioactive material transport. This publication provides guidance on methods and practical examples to develop QA programmes for the safe transport of radioactive material. It provides information on how to develop the programme, the standards and the common features of a QA programme

Investigations of different types of gaskets for ILC cavity flanges

International Nuclear Information System (INIS)

Budagov, Yu.; Sabirov, B.; Shirkov, G.; Sisakyan, A.; Sukhanova, A.; Trubnikov, G.; Basti, A.; Bedeschi, F.; Frasconi, F.; Ragonesi, A.

2009-01-01

The paper describes the procedures adopted to carefully test the He leak rate of several types of vacuum seals. All the tests were performed at room temperature and at liquid nitrogen (LN 2 ) temperature (77 K), and after thermal cycles between these two temperature levels. The paper also reports the test results in the INFN-Pisa clean room aimed to measure particle contamination while assembling the flange connections. The tests of the Quick Disconnect System using a new conical flange design and an external clamp were carried out. Two types of gaskets: the Helicoflex and the Ultra-Flex, were tested with this system

Advisory material for the IAEA regulations for the safe transport of radioactive material. Safety guide

International Nuclear Information System (INIS)

2008-01-01

Since the first edition in 1961, the Regulations for the Safe Transport of Radioactive Material of the IAEA (IAEA Regulations) have served as the basis of safety for the transport of radioactive material worldwide. In the discussions leading to the first edition of the IAEA Regulations, it was realized that there was need for a publication to supplement the Regulations which could give information of individual provisions as to their purpose, their scientific background and how to apply them in practice. In response, the Agency published Safety Series No. 7, entitled, in its first edition in 1961, 'Notes on Certain Aspects of the Regulations'. An additional source of information on the Regulations, providing advice on 'how' the user should comply with them which could be augmented from time to time in the light of latest experience, was provided by the Agency, initially in relation to the 1973 edition of the Regulations. This was entitled 'Advisory Material for the IAEA Regulations for the Safe Transport of Radioactive Material' and designated Safety Series No. 37. This document is the result of combining the two Safety Series in a single publication. Thus the primary purpose of this publication is to provide guidance to users on proven and acceptable ways of complying with the Regulations. This Advisory Material is not a stand-alone text and it only has significance when used as a companion to the IAEA Safety Standards Series No. ST-1, Regulations for the Safe Transport of Radioactive Material (1996 edition)

Safe transport of radioactive material. 4. ed

International Nuclear Information System (INIS)

2006-01-01

The IAEA has been publishing Regulations for the Safe Transport of Radioactive Material since 1961. Meeting its statutory obligation to foster the exchange and training of scientists and experts in the field of peaceful uses of atomic energy, the IAEA has developed a standardized approach to transport safety training. This training manual is an anchor of the standardized approach to training. It is a compendium of training modules for courses related to the different aspects of safety of transport of radioactive material. Keeping in view the specific needs of the potential users, the manual includes material that can be used for a variety of training programmes of duration ranging from half-a-day to ten days, for specific audiences such as competent authority personnel, public authorities, emergency response personnel and cargo handlers

Closure for casks containing radioactive materials

International Nuclear Information System (INIS)

Hall, G.V.B.; Mallory, C.W.

1990-01-01

This patent describes an improved closure for covering and sealing an opening in a single cask for containing radioactive material, wherein the opening is characterized by a ledge. It comprises: an inner lid receivable within the opening and having a gasket means that is seatable over the ledge; an outer lid which is likewise receivable into the opening and securable therearound when the outer lid is rotated relative to the opening. The inner lid remaining stationary relative to the cask opening when the outer lid is rotated and having no torque applied thereto by the outer lid when the outer lid is rotated, and bolt means threadedly mounted through the outer lid for applying a compressive force between the inner and outer lids after the outer lid has been secured to the opening in order to depress the gasket means of the inner lid into sealing engagement with the ledge while avoiding the application of torsion between the gasket means and the ledge

Safe Transport of Radioactive Material, International Regulations and its Supporting Documents

International Nuclear Information System (INIS)

El-Shinawy, R.M.K.

2005-01-01

Safe transport of radioactive material regulations issued by IAEA since 1961, provide standards for insuring a high level of safety of people,transport workers, property and environment against radiation, contamination and criticality hazards as well as thermal effects associated with the transport of the radioactive wastes and material. The history ,development, philosophy and scope of these international regulations were mentioned as well as the different supporting documents to the regulations for safe transport of radioactive material were identified.The first supporting document , namely TS - G-1.1 ( ST-2) ,Advisory material is also issued by the IAEA.It contains both the advisory and explanatory materials previously published in safety series No 7 and 37 and therefore TS-G-1.1 (ST-2) will supersede safety series No 7 and 37. The second supporting document namely TS-G-1.2 (ST-3), planning and preparing for emergency response to transport accidents involving radioactive material ,which will supersede safety series No 87. In addition to quality assurance (SS=113), compliance assurance (SS=112), the training manual and other

Safe Transport of Radioactive Material, International Regulations and its Supporting Documents

Energy Technology Data Exchange (ETDEWEB)

El-Shinawy, R M.K. [Radiation Protection Dept., NRC, Atomic Energy Authority, Cairo (Egypt)

2005-04-01

Safe transport of radioactive material regulations issued by IAEA since 1961, provide standards for insuring a high level of safety of people,transport workers, property and environment against radiation, contamination and criticality hazards as well as thermal effects associated with the transport of the radioactive wastes and material. The history ,development, philosophy and scope of these international regulations were mentioned as well as the different supporting documents to the regulations for safe transport of radioactive material were identified.The first supporting document , namely TS - G-1.1 ( ST-2) ,Advisory material is also issued by the IAEA.It contains both the advisory and explanatory materials previously published in safety series No 7 and 37 and therefore TS-G-1.1 (ST-2) will supersede safety series No 7 and 37. The second supporting document namely TS-G-1.2 (ST-3), planning and preparing for emergency response to transport accidents involving radioactive material ,which will supersede safety series No 87. In addition to quality assurance (SS=113), compliance assurance (SS=112), the training manual and other.

Safe transport of radioactive material. Second edition

International Nuclear Information System (INIS)

1996-01-01

In 1991, the International Atomic Energy Agency published Training Course Series No. 1 (TCS-1), a training manual that provides in 20 chapters a detailed discussion of the background, philosophy, technical bases and requirements and implementation aspects of the Regulations for the Safe Transport of Radioactive Material. The Transport Regulations are widely implemented by the IAEA's Member States and are also used as the bases for radioactive material transport requirements of modal organisations such as the International Maritime Organization and the International Civil Aviation Organization. This document is a supplement of TCS-1 to provide additional material in the form of learning aids and new exercises, that have been developed with the use of TCS-1 at succeeding IAEA training courses. The learning aids in the first part of the supplement are hitherto unpublished material that provide detailed guidance useful in solving the exercises presented in the second part. Solutions to the exercises are on field at the IAEA Secretariat and are available by arrangement to lectures presenting IAEA training courses. 4 refs, 1 fig., 6 tabs

Optimized bolt tightening strategies for gasketed flanged pipe joints of different sizes

International Nuclear Information System (INIS)

Abid, Muhammad; Khan, Ayesha; Nash, David Hugh; Hussain, Masroor; Wajid, Hafiz Abdul

2016-01-01

Achieving a proper preload in the bolts of a gasketed bolted flanged pipe joint during joint assembly is considered important for its optimized performance. This paper presents results of detailed non-linear finite element analysis of an optimized bolt tightening strategy of different joint sizes for achieving proper preload close to the target stress values. Industrial guidelines are considered for applying recommended target stress values with TCM (torque control method) and SCM (stretch control method) using a customized optimization algorithm. Different joint components performance is observed and discussed in detail.

Estimation of pressure drop in gasket plate heat exchangers

Directory of Open Access Journals (Sweden)

Neagu Anisoara Arleziana

2016-06-01

Full Text Available In this paper, we present comparatively different methods of pressure drop calculation in the gasket plate heat exchangers (PHEs, using correlations recommended in literature on industrial data collected from a vegetable oil refinery. The goal of this study was to compare the results obtained with these correlations, in order to choose one or two for practical purpose of pumping power calculations. We concluded that pressure drop values calculated with Mulley relationship and Buonopane & Troupe correlation were close and also Bond’s equation gave results pretty close to these but the pressure drop is slightly underestimated. Kumar correlation gave results far from all the others and its application will lead to oversize. In conclusion, for further calculations we will chose either the Mulley relationship or the Buonopane & Troupe correlation.

Russia-U.S. joint program on the safe management of nuclear materials

International Nuclear Information System (INIS)

Witmer, F.E.; Krumpe, P.F.; Carlson, D.D.

1998-06-01

The Russia-US joint program on the safe management of nuclear materials was initiated to address common technical issues confronting the US and Russia in the management of excess weapons grade nuclear materials. The program was initiated after the 1993 Tomsk-7 accident. This paper provides an update on program activities since 1996. The Fourth US Russia Nuclear Materials Safety Management Workshop was conducted in March 1997. In addition, a number of contracts with Russian Institutes have been placed by Lawrence Livermore National Laboratory (LLNL) and Sandia National Laboratories (SNL). These contracts support research related to the safe disposition of excess plutonium (Pu) and highly enriched uranium (HEU). Topics investigated by Russian scientists under contracts with SNL and LLNL include accident consequence studies, the safety of anion exchange processes, underground isolation of nuclear materials, and the development of materials for the immobilization of excess weapons Pu

Inexpensive and Safe DNA Gel Electrophoresis Using Household Materials

Science.gov (United States)

Ens, S.; Olson, A. B.; Dudley, C.; Ross, N. D., III; Siddiqi, A. A.; Umoh, K. M.; Schneegurt, M. A.

2012-01-01

Gel electrophoresis is the single most important molecular biology technique and it is central to life sciences research, but it is often too expensive for the secondary science classroom or homeschoolers. A simple safe low-cost procedure is described here that uses household materials to construct and run DNA gel electrophoresis. Plastic…

Zero-temperature entropy of fully frustrated generalized Sierpiński gaskets

Science.gov (United States)

Chang, C. Y.; Hui, P. M.; Yu, K. W.

1993-01-01

The Ising model with antiferromagnetic couplings on a family of generalized Sierpiński gaskets is studied using an exact technique developed recently by Stinchcombe [Phys. Rev. B 41 (1990) 2510]. A general expression of the zero-temperature entropy per spin, SAFMb(0), is given for general b, where b is a rescaling factor characterizing the fractals. Exact expressions for SAFMb (0) are derived for the cases b = 2,3,4,5,6. These expressions are evaluated numerically and results are compared to those obtained previously by numerical iterations of renormalization-group equations. The asymptotic behavior of SAFMb(0) in the limit of large b is discussed.

International conference on safe decommissioning for nuclear activities: Assuring the safe termination of practices involving radioactive materials. Contributed papers

Energy Technology Data Exchange (ETDEWEB)

NONE

2002-07-01

Thousands of operations involving the use of radioactive substances will end during the current century. While there is considerable regulatory experience in the 'front end' of the regulatory system for practices, the experience at the back end is more limited as fewer practices have actually been terminated. When a practice is terminated because the facility has reached the end of its useful life, action has to betaken to ensure the safe shutdown of the facility and allow the removal of regulatory controls. There are many issues involved in the safe termination of practices. These include setting criteria for the release of material and sites from regulatory control; determining the suitability of the various options for decommissioning nuclear facilities, managing the waste and material released from control (recycling, reuse or disposal), and the eventual remediation of the site. Some countries have put in place regulatory infrastructures and have developed programmes to manage the associated decommissioning and remediation activities. Other countries are at the stage of assessing what is involved in terminating such practices. The purpose of this Conference is to foster an information exchange on the safe an orderly termination of practices that involve the use of radioactive substances, including both decommissioning and environmental remediation, and to promote improved coherence internationally on strategies and criteria for the safe termination of practices.

International conference on safe decommissioning for nuclear activities: Assuring the safe termination of practices involving radioactive materials. Contributed papers

International Nuclear Information System (INIS)

2002-01-01

Thousands of operations involving the use of radioactive substances will end during the current century. While there is considerable regulatory experience in the 'front end' of the regulatory system for practices, the experience at the back end is more limited as fewer practices have actually been terminated. When a practice is terminated because the facility has reached the end of its useful life, action has to betaken to ensure the safe shutdown of the facility and allow the removal of regulatory controls. There are many issues involved in the safe termination of practices. These include setting criteria for the release of material and sites from regulatory control; determining the suitability of the various options for decommissioning nuclear facilities, managing the waste and material released from control (recycling, reuse or disposal), and the eventual remediation of the site. Some countries have put in place regulatory infrastructures and have developed programmes to manage the associated decommissioning and remediation activities. Other countries are at the stage of assessing what is involved in terminating such practices. The purpose of this Conference is to foster an information exchange on the safe an orderly termination of practices that involve the use of radioactive substances, including both decommissioning and environmental remediation, and to promote improved coherence internationally on strategies and criteria for the safe termination of practices

Compilation of current literature on seals, closures, and leakage for radioactive material packagings

International Nuclear Information System (INIS)

Warrant, M.M.; Ottinger, C.A.

1989-01-01

This report presents an overview of the features that affect the sealing capability of radioactive material packagings currently certified by the US Nuclear Regulatory Commission. The report is based on a review of current literature on seals, closures, and leakage for radioactive material packagings. Federal regulations that relate to the sealing capability of radioactive material packagings, as well as basic equations for leakage calculations and some of the available leakage test procedures are presented. The factors which affect the sealing capability of a closure, including the properties of the sealing surfaces, the gasket material, the closure method and the contents are discussed in qualitative terms. Information on the general properties of both elastomer and metal gasket materials and some specific designs are presented. A summary of the seal material, closure method, and leakage tests for currently certified packagings with large diameter seals is provided. 18 figs., 9 tabs

Regulatory Framework and Current Practices of the Radioactive Material Safe and Secure Transport in Albania

International Nuclear Information System (INIS)

Dollani, K.; Grillo, B.; Telhaj, E.

2016-01-01

Attempts for the establishing of a safe and secure radioactive material transport in Albania began a decade ago with formulation of the different regulation in the field of safe and secure handling of the radioactive materials. In 2004 a special regulation for the safe transport of radioactive material was prepared and approved by the National Radiation Protection Commission). This regulation has been based in the IAEA standards for the radioactive material transport and was reviewed periodically. The last regulation of the radioactive material transport was approved by Albanian government through a governmental ordinance. The transport of the radioactive material in Albania is performed by licensed subjects, which fulfill all requirements of the mentioned governmental ordinance. Based in the existing regulation, for each transport of radioactive material, a special permission is issued by NRPC. The issuing of permission allows competent authority to provide necessary information on transport regularity and to have under survey all transports of the radioactive material carried out inside the country. Last year were issued more than 80 permissions for the transport of the different types and categories of the radioactive sources. (author)

The amended regulations for the safe transport of radioactive materials in Japan

International Nuclear Information System (INIS)

Takemura, Yoshio

1978-01-01

To cope with the inadequacies of the laws and regulations including the Law Concerning Prevention of Radiation Injuries Due to Radioisotopes, Etc., the Amended Regulations for the Safe Transport of Radioactive Materials in Japan has been issued. It is based on the Regulations of IAEA for the Safe Transport of Radioactive Materials and the Technical Standards for the Transport of Radioactive Materials decided by the AEC of Japan. In the amended regulations, emphasis is placed on the safety design of transporting goods. They are classified in Types L, A and B according to shock resistance and fire resistance, and the quantities of radioisotopes allowed to be contained in respective types are specified. The following matters are described: basic ideas concerning the types of transporting goods, test standards for the goods, transport standards for the goods, and nondestructive test apparatuses in transport. (Mori, K.)

Acid Aging Effects on Surfaces of PTFE Gaskets Investigated by Thermal Analysis

Directory of Open Access Journals (Sweden)

C. Fragassa

2016-12-01

Full Text Available This paper investigates the effect of a prolonged acid attack on the surface of PTFE by Thermogravimetric Analysis (TGA and Differential Scanning Calorimetry (DSC. PTFE is very non-reactive, partly because of the strength of carbon–fluorine bonds and for its high crystallinity, and, as a consequence, it is often used in containers and pipework with reactive and corrosive chemicals. The PTFE under analysis is commercialized by two alternative producers in form of Teflon tapes. These tapes are adopted, as gaskets, in process plants where tires moulds are cleaned by acid solutions inside a multistage ultrasonic process. In this case, PTFE shows, in a relatively short operation time, inexplicably phenomena of surface degradation, which could be related, in general terms, to an acid attack. But, even considering the combined effect of ultrasonic waves, temperature, humidity and acid attack, the PTFE properties of resistance nominally exclude the risk of the extreme erosion phenomena as observed. The present experimental research aim at investigating this contradiction. A possible explanation could be related to the presence in the cleaning solution of unexpected fluorides, able to produce fluorinating agents and, thus, degrade carbon-fluorine bonds. Considering more the 300 chemical elements a tire compound consists in, it is really complex to preserve the original chemical composition of the cleaning solution. In this research PTFE samples have been treated with different mixtures of acids with the aim at investigating the different aging effects. The thermal analysis has permitted the experimental characterization of PTFE surface properties after acid attack, providing evidence of the degradation phenomena. In particular, the different acid treatments adopted for accelerating the aging of gaskets have highlighted the different behaviour of the PTFE matrix, but also differences between manufacturers.

Materials for passively safe reactors

International Nuclear Information System (INIS)

Simnad, T.

1993-01-01

Future nuclear power capacity will be based on reactor designs that include passive safety features if recent progress in advanced nuclear power developments is realized. There is a high potential for nuclear systems that are smaller and easier to operate than the current generation of reactors, especially when passive or intrinsic characteristics are applied to provide inherent stability of the chain reaction and to minimize the burden on equipment and operating personnel. Taylor, has listed the following common generic technical features as the most important goals for the principal reactor development systems: passive stability, simplification, ruggedness, case of operation, and modularity. Economic competitiveness also depends on standardization and assurance of licensing. The performance of passively safe reactors will be greatly influenced by the successful development of advanced fuels and materials that will provide lower fuel-cycle costs. A dozen new designs of advanced power reactors have been described recently, covering a wide spectrum of reactor types, including pressurized water reactors, boiling water reactors, heavy-water reactors, modular high-temperature gas-cooled reactors (MHTGRs), and fast breeder reactors. These new designs address the need for passive safety features as well as the requirement of economic competitiveness

Safe transport of spent fuels after long-term storage

International Nuclear Information System (INIS)

Aritomi, M.; Takeda, T.; Ozaki, S.

2004-01-01

Considering the scarcity of energy resources in Japan, a nuclear energy policy pertaining to the spent fuel storage has been adopted. The nuclear energy policy sets the rules that spent fuels generated from LWRs shall be reprocessed and that plutonium and unburnt uranium shall be recovered and reused. For this purpose, a reprocessing plant, which has a reprocessing capability of 800 ton/yr, is under construction at Rokkasho Village. However, it is anticipated that the start of its operation will be delayed. In addition, the amount of spent fuels generated from nuclear power plants exceeds its reprocessing capability. Therefore, the establishment of storage technology for spent fuels becomes an urgent problem in Japan in order to continue smoothly the LWR operations. In this paper, the background of nuclear power generation in Japan is introduced at first. Next, the policy of spent fuel storage in Japan and circumstances surrounding the spent fuels in Japan are mentioned. Furthermore, the major subjects for discussions to settle and improve 'Standard for Safety Design and Inspection of Metal Casks for Spent Fuel Interim Storage Facility' in Atomic Energy Society of Japan are discussed, such as the integrity of fuel cladding, basket, shielding material and metal gasket for the long term storage for achieving safe transport of spent fuels after the storage. Finally, solutions to the unsolved subject in establishing the spent fuel interim storage technologies ase introduced accordingly

Advisory material for the IAEA regulations for the safe transport of radioactive material (1985 edition). 3. ed.

International Nuclear Information System (INIS)

1990-01-01

The IAEA Regulations for the Safe Transport of Radioactive Material provide standards for ensuring a high level of safety of people, property and the environment against radiation and criticality hazards as well as thermal effects associated with the transport of radioactive material. The basic requirements to be met are: Effective containment of radioactive material; Effective control of radiation emitted from the package; A subcritical condition for any fissile material; and Adequate dissipation of any heat generated within the package. Effective quality assurance and compliance assurance programmes are required, for example: (a) Appropriate and sound packages are used; (b) The activity of radioactive material in each package does not exceed the regulatory activity limit for that material and that package type; (c) The radiation levels external to, and the contamination levels on, surfaces of packages do not exceed the appropriate limits; (d) Packages are properly marked and labelled and transport documents are completed; (e) the number of packages containing radioactive material in a conveyance is within the regulatory limits; (f) Packages of radioactive material are stowed in conveyances and are stored at a safe distance from persons and photosensitive materials; (g) Only those transport and lifting devices which have been tested are used in loading, conveying and unloading packages of radioactive material; and (h) Packages of radioactive material are properly secured for transport. The control of the transport of radioactive materials may be necessary also for other reasons, e.g. safeguards control and physical protection of nuclear materials and control of a property. For radioactive materials having other dangerous properties, the regulations of Member States, modal conventions and agreements, and other relevant documents of international organizations need to be applied. A Member State may require in its national regulations that an additional approval be

Explanatory material for the IAEA regulations for the safe transport of radioactive material (1985 edition). 2. ed. (as amended 1990)

International Nuclear Information System (INIS)

1990-01-01

This publication is an updated version of the Second Edition of the Explanatory Material for the IAEA Regulations for the Safe Transport of Radioactive Material (1985 Edition) and replaces all previous versions of Safety Series No. 7. This publication includes the changes to Safety Series No. 7 contained in the Regulations for the Safe Transport of Radioactive Material, 1985 Edition, Supplement 1988, as well as modifications adopted by the Review Panel that was convened in Vienna, 10-14 July 1989. For the convenience of the user, the old Safety Series style adopted in the original publication has been retained, although the old style has now been superseded by a new one, affecting the structure, the format and the cover of the Safety Series. It should be noted, however, that future editions will be published in the new style.

Advisory Material for the IAEA Regulations for the Safe Transport of Radioactive Material. Safety Guide (Spanish Edition)

International Nuclear Information System (INIS)

2010-01-01

This Safety Guide provides recommendations on achieving and demonstrating compliance with IAEA Safety Standards Series No. TS-R-1, Regulations for the Safe Transport of Radioactive Material, 2005 Edition, establishing safety requirements to be applied to the national and international transport of radioactive material. Transport is deemed to comprise all operations and conditions associated with and involved in the movement of radioactive material; these include the design, fabrication and maintenance of packaging, and the preparation, consigning, handling, carriage, storage in transit and receipt at the final destination of packages. This publication supersedes IAEA Safety Series No. TS-G-1.1, 2002 Edition

Relevant documents to IAEA regulations for the safe transport of radioactive materials

International Nuclear Information System (INIS)

El-Shinawy, R.M.K.; Sabek, M.G.; Gomma, M.

1998-01-01

IAEA regulations for the safe transport of radioactive materials provide standards for insuring a high level of safety of people, property, and environment against radiation, contamination, and criticality hazards as well as thermal effects associated with the transport of radioactive materials. IAEA routinely publishes technical reports which are relevant to radioactive material transportation such as INTERTRAN, directory of transport packaging test facilities, and others. A case study was performed to assess the impact of transporting radioactive materials through the suez canal using the two computer codes namely INTERTRAN and RADTRAN-4 which are part of IAEA technical documents. A comparison of the results of these two codes is given

Regulations for the safe transport of radioactive material. 1996 ed.

International Nuclear Information System (INIS)

1996-01-01

This publication is the revised version of the IAEA's Regulations for the Safe Transport of Radioactive Materials as approved by the Board of Governors in September 1996. It establishes standards of safety which provide an acceptable level of control of the radiation, criticality and thermal hazards to persons, property and the environment that are associated with the transport of radioactive material. After an introductory section, the publication is structured as follows: Section 2 defines the terms that are required for the purposes of the Regulations; Section 3 provides general provisions; Section 4 gives the activity limits and material restrictions used throughout these Regulations; Section 5 provides requirements and controls for transport; Section 6 provides requirements for radioactive materials and for packagings and packages; Section 7 provides requirements for test procedures; Section 8 provides approval and administrative requirements. The requirements for the transport of specified types of consignments are included in an abbreviated form as Schedules. Refs, figs, tabs

A discrete model on Sierpinski gasket substrate for a conserved current equation with a conservative noise

Science.gov (United States)

Kim, Dae Ho; Kim, Jin Min

2012-09-01

A conserved discrete model on the Sierpinski gasket substrate is studied. The interface width W in the model follows the Family-Vicsek dynamic scaling form with growth exponent β ≈ 0.0542, roughness exponent α ≈ 0.240 and dynamic exponent z ≈ 4.42. They satisfy a scaling relation α + z = 2zrw, where zrw is the random walk exponent of the fractal substrate. Also, they are in a good agreement with the predicted values of a fractional Langevin equation \\frac{\\partial h}{\\partial t}={\

BIOCOMPATIBLE FLUORESCENT MICROSPHERES: SAFE PARTICLES FOR MATERIAL PENETRATION STUDIES

Energy Technology Data Exchange (ETDEWEB)

Farquar, G; Leif, R

2009-07-15

Biocompatible polymers with hydrolyzable chemical bonds have been used to produce safe, non-toxic fluorescent microspheres for material penetration studies. The selection of polymeric materials depends on both biocompatibility and processability, with tailored fluorescent properties depending on specific applications. Microspheres are composed of USFDA-approved biodegradable polymers and non-toxic fluorophores and are therefore suitable for tests where human exposure is possible. Micropheres were produced which contain unique fluorophores to enable discrimination from background aerosol particles. Characteristics that affect dispersion and adhesion can be modified depending on use. Several different microsphere preparation methods are possible, including the use of a vibrating orifice aerosol generator (VOAG), a Sono-Tek atomizer, an emulsion technique, and inkjet printhead. Applications for the fluorescent microspheres include challenges for biodefense system testing, calibrants for biofluorescence sensors, and particles for air dispersion model validation studies.

A discrete model on Sierpinski gasket substrate for a conserved current equation with a conservative noise

International Nuclear Information System (INIS)

Kim, Dae Ho; Kim, Jin Min

2012-01-01

A conserved discrete model on the Sierpinski gasket substrate is studied. The interface width W in the model follows the Family–Vicsek dynamic scaling form with growth exponent β ≈ 0.0542, roughness exponent α ≈ 0.240 and dynamic exponent z ≈ 4.42. They satisfy a scaling relation α + z = 2z rw , where z rw is the random walk exponent of the fractal substrate. Also, they are in a good agreement with the predicted values of a fractional Langevin equation where η c is a conservative noise. (paper)

Modified Sierpinski Gasket Patch Antenna for UMTS and 2.4/5.2 WLAN

Directory of Open Access Journals (Sweden)

Y. E. Ali

2013-05-01

Full Text Available A modified Sierpinski Gasket fractal antenna for multiband application is proposed in this paper. The modified ground plane and the microstrip feed are used to obtain the wider bandwidth at the resonance frequency. The antenna is designed and printed on two layers FR-4 substrate (ϵr=4.4 and h=1.6 mm to cover the UMTS and 2.4/5.2 WLAN. The radiation pattern of the proposed antenna is similar to an omnidirectional. The proposed antenna has maximum gain of 1.88, 1.6, 4.31 dB at 2, 2.4, 5.2 GHz, respectively The properties of the antenna such as return losses, radiation pattern, input resistance and gain are determined via numerical CST Microwave Studio 2010 software.

Modular glovebox connector and associated good practices for control of radioactive and chemically toxic materials

International Nuclear Information System (INIS)

Hoover, M.D.; Mewhinney, C.J.; Newton, G.J.

1999-01-01

Design and associated good practices are described for a modular glovebox connector to improve control of radioactive and chemically toxic materials. The connector consists of an anodized aluminum circular port with a mating spacer, gaskets, and retaining rings for joining two parallel ends of commercially available or custom-manufactured glovebox enclosures. Use of the connector allows multiple gloveboxes to be quickly assembled or reconfigured in functional units. Connector dimensions can be scaled to meet operational requirements for access between gloveboxes. Options for construction materials are discussed, along with recommendations for installation of the connector in new or retrofitted systems. Associated good practices include application of surface coatings and caulking, use of disposable glovebags, and proper selection and protection of gasket and glove materials. Use of the connector at an inhalation toxicology research facility has reduced the time and expense required to reconfigure equipment for changing operational requirements, the dispersion of contamination during reconfigurations, and the need for decommissioning and disposal of contaminated enclosures

Comprehensive training structure for the safe transport of radioactive materials in Switzerland

International Nuclear Information System (INIS)

Pfeiffer, H.J.; Smith, L.

1993-01-01

The introduction of the 1985 IAEA Regulations for the Safe Transport of Radioactive Materials into Swiss national dangerous goods transport regulations has induced significant changes to the national radiation protection regulations. The combination of these two sets of regulatory requirements has in turn given rise to a major expansion in the national training infrastructure for the safe transport of RAM material. The established nationally recognized courses for vehicle drivers in accordance with national and regional regulations is now supplemented by an IAEA level 2 course for managers and responsible persons with consignors and shippers. A new IAEA level 3 course specifically for inspectors carrying out inspections during shipment is planned to commence in 1993. National one day general information seminars on RAM transportation are now an established part of the training scenario in Switzerland. Commencing in 1992, annual two day seminars for supervising authority inspectors involved in organizational compliance assurance are planned. Experience to date for this significantly increased activity in training has been that of enthusiastic cooperation between all parties concerned. (J.P.N.)

Changes in the regulations for the safe transport of radioactive material

International Nuclear Information System (INIS)

Lopez Vietri, Jorge R.; Vidal, Dora N.; Piumetti, Elsa H.; Capadona, Nancy M.

2000-01-01

The objective of this paper is to describe and to analyze the relevant changes, dealing with the design, operation and administrative requirements, to be introduced in the Revision 1 of the AR 10.16.1 standard 'Transport of radioactive material' that will be put into force on July, 1st 2001 by the Nuclear Regulatory Authority (competent authority of Argentina). In that way, the Revision 1 of the mentioned standard will be coincident with the 1996 edition (revised) of the 'Regulations for the safe transport of radioactive material', Safety Standards Series No. TS-R-1 (ST-1, revised) issued by the International Atomic Energy Agency (IAEA). (author)

BIOCOMPATIBLE FLUORESCENT MICROSPHERES: SAFE PARTICLES FOR MATERIAL PENETRATION STUDIES

Energy Technology Data Exchange (ETDEWEB)

farquar, G; Leif, R

2008-09-12

Biocompatible polymers with hydrolyzable chemical bonds are being used to produce safe, non-toxic fluorescent microspheres for material penetration studies. The selection of polymeric materials depends on both biocompatibility and processability, with tailored fluorescent properties depending on specific applications. Microspheres are composed of USFDA-approved biodegradable polymers and non-toxic fluorophores and are therefore suitable for tests where human exposure is possible. Micropheres are being produced which contain unique fluorophores to enable discrimination from background aerosol particles. Characteristics that affect dispersion and adhesion can be modified depending on use. Several different microsphere preparation methods are possible, including the use of a vibrating orifice aerosol generator (VOAG), a Sono-Tek atomizer, an emulsion technique, and inkjet printhead. The advantages and disadvantages of each method will be presented and discussed in greater detail along with fluorescent and charge properties of the aerosols. Applications for the fluorescent microspheres include challenges for biodefense system testing, calibrants for biofluorescence sensors, and particles for air dispersion model validation studies.

Analyzing the photonic band gaps in two-dimensional plasma photonic crystals with fractal Sierpinski gasket structure based on the Monte Carlo method

Energy Technology Data Exchange (ETDEWEB)

Zhang, Hai-Feng, E-mail: hanlor@163.com [College of Optoelectronic Engineering, Nanjing University of Posts and Telecommunications, Nanjing, 210023 ,China (China); Key Laboratory of Radar Imaging and Microwave Photonics (Nanjing Univ. Aeronaut. Astronaut.), Ministry of Education, Nanjing University of Aeronautics and Astronautics, Nanjing, 210016 (China); Liu, Shao-Bin [Key Laboratory of Radar Imaging and Microwave Photonics (Nanjing Univ. Aeronaut. Astronaut.), Ministry of Education, Nanjing University of Aeronautics and Astronautics, Nanjing, 210016 (China)

2016-08-15

In this paper, the properties of photonic band gaps (PBGs) in two types of two-dimensional plasma-dielectric photonic crystals (2D PPCs) under a transverse-magnetic (TM) wave are theoretically investigated by a modified plane wave expansion (PWE) method where Monte Carlo method is introduced. The proposed PWE method can be used to calculate the band structures of 2D PPCs which possess arbitrary-shaped filler and any lattice. The efficiency and convergence of the present method are discussed by a numerical example. The configuration of 2D PPCs is the square lattices with fractal Sierpinski gasket structure whose constituents are homogeneous and isotropic. The type-1 PPCs is filled with the dielectric cylinders in the plasma background, while its complementary structure is called type-2 PPCs, in which plasma cylinders behave as the fillers in the dielectric background. The calculated results reveal that the enough accuracy and good convergence can be obtained, if the number of random sampling points of Monte Carlo method is large enough. The band structures of two types of PPCs with different fractal orders of Sierpinski gasket structure also are theoretically computed for a comparison. It is demonstrate that the PBGs in higher frequency region are more easily produced in the type-1 PPCs rather than in the type-2 PPCs. Sierpinski gasket structure introduced in the 2D PPCs leads to a larger cutoff frequency, enhances and induces more PBGs in high frequency region. The effects of configurational parameters of two types of PPCs on the PBGs are also investigated in detail. The results show that the PBGs of the PPCs can be easily manipulated by tuning those parameters. The present type-1 PPCs are more suitable to design the tunable compacted devices.

Advisory Material for the IAEA Regulations for the Safe Transport of Radioactive Material (2012 Ed.). Specific Safety Guide

Energy Technology Data Exchange (ETDEWEB)

NONE

2014-06-15

This Safety Guide provides recommendations and guidance on achieving and demonstrating compliance with IAEA Safety Standards Series No. SSR-6, Regulations for the Safe Transport of Radioactive Material (2012 Edition), which establishes the requirements to be applied to the national and international transport of radioactive material. Transport is deemed to comprise all operations and conditions associated with and involved in the movement of radioactive material, including the design, fabrication and maintenance of packaging, and the preparation, consigning, handling, carriage, storage in transit and receipt at the final destination of packages. This publication supersedes IAEA Safety Standards Series No. TS-G-1.1 Rev. 1, which was issued in 2008.

Advisory material for the IAEA Regulations for the safe transport of radioactive material (1985 Edition). 3. ed.

International Nuclear Information System (INIS)

1987-01-01

The purpose of this document is to provide advice on the application of the provisions of the 1985 Edition of Safety Series No. 6 (concerning the IAEA Regulations for the Safe Transport of Radioactive Material) in order to help achieve compliance with the regulatory standards. This document also reflects the corrections and changes implemented by the 1986 Supplement to the Regulations for the Safe Transport of Radioactive Material. Its intent is to describe methods, techniques and practices (citing any appropriate national and international standards) which can be considered a means of satisfying certain requirements. It should always be read as offering 'a way' or 'ways' rather than 'the unique way' of achieving compliance. The information provided is to be considered purely advisory and never mandatory, except where a competent authority may require use of any part or parts of the text. This document provides information about the technical requirements of the Regulations and about the methods and technology which may be employed to satisfy them, for the benefit of designers and manufacturers of packagings, consignors, carriers, competent authorities and others, i.e. it provides 'how' information

Regulations for the safe transport of radioactive materials. 1973 revised edition (as amended).

International Nuclear Information System (INIS)

1979-01-01

On the basis of a comprehensive review carried out by a panel of experts, a revised version of the International Atomic Energy Agency's Regulations for the Safe Transport of Radioactive Materials was approved by the Board of Governors in September 1972 and published in April 1973 as Safety Series No.6 - 1973 Revised Edition. Minor amendments, together with a number of changes of detail were promulgated by the Director General in 1975 and 1977. In October 1978, the Standing Advisory Group on the Safe Transport of Radioactive Materials, established by the Director General in 1977, reviewed and recommended a small number of additional amendments. The recommendations of SAGSTRAM were subsequently accepted by the Director General. All these minor amendments and changes of detail are incorporated in the present text of the Regulations. The purpose of these Regulations is to establish standards of safety which provide an acceptable level of control of the radiation hazards to persons, property and the environment that are associated with the transport of radioactive material. They apply to the transport by land, water or air, including transport on own account, of radioactive material other than that which is an integral part of the means of transport. Transport includes any operation incidental to the whole course of carriage, such as loading, unloading and storage in transit. The term includes both normal transport and that under accident conditions

Safe Handling and Use of Flammable and Combustible Materials. Module SH-30. Safety and Health.

Science.gov (United States)

Center for Occupational Research and Development, Inc., Waco, TX.

This student module on safe handling and use of flammable and combustible materials is one of 50 modules concerned with job safety and health. This module introduces the student to the hazards of flammable and combustible materials and the measures necessary to control those hazards. Following the introduction, 14 objectives (each keyed to a page…

Seals, Concrete Anchors, and Connections

Science.gov (United States)

1989-02-01

caulking compounds, nonhardening extruded tapes, nonhardening mastics, strippable spray coatings, pressure sensitive tapes, gaskets, adhesives, fabrics...films, etc. Although all of these materials may provide a seal, care must be taken when selecting a sealing material as to its chemical and...gaskets have performed satisfactorily. Another factor to be considered in the selection of gasketing material is its compatibility with both the

System design for safe robotic handling of nuclear materials

International Nuclear Information System (INIS)

Drotning, W.; Wapman, W.; Fahrenholtz, J.; Kimberly, H.; Kuhlmann, J.

1996-01-01

Robotic systems are being developed by the Intelligent Systems and Robotics Center at Sandia National Laboratories to perform automated handling tasks with radioactive nuclear materials. These systems will reduce the occupational radiation exposure to workers by automating operations which are currently performed manually. Because the robotic systems will handle material that is both hazardous and valuable, the safety of the operations is of utmost importance; assurance must be given that personnel will not be harmed and that the materials and environment will be protected. These safety requirements are met by designing safety features into the system using a layered approach. Several levels of mechanical, electrical and software safety prevent unsafe conditions from generating a hazard, and bring the system to a safe state should an unexpected situation arise. The system safety features include the use of industrial robot standards, commercial robot systems, commercial and custom tooling, mechanical safety interlocks, advanced sensor systems, control and configuration checks, and redundant control schemes. The effectiveness of the safety features in satisfying the safety requirements is verified using a Failure Modes and Effects Analysis. This technique can point out areas of weakness in the safety design as well as areas where unnecessary redundancy may reduce the system reliability

Development of a National System to Regulate Safe Transport of Radioactive Materials in Ukraine

International Nuclear Information System (INIS)

Gashev, M.; Kutuzova, T.; Sakalo, V.

2016-01-01

The paper provides brief information on development of the legislative framework and regulatory requirements in transport of radioactive materials in Ukraine. The application of IAEA documents is demonstrated and their contribution to the improvement of the national regulatory control system and processes of its harmonization with international safety requirements is underlined. Proposals for coordination and interaction enhancement in order to improve safety in safe transport of radioactive materials are defined in the conclusion. (author)

Russian-U.S. joint program on the safe management of nuclear materials

International Nuclear Information System (INIS)

Witmer, F.E.; Krumpe, P.F.; Carlson, D.D.

1997-12-01

The Russian-US joint program on the safety of nuclear materials was initiated in response to the 1993 Tomsk-7 accident. The bases for this program are the common technical issues confronting the US and Russia in the safe management of excess weapons grade nuclear materials. The US and Russian weapons dismantlement process is producing hundreds of tons of excess Pu and HEU fissile materials. The US is on a two path approach for disposition of excess Pu: (1) use Pu in existing reactors and/or (2) immobilize Pu in glass or ceramics followed by geologic disposal. Russian plans are to fuel reactors with excess Pu. US and Russia are both converting and blending HEU into LEU for use in existing reactors. Fissile nuclear materials storage, handling, processing, and transportation will be occurring in both countries for tens of years. A table provides a history of the major events comprising the Russian-US joint program on the safety of nuclear materials. A paper delineating program efforts was delivered at the SPECTRUM '96 conference. This paper provides an update on program activities since then

The experience of the Republic of Belarus in the field of safe and secure transport of radioactive material

International Nuclear Information System (INIS)

Astashka, R.; Kronava, Z.; Prykhodzka, A.; Tkachonak, I.

2016-01-01

The experience of the safe and secure transport of radioactive material of the Republic of Belarus includes domestic and international movements. Transit is a substantial part of international movements taking into account the location of the country. Legislative and regulatory requirements on safety and security of radioactive material transport being in force in the country include the demands making by such state structures as the Department on Nuclear and Radiation Safety, the Department on supervision for the safe industrial activities, the Ministry of Health of the Republic of Belarus. At the same time response to accidents and security events belongs to the scope of activity of special subdivisions of the Ministry for Emergency Situations and the Ministry of Internal Affairs of the Republic of Belarus. For safety purposes all the above-mentioned structures are executing their duties in close collaboration with each other and are following the IAEA safety and security recommendations. The regulatory infrastructure concerning the safe and secure transport of radioactive material of the Republic of Belarus is the subject of the contributed paper. (author)

Regional training course on safe transport of radioactive material. Folder documentation

International Nuclear Information System (INIS)

1999-01-01

Folder including documentation distributed to the participants to the International Atomic Energy Agency (IAEA) Regional Training Course on Safe Transport of Radioactive Material organised by the IAEA in co-operation with the Government of Argentina through the Nuclear Regulatory Authority, held in Buenos Aires, Argentina, 13 September -1 October 1999. The course was intended to people from IAEA Member States in the Latin American and Caribbean region. The instruction language was spanish and some lectures was delivered in english. The documentation was Spanish and some lectures was delivered in English. The documentation was in Spanish and included: copies of transparencies used during lectures, exercises of application, main training document (introduction; shipments of radioactive material; applicable regulations; basic principles; scope and objective of the IAEA Transport Regulations; package design requirements; type of packages and their contents limits; Q system; special form radioactive material requirements; radiation protection requirements; fissile material transport requirements; controls, contamination, radiation level, transport index; operational and administrative requirements; consignors' responsibilities; approval certificates, transport under special arrangements; emergency planning and procedures; physical protection aspects during transport. Guidelines for consignors, radiation detectors, complement to the training manual on main changes included in the 1996 Edition of IAEA Transport Regulations

Explanatory material for the IAEA regulations for the safe transport of radioactive material (1985 edition). 2. ed

International Nuclear Information System (INIS)

1987-01-01

This document pertains to Safety Series No. 7 of the IAEA, which is to explain the provisions of the IAEA Safety Series No. 6 in order to help comprehension of the regulatory standards and to promote compliance, public acceptance and further development of the Regulations. The document also reflects corrections and changes implemented by the 1986 Supplement to the Regulations for the Safe Transport of Radioactive Material. The intent of the document is to show why certain provisions of Safety Series No. 6 exist, why they are so formed (including any relevant history) and the rationale behind the provisions. Definitions are presented, basic principles established, activity and fissile material limits as well as computational techniques are presented. The detailed requirements (the latter sections are built on this information) concern: shipping and storage, material packagings and packages which govern design. Test requirements are provided. Approval and administrative requirements are stated. Heavy emphasis is placed on providing safety through design. It contains the cornerstone of the basic requirements for packagings, packages and material-related aspects.

Integrated pressure sensor systems in the cylinder-head gasket; Integrierte Drucksensorik in der Zylinderkopfdichtung

Energy Technology Data Exchange (ETDEWEB)

Diez, A.; Maier, U. [ElringKlinger AG (Germany); Eifler, G. [ElringKlinger Motortechnik GmbH (Germany); Schnepf, M. [Kistler Instrumente AG, Winterthur (Switzerland)

2004-01-01

The optimisation of engine management plays a major role in the development of modern engines. A significant contribution to this optimisation will be made by a cylinder-head gasket with integrated pressure sensors of the quality required to measure in-cylinder pressure, which ElringKlinger AG together with Kistler Instrumente AG are currently working on. The goal is to provide the automotive industry with a system that makes it possible to optimally control combustion in each individual cylinder. (orig.) [German] Die Optimierung des Motormanagements spielt bei der Entwicklung moderner Motoren eine zentrale Rolle. Eine Zylinderkopfdichtung mit integrierten Druckaufnehmern in Indizierqualitaet, an der die Elring-Klinger AG und die Kistler Instrumente AG derzeit gemeinsam arbeiten, soll hierzu einen entscheidenden Beitrag leisten. Ziel ist es, der Automobilindustrie ein System zur Verfuegung zu stellen, das eine optimierte und zylinderindividuelle Steuerung der Verbrennung ermoeglicht. (orig.)

Comparison of Finite Element Modeling and Experimental Pressure Distribution in a Diamond Anvil Cell

Science.gov (United States)

Kondrat'yev, Andreiy I.; Murphy, Michael J.; Weir, Samuel T.; Vohra, Yogesh K.

2002-10-01

Ultra high pressures can be obtained in a Diamond Anvil Cell (DAC) device by optimizing the geometrical shape of diamond anvil and by use of high strength gasket materials. Radial pressure distribution in a diamond-coated rhenium gasket was measured by the micro-collimated X-ray diffraction techniques at NSLS, Brookhaven National Laboratory up to peak pressure of 220 GPa. The process of DAC compression was described by finite element analysis using NIKE-2D software. The mechanical properties of the diamond-coated gasket material were modeled and radial pressure distribution obtained was in good agreement with the experimental data. The calculated shear stress in diamond in the axial direction was shown to depend strongly on the yield strength of the gasket material and may limit the ultimate pressure that can be obtained with the use of high strength gasket materials. Supported by the National Science Foundation (NSF) Grant No. DMR-0203779.

Properties and Corrosion Performance of Self-reinforced Composite PEEK for Proposed Use as a Modular Taper Gasket.

Science.gov (United States)

Ouellette, Eric S; Gilbert, Jeremy L

2016-11-01

bulk PEEK (modulus = 5.0 ± 0.3 GPa, 2.8 ± 0.1 GPa, respectively, p PEEK (44.2% ± 3%, 39.5% ± 0.5%, respectively, p = 0.039), but had comparable crystalline orientation as compared with the initial PEEK fibers. SRC-PEEK reduced fretting currents compared with metal-on-metal controls by two to three orders of magnitude in both variable load (4.0E-5 ± 3.8E-5 μA versus 2.9E-3 ± 7.1E-4 μA, respectively, p = 0.018) and variable potential (7.5E-6 ± 4.7E-6 μA versus 5.3E-3 ± 1.4E-3 μA, respectively, p = 0.022) fretting corrosion testing. Minimal damage was observed on surfaces insulated with SRC-PEEK, whereas control surfaces showed considerable fretting corrosion damage and metal transfer. The SRC-PEEK gaskets in this study demonstrated higher crystallinity and crystalline orientation and improved monotonic tensile properties compared with bulk PEEK with the ability to effectively insulate Ti6Al4V and CoCrMo alloy surfaces and prevent the initiation of fretting corrosion under high contact-stress conditions. This novel SRC-PEEK material may offer potential as a thin film gasket material for modular tapers. Pending further in vitro and in vivo analyses, this approach may be able to preserve the advantages of modular junctions for surgeons while potentially limiting the downside risks associated with mechanically assisted crevice corrosion.

Study on domestic material purchasing in MSR manufacture of conventional island

International Nuclear Information System (INIS)

Xie Zhengmao

2010-01-01

Combining the real case of Dongfang Electric (Guangzhou) Heavy Machinery Co., Ltd. trying to purchase the domestic sealing gasket as needed in the MSR of the conventional island, this paper describes the trends and relevant experience about nuclear power equipment manufacturers purchasing materials in the domestic market, and provides a reference to broadening the procurement channels of the purchasing departments of nuclear equipment manufacturers. (author)

Method for making a low density polyethylene waste form for safe disposal of low level radioactive material

Science.gov (United States)

Colombo, P.; Kalb, P.D.

1984-06-05

In the method of the invention low density polyethylene pellets are mixed in a predetermined ratio with radioactive particulate material, then the mixture is fed through a screw-type extruder that melts the low density polyethylene under a predetermined pressure and temperature to form a homogeneous matrix that is extruded and separated into solid monolithic waste forms. The solid waste forms are adapted to be safely handled, stored for a short time, and safely disposed of in approved depositories.

Role IAEA implementation of ICRP-60 on regulations the safe transport of radioactive material

International Nuclear Information System (INIS)

Elshinawy, R.K.M.; Gomaa, M.A.

1994-01-01

In november 1990, the (ICRP) adopted its 1990 recommendations (ICRP-60) ( 1). These recommendations will significantly influence not only IAEA's basic safety standards (safety series 9) ( 2), but also the IAEA regulations for the safe transport of radioactive material ( 3) and its supporting documents ( 4-6). IAEA experts are currently engaged in the revision of the transport regulations. This revision process led to the publication of the revised transport regulations of 1966. The transport regulations are developed to ensure safety during movement of radioactive materials, and to provide reasonable assurance that the transport activities comply with the basic safety standards for radiation protection

Report of consultants to the IAEA on requirements for the safe transport of low hazard radioactive materials

International Nuclear Information System (INIS)

Collin, W.; Grenier, M.; Hopkins, D.

1982-01-01

In the present paper changes are recommmended to certain definitions given in the 2nd draft revision of the IAEA 'regulations for the safe transport of radioactive materials (safety series no. 6)'. (orig./RW)

A report on the on-going researches on safe transport of radioactive materials as collected by the IAEA in 1980

International Nuclear Information System (INIS)

1981-01-01

Presented are brief reports made by Member States on research in progress in the area of safe transport of radioactive materials. Most of the research reported deals with some aspect of packaging or container design. The research contracts within the IAEA's coordinated research programme on safe transport are also outlined

Safe and Secure Transportation of Radioactive Materials in Pakistan and Future Challenges

International Nuclear Information System (INIS)

Muneer, Muhammad; Ejaz, Asad

2016-01-01

PNRA is the sole organization in the country responsible to regulate all matters pertaining to ionizing radiations. For the safety of transport of radioactive material in the country, PNRA has adopted IAEA TS-R-1 as a national regulation. To cover the security aspects and emergency situations, if any, during the transportation of radioactive material, PNRA has issued the regulatory guide on ‘Transportation of Radioactive Material by Road in Pakistan’. In Pakistan, low to medium activity radioactive sources are transported from one place to another by road for the purpose of industrial radiography, well logging, medical application, etc. According to national policy, sealed radioactive sources of half life greater than 1 year and with initial activity of 100 GBq or more imported in the country are required to be returned to country of origin (exported) after its use. Although the activities related to transport of radioactive material remained safe and secure and no major accident/incident has been reported so far, however, the improvement/enhancement in the regulatory infrastructure is a continuous process. In future, more challenges are expected to be faced in the safety of transport packages. This paper will describe the steps taken by PNRA for the safety and security of transport of radioactive material in the country and future challenges. (author)

Status of Philippine regulatory infrastructure for the safe transport of radioactive materials

International Nuclear Information System (INIS)

Parami, V.K.; De Jesus, T.G.

2004-01-01

This paper presents some regulatory practices and experiences of the Philippine Nuclear Research Institute (PNRI) in ensuring safe transport of radioactive materials. The regulation and licensing the use of radioactive materials started in 1958. The number of packages containing radioactive materials transported into and within the country has increased with the increase number of licensees. During the period 2000-2002, the total number of licensees is 293, 311 and 311 respectively. The PNRI issues certificates of release and certificate of transport/authority to transport. Based on the data of certificates, the topmost sealed source shipments from abroad, mostly in type A package, are 192 Ir and 125 I for brachytherapy. For unsealed sources, also mostly in type A package, the topmost radioactive materials are 99m Tc (generators), 131 I, 201 Tl mainly for medical diagnosis. From the data on certificates of transport, the total number of packages inspected for the period 2000-2002 is 464, 577 and 747 respectively. The experiences in the enforcement of the transport regulations and the implication of issuing certificates of release and transport are discussed and recommendations are presented. (Authors)

Static seals and their application in water-cooled nuclear reactor systems

International Nuclear Information System (INIS)

Anon.

1976-01-01

Information relative to six types of static seals commonly used in the primary cooling systems of nuclear reactors is compiled. This information includes a description of each type of seal, its material of construction, design features, operating experience, and advantages and disadvantages. The types covered include spiral-wound asbestos-filled gaskets, hollow metallic O-rings, Belleville spring type of gasketed joints, integrated elastomer and metal retainer gaskets, and solid metal gaskets with heavy cross sections. Omega, canopy, and lip seals are discussed briefly, and information on flange design for gasketing is also presented

Two Inexpensive and Non-destructive Techniques to Correct for Smaller-Than-Gasket Leaf Area in Gas Exchange Measurements

Directory of Open Access Journals (Sweden)

Andreas M. Savvides

2018-04-01

Full Text Available The development of technology, like the widely-used off-the-shelf portable photosynthesis systems, for the quantification of leaf gas exchange rates and chlorophyll fluorescence offered photosynthesis research a massive boost. Gas exchange parameters in such photosynthesis systems are calculated as gas exchange rates per unit leaf area. In small chambers (<10 cm2, the leaf area used by the system for these calculations is actually the internal gasket area (AG, provided that the leaf covers the entire AG. In this study, we present two inexpensive and non-destructive techniques that can be used to easily quantify the enclosed leaf area (AL of plant species with leaves of surface area much smaller than the AG, such as that of cereal crops. The AL of the cereal crop species studied has been measured using a standard image-based approach (iAL and estimated using a leaf width-based approach (wAL. iAL and wAL did not show any significant differences between them in maize, barley, hard and soft wheat. Similar results were obtained when the wAL was tested in comparison with iAL in different positions along the leaf in all species studied. The quantification of AL and the subsequent correction of leaf gas exchange parameters for AL provided a precise quantification of net photosynthesis and stomatal conductance especially with decreasing AL. This study provides two practical, inexpensive and non-destructive solutions to researchers dealing with photosynthesis measurements on small-leaf plant species. The image-based technique can be widely used for quantifying AL in many plant species despite their leaf shape. The leaf width-based technique can be securely used for quantifying AL in cereal crop species such as maize, wheat and barley along the leaf. Both techniques can be used for a wide range of gasket shapes and sizes with minor technique-specific adjustments.

Guide to the design, testing and use of packaging for the safe transport of radioactive materials

International Nuclear Information System (INIS)

1976-01-01

This guide gives to designers, manufacturers and users of packaging, advice supplementary to, or in amplification of, the recommendations made by the International Atomic Energy Agency for the safe transport of radioactive materials as given in IAEA Safety Series No. 6 (1973) and the advisory material given in IAEA Safety Series No. 37 (1973). This guide should be read and used in conjunction with these recommendations, the appropriate national regulations and any applicable regulations or requirements of the carriers concerned. (author)

Non-linear analysis of a closure manway using spiral wound gasket with metal-metal contact and a new geometry approach

International Nuclear Information System (INIS)

Jesus Miranda, C.A. de.

1992-01-01

The results of a PWR pressurizer closure manway analysis are presented. The manway geometry is slightly different from the conventional solution with the goal to reduce the bending stresses in the bolts when the system is pressurized. So the salt stresses value will also be reduced. The viability of the proposed solution will be confirmed by: verification of the stresses in the bolts connecting the blind flange to the nozzle by ASME III, subsection NB and level of the tightness reached in the spiral wound (type SG) gasket based in the criteria defined in the references. (author)

IAEA mode-related research in the safe transport of radioactive material

Energy Technology Data Exchange (ETDEWEB)

Blalock, L.G.; Rawl, R.R. [International Atomic Energy Agency, IAEA, Vienna (Austria)

1998-07-01

The International Atomic Energy Agency sponsors Co-ordinated Research Programmes (CRP) in the safe transport of radioactive material. The CRPs are intended to encourage research by Member States in identified areas and to facilitate co-ordination of exchange of information and resources to reach a common understanding of the problem and alternative solutions. Two of these programmes are: Accident Severity at Sea During the Transport of Radioactive Material and Accident Severity During the Air Transport of Radioactive Material. This paper will discuss these two programmes and their relationship to the continuing regulatory revision process and interfaces with the International Maritime Organization (IMO) and the International Civil Aviation Organization (ICAO). Some Member States and non-governmental organizations in IMO meetings expressed concerns that accidents on board ships may be more severe than the IAEA regulatory tests account for, and that package failure with subsequent release of radioactive material may occur. The CRP on accident severity at sea was established to develop further quantitative information on potential accident severities during the transport of radioactive material by ships. The primary objective of this programme is to collect and evaluate statistical data of marine accidents, perform analyses of potential accident conditions and evaluate the risks resulting from such shipments. The CRP on air transport was established to make a major international effort to collect relevant frequency and severity data and to analyze it so the accident forces to which a packages of radioactive material might be subjected to in a severe air accident can be more confidently quantified. Several countries have ongoing data collection activities related to aircraft accidents and severity and other sources of statistics for in-flight aircraft accidents will be explored. The International Civil Aviation Organization informed the IAEA of their plans to improve

IAEA mode-related research in the safe transport of radioactive material

International Nuclear Information System (INIS)

Blalock, L.G.; Rawl, R.R.

1998-01-01

The International Atomic Energy Agency sponsors Co-ordinated Research Programmes (CRP) in the safe transport of radioactive material. The CRPs are intended to encourage research by Member States in identified areas and to facilitate co-ordination of exchange of information and resources to reach a common understanding of the problem and alternative solutions. Two of these programmes are: Accident Severity at Sea During the Transport of Radioactive Material and Accident Severity During the Air Transport of Radioactive Material. This paper will discuss these two programmes and their relationship to the continuing regulatory revision process and interfaces with the International Maritime Organization (IMO) and the International Civil Aviation Organization (ICAO). Some Member States and non-governmental organizations in IMO meetings expressed concerns that accidents on board ships may be more severe than the IAEA regulatory tests account for, and that package failure with subsequent release of radioactive material may occur. The CRP on accident severity at sea was established to develop further quantitative information on potential accident severities during the transport of radioactive material by ships. The primary objective of this programme is to collect and evaluate statistical data of marine accidents, perform analyses of potential accident conditions and evaluate the risks resulting from such shipments. The CRP on air transport was established to make a major international effort to collect relevant frequency and severity data and to analyze it so the accident forces to which a packages of radioactive material might be subjected to in a severe air accident can be more confidently quantified. Several countries have ongoing data collection activities related to aircraft accidents and severity and other sources of statistics for in-flight aircraft accidents will be explored. The International Civil Aviation Organization informed the IAEA of their plans to improve

Regulations for the Safe Transport of Radioactive Materials. 1964 Revised Edition

International Nuclear Information System (INIS)

1965-01-01

In 1961 the International Atomic Energy Agency, within the framework of its statutory functions and in accordance with recommendations made by its Preparatory Commission and by the Economic and Social Council of the United Nations, published safety regulations which could be applied to the national and international transport of radio active materials by all means of transport. At the same time, the Director General of the Agency indicated that these regulations would be revised at appropriate intervals in consultation with Member States and the organizations concerned and invited suggestions for their improvement in the light of experience and increased knowledge. In preparing the revised regulations presented in this document, the Agency has received considerable support from its Member States and the organizations concerned, which have made extensive studies and suggestions in order to assist in its work. The Agency also convened several meetings of experts from its Member States and of representatives of a number of international organizations, and has been represented in several meetings convened by those organizations. In publishing the revised transport regulations which result from that co-ordinated effort, the Agency aims at proposing a lasting framework of principles and rules, complemented by appropriate technical data, acceptable for the safe transport of radio active materials by air, land and water. In particular, the developments which have been introduced concerning the packaging requirements, the nuclear safety criteria for the transport of fissile materials and the methods for testing packages should facilitate the international acceptance of packages by the authorities concerned. The Board of Governors of the Agency approved the revised regulations in June and September 1964. It authorized the Director General to apply them, as appropriate, to Agency operations and Agency assisted operations and to recommend to Member States and to the

Application of the regulations for the safe transport of radioactive material to bulk shipments of materials in minerals industry

International Nuclear Information System (INIS)

Tsurikov, Nick; Hinrichsen, Paul John; Omar, M.; Fernandes, R.

2007-01-01

Full text: The following discussion is based on the IAEA Regulations for the Safe Transport of Radioactive Material (T S -R-1,2005)[1] and Advisory Material for these Regulations (T S -G-1.1,2003)[2]. There were many amendments to the first issue of T S -R-1 (1996-2000) [3], several changes were also made when the Regulations were adopted in Australia [4]. The marks [->] or [->?] have been used in the text to indicate where a change has occurred between the references [1, 2, 3 and 4]. The mark [->] indicates that there is a difference in wording between 2000 and 2005 editions, the mark indicates that if in a particular jurisdiction 1996-2000 Transport Regulations are in force, additional consultation with an appropriate regulatory authority is required.

Biosafety Procedure for Safe Handling of Genetically Modified Plant Materials in Bio Design Facility

International Nuclear Information System (INIS)

Zaiton Ahmad; Shuhaimi Shamsudin; Mohamed Najli Mohamed Yasin; Affrida Abu Hassan; Mohd Zaid Hassan; Rusli Ibrahim

2015-01-01

Bio Design Facility is the specifically designed glass house for propagation, screening and analysis of high quality plant varieties developed through biotechnology or a combination of nuclear technology and biotechnology. High quality plant varieties especially genetically modified plants (GMO) require a special glass house facility for propagation and screening to isolate them from cross-pollinating with wild type varieties in surrounding ecosystem, and for carrying out evaluation of possible risks of the plants to human, animal and environment before they are proven safe for field trials or commercial release. This facility which was developed under the Ninth Malaysia Plan is classified as the Plant Containment Level 2 and is compliance with the bio safety regulations and guidance for the safe release of GMO according to Malaysian Bio safety Act 2007. Bio Design Facility is fully operational since 2010 and in 2012, it has also been certified as the glass house for post-entry quarantine by The Department of Agriculture. This paper summarizes the bio safety procedure for a safe, controlled and contained growing and evaluation of GMO in Bio Design Facility. This procedure covers the physical (containment and equipment's) and operational (including responsibility, code of practice, growing, decontamination and disposal of plant materials, emergency and contingency plan) aspects of the facility. (author)

The management system for the safe transport of radioactive material. Safety guide

International Nuclear Information System (INIS)

2008-01-01

The purpose of this Safety Guide is to provide information to organizations that are developing, implementing or assessing a management system for activities relating to the transport of radioactive material. Such activities include, but are not limited to, design, fabrication, inspection and testing, maintenance, transport and disposal of radioactive material packaging. This publication is intended to assist those establishing or improving a management system to integrate safety, health, environmental, security, quality and economic elements to ensure that safety is properly taken into account in all activities of the organization. Contents: 1. Introduction; 2. Management system; 3. Management responsibility; 4. Resource management; 5. Process implementation; 6. Measurement, assessment and improvement; Appendix: Graded approach for management systems for the safe transport of radioactive materials; Annex I: Two examples of management systems; Annex II: Examples of management system standards; Annex III: Example of a documented management system (or quality assurance programme) for an infrequent consignor; Annex IV: Example of a documented management system (or quality assurance programme) description for an infrequent carrier; Annex V: Example of a procedure for control of records; Annex VI: Example of a procedure for handling packages containing radioactive materials, including receipt and dispatch; Annex VII: Example of a packaging maintenance procedure in a complex organization; Annex VIII: Example of an internal audit procedure in a small organization; Annex IX: Example of a corrective and preventive action procedure

Status of the Regulation for safe and secure transport of radioactive materials in Madagascar

International Nuclear Information System (INIS)

Raoelina Andriambololona; Zafimanjato, J.L.R.; Solofoarisina, W.C.; Randriantseheno, H.F.

2011-01-01

Radioactive sources are widely used in medicine, in industrial exploration and development, as well as in basic scientific research and education in Madagascar. The ability to use such radioactive materials in these sectors depends on their safe and secure transport both within and between countries. Transport safety of radioactive materials within the country is regulated. The law No. 97-041 on radiation protection and radioactive waste management in Madagascar promulgated in January 1998 and the decree No.2735/94 dealing the transport of radioactive materials promulgated in June 1994 govern all activities related to the transport of radioactive material. This law was established to meet the requirements of the International Basic Safety Standards (BSS, IAEA Safety Series 115). It is not fully consistent with current international standards (GS-R-1). Indeed, in order to enhance the security of radioactive sources, Madagascar has implemented the Code of Conduct and the Guidance on the Import and Export of Radioactive Sources. Faced with delays and denials of shipment of radioactive materials issues, the National Focal Point has been appointed to work with ISC members and the regional networks on the global basis.

Status of the regulation for safe and secure transport of radioactive materials in Madagascar

International Nuclear Information System (INIS)

Andriambololona, Raoelina; Zafimanjato, J.L.R.; Solofoarisina, W.C.; Randriantseheno, H.F.

2016-01-01

Radioactive sources are widely used in medicine, in industrial exploration and development, as well as in basic scientific research and education in Madagascar. The ability to use such radioactive materials in these sectors depends on their safe and secure transport both within and between countries. Transport safety of radioactive materials within the country is regulated. The law n° 97-041 on radiation protection and radioactive waste management in Madagascar promulgated in January 1998 and the decree n° 2735/94 dealing the transport of radioactive materials promulgated in June 1994 govern all activities related to the transport of radioactive material. This law was established to meet the requirements of the International Basic Safety Standards (BSS, IAEA Safety Series 115). It is not fully consistent with current international standards (GS-R-1). Indeed, in order to enhance the security of radioactive sources, Madagascar has implemented the Code of Conduct and the Guidance on the Import and Export of Radioactive Sources. Faced with delays and denials of shipment of radioactive materials issues, the National Focal Point has been appointed to work with ISC members and the regional networks on the global basis. (author)

A double stage dry-wet-fermentation process for a fast and safe digestion of different kinds of organic material

International Nuclear Information System (INIS)

Busch, G.; Sieber, M.; Buschmann, J.; Burkhardat, M.

2009-01-01

The fermentation of organic material is a four-step-process. It is admissible to merge the first two steps (hydrolysis and acidification) to hydrolysis in general and the last two steps (aceto genesis and methano genesis) to methano genesis. The Brandenburg University of Technology in Cottbus has devised a double stage dry-wet-fermentation process for fast and safe anaerobic degradation. Using these processes, it is possible to decompose different kinds of organic material like renewable material (e. g. maize silage), waste (e. g. household-waste) and industrial material (e. g. glycerine). (Author)

40 CFR 63.685 - Standards: Tanks.

Science.gov (United States)

2010-07-01

... off-site material from containers to another off-site material management unit, an owner or operator... roof except for automatic bleeder vents (vacuum breaker vents) and the rim space vents is to provide a... gasketed cover or a gasketed lid except for leg sleeves, automatic bleeder vents, rim space vents, column...

The Network of Excellence 'Knowledge-based Multicomponent Materials for Durable and Safe Performance'

International Nuclear Information System (INIS)

Moreno, Arnaldo

2008-01-01

The Network of Excellence 'Knowledge-based Multicomponent Materials for Durable and Safe Performance' (KMM-NoE) consists of 36 institutional partners from 10 countries representing leading European research institutes and university departments (25), small and medium enterprises, SMEs (5) and large industry (7) in the field of knowledge-based multicomponent materials (KMM), more specifically in intermetallics, metal-ceramic composites, functionally graded materials and thin layers. The main goal of the KMM-NoE (currently funded by the European Commission) is to mobilise and concentrate the fragmented scientific potential in the KMM field to create a durable and efficient organism capable of developing leading-edge research while spreading the accumulated knowledge outside the Network and enhancing the technological skills of the related industries. The long-term strategic goal of the KMM-NoE is to establish a self-supporting pan-European institution in the field of knowledge-based multicomponent materials--KMM Virtual Institute (KMM-VIN). It will combine industry oriented research with educational and training activities. The KMM Virtual Institute will be founded on three main pillars: KMM European Competence Centre, KMM Integrated Post-Graduate School, KMM Mobility Programme. The KMM-NoE is coordinated by the Institute of Fundamental Technological Research (IPPT) of the Polish Academy of Sciences, Warsaw, Poland

Development of an evaluation method for long-term sealability of the spent fuel storage cask

International Nuclear Information System (INIS)

Kato, Osamu; Ito, Chihiro; Saegusa, Toshiari

1996-01-01

One of the characteristics of the cask storage method of spent fuel is that containment of radioactive materials is assured by the storage cask itself. Thus, the seal structure of the cask is designed to have a highly reliable multi-barrier system using metallic gaskets instead of the conventional rubber gaskets. Although, it has been reported that the containment feature of the metallic gaskets is influenced by the plastic deformation and stress relaxation of the gaskets for a short-term usage, no research report has been published on the containment feature of the metallic gaskets for a long-term usage. In this paper, the stress relaxation features of the metallic gaskets is investigated which will directly influence the long-term sealability of the storage cask, at first. Next, the relationship between the temperature/time dependence of the plastic deformation and the containment features of the metallic gaskets. Finally, an evaluation method of the long-term sealability from experimental data of a short-term behavior of the metallic gaskets is proposed. (author)

Safe transport of radioactive materials

Energy Technology Data Exchange (ETDEWEB)

NONE

1977-12-31

The film shows the widespread use of radioactive materials in industry, medicine and research and explains the need for transporting nuclear material from producer to user. It shows the way in which packages containing radioactive materials are handled during transport and explains the most important provisions of the IAEA transport regulations, safety series no. 6, such as packaging design criteria and testing requirements, illustrated by various tests carried out, specimen packages and package and freight container labelling. Also illustrated are practical measures to be taken in case of an accident

Order No. 20558 of 6 May 1964 - Adoption of the IAEA rules for the safe transport of radioactive materials

International Nuclear Information System (INIS)

1964-01-01

This Order adopts the IAEA Regulations for the Safe Transport of radioactive Materials in Portugal, together with any subsequent modifications made to the Regulations pending the publication of regulations to be elaborated by the Commission for protection against ionizing radiation. (NEA) [fr

The Network of Excellence ``Knowledge-based Multicomponent Materials for Durable and Safe Performance''

Science.gov (United States)

Moreno, Arnaldo

2008-02-01

The Network of Excellence "Knowledge-based Multicomponent Materials for Durable and Safe Performance" (KMM-NoE) consists of 36 institutional partners from 10 countries representing leading European research institutes and university departments (25), small and medium enterprises, SMEs (5) and large industry (7) in the field of knowledge-based multicomponent materials (KMM), more specifically in intermetallics, metal-ceramic composites, functionally graded materials and thin layers. The main goal of the KMM-NoE (currently funded by the European Commission) is to mobilise and concentrate the fragmented scientific potential in the KMM field to create a durable and efficient organism capable of developing leading-edge research while spreading the accumulated knowledge outside the Network and enhancing the technological skills of the related industries. The long-term strategic goal of the KMM-NoE is to establish a self-supporting pan-European institution in the field of knowledge-based multicomponent materials—KMM Virtual Institute (KMM-VIN). It will combine industry oriented research with educational and training activities. The KMM Virtual Institute will be founded on three main pillars: KMM European Competence Centre, KMM Integrated Post-Graduate School, KMM Mobility Programme. The KMM-NoE is coordinated by the Institute of Fundamental Technological Research (IPPT) of the Polish Academy of Sciences, Warsaw, Poland.

Impact of Different Standard Type A7A Drum Closure-Ring Practices on Gasket Contraction and Bolt Closure Distance– 15621

Energy Technology Data Exchange (ETDEWEB)

Ketusky, Edward [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Blanton, Paul [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Bobbitt, John H. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

2015-03-11

The Department of Energy, the Savannah River National Laboratory, several manufacturers of specification drums, and the United States Department of Transportation (DOT) are collaborating in the development of a guidance document for DOE contractors and vendors who wish to qualify containers to DOT 7A Type A requirements. Currently, the effort is focused on DOT 7A Type A 208-liter (55-gallons) drums with a standard 12-gauge bolted closure ring. The U.S. requirements, contained in Title 49, Part 178.350 “Specification 7A; general packaging, Type A specifies a competent authority review of the packaging is not required for the transport of (Class 7) radioactive material containing less than Type A quantities of radioactive material. For Type AF drums, a 4 ft. regulatory free drop must be performed, such that the drum “suffers maximum damage.” Although the actual orientation is not defined by the specification, recent studies suggest that maximum damage would result from a shallow angle top impact, where kinetic energy is transferred to the lid, ultimately causing heavy damage to the lid, or even worse, causing the lid to come off. Since each vendor develops closure recommendations/procedures for the drums they manufacture, key parameters applied to drums during closing vary based on vendor. As part of the initial phase of the collaboration, the impact of the closure variants on the ability of the drum to suffer maximum damage is investigated. Specifically, closure testing is performed varying: 1) the amount of torque applied to the closure ring bolt; and, 2) stress relief protocol, including: a) weight of hammer; and, b) orientation that the hammer hits the closure ring. After closure, the amount of drum lid gasket contraction and the distance that the closure bolt moves through the closure ring is measured.

Alternative Fuels Compatibility with Army Equipment Testing - Alternative Fuels Material Compatibility Analysis

Science.gov (United States)

2012-02-21

96906) 5330-00-182-3170 O-ring Butadiene-acrylonitrile class NBR AAFARS 13217E5363 (97403) 5330-00-235-4716 Gasket, Sight Gauge Rubber synthetic...Butadiene-acrylonitrile class NBR FSSP 13216E8238 (97403) 5330-00-647-2072 Gasket Rubber synthetic AAFARS MS28774-017 (96906) 5330-00-833-4210 Back...ring Butadiene-acrylonitrile class NBR AAFARS 5331-00-641-1119 O-ring Rubber synthetic AAFARS M25988/1-017 (81349) 5331-00-759-2121 O-ring

SEAL FOR HIGH SPEED CENTRIFUGE

Science.gov (United States)

Skarstrom, C.W.

1957-12-17

A seal is described for a high speed centrifuge wherein the centrifugal force of rotation acts on the gasket to form a tight seal. The cylindrical rotating bowl of the centrifuge contains a closure member resting on a shoulder in the bowl wall having a lower surface containing bands of gasket material, parallel and adjacent to the cylinder wall. As the centrifuge speed increases, centrifugal force acts on the bands of gasket material forcing them in to a sealing contact against the cylinder wall. This arrangememt forms a simple and effective seal for high speed centrifuges, replacing more costly methods such as welding a closure in place.

Weapons-grade nuclear material - open questions of a safe disposal

International Nuclear Information System (INIS)

Closs, K.D.; Giraud, J.P.; Grill, K.D.; Hensing, I.; Hippel, F. von; Holik, J.; Pellaud, B.

1995-01-01

There are suitable technologies available for destruction of weapons-grade uranium and plutonium. Weapons-grade uranium, consisting to 90% of the isotope U-235, can be diluted with the uranium isotope U-238 to make it non-weapons-grade, but it will then still be a material that can be used as a fuel in civil nuclear reactors. For safe plutonium disposal, several options are under debate. There is for instance a process called ''reverse reprocessing'', with the plutonium being blended with high-level radioactive fission products and then being put into a waste form accepted for direct ultimate disposal. The other option is to convert weapons-grade plutonium into MOX nuclear fuel elements and then ''burn'' them in civil nuclear power reactors. This is an option favoured by many experts. Such fuel elements should stay for a long time in the reactor core in order to achieve high burnups, and should then be ready for ultimate disposal. This disposal pathway offers essential advantages: the plutonium is used up or depleted as a component of reactor fuel, and thus is no longer available for illegal activities, and it serves as an energy source for power generation. (orig./HP) [de

Regulations for the Safe Transport of Radioactive Material. 2012 Edition. Specific Safety Requirements

Energy Technology Data Exchange (ETDEWEB)

NONE

2012-10-15

The IAEA's Statute authorizes the Agency to 'establish or adopt... standards of safety for protection of health and minimization of danger to life and property' - standards that the IAEA must use in its own operations, and which States can apply by means of their regulatory provisions for nuclear and radiation safety. The IAEA does this in consultation with the competent organs of the United Nations and with the specialized agencies concerned. A comprehensive set of high quality standards under regular review is a key element of a stable and sustainable global safety regime, as is the IAEA's assistance in their application. The IAEA commenced its safety standards programme in 1958. The emphasis placed on quality, fitness for purpose and continuous improvement has led to the widespread use of the IAEA standards throughout the world. The Safety Standards Series now includes unified Fundamental Safety Principles, which represent an international consensus on what must constitute a high level of protection and safety. With the strong support of the Commission on Safety Standards, the IAEA is working to promote the global acceptance and use of its standards. Standards are only effective if they are properly applied in practice. The IAEA's safety services encompass design, siting and engineering safety, operational safety, radiation safety, safe transport of radioactive material and safe management of radioactive waste, as well as governmental organization, regulatory matters and safety culture in organizations. These safety services assist Member States in the application of the standards and enable valuable experience and insights to be shared. Regulating safety is a national responsibility, and many States have decided to adopt the IAEA's standards for use in their national regulations. For parties to the various international safety conventions, IAEA standards provide a consistent, reliable means of ensuring the effective fulfilment of obligations under the

Regulations for the Safe Transport of Radioactive Material. 2012 Edition. Specific Safety Requirements

International Nuclear Information System (INIS)

2012-01-01

The IAEA's Statute authorizes the Agency to 'establish or adopt... standards of safety for protection of health and minimization of danger to life and property' - standards that the IAEA must use in its own operations, and which States can apply by means of their regulatory provisions for nuclear and radiation safety. The IAEA does this in consultation with the competent organs of the United Nations and with the specialized agencies concerned. A comprehensive set of high quality standards under regular review is a key element of a stable and sustainable global safety regime, as is the IAEA's assistance in their application. The IAEA commenced its safety standards programme in 1958. The emphasis placed on quality, fitness for purpose and continuous improvement has led to the widespread use of the IAEA standards throughout the world. The Safety Standards Series now includes unified Fundamental Safety Principles, which represent an international consensus on what must constitute a high level of protection and safety. With the strong support of the Commission on Safety Standards, the IAEA is working to promote the global acceptance and use of its standards. Standards are only effective if they are properly applied in practice. The IAEA's safety services encompass design, siting and engineering safety, operational safety, radiation safety, safe transport of radioactive material and safe management of radioactive waste, as well as governmental organization, regulatory matters and safety culture in organizations. These safety services assist Member States in the application of the standards and enable valuable experience and insights to be shared. Regulating safety is a national responsibility, and many States have decided to adopt the IAEA's standards for use in their national regulations. For parties to the various international safety conventions, IAEA standards provide a consistent, reliable means of ensuring the effective fulfilment of obligations under the

Schedules of Provisions of the IAEA Regulations for the Safe Transport of Radioactive Material (2009 Ed.). Safety Guide

International Nuclear Information System (INIS)

2014-01-01

This Safety Guide is issued in support of Regulations for the Safe Transport of Radioactive Material (IAEA Safety Standards Series No. TS-R-1, 2009 Edition). It lists the paragraph numbers of the Transport Regulations that are relevant for specified types of consignment, classified according to their UN numbers. It does not provide additional recommendations. The intended users are consignors and consignees, carriers, shippers, regulators, and end users involved in the transport of radioactive material. A person or organization intending to transport a particular type of consignment of radioactive material must meet requirements in all sections of the Transport Regulations. This Safety Guide aids users by providing a listing of the relevant requirements of the Transport Regulations for each type of radioactive material, package or shipment. Once a consignor has classified the radioactive material to be shipped, the appropriate UN number can be assigned and the paragraph numbers of the requirements that apply for the shipment can be found in the corresponding schedule

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

International Nuclear Information System (INIS)

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

2015-01-01

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

Using safe materials to control Varroa mites with studying grooming behavior of honey bees and morphology of Varroa over winter

OpenAIRE

Hossam F. Abou-Shaara

2017-01-01

Extracts of drone larvae and propolis as safe materials are anticipated to boost the grooming behavior of honey bees against Varroa mites. It is also expected that grooming behavior of bees and morphology of Varroa are stable during the least active period of the year to bee colonies (i.e winter). Sugar syrup alone or mixed with drone larvae extract or propolis extract were examined as potential Varroa control materials to test these hypothesizes. Moreover, percentages of groomed mites along ...

30 years of experience in safe transportation of nuclear materials

International Nuclear Information System (INIS)

Kaneko, K.

2004-01-01

In April 2003, Nuclear Fuel Transport Co., Ltd. (NFT) marked the 30 th anniversary of its founding. NFT was established in 1973 and in 1978, commenced SF transport to the reprocessing plant in Tokai-mura. And then, after making preparations to transport nuclear materials to the various facilities at the Nuclear Fuel Cycle Center in Rokkasho-mura, NFT successfully started transportation of LLW (low level waste) to Rokksho-mura's LLW disposal center in 1992, domestic land transportation of HLW returned from overseas to the HLW storage center in 1995, domestic land transportation of natural hexafluoride delivered from overseas to the uranium enrichment plant in 1996, and transportation of SF to the reprocessing plant in 2000. NFT has realized an annual SF transportation capacity of 300 MTU and is currently making great company wide efforts to meet the Rokkasho Reprocessing Plant's future SF annual reprocessing capacity of 800MTU. At the end of FY2003, NFT had successfully transported 560 casks (about 1,730 MTU) of SF in more than 200 voyages in total, about 160,000 drums of LLW in around 100 voyages in total. This paper introduces the record of safe transport and its experience over the past 30 years and prospect for future transport business

30 years of experience in safe transportation of nuclear materials

Energy Technology Data Exchange (ETDEWEB)

Kaneko, K. [Nuclear Fuel Transport Co., Ltd., Tokyo (Japan)

2004-07-01

In April 2003, Nuclear Fuel Transport Co., Ltd. (NFT) marked the 30{sup th} anniversary of its founding. NFT was established in 1973 and in 1978, commenced SF transport to the reprocessing plant in Tokai-mura. And then, after making preparations to transport nuclear materials to the various facilities at the Nuclear Fuel Cycle Center in Rokkasho-mura, NFT successfully started transportation of LLW (low level waste) to Rokksho-mura's LLW disposal center in 1992, domestic land transportation of HLW returned from overseas to the HLW storage center in 1995, domestic land transportation of natural hexafluoride delivered from overseas to the uranium enrichment plant in 1996, and transportation of SF to the reprocessing plant in 2000. NFT has realized an annual SF transportation capacity of 300 MTU and is currently making great company wide efforts to meet the Rokkasho Reprocessing Plant's future SF annual reprocessing capacity of 800MTU. At the end of FY2003, NFT had successfully transported 560 casks (about 1,730 MTU) of SF in more than 200 voyages in total, about 160,000 drums of LLW in around 100 voyages in total. This paper introduces the record of safe transport and its experience over the past 30 years and prospect for future transport business.

TN trademark FLEX: a new generation of fluorocarbon o-rings developed by COGEMA logistics with enhanced characteristics at low temperature (-40 C)

International Nuclear Information System (INIS)

Issard, H.; Andre, R.

2004-01-01

Three main types of elastomers are used for the sealing of radioactive material transport casks with elastomeric gaskets: EPDM, fluorocarbons type Viton registered (standard designation: FKM) and silicon rubbers. Each rubber has specific characteristics in terms of temperature range, permeability, coefficient of expansion.. For the casks where high temperatures can be reached (200 C in continuous using), FKM gaskets are generally used. The problem is that this type of gasket does not guarantee the leaktightness at -40 C, which is a regulatory requirement. Two solutions are generally used: to specify a minimum heat load or a minimum ambient temperature. The direct consequence is that it is impossible to get B(U) approvals on the new concepts when FKM gaskets are used but only B(M) approvals, which generate significant additional justification costs (multiple submittals of Safety Analysis Reports, calculation of the minimum heat load or of the minimum ambient temperature..). Thus, it is important to develop gaskets with the same performance as FKM gaskets at high temperature but with enhanced performance at low temperature (and mainly, which guarantee the leaktightness at -40 C). COGEMA LOGISTICS has qualified a new generation of fluorocarbon O-rings (TN trademark FLEX gaskets) which can be used in continuous service on a -47 C/+200 C temperature range. TN trademark FLEX gaskets will be implemented on new casks designs

Software development for specific geometry and safe design of isotropic material multicell beams

International Nuclear Information System (INIS)

Tariq, M.M.; Ahmed, M.A.

2011-01-01

Comparison of analytical results with finite element results for analysis of isotropic material multicell beams subjected to free torsion case is the main idea of this paper. Progress in the fundamentals and applications of advanced materials and their processing technologies involves costly experiments and prototype testing for reliability. The software development for design analysis of structures with advanced materials is a low cost but challenging research. Multicell beams have important industrial applications in the aerospace and automotive sectors. This paper explains software development to test different materials in design of a multicell beam. Objective of this paper is to compute the torsional loading of multicell beams of isotropic materials for safe design in both symmetrical and asymmetrical geometries. Software has been developed in Microsoft Visual Basic. Distribution of Saint Venant shear flows, shear stresses, factors of safety, volume, mass, weight, twist, polar moment of inertia and aspect ratio for free torsion in multicell beam have been calculated using this software. The software works on four algorithms, these are, Specific geometry algorithm, material selection algorithm, factor of safety algorithm and global algorithm. User can specify new materials analytically, or choose a pre-defined material from the list, which includes, plain carbon steels, low alloy steels, stainless steels, cast irons, aluminum alloys, copper alloys, magnesium alloys, titanium alloys, precious metals and refractory metals. Although this software is restricted to multicell beam comprising of three cells, however future versions can have ability to address more complicated shapes and cases of multicell beams. Software also describes nomenclature and mathematical formulas applied to help user understand the theoretical background. User can specify geometry of multicell beam for three rectangular cells. Software computes shear flows, shear stresses, safety factors

Gallium oxide nanorods as novel, safe and durable anode material for Li- and Na-ion batteries

International Nuclear Information System (INIS)

Meligrana, Giuseppina; Lueangchaichaweng, Warunee; Colò, Francesca; Destro, Matteo; Fiorilli, Sonia; Pescarmona, Paolo P.; Gerbaldi, Claudio

2017-01-01

Highlights: • Gallium oxide nanorods applied for the first time as anode material for Li-/Na-ion batteries. • Durable ambient temperature cycling (400 cycles) was observed in Li-based cells. • Stable reversible cycling (> 200 mAh g"−"1) was achieved for the first time in Na-based cells. - Abstract: Gallium oxide nanorods prepared by template-free synthesis are reported for the first time as safe and durable anode material for lithium- and sodium-ion batteries. The ambient temperature electrochemical response of the nanorods, tested by cyclic voltammetry and constant-current reversible cycling, is highly satisfying in terms of remarkable stability and capacity retention upon long-term operation (400 cycles), even at high current densities. The newly proposed application of gallium oxide nanorods as electrode material is notable also because this material can preserve the electrical pathway without the need of any “buffer matrix” to compensate for the expansion upon lithium or sodium reversible storage. The highly promising electrochemical performance is attributed to the high aspect ratio and high surface area that stem from the nanorod morphology and which can lead to short diffusion path and fast kinetics of both cations (Li"+ or Na"+) and electrons.

Safeguards Automated Facility Evaluation (SAFE) methodology

International Nuclear Information System (INIS)

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

1978-01-01

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

Test and evaluation report for Westinghouse Hanford Company's 1-L Liquid Shipper, Docket 95-41-7A, Type A container

International Nuclear Information System (INIS)

Kelly, D.L.

1995-11-01

This report documents the U.S. Department of Transportation Specification 7A Type A (DOT-7A) compliance test results of the 1-L Liquid Shipper packaging. The 1-L Liquid Shipper consists of the 3M SafeSend polyethylene canister base and cap with integral sorbent material, a quad ring gasket, a plastic bag, and six foam inserts. A 1-L narrow-mouth, Teflon bottle with Tefzel lid holds contents. The inner bottle is placed inside the SafeSend container. The inner bottle content weight cannot exceed 2000 g (4.4 lb). Total bottle weight, including contents cannot exceed 2167.5 g (4.78 lb). The nominal gross weight of the assembled packaging is to be no more that 3830.5 g (8.4 lb). The approved packaging system is designed to ship Type A quantities of radioactive materials, normal form. Contents may be liquid or solid form. Liquid contents may have a specific gravity less than or equal to (<2). Solid materials are limited in weight, to include packaging, to the gross weight of the as-tested liquids and bottles

Regulatory control for safe usage of radiation sources in India

International Nuclear Information System (INIS)

Ghosh, P.K.; Sonawane, A.U.

1998-01-01

The widespread applications of radioactive materials and radiation generating equipment in the field of industry, medicine agriculture and research in India necessitated the establishment of an efficient regulatory framework and consequently the Atomic Energy Regulatory Board (AERB) was constituted to exercise regulatory control over the safe usage of the radioactive materials and the radiation generating equipment. The Atomic Energy Act, 1962 and the Radiation Protection Rules, 1971 promulgated under the Act forms the basis of radiation safety in India and Chairman, AERB is the Competent Authority to enforce the regulatory provisions of the Radiation Protection Rules, 1971, for safe use of radiation source in the country. AERB has published a number of documents such as Radiation Surveillance Procedures, Standards, Codes, Guides and Manuals for safe use and handling of radioactive materials and radiation generating equipment. Apart from nuclear fuel cycle documents, these publications pertain to industrial radiography, medical application of radiation, transport of radioactive material, industrial gamma irradiators, X-ray units etc. AERB safety related publications are based on international standards e.g. BSS, IAEA, ICRP, ISO etc. This paper outlines the methodology of regulatory control exercised by AERB for safe use of the radioactive materials and the radiation generating equipment in the country. (author)

Assessing the management system to demonstrate the safe of transport of radioactive material

Energy Technology Data Exchange (ETDEWEB)

Bruno, Natanael C.; Mattar, Patricia M.; Pontes, Andre T., E-mail: nbruno@cnen.gov.br, E-mail: pmattar@cnen.gov.br, E-mail: atpontes@id.uff.br [Comissao Nacional de Energia Nuclear (CNEN), Rio de Janeiro, RJ (Brazil); Universidade Federal Fluminense (UFF), Niteroi, RJ (Brazil)

2017-11-01

Radioactive materials are used for medical purposes, to avoid greenhouse gas effect in energy production plants, food and other products sterilization, research and sophisticated measurement technologies. Transport of radioactive material involves a range of actors each one having specific responsibilities for safety. Through Management System, consignors and carriers fulfil objective evidences that safety requirements are met in practice, while compliance assurance programs allow regulatory bodies and/or competent authorities to demonstrate to society that public, workers and environment are protected. According to the International Atomic Energy Agency (IAEA), safety has to be achieved and maintained through an effective management system. This system should integrate all elements of management so that requirements for safety are established and applied consistently with other requirements, including those related to human performance, quality and security, and that safety is not compromised by other requirements or demands. Comissao Nacional de Energia Nuclear (CNEN), the Brazilian Regulatory Body for the safe transport of radioactive materials, adopt international standards to establish safety requirements deemed relevant for protection of health and minimization of danger to life and property, and to provide for the application of these standards. Seeking for continuous improvement, the adherence of the practices adopted by CNEN's Transport Safety Unit (TSU) against the recommendations from the IAEA was assessed. This assessment led to the elaboration of proposals for improvement as well as the identification of good practices. The methodology used to perform this assessment was the SARIS methodology, developed by the IAEA. This paper will describe the most relevant findings of this study. (author)

Assessing the management system to demonstrate the safe of transport of radioactive material

International Nuclear Information System (INIS)

Bruno, Natanael C.; Mattar, Patricia M.; Pontes, Andre T.

2017-01-01

Radioactive materials are used for medical purposes, to avoid greenhouse gas effect in energy production plants, food and other products sterilization, research and sophisticated measurement technologies. Transport of radioactive material involves a range of actors each one having specific responsibilities for safety. Through Management System, consignors and carriers fulfil objective evidences that safety requirements are met in practice, while compliance assurance programs allow regulatory bodies and/or competent authorities to demonstrate to society that public, workers and environment are protected. According to the International Atomic Energy Agency (IAEA), safety has to be achieved and maintained through an effective management system. This system should integrate all elements of management so that requirements for safety are established and applied consistently with other requirements, including those related to human performance, quality and security, and that safety is not compromised by other requirements or demands. Comissao Nacional de Energia Nuclear (CNEN), the Brazilian Regulatory Body for the safe transport of radioactive materials, adopt international standards to establish safety requirements deemed relevant for protection of health and minimization of danger to life and property, and to provide for the application of these standards. Seeking for continuous improvement, the adherence of the practices adopted by CNEN's Transport Safety Unit (TSU) against the recommendations from the IAEA was assessed. This assessment led to the elaboration of proposals for improvement as well as the identification of good practices. The methodology used to perform this assessment was the SARIS methodology, developed by the IAEA. This paper will describe the most relevant findings of this study. (author)

The safe transport of radioactive materials

International Nuclear Information System (INIS)

Swindell, G.E.

1975-01-01

In the course of transport by road, rail, sea and air, consignments of radioactive material are in close proximity to ordinary members of the public and in most cases they are loaded and unloaded by transport workers who have no special training or experience in the handling of radioactive substances. The materials being transported cover a wide variety - ranging from small batches of short-lived radionuclides used in medical practice which can be transported in small sealed lead pots in cardboard boxes, to large, extremely radioactive consignments of irradiated nuclear fuel in flasks weighing many tons. With the growing development of nuclear power programmes the transport of irradiated fuel is likely to increase markedly. It is clear that unless adequate regulations concerning the design and assembly of the packages containing these materials are precisely set down and strictly carried out, there would be a high probability that some of the radioactive contents would be released, leading to contamination of other transported goods and the general environment, and to the delivery of a radiation dose to the transport workers and the public. An additional requirement is that the transport should proceed smoothly and without delay. This is particularly important for radioactive materials of short half-life, which would lose significant amounts of their total activity in unnecessary delays at international boundaries. Therefore, it is essential that the regulations are also enforced, to ensure that the radioactive material is contained and the surrounding radiation level reduced to a value which poses no threat to other sensitive goods such as photographic film, or to transport workers and other passengers. These regulations should be as uniform as possible on an international basis, so that consignments can move freely from one country to another with as little delay as possible at the frontiers. (author)

An aqueous, polymer-based redox-flow battery using non-corrosive, safe, and low-cost materials

Science.gov (United States)

Janoschka, Tobias; Martin, Norbert; Martin, Udo; Friebe, Christian; Morgenstern, Sabine; Hiller, Hannes; Hager, Martin D.; Schubert, Ulrich S.

2015-11-01

For renewable energy sources such as solar, wind, and hydroelectric to be effectively used in the grid of the future, flexible and scalable energy-storage solutions are necessary to mitigate output fluctuations. Redox-flow batteries (RFBs) were first built in the 1940s and are considered a promising large-scale energy-storage technology. A limited number of redox-active materials--mainly metal salts, corrosive halogens, and low-molar-mass organic compounds--have been investigated as active materials, and only a few membrane materials, such as Nafion, have been considered for RFBs. However, for systems that are intended for both domestic and large-scale use, safety and cost must be taken into account as well as energy density and capacity, particularly regarding long-term access to metal resources, which places limits on the lithium-ion-based and vanadium-based RFB development. Here we describe an affordable, safe, and scalable battery system, which uses organic polymers as the charge-storage material in combination with inexpensive dialysis membranes, which separate the anode and the cathode by the retention of the non-metallic, active (macro-molecular) species, and an aqueous sodium chloride solution as the electrolyte. This water- and polymer-based RFB has an energy density of 10 watt hours per litre, current densities of up to 100 milliamperes per square centimetre, and stable long-term cycling capability. The polymer-based RFB we present uses an environmentally benign sodium chloride solution and cheap, commercially available filter membranes instead of highly corrosive acid electrolytes and expensive membrane materials.

An aqueous, polymer-based redox-flow battery using non-corrosive, safe, and low-cost materials.

Science.gov (United States)

Janoschka, Tobias; Martin, Norbert; Martin, Udo; Friebe, Christian; Morgenstern, Sabine; Hiller, Hannes; Hager, Martin D; Schubert, Ulrich S

2015-11-05

For renewable energy sources such as solar, wind, and hydroelectric to be effectively used in the grid of the future, flexible and scalable energy-storage solutions are necessary to mitigate output fluctuations. Redox-flow batteries (RFBs) were first built in the 1940s and are considered a promising large-scale energy-storage technology. A limited number of redox-active materials--mainly metal salts, corrosive halogens, and low-molar-mass organic compounds--have been investigated as active materials, and only a few membrane materials, such as Nafion, have been considered for RFBs. However, for systems that are intended for both domestic and large-scale use, safety and cost must be taken into account as well as energy density and capacity, particularly regarding long-term access to metal resources, which places limits on the lithium-ion-based and vanadium-based RFB development. Here we describe an affordable, safe, and scalable battery system, which uses organic polymers as the charge-storage material in combination with inexpensive dialysis membranes, which separate the anode and the cathode by the retention of the non-metallic, active (macro-molecular) species, and an aqueous sodium chloride solution as the electrolyte. This water- and polymer-based RFB has an energy density of 10 watt hours per litre, current densities of up to 100 milliamperes per square centimetre, and stable long-term cycling capability. The polymer-based RFB we present uses an environmentally benign sodium chloride solution and cheap, commercially available filter membranes instead of highly corrosive acid electrolytes and expensive membrane materials.

Instructions for safe transport of radioactive materials

International Nuclear Information System (INIS)

2005-01-01

This entrance includes 5 chapters and tables and supplement. Chapter I contains the definitions and general provisions contained 5 materials. Chapter II contains radioactive materials packaging and permissible limits and it contains 8 materials. The provisions of Chapter III contains descriptions Missionaries. Chapter IV describes shipping instructions. As for the separation of V It contains Final provisions. The entrance contains number of tables speaks of the basic values of radioactive isotopes and radiation also limits activity and the requirements of industrial parcels and limits transactions to transport freight containers, as well as the International Classification of hazardous materials. This also includes entrance to the Supplement to some forms and Alohat

Implementation of the 1996 edition of the IAEA regulations for the safe transport of radioactive material

International Nuclear Information System (INIS)

Rawl, R.R.; Kervella, O.

1998-01-01

The International Atomic Energy Agency (IAEA) completed a 10 year and revision of its 'Regulations for the Safe Transport of Radioactive Material' with approval of the amendments by its Board of Governors in September 1996. The revised edition contains some important changes in the regulations, including: type C package requirements; provisions for low dispersible material; uranium hexafluoride packaging; exemption value specifications; operational requirements, including the creation of a criticality safety index and new proper shipping names/UN numbers. The 1996 edition of the IAEA regulations has been published and corresponding revisions now being considered by the international transport safety organizations and Member States. In particular, the United Nations Committee of Experts on the Transport of Dangerous Goods, International Civil Aviation Organization and International Maritime Organization and preparing revisions to take into account the revised Class 7 requirements. An effective date of 1 January 2001 has been recommended so that international and domestic requirements might come into force simultaneously, thereby avoiding disruptive out-of-phase implementation. (authors)

Plutonium safe handling

International Nuclear Information System (INIS)

Tvehlov, Yu.

2000-01-01

The abstract, prepared on the basis of materials of the IAEA new leadership on the plutonium safe handling and its storage (the publication no. 9 in the Safety Reports Series), aimed at presenting internationally acknowledged criteria on the radiation danger evaluation and summarizing the experience in the safe management of great quantities of plutonium, accumulated in the nuclear states, is presented. The data on the weapon-class and civil plutonium, the degree of its danger, the measures for provision of its safety, including the data on accident radiation consequences with the fission number 10 18 , are presented. The recommendations, making it possible to eliminate the super- criticality danger, as well as ignition and explosion, to maintain the tightness of the facility, aimed at excluding the radioactive contamination and the possibility of internal irradiation, to provide for the plutonium security, physical protection and to reduce irradiation are given [ru

Assessment of the application of the IAEA regulations for the safe transport of radioactive material

International Nuclear Information System (INIS)

1986-12-01

The IAEA, working with the individual Member States, undertook to examine the manner in which domestic, import, export and through-country shipments of radioactive materials are controlled and regulated worldwide. The information to be examined was collected by a questionnaire, which was sent to Member States in July 1984. Copies of the letter and the questionnaire are in Appendix I of this document. The follow-up letters, repeating the request to provide the IAEA with data and asking authorization to publish the data obtained through the questionnaire, were sent in February 1985 (Appendix II and III). By the end of June 1986 completed questionnaires had been received from 53 Member States. These Member States are listed in Appendix IV. The results of the examination are summarized in this report. The results indicate the important role the international organizations play in the transport of radioactive material. All the Member States involved in this examination regulate the transport of radioactive material within their country on the basis of international agreements, regulations and recommendations. The IAEA Regulations for the Safe Transport of Radioactive Material, Safety Series No. 6, is the ultimately controlling document since it serves as the basis for the radioactive material portions of other international transport documents (Appendix V) and since it is made directly binding in the regulations of many countries. In addition to the questions concerning the adoption of the regulations, some questions on the implementation of the transport regulations, e.g. on competent authorities and other regulatory bodies as well as quality assurance, were presented in the questionnaire. This report concerns only the adoption of the regulations

Safe sex

Science.gov (United States)

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

Epoxidized soy bean oil migrating from the gaskets of lids into food packed in glass jars. Analysis by on-line liquid chromatography-gas chromatography.

Science.gov (United States)

Fankhauser-Noti, Anja; Fiselier, Katell; Biedermann-Brem, Sandra; Grob, Koni

2005-08-05

The migration of epoxidized soy bean oil (ESBO) from the gasket in the lids of glass jars into foods, particularly those rich in edible oil, often far exceeds the legal limit (60 mg/kg). ESBO was determined through a methyl ester isomer of diepoxy linoleic acid. Transesterification occurred directly in the homogenized food. From the extracted methyl esters, the diepoxy components were isolated by normal-phase LC and transferred on-line to gas chromatography with flame ionization detection using the on-column interface in the concurrent solvent evaporation mode. The method involves verification elements to ensure the reliability of the results for every sample analyzed. The detection limit is 2-5 mg/kg, depending on the food. Uncertainty of the procedure is below 10%.

The safe home project.

Science.gov (United States)

Arphorn, Sara; Jiraniratisai, Sopaphan; Rungtakul, Rungsri; Phutta, Nikom

2011-12-01

The Thai Health Promotion Foundation supported the Improvement of Quality of Life of Informal Workers project in Ban Luang District, Amphur Photaram, Ratchaburi Province. There were many informal workers in Ban Luang District. Sweet-crispy fish producers in Ban Luang were the largest group among the sweet-crispy fish producers in Thailand. This project was aimed at improving living and working conditions of informal workers, with a focus on the sweet-crispy fish group. Good practices of improved living and working conditions were used to help informal workers build safe, healthy and productive work environments. These informal workers often worked in substandard conditions and were exposed to various hazards in the working area. These hazards included risk of exposure to hot work environment, ergonomics-related injuries, chemical hazards, electrical hazards etc. Ergonomics problems were commonly in the sweet-crispy fish group. Unnatural postures such as prolonged sitting were performed dominantly. One hundred and fifty informal workers participated in this project. Occupational health volunteers were selected to encourage occupational health and safety in four groups of informal workers in 2009. The occupational health volunteers trained in 2008 were farmers, beauty salon workers and doll makers. The occupational health and safety knowledge is extended to a new informal worker group: sweet-crispy fish producer, in 2009. The occupational health and safety training for sweet-crispy fish group is conducted by occupational health volunteers. The occupational health volunteers increased their skills and knowledge assist in to make safe home and safe community through participatory oriented training. The improvement of living and working condition is conducted by using a modified WISH, Work Improvement for Safe Home, checklist. The plans of improvement were recorded. The informal workers showed improvement mostly on material handling and storage. The safe uses and safe

Regulations for the Safe Transport of Radioactive Material. 2012 Edition. Specific Safety Requirements (Arabic Edition)

Energy Technology Data Exchange (ETDEWEB)

NONE

2012-07-01

The IAEA's Statute authorizes the Agency to 'establish or adopt' standards of safety for protection of health and minimization of danger to life and property' - standards that the IAEA must use in its own operations, and which States can apply by means of their regulatory provisions for nuclear and radiation safety. The IAEA does this in consultation with the competent organs of the United Nations and with the specialized agencies concerned. A comprehensive set of high quality standards under regular review is a key element of a stable and sustainable global safety regime, as is the IAEA's assistance in their application. The IAEA commenced its safety standards programme in 1958. The emphasis placed on quality, fitness for purpose and continuous improvement has led to the widespread use of the IAEA standards throughout the world. The Safety Standards Series now includes unified Fundamental Safety Principles, which represent an international consensus on what must constitute a high level of protection and safety. With the strong support of the Commission on Safety Standards, the IAEA is working to promote the global acceptance and use of its standards. Standards are only effective if they are properly applied in practice. The IAEA's safety services encompass design, siting and engineering safety, operational safety, radiation safety, safe transport of radioactive material and safe management of radioactive waste, as well as governmental organization, regulatory matters and safety culture in organizations. These safety services assist Member States in the application of the standards and enable valuable experience and insights to be shared. Regulating safety is a national responsibility, and many States have decided to adopt the IAEA's standards for use in their national regulations. For parties to the various international safety conventions, IAEA standards provide a consistent, reliable means of ensuring the effective fulfilment of obligations under the conventions

Regulations for the Safe Transport of Radioactive Material. 2012 Edition. Specific Safety Requirements (Chinese Edition)

Energy Technology Data Exchange (ETDEWEB)

NONE

2013-03-01

The IAEA's Statute authorizes the Agency to 'establish or adopt' standards of safety for protection of health and minimization of danger to life and property' - standards that the IAEA must use in its own operations, and which States can apply by means of their regulatory provisions for nuclear and radiation safety. The IAEA does this in consultation with the competent organs of the United Nations and with the specialized agencies concerned. A comprehensive set of high quality standards under regular review is a key element of a stable and sustainable global safety regime, as is the IAEA's assistance in their application. The IAEA commenced its safety standards programme in 1958. The emphasis placed on quality, fitness for purpose and continuous improvement has led to the widespread use of the IAEA standards throughout the world. The Safety Standards Series now includes unified Fundamental Safety Principles, which represent an international consensus on what must constitute a high level of protection and safety. With the strong support of the Commission on Safety Standards, the IAEA is working to promote the global acceptance and use of its standards. Standards are only effective if they are properly applied in practice. The IAEA's safety services encompass design, siting and engineering safety, operational safety, radiation safety, safe transport of radioactive material and safe management of radioactive waste, as well as governmental organization, regulatory matters and safety culture in organizations. These safety services assist Member States in the application of the standards and enable valuable experience and insights to be shared. Regulating safety is a national responsibility, and many States have decided to adopt the IAEA's standards for use in their national regulations. For parties to the various international safety conventions, IAEA standards provide a consistent, reliable means of ensuring the effective fulfilment of obligations under the conventions

Regulations for the Safe Transport of Radioactive Material. 2012 Edition. Specific Safety Requirements (French Edition)

International Nuclear Information System (INIS)

2013-01-01

The IAEA's Statute authorizes the Agency to ''establish or adopt standards of safety for protection of health and minimization of danger to life and property'' - standards that the IAEA must use in its own operations, and which States can apply by means of their regulatory provisions for nuclear and radiation safety. The IAEA does this in consultation with the competent organs of the United Nations and with the specialized agencies concerned. A comprehensive set of high quality standards under regular review is a key element of a stable and sustainable global safety regime, as is the IAEA's assistance in their application. The IAEA commenced its safety standards programme in 1958. The emphasis placed on quality, fitness for purpose and continuous improvement has led to the widespread use of the IAEA standards throughout the world. The Safety Standards Series now includes unified Fundamental Safety Principles, which represent an international consensus on what must constitute a high level of protection and safety. With the strong support of the Commission on Safety Standards, the IAEA is working to promote the global acceptance and use of its standards. Standards are only effective if they are properly applied in practice. The IAEA's safety services encompass design, siting and engineering safety, operational safety, radiation safety, safe transport of radioactive material and safe management of radioactive waste, as well as governmental organization, regulatory matters and safety culture in organizations. These safety services assist Member States in the application of the standards and enable valuable experience and insights to be shared. Regulating safety is a national responsibility, and many States have decided to adopt the IAEA's standards for use in their national regulations. For parties to the various international safety conventions, IAEA standards provide a consistent, reliable means of ensuring the effective fulfilment of obligations under the

Regulations for the Safe Transport of Radioactive Material. 2012 Edition. Specific Safety Requirements (Chinese Edition)

International Nuclear Information System (INIS)

2013-01-01

The IAEA's Statute authorizes the Agency to 'establish or adopt' standards of safety for protection of health and minimization of danger to life and property' - standards that the IAEA must use in its own operations, and which States can apply by means of their regulatory provisions for nuclear and radiation safety. The IAEA does this in consultation with the competent organs of the United Nations and with the specialized agencies concerned. A comprehensive set of high quality standards under regular review is a key element of a stable and sustainable global safety regime, as is the IAEA's assistance in their application. The IAEA commenced its safety standards programme in 1958. The emphasis placed on quality, fitness for purpose and continuous improvement has led to the widespread use of the IAEA standards throughout the world. The Safety Standards Series now includes unified Fundamental Safety Principles, which represent an international consensus on what must constitute a high level of protection and safety. With the strong support of the Commission on Safety Standards, the IAEA is working to promote the global acceptance and use of its standards. Standards are only effective if they are properly applied in practice. The IAEA's safety services encompass design, siting and engineering safety, operational safety, radiation safety, safe transport of radioactive material and safe management of radioactive waste, as well as governmental organization, regulatory matters and safety culture in organizations. These safety services assist Member States in the application of the standards and enable valuable experience and insights to be shared. Regulating safety is a national responsibility, and many States have decided to adopt the IAEA's standards for use in their national regulations. For parties to the various international safety conventions, IAEA standards provide a consistent, reliable means of ensuring the effective fulfilment of obligations under the conventions

Regulations for the Safe Transport of Radioactive Material. 2012 Edition. Specific Safety Requirements (Arabic Edition)

International Nuclear Information System (INIS)

2012-01-01

The IAEA's Statute authorizes the Agency to 'establish or adopt' standards of safety for protection of health and minimization of danger to life and property' - standards that the IAEA must use in its own operations, and which States can apply by means of their regulatory provisions for nuclear and radiation safety. The IAEA does this in consultation with the competent organs of the United Nations and with the specialized agencies concerned. A comprehensive set of high quality standards under regular review is a key element of a stable and sustainable global safety regime, as is the IAEA's assistance in their application. The IAEA commenced its safety standards programme in 1958. The emphasis placed on quality, fitness for purpose and continuous improvement has led to the widespread use of the IAEA standards throughout the world. The Safety Standards Series now includes unified Fundamental Safety Principles, which represent an international consensus on what must constitute a high level of protection and safety. With the strong support of the Commission on Safety Standards, the IAEA is working to promote the global acceptance and use of its standards. Standards are only effective if they are properly applied in practice. The IAEA's safety services encompass design, siting and engineering safety, operational safety, radiation safety, safe transport of radioactive material and safe management of radioactive waste, as well as governmental organization, regulatory matters and safety culture in organizations. These safety services assist Member States in the application of the standards and enable valuable experience and insights to be shared. Regulating safety is a national responsibility, and many States have decided to adopt the IAEA's standards for use in their national regulations. For parties to the various international safety conventions, IAEA standards provide a consistent, reliable means of ensuring the effective fulfilment of obligations under the conventions

Safe handling of tritium

International Nuclear Information System (INIS)

1991-01-01

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

Effect of the Crevice Former on the Corrosion Behavior of 316L Stainless Steel in Chloride-Containing Synthetic Tap Water

Science.gov (United States)

Kim, Seon-Hong; Lee, Ji-Hoon; Kim, Jung-Gu; Kim, Woo-Cheol

2018-05-01

To restrain the failure of the plate heat exchanger (PHE) in customer boiler working fluid, the effect of crevice former type on the corrosion behavior of the 316L stainless steel plate was investigated using electrochemical methods and surface analyses in chloride-containing synthetic tap water (60 °C). The localized corrosion under metal-metal crevice condition was initiated more easily than that under the metal-gasket crevice condition due to the restricted mass transport at the gasket crevice mouth. However, the anodic current under the metal-metal crevice condition was lower than that under metal-gasket crevice condition at a higher anodic potential, indicating that that the metal dissolution under EPDM crevice would be higher than that under metal crevice under the accelerated corrosion condition. Because narrow crevice gap that was formed under gasket accelerated the anodic dissolution at the crevice mouth, the perforation tendency under metal-gasket crevice condition is much higher than that under metal-metal crevice condition. As a result, the crevice geometry, especially the crevice gap, mainly affected the corrosion behavior of PHE material.

Regulations for the safe transport of radioactive material. 1985 ed. Supplement 1988

International Nuclear Information System (INIS)

1988-01-01

A major revision of the Agency's Regulations for the Safe Transport of Radioactive Material, Safety Series No. 6, was undertaken during a period of several years, culminating in the publication of the 1985 Edition. In order to consider minor problems in the new edition, the Agency convened a panel of experts in January 1986. This panel recommended some amendments which were subsequently published as Supplement 1986 to the Regulations. A further review panel meeting took place in June 1987. The amendments which were recommended for early adoption were themselves divided into two kinds. The first of these are designated as minor changes. The second kind of amendment recommended for early adoption comprises actual changes to regulatory provisions. Several changes of this second type were recommended by the panel and are included in this Supplement. The Supplement also contains the amended texts of the supporting documents, Safety Series Nos 7, 37 and 80, which are necessary to correct minor errors as well as to provide complementary information for the changes introduced to the Regulations themselves. In addition, the Supplement embodies the contents of Supplement 1986, which is consequently superseded.

Advisory group for the comprehensive review of the Agency's regulations for the safe transport of radioactive materials. Vienna, 1-12 September 1980

International Nuclear Information System (INIS)

Rawl, R.R.

1981-05-01

The discussions and recommendations for the revision of the IAEA regulations for the safe transport of radioactive materials are reported. The last revision of the regulations was published in 1973. The regulations have been adopted by all international bodies concerned with transport and by almost all individual Member States. In view of the developments in the means of transport, the volume of traffic and the nature of materials transported, Member States and international organizations rely on the Agency for advice and guidance. Hence the regulations are to be reviewed by 1983

Regulations for the safe transport of radioactive materials

International Nuclear Information System (INIS)

Kgogo, Obonye

2016-04-01

The report provides insight and investigates whether Transport Regulations in Botswana follow international standards for transport of radioactive material. Radioactive materials are very useful in most of our activities and are manufactured in different countries, therefore end up traversing from one country to another and being transported in national roads .The IAEA regulation for the Transport of radioactive material is used as the reference guideline in this study. The current Regulations for Transport of radioactive material in Botswana do not cover all factors which need to be considered when transporting radioactive although they refer to IAEA regulations. Basing on an inadequacy of the regulations and category of radioactive materials in the country recommendations were made concerning security, packaging and worker training's. The regulations for the Transport of radioactive material in Botswana need to be reviewed and updated so that they can relate to international standard. (au)

The IAEA regulations for the safe transport of radioactive material; new strategies for the future

International Nuclear Information System (INIS)

Selling, H.A.; Brittinger, M.T.M.

1993-01-01

This paper presents a historic review of 30 years experience with the IAEA's Regulations for the Safe Transport of Radioactive Material as the basis for regulatory control of those materials worldwide. It is demonstrated that the underlying principles and fundamental philosophy have proven their validity and have been the main reason for the excellent safety record of transport operations. The IAEA Regulations are currently halfway a comprehensive revision process aiming at the publication of a new edition by 1996. Although the main principles are likely to be maintained in the next edition of the Regulations, some developments in this area will undoubtedly have an effect on their structure. The main new developments are: the air transport of large quantities of radioactive material, requiring that a risk basis be established which is comparable with other modes of transport, transport of uranium hexafluoride requiring provisions which include the associated chemical hazards, the transport of large volumes of radioactive waste originating from decommissioning of nuclear power stations, and the influence of the new risk estimates for exposure to ionizing radiation and consequently the lower dose limits as recommended by ICRP. This paper will make an attempt to identify the problems associated with those developments, to outline its programme of activities intended to address the problems and to suggest possible solutions as recommended by the IAEA senior advisory group in this subject area. (J.P.N.)

Guidelines for safe design of shipping packages against brittle fracture

International Nuclear Information System (INIS)

1993-08-01

In 1992, the ninth meeting of the Standing Advisory Group on the Safe Transport of Radioactive Materials recommended the publication of this TECDOC in an effort to promote the widest debate on the criteria for the brittle fracture safe design of transport packages. The published IAEA advice on the influence of brittle fracture on material integrity is contained in Appendix IX of the Advisory Material for the IAEA Regulations for the Safety Transport of Radioactive Material (1985 Edition, as amended 1990), Safety Series No. 37. This guidance is limited in scope, dealing only with ferritic steels in general terms. It is becoming more common for designers to specify materials other than austenitic stainless steel for packaging components. The data on ferritic steels cannot be assumed to apply to other metals, hence the need for further guidance on the development of relationships describing material properties at low temperatures. The methods described in this TECDOC will be considered by the Revision Panel for inclusion in the 1996 Edition of the IAEA Regulations for the Safe Transport of Radioactive Material and the supporting documents. If accepted by the Revision Panel, this advice will be a candidate for upgrading to a Safety Practice. In the interim period, this TECDOC offers provisional advice on brittle fracture evaluation. It is acknowledged that, at this stage, the views expressed do not necessarily reflect those of the governments of Member States or organizations under whose auspices this manuscript was produced. Refs and figs

Experiences for the Safe and Secure transport of Radioactive Material in Islamic Republic of Iran

International Nuclear Information System (INIS)

Hajizadeh, B.; Eshraghi, A.; Deevband, M.R.; Kardan, M.R.

2016-01-01

The Iranian Nuclear Regulatory Authority (INRA) has been addressed the actions to be taken in respect of the safe and secure transport of radioactive material. Firstly, INRA translated TS-R-1 and approved it as national standard and imparted it to all entities that engage in transport of radioactive material. Training course was provided for the designers, consignors, carriers and consignees based on their actions in transport of radioactive material. All radioactive material carrier companies were enforced to observe all aspects of national standard and receive an authorized license of National Radiation Protection Department (NRPD). The NRPD has written procedures to regain control of the radiation sources together with the National Waste Management Department. Transport arrangements are in place for imported and exported sources. According to the Code of Conduct on safety and security, the sources category I, II and III have been registered in data bases carefully so far. All the licensees are obligated to inform the Regulatory Authority for any changes in position, application, possession, transfer or waste of radiation sources. There is a formal agreement with the National Security Council to permit the import of scrap metal at major entry points on the borders. Scrap metal importers are required to use these points of entry which are monitored by officers of the NRPD and portal gate monitors which are installed at the main entry points and be controlled from unique centre. If required, the NRPD will supply staff to other border entry points. Presently some portal gate monitors are in progress at the borderline customs also. All the major metal recycling facilities in IRAN have installed portal gate monitors to recheck their scrap metal imports. (author)

Experiences for the Safe and Secure Transport of Radioactive Material in Islamic Republic of Iran

International Nuclear Information System (INIS)

Hajizadeh, B.; Eshraghi, A.; Deevband, M.R.; Kardan, M.R.

2011-01-01

The Iranian Nuclear Regulatory Authority (INRA) has been addressed the actions to be taken in respect of the safe and secure transport of radioactive material. Firstly, INRA translated TS-R-1 and approved it as national standard and imparted it to all entities that engage in transport of radioactive material. Training course was provided for the designers, consignors, carriers and consignees based on their actions in transport of radioactive material. All radioactive material carrier companies were enforced to observe all aspects of national standard and receive an authorized license of National Radiation Protection Department (NRPD). The NRPD has written procedures to regain control of the radiation sources together with the National Waste Management Department. Transport arrangements are in place for imported and exported sources. According to the Code of Conduct on safety and security, the sources category I, II and III have been registered in data bases carefully so far. All the licensees are obligated to inform the Regulatory Authority for any changes in position, application, possession, transfer or waste of radiation sources. There is a formal agreement with the National Security Council to permit the import of scrap metal at major entry points on the borders. Scrap metal importers are required to use these points of entry which are monitored by officers of the NRPD and portal gate monitors which are installed at the main entry points and be controlled from unique centre. If required, the NRPD will supply staff to other border entry points. Presently some portal gate monitors are in progress at the borderline customs also. All the major metal recycling facilities in IRAN have installed portal gate monitors to recheck their scrap metal imports. (author)

Premiering SAFE for Safety Added Fuel Element - 15020

International Nuclear Information System (INIS)

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

2015-01-01

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

The ICRP 60 and the agency's regulations for the safe transport of radioactive material

International Nuclear Information System (INIS)

Biaggio, A.L.; Novo, R.G.

1993-01-01

The International Commission on Radiological Protection (ICRP) has adopted its new '1990 Recommendations of the International Commission on Radiological Protection' in November 1990, they were published in 1991 as 'ICRP Publication 60.' Two main scenarios are considered by the new ICRP's recommendations: a) Protection in proposed and continuing practices (further subdivided as protection against actual exposures and protection against potential exposures); and b) Protection by intervention. Although intervention means any activity in order to decrease the overall exposure, removing existing sources, modifying pathways or reducing the number of exposed individuals, in relation to the transport of radioactive materials, protection by intervention is related mainly to emergency planning, while protection against actual and potential exposures can be considered as the subject of most of the requirements of the 'Regulations for the Safe Transport of Radioactive Material', of the International Atomic Energy Agency (IAEA). The on-going revision of the IAEA Safety Series No. 9, which is aimed at putting this publication in line with the new ICRP recommendations will, for the first time, provide a convalidated radiological framework for the 1996 revision of the Agency Transport Regulations. However, to adapt to the transport area the radiological principles and criteria will require a significant effort and a carefully evaluation of the overall impact of each change proposed. (J.P.N.)

Degradation of elastomers by tritium beta radiation

International Nuclear Information System (INIS)

Zapp, P.E.; Tuer, G.L. Jr.

1984-01-01

Based on its tritium radiation resistance, ethylene propylene rubber has been selected as a candidate for replacement of nitrile rubber in the SRP tritium facilities. A specification for flange gasket material has been developed for ethylene propylene such that its mechanical properties are similar to those of nitrile rubber. In-process testing of ethylene propylene and nitrile gaskets will be conducted in the tritium facilities under identical exposure conditions

Regulations of safe transport of radioactive material

International Nuclear Information System (INIS)

Patel, R.J.; Sumathi, E.

2017-01-01

BARC is a multi-disciplinary nuclear research organisation with facilities located at various parts of the country. The nuclear and radiological facilities in BARC include fuel fabrication facilities, nuclear research reactors, radiological laboratories, nuclear recycle facilities, waste management facilities and other associated facilities. RAdioactive Material (RAM) such as fresh nuclear fuel, irradiated fuel, radioactive sources, vitrified high level wastes, special nuclear material etc., are transported between these facilities either within the controlled premises or in public domain. In BARC the regulatory approval for the packages used for transport of RAM is issued by BARC Safety Council (BSC). Competent Authority for issuing the design approval for the BARC packages in public domain is Director, BARC. In this aspect BSC is assisted by Safety Review Committee-Transport of Radioactive Material (SRC-TRM) constituted by BSC entrusted with the mandate to ensure the packages are designed, manufactured and transported in accordance with the current regulations. This article summarizes the regulatory requirements for transport of RAM and experience in BARC facilities

FLiNaK compatibility studies with Inconel 600 and silicon carbide

Energy Technology Data Exchange (ETDEWEB)

Yoder, Graydon L., E-mail: yodergljr@ornl.gov [Oak Ridge National Laboratory, Bldg. 5700, MS 6167 Bethel Valley Rd., Oak Ridge, TN 37831 (United States); Heatherly, Dennis; Wilson, Dane [Oak Ridge National Laboratory, Bldg. 5700, MS 6167 Bethel Valley Rd., Oak Ridge, TN 37831 (United States); Caja, Mario [Electrochemical Systems, Inc. (ESI), 9320 Collingwood Rd., Knoxville, TN 37922 (United States)

2016-10-15

Highlights: • A versatile experimental design has been developed to examine liquid fluoride salt materials compatibility behavior. • Samples of silicon carbide and a grafoil/nickel spiral wound gasket were exposed to FLiNaK salt at 700 °C for 90 days and showed no degradation. • Alloy 600 showed material effects penetrating up to 300 μm below the salt interface after exposure to the salt for 90 days at 700 °C. • Comparison of the Alloy 600 corrosion results with existing data indicated that results were comparable to the few corrosion results available for Alloy 600. • Sapphire viewing windows incorporated in the experiment showed fogging by condensed salt components at the highest test temperatures. - Abstract: A small liquid fluoride salt test apparatus has been constructed and testing has been conducted to examine the compatibility of silicon carbide (SiC), Inconel 600 and a spiral wound gasket material in FLiNaK, the ternary eutectic alkaline metal fluoride salt mixture. These tests were conducted to evaluate materials and sealing systems that could be used in fluoride salt systems. Three months of testing at 700 °C was conducted to assure that these materials and seals would be acceptable when operating under prototypic operating conditions. The SiC specimens showed little or no change over the test period, while the spiral wound gasket material did not show any degradation except that salt might have been seeping into the outermost spirals of the gasket. The Inconel 600 specimens showed regions of voiding which penetrated the specimen surface to about 250 μm in depth. Analysis indicated that the salt had leached chrome from the Inconel surface, as was expected for this material.

40 CFR 59.625 - How do I select emission families?

Science.gov (United States)

2010-07-01

... material (including pigments, plasticizers, UV inhibitors, or other additives that may affect control of emissions). (2) Production method. (3) Spout and cap design. (4) Gasket material and design. (5) Emission...

Guideline for the preparation of safe operating procedures

International Nuclear Information System (INIS)

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

1981-03-01

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

Concept of an inherently-safe high temperature gas-cooled reactor

International Nuclear Information System (INIS)

Ohashi, Hirofumi; Sato, Hiroyuki; Tachibana, Yukio; Kunitomi, Kazuhiko; Ogawa, Masuro

2012-01-01

As the challenge to ensure no harmful release of radioactive materials at the accidents by deterministic approach instead to satisfy acceptance criteria or safety goal for risk by probabilistic approach, new concept of advanced reactor, an inherently-safe high temperature gas-cooled reactor, is proposed based on the experience of the operation of the actual High Temperature Gas-cooled Reactor (HTGR) in Japan, High Temperature Engineering Test Reactor (HTTR), and the design of the commercial plant (GTHTR300), utilizing the inherent safety features of the HTGR (i.e., safety features based on physical phenomena). The safety design philosophy of the inherently-safe HTGR for the safety analysis of the radiological consequences is determined as the confinement of radioactive materials is assured by only inherent safety features without engineered safety features, AC power or prompt actions by plant personnel if the design extension conditions occur. Inherent safety features to prevent the loss or degradation of the confinement function are identified. It is proposed not to apply the probabilistic approach for the evaluation of the radiological consequences of the accidents in the safety analysis because no inherent safety features fail for the mitigation of the consequences of the accidents. Consequently, there are no event sequences to harmful release of radioactive materials if the design extension conditions occur in the inherently-safe HTGR concept. The concept and future R and D items for the inherently-safe HTGR are described in this paper.

Guideline for the preparation of safe operating procedures

International Nuclear Information System (INIS)

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

1977-03-01

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

Implementation of Safe-by-Design for Nanomaterial Development and Safe Innovation: Why We Need a Comprehensive Approach.

Science.gov (United States)

Kraegeloh, Annette; Suarez-Merino, Blanca; Sluijters, Teun; Micheletti, Christian

2018-04-14

Manufactured nanomaterials (MNMs) are regarded as key components of innovations in various fields with high potential impact (e.g., energy generation and storage, electronics, photonics, diagnostics, theranostics, or drug delivery agents). Widespread use of MNMs raises concerns about their safety for humans and the environment, possibly limiting the impact of the nanotechnology-based innovation. The development of safe MNMs and nanoproducts has to result in a safe as well as functional material or product. Its safe use, and disposal at the end of its life cycle must be taken into account too. However, not all MNMs are similarly useful for all applications, some might bear a higher hazard potential than others, and use scenarios could lead to different exposure probabilities. To improve both safety and efficacy of nanotechnology, we think that a new proactive approach is necessary, based on pre-regulatory safety assessment and dialogue between stakeholders. On the basis of the work carried out in different European Union (EU) initiatives, developing and integrating MNMs Safe-by-Design and Trusted Environments (NANoREG, ProSafe, and NanoReg2), we present our point of view here. This concept, when fully developed, will allow for cost effective industrial innovation, and an exchange of key information between regulators and innovators. Regulators are thus informed about incoming innovations in good time, supporting a proactive regulatory action. The final goal is to contribute to the nanotechnology governance, having faster, cheaper, effective, and safer nano-products on the market.

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

Science.gov (United States)

2011-03-08

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

Penelitian pengaruh variasi China clay dan napthenoc oil terhadap kekerasan dan ketahanan sobek kompon karet untuk lis pintu almari es

Directory of Open Access Journals (Sweden)

Sri Brataningsih Puji Lestari

1995-06-01

Full Text Available The aim of this research is to know influence of naphthenic oil and filler china clay to the physical properties of hardness and tear resistant rubber compound for refrigerator gasket. It makes from natural rubber (pale crepe and synthetic rubber (SBR 1502 as material with addition ingredients are china clay, stearic, guanidine, naphthenic oil, paraffin wax, coumarone resin, zink okside, stearic acid, guanidine, sulfonamide, ASOP, titan diokside, brown factice and sulphur. Rubber compound for refrigerator gasket, formed to slab by hydraulic press at 150C and 150 kg/cm2. Than tasted hardness and tear resistant. The result of this research indicated naphthenic oil and filler china clay variation are high significant to hardness and tear resistant properties of rubber compound for refrigerator gasket.

Development of Safe Food Handling Guidelines for Korean Consumers.

Science.gov (United States)

Kang, Hee-Jin; Lee, Min-Woo; Hwang, In-Kyeong; Kim, Jeong-Weon

2015-08-01

The purpose of this study was to develop guidelines for Korean consumers with regard to safe food handling practices at home by identifying current food handling issues. Korean consumers' behaviors regarding their safe food handling were identified via survey questionnaires that included items on individual hygiene practices, prepreparation steps when cooking, the cooking process, and the storage of leftover foods. The subjects were 417 Korean parents with elementary school children living in Seoul and Gyeonggi Province in the central area of Korea. The survey results revealed gaps between the knowledge or practices of Korean consumers and scientific evidence pertaining to safe food handling practices. Based on these findings, a leaflet on safe food handling guidelines was developed in accordance with Korean food culture. These guidelines suggest personal hygiene practices as well as fundamental principles and procedures for safe food handling from the stage of food purchase to that of keeping leftover dishes. A pilot application study with 50 consumers revealed that the guidelines effectively improved Korean consumers' safe food handling practices, suggesting that they can serve as practical educational material suitable for Korean consumers.

105-H Reactor Interim Safe Storage Project Final Report

International Nuclear Information System (INIS)

Ison, E.G.

2008-01-01

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

EUROSAFE forum 2013. Safe disposal of nuclear waste

Energy Technology Data Exchange (ETDEWEB)

NONE

2013-07-01

The proceedings of the EUROSAFE forum 2013 - safe disposal of nuclear waste include contributions to the following topics: Nuclear installation safety - assessment; nuclear installation safety - research; waste and decommissioning - dismantling; radiation protection, 3nvironment and emergency preparedness; security of nuclear installations and materials.

Cool and Safe: Multiplicity in Safe Innovation at Unilever

Science.gov (United States)

Penders, Bart

2011-01-01

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

NCO-5 Technician Cuts Finger while Cutting Gasket Material

Energy Technology Data Exchange (ETDEWEB)

Trujillo, Stanley [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Schreiber, Stephen Bruce [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Mcneel, John Worth [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Monsalve-Jones, Robert A. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Welsh, Mark [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Ortega, Greg N. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Martinez, Xavier Baltazar [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Padilla, Ruby A. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2015-12-10

As part of the ADPSM Safety Improvement Plan, the WSST has established a subcommittee for a Learning Team. The purpose of a Learning Team is to transfer and communicate the information into operational feedback and improvement. We want to pay attention to the small things that go wrong because they are often early warning signals and may provide insight into the health of the whole system.

The quest for safe and reliable fuel cladding materials

Energy Technology Data Exchange (ETDEWEB)

Pino, Eddy S.; Abe, Alfredo Y., E-mail: eddypino132@hotmail.com [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil); Giovedi, Claudia, E-mail: claudia.giovedi@labrisco.usp.br [Universidade de Sao Paulo (POLI/USP), Sao Paulo, SP (Brazil). Lab. de Analise, Avaliacao e Gerenciamento de Risco

2015-07-01

The tragic Fukushima Daiichi Nuclear Plant accident of March, 2011, has brought great unrest and challenge to the nuclear industry, which, in collaboration with universities and nuclear research institutes, is making great efforts to improve the safety in nuclear reactors developing accident tolerant fuels (ATF). This involves the study of different materials to be applied as cladding and, also, the improvement in the fuel properties in order to enhance the fuel performance and safety, specifically under accident conditions. Related to the cladding, iron based alloys and silicon carbide (SiC) materials have been studied as a good alternative. In the case of austenitic stainless steel, there is the advantage that the austenitic stainless steel 304 was used as cladding material in the first PWR (Pressurized Water Reactor) registering a good performance. Then, alternated cladding materials such as iron based alloys (304, 310, 316, 347) should be used to replace the zirconium-based alloys in order to improve safety. In this paper, these cladding materials are evaluated in terms of their physical and chemical properties; among them, strength and creep resistance, thermal conductivity, thermal stability and corrosion resistance. Additionally, these properties are compared with those of conventional zirconium-based alloys, the most used material in actual PWR, to assess the advantages and disadvantages of each material concerning to fuel performance and safety contribution. (author)

The quest for safe and reliable fuel cladding materials

International Nuclear Information System (INIS)

Pino, Eddy S.; Abe, Alfredo Y.; Giovedi, Claudia

2015-01-01

The tragic Fukushima Daiichi Nuclear Plant accident of March, 2011, has brought great unrest and challenge to the nuclear industry, which, in collaboration with universities and nuclear research institutes, is making great efforts to improve the safety in nuclear reactors developing accident tolerant fuels (ATF). This involves the study of different materials to be applied as cladding and, also, the improvement in the fuel properties in order to enhance the fuel performance and safety, specifically under accident conditions. Related to the cladding, iron based alloys and silicon carbide (SiC) materials have been studied as a good alternative. In the case of austenitic stainless steel, there is the advantage that the austenitic stainless steel 304 was used as cladding material in the first PWR (Pressurized Water Reactor) registering a good performance. Then, alternated cladding materials such as iron based alloys (304, 310, 316, 347) should be used to replace the zirconium-based alloys in order to improve safety. In this paper, these cladding materials are evaluated in terms of their physical and chemical properties; among them, strength and creep resistance, thermal conductivity, thermal stability and corrosion resistance. Additionally, these properties are compared with those of conventional zirconium-based alloys, the most used material in actual PWR, to assess the advantages and disadvantages of each material concerning to fuel performance and safety contribution. (author)

The impact of the new IAEA transport regulations for the safe transport of radioactive materials on package design and transport

International Nuclear Information System (INIS)

Schneider, K.

1989-01-01

In April 1985 the 1985 Edition of the IAEA Safety Series No. 6, Regulations for the Safe Transport of Radioactive Materials, was issued. This is a completely revised edition which shall come into force internationally in the late eighties. This edition will supersede the 1973 (As Amended, 1979) edition. A paragraph by paragraph comparison is carried through, followed by a consideration on the impact on general requirements for packaging and transport. A detailed estimate on packaging design and transport is performed for typical products of the nuclear fuel cycle. The major practical consequences likely to be encountered are presented

Mechanical-property changes of structural composite materials after low-temperature proton irradiation: Implications for use in SSC magnet systems

International Nuclear Information System (INIS)

Morena, J.; Snead, C.L. Jr.; Czajkowski, C.; Skaritka, J.

1993-01-01

Longterm physical, mechanical, electrical, and other properties of advanced composites, plastics, and other polymer materials are greatly affected by high-energy proton, neutron, electron, and gamma radiation. The effects of high-energy particles on materials is a critical design parameter to consider when choosing polymeric structural, nonstructural, and elastomeric matrix resin systems. Polymer materials used for filled resins, laminates, seals, gaskets, coatings, insulation and other nonmetallic components must be chosen carefully, and reference data viewed with caution. Most reference data collected in the high-energy physics community to date reflects material property degradation using other than proton irradiations. In most instances, the data were collected for room-temperature irradiations, not 4.2 K or other cryogenic temperatures, and at doses less than 10 8 --10 9 Rad. Energetic proton (and the accompanying spallation-product particles) provide good simulation fidelity to the expected radiation fields predicted for the cold-mass regions of the SSC magnets, especially the corrector magnets. The authors present here results for some structural composite materials which were part of a larger irradiation-characterization of polymeric materials for SSC applications

Inherently safe passive gas monitoring system

Energy Technology Data Exchange (ETDEWEB)

Cordaro, Joseph V.; Bellamy, John Stephen; Shuler, James M.; Shull, Davis J.; Leduc, Daniel R.

2016-09-06

Generally, the present disclosure is directed to gas monitoring systems that use inductive power transfer to safely power an electrically passive device included within a nuclear material storage container. In particular, the electrically passive device can include an inductive power receiver for receiving inductive power transfer through a wall of the nuclear material storage container. The power received by the inductive power receiver can be used to power one or more sensors included in the device. Thus, the device is not required to include active power generation components such as, for example, a battery, that increase the risk of a spark igniting flammable gases within the container.

A Safe Protocol for Amalgam Removal

Directory of Open Access Journals (Sweden)

Dana G. Colson

2012-01-01

Full Text Available Today's environment has different impacts on our body than previous generations. Heavy metals are a growing concern in medicine. Doctors and individuals request the removal of their amalgam (silver mercury restorations due to the high mercury content. A safe protocol to replace the silver mercury filling will ensure that there is minimal if any absorption of materials while being removed. Strong alternative white composite and lab-processed materials are available today to create a healthy and functioning mouth. Preparation of the patient prior to the procedure and after treatment is vital to establish the excretion of the mercury from the body.

Characterization of nuclear reactor containment penetrations. Preliminary report

International Nuclear Information System (INIS)

Bump, T.R.; Seidensticker, R.W.; Shackelford, M.A.; Gambhir, V.K.; McLennan, G.L.

1984-06-01

This report summarizes the survey work conducted by Argonne National Laboratory on the design and details of major penetrations in 22 nuclear power plants. The survey includes all containment types and materials in current use. It also includes details of all types of penetrations (except for electrical penetration assemblies and valves) and the seals and gaskets used in them. The report provides a test matrix for testing major penetrations and for testing seals and gaskets in order to evaluate their leakage potential under severe accident conditions

The SafeCOP ECSEL Project: Safe Cooperating Cyber-Physical Systems Using Wireless Communication

DEFF Research Database (Denmark)

Pop, Paul; Scholle, Detlef; Hansson, Hans

2016-01-01

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

How safe is safe enough?

International Nuclear Information System (INIS)

Desnoyers, B.; Chanzy, Y.

2004-01-01

The IAEA Regulations for the Safe Transport of Radioactive Material, were historically established with the objective to reduce the probability that persons be exposed to unacceptable doses due to normal operation or accident situations during transport of radioactive material. Based on the International Basic Safety Standards for Protection against Ionizing Radiation (BSS), the definition, which was adopted for an unacceptable dose for an accident situation, is the excess of the maximum dose limits permissible in a single year for the occupational exposure of a worker in the BSS. Concerning the severity of accident situations, it has always be clearly stated that the objective of the tests for demonstrating ability to withstand accident conditions of transport was not to cover every accident condition, but solely most of them. The last available evaluations regarding the rate of accidents which are covered by the standardised accident conditions of transport defined in the IAEA Regulations give a range of about 80%, plus or minus 15% which depends on transport mode and studies. Consequently, slight variations in the capabilities of the packages to meet the specified performance would probably not have significant consequences on the protection level in case of accident. In the assessment of the compliance with the regulations, the tendency of experts, taking advantage of the enhanced performances of computer calculation codes, is to ask more and more calculations, with more and more accuracy, leading to more and more restrictions. Consequently, cost and delay are considerably increased without any evidence of an equivalent effect on the level of protection. This paper will initiate a reflection on the general objectives and principles when implementing the Regulations, in such a way that demonstrations remain cost effective, taking into account evolution of the techniques and a high level of safety

Safe Kids Worldwide

Science.gov (United States)

... Blog Videos Newsletter facebook twitter instagram pinterest gplus youtube Search Menu Why It Matters Who We Are What We Do Find Your Safe Kids Safe Kids Day Main menu Keeping All Kids Safe Safety Tips Get Involved 4 Star Charity Donate Text Burns and Scalds 4 tips ...

Regulations for the safe transport of radioactive material. 1985 ed. Supplement 1986

International Nuclear Information System (INIS)

1986-01-01

Following a six-year effort, a major revision to the Agency's Regulations for the Safe Transport of Radioactive Material (Safety Series No. 6) was issued in 1985. In order to address minor problems with the 1985 Edition of Safety Series No. 6, a panel of experts convened by the International Atomic Energy Agency met from 13 to 17 January 1986. This panel considered minor inconsistencies, omissions or errors that had occurred in the course of preparing the 1985 Edition of Safety Series No. 6, and recommended that two types of change be made. First, changes which will correct errors in the presentation of the text, translation errors (in the French, Russian and Spanish versions of the 1985 Edition), and drafting which failed to express the intent of the panels which reviewed the previous edition of the Regulations; these minor changes are promulgated herewith by the authority of the Director General. Secondly, changes of detail which can only be introduced in accordance with the procedure approved by the Board of Governors on 22 September 1972, which authorizes the Director General to promulgate such changes after giving Governments not less than ninety days' notice and taking into account any comments that they make. Three changes of this second type were recommended by the panel, and were circulated according to the 'ninety-day rule' amendment procedure on 3 February 1986. Those changes which received unanimous support by Member States are included in this Supplement. Corrected text to the 1985 Edition of Safety Series No. 6 (paragraphs, tables, etc.) is provided in this Supplement, and this corrected text supersedes the corresponding portions of the 1985 Edition of Safety Series No. 6.

Study of the hydro-mechanical behaviour of expanded graphite gaskets; Etude du comportement et de l`etancheite de joints en graphite expnase

Energy Technology Data Exchange (ETDEWEB)

Patron, E. [Electricite de France (EDF), Direction des Etudes et Recherches, 92 - Clamart (France)

1997-12-31

The poro-mechanical behaviour models developed by O. Coussy permit to consider various phenomena observed experimentally: thermo-hydro-mechanical couplings, plasticity, etc. The aim of this study is to implement the simplest poro-mechanical model (i.e. the isotropic linear poro-elastic model) to model the gasket hydro-mechanical behaviour. First, isotropic poro-elastic characteristics of expanded graphite have been estimated from these tests conducted at Departement Mecanique et Technologie des Composants (MTC) and data from literature. Then, analytical solutions of the tightness tests developed at the MTC Department have been carried out. These calculations provide a first estimation of porosity variations during a tightness tests with metal/metal contact or in elastic recovery, and during a `hot thermal transient`. Thickness controlled numerical calculations have proved the analytical calculations relevance. With regard to simulation of tests with metal/metal contact or `hot thermal transient`, stress controlled numerical calculations have pointed out: - a greater vertical displacement on the inner side of the graphite ring and - a z dependence of the radial displacement and thus a porous differential variation between the upper and lower faces of the ring. (author). 21 refs.

Photovoltaic panel clamp

Science.gov (United States)

Mittan, Margaret Birmingham [Oakland, CA; Miros, Robert H. J. [Fairfax, CA; Brown, Malcolm P [San Francisco, CA; Stancel, Robert [Loss Altos Hills, CA

2012-06-05

A photovoltaic panel clamp includes an upper and lower section. The interface between the assembled clamp halves and the module edge is filled by a flexible gasket material, such as EPDM rubber. The gasket preferably has small, finger like protrusions that allow for easy insertion onto the module edge while being reversed makes it more difficult to remove them from the module once installed. The clamp includes mounting posts or an integral axle to engage a bracket. The clamp also may include a locking tongue to secure the clamp to a bracket.

"Same Room, Safe Place".

Science.gov (United States)

Keene Woods, Nikki

2017-04-01

There are many different professional stances on safe sleep and then there is the reality of caring for a newborn. There is a debate among professionals regarding safe sleep recommendations. The continum of recommendations vary from the American Academy of Pediatrics (AAP) Safe Sleep Guidelines to the bed-sharing recommendations from the Mother-Baby Behavioral Sleep Laboratory. The lack of consistent and uniform safe sleep recommendations from health professionals has been confusing for families but has more recently raised a real professional ethical dilemma. Despite years of focused safe sleep community education and interventions, sleep-related infant deaths are on the rise in many communities. This commentary calls for a united safe sleep message from all health professionals to improve health for mothers and infants most at-risk, "Same Room, Safe Place."

Synthesis, Structure, and Sodium Mobility of Sodium Vanadium Nitridophosphate: A Zero-Strain and Safe High Voltage Cathode Material for Sodium-Ion Batteries

Directory of Open Access Journals (Sweden)

Huang Zhang

2017-06-01

Full Text Available Herein, the nitridophosphate Na3V(PO33N is synthesized by solid state method. X-ray diffraction (XRD and Rietveld refinement confirm the cubic symmetry with P213 space group. The material exhibits very good thermal stability and high operating voltage of 4.0 V vs. Na/Na+ due to V3+/V4+ redox couple. In situ X-ray diffraction studies confirm the two-phase (de-sodiation process to occur with very low volume changes. The refinement of the sodium occupancies reveal the low accessibility of sodium cations in the Na2 and Na3 sites as the main origin for the lower experimental capacity (0.38 eq. Na+, 28 mAh g−1 versus the theoretical one (1.0 eq. Na+, 74 mAh g−1. These observations provide valuable information for the further optimization of this materials class in order to access their theoretical electrochemical performance as a potentially interesting zero-strain and safe high-voltage cathode material for sodium-ion batteries.

Safeguards Automated Facility Evaluation (SAFE) methodology

International Nuclear Information System (INIS)

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

1978-08-01

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

Safe-geometry pneumatic nuclear fuel powder blender

International Nuclear Information System (INIS)

Lyon, W.L.

1980-01-01

A safe geometry nuclear fuel powder is claimed blender of a pneumatic type having a plurality of narrow flat-walled blending chambers or ''slab tanks'' extending radially outward from a pneumatic spouting tube having an inlet and an outlet at bottom and top, respectively, open to each slab tank or blending chamber and contained within a cylindrical cone-bottomed shell filled with neutron-absorbing material between the blending chambers

Safe transport of tritium-producing burnable absorber rods: Intergovernmental regulations perspective

International Nuclear Information System (INIS)

Steinhoff, R.L.; Patterson, J.; Helvey, E.

2000-01-01

The state, tribal, and local governments along the shipment corridors share the US Department of Energy's (DOE's) goal of safe and uneventful radioactive materials transportation. The various governmental bodies involved can have different interpretations of a safe and uneventful shipping campaign. However, that gap has narrowed in recent years, due in part to improved coordination among DOE and the affected states, tribes, and municipal governments. This paper describes how the interactions between a new DOE radioactive materials transportation program and the corridor governments bridged that gap to create a shipping campaign that most of those involved viewed as safer and more publicly acceptable than had the process not occurred. It also describes the successful interaction between two DOE shipment campaigns transporting along much of the same route during the same time period

DroidSafe

Science.gov (United States)

2016-12-01

Massachusetts Avenue, Build E19-750 Cambridge , MA 02139-4307 8. PERFORMING ORGANIZATION REPORT NUMBER 9. SPONSORING/MONITORING AGENCY NAME(S) AND ADDRESS...Activity objects illustrating the challenges of points-to and information flow analysis...measure how many malicious flows Droid- Safe was able to detect). As these results illustrate , DroidSafe implements an analysis of unprece- dented

STRRAP system-A software for hazardous materials risk assessment and safe distances calculation

International Nuclear Information System (INIS)

Godoy, S.M.; Santa Cruz, A.S.M.; Scenna, N.J.

2007-01-01

This work presents a powerful computational tool (Stochastic Toxic Release Risk Assessment Package, STRRAP) useful in risk assessment and emergency planning (safe distance calculation), which allows to handle the stochastic uncertainty of atmospheric parameters, critical for risk calculation when diffusion of hazardous gases or particulate matter occur as a consequence of an emission or accidental release. In fact, the random behaviour of wind intensity, wind direction, atmospheric stability and temperature, given a time horizon, (a season or a complete year), is taken into account considering also the day or night condition. STRRAP can be used for releases or emissions from static sources (for example a stack or a fixed tank in a facility) or from transportation accidents (road, rail, maritime and pipeline transport) involving different scenarios. After a stochastic simulation based on well-known diffusion models (dense and light gases, particulate matter) is carried out, the downwind pollutant concentrations are obtained, in order to compute safe distances and/or individual and societal risks. Some study cases are analyzed to show STRRAP capabilities

Long term integrity of spent fuel and construction materials for dry storage facilities

Energy Technology Data Exchange (ETDEWEB)

Saegusa, T [CRIEPI (Japan)

2012-07-01

In Japan, two dry storage facilities at reactor sites have already been operating since 1995 and 2002, respectively. Additionally, a large scale dry storage facility away from reactor sites is under safety examination for license near the coast and desired to start its operation in 2010. Its final storage capacity is 5,000tU. It is therefore necessary to obtain and evaluate the related data on integrity of spent fuels loaded into and construction materials of casks during long term dry storage. The objectives are: - Spent fuel rod: To evaluate hydrogen migration along axial fuel direction on irradiated claddings stored for twenty years in air; To evaluate pellet oxidation behaviour for high burn-up UO{sub 2} fuels; - Construction materials for dry storage facilities: To evaluate long term reliability of welded stainless steel canister under stress corrosion cracking (SCC) environment; To evaluate long term integrity of concrete cask under carbonation and salt attack environment; To evaluate integrity of sealability of metal gasket under long term storage and short term accidental impact force.

Safe havens in Europe

DEFF Research Database (Denmark)

Paldam, Martin

2013-01-01

Eleven safe havens exist in Europe providing offshore banking and low taxes. Ten of these states are very small while Switzerland is moderately small. All 11 countries are richer than their large neighbors. It is shown that causality is from small to safe haven to wealth, and that theoretically...... equilibriums are likely to exist where a certain regulation is substantially lower in a small country than in its big neighbor. This generates a large capital inflow to the safe havens. The pool of funds that may reach the safe havens is shown to be huge. It is far in excess of the absorptive capacity...... of the safe havens, but it still explains, why they are rich. Microstates offer a veil of anonymity to funds passing through, and Switzerland offers safe storage of funds....

Third meeting of the advisory group for the comprehensive review of the IAEA regulations for the safe transport of radioactive materials, Vienna, 7-11 November 1983

International Nuclear Information System (INIS)

Rawl, R.R.

This meeting was the third and final planned stage in the process to revise the Agency's Regulations for the Safe Transport of Radioactive Materials, Safety Series No. 6. Its task was to consider comments which had been submitted in response to the Agency's circulation of the third draft revision of Safety Series No. 6 and to make any necessary changes to the draft that the Advisory Group felt were necessary

Traveling Safely with Medicines

Science.gov (United States)

... Medications Safely My Medicine List How to Administer Traveling Safely with Medicines Planes, trains, cars – even boats ... your trip, ask your pharmacist about how to travel safely with your medicines. Make sure that you ...

Infant Safe Sleep Interventions, 1990-2015: A Review.

Science.gov (United States)

Salm Ward, Trina C; Balfour, Giselle M

2016-02-01

Sleep-related infant deaths remain a major public health issue. Multiple interventions have been implemented in efforts to increase adherence to safe sleep recommendations. We conducted a systematic review of the international research literature to synthesize research on interventions to reduce the risk of sleep-related deaths and their effectiveness in changing infant sleep practices. We searched PubMed, CINAHL, PsycINFO, and Google Scholar for peer-reviewed articles published between 1990 and 2015 which described an intervention and reported results. Twenty-nine articles were included for review. Studies focused on infant caregivers, health care professionals, peers, and child care professionals. Targeted behaviors included sleep position, location, removing items from the crib, breastfeeding, smoke exposure, clothing, pacifier use, and knowledge of Sudden Infant Death Syndrome. Most articles described multi-faceted interventions, including: one-on-one or group education, printed materials, visual displays, videos, and providing resources such as cribs, pacifiers, wearable blankets, and infant t-shirts. Two described public education campaigns, one used an educative questionnaire, and one encouraged maternal note taking. Health professional interventions included implementing safe sleep policies, in-service training, printed provider materials, eliciting agreement on a Declaration of Safe Sleep Practice, and sharing adherence data. Data collection methods included self-report via surveys and observational crib audits. Over half of the studies utilized comparison groups which helped determine effectiveness. Most articles reported some degree of success in changing some of the targeted behaviors; no studies reported complete adherence to recommendations. Future studies should incorporate rigorous evaluation plans, utilize comparison groups, and collect demographic and collect follow-up data.

Statistical study of static gasket conductance; Etude statistique de la conductance d'un joint d'etancheite statique

Energy Technology Data Exchange (ETDEWEB)

Flukiger, F

2005-10-15

This work is motivated by tightness technological problems associated with metallic gasket. The objective is a better understanding of leakage mechanisms, through the development of new computational tools. In this study, the aperture field between two rough surfaces in contact is described by a short correlated isotropic random Gaussian process. The system is studied as a set of independent elementary surfaces. Joint conductances are evaluated from a statistical study on those elementary surfaces. A computational code is developed using a network approach based on lubrication theory estimation of local conductances. The global conductance computation becomes analogous to an electrical problem for which the resistances are distributed on a random network. The network is built from the identification of the aperture field critical points. Maxima are linked through saddle points. Bond conductances are estimated at the aperture field saddle points. First, a purely plastic model of deformations is considered. Near percolation threshold the conductances display a power behaviour. Far from percolation threshold, numerical results are favourably compared with an effective medium approximation. Secondly, we study the impact of elastic deformations. A computational code based on Boussinesq approximation is coupled to the network approach. The results indicate a significant impact of elastic deformations on conductances. Finally, the network approach is adapted to simulate quasi-static drainage thanks to a classical invasion percolation algorithm. A good comparison between previous experiments and numerical predictions is obtained. (author)

Injection Laryngoplasty Materials

OpenAIRE

Haldun Oðuz

2013-01-01

Injection laryngoplasty is one of the treatment options for voice problems. In the recent years, more safe and more biocompatible injection materials are available on the market. Long and short term injection materials are discussed in this review.

From unwanted pregnancy to safe abortion: Sharing information about abortion in Asia through animation.

Science.gov (United States)

Krishnan, Shweta; Dalvie, Suchitra

2015-05-01

Although unsafe abortion continues to be a leading cause of maternal mortality in many countries in Asia, the right to safe abortion remains highly stigmatized across the region. The Asia Safe Abortion Partnership, a regional network advocating for safe abortion, produced an animated short film entitled From Unwanted Pregnancy to Safe Abortion to show in conferences, schools and meetings in order to share knowledge about the barriers to safe abortion in Asia and to facilitate conversations on the right to safe abortion. This paper describes the making of this film, its objectives, content, dissemination and how it has been used. Our experience highlights the advantages of using animated films in addressing highly politicized and sensitive issues like abortion. Animation helped to create powerful advocacy material that does not homogenize the experiences of women across a diverse region, and at the same time emphasize the need for joint activities that express solidarity. Copyright © 2015. Published by Elsevier Ltd.

Regulations for the safe transport of radioactive material. 1996 edition (revised)

International Nuclear Information System (INIS)

2000-01-01

Following a comprehensive review by panels of experts convened by the IAEA starting in 1991, a revised version of the IAEA Regulations for the Safe Transport of Radioactive Material (formerly Safety Series No. 6) was approved by the Board of Governors in September 1996. This publication supersedes all editions of the Regulations issued under Safety Series No. 6. By 1969, the Regulations had been adopted by almost all international organizations concerned with transport and used by many Member States for their own regulations. Through the worldwide adoption of the IAEA Regulations for all modes of transport, a very high standard of safety in transport has been achieved. In the revisions since the first edition, attempts have been made to find a balance between the need to take account of technical advances and operational experience, and the desirability of providing a stable framework of regulatory requirements. One of the aims of this approach is to allow packages designed to previous versions of the Regulations to continue to be used for a reasonable period of time. It is recognized that not all regulatory changes can be implemented simultaneously; Member States and international organizations are therefore invited, in adopting this revision, to provide for use of both the 'old' requirements and the 'new' ones during a period of transition that may last for a few years. It is further recommended that adoption of these revised Regulations occur within a period of five years from publication to achieve worldwide harmonization of their application. In implementing the provisions of these Regulations, it may be necessary for Member States to issue complementary national regulations. Except as necessary for solely domestic purposes, such national regulations should not conflict with these Regulations. For convenience, the requirements to be met for the transport of specified types of consignments are included in an abbreviated form as Schedules in this publication

Regulations for the safe transport of radioactive material. 1996 edition (revised)

International Nuclear Information System (INIS)

2002-01-01

Following a comprehensive review by panels of experts convened by the IAEA starting in 1991, a revised version of the IAEA Regulations for the Safe Transport of Radioactive Material (formerly Safety Series No. 6) was approved by the Board of Governors in September 1996. This publication supersedes all editions of the Regulations issued under Safety Series No. 6. By 1969, the Regulations had been adopted by almost all international organizations concerned with transport and used by many Member States for their own regulations. Through the worldwide adoption of the IAEA Regulations for all modes of transport, a very high standard of safety in transport has been achieved. In the revisions since the first edition, attempts have been made to find a balance between the need to take account of technical advances and operational experience, and the desirability of providing a stable framework of regulatory requirements. One of the aims of this approach is to allow packages designed to previous versions of the Regulations to continue to be used for a reasonable period of time. It is recognized that not all regulatory changes can be implemented simultaneously. Member States and international organizations are therefore invited, in adopting this revision, to provide for use of both the 'old' requirements and the 'new' ones during a period of transition that may last for a few years. It is further recommended that adoption of these revised Regulations occur within a period of five years from publication to achieve worldwide harmonization of their application. In implementing the provisions of these Regulations, it may be necessary for Member States to issue complementary national regulations. Except as necessary for solely domestic purposes, such national regulations should not conflict with these Regulations. For convenience, the requirements to be met for the transport of specified types of consignments are included in an abbreviated form as Schedules in this publication

SAFE Newsletter

OpenAIRE

2013-01-01

The Center of Excellence SAFE – “Sustainable Architecture for Finance in Europe” – is a cooperation of the Center for Financial Studies and Goethe University Frankfurt. It is funded by the LOEWE initiative of the State of Hessen (Landes-Offensive zur Entwicklung wissenschaftlich-ökonomischer Exzellenz). SAFE brings together more than 40 professors and just as many junior researchers who are all dedicated to conducting research in support of a sustainable financial architecture. The Center has...

Safe and unsafe duration of fasting for children with MCAD deficiency

NARCIS (Netherlands)

Derks, Terry G J; van Spronsen, Francjan J; Rake, Jan Peter; van der Hilst, Christian S; Span, Mark M; Smit, G Peter A

OBJECTIVE: To study the safe and unsafe duration of fasting in children with medium chain acyl-Coenzyme A dehydrogenase (MCAD) deficiency, the literature and the database on Dutch MCAD-deficient patients were searched for data on fasting studies in patients with MCAD deficiency. MATERIALS AND

SAFE-AXISYM, Stress Analysis of Axisymmetric Composite Structure by Finite Elements Method

International Nuclear Information System (INIS)

Cornell, D.C.

1967-01-01

1 - Nature of physical problem solved: SAFE-AXISYM is a program for the analysis of multi-material axisymmetric composite structures. It is designed for the analysis of heterogeneous structures such as reinforced and/or prestressed concrete vessels. The structure is assumed to be linearly elastic, and only bodies of revolution subjected to axisymmetric loading can be treated. 2 - Method of solution: SAFE-AXISYM uses a finite element method with a modified Gauss-Seidel iteration scheme. A reference grid subdivides the structure into ring-like small, finite elements, the vertices of which are called nodes. The grid may be generated by hand, by the computer or by a combination of the two methods. Each node has two degrees of freedom, translation in the and in the axial direction. Both zero and non-zero fixed displacement constraints may be assumed, and the loading condition may be mechanical and/or thermal. 3 - Restrictions on the complexity of the problem: Multi-material structures with varying rigidities converge very slowly. Not valid for incompressible materials. Maximum number of nodes = 475. Maximum number of elements = 1100

Safe Grid

Science.gov (United States)

Chow, Edward T.; Stewart, Helen; Korsmeyer, David (Technical Monitor)

2003-01-01

The biggest users of GRID technologies came from the science and technology communities. These consist of government, industry and academia (national and international). The NASA GRID is moving into a higher technology readiness level (TRL) today; and as a joint effort among these leaders within government, academia, and industry, the NASA GRID plans to extend availability to enable scientists and engineers across these geographical boundaries collaborate to solve important problems facing the world in the 21 st century. In order to enable NASA programs and missions to use IPG resources for program and mission design, the IPG capabilities needs to be accessible from inside the NASA center networks. However, because different NASA centers maintain different security domains, the GRID penetration across different firewalls is a concern for center security people. This is the reason why some IPG resources are been separated from the NASA center network. Also, because of the center network security and ITAR concerns, the NASA IPG resource owner may not have full control over who can access remotely from outside the NASA center. In order to obtain organizational approval for secured remote access, the IPG infrastructure needs to be adapted to work with the NASA business process. Improvements need to be made before the IPG can be used for NASA program and mission development. The Secured Advanced Federated Environment (SAFE) technology is designed to provide federated security across NASA center and NASA partner's security domains. Instead of one giant center firewall which can be difficult to modify for different GRID applications, the SAFE "micro security domain" provide large number of professionally managed "micro firewalls" that can allow NASA centers to accept remote IPG access without the worry of damaging other center resources. The SAFE policy-driven capability-based federated security mechanism can enable joint organizational and resource owner approved remote

A parametric study of contact problem on a large size flange

International Nuclear Information System (INIS)

Mukherjee, A.B.; Narayanan, T.; Dhondkar, J.K.; Mehra, V.K.

1989-01-01

Continuous change of contact point on gasket face with the application of bolt load makes it a non-linear problem. Thus the geometric non-linearity of the structure is simulated and a stress distribution over the gasket face is presented in this paper. The paper also describes the use of taper on the gasket face to reduce the stress peaking and to optimize the gasket face separation

ICE911 Research: Floating Safe Inert Materials to Preserve Ice and Conserve Water in Order to Mitigate Climate Change Impacts

Science.gov (United States)

Field, L. A.; Manzara, A.; Chetty, S.; Venkatesh, S.; Scholtz, A.

2015-12-01

Ice911 Research has conducted years of field testing to develop and test localized reversible engineering techniques to mitigate the negative impacts of polar ice melt. The technology uses environmentally safe materials to reflect energy in carefully selected, limited areas from summertime polar sun. The technology is now being adapted to help with California's drought. We have tested the albedo modification technique on a small scale over seven Winter/Spring seasons at sites including California's Sierra Nevada Mountains, a Canadian lake, and a small artificial pond in Minnesota about 100 ft in diameter and 6 ft deep at the center, using various materials and an evolving array of instrumentation. On the pond in Minnesota, this year's test results for ice preservation, using hollow glass spheres deployed over our largest test areas yet, showed that glass bubbles can provide an effective material for increasing albedo, significantly reducing the melting rate of ice. This year Ice911 also undertook its first small Arctic field test in Barrow, Alaska on a lake in Barrow's BEO area, and results are still coming in. The technology that Ice911 has been developing for ice preservation has also been shown to keep small test areas of water cooler, in various small-scale tests spanning years. We believe that with some adaptations of the technology, the materials can be applied to reservoirs and lakes to help stretch these precious resources further in California's ongoing drought. There are several distinct advantages for this method over alternatives such as large reverse osmosis projects or building new reservoirs, which could possibly allow a drought-stricken state to build fewer of these more-costly alternatives. First, applying an ecologically benign surface treatment of Ice911's materials can be accomplished within a season, at a lower cost, with far less secondary environmental impact, than such capital-and-time-intensive infrastructure projects. Second, keeping

Regulations for the safe transport of radioactive materials. 1973 rev. ed

International Nuclear Information System (INIS)

1973-01-01

The purpose of these Regulations is to establish standards of safety which provide an acceptable level of control of the radiation hazards to persons, property and the environment that are associated with the transport of radioactive material. These Regulations shall apply to the transport by land, water or air, including transport on own account, of radioactive material other than that which is an integral part of the means of transport. Transport shall be deemed to include any operation incidental to the whole course of carriage, such as loading, unloading and storage in transit. The term includes both normal transport and that under accident conditions. These Regulations do not apply within establishments where the radioactive material is produced, used or stored, other than in the course of transport, and in respect of which other appropriate safety regulations are in force. In the transport of radioactive materials, any other hazardous characteristics of these materials such as explosiveness, inflammability, pyrophoricity, chemical toxicity, and corrosiveness must be taken into account in such a manner as to be in compliance with the relevant transport regulations for dangerous goods of each of the countries through or into which the materials will be transported, as well as in compliance with these Regulations.

Evaluation of Ion Exchange Materials in K Basin Floor Sludge and Potential Solvents for PCB Extraction from Ion Exchange Materials

International Nuclear Information System (INIS)

Schmidt, A.J.; Klinger, G.S.; Bredt, P.R.

1998-01-01

Approximately 73 m 3 of heterogeneous solid material, ''sludge,'' (upper bound estimate, Packer 1997) have accumulated at the bottom of the K Basins in the 100 K Area of the Hanford Site. This sludge is a mixture of spent fuel element corrosion products, ion exchange materials (organic and inorganic), graphite-based gasket materials, iron and aluminum metal corrosion products, sand, and debris (Makenas et al. 1996, 1997). In addition, small amounts of polychlorinated biphenyls (PCBs) have been found. These small amounts are significant from a regulatory standpoint. Ultimately, it is planned to transfer the K Basins sludge to the Hanford double shell tanks (DSTs). Chemical pretreatment is required to address criticality issues and the destruction or removal of PCBs before the K Basin sludge can be transferred to the DSTs. Eleven technologies have been evaluated (Papp 1997) as potential pretreatment methods. Based on the evaluations and engineering studies and limited testing, Fluor Daniel Hanford recommended solvent washing of the K Basin sludge, followed by nitric acid dissolution and, potentially, peroxide addition (FDH 1997). The solvent washing (extraction) and peroxide addition would be used to facilitate PCB removal and destruction. Following solvent extraction, the PCBs could be distilled and concentrated for disposal as a low-level waste. The purpose of the work reported here was to continue investigating solvent extraction, first by better identifying the ion exchange materials in the actual sludge samples and then evaluating various solvents for removing the PCBs or possibly dissolving the resins. This report documents some of the process knowledge on ion exchange materials used and spilled in the K Basins and describes the materials identified from wet sieving KE Basin floor and canister sludge and the results of other analyses. Several photographs are included to compare materials and illustrate material behavior. A summary of previous tests on solvent

Online Learning of Safe Patient Transfers in Occupational Therapy Education

Directory of Open Access Journals (Sweden)

Cynthia L. Hayden D. H. Ed., OTR/L, CHT

2013-02-01

Full Text Available Online higher education is steadily increasing. For programs in allied health to be offered effectively in an elearning format, clinical psychomotor skills need to be addressed. The aim of this research was to design, implement, and evaluate an online safe patient transfers module for occupational therapy assistant (OTAstudents. The efficacy of teaching safe patient transfers in an e-learning environment was appraised using both quantitative and qualitative analysis. The applied research project was completed at a Tennessee community college. A convenience sample of eighteen students participated in the pilot study. Twenty-five studentsparticipated in the subsequent study. The instructional design of the course was based on Mager’s CriterionReferenced Instruction model. Streaming video was used as the delivery method for course material. A pretest/posttest evaluated the students’ cognitive knowledge of safe patient transfers. A behavioral transferscompetency checklist was used to rate videotapes of students’ performance of assisted stand pivot and dependent sliding board transfers. Research findings indicated students were able to learn this psychomotor clinical skill online with beginning proficiency. A paired t-test showed marked improvement of cognitive knowledge. A student learning survey revealed the majority of students preferred at least one hands-on classroom session where instructor feedback and interaction with classmates confirmed safe and effectiveclinical technique.

Generation of deposits and self ignited fires in H2S-H2O services (Paper No. 4.6)

International Nuclear Information System (INIS)

Agarwal, A.K.; Hiremath, S.C.

1992-01-01

The Heavy Water Plant (Kota) uses a large inventory of H 2 S gas at a nominal pressure and temperature. The plant has used mild steels/carbon steels as the material of construction of vessels, piping, flanges and fasteners. The entire construction is with flanged joints with raised face and spiral wound gaskets. Any leakages from any of the pipe line, flanged joints, heat exchanger covers, valve bonnets, valve glands etc causes H 2 S and H 2 O to leak out which generate deposits around the leakage paths after reaction with mild steel/carbon steels. The deposits grow into hard material, cause corrosion and thinning of stud bolts and gasket outer rings, weaken the confidence in the joint, and also cause ignited fires as they provide a source of ignition under certain conditions. (author). 2 refs

Critical review of the equipment hatch of a large dry steel containment. The DEFENDER IMPROVEMENT

International Nuclear Information System (INIS)

Mantega, F.; Penno, E.; Vanini, P.

1994-01-01

Performances of the Containment System under Severe Accident conditions depend on a number of different features and components. The equipment hatch may be considered a critical component because it is a potential main contributor to the total Containment leak rate during a Severe accident and a potential (depending on the design) direct leak path between the containment atmosphere and the environment. The analytical study performed to anticipate the response of the equipment hatch of a large dry steel containment under Severe Accident condition has pointed out some questions of concern. The possible leak tightness failure mechanism are related to: the gaskets elastic characteristics degradation due to thermal and radiological aging; the deformation of the hatch sleeve induced by the containment wall; and the differential expansion between gasket material and steel. Beside, the equipment hatch may be considered a single barrier and although it is equipped with two gaskets, it is not difficult to demonstrate that a backup function cannot be assigned to the external gasket. For these reason it seems to be necessary to realize a wider application of the 'Defence in Depth' criteria in the design of this component. The DEFENDER (DEFENce in Depth Equipment hatch Requalification) might be a solution to increase the margin of safety of the equipment hatch under the Severe Accident condition. (author)

High-energy cathode material for long-life and safe lithium batteries

Science.gov (United States)

Sun, Yang-Kook; Myung, Seung-Taek; Park, Byung-Chun; Prakash, Jai; Belharouak, Ilias; Amine, Khalil

2009-04-01

Layered lithium nickel-rich oxides, Li[Ni1-xMx]O2 (M=metal), have attracted significant interest as the cathode material for rechargeable lithium batteries owing to their high capacity, excellent rate capability and low cost. However, their low thermal-abuse tolerance and poor cycle life, especially at elevated temperature, prohibit their use in practical batteries. Here, we report on a concentration-gradient cathode material for rechargeable lithium batteries based on a layered lithium nickel cobalt manganese oxide. In this material, each particle has a central bulk that is rich in Ni and a Mn-rich outer layer with decreasing Ni concentration and increasing Mn and Co concentrations as the surface is approached. The former provides high capacity, whereas the latter improves the thermal stability. A half cell using our concentration-gradient cathode material achieved a high capacity of 209mAhg-1 and retained 96% of this capacity after 50 charge-discharge cycles under an aggressive test profile (55∘C between 3.0 and 4.4V). Our concentration-gradient material also showed superior performance in thermal-abuse tests compared with the bulk composition Li[Ni0.8Co0.1Mn0.1]O2 used as reference. These results suggest that our cathode material could enable production of batteries that meet the demanding performance and safety requirements of plug-in hybrid electric vehicles.

A study on the safety regulation of byproduct material

Energy Technology Data Exchange (ETDEWEB)

Song, Jong Soon; Song, Yang Su [Chosun Univ., Gwangju (Korea, Republic of)

1999-04-15

The objective of this study is to develop the technical criteria and regulatory system for establishing the safe regulation of byproduct material institutionally. Up to this point, domestically, though many byproduct materials are distributed and used already, it seems that there are no related technical criteria and regulatory system and it becomes an obstacle in the development of relating industry. Since this kind of situation may give negative impact on the proper recognizance of the radiation to public, it is very urgent to establish the safe regulation of byproduct material. In relating to the domestic license of byproduct material, a survey of technical criteria and status of regulation in U.S.A. A determination of range of application and contents of byproduct material. A tentative suggestion of related technical criteria and regulatory system. A study was performed about the above topics to establish the safe regulation of byproduct material institutionally, and this can be contributed in establishing the proper domestic technical criteria related.

Issues Associated with Tritium Legacy Materials

International Nuclear Information System (INIS)

Mills, Michael

2008-01-01

This paper highlights some of the issues associated with the treatment of legacy materials linked to research into tritium over many years and also of materials used to contain or store tritium. The aim of the work is to recover tritium where practicable, and to leave the residual materials passively safe, either for disposal or for continued storage. A number of materials are currently stored at AWE which either contain tritium or have been used in tritium processing. It is essential that these materials are characterised such that a strategy may be developed for their safe stewardship, and ultimately for their treatment and disposal. Treatment processes for such materials are determined by the application of best practicable means (BPM) studies in accordance with the requirements of the Environment Agency of England and Wales. Clearly, it is necessary to understand the objectives of legacy material treatment / processing and the technical options available before a definitive BPM study is implemented. The majority of tritium legacy materials with which we are concerned originate from the decommissioning of a facility that was operational from the late 1950's through to the late 1990's when, on post-operative clear-out (POCO), the entire removable and transportable tritium inventory was moved to new, purpose built facilities. One of the principle tasks to be undertaken in the new facilities is the treatment of the legacy materials to recover tritium wherever practicable, and render the residual materials passively safe for disposal or continued storage. Where tritium recovery was not reasonably or technically feasible, then a means to assure continued safe storage was to be devised and implemented. The legacy materials are in the following forms: - Uranium beds which may or may not contain adsorbed tritium gas; - Tritium gas stored in containers; - Tritide targets for neutron generation; - Tritides of a broad spectrum of metals manufactured for research / long

The Pennsylvania State University Light Water Ultra-Safe Plant Concept: 3rd quarter progress report

International Nuclear Information System (INIS)

Klevans, E.

1987-01-01

Progress in the Ultra Safe study has substantially increased since the last report. The search for pressurizing pump turbine component information is now complete and a final plant layout for detailed evaluation has been chosen. Significant results for the normal operation performance of the Ultra Safe pressurizing technique are included. The plan of attack for the evaluation of the Ultra Safe shutdown scenario and natural circulation capability is discussed. This process is expected to be the next key area for analysis. The reactor design is complete including a change to alleviate the need for a soluble boron system. Material on the reactor building layout is also provided

Are Detox Diets Safe?

Science.gov (United States)

... Safe Videos for Educators Search English Español Are Detox Diets Safe? KidsHealth / For Teens / Are Detox Diets ... seguras las dietas de desintoxicación? What Is a Detox Diet? The name sounds reassuring — everyone knows that ...

The development of shifting radioactive material

International Nuclear Information System (INIS)

Chen Haiteng; Chen Yonghong; Yin Fujun; Che Mingsheng; Hu Xiaodan; Yao Shouzhong

2010-01-01

In nuclear field, When the nuclear material shifting from the glove-box,use the technology of plastic welding package in accordance with tradition. There are some defects in this technology because of the plastic character, such as package pierced easily, wrapper not fitted storage for long term, etc. Because of this limit. Plastic shifting technology is only fit for shifting radwaste and nuclear material not need storage from radioactive close area to non-radioactive open area for long term.As the nuclear material exiting leak when shifting in plastic package,and the plastic material don't meet the need of storaging safely for long term.We research into a new technology of nuclear material shifting. When nuclear material is carried out from the glove box. It should be sealed by welding case, then it can be storaged safely for long term. At the same time, nuclear material wouldn't pollute the glove box outside.The study achieved well effect in apply. (authors)

Using safe materials to control Varroa mites with studying grooming behavior of honey bees and morphology of Varroa over winter

Directory of Open Access Journals (Sweden)

Hossam F. Abou-Shaara

2017-12-01

Full Text Available Extracts of drone larvae and propolis as safe materials are anticipated to boost the grooming behavior of honey bees against Varroa mites. It is also expected that grooming behavior of bees and morphology of Varroa are stable during the least active period of the year to bee colonies (i.e winter. Sugar syrup alone or mixed with drone larvae extract or propolis extract were examined as potential Varroa control materials to test these hypothesizes. Moreover, percentages of groomed mites along with body lengths and widths of Varroa were studied on weekly basis during winter. The results showed that propolis extract was able to increase the number of fallen mites under field conditions but with lethal impacts on bee workers in the laboratory than extract of drone larvae or sugar syrup. All the treatments were not able to boost the grooming behavior of bees. The results proved that grooming behavior was stable during winter. Therefore, it is better to select colonies with grooming potential against Varroa during winter in selection programs. December was significantly the minimal month in percentage of groomed mites based on the overall means. Means of measured characteristics of Varroa declined significantly over the study period. For beekeepers, using sugar syrup as spray on bees during regularly colony inspection can help managing Varroa populations without harming the bees.

Safe Anesthesia For Every Tot

DEFF Research Database (Denmark)

Weiss, Markus; Vutskits, Laszlo; Hansen, Tom G

2015-01-01

PURPOSE OF REVIEW: The term 'safe use of anesthesia in children is ill-defined and requires definition of and focus on the 'safe conduct of pediatric anesthesia'. RECENT FINDINGS: The Safe Anesthesia For Every Tot initiative (www.safetots.org) has been set up during the last year to focus...... on the safe conduct of pediatric anesthesia. This initiative aims to provide guidance on markers of quality anesthesia care. The introduction and implementation of national regulations of 'who, where, when and how' are required and will result in an improved perioperative outcome in vulnerable children....... The improvement of teaching, training, education and supervision of the safe conduct of pediatric anesthesia are the main goals of the safetots.org initiative. SUMMARY: This initiative addresses the well known perioperative risks in young children, perioperative causes for cerebral morbidity as well as gaps...

Final hazard classification and auditable safety analysis for the 105-C Reactor Interim Safe Storage Project

International Nuclear Information System (INIS)

Rodovsky, T.J.; Larson, A.R.; Dexheimer, D.

1996-12-01

This document summarizes the inventories of radioactive and hazardous materials present in the 105-C Reactor Facility and the operations associated with the Interim Safe Storage Project which includes decontamination and demolition and interim safe storage of the remaining facility. This document also establishes a final hazard classification and verifies that appropriate and adequate safety functions and controls are in place to reduce or mitigate the risk associated with those operations

Safe sorting of GFP-transduced live cells for subsequent culture using a modified FACS vantage

DEFF Research Database (Denmark)

Sørensen, T U; Gram, G J; Nielsen, S D

1999-01-01

BACKGROUND: A stream-in-air cell sorter enables rapid sorting to a high purity, but it is not well suited for sorting of infectious material due to the risk of airborne spread to the surroundings. METHODS: A FACS Vantage cell sorter was modified for safe use with potentially HIV infected cells...... culture. CONCLUSIONS: Sorting of live infected cells can be performed safely and with no deleterious effects on vector expression using the modified FACS Vantage instrument....

Can active proton interrogation find shielded nuclear threats at human-safe radiation levels?

Energy Technology Data Exchange (ETDEWEB)

Liew, Seth Van, E-mail: vanliew@gmail.com

2017-05-21

A new method of low-dose proton radiography is presented. The system is composed of an 800 MeV proton source, bending magnets, and compact detectors, and is designed for drive-through cargo scanning. The system has been simulated using GEANT4. Material identification algorithms and pixel sorting methods are presented that allow the system to perform imaging at doses low enough to scan passenger vehicles and people. Results are presented on imaging efficacy of various materials and cluttered cargoes. The identification of shielded nuclear materials at human-safe doses has been demonstrated.

Safe and Sustainable: Optimizing Material Flows in a Circular Economy

DEFF Research Database (Denmark)

Fantke, Peter

(unsustainable). When maximizing resource use efficiency and reducing carbon and other emissions through recycling (sustainable), direct consumer exposure is often increased through cross-contamination of recycled materials (unsafe). Hence, circular economy currently fails to unite the required expertise...... to imultaneously increase sustainability and reduce exposure to chemicals in materials reused across life cycles of different products. For a way out of this dilemma, a paradigm shift is needed towards a comprehensive and quantitative assessment framework.......Increasing the sustainability of a globally connected economy is gaining wide attention in a world with limited natural resources and growing chemical pollution. The circular economy has emerged as away to reduce carbon and other emissions, while increasing resource efficiency over several product...

Gender dysphoria and the controversy over the Safe Schools program.

Science.gov (United States)

Parkinson, Patrick

2017-10-01

The Safe Schools program has attracted great controversy. On one end of the spectrum, it is defended as an anti-bullying program for young people who identify themselves as gay or lesbian, or have issues concerning their gender identity. On the other end of the spectrum, it is regarded as social engineering. This article seeks to promote a discussion of the way in which gender identity issues are addressed in the Safe Schools program. It is argued that the information in this program to Principals, teachers and young people is inaccurate and misleading. The program, as presently designed, may actually cause harm to children and young people who experience gender identity issues because it promotes gender transitioning without expert medical advice. The Safe Schools materials do not acknowledge that the great majority of children resolve gender dysphoria issues around the time of puberty. It may be much more difficult for a child to accept his or her gender at puberty if he or she has already changed name and gender identity in primary school. These deficits need to be addressed if the program is to continue.

9 CFR 381.144 - Packaging materials.

Science.gov (United States)

2010-01-01

... to health. All packaging materials must be safe for the intended use within the meaning of section..., from the packaging supplier under whose brand name and firm name the material is marketed to the... distinguishing brand name or code designation appearing on the packaging material shipping container; must...

Design improvements for gloveboxes used [in] 238PuO2 process operations

International Nuclear Information System (INIS)

George, T.G.

1997-01-01

238 PuO 2 process operations are housed in a complex of 76 gloveboxes and introductory hoods connected by means of an overhead trolley housed in a tunnel. Because a significant number of the gloveboxes used for 238 PuO 2 processing were installed before the original startup of the facility in 1978, they have been in service for nearly 20 years. During a recent heat source production campaign, numerous contamination releases in the 238 PuO 2 processing area were traced to degraded elastomer gaskets used for glovebox connections, and attachment of feed-throughs, service panels, and windows. Evaluation of the degraded gaskets revealed that a combination of radiolytic degradation related to the high specific activity of 238 Pu, and extended service at high altitude in a low (to extremely low) humidity environment had resulted in accelerated gasket aging. However, it was also apparent that gasket design was the most important factor in actual contamination release. All of the contamination releases that were traced to degraded gaskets occurred in variations of a design that used a spline to expand an elastomeric gasket into the space between a connecting flange, window, or service panel, and a glovebox opening. No contamination releases were traced to the gasket design that employed bolted clamps to compress the gasket between a connecting flange, window, or panel, and the exterior surface of a glovebox opening. As a result of these findings, the Actinide Ceramics group at LANL (NMT-9) has initiated a routine replacement and upgrade program to replace aging gloveboxes. All of the new gloveboxes will utilize the preferred gasket design, which is expected to reduce the number and frequency of contamination releases

Development of Self-Remediating Packaging for Safe and Secure Transport of Infectious Substances.

Energy Technology Data Exchange (ETDEWEB)

Guilinger, Terry Rae; Gaudioso, Jennifer M; Aceto, Donato Gonzalo; Lowe, Kathleen M.; Tucker, Mark D; Salerno, Reynolds Mathewson; Souza, Caroline Ann

2006-11-01

As George W. Bush recognized in November 2001, "Infectious diseases make no distinctions among people and recognize no borders." By their very nature, infectious diseases of natural or intentional (bioterrorist) origins are capable of threatening regional health systems and economies. The best mechanism for minimizing the spread and impact of infectious disease is rapid disease detection and diagnosis. For rapid diagnosis to occur, infectious substances (IS) must be transported very quickly to appropriate laboratories, sometimes located across the world. Shipment of IS is problematic since many carriers, concerned about leaking packages, refuse to ship this material. The current packaging does not have any ability to neutralize or kill leaking IS. The technology described here was developed by Sandia National Laboratories to provide a fail-safe packaging system for shipment of IS that will increase the likelihood that critical material can be shipped to appropriate laboratories following a bioterrorism event or the outbreak of an infectious disease. This safe and secure packaging method contains a novel decontaminating material that will kill or neutralize any leaking infectious organisms; this feature will decrease the risk associated with shipping IS, making transport more efficient. 3 DRAFT4

SAFE/SNAP application to shipboard security

International Nuclear Information System (INIS)

Grady, L.M.; Walker, J.L.; Polito, J.

1981-11-01

An application of the combined Safeguards Automated Facility Evaluation/Safeguards Network Analysis Procedure (SAFE/SNAP) modeling technique to a physical protection system (PPS) aboard a generic ship is described. This application was performed as an example of how the SAFE and SNAP techniques could be used. Estimates of probability of interruption and neutralization for the example shipboard PPS are provided by SAFE as well as an adversary scenario, which serves as input to SNAP. This adversary scenario is analyzed by SNAP through four cases which incorporate increasingly detailed security force tactics. Comparisons between the results of the SAFE and SNAP analyses are made and conclusions drawn on the validity of each technique. Feedback from SNAP to SAFE is described, and recommendations for upgrading the ship based on the results of the SAFE/SNAP application are also discussed

The effect of material difference and flange nominal size on the sealing performance of new gasketless flanges

International Nuclear Information System (INIS)

Noda, Nao-Aki; Inoue, Akifumi; Nagawa, Masato; Shiraishi, Fumitaka

2002-01-01

This paper deals with a new seal system between flange joints without using a gasket. This gasketless flange includes a groove and an annular lip that is machined in one of the flange rings which when removed being in contact with the other flange to form a seal line when the flanges are assembled. In this study, firstly, fundamental dimensions are examined for unplasticized polyvinyl chloride (PVC-U JIS) to obtain the best sealing performance. Then, the effects of material difference and flange nominal size upon the sealing performance of the new gasketless flange are investigated for two types of materials, 0.25% carbon steel (S25C JIS) and PVC-U. It is found that the critical internal pressure at which leakage appears is mainly controlled by the maximum stress at the annular lip for each material even if the flange nominal sizes are different. The gasketless flange made by PVC-U shows the higher critical internal pressure compared with the case of S25C if the same clamping forces are applied. The effect of stress relaxation for PVC-U on the sealing performance is also considered. Then, it may be concluded that this PVC-U gasketless flange as well as S25C has good sealing performance

Improving Safe Sleep Modeling in the Hospital through Policy Implementation.

Science.gov (United States)

Heitmann, Rachel; Nilles, Ester K; Jeans, Ashley; Moreland, Jackie; Clarke, Chris; McDonald, Morgan F; Warren, Michael D

2017-11-01

Introduction Sleep-related infant deaths are major contributors to Tennessee's high infant mortality rate. The purpose of this initiative was to evaluate the impact of policy-based efforts to improve modeling of safe sleep practices by health care providers in hospital settings across Tennessee. Methods Safe sleep policies were developed and implemented at 71 hospitals in Tennessee. Policies, at minimum, were required to address staff training on the American Academy of Pediatrics' safe sleep recommendations, correct modeling of infant safe sleep practices, and parent education. Hospital data on process measures related to training and results of crib audits were compiled for analysis. Results The overall observance of infants who were found with any risk factors for unsafe sleep decreased 45.6% (p ≤ 0.001) from the first crib audit to the last crib audit. Significant decreases were noted for specific risk factors, including infants found asleep not on their back, with a toy or object in the crib, and not sleeping in a crib. Significant improvements were observed at hospitals where printed materials or video were utilized for training staff compared to face-to-face training. Discussion Statewide implementation of the hospital policy intervention resulted in significant reductions in infants found in unsafe sleep situations. The most common risk factors for sleep-related infant deaths can be modeled in hospitals. This effort has the potential to reduce sleep-related infant deaths and ultimately infant mortality.

9 CFR 317.24 - Packaging materials.

Science.gov (United States)

2010-01-01

... packaging materials must be safe for their intended use within the meaning of section 409 of the Federal... supplier under whose brand name and firm name the material is marketed to the official establishment. The... additive regulations. The guaranty must identify the material, e.g., by the distinguishing brand name or...

Chernobyl new safe confinement

International Nuclear Information System (INIS)

Dodd, L.

2011-01-01

The author presents the new safe confinement that will be commissioned at Unit 4 of the Chernobyl NPP in 2015. The confinement will ensure that Chernobyl Unit 4 will be placed in an environmentally safe condition for at least next 100 years. The article highlights the current work status, future perspectives and the feasibility of confinement concept [ru

Asymptotically Safe Dark Matter

DEFF Research Database (Denmark)

Sannino, Francesco; Shoemaker, Ian M.

2015-01-01

We introduce a new paradigm for dark matter (DM) interactions in which the interaction strength is asymptotically safe. In models of this type, the coupling strength is small at low energies but increases at higher energies, and asymptotically approaches a finite constant value. The resulting...... searches are the primary ways to constrain or discover asymptotically safe dark matter....

Guidance notes : safe practice for the use of nuclear density meters

International Nuclear Information System (INIS)

2000-06-01

These 'Guidance notes' have been written to provide information for owners and users on the safe care and use of instruments containing radioactive materials used for the measurement of moisture content and/or density of materials. They give practical guidance on compliance with the requirements of radiation protection legislation and the 'Code of safe practice for the use of nuclear density meters, NRL C15'. Some of these instruments have been known as 'soil moisture gauges' and others as 'nuclear density meters' or just 'NDMs'. For simplicity, these 'Guidance notes' will follow industry terminology and use the term 'nuclear density meter'. Some parts of these 'Guidance notes' and of the 'Code, NRL C15' are relevant for users of asphalt gauges containing radioactive sources. These are normally laboratory bench instruments, and are not portable field instruments. Nevertheless, the radioactive sources used are similar to those used for moisture measurement and the safety implications are similar. The units of measurement of radioactivity and radiation dose are discussed in Appendix 1. Appendix 2 contains consent application forms while sample transport forms can be found in Appendix 3. (author). 10 refs

Steam generator materials

International Nuclear Information System (INIS)

Kim, Joung Soo; Han, J. H.; Kim, H. P.; Lim, Y. S.; Lee, D. H.; Suh, J. H.; Hwang, S. S.; Hur, D. H.; Kim, D. J.; Kim, Y. H.

2002-05-01

In order to keep the nuclear power plant(NPP)s safe and increase their operating efficiency, axial stress corrosion cracking(SCC)(IGA/IGSCC, PWSCC, PbSCC) test techniques were developed and SCC property data of the archive steam generator tubing materials having been used in nuclear power plants operating in Korea were produced. The data obtained in this study were data-based, which will be used to clarify the damage mechanisms, to operate the plants safely, and to increase the lifetime of the tubing. In addition, the basic technologies for the improvement of the SCC property of the tubing materials, for new SCC inhibition, for damaged tube repair, and for manufacturing processes of the tubing were developed. In the 1 phase of this long term research, basic SCC test data obtained from the archive steam generator tubing materials used in NPPs operating in Korea were established. These basic technologies developed in the 1 phase will be used in developing process optimization during the 2 phase in order to develop application technologies to the field nuclear power plants

10 CFR 71.87 - Routine determinations.

Science.gov (United States)

2010-01-01

... REGULATORY COMMISSION (CONTINUED) PACKAGING AND TRANSPORTATION OF RADIOACTIVE MATERIAL Operating Controls and...; (c) Each closure device of the packaging, including any required gasket, is properly installed and..., is present and in proper condition; (h) Any structural part of the package that could be used to lift...

75 FR 1734 - Children’s Online Privacy Protection Rule Safe Harbor Proposed Self-Regulatory Guidelines; i-SAFE...

Science.gov (United States)

2010-01-13

... Proposed Self-Regulatory Guidelines; i-SAFE, Inc. Application for Safe Harbor AGENCY: Federal Trade... for public comment concerning proposed self-regulatory guidelines submitted by i-SAFE, Inc. under the... approval self-regulatory guidelines that would implement the Rule's protections.\\3\\ \\1\\ 64 FR 59888 (1999...

METHODOLOGICAL APPROACHES TO ORGANIZATION OF SAFE INFORMATION AND EDUCATIONAL ENVIRONMENT OF THE UNIVERSITY

Directory of Open Access Journals (Sweden)

A. N. Privalov

2017-01-01

Full Text Available Introduction. One of the tendencies of modern higher education is the ubiquitous use of information and communication technologies. At the same time, the functioning of the electronic information and educational environment (IEE of the university should be based on the means of IEE and the condition of its information security.The aim of the research is conceptualization of a problem of the rational organization of the safe information and education environment of higher education institution wherein reliable protection of its infrastructure, the personal and unique information of a pupil and teacher and virtual space of their educational interaction is provided.Methodology and research methods. System-based approach is a key approach to organization of safe educational environment of the university. From the point of view of authors, personal-activity and functional approaches are expedient while designing and development of a safe IEE. Socio-historical and theoretical-methodological analysis, modeling, research and synthesis of experience of effective application of the systems approach in educational professional organizations are used.Results and scientific novelty. The concept «safe information educational environment of the university» is specified wherein the first word has to express a predominant quality of the system. Creating a safe information environment in educational professional organizations provides a convenient and safe educational environment in the process of professional training of university students. The components and directions for the organization of the safe IEE are highlighted. Practical recommendations for its design and successful functioning are given.Practical significance. The materials of the present research can be demanded by managers and administrative employees of educational organizations. 

Safeness of radiological machinery

International Nuclear Information System (INIS)

Yokoyama, Shun

1979-01-01

The human factors affecting the safeness of radiological machinery, which are often very big and complicated machines, are described from the stand point of handling. 20 to 50% of the troubles on equipments seem to be caused by men. This percentage will become even higher in highly developed equipments. Human factors have a great influence on the safeness of radiological equipments. As the human factors, there are sensory factors and knowledge factors as well as psychological factors, and the combination of these factors causes mishandling and danger. Medical services at present are divided in various areas, and consist of the teamwork of the people in various professions. Good human relationship, education and control are highly required to secure the safeness. (Kobatake, H.)

Design improvements for gloveboxes used [in] {sup 238}PuO{sub 2} process operations

Energy Technology Data Exchange (ETDEWEB)

George, T.G. [Los Alamos National Lab., NM (United States). Nuclear Materials Technology Div.

1997-09-01

{sup 238}PuO{sub 2} process operations are housed in a complex of 76 gloveboxes and introductory hoods connected by means of an overhead trolley housed in a tunnel. Because a significant number of the gloveboxes used for {sup 238}PuO{sub 2} processing were installed before the original startup of the facility in 1978, they have been in service for nearly 20 years. During a recent heat source production campaign, numerous contamination releases in the {sup 238}PuO{sub 2} processing area were traced to degraded elastomer gaskets used for glovebox connections, and attachment of feed-throughs, service panels, and windows. Evaluation of the degraded gaskets revealed that a combination of radiolytic degradation related to the high specific activity of {sup 238}Pu, and extended service at high altitude in a low (to extremely low) humidity environment had resulted in accelerated gasket aging. However, it was also apparent that gasket design was the most important factor in actual contamination release. All of the contamination releases that were traced to degraded gaskets occurred in variations of a design that used a spline to expand an elastomeric gasket into the space between a connecting flange, window, or service panel, and a glovebox opening. No contamination releases were traced to the gasket design that employed bolted clamps to compress the gasket between a connecting flange, window, or panel, and the exterior surface of a glovebox opening. As a result of these findings, the Actinide Ceramics group at LANL (NMT-9) has initiated a routine replacement and upgrade program to replace aging gloveboxes. All of the new gloveboxes will utilize the preferred gasket design, which is expected to reduce the number and frequency of contamination releases.

Safe Kids Week: Analysis of gender bias in a national child safety campaign, 1997-2016.

Science.gov (United States)

Bauer, Michelle E E; Brussoni, Mariana; Giles, Audrey R; Fuselli, Pamela

2017-09-29

Background and Purpose Child safety campaigns play an important role in disseminating injury prevention information to families. A critical discourse analysis of gender bias in child safety campaign marketing materials can offer important insights into how families are represented and the potential influence that gender bias may have on uptake of injury prevention information. Methods Our approach was informed by poststructural feminist theory, and we used critical discourse analysis to identify discourses within the poster materials. We examined the national Safe Kids Canada Safe Kids Week campaign poster material spanning twenty years (1997-2016). Specifically, we analyzed the posters' typeface, colour, images, and language to identify gender bias in relation to discourses surrounding parenting, safety, and societal perceptions of gender. Results The findings show that there is gender bias present in the Safe Kids Week poster material. The posters represent gender as binary, mothers as primary caregivers, and showcase stereotypically masculine sporting equipment among boys and stereotypically feminine equipment among girls. Interestingly, we found that the colour and typeface of the text both challenge and perpetuate the feminization of safety. Discussion It is recommended that future child safety campaigns represent changing family dynamics, include representations of children with non-traditionally gendered sporting equipment, and avoid the representation of gender as binary. This analysis contributes to the discussion of the feminization of safety in injury prevention research and challenges the ways in which gender is represented in child safety campaigns. © Article author(s) (or their employer(s) unless otherwise stated in the text of the article) 2017. All rights reserved. No commercial use is permitted unless otherwise expressly granted.

Compliance assurance for the safe transport of radioactive material. Safety guide

International Nuclear Information System (INIS)

2009-01-01

The objectives of this Safety Guide are to assist competent authorities in the development and maintenance of compliance assurance programmes in connection with the transport of radioactive material, and to assist applicants, licensees and organizations in their interactions with competent authorities. In order to increase cooperation between competent authorities and to promote the uniform application of international regulations and recommendations, it is desirable to adopt a common approach to regulatory activities. This Safety Guide is intended to assist in accomplishing such a uniform application by recommending most of the actions for which competent authorities need to provide in their programmes for ensuring compliance with the Transport Regulations. This Safety Guide addresses radiation safety aspects of the transport of radioactive material; that is, the subjects that are covered by the Transport Regulations. Radioactive material may have other dangerous properties, however, such as explosiveness, flammability, pyrophoricity, chemical toxicity and corrosiveness; these properties are required to be taken into account in the regulatory control of the design and transport of packages. Physical protection and systems for accounting for and control of nuclear material are also discussed in this Safety Guide. These subjects are not within the scope of the Transport Regulations, but information on them is included here because they must be taken into account in the overall regulatory control of transport, especially when the regulatory framework is being established. Section 1 informs about the background, the objective, the scope and the structure of this publication. Section 2 provides recommendations on the responsibilities and functions of the competent authority. Section 3 provides information on the various national and international regulations and guides for the transport of radioactive material. Section 4 provides recommendations on carrying out

The safe use of radiation sources

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-12-01

of Sealed Sources', and 'Safety and Regulation of Radiation Sources', were held at Argonne National Laboratory, Argonne, Illinois, in 1989 and 1990, respectively. Two regional courses on 'Safety and Regulation of Radiation Sources', were held in 1991, one in Mexico City, in Spanish, for the Latin American Region, and the other in Kuala Lumpur, Malaysia, for the Asian Region. In order to encourage training in radiation safety, the IAEA developed a new series on training courses, the first of which is the Manual on Safe Transport of Radioactive Material, issued in 1991. Because of the success of this manual and of the five training courses held in 1989, 1990 and 1991 on the safety of radiation sources, it was decided to develop a hotline on the safe useand regulation of radiation sources. This manual may also be used at other such courses that individual Member States may wish to sponsor.

The safe use of radiation sources

International Nuclear Information System (INIS)

1995-01-01

of Sealed Sources', and 'Safety and Regulation of Radiation Sources', were held at Argonne National Laboratory, Argonne, Illinois, in 1989 and 1990, respectively. Two regional courses on 'Safety and Regulation of Radiation Sources', were held in 1991, one in Mexico City, in Spanish, for the Latin American Region, and the other in Kuala Lumpur, Malaysia, for the Asian Region. In order to encourage training in radiation safety, the IAEA developed a new series on training courses, the first of which is the Manual on Safe Transport of Radioactive Material, issued in 1991. Because of the success of this manual and of the five training courses held in 1989, 1990 and 1991 on the safety of radiation sources, it was decided to develop a hotline on the safe use and regulation of radiation sources. This manual may also be used at other such courses that individual Member States may wish to sponsor

Regulations for the Safe Transport of Radioactive Material. 2012 Edition. Specific Safety Requirements (French Edition); Reglement de transport des matieres radioactives. Edition de 2012

Energy Technology Data Exchange (ETDEWEB)

NONE

2013-03-15

The IAEA's Statute authorizes the Agency to ''establish or adopt standards of safety for protection of health and minimization of danger to life and property'' - standards that the IAEA must use in its own operations, and which States can apply by means of their regulatory provisions for nuclear and radiation safety. The IAEA does this in consultation with the competent organs of the United Nations and with the specialized agencies concerned. A comprehensive set of high quality standards under regular review is a key element of a stable and sustainable global safety regime, as is the IAEA's assistance in their application. The IAEA commenced its safety standards programme in 1958. The emphasis placed on quality, fitness for purpose and continuous improvement has led to the widespread use of the IAEA standards throughout the world. The Safety Standards Series now includes unified Fundamental Safety Principles, which represent an international consensus on what must constitute a high level of protection and safety. With the strong support of the Commission on Safety Standards, the IAEA is working to promote the global acceptance and use of its standards. Standards are only effective if they are properly applied in practice. The IAEA's safety services encompass design, siting and engineering safety, operational safety, radiation safety, safe transport of radioactive material and safe management of radioactive waste, as well as governmental organization, regulatory matters and safety culture in organizations. These safety services assist Member States in the application of the standards and enable valuable experience and insights to be shared. Regulating safety is a national responsibility, and many States have decided to adopt the IAEA's standards for use in their national regulations. For parties to the various international safety conventions, IAEA standards provide a consistent, reliable means of ensuring the effective fulfilment of obligations under the

Final Environmental Assessment: Perimeter Fence Upgrade and Demolition of Two Sheds and Two Water Tanks, Lake Kickapoo Air Force Space Surveillance Station, Texas

Science.gov (United States)

2012-11-01

conglomerates of the Nocona and Archer City Formations. Quaternary gravels, terrace deposits, and alluvium are present along the major drainages in the...packings, gaskets, resilient floor covering, pliable sealants and mastics and asphalt roofing products containing more than one percent asbestos...flooring and roofing materials. Less commonly used as a building material since the mid-1970s, asbestos is still in use or distribution in certain

Randomized Trial of a Children's Book Versus Brochures for Safe Sleep Knowledge and Adherence in a High-Risk Population.

Science.gov (United States)

Hutton, John S; Gupta, Resmi; Gruber, Rachel; Berndsen, Jennifer; DeWitt, Thomas; Ollberding, Nicholas J; Van Ginkel, Judith B; Ammerman, Robert T

Sleep-related infant deaths have plateaued in the past decade, disproportionately affecting low socioeconomic status (SES) families. Printed materials are widely used for anticipatory guidance, yet none for safe sleep has been studied. We tested the efficacy of a specially designed children's book compared to brochures for safe sleep knowledge and adherence, which we hypothesized would be greater due to superior readability and engagement. This randomized controlled trial involved low-SES mothers (n = 282) enrolled in a home visiting program. Home visitors (n = 56) were randomly assigned to perform safe sleep teaching and assessments during 3 visits: third trimester, 1 week old, and 2 months old, exclusively utilizing a specially designed children's book or brochures, and surveys incorporating the American Academy of Pediatrics' safe sleep recommendations. Outcomes were safe sleep knowledge, adherence, and usefulness of materials, controlling for maternal health literacy. Safe sleep knowledge increased across all time points with no overall group difference, though gains for sleep-evocative and general health items varied. Odds of bed sharing were higher and exclusive crib use lower for the brochure group (P book and mothers in the book group reported more book sharing with their baby. While a specially designed children's book and brochures were equally effective conveying aggregate safe sleep knowledge in low-SES mothers, adherence to exclusive crib use and avoiding bed sharing were greater in the book group, attributable to enhanced dialogue, readability and emotional engagement. Children's books are a promising mode of anticipatory guidance, warranting further investigation. Copyright © 2017 Academic Pediatric Association. Published by Elsevier Inc. All rights reserved.

Safe Cooperating Cyber-Physical Systems using Wireless Communication

DEFF Research Database (Denmark)

Pop, Paul; Scholle, Detlef; Sljivo, Irfan

2017-01-01

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

Systems for the safe operation of the JET tokamak with tritium

International Nuclear Information System (INIS)

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

1999-01-01

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

InaSAFE applications in disaster preparedness

Science.gov (United States)

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

2015-04-01

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

Safe Minimum Internal Temperature Chart

Science.gov (United States)

... Internal Temperature Chart Safe steps in food handling, cooking, and storage are essential in preventing foodborne illness. You can't see, smell, or taste harmful bacteria that may cause illness. In every step of food preparation, follow the four guidelines to keep food safe: ...

General problems associated with the control and safe use of radiation sources (199)

International Nuclear Information System (INIS)

Ahmed, J.U.

1993-01-01

There are problems at various levels in ensuring safety in the use of radiation sources. A relatively new problem that warrants international action is the smuggling of radioactive material across international borders. An international convention on the control and safe use of radiation sources is essential to provide a universally harmonized mechanism for ensuring safety

Study on the Post-Fire Safe-Shutdown Analysis for CANDU NPPs

Energy Technology Data Exchange (ETDEWEB)

Kim, In Hwan; Kim, Yun Jung; Park, Mun Hee [KHNP Central Research Institute, Daejeon (Korea, Republic of)

2015-10-15

The purpose of this paper is to study a method of the Post-Fire Safe-Shutdown Analysis in order to apply to CANDU NPPs when one group of the Safety Structures, Systems and Components(SCCs) is failed by Fire. The purpose of Fire Protection is prevention, suppression of the fire and mitigation of the effect on the Nuclear Safety. When fire takes place at the Nuclear Power Plants(NPPs), the reactor should achieve and maintain safe shut-down condition and minimize radioactive material release to an environment. The purpose of the Post-Fire SSA process is an evaluation process during a fire at NPPs. At this study, the process was conceptually adopted for control room complex of CANDU NPPs. The Core Damage Frequency of the Reactor will be evaluated more accurately if the SSA is adopted adequately at a fire.

Quality performance-based training enhances safe and effective transport operations

International Nuclear Information System (INIS)

McCall, D.L.

1993-01-01

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

Safe affordable fission engine (SAFE 30) module conductivity test thermal model correlation

International Nuclear Information System (INIS)

Roman, Jose

2001-01-01

The SAFE 30 is a simple, robust space fission power system that is comprised of several independent modules. Each module contains 4 fuel tubes bonded to a central heatpipe. Fission energy is conducted from the fuel tubes to the heatpipe, which in turn transfers the energy to a power conversion system. This paper benchmarks a thermal model of the SAFE 30 with actual test data from simulated SAFE 30 module tests. Two 'dummy' SAFE 30 modules were fabricated - each consisted of 4 1-inch dia. tubes (simulating the fuel tubes) bonded to a central '1' dia. tube (simulating the heatpipe). In the first module the fuel tubes were simply brazed to the heatpipe along the line of contact (leaving void space in the interstices), and in the second module the tubes and heatpipe were brazed via tri-cusps that completely fill the interstices between the tubes. In these tests, fission energy is simulated by placing resistance heaters within each of the 4 fuel tubes. The tests were conducted in a vacuum chamber in 4 configurations: tri-cusps filled with and without an outer insulation wrap, and no tri-cusps with and without an outer insulation wrap. The baseline SAFE 30 configuration uses the brazed tri-cusps. During the tests, the power applied to the heaters was varied in a stepwise fashion, until a steady-state temperature profile was reached. These temperature levels varied between 773 K and 1073 K. To benchmark the thermal model, the input energy and chamber surface temperature were used as boundary conditions for the model. The analytical results from the nodes at the same location as the test thermocouples were plotted again test data to determinate the accuracy of the analysis. The unknown variables on the analysis are the radiation emissivity of the pipe and chamber and the radiation view factor between the module and the chamber. A correlation was determined using a parametric analysis by varying the surface emissivity and view factor until a good match was reached. This

Ultrasonic examination for safe end to nozzle dissimilar metal welds of steam generator

International Nuclear Information System (INIS)

Wang Zhuowei; Yu Jingsheng; Wang Jianjun

2014-01-01

The safe-end weld of steam generator is narrow seam weld with dissimilar metal, the filling material is nickel alloy 152/182 (material 690). The interior structure is of great anisotropic, and fake signal may occur during the defect detection by ultrasonic wave and the error for defect location may be increased. Stratified inspection by ultrasonic transducers with different angle and focus is a practical method which is verified by the real inspection while the linear indication in the inside surface besides the interior flaws are detected. (authors)

How is safe information about science and technology communicated tangibly?

International Nuclear Information System (INIS)

Kawai, Jun; Funabiki, Jun

2008-01-01

Nuclear power plants hit by the Chuetsu-oki earthquake in 2007 made clear difficulties for engineers to communicate the safe information to the public. Such communication difficulties are common to advanced science in nuclear energy as well as environmental issues, biotechnologies and others. This article introduced 'science editorial guides' established in order to realize tangible expression of science and technology information' on business. Guides consist of (1) 'prepare materials for science communication', (2) arouse concerns', (3) 'encourage understanding' and (4) memorize'. (T. Tanaka)

Fly ash. Quality recycling material

Energy Technology Data Exchange (ETDEWEB)

Blomster, D.; Leisio, C.

1996-11-01

Imatran Voima`s coal-fired power plants not only generate power and heat but also produce fly ash which is suitable raw material for recycling. This material for recycling is produced in the flue gas cleaning process. It is economical and, thanks to close quality control, is suitable for use as a raw material in the building materials industry, in asphalt production, and in earthworks. Structures made from fly ash are also safe from an environmental point of view. (orig.)

46 CFR 160.041-3 - Construction and workmanship.

Science.gov (United States)

2010-10-01

... construction, with the body, handle, and all fittings of a corrosion-resistant material or suitably protected against corrosion. All ferrous metal employed shall be protected by hot dip galvanizing, or other equally... and joints shall be welded or brazed. Either the body or the cover shall contain a gasket of molded...

76 FR 39813 - Notice of Funding Availability of Applications (NOFA) for Section 514 Farm Labor Housing Loans...

Science.gov (United States)

2011-07-07

... insulation exceeds code for a maximum of 2 points. (2 points total) Reduction in building shell air leakage.... Building shell air leakage may be reduced through materials such as caulk, spray foam, gaskets, and house... and biomass/biofuel systems that do not use fossil fuels in production. Geo-exchange systems are...

Steering teens safe: a randomized trial of a parent-based intervention to improve safe teen driving.

Science.gov (United States)

Peek-Asa, Corinne; Cavanaugh, Joseph E; Yang, Jingzhen; Chande, Vidya; Young, Tracy; Ramirez, Marizen

2014-07-31

Crashes are the leading cause of death for teens, and parent-based interventions are a promising approach. We assess the effectiveness of Steering Teens Safe, a parent-focused program to increase safe teen driving. Steering Teens Safe aimed to improve parental communication with teens about safe driving using motivational interviewing techniques in conjunction with 19 safe driving lessons. A randomized controlled trial involved 145 parent-teen dyads (70 intervention and 75 control). Intervention parents received a 45-minute session to learn the program with four follow-up phone sessions, a DVD, and a workbook. Control parents received a standard brochure about safe driving. Scores were developed to measure teen-reported quantity and quality of parental communication about safe driving. The main outcome measure was a previously validated Risky Driving Score reported by teens. Because the Score was highly skewed, a generalized linear model based on a gamma distribution was used for analysis. Intervention teens ranked their parent's success in talking about driving safety higher than control teens (p = 0.035) and reported that their parents talked about more topics (non-significant difference). The Risky Driving Score was 21% lower in intervention compared to control teens (85% CI = 0.60, 1.00). Interaction between communication quantity and the intervention was examined. Intervention teens who reported more successful communication had a 42% lower Risky Driving Score (95% CI = 0.37, 0.94) than control parents with less successful communication. This program had a positive although not strong effect, and it may hold the most promise in partnership with other programs, such as Driver's Education or Graduated Driver's License policies. ClinicalTrials.gov NCT01014923. Registered Nov. 16, 2009.

Staying Safe in the Water

Centers for Disease Control (CDC) Podcasts

In this podcast, Dr. Julie Gilchrist, a pediatrician and medical epidemiologist from CDC’s Injury Center, talks about staying safe in the water. Tips are for all audiences, with a focus on preventing drownings and keeping children safe in and around the pool, lake, or ocean.

Basic concepts of materials accounting

International Nuclear Information System (INIS)

Markin, J.T.

1989-01-01

The importance of accounting for nuclear materials to the efficient, safe, and economical operation of nuclear facilities is introduced, and the following topics are covered: material balance equation; item control areas; material balance uncertainty; decision procedures for materials accounting; conventional and near-real-time accounting; regulatory requirements of the US Department of Energy and the Nuclear Regulatory Commission; and a summary related to the development of a materials accounting system to implement the basic concepts described. The summary includes a section on each of the following: problem definition, system objectives, and system design

Safe biodegradable fluorescent particles

Science.gov (United States)

Martin, Sue I [Berkeley, CA; Fergenson, David P [Alamo, CA; Srivastava, Abneesh [Santa Clara, CA; Bogan, Michael J [Dublin, CA; Riot, Vincent J [Oakland, CA; Frank, Matthias [Oakland, CA

2010-08-24

A human-safe fluorescence particle that can be used for fluorescence detection instruments or act as a safe simulant for mimicking the fluorescence properties of microorganisms. The particle comprises a non-biological carrier and natural fluorophores encapsulated in the non-biological carrier. By doping biodegradable-polymer drug delivery microspheres with natural or synthetic fluorophores, the desired fluorescence can be attained or biological organisms can be simulated without the associated risks and logistical difficulties of live microorganisms.

High temperature performance limit of containment system of transport cask

International Nuclear Information System (INIS)

Kato, Osamu; Saegusa, Toshiari

1998-01-01

The containment performance of a containment system using elastomer gaskets for transport casks under a high temperature and high pressure was clarified. Major results are as follows; (1) The deformation characteristics of the gaskets were represented by the compressive permanent strain rate (Dp). The temperature and time dependence was shown by Larson-Miller Parameter (LMP). (2) Generally, the high temperature performance limit is obtained by a value of LMP when the Dp value reaches 80%. However, the gaskets (FKM, VMQ, EPDM) used for real transport casks were not damaged and the containment performance was not deteriorated as a conservative condition. (3) Assuming that the service period of the gaskets for transport casks is 3 months or 1 year, the high temperature performance limit of the gasket made of fluorine rubber (FKM) is 202degC or 182degC, respectively, which includes safety margin. (author)

Safe Haven.

Science.gov (United States)

Bush, Gail

2003-01-01

Discusses school libraries as safe havens for teenagers and considers elements that foster that atmosphere, including the physical environment, lack of judgments, familiarity, leisure, and a welcoming nature. Focuses on the importance of relationships, and taking the time to listen to teens and encourage them. (LRW)

Safe abortion information hotlines: An effective strategy for increasing women's access to safe abortions in Latin America.

Science.gov (United States)

Drovetta, Raquel Irene

2015-05-01

This paper describes the implementation of five Safe Abortion Information Hotlines (SAIH), a strategy developed by feminist collectives in a growing number of countries where abortion is legally restricted and unsafe. These hotlines have a range of goals and take different forms, but they all offer information by telephone to women about how to terminate a pregnancy using misoprostol. The paper is based on a qualitative study carried out in 2012-2014 of the structure, goals and experiences of hotlines in five Latin American countries: Argentina, Chile, Ecuador, Peru and Venezuela. The methodology included participatory observation of activities of the SAIH, and in-depth interviews with feminist activists who offer these services and with 14 women who used information provided by these hotlines to induce their own abortions. The findings are also based on a review of materials obtained from the five hotline collectives involved: documents and reports, social media posts, and details of public demonstrations and statements. These hotlines have had a positive impact on access to safe abortions for women whom they help. Providing these services requires knowledge and information skills, but little infrastructure. They have the potential to reduce the risk to women's health and lives of unsafe abortion, and should be promoted as part of public health policy, not only in Latin America but also other countries. Additionally, they promote women's autonomy and right to decide whether to continue or terminate a pregnancy. Copyright © 2015. Published by Elsevier Ltd.

Code of safe practice for the use of x-rays in dentistry

International Nuclear Information System (INIS)

1991-06-01

The purpose of this Code of Safe Practice for the Use of X-rays in Dentistry is to provide criteria for working procedures, x-ray equipment and protective materials necessary for the use of x-rays in dental diagnosis according to currently accepted standards of safety. Conformity with this code may be taken as a primary indication of compliance with radiation protection legislation. 7 refs., 1 ill

Compliance assurance for the safe transport of radioactive material

International Nuclear Information System (INIS)

1994-01-01

The purpose of this book is to assist competent authorities in the development and maintenance of compliance assurance programmes in connection with the transport of radioactive material, and to assist applicants, licensees and organizations in their interactions, with competent authorities. In order to increase co-operation between competent authorities and to promote uniform application of international regulations and recommendations it is desirable to adopt a common approach to regulatory activities. This book is intended to assist in accomplishing such uniform application by laying down most of the actions that competent authorities need to provide for in their programmes for ensuring regulatory compliance. 23 refs, figs and tabs

Regulations for the Safe Transport of Radioactive Material, 2009 ed. Safety Requirements

International Nuclear Information System (INIS)

2009-01-01

This publication establishes the regulations that are applied to the transport of radioactive material by all modes of transport on land, water or in the air, including transport that is incidental to the use of the radioactive material. The objective and scope of the regulations are described in detail as well as the range of their application. The publication provides requirements useful to governments, regulators, operators of nuclear and radiation facilities, carriers, users of radiation sources and cargo handling personnel. Contents: 1. Introduction; 2. Definitions; 3. General provisions; 4. Activity limits and classification; 5. Requirements and controls for transport; 6. Requirements for radioactive materials and for packagings and packages; 7. Test procedures; 8. Approval and administrative requirements; Annex I: Summary of approval and prior notification requirements; Annex II: Conversion factors and prefixes.

Effects of irritant chemicals on Aedes aegypti resting behavior: is there a simple shift to untreated "safe sites"?

Directory of Open Access Journals (Sweden)

Hortance Manda

2011-07-01

Full Text Available BACKGROUND: Previous studies have identified the behavioral responses of Aedes aegypti to irritant and repellent chemicals that can be exploited to reduce man-vector contact. Maximum efficacy of interventions based on irritant chemical actions will, however, require full knowledge of variables that influence vector resting behavior and how untreated "safe sites" contribute to overall impact. METHODS: Using a laboratory box assay, resting patterns of two population strains of female Ae. aegypti (THAI and PERU were evaluated against two material types (cotton and polyester at various dark:light surface area coverage (SAC ratio and contrast configuration (horizontal and vertical under chemical-free and treated conditions. Chemicals evaluated were alphacypermethrin and DDT at varying concentrations. RESULTS: Under chemical-free conditions, dark material had significantly higher resting counts compared to light material at all SAC, and significantly increased when material was in horizontal configuration. Cotton elicited stronger response than polyester. Within the treatment assays, significantly higher resting counts were observed on chemical-treated dark material compared to untreated light fabric. However, compared to matched controls, significantly less resting observations were made on chemical-treated dark material overall. Most importantly, resting observations on untreated light material (or "safe sites" in the treatment assay did not significantly increase for many of the tests, even at 25% SAC. Knockdown rates were ≤5% for all assays. Significantly more observations of flying mosquitoes were made in test assays under chemical-treatment conditions as compared to controls. CONCLUSIONS/SIGNIFICANCE: When preferred Ae. aegypti resting sites are treated with chemicals, even at reduced treatment coverage area, mosquitoes do not simply move to safe sites (untreated areas following contact with the treated material. Instead, they become agitated

More than a Safe Space

Science.gov (United States)

Sadowski, Michael

2016-01-01

Over the past three decades, much of the conversation about LGBTQ students in schools has centered on safety--anti-bullying policies, the "safe space" of gay-straight alliances, and "safe zones" marked by rainbow-colored stickers on classroom doors. In this article, Michael Sadowski argues that it's time to move beyond safety…

Plasma-material interactions

International Nuclear Information System (INIS)

Wilson, K.L.

1984-01-01

Plasma-interactive components must be resistant to erosion processes, efficient in heat removal, and effective in minimizing tritium inventory and permeation. As long as plasma edge temperatures are 50 eV, no one material can satisfy the diverse requirements imposed by these plasma materials interactions. The only solution is the design of duplex, or even more complicated, structures. The material that faces the plasma should be low atomic number, with acceptable erosion and evaporation characteristics. The substrate material must have high thermal conductivity for heat removal. Finally, materials must be selected judiciously for tritium compatibility. In conclusion, materials play a critical role in the achievement of safe and economical magnetic fusion energy. Improvements in materials have already led to many advances in present day device operation, but additional innovative materials solutions are required for the critical plasma materials interaction issues in future power reactors

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

African Journals Online (AJOL)

Results: Safe injection procedures regarding final waste disposal were sufficiently adopted, while measures regarding disposable injection equipment, waste containers, hand hygiene, as well as injection practices were inadequately carried out. Lack of job aid posters that promote safe injection and safe disposal of ...

Filter assembly for metallic and intermetallic tube filters

Science.gov (United States)

Alvin, Mary Anne; Lippert, Thomas E.; Bruck, Gerald J.; Smeltzer, Eugene E.

2001-01-01

A filter assembly (60) for holding a filter element (28) within a hot gas cleanup system pressure vessel is provided, containing: a filter housing (62), said filter housing having a certain axial length and having a peripheral sidewall, said sidewall defining an interior chamber (66); a one piece, all metal, fail-safe/regenerator device (68) within the interior chamber (66) of the filter housing (62) and/or extending beyond the axial length of the filter housing, said device containing an outward extending radial flange (71) within the filter housing for seating an essential seal (70), the device also having heat transfer media (72) disposed inside and screens (80) for particulate removal; one compliant gasket (70) positioned next to and above the outward extending radial flange of the fail-safe/regenerator device; and a porous metallic corrosion resistant superalloy type filter element body welded at the bottom of the metal fail-safe/regenerator device.

Clarification of Safe Delivery by Iranian Experts Based on Clinical Governance: A Qualitative Study

Directory of Open Access Journals (Sweden)

Forozun Olfati

2015-10-01

Full Text Available Objective:To clarify the principles of a safe delivery based on Clinical Governance Criteria, as recommended by the pertinent experts.Materials and methods:The current study was part of a qualitative research conducted by content analysis method in 2013 and purposive sampling, performing 24 in-depth interviews based on semi-structured questions and analyzed using thematic content analysis. The participants in this research included midwives, obstetricians, managers, and hospital doctors. The data were under continuous consideration and comparative analysis in order to achieve data saturation.Results:The main concepts derived from interpretations of the pertinent experts include: Patient & Public involvement; Risk Management; Education; Clinical efficiency; Clinical audit; Personnel & Management.Conclusion:In a safe delivery, there is a vicious cycle of causes the elimination of which is only possible through benchmarking patterns that attend to most aspects of a safe delivery.Changes to services require utilization of appropriate change management strategies.

Keeping Sealed Radioactive Sources Safe and Secure

International Nuclear Information System (INIS)

Potterton, Louise

2013-01-01

Radioactive sources are used in a wide variety of devices in medical, industrial, agricultural and research facilities worldwide. These sources, such as cobalt-60 and caesium-137, emit high levels of ionizing radiation, which can treat cancer, measure materials used in industry and sterilize food and medical appliances. Problems may arise when these sources are no longer needed, or if they are damaged or decayed. If these sources are not properly stored they can be a threat to human health and the environment and pose a security risk. Procedures to secure these spent or 'disused' sources are often highly expensive and need specialized assistance. The IAEA helps its States find long term solutions for the safe and secure storage of disused sealed radioactive sources (DSRSs)

Managing Cassini Safe Mode Attitude at Saturn

Science.gov (United States)

Burk, Thomas A.

2010-01-01

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

Better safe than sorry: Increasing safety in radioactive waste management

International Nuclear Information System (INIS)

Gaspar, Miklos; Mutluer, Adem

2015-01-01

Abderrahim Bouih used to be worried about space. In charge of managing Morocco’s radioactive waste since 2006, he had long projected that the country’s sole radioactive waste facility would fill up by 2019. Thanks to a new methodology he and his colleagues learned through an IAEA project, they can now dismantle smoke detectors, lightning rods and other waste that contains radioactive material, safely separating the radioactive components from the metal, and significantly reducing the amount of radioactive waste they need to store.

USING POLYMERIC HYDROGEN GETTERS TO PREVENT COMBUSTIBLE ATMOSPHERES DURING INTERIM SAFE STORAGE OF PLUTONIUM OXIDE

International Nuclear Information System (INIS)

Woodsmall, T

2007-01-01

Nuclear Materials Management (NMM) of WSRC has recently installed the capability to perform both non-destructive and destructive examination of 3013 containers of Pu oxide in accordance with DOE-STD-3013. The containers will be opened and the oxide will be sampled for analysis. The remaining bulk oxide must then be safely stored in a non-3013-compliant configuration. Available processing equipment and controls cannot prevent the oxide from adsorbing moisture during this process. Subsequent radiolysis of moisture during storage may generate combustible quantities of gases while waiting final processing, and satisfying DOE Interim Safe Storage Criteria (ISSC) would require that storage containers be vented at impractical frequencies. With support from an independent National Laboratory, WSRC/NMM has demonstrated that a commercial hydrogen getter material will effectively prevent the accumulation of combustible gas concentrations. A project overview, including storage requirements and strategies, as well as getter technology, current test results, and anticipated future developments will be addressed

Some views on the two-year review/revision cycle of the IAEA ''regulations for the safe transport of radioactive material''

International Nuclear Information System (INIS)

Fasten, C.; Nitsche, F.

2004-01-01

The ''Regulations for the Safe Transport of Radioactive Material'' of the International Atomic Energy Agency (IAEA), Vienna were last issued as a complete revised edition in 1996 as Safety Standards Series No. ST-1 [1]. A modification to this edition was made in 2000 - only in English - incorporating minor editorial corrections published as Safety Standards Series No. TS-R-1 (ST-1, Revised). Issues in French, Russian and Spanish followed shortly. A continuos review/revision process of the transport regulations was initiated in 2000 to publish an amended or a revised edition every two years. This two-year review cycle has been established to harmonise it with the review cycles of the other United Nations dangerous goods regulatory bodies, namely - the UN Committee of Experts on the Transport of Dangerous Goods, Geneva - the International Civil Aviation Organisation (ICAO), Montreal - the International Maritime Organisation (IMO), London and - the United Nations Economic Commission for Europe (UN-ECE) - Inland Transport Committee, Geneva. - Intergovernmental Organisation for International Carriage by rail (OTIF), Bern. These bodies are responsible to issue the regulations for the transport of all classes of dangerous goods (where the class 7 is ''Radioactive Material''), for the international air transport (ICAO), for the international maritime transport (IMO) and the European road, rail and inland waterway transport (UN-ECE, OTIF). The regulations of the above mentioned bodies have been published for many years within a two year period with good experience. Since 2000 the IAEA has been using the two-year cycle also. Based on this relative short time of application first experiences with this two-year cycle will be discussed

Nuclear Materials Management for the Nevada Test Site (NTS)

International Nuclear Information System (INIS)

Jesse C. Schreiber

2007-01-01

The Nevada Test Site (NTS) has transitioned from its historical role of weapons testing to a broader role that is focused on being a solution to multiple National Nuclear Security Administration (NNSA) challenges and opportunities with nuclear materials for the nation. NTS is supporting other NNSA sites challenged with safe nuclear materials storage and disposition. NNSA, with site involvement, is currently transforming the nuclear stockpile and supporting infrastructure to meet the 2030 vision. Efforts are under way to make the production complex smaller, more consolidated, and more modern. With respect to the nuclear material stockpile, the NNSA sites are currently reducing the complex nuclear material inventory through dispositioning and consolidating nuclear material. This includes moving material from other sites to NTS. State-of-the-art nuclear material management and control practices at NTS are essential for NTS to ensure that these new activities are accomplished in a safe, secure, efficient, and environmentally responsible manner. NTS is aggressively addressing this challenge

Inherently safe light water reactors

International Nuclear Information System (INIS)

Ise, Takeharu

1987-01-01

Today's large nuclear power reactors of world-wise use have been designed based on the philosophy. It seems that recent less electricity demand rates, higher capital cost and the TMI accident let us acknowledge relative small and simplified nuclear plants with safer features, and that Chernobyl accident in 1983 underlines the needs of intrinsic and passive safety characteristics. In such background, several inherently safe reactor concepts have been presented abroad and domestically. First describing 'Can inherently safe reactors be designed,' then I introduce representative reactor concepts of inherently safe LWRs advocated abroad so far. All of these innovative reactors employ intrinsic and passive features in their design, as follows: (1) PIUS, an acronym for Process Inherent Ultimate Safety, or an integral PWR with passive heat sink and passive shutdown mechanism, advocated by ASEA-ATOM of Sweden. (2) MAP(Minimum Attention Plant), or a self-pressurized, natural circulation integral PWR, promoted by CE Inc. of the U.S. (3) TPS(TRIGA Power System), or a compact PWR with passive heat sink and inherent fuel characteristics of large prompt temperature coefficient, prompted by GA Technologies Inc. of the U.S. (4) PIUS-BWR, or an inherently safe BWR employing passively actuated fluid valves, in competition with PIUS, prompted by ORNL of the U.S. Then, I will describe the domestic trends in Japan and the innovative inherently safe LWRs presented domestically so far. (author)

Dementia - keeping safe in the home

Science.gov (United States)

... this page: //medlineplus.gov/ency/patientinstructions/000031.htm Dementia - keeping safe in the home To use the ... make sure the homes of people who have dementia are safe for them. Safety Tips for the ...

Safety protection suggestion of naturally occurring radioactive materials in the oil and gas industry

International Nuclear Information System (INIS)

Zhou Xiaojian; Zhou Qifu; Wang Xiaotao; Xu Zhongyang; Song Peifeng

2014-01-01

It's not enough concern about the naturally occurring radioactive materials (NORM) of oil and gas industry in China. NORM with radium and radon mainly exist in the scale, sludge and production water, and they tend to deposit on the pipe wall, wellhead equipment and so on. These materials are a threat to the health of workers, so it is very important to have the safe disposal of them. This paper introduces the radioactive hazards and puts for-ward the safe disposal measures so as to provide the reference for the safe disposal of radioactive materials. Some management and technical advices are presented too. (authors)

Royal Decree 1749/1984 of 1 August approving the national regulations on the safe transport of dangerous goods by air together with technical instructions for the safe transport of dangerous goods by air

International Nuclear Information System (INIS)

1984-01-01

This Royal Decree approves the national Regulations on the safe transport of dangerous goods by air. The Regulations as well as the attached detailed technical instructions are based on the 1981 revised text of the Annex concerning dangerous goods of the Chicago Convention on International Civil Aviation. It also covers radioactive materials. (NEA) [fr

Drug discovery and the impact of the safe harbor provision of the Hatch- Waxman Act.

Science.gov (United States)

Goodson, Susanne H

2010-01-01

Many facets of drug discovery involve the use of patented materials and methods, subjecting the researcher to potential liability from infringement of the underlying patents. Enacted in 1984, the Hatch-Waxman Act established a “safe harbor” for activities that would otherwise constitute infringement of a patented invention, if those activities were “solely for uses reasonably related to the development and submission of information under a Federal law which regulates the manufacture, use, or sale of drugs or veterinary biological products”. This article examines the major court decisions interpreting the scope of the safe harbor and their application to various activities in drug development.

Breastfeeding FAQs: Safely Storing Breast Milk

Science.gov (United States)

... Search English Español Breastfeeding FAQs: Safely Storing Breast Milk KidsHealth / For Parents / Breastfeeding FAQs: Safely Storing Breast ... may have. How do I store my breast milk? You can freeze and/or refrigerate your pumped ( ...

Test for radioactive material transport package safety

International Nuclear Information System (INIS)

Li Guoqiang; Zhao Bing; Zhang Jiangang; Wang Xuexin; Ma Anping

2012-01-01

Regulations on radioactive material transport in China were introduced. Test facilities and data acquiring instruments for radioactive material package in China Institute for Radiation Protection were also introduced in this paper, which were used in drop test and thermal test. Test facilities were constructed according to the requirements of IAEA's 'Regulations for the Safe Transport of Radioactive Material' (TS-R-l) and Chinese 'Regulations for the Safe Transport of Radioactive Material' (GB 11806-2004). Drop test facilities were used in free drop test, penetration test, mechanical test (free drop test Ⅰ, free drop test Ⅱ and free drop test Ⅲ) of type A and type B packages weighing less than thirteen tons. Thermal test of type B packages can be carried out in the thermal test facilities. Certification tests of type FCo70-YQ package, type 30A-HB-01 package, type SY-I package and type XAYT-I package according to regulations were done using these facilities. (authors)

Curiosity's Autonomous Surface Safing Behavior Design

Science.gov (United States)

Neilson, Tracy A.; Manning, Robert M.

2013-01-01

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

Removing Hair Safely

Science.gov (United States)

... For Consumers Home For Consumers Consumer Updates Removing Hair Safely Share Tweet Linkedin Pin it More sharing ... related to common methods of hair removal. Laser Hair Removal In this method, a laser destroys hair ...

Critically safe volume vacuum pickup for use in wet or dry cleanup of radioactive enclosures

International Nuclear Information System (INIS)

Zeren, J.D.

1993-01-01

A physical compact vacuum pickup device of critically safe volume and geometric shape is provided for use in radioactive enclosures, such as a small glove box, to facilitate manual cleanup of either wet or dry radioactive material. The device is constructed and arranged so as to remain safe when filled to capacity with plutonium-239 oxide. Two fine mesh filter bags are supported on the exterior of a rigid fine mesh stainless steel cup. This assembly is sealed within, and spaced from, the interior walls of a stainless steel canister. An air inlet communicates with the interior of the canister. A modified conventional vacuum head is physically connected to, and associated with, the interior of the mesh cup. The volume of the canister, as defined by the space between the mesh cup and the interior walls of the canister, forms a critically safe volume and geometric shape for dry radioactive particles that are gathered within the canister. A critically safe liquid volume is maintained by operation of a suction terminating float valve, and/or by operation of redundant vacuum check/liquid drain valves and placement of the air inlet. 5 figures

SAFE-PLANE, Stress Analysis of Planar Structure by Finite Elements Method

International Nuclear Information System (INIS)

Cornell, D.C.; Reich, Morris

1967-01-01

1 - Description of problem or function: SAFE-PLANE is applied to two- dimensional structures of arbitrary geometry under in-plane loads. Either plane stress or plane strain conditions may be imposed. Mechanical and thermal loads are permitted. 2 - Method of solution: The finite-element method is used to construct a mathematical model by assembling discrete elements. The total potential energy of the structure is determined and subsequently minimized by iteration on components of the displacement field until static equilibrium of the structure is attained. Strains and stresses are computed from the resulting displacements. 3 - Restrictions on the complexity of the problem: Multi-material structures with varying rigidities converge very slowly. Not valid for incompressible materials. Maximum number of nodal points = 675. Maximum number of elements = 1350

Regulations for the Safe Transport of Radioactive Material. 2012 Edition. Specific Safety Requirements. (Russian Edition); Pravila bezopasnoj perevozki radioaktivnykh materialov. Izdanie 2012 goda. Konkretnye trebovaniya bezopasnosti

Energy Technology Data Exchange (ETDEWEB)

NONE

2013-03-15

The IAEA's Statute authorizes the Agency to 'establish or adopt' standards of safety for protection of health and minimization of danger to life and property' - standards that the IAEA must use in its own operations, and which States can apply by means of their regulatory provisions for nuclear and radiation safety. The IAEA does this in consultation with the competent organs of the United Nations and with the specialized agencies concerned. A comprehensive set of high quality standards under regular review is a key element of a stable and sustainable global safety regime, as is the IAEA's assistance in their application. The IAEA commenced its safety standards programme in 1958. The emphasis placed on quality, fitness for purpose and continuous improvement has led to the widespread use of the IAEA standards throughout the world. The Safety Standards Series now includes unified Fundamental Safety Principles, which represent an international consensus on what must constitute a high level of protection and safety. With the strong support of the Commission on Safety Standards, the IAEA is working to promote the global acceptance and use of its standards. Standards are only effective if they are properly applied in practice. The IAEA's safety services encompass design, siting and engineering safety, operational safety, radiation safety, safe transport of radioactive material and safe management of radioactive waste, as well as governmental organization, regulatory matters and safety culture in organizations. These safety services assist Member States in the application of the standards and enable valuable experience and insights to be shared. Regulating safety is a national responsibility, and many States have decided to adopt the IAEA's standards for use in their national regulations. For parties to the various international safety conventions, IAEA standards provide a consistent, reliable means of ensuring the effective fulfilment of obligations under the conventions

Transport of radioactive material in Bangladesh: a regulatory perspective

International Nuclear Information System (INIS)

Mollah, A.S.

2004-01-01

Radioactive material is transported in Bangladesh in various types of packages and by different modes of transport. The transport of radioactive materials involves a risk both for the workers and members of the public. The safe transport of radioactive material is ensured in Bangladesh by compliance with Nuclear Safety and Radiation Control (NSRC) Act-93 and NSRC Rules-97. The Bangladesh Atomic Energy Commission (BAEC) is the competent authority for the enforcement of the NSRC act and rules. The competent authority has established regulatory control at each stage to ensure radiation safety to transport workers, members of general public and the environment. An overview is presented of the activities related to the transport of radioactive material in Bangladesh. In particular, the applicable legislation, the scope of authority and the regulatory functions of the competent authority are discussed. The categories of radioactive materials transported and the packaging requirements for the safe transport of these radioactive materials are also described. (author)

Transporting radioactive materials: Q ampersand A to your questions

International Nuclear Information System (INIS)

1993-04-01

Over 2 million packages of radioactive materials are shipped each year in the United States. These shipments are carried by trucks, trains, ships, and airplanes every day just like other commodities. Compliance with Federal regulations ensures that radioactive materials are transported safely. Proper packaging is the key to safe shipment. Package designs for radioactive materials must protect the public and the environment even in case of an accident. As the level of radioactivity increases, packaging design requirements become more stringent. Radioactive materials have been shipped in this country for more than 40 years. As with other commodities, vehicles carrying these materials have been involved in accidents. However, no deaths or serious injuries have resulted from exposure to the radioactive contents of these shipments. People are concerned about how radioactive shipments might affect them and the environment. This booklet briefly answers some of the commonly asked questions about the transport of radioactive materials. More detailed information is available from the sources listed at the end of this booklet

Potential safe termination by injection of polypropylene pellets in JET

International Nuclear Information System (INIS)

Schmidt, G.L.; Ali-Arshad, S.; Bartlett, D.

1995-01-01

Thermal energy and the magnetic field energy associated with the plasma current must be dissipated safely when a tokamak discharge is terminated in a disruption. Magnetic energy can be dissipated by impurity radiation if position control is maintained. Prior to the dissipation of magnetic energy, thermal energy is usually conducted to the plasma contact points on a 1ms time scale in a thermal quench. A resistive, highly radiating plasma formed prior to the thermal quench, might dissipate both the thermal and magnetic energy by radiation minimizing damage due to local deposition. High speed injection of a low Z material can produce a resistive, highly radiating plasma on a 1ms time scale. Neon has recently been used in such an application on JT60-U. A large carbon pellet producing dilution temperatures < 1 keV is a possible alternative. This paper summarizes the results of an initial experiment performed in JET using carbon injected at high speed, as a 6mm polypropylene pellet, to investigate this potential approach to a safe plasma termination

Developing Safe Schools Partnerships with Law Enforcement

Science.gov (United States)

Rosiak, John

2009-01-01

Safe schools are the concern of communities throughout the world. If a school is safe, and if children feel safe, students "are better able to learn. But what are the steps to make" this happen? First, it is important to understand the problem: What are the threats to school safety? These include crime-related behaviors that find their way to…

Criteria for the safe storage of enriched uranium at the Y-12 Plant

International Nuclear Information System (INIS)

Cox, S.O.

1995-07-01

Uranium storage practices at US Department of Energy (DOE) facilities have evolved over a period spanning five decades of programmatic work in support of the nuclear deterrent mission. During this period, the Y-12 Plant in Oak Ridge, Tennessee has served as the principal enriched uranium facility for fabrication, chemical processing, metallurgical processing and storage. Recent curtailment of new nuclear weapons production and stockpile reduction has created significant amounts of enriched uranium available as a strategic resource which must be properly and safely stored. This standard specifies criteria associated with the safe storage of enriched uranium at the Y-12 Plant. Because programmatic needs, compliance regulations and desirable materials of construction change with time, it is recommended that these standards be reviewed and amended periodically to ensure that they continue to serve their intended purpose

Compliance assurance in the safe transport of radioactive materials in Switzerland

International Nuclear Information System (INIS)

Smith, L.

1994-01-01

Quality Assurance in the transport of radioactive materials (RAM) has been a legal requirement in Switzerland since 1 January 1990. Some four years later, Switzerland is well on the way to having a comprehensive system of Compliance Assurance covering the transport of RAM. By the end of 1994 Compliance Assurance will be fully operational with regard to nuclear fuel cycle shipments which account for over 90% of all radioactivity transported in Switzerland. Compliance Assurance has been delayed in Switzerland for non-fuel-cycle radioactive material shipments. This has been due to the need to modify the legal infrastructure for the relevant supervisory authorities. Nevertheless, it is hoped to have Compliance Assurance related to Radiation Units (large sources in Type B packages) operational before the end of 1994. Systematic progress is being made regarding Compliance Assurance relating to the movement of smaller sources. This involves a very large number of smaller organisations and will take some time to become routine. (author)

Towards Safe Robotic Surgical Systems

DEFF Research Database (Denmark)

Sloth, Christoffer; Wisniewski, Rafael

2015-01-01

a controller for motion compensation in beating-heart surgery, and prove that it is safe, i.e., the surgical tool is kept within an allowable distance and orientation of the heart. We solve the problem by simultaneously finding a control law and a barrier function. The motion compensation system is simulated...... from several initial conditions to demonstrate that the designed control system is safe for every admissible initial condition....

Safe use of ionizing radiations

Energy Technology Data Exchange (ETDEWEB)

1973-01-01

Based on the ''Code of Practice for the protection of persons against ionizing radiations arising from medical and dental use'' (CIS 74-423), this handbook shows how hospital staff can avoid exposing themselves and others to these hazards. It is designed particularly for junior and student nurses. Contents: ionizing radiations, their types and characteristics; their uses and dangers; basic principles in their safe use; safe use in practice; explanation of terms.

Staying Safe in the Water

Centers for Disease Control (CDC) Podcasts

2008-05-15

In this podcast, Dr. Julie Gilchrist, a pediatrician and medical epidemiologist from CDC’s Injury Center, talks about staying safe in the water. Tips are for all audiences, with a focus on preventing drownings and keeping children safe in and around the pool, lake, or ocean.  Created: 5/15/2008 by National Center for Injury Prevention and Control (NCIPC).   Date Released: 5/19/2008.

Regulatory Framework for the Safe and Secure Transport of Nuclear Material in Japan

International Nuclear Information System (INIS)

Konnai, A.; Shibasaki, N.; Ikoma, Y.; Kato, M.; Yamauchi, T.; Iwasa, T.

2016-01-01

Regulations for nuclear material transport in Japan are based on international regulations. Safety and security regulations, however, have sometime different aspects which have caused a conflict of operations. This paper aims to introduce framework of safety and security regulations for nuclear material transport in Japan, and shows some issues in cooperation of these regulations. (author)

Fractal modeling of fluidic leakage through metal sealing surfaces

Science.gov (United States)

Zhang, Qiang; Chen, Xiaoqian; Huang, Yiyong; Chen, Yong

2018-04-01

This paper investigates the fluidic leak rate through metal sealing surfaces by developing fractal models for the contact process and leakage process. An improved model is established to describe the seal-contact interface of two metal rough surface. The contact model divides the deformed regions by classifying the asperities of different characteristic lengths into the elastic, elastic-plastic and plastic regimes. Using the improved contact model, the leakage channel under the contact surface is mathematically modeled based on the fractal theory. The leakage model obtains the leak rate using the fluid transport theory in porous media, considering that the pores-forming percolation channels can be treated as a combination of filled tortuous capillaries. The effects of fractal structure, surface material and gasket size on the contact process and leakage process are analyzed through numerical simulations for sealed ring gaskets.

Structural materials for fusion reactors

International Nuclear Information System (INIS)

Victoria, M.; Baluc, N.; Spaetig, P.

2001-01-01

In order to preserve the condition of an environmentally safe machine, present selection of materials for structural components of a fusion reactor is made not only on the basis of adequate mechanical properties, behavior under irradiation and compatibility with other materials and cooling media, but also on their radiological properties, i.e. activity, decay heat, radiotoxicity. These conditions strongly limit the number of materials available to a few families of alloys, generically known as low activation materials. We discuss the criteria for deciding on such materials, the alloys resulting from the application of the concept and the main issues and problems of their use in a fusion environment. (author)

Safe operating envelope

Energy Technology Data Exchange (ETDEWEB)

Oliva, N [Ontario Hydro, Toronto, ON (Canada)

1997-12-01

Safe Operating Envelope is described representing: The outer bound of plant conditions within which day-to-day plant operation must be maintained in order to comply with regulatory requirements, associated safety design criteria and corporate nuclear safety goals. Figs.

Safe operating envelope

International Nuclear Information System (INIS)

Oliva, N.

1997-01-01

Safe Operating Envelope is described representing: The outer bound of plant conditions within which day-to-day plant operation must be maintained in order to comply with regulatory requirements, associated safety design criteria and corporate nuclear safety goals. Figs

Metallic iron for safe drinking water provision: Considering a lost knowledge.

Science.gov (United States)

Mwakabona, Hezron T; Ndé-Tchoupé, Arnaud Igor; Njau, Karoli N; Noubactep, Chicgoua; Wydra, Kerstin D

2017-06-15

Around year 1890, the technology of using metallic iron (Fe 0 ) for safe drinking water provision was already established in Europe. The science and technology to manufacture suitable Fe 0 materials were known and further developed in this period. Scientists had then developed skills to (i) explore the suitability of individual Fe 0 materials (e.g. iron filling, sponge iron) for selected applications, and (ii) establish treatment processes for households and water treatment plants. The recent (1990) discovery of Fe 0 as reactive agent for environmental remediation and water treatment has not yet considered this ancient knowledge. In the present work, some key aspects of the ancient knowledge are presented together with some contemporised interpretations, in an attempt to demonstrate the scientific truth contained therein. It appears that the ancient knowledge is an independent validation of the scientific concept that in water treatment (Fe 0 /H 2 O system) Fe 0 materials are generators of contaminant collectors. Copyright © 2017 Elsevier Ltd. All rights reserved.

An Automated Safe-to-Mate (ASTM) Tester

Science.gov (United States)

Nguyen, Phuc; Scott, Michelle; Leung, Alan; Lin, Michael; Johnson, Thomas

2013-01-01

Safe-to-mate testing is a common hardware safety practice where impedance measurements are made on unpowered hardware to verify isolation, continuity, or impedance between pins of an interface connector. A computer-based instrumentation solution has been developed to resolve issues. The ASTM is connected to the circuit under test, and can then quickly, safely, and reliably safe-to-mate the entire connector, or even multiple connectors, at the same time.

Numerical studies of large penetrations and closures for containment vessels subjected to loadings beyond the design basis

International Nuclear Information System (INIS)

Kulak, R.F.; Hsieh, B.J.; Kennedy, J.M.; Ash, J.E.; McLennan, G.A.

1984-01-01

Numerical simulations of the macro-deformations of the sealing surfaces (gasketed junctures) of a PWR steel containment vessel's equipment hatch and a BWR Mk II containment vessel head have been performed. Results for the equipment hatch juncture indicate that the rotations of the hatch cover and penetration sleeve must be accounted for when performing leakage analysis because they can effect the compression of the gasket even though the gasket is in a pressure-seated configuration. Results from a leakage analysis indicated that excessive leakage can occur if the surface roughness is high and/or the compression set is high. Results for the Mk II head show that both the temperature and pressure loadings must be taken into account to obtain realistic responses. The temperature difference between the flanges and bolts has the important net effect of keeping the gasketed juncture closed, that is in metal-to-metal contact. Due to the high accident temperature, the gasket itself was found to achieve 100% compression set and thus could not perform its sealing function within the juncture

Influences of Contact Pressure on the Performances of Polymer Electrolyte Fuel Cells

Directory of Open Access Journals (Sweden)

Prakash C. Ghosh

2013-01-01

Full Text Available Fuel cells face major challenges in sustaining the laboratory-scale performance during the scale up. The contact resistance mainly arises from the dimensional mismatch between gasket and gas diffusion layer during scale up, which may cause diminution in performance. In the present work, experiment as well as modelling is carried out for different combinations of clamping force and gasket thickness. The polarisation behaviours of PEFCs configured under different clamping torques and gasket thicknesses are analysed. The combination of 0.3 mm gasket and 0.3 mm GDL under 3 Nm and 5 Nm clamping forces offers 480 mΩ cm2 and 148 mΩ cm2 contact resistances, respectively. The configurations under 3 Nm and 5 Nm clamping torques with 0.2 mm thick gasket offer contact resistances as low as 23 mΩ cm2 and 11 mΩ cm2, respectively. The polarisation behaviour obtained from the experiment of such configurations is found to be in good agreement with the modelling results.

Selection of exception limits for all actinide nuclides based on revised criteria for safe international transport

International Nuclear Information System (INIS)

Lavarenne, C.; Rouyer, V.; Sert, G.; Mennerdahl, D.; Dean, C.; Barton, N.; Jean, F.

2003-01-01

Since 1998, there have been some speculations about future transport of significant quantities and concentrations of other actinide nuclides than the four currently listed in the regulation for the safe transport of the radioactive material. Therefore, it raised a need to specify exception limits for such actinides. Additionally, the total fissile nuclide mass per consignment of excepted packages was limited in the 1996 edition of the regulations (a conveyance limit is preliminary supported in the 2003 revision). The proposed changes of the rules have to take this new control into account. The European Community (DGTREN) decided to fund a project related to this subject. In order to define credible exception limits, it was necessary to have reasonably accurate data for all actinide nuclides. Then the authors of the study decided to perform calculations with different codes (MONK, MCNP, CRISTAL, SCALE) and different cross-section libraries (JEF2.2, ENDFB, JENDL, etc.). This article presents the work achieved and gives propositions of modification for the IAEA requirements for the Safe Transport of Radioactive Material related to, firstly, the list of the fissile materials, and secondly, the rule to determine the quantities of actinide nuclides that can be excepted from the requirements for the packages containing fissile materials. The participants acknowledge the DGTREN who made this work possible due to its support. (author)

USING THE SAFE SYSTEM APPROACH TO KEEP OLDER DRIVERS SAFELY MOBILE

Directory of Open Access Journals (Sweden)

Jim LANGFORD

2006-01-01

Full Text Available In 2003, Australian road transport jurisdictions collectively accepted that the greatest road safety gains would be achieved through adopting a Safe System approach, derived from Sweden's Vision Zero and the Netherlands' Sustainable Safety strategies. A key objective of all three approaches is to manage vehicles, the road infrastructure, speeds, road users and the interactions between these components, to ensure that in the event of crashes, crash energies will remain at levels that minimize the probability of death and serious injury. Older drivers pose a particular challenge to the Safe System approach, given particularly their greater physical frailty, their driving patterns and for some at least, their reduced fitness to drive. This paper has analyzed the so-called ‘older driver problem’ and identified a number of key factors underpinning their crash levels, for which countermeasures can be identified and implemented within a Safe System framework. The recommended countermeasures consist of: (1 safer roads, through a series of design improvements particularly governing urban intersections; (2 safer vehicles, through both the promotion of crashworthiness as a critical consideration when purchasing a vehicle and the wide use of developed and developing ITS technologies; (3 safer speeds especially at intersections; and (4 safer road users, through both improved assessment procedures to identify the minority of older drivers with reduced fitness to drive and educational efforts to encourage safer driving habits particularly but not only through self-regulation.

Feeling safe during an inpatient hospitalization: a concept analysis.

Science.gov (United States)

Mollon, Deene

2014-08-01

This paper aims to explore the critical attributes of the concept feeling safe. The safe delivery of care is a high priority; however; it is not really known what it means to the patient to 'feel safe' during an inpatient hospitalization. This analysis explores the topic of safety from the patient's perspective. Concept analysis. The data bases of CINAHL, Medline, PsychInfo and Google Scholar for the years 1995-2012 were searched using the terms safe and feeling safe. The eight-step concept analysis method of Walker and Avant was used to analyse the concept of feeling safe. Uses and defining attributes, as well as identified antecedents, consequences and empirical referents, are presented. Case examples are provided to assist in the understanding of defining attributes. Feeling safe is defined as an emotional state where perceptions of care contribute to a sense of security and freedom from harm. Four attributes were identified: trust, cared for, presence and knowledge. Relationship, environment and suffering are the antecedents of feeling safe, while control, hope and relaxed or calm are the consequences. Empirical referents and early development of a theory of feeling safe are explored. This analysis begins the work of synthesizing qualitative research already completed around the concept of feeling safe by defining the key attributes of the concept. Support for the importance of developing patient-centred models of care and creating positive environments where patients receive high-quality care and feel safe is provided. © 2014 John Wiley & Sons Ltd.

Creating Safe Spaces for Music Learning

Science.gov (United States)

Hendricks, Karin S.; Smith, Tawnya D.; Stanuch, Jennifer

2014-01-01

This article offers a practical model for fostering emotionally safe learning environments that instill in music students a positive sense of self-belief, freedom, and purpose. The authors examine the implications for music educators of creating effective learning environments and present recommendations for creating a safe space for learning,…

Keeping Food Safe

Centers for Disease Control (CDC) Podcasts

2009-05-27

This CDC Kidtastics podcast discusses things kids and parents can do to help prevent illness by keeping food safe.  Created: 5/27/2009 by National Center for Zoonotic, Vector-Borne, and Enteric Diseases (NCZVED).   Date Released: 5/27/2009.

The convention on the physical protection of nuclear material

International Nuclear Information System (INIS)

1980-05-01

This document contains the full text of a convention to facilitate the safe transfer of nuclear material, and to insure the physical protection of nuclear material in domestic use, storage, and transport. Two annexes are included, which establish categories of nuclear materials and levels of physical protection to be applied in international transport

Regulations for the Safe Transport of Radioactive Materials. Vietnam Standard (TCVN 4985-89)

International Nuclear Information System (INIS)

1989-01-01

The regulations were prepared in line with the Safety Regulation for Ionizing Radiations 1988 of Vietnam. Its purpose is to provide requirements in transport of radioactive materials. The exposure levels of transport personnel are determined. The package for different types of materials is regulated. The orders and procedures in transport are defined. In addition, specific requirements for each mean of transport are given. (N.H.A)

Safe injection practice among health care workers, Gharbiya, Egypt.

Science.gov (United States)

Ismail, Nanees A; Aboul Ftouh, Aisha M; El Shoubary, Waleed H

2005-01-01

A cross-sectional study was conducted in 25 health care facilities in Gharbiya governorate to assess safe injection practices among health care workers (HCWs). Two questionnaires, one to collect information about administrative issues related to safe injection and the other to collect data about giving injections, exposure to needle stick injuries, hepatitis B vaccination status and safe injection training. Practices of injections were observed using a standardized checklist. The study revealed that there was lack of both national and local infection control policies and lack of most of the supplies needed for safe injection practices. Many safe practices were infrequent as proper needle manipulation before disposal (41%), safe needle disposal (47.5%), reuse of used syringe & needle (13.2%) and safe syringe disposal (0%). Exposure to needle stick injuries were common among the interviewed HCWs (66.2%) and hand washing was the common post exposure prophylaxis measure (63.4%). Only 11.3% of HCWs had full course hepatitis B vaccination. Infection control -including safe injections- training programs should be afforded to all HCWs.

SafeNet: a methodology for integrating general-purpose unsafe devices in safe-robot rehabilitation systems.

Science.gov (United States)

Vicentini, Federico; Pedrocchi, Nicola; Malosio, Matteo; Molinari Tosatti, Lorenzo

2014-09-01

Robot-assisted neurorehabilitation often involves networked systems of sensors ("sensory rooms") and powerful devices in physical interaction with weak users. Safety is unquestionably a primary concern. Some lightweight robot platforms and devices designed on purpose include safety properties using redundant sensors or intrinsic safety design (e.g. compliance and backdrivability, limited exchange of energy). Nonetheless, the entire "sensory room" shall be required to be fail-safe and safely monitored as a system at large. Yet, sensor capabilities and control algorithms used in functional therapies require, in general, frequent updates or re-configurations, making a safety-grade release of such devices hardly sustainable in cost-effectiveness and development time. As such, promising integrated platforms for human-in-the-loop therapies could not find clinical application and manufacturing support because of lacking in the maintenance of global fail-safe properties. Under the general context of cross-machinery safety standards, the paper presents a methodology called SafeNet for helping in extending the safety rate of Human Robot Interaction (HRI) systems using unsafe components, including sensors and controllers. SafeNet considers, in fact, the robotic system as a device at large and applies the principles of functional safety (as in ISO 13489-1) through a set of architectural procedures and implementation rules. The enabled capability of monitoring a network of unsafe devices through redundant computational nodes, allows the usage of any custom sensors and algorithms, usually planned and assembled at therapy planning-time rather than at platform design-time. A case study is presented with an actual implementation of the proposed methodology. A specific architectural solution is applied to an example of robot-assisted upper-limb rehabilitation with online motion tracking. Copyright © 2014 Elsevier Ireland Ltd. All rights reserved.

Qualitative Analysis of Infant Safe Sleep Public Campaign Messaging.

Science.gov (United States)

Peacock, Nadine R; Altfeld, Susan; Rosenthal, Allison L; Garland, Caitlin E; Massino, Jill M; Smith, Sherri L; Rowe, Hillary L; Wagener, Sarah E

2018-03-01

The 1994 Back to Sleep public education campaign resulted in dramatic reductions in sleep-related infant deaths, but comparable progress in recent years has been elusive. We conducted qualitative analyses of recent safe sleep campaigns from 13 U.S. cities. Goals were to (a) determine whether the campaigns reflect the full range of American Academy of Pediatrics (AAP) 2011 safe sleep recommendations, (b) describe tone and framing of the messages (e.g., use of fear appeals), (c) describe targeting/tailoring of messages to priority populations, and (d) ascertain whether the campaigns have been evaluated for reach and/or effectiveness. Methods included computer-assisted analyses of campaign materials and key informant interviews. All campaigns included "ABC" (Alone, Back, Crib) messaging; many ignored other AAP recommendations such as breastfeeding, room-sharing, immunizations, and avoiding smoke exposure. Campaigns frequently targeted priority populations such as African Americans. Fear appeals were used in three quarters of the campaigns, and 60% of the fear-based campaigns used guilt/blame messaging. We did not find published evaluation data for any of the campaigns. More attention is needed in public education campaigns to the full range of AAP recommendations, and evaluations are needed to determine the impact of these interventions on knowledge, behavior, and health outcomes.

Implicit attitudes towards risky and safe driving

DEFF Research Database (Denmark)

Martinussen, Laila Marianne; Sømhovd, Mikael Julius; Møller, Mette

; further, self-reports of the intention to drive safely (or not) are socially sensitive. Therefore, we examined automatic preferences towards safe and risky driving with a Go/No-go Association Task (GNAT). The results suggest that (1) implicit attitudes towards driving behavior can be measured reliably...... with the GNAT; (2) implicit attitudes towards safe driving versus towards risky driving may be separable constructs. We propose that research on driving behavior may benefit from routinely including measures of implicit cognition. A practical advantage is a lesser susceptibility to social desirability biases......, compared to self-report methods. Pending replication in future research, the apparent dissociation between implicit attitudes towards safe versus risky driving that we observed may contribute to a greater theoretical understanding of the causes of unsafe and risky driving behavior....

Evaluation of the biocompatibility of a coating material for an implantable bladder volume sensor

Directory of Open Access Journals (Sweden)

Su-Jin Kim

2012-03-01

Full Text Available As the applications for implantable medical devices have increased, the need for biocompatible packaging materials has become important. Recently, we reported an implantable sensor for real-time monitoring of the changes in bladder volume, which necessitated finding a safe coating material for use in bladder tissue. At present, materials like polyethylene glycol (PEG, polydimethylsiloxane (PDMS and parylene-C are used in biomedical devices or as coating materials, owing to their excellent safety in various medical fields. However, few studies have assessed their safety in bladder tissue, therefore, we evaluated the biocompatibility of PEG, PDMS and parylene-C in the bladder. All three materials turned out to be safe in in vitro tests of live/dead staining and cell viability. In vivo tests with hematoxylin and eosin and immunofluorescence staining with MAC387 showed no persistent inflammation. Therefore, we consider that the three materials are biocompatible in bladder tissue. Despite this safety, however, PEG has biodegradable characteristics and thus is not suitable for use as packaging. We suggest that PDMS and parylene-C can be used as safe coating materials for the implantable bladder volume sensor reported previously.

Comparing the level of dexterity offered by latex and nitrile SafeSkin gloves.

Science.gov (United States)

Sawyer, Jo; Bennett, Allan

2006-04-01

An increase in the occurrence of latex allergy has been concurrent with the increasing use of latex gloves by laboratory and healthcare workers. In recent years nitrile gloves have been used to replace latex gloves to prevent latex allergy. Nitrile gloves offer a comparable level of protection against chemical and biological agents and are more puncture resistant. However, if manual dexterity is compromised by nitrile gloves to a greater degree than latex then this may increase the risk of sharps injuries. The Purdue pegboard test, which measures both gross and fine finger dexterity, was used to test the dexterity levels of two glove types used at HPA CEPR; Kimberly-Clark SafeSkin nitrile and latex laboratory gloves. There was a statistically significant 8.6% increase in fine finger dexterity provided by latex compared with nitrile SafeSkin laboratory gloves but no difference in gross dexterity between the glove types. There was no significant relationship between glove dexterity and age or gender. The selection of glove size was influenced by the digit length of participants. Moreover, those with longer, thinner fingers appeared to have an advantage when using nitrile SafeSkin gloves. The level of dexterity provided by latex and nitrile SafeSkin gloves for tasks on a gross dexterity level are comparable and health workers will benefit from the non-allergenic properties of nitrile. For tasks requiring fine finger dexterity nitrile SafeSkin gloves may impede dexterity. Despite this, the degree of restriction appears to have a negligible impact on safety in this study when compared with the risk of latex sensitization and subsequent allergy. In addition to glove material, working practices must also take into account glove size, fit, grip and thickness, as these factors can all influence dexterity.

Raising students and educators awareness of radioactive materials transport through creative classroom materials and exhibits

International Nuclear Information System (INIS)

Holm, J.; Sandoz, C.; Dickenson, J.; Lee, J.C.; Smith, A.M.

1994-01-01

The public is concerned about how the shipping and handling of radioactive materials affects them and their environment. Through exhibit showings doing professional education conferences and smaller, focussed workshops, the United States Department of Energy (DOE) has found teachers and students to be an especially interested audience for hazardous and radioactive materials transportation information. DOE recognizes the importance of presenting educational opportunities to students about scientific and societal issues associated with planning for and safely transporting these types of materials. Raising students' and educators' awareness of hazardous and radioactive materials transport through creative classroom materials and exhibits may help them make informed decisions as adults about this often controversial and difficult issue

Prospects for inherently safe reactors

International Nuclear Information System (INIS)

Barkenbus, J.N.

1988-01-01

Public fears over nuclear safety have led some within the nuclear community to investigate the possibility of producing inherently safe nuclear reactors; that is, reactors that are transparently incapable of producing a core melt. While several promising designs of such reactors have been produced, support for large-scale research and development efforts has not been forthcoming. The prospects for commercialization of inherently safe reactors, therefore, are problematic; possible events such as further nuclear reactor accidents and superpower summits, could alter the present situation significantly. (author)

Materials Handling. Module SH-01. Safety and Health.

Science.gov (United States)

Center for Occupational Research and Development, Inc., Waco, TX.

This student module on materials handling is one of 50 modules concerned with job safety and health. It presents the procedures for safe materials handling. Discussed are manual handling methods (lifting and carrying by hand) and mechanical lifting (lifting by powered trucks, cranes or conveyors). Following the introduction, 15 objectives (each…

Sea transport of radioactive materials in Egypt (invited paper)

International Nuclear Information System (INIS)

El-Shinawy, R.M.K.; Gomaa, M.A.

1998-01-01

In Egypt the national regulations for safe transport of radioactive materials (RAM) are based on the International Atomic Energy Agency (IAEA) regulations. In addition, regulations for the safe transport of these materials through the Suez Canal (SC) were laid down by the Egyptian Atomic Energy Authority (EAEA) and the Suez Canal Authority (SCA). They are continuously updated to meet the increased knowledge and the experience gained. The technical and protective measures taken during transport of RAM through SC are mentioned. Assessment of the impact of transporting radioactive materials through the Suez Canal using the INTERTRAN computer code was carried out in cooperation with IAEA. The transported activities and empty containers, the number of vessels carrying RAM through the Canal from 1963 to 1996 and their nationalities are also discussed. The protective measures are mentioned. (author)

50 CFR 216.91 - Dolphin-safe labeling standards.

Science.gov (United States)

2010-10-01

... 50 Wildlife and Fisheries 7 2010-10-01 2010-10-01 false Dolphin-safe labeling standards. 216.91... MAMMALS Dolphin Safe Tuna Labeling § 216.91 Dolphin-safe labeling standards. (a) It is a violation of... include on the label of those products the term “dolphin-safe” or any other term or symbol that claims or...

Experimental study of metal gasketed joints for ultra-high vacuums; Etude experimentale de joints metalliques pour ultra-vide

Energy Technology Data Exchange (ETDEWEB)

Boulloud, J. P.; Schweitzer, J. [Commissariat a l' energie atomique et aux energies alternatives - CEA, Service de Physique Appliquee, groupe de Vide, Centre d' Etudes Nucleaires de Saclay (France)

1960-07-01

Various type of leak-tight metal joints have been studied with their application in assemblies containing total vacuums in mind. Their integrity has been tested with a helium leak detector, and leaks of about 2 x 10{sup -12} cm{sup 3} Atm/s per meter of joint have been measured, simultaneously with the clamping effort applied at the joint and the deformation of the metal gasket. The integrity to clamping effort ratio curve is not retraced in reverse upon relaxation of the clamping effort, but a 'return curve' analogous to a hysteresis cycle explains why certain types of joint retain their integrity at high temperatures. The use of a tracer gas permits discrimination between external permeation of the joint and gas from occlusions between its mating surfaces. The authors have been led to consider that neither the nature nor the purity or surface condition of the joint have any basic influence on its integrity. Clamping effort values in respect of various joints and necessary for total integrity are indicated. Reprint of a paper published in Le vide, no. 82, Jul-Aug 1959 [French] L'etude de differents types de joints metalliques etanches, en vue de leur application a l'ultra-vide, a ete effectuee a l'aide d'un detecteur de fuite a helium. On a mesure simultanement le debit de fuite, l'effort applique sur le joint et sa deformation. On a reussi a mesurer des debits de fuite de l'ordre de 2 x 10{sup -12} cm{sup 3} Atm/s/m de joint pour l'air. La courbe de l'etancheite en fonction de l'effort applique n'est pas reversible et on a pu mettre en evidence un 'cycle d'hysteresis' qui explique que certains joints conservent leur etancheite a haute temperature. La methode de mesure d'etancheite au moyen d'un gaz traceur a amene a faire une distinction entre la permeation et le degazage des gaz occlus dans l'interface des joints et a considerer que ni la nature, ni la purete et ni l'etat de surface du joint n'ont une influence primordiale sur l'etancheite de joint. Des valeurs

Medications: Using Them Safely

Science.gov (United States)

... to Safely Give Ibuprofen Childproofing and Preventing Household Accidents Medicines for Diabetes Complementary and Alternative Medicine How Do Pain Relievers Work? What Medicines Are and What They Do Medicines ...

Regulations for the safe transport of radioactive material, 2005 edition. Safety requirements

International Nuclear Information System (INIS)

2005-01-01

This publication includes amendments to the 1996 Edition (As Amended 2003) arising from the second cycle of the biennial review and revision process, as agreed by the Transport Safety Standards Committee (TRANSSC) at its ninth meeting in March 2004, as endorsed by the Commission on Safety Standards at its meeting in June 2004 and as approved by the IAEA Board of Governors in November 2004. Although this publication is identified as a new edition, there are no changes that affect the administrative and approval requirements in Section VIII. The fields covered are General Provisions (radiation protection; emergency response; quality assurance; compliance assurance; non-compliance; special arrangement and training); Activity Limits and Materials Restrictions, Requirement and Controls for Transport , Requirements for Radioactive Materials and for Packagings and Packages, Test Procedures, Approval and Administrative Requirements

Clinical Practice Guideline: Safe Medication Use in the ICU.

Science.gov (United States)

Kane-Gill, Sandra L; Dasta, Joseph F; Buckley, Mitchell S; Devabhakthuni, Sandeep; Liu, Michael; Cohen, Henry; George, Elisabeth L; Pohlman, Anne S; Agarwal, Swati; Henneman, Elizabeth A; Bejian, Sharon M; Berenholtz, Sean M; Pepin, Jodie L; Scanlon, Mathew C; Smith, Brian S

2017-09-01

To provide ICU clinicians with evidence-based guidance on safe medication use practices for the critically ill. PubMed, Cochrane Database of Systematic Reviews, Cochrane Central Register of Controlled Trials, CINAHL, Scopus, and ISI Web of Science for relevant material to December 2015. Based on three key components: 1) environment and patients, 2) the medication use process, and 3) the patient safety surveillance system. The committee collectively developed Population, Intervention, Comparator, Outcome questions and quality of evidence statements pertaining to medication errors and adverse drug events addressing the key components. A total of 34 Population, Intervention, Comparator, Outcome questions, five quality of evidence statements, and one commentary on disclosure was developed. Subcommittee members were assigned selected Population, Intervention, Comparator, Outcome questions or quality of evidence statements. Subcommittee members completed their Grading of Recommendations Assessment, Development, and Evaluation of the question with his/her quality of evidence assessment and proposed strength of recommendation, then the draft was reviewed by the relevant subcommittee. The subcommittee collectively reviewed the evidence profiles for each question they developed. After the draft was discussed and approved by the entire committee, then the document was circulated among all members for voting on the quality of evidence and strength of recommendation. The committee followed the principles of the Grading of Recommendations Assessment, Development, and Evaluation system to determine quality of evidence and strength of recommendations. This guideline evaluates the ICU environment as a risk for medication-related events and the environmental changes that are possible to improve safe medication use. Prevention strategies for medication-related events are reviewed by medication use process node (prescribing, distribution, administration, monitoring). Detailed

Biodegradable starch-based polymeric materials

Science.gov (United States)

Suvorova, Anna I.; Tyukova, Irina S.; Trufanova, Elena I.

2000-05-01

The effects of low-molecular-weight additives, temperature and mechanical action on the structure and properties of starch are discussed. Special attention is given to mixtures of starch with synthetic polymers, e.g., co-polymers of ethylene with vinyl acetate, vinyl alcohol, acrylic acid, cellulose derivatives and other natural polymers. These mixtures can be used in the development of novel environmentally safe materials (films, coatings, packaging materials) and various articles for short-term use. The bibliography includes 105 references.

Safe havens in Europe: Switzerland and the ten dwarfs

Directory of Open Access Journals (Sweden)

Martin Paldam

2013-12-01

Full Text Available Eleven safe havens exist in Europe providing offshore banking and low taxes. Ten of these states are very small while Switzerland is moderately small. All 11countries are richer than their large neighbors. It is shown that causality is from small to safe haven towealth, and that theoretically equilibriums are likely to exist where a certain regulation is substantially lower in a small country than in its big neighbor. This generates a large capital inflow to the safe havens. The pool of funds that may reach the safe havens is shown to be huge. It is far in excess of the absorptive capacity of the safe havens, but it still explains, why they are rich. Microstates offer a veil of anonymity to funds passing through, and Switzerland offers safe storage of funds.

Advanced microsystems for automotive applications 2013 smart systems for safe and green vehicles

CERN Document Server

Meyer, Gereon

2013-01-01

The road vehicle of the future will embrace innovations from three major automotive technology fields: driver assistance systems, vehicle networking and alternative propulsion. Smart systems such as adaptive ICT components and MEMS devices, novel network architectures, integrated sensor systems, intelligent interfaces and functional materials form the basis of these features and permit their successful and synergetic integration. They increasingly appear to be the key enabling technologies for safe and green road mobility. For more than fifteen years the International Forum on Advanced Microsystems for Automotive Applications (AMAA) has been successful in detecting novel trends and in discussing the technological implications from early on. The topic of the AMAA 2013 will be “Smart Systems for Safe and Green Vehicles”. This book contains peer-reviewed papers written by leading engineers and researchers which all address the ongoing research and novel developments in the field. www.amaa.de.

Safe and Liquid Mortgage Bonds

DEFF Research Database (Denmark)

Dick-Nielsen, Jens; Gyntelberg, Jacob; Lund, Jesper

This paper shows that strict match pass-through funding of covered bonds provides safe and liquid mortgage bonds. Despite a 30% drop in house prices during the 2008 global crisis Danish mortgage bonds remained as liquid as most European government bonds. The Danish pass-through system effectively...... eliminates credit risk from the investor's perspective. Similar to other safe bonds, funding liquidity becomes the main driver of mortgage bond liquidity and this creates commonality in liquidity across markets and countries. These findings have implications for how to design a robust mortgage bond system...

Radiological engineering services for the design of special contamination containments. Final report

International Nuclear Information System (INIS)

1996-01-01

The purpose of this study was to provide radiological engineering services for the design of special contamination containments. These containments were to be used during the replacement of leaking and damaged gaskets on the glove boxes in Technical Area-55 (TA-55). The damaged gaskets involved 18 windows and 5 interconnecting spool pieces in fuel processing glove boxes. The work scope included the design and manufacture of special contamination containment enclosures (containments), the preparation of procedures and tool lists to support gasket replacement while using the containments, and the training of appropriate TA-55 personnel in the proper installation, operation and removal of the containments. It was originally anticipated that two basic containment designs would be required, one for the windows and one for spool pieces. Upon examination of the glove boxes it was evident that the individual space envelopes and interferences associated with each glove box would require uniquely designed containments for effective gasket replacement. This resulted in 13 individual containment designs that accommodated the interferences and allowed gasket replacement within the containment. Successful use of the containments for glove box gasket replacement was a significant accomplishment. The operation has proven that a properly managed containment program can enhance routine maintenance of the glove boxes while preventing a contamination release. The ability to perform these operations in containments reduces costs by preventing a contaminant release and eliminating the associated cleanup expenses, reduced radioactive waste and fuel processing down time

Directory of national competent authorities' approval certificates for package design, special form material and shipment of radioactive material. 1994 ed

International Nuclear Information System (INIS)

1994-08-01

This is the fifth annual report being published by the Secretariat of the International Atomic Energy Agency since implementing its database on package approval certificates (PACKTRAM) at the recommendation of the Standing Advisory Group on the Safe Transport of Radioactive Material (SAGSTRAM). The reporting format was established at consecutive meetings of SAGSTRAM, whose membership consists of national competent authorities responsible for the transport of radioactive material from those Member States who have a nuclear industry and others who have shown a keen interest in the IAEA's transport safety programme. Through the PACKTRAM database, the Secretariat collects administrative and technical information on package approval certificates to assist national competent authorities in regulating radioactive material movements in their country. The database carries information on extant certificates and those that expired within the last two complete calendar years. The 1985 Edition of IAEA Safety Series No. 6, the ''Regulations for the Safe Transport of Radioactive Material'' highlights the role of competent authorities in assuring regulatory compliance in their own countries. Package approval certificates are an important aspect of that function. This document aims to be a useful reference for competent authorities as well as for manufacturers and shippers of radioactive material

Directory of national competent authorities' approval certificates for package design, special form material and shipment of radioactive material. 1995 edition

International Nuclear Information System (INIS)

1995-09-01

This is the sixth annual report being published by the Secretariat of the International Atomic Energy Agency since implementing its database on package approval certificates (PACKTRAM) at the recommendation of the Standing Advisory Group on the Safe Transport of Radioactive Material (SAGSTRAM). The reporting format was established at consecutive meetings of SAGSTRAM, whose membership consists of national competent authorities responsible for the transport of radioactive material from those Member States who have a nuclear industry and others who have shown a keen interest in the IAEA's transport safety programme. Through the PACKTRAM database, the Secretariat collects administrative and technical information on package approval certificates to assist national competent authorities in regulating radioactive material movements in their country. The database carries information on extant certificates and those that expired within the last complete calendar year. The 1985 Edition of IAEA Safety Series No. 6, the ''Regulations for the Safe Transport of Radioactive Material'' highlights the role of competent authorities in assuring regulatory compliance in their own countries. Package approval certificates are an important aspect of that function. This document aims to be a useful reference for competent authorities as well as for manufacturers and shippers of radioactive material. 6 tabs

Material and construction of primary components

International Nuclear Information System (INIS)

Kaser, A.; Wallner, F.

1978-01-01

The construction of SNR's requires specific properties of the materials, i.e. high strength at temperatures of 600 0 C, adequate creep rupture strength, low long-time embrittlement. Aspects are given for optimalization of the mentioned properties with regard to safe manufacture especially good weldability. The austenitic material X6CrNil811 similar the type AISI 304 SS finally was chosen. Besides the fundamental analysis of the material properties it will be reported about the experiences gained during the manufacturing of the essential components. (author)

Storage of radioactive material - accidents - precipitation - personnel monitoring

International Nuclear Information System (INIS)

Matijasic, A.; Gacinovic, O.

1961-12-01

This volume covers the reports on four routine tasks concerned with safe handling of radioactive material and influence of nuclear facilities on the environment. The tasks performed were as follows: Storage of solid and liquid radioactive material; actions in case of accidents; radiation monitoring of the fallout, water and ground; personnel dosimetry

Implementation of an Improved Safe Operating Envelope

International Nuclear Information System (INIS)

Prime, Robyn; McIntyre, Mark; Reeves, David

2008-01-01

This paper is a continuation of the paper presented at IYNC 2004 on 'The Definition of a Safe Operating Envelope'. The current paper concentrates on the implementation process of the Safe Operating Envelope employed at the Point Lepreau Generating Station. (authors)

State summary of radioactive material transport sector in Brazil

International Nuclear Information System (INIS)

Heilbron Filho, P.F.L.; Xavier, A.M.

1991-07-01

The main aim of this work is the scientific cooperation with the CNEA (Argentina) in the area of safe transport of radioactive materials, intending to find solutions to some rural problems and, also, to standardize the transport of radioactive materials between Brazil and Argentina. (E.O.)

Selection of exception limits for all actinide nuclides based on revised criteria for safe international transport and including storage delay

International Nuclear Information System (INIS)

Lavarenne, C.; Rouyer, V.; Mennerdahl, D.; Dean, C.; Barton, N.; Jean, F.

2004-01-01

Since 1998, there have been some speculations about future transport of significant quantities and concentrations of other actinide nuclides than the four currently listed in the regulation for the safe transport of the radioactive material. Therefore, it raised a need to specify exception limits for such actinides. In order to define credible exception limits, it was necessary to have reasonably accurate data for all actinide nuclides. Then the DGTREN/participants decided to perform calculations with different codes (MONK, MCNP, CRISTAL and SCALE) and different cross-section libraries (JEF2.2, ENDFB, etc.). The parameters of interest (such as k-infinite, critical masses) were determined. This article presents the work achieved and the questions raised, e.g. related to the effect of the radioactive decay of the isotopes on the criticality risks. It also points out the need for an evolution of the regulation of the safe transport of radioactive materials and gives a proposition of modification for the IAEA requirements related to, firstly, the list of the fissile materials, secondly, the rule to determine the quantities of actinide nuclides that can be excepted from the requirements for the packages containing fissile materials

Recommended nuclear criticality safety experiments in support of the safe transportation of fissile material

International Nuclear Information System (INIS)

Tollefson, D.A.; Elliott, E.P.; Dyer, H.R.; Thompson, S.A.

1993-01-01

Validation of computer codes and nuclear data (cross-section) libraries using benchmark quality critical (or certain subcritical) experiments is an essential part of a nuclear criticality safety evaluation. The validation results establish the credibility of the calculational tools for use in evaluating a particular application. Validation of the calculational tools is addressed in several American National Standards Institute/American Nuclear Society (ANSI/ANS) standards, with ANSI/ANS-8.1 being the most relevant. Documentation of the validation is a required part of all safety analyses involving significant quantities of fissile materials. In the case of transportation of fissile materials, the safety analysis report for packaging (SARP) must contain a thorough discussion of benchmark experiments, detailing how the experiments relate to the significant packaging and contents materials (fissile, moderating, neutron absorbing) within the package. The experiments recommended in this paper are needed to address certain areas related to transportation of unirradiated fissile materials in drum-type containers (packagings) for which current data are inadequate or are lacking

Implementation of an Improved Safe Operating Envelope

Energy Technology Data Exchange (ETDEWEB)

Prime, Robyn; McIntyre, Mark [NB Power Nuclear, P.O. Box 600, Lepreau, NB (Canada); Reeves, David [Atlantic Nuclear Services Ltd., PO Box 1268 Fredericton, NB (Canada)

2008-07-01

This paper is a continuation of the paper presented at IYNC 2004 on 'The Definition of a Safe Operating Envelope'. The current paper concentrates on the implementation process of the Safe Operating Envelope employed at the Point Lepreau Generating Station. (authors)

Interim guidance on the safe transport of uranium hexafluoride

International Nuclear Information System (INIS)

1991-06-01

Uranium hexafluoride (UF 6 ) is a radioactive material that has significant non-radiological hazardous properties. In conformity with international regulatory practice for dangerous goods transport, these properties are classed as ''subsidiary risks'', although they predominate in the cases of depleted and natural UF 6 . UF 6 is transported as a solid material below atmospheric pressure. The IAEA Regulations for the Safe Transport of Radioactive Material, 1985 Edition, Safety Series No. 6, make recommendations that aimed to provide an adequate level of safety against radiological and criticality hazards. The basis for these is that the stringency of package performance requirements, operational procedures and approval and administrative procedures is graded relative to the severity of the hazard. The cylinders used for transporting UF 6 are also used in the production, storage and use of the material and that the fraction of their life cycle in which transport is involved is small. Consideration must also be given to the large number of existing cylinders (estimated to be between 60,000 and 70,000). Specific recommendations provided for UF 6 transport, listed in Section II, are additional to the requirements of the Regulations. The intent of these additional recommendations is to restrict contamination and to provide protection to workers and to the general public against the chemical hazard possibly resulting from a severe accident involving the transport of UF 6 , and in addition against the consequences of explosive rupture of small bare cylinders of UF 6 . 20 refs, figs and tabs

From Safe Systems to Patient Safety

DEFF Research Database (Denmark)

Aarts, J.; Nøhr, C.

2010-01-01

for the third conference with the theme: The ability to design, implement and evaluate safe, useable and effective systems within complex health care organizations. The theme for this conference was "Designing and Implementing Health IT: from safe systems to patient safety". The contributions have reflected...... and implementation of safe systems and thus contribute to the agenda of patient safety? The contributions demonstrate how the health informatics community has contributed to the performance of significant research and to translating research findings to develop health care delivery and improve patient safety......This volume presents the papers from the fourth International Conference on Information Technology in Health Care: Socio-technical Approaches held in Aalborg, Denmark in June 2010. In 2001 the first conference was held in Rotterdam, The Netherlands with the theme: Sociotechnical' approaches...

The first safe country

Directory of Open Access Journals (Sweden)

Raffaela Puggioni

2012-06-01

Full Text Available The Dublin II Regulation makes the first safe country of refuge solelyresponsible for refugees and asylum seekers. In the case of Italy, thefirst responsible country has not been acting responsibly.

Karate: Keep It Safe.

Science.gov (United States)

Jordan, David

1981-01-01

Safety guidelines for each phase of a karate practice session are presented to provide an accident-free and safe environment for teaching karate in a physical education or traditional karate training program. (JMF)

Prepare to protect: Operating and maintaining a tornado safe room.

Science.gov (United States)

Herseth, Andrew; Goldsmith-Grinspoon, Jennifer; Scott, Pataya

2017-06-01

Operating and maintaining a tornado safe room can be critical to the effective continuity of business operations because a firm's most valuable asset is its people. This paper describes aspects of operations and maintenance (O&M) for existing tornado safe rooms as well as a few planning and design aspects that affect the ultimate operation of a safe room for situations where a safe room is planned, but not yet constructed. The information is based on several Federal Emergency Management Agency safe room publications that provide guidance on emergency management and operations, as well as the design and construction of tornado safe rooms.

Safe actinide disposition in molten salt reactors

International Nuclear Information System (INIS)

Gat, U.

1997-01-01

Safe molten salt reactors (MSR) can readily accommodate the burning of all fissile actinides. Only minor compromises associated with plutonium are required. The MSRs can dispose safely of actinides and long lived isotopes to result in safer and simpler waste. Disposing of actinides in MSRs does increase the source term of a safety optimized MSR. It is concluded that the burning and transmutation of actinides in MSRs can be done in a safe manner. Development is needed for the processing to handle and separate the actinides. Calculations are needed to establish the neutron economy and the fuel management. 9 refs

Safe Sleep for Babies

Science.gov (United States)

... 5 MB] Read the MMWR Science Clips Safe Sleep for Babies Eliminating hazards Recommend on Facebook Tweet ... Page Problem Every year, there are thousands of sleep-related deaths among babies. View large image and ...

Criticality Control Fissile of Materials. Proceedings of the Symposium on Criticality Control of Fissile Materials

Energy Technology Data Exchange (ETDEWEB)

NONE

1966-05-15

Criticality control comprises all the administrative and technical procedures which enable the storage and processing of fissile material to be carried out under conditions of nuclear safety. It is of particular importance in the safe design and operation of chemical and metallurgical plants processing fissile material, in the handling and storage of enriched fuel for reactors, and in transportation of fissile material. The growth of nuclear power, with its increasing use of fissile material and production of plutonium, is leading to an ever widening need for this discipline. This Symposium was held 4 Vulgar-Fraction-One-Half years after the only other international meeting on this topic, at which the first broad exchange of ideas and theories enabled a comparison to be drawn between the various ways in which the subject is handled in the different countries. That meeting showed that criticality safety was often achieved by procedures known to be ultra-safe, as there was a great lack of useful experimental data with which to check theoretical models. Since that time the quantities of material being processed have increased, and with the now urgent necessity of achieving economic, and hence commercially competitive, operation, the procedure of using arbitrary factors of safety is no longer adequate. Plant Managers now require good data on the basis of which they can choose a suitable factor of safety, and design a process to be safe under any foreseeable circumstances. The present Symposium showed the great increase in the amount of available experimental data and its importance in checking the now highly sophisticated computer calculations. There are many diagrams in these Proceedings with curves from which critical parameters for various configurations can be taken. The dearth of data for plutonium systems is causing some difficulty in plutonium processing plants, which are becoming commercially important. The excellent safety record of the atomic energy industry

[Safeguards for the physical protection of nuclear materials and facilities

International Nuclear Information System (INIS)

Jones, O.E.

1975-01-01

Testimony is given on the subject of safeguards for the physical protection of nuclear materials and facilities, particularly during transportation. The ERDA nation-wide safe-secure transportation system and the Safe-Secure Trailer are described. The nationwide ERDA voice communication system is also described. Development of hardware and systems is discussed. The use of adversary simulation for evaluating protection systems is mentioned

Removal of root filling materials.

LENUS (Irish Health Repository)

Duncan, H.F. Chong, B.S.

2011-05-01

Safe, successful and effective removal of root filling materials is an integral component of non-surgical root canal re-treatment. Access to the root canal system must be achieved in order to negotiate to the canal terminus so that deficiencies in the original treatment can be rectified. Since a range of materials have been advocated for filling root canals, different techniques are required for their removal. The management of commonly encountered root filling materials during non-surgical re-treatment, including the clinical procedures necessary for removal and the associated risks, are reviewed. As gutta-percha is the most widely used and accepted root filling material, there is a greater emphasis on its removal in this review.

Escola segura Safe school

Directory of Open Access Journals (Sweden)

Edson Ferreira Liberal

2005-11-01

Full Text Available OBJETIVO: Revisão das estratégias para tornar o ambiente escolar seguro. Inicialmente os autores contextualizam a violência e os acidentes no ambiente escolar e fazem recomendações, baseadas em dados da literatura, para a implantação de escolas seguras. FONTE DE DADOS: Artigos publicados entre 1993 e 2005 na base de dados MEDLINE. Dados nacionais epidemiológicos e da literatura também foram pesquisados. SÍNTESE DOS DADOS: Há evidência crescente de que a intervenção tem múltiplos componentes. O foco político é a prática em educação em saúde com o envolvimento de toda a comunidade. O norte dessas intervenções é ajudar estudantes e toda a comunidade a adotar um comportamento seguro e saudável. As escolas estão assumindo um envolvimento crescente na promoção da saúde, prevenção de doenças e prevenção de trauma. Nesse contexto de prevenção de causas externas de morbimortalidade, é importante reconhecer o risco ambiental, locais e comportamentos de risco como favoráveis ao trauma e à violência, além de um novo conceito de acidentes como algo que possa ser evitado. CONCLUSÃO: A implementação da escola segura representa uma nova direção promissora para o trabalho preventivo baseado na escola. É importante notar que uma escola segura deve intervir não meramente na sua estrutura física, mas também torná-la tão segura quanto possível, trabalhando com a comunidade escolar por meio de educação em saúde, discutindo principalmente o comportamento saudável.OBJECTIVE: To review the strategies to make school a safe environment. The paper first addresses the social context of accidents and violence in the school environment, and makes recommendations, based on the literature data, for the implementation of safe schools. SOURCE OF DATA: Articles published between 1993 and 2005 in the MEDLINE database. Brazilian epidemiological and literature data have also been searched. SUMMARY OF THE FINDINGS: There is

Operational and materials aspects of aging management

International Nuclear Information System (INIS)

Muscara, J.; Vora, J.P.; Moyer, C.E.

2005-01-01

Understanding degradation phenomena and managing the detrimental effects of aging are important aspects of commercial nuclear power plant operations. Potential for materials degradation should be considered early in the design and development stages; during manufacturing, construction, and installation; and during all aspects of plant operation and maintenance. This would lead to increased reliability during plant operations, and would reduce the need for mitigating actions and unplanned maintenance. Thus, it is necessary to instill a culture at the technical, administrative, and management levels that continually asks, 'What happens with time?' The answer to this question is central to the continuous safe and economical operation of nuclear power plants. Based on the past 25 years of aging-related research at the U.S. Nuclear Regulatory Commission (NRC), the authors present an overview of the key elements of understanding and managing aging, and how they should be integrated for safe and economical power plant operation. The focus of this paper is hardware-oriented engineering and aging of materials. The paper discusses previous and ongoing NRC research studies on non-destructive examination and materials degradation that can be applied for proactive management of materials degradation and aging during plant operations. (author)

Controlled maritime storage of noxious materials

International Nuclear Information System (INIS)

1984-01-01

The invention relates to an accommodation for the controlled storage of noxious material, especially of radioactive material packed in vessels. The invention provides a storage accommodation far from populated regions, in which this material may be stored during a long period in a safe and controlled way and from which it may be winned back in a simple and cheap way. For that purpose, a floating and submersible construction is designed that may be let down to the sea-bottom at least partially and that is fitted with a closable entrance. (Auth.)

SRS K-area material storage. Expanding capabilities

International Nuclear Information System (INIS)

Koenig, R.

2013-01-01

In support of the Department of Energy’s continued plans to de-inventory and reduce the footprint of Cold War era weapons’ material production sites, the K-Area Material Storage (KAMS) facility, located in the K-Area Complex (KAC) at the Savannah River Site reservation, has expanded since its startup authorization in 2000 to accommodate DOE’s material consolidation mission. During the facility’s growth and expansion, KAMS will have expanded its authorization capability of material types and storage containers to allow up to 8200 total shipping containers once the current expansion effort completes in 2014. Recognizing the need to safely and cost effectively manage other surplus material across the DOE Complex, KAC is constantly evaluating the storage of different material types within K area. When modifying storage areas in KAC, the Documented Safety Analysis (DSA) must undergo extensive calculations and reviews; however, without an extensive and proven security posture the possibility for expansion would not be possible. The KAC maintains the strictest adherence to safety and security requirements for all the SNM it handles. Disciplined Conduct of Operations and Conduct of Projects are demonstrated throughout this historical overview highlighting various improvements in capability, capacity, demonstrated cost effectiveness and utilization of the KAC as the DOE Center of Excellence for safe and secure storage of surplus SNM.

Buying & Using Medicine Safely

Science.gov (United States)

... Reducers Safe Daily Use of Aspirin Medication Health Fraud Resources for You FDA Consumer Updates (Drugs) Page ... feeds Follow FDA on Twitter Follow FDA on Facebook View FDA videos on YouTube View FDA photos ...

Virus Alert: Ten Steps to Safe Computing.

Science.gov (United States)

Gunter, Glenda A.

1997-01-01

Discusses computer viruses and explains how to detect them; discusses virus protection and the need to update antivirus software; and offers 10 safe computing tips, including scanning floppy disks and commercial software, how to safely download files from the Internet, avoiding pirated software copies, and backing up files. (LRW)

Safe driving for teens

Science.gov (United States)

Driving and teenagers; Teens and safe driving; Automobile safety - teenage drivers ... months before taking friends as passengers. Teenage-related driving deaths occur more often in certain conditions. OTHER SAFETY TIPS FOR TEENS Reckless driving is still a ...

Program in change: shipment of hazardous materials at the INEL

International Nuclear Information System (INIS)

Reed, L.L.

1984-01-01

Positive measures such as education, control, and auditing ability should be incorporated into each hazardous material shipping program to assure compliance with regulations and the safe movement of hazardous materials. This paper discusses these and other pertinent components of a shipping program. 3 references

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

International Nuclear Information System (INIS)

Watson, Dan; Eyman, Jeff

2003-01-01

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

SAFE: A computer code for the steady-state and transient thermal analysis of LMR fuel elements

International Nuclear Information System (INIS)

Hayes, S.L.

1993-12-01

SAFE is a computer code developed for both the steady-state and transient thermal analysis of single LMR fuel elements. The code employs a two-dimensional control-volume based finite difference methodology with fully implicit time marching to calculate the temperatures throughout a fuel element and its associated coolant channel for both the steady-state and transient events. The code makes no structural calculations or predictions whatsoever. It does, however, accept as input structural parameters within the fuel such as the distributions of porosity and fuel composition, as well as heat generation, to allow a thermal analysis to be performed on a user-specified fuel structure. The code was developed with ease of use in mind. An interactive input file generator and material property correlations internal to the code are available to expedite analyses using SAFE. This report serves as a complete design description of the code as well as a user's manual. A sample calculation made with SAFE is included to highlight some of the code's features. Complete input and output files for the sample problem are provided

Safe operation of critical assemblies and research reactors

Energy Technology Data Exchange (ETDEWEB)

NONE

1960-09-15

Some countries have accumulated considerable experience in the operation of these reactors and have in the process developed safe practices. On the other hand, other countries which have recently acquired, or will soon acquire, such reactors do not have sufficient background of experience with them to have developed full knowledge regarding their safe operation. In this situation, the International Atomic Energy Agency has considered that it would be useful to make available to all its Member States a set of recommendations on the safe operation of these reactors, based on the accumulated experience and best practices. The Director General accordingly nominated a Pane Ion Safe Operation of Critical Assemblies and Research Reactors to assist the Agency's Secretariat in drafting such recommendations

Elaboration of Safe Community Assessment System

Directory of Open Access Journals (Sweden)

Birutė Mikulskienė

2013-08-01

Full Text Available The paper aims to design an assessment system to monitor and evaluate safety parameters and administrative efforts with the purpose to increase safety in municipalities. The safety monitoring system considered is to be the most important tool for creation and development of safe communities in Lithuania. Several methods were applied to achieve this purpose. In order to determine the role of local government in ensuring the safety of people, property and environment at the local level of a meta-analysis of research reports, the Lithuanian national legislation, strategic planning documents of the state and local government were carried out. Analysis of statistical data, structural analysis, comparative analysis and synthesis methods were used while investigating the areas of safety uncertainty, risk groups, identifying safety risk factors, determining their relationship, and creating a safe community assessment system. A safe community assessment system, which consists of two types of criteria, has been elaborated. The assessment system is based on the multi-level criteria for safety monitoring and the multi-level criteria for the evaluation of municipal activities in the field of building safety. Links between the criteria, peculiarities of their application and advantages in the process of safe community creation and development are analyzed. Design and implementation of the safe community assessment system is one of the most important stages to implement the idea of safe communities. The proposed system integrates a variety of risk areas, the safety achievement criteria are linked to the criteria used in the strategic planning. Periodic assessment of the safety situation using the proposed system ensures possibility to monitor current local safety conditions and assess the changes and the trends. A safe community assessment system is proposed to be used as a tool to unified municipalities safety comprehensiveness and compare safety level in

Elaboration of Safe Community Assessment System

Directory of Open Access Journals (Sweden)

Algirdas Astrauskas

2011-12-01

Full Text Available The paper aims to design an assessment system to monitor and evaluate safety parameters and administrative efforts with the purpose to increase safety in municipalities. The safety monitoring system considered is to be the most important tool for creation anddevelopment of safe communities in Lithuania. Several methods were applied to achieve this purpose. In order to determine the role of local government in ensuring the safety of people, property and environment at the local level of a meta-analysis of research reports,the Lithuanian national legislation, strategic planning documents of the state and local government were carried out. Analysis of statistical data, structural analysis, comparative analysis and synthesis methods were used while investigating the areas of safety uncertainty, risk groups, identifying safety risk factors, determining their relationship, and creating a safe community assessment system.A safe community assessment system, which consists of two types of criteria, has been elaborated. The assessment system is based on the multi-level criteria for safety monitoring and the multi-level criteria for the evaluation of municipal activities in the field of building safety. Links between the criteria, peculiarities of their application and advantages in the process of safe community creation and development are analyzed.Design and implementation of the safe community assessment system is one of the most important stages to implement the idea of safe communities. The proposed system integrates a variety of risk areas, the safety achievement criteria are linked to the criteria used in thestrategic planning. Periodic assessment of the safety situation using the proposed system ensures possibility to monitor current local safety conditions and assess the changes and the trends. A safe community assessment system is proposed to be used as a tool to unified municipalities safety comprehensiveness and compare safety level in

The safe control of the transport of radioactive material in France

International Nuclear Information System (INIS)

Chaumette, L.

2000-01-01

The regulation of the transport of radioactive and fissile material for civil use concerns the protection of human beings and the environment against the radiological risk which can occur by these conveyed material. That's why this regulation particularly calls upon the law of the protection of the environment, upon the law of the transport of dangerous goods and upon the nuclear law. According to the International Atomic Energy Agency [I.A.E.A.], the implementation of this regulation gives the transport a high level of safety. It comes from I.A.E.A's recommendations which have taken into account lessons from the scientific research and from technical experiences. These recommendations are implemented in international binding modal regulations so that they can be adapted to the ways of transport. Their acceptance in the inner law goes with some national specific laws, mainly connected with the operator's missions and responsibilities. So this technical and administrative regulation is rather complex, and its codification would make it clearer. Nevertheless the whole regulation meets the double aim of the law in transport of dangerous goods which is to insure the safety of this transport of dangerous goods without prejudicing exchanges. In order to apply the regulation, the operators use supervision procedure to check their activities are in conformity with the law. In addition to these procedures, the Authorities supervise this conformity from time to time, by making boring. Operators and the Authorities involve their responsibility which is dependent either on the system of civil responsibility in case of damage, or on the system of administrative responsibility in case of error or risk, or on the system of penal responsibility in case of infraction of the law. So the operators have to apply the regulation and the Administration has to enforce this regulation they have built up. However, the self-control of the safety of the transport of radioactive

Safe use of nanomaterials

CERN Multimedia

2013-01-01

The use of nanomaterials  is on the increase worldwide, including at CERN. The HSE Unit has established a safety guideline to inform you of the main requirements for the safe handling and disposal of nanomaterials at CERN.   A risk assessment tool has also been developed which guides the user through the process of evaluating the risk for his or her activity. Based on the calculated risk level, the tool provides a list of recommended control measures.   We would therefore like to draw your attention to: Safety Guideline C-0-0-5 - Safe handling and disposal of nanomaterials; and Safety Form C-0-0-2 - Nanomaterial Risk Assessment   You can consult all of CERN’s safety rules and guidelines here. Please contact the HSE Unit for any questions you may have.   The HSE Unit

25 CFR 700.55 - Decent, safe, and sanitary dwelling.

Science.gov (United States)

2010-04-01

... 25 Indians 2 2010-04-01 2010-04-01 false Decent, safe, and sanitary dwelling. 700.55 Section 700... PROCEDURES General Policies and Instructions Definitions § 700.55 Decent, safe, and sanitary dwelling. (a) General. The term decent, safe, and sanitary dwelling means a dwelling which— (1) Meets applicable federal...

Radioactive Dry Process Material Treatment Technology Development

Energy Technology Data Exchange (ETDEWEB)

Park, J. J.; Hung, I. H.; Kim, K. K. (and others)

2007-06-15

The project 'Radioactive Dry Process Material Treatment Technology Development' aims to be normal operation for the experiments at DUPIC fuel development facility (DFDF) and safe operation of the facility through the technology developments such as remote operation, maintenance and pair of the facility, treatment of various high level process wastes and trapping of volatile process gases. DUPIC Fuel Development Facility (DFDF) can accommodate highly active nuclear materials, and now it is for fabrication of the oxide fuel by dry process characterizing the proliferation resistance. During the second stage from march 2005 to February 2007, we carried out technology development of the remote maintenance and the DFDF's safe operation, development of treatment technology for process off-gas, and development of treatment technology for PWR cladding hull and the results was described in this report.

Fracture mechanics aspects in the safe design of ductile iron shipping and storage containers

International Nuclear Information System (INIS)

Sappok, M.; Bounin, D.

1996-01-01

Containers made of ductile cast iron provide a safe method for transport of radioactive material. Contrary to widespread opinion ductile cast iron is a very tough material and can be manufactured in heavy sections. The containers are designed to withstand the very high impact loads of accidents like free drops onto unyielding targets. The design is based on postulated undetected crack-like flaws at the highest stressed location. Design must show that applied stress intensities are smaller than fracture toughness and no crack initiation and therefore also no crack propagation can occur. The design procedure followed in this paper is given in a new guideline still being drafted by the International Atomic Energy Agency

Transfer pricing and safe harbours

Directory of Open Access Journals (Sweden)

Veronika Solilová

2013-01-01

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

Atomistic Simulations of Small-scale Materials Tests of Nuclear Materials

International Nuclear Information System (INIS)

Shin, Chan Sun; Jin, Hyung Ha; Kwon, Jun Hyun

2012-01-01

Degradation of materials properties under neutron irradiation is one of the key issues affecting the lifetime of nuclear reactors. Evaluating the property changes of materials due to irradiations and understanding the role of microstructural changes on mechanical properties are required for ensuring reliable and safe operation of a nuclear reactor. However, high dose of neuron irradiation capabilities are rather limited and it is difficult to discriminate various factors affecting the property changes of materials. Ion beam irradiation can be used to investigate radiation damage to materials in a controlled way, but has the main limitation of small penetration depth in the length scale of micro meters. Over the past decade, the interest in the investigations of size-dependent mechanical properties has promoted the development of various small-scale materials tests, e.g. nanoindentation and micro/nano-pillar compression tests. Small-scale materials tests can address the issue of the limitation of small penetration depth of ion irradiation. In this paper, we present small-scale materials tests (experiments and simulation) which are applied to study the size and irradiation effects on mechanical properties. We have performed molecular dynamics simulations of nanoindentation and nanopillar compression tests. These atomistic simulations are expected to significantly contribute to the investigation of the fundamental deformation mechanism of small scale irradiated materials

Inherently safe technologies-chemical and nuclear

International Nuclear Information System (INIS)

Weinberg, A.M.

1984-01-01

Probabilistic risk assessments show an inverse relationship between the likelihood and the consequences of nuclear and chemical plant accidents, but the Bhopal accident has change public complacency about the safety of chemical plants to such an extent that public confidence is now at the same low level as with nuclear plants. The nuclear industry's response was to strengthen its institutions and improve its technologies, but the public may not be convinced. One solution is to develop reactors which do not depend upon the active intervention of humans of electromechanical devices to deal with emergencies, but which have physical properties that limit the possible temperature and power of a reactor. The Process Inherent Ultimately Safe and the modular High-Temperature Gas-Cooled reactors are two possibilities. the chemical industry needs to develop its own inherently safe design precepts that incorporate smallness, safe processes, and hardening against sabotage. 5 references

Intrinsically Safe and Economical Reactor (ISER)

International Nuclear Information System (INIS)

Wakabayashi, Hiroaki; Asahi, Yoshiro

1991-01-01

The Intrinsically Safe and Economical Reactor (ISER) is designed based on the principle of a process inherent ultimate safe reactor, PIUS, a so-called inherently safe reactor (ISR). ISER has been developed joingly by the members of the Kanagawa Institute of Technology, the University of Tokyo, the Japan Atomic Energy Research Institute (JAERI) and several industrial firms in Japan. This paper describes the requirements for the next generation of power reactor, the safety design philosphy of ISR and ISER, the controllability of ISER and the results of analyses of some of the design-based accidents (DBA) of ISER, namely station blackout, accidents in which the pressurizer relief valve becomes jammed and stuck in open position and tube breaks in the steam generator. It is concluded that the ISER can ensure a wide range of contraollabitily and fuel integrity for all the analysed DBAs. (orig.)

Directory of national competent authorities' approval certificates for package design, special form material and shipment of radioactive material. 1993 ed

International Nuclear Information System (INIS)

1993-10-01

This is the fourth annual report being published by the Secretariat of the International Atomic Energy Agency since implementing its database on package approval certificates (PACKTRAM) at the recommendation of the Standing Advisory Group on the Safe Transport of Radioactive Material (SAGSTRAM). The reporting format was established at consecutive meetings of SAGSTRAM, whose memberships consists of national competent authorities responsible for the transport of radioactive material from those Member States who have a nuclear industry and others who have shown a keen interest in the IAEA's transport safety programme. Through the PACKTRAM database, the Secretariat collects administrative and technical information on package approval certificates to assist national competent authorities in regulating radioactive material movements in their country. The database carries information on extant certificates and those that expired within the last two complete calendar years. The 1985 Edition of IAEA Safety Series No. 6, the 'Regulations for the Safe Transport of Radioactive Material'' highlights the role of competent authorities in assuring regulatory compliance in their own countries. Package approval certificates are an important aspect of that function. This document aims to be a useful reference for competent authorities as well as for manufacturers and shippers of radioactive material. 6 tabs

Directory of national competent authorities` approval certificates for package design, special form material and shipment of radioactive material. 1995 edition

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-09-01

This is the sixth annual report being published by the Secretariat of the International Atomic Energy Agency since implementing its database on package approval certificates (PACKTRAM) at the recommendation of the Standing Advisory Group on the Safe Transport of Radioactive Material (SAGSTRAM). The reporting format was established at consecutive meetings of SAGSTRAM, whose membership consists of national competent authorities responsible for the transport of radioactive material from those Member States who have a nuclear industry and others who have shown a keen interest in the IAEA`s transport safety programme. Through the PACKTRAM database, the Secretariat collects administrative and technical information on package approval certificates to assist national competent authorities in regulating radioactive material movements in their country. The database carries information on extant certificates and those that expired within the last complete calendar year. The 1985 Edition of IAEA Safety Series No. 6, the ``Regulations for the Safe Transport of Radioactive Material`` highlights the role of competent authorities in assuring regulatory compliance in their own countries. Package approval certificates are an important aspect of that function. This document aims to be a useful reference for competent authorities as well as for manufacturers and shippers of radioactive material. 6 tabs.

Directory of national competent authorities' approval certificates for package design, special form material and shipment of radioactive material. 1999 Edition

International Nuclear Information System (INIS)

1999-08-01

This is the tenth annual report being published by the Secretariat of the International Atomic Energy Agency since implementing its database on package approval certificates (PACKTRAM) at the recommendation of the Transport Safety Standards Advisory Committee (TRANSSAC), formerly known as the Standing Advisory Group on the Safe Transport of Radioactive Material (SAGSTRAM). The reporting format was established at consecutive meetings of SAGSTRAM and endorsed by TRANSSAC, whose membership consists of national competent authorities responsible for the transport of radioactive material from those Member States who have a nuclear industry and others who have shown a keen interest in the IAEA's transport safety programme. Through the PACKTRAM database, the Secretariat collects administrative and technical information on package approval certificates to assist national competent authorities in regulating radioactive material movements in their country. The database carries information on extant certificates and those that expired within the last complete calendar year. The 1985 Edition of IAEA Safety Series No. 6, the 'Regulations for the Safe Transport of Radioactive Material' highlights the role of competent authorities in assuring regulatory compliance in their own countries. Package approval certificates are an important aspect of that function. This document aims to be a useful reference for competent authorities as well as for manufacturers and shippers of radioactive material

Implementation of the NANoREG Safe-by-Design approach for different nanomaterial applications

International Nuclear Information System (INIS)

Micheletti, C; Roman, M; Tedesco, E; Olivato, I; Benetti, F

2017-01-01

The Safe-by-Design (SbD) concept is already in use in different industrial sectors as an integral part of the innovation process management. However, the adopted approach is often limited to design solutions aiming at hazard reduction. Safety is not always considered during the innovation process, mainly due to the lack of knowledge (e.g. in small and medium companies, SMEs) and the lack of dialogue between actors along the innovation chain. The net result is that safety is considered only at the end of the innovation process at the market authorization phase, with potential loss of time and money. This is especially valid for manufactured nanomaterials (MNM) for which the regulatory context is not completely developed, and the safety knowledge is not readily available. In order to contribute to a sustainable innovation process in the nanotechnology field by maximising both benefits and safety, the NANoREG project developed a Safe Innovation approach, based on two elements: the Safe-by-Design approach which aims at including risk assessment into all innovation stages; and the Regulatory Preparedness, focused on the dialogue with stakeholders along the innovation chain. In this work we present some examples about the implementation in our Laboratory of this approach for different MNM applications, covering different steps of the innovation chain. The case studies include: the feasibility study of a medical device including substances, for topical application; the testing of two potential nanotech solutions for the consolidation of cultural heritage artifacts; the testing of coatings already on the market for other uses, which was tested as food contact materials (FCM) to evaluate the conformity to food applications. These three examples represent a good opportunity to show the importance of NANoREG SbD and Safe Innovation Approach in general, for developing new nanotechnology-based products, also highlighting the crucial role of EU ProSafe project in promoting this

Implementation of the NANoREG Safe-by-Design approach for different nanomaterial applications

Science.gov (United States)

Micheletti, C.; Roman, M.; Tedesco, E.; Olivato, I.; Benetti, F.

2017-06-01

The Safe-by-Design (SbD) concept is already in use in different industrial sectors as an integral part of the innovation process management. However, the adopted approach is often limited to design solutions aiming at hazard reduction. Safety is not always considered during the innovation process, mainly due to the lack of knowledge (e.g. in small and medium companies, SMEs) and the lack of dialogue between actors along the innovation chain. The net result is that safety is considered only at the end of the innovation process at the market authorization phase, with potential loss of time and money. This is especially valid for manufactured nanomaterials (MNM) for which the regulatory context is not completely developed, and the safety knowledge is not readily available. In order to contribute to a sustainable innovation process in the nanotechnology field by maximising both benefits and safety, the NANoREG project developed a Safe Innovation approach, based on two elements: the Safe-by-Design approach which aims at including risk assessment into all innovation stages; and the Regulatory Preparedness, focused on the dialogue with stakeholders along the innovation chain. In this work we present some examples about the implementation in our Laboratory of this approach for different MNM applications, covering different steps of the innovation chain. The case studies include: the feasibility study of a medical device including substances, for topical application; the testing of two potential nanotech solutions for the consolidation of cultural heritage artifacts; the testing of coatings already on the market for other uses, which was tested as food contact materials (FCM) to evaluate the conformity to food applications. These three examples represent a good opportunity to show the importance of NANoREG SbD and Safe Innovation Approach in general, for developing new nanotechnology-based products, also highlighting the crucial role of EU ProSafe project in promoting this

Directory of national competent authorities' approval certificates for package design, special form material and shipment of radioactive material. 1997 Edition

International Nuclear Information System (INIS)

1997-08-01

This is the eighth annual report being published by the Secretariat of the International Atomic Energy Agency since implementing its database on package approval certificates (PACKTRAM) at the recommendation of the then Standing Advisory Group on the Safe Transport of Radioactive Material (SAGSTRAM). The functions of SAGSTRAM were taken over in 1996 by the Transport Safety Standards Advisory Committee (TRANSSAC). The reporting format was established at consecutive meetings of SAGSTRAM, whose membership consisted of national competent authorities responsible for the transport of radioactive material from those Member States who have a nuclear industry and others who showed a keen interest in the IAEA's transport safety programme. TRANSSAC underscores the importance of data collecting activities and recommends the continued publication of this annual report. The 1985 Edition of Safety Series No. 6, the ''Regulations for the Safe Transport of Radioactive Material'', highlights the role of competent authorities in assuring regulatory compliance in their own countries. The issuance of package approval certificates is an important aspects of that function. This document aims to be a useful reference for competent authorities as well as for manufacturers and shippers of radioactive material. 6 tabs

THE CONSEQUENCES OF GLOBALIZATION UPON SAFE TOURISM

Directory of Open Access Journals (Sweden)

Svetlana Mihić

2009-11-01

Full Text Available Globalization, a phenomenon on the rise, is characterized by the free cross-bor- der movement of individuals, technologies, and capital. It has far- reaching consequen- ces for tourism, too, as it implies travel for leisure and business, and correspondingly, financial transfers between various nation states. Startinf from the status quo in the field, the current paper sets out to analyze the consequences and implications of globalization upon safe tourism and conduct a marketing research into the perceptions of consumers upon Serbia as a safe vacation destination for the purpose of safe tourism. Finally the research results will be presented and several solutions will be provided for improving security in tourism zones

Sun Safe Mode Controller Design for LADEE

Science.gov (United States)

Fusco, Jesse C.; Swei, Sean S. M.; Nakamura, Robert H.

2015-01-01

This paper presents the development of sun safe controllers which are designed to keep the spacecraft power positive and thermally balanced in the event an anomaly is detected. Employed by NASA's Lunar Atmosphere and Dust Environment Explorer (LADEE), the controllers utilize the measured sun vector and the spacecraft body rates for feedback control. To improve the accuracy of sun vector estimation, the least square minimization approach is applied to process the sensor data, which is proven to be effective and accurate. To validate the controllers, the LADEE spacecraft model engaging the sun safe mode was first simulated and then compared with the actual LADEE orbital fight data. The results demonstrated the applicability of the proposed sun safe controllers.

Transport of radioactive materials by post

International Nuclear Information System (INIS)

1984-11-01

The objective of the Seminar was to encourage safe and efficient carriage of radioactive material by post. Adequate, up-to-date regulations for international and domestic shipment of radioactive material by all modes of transport, including by mail, have been published by the IAEA. UPU, ICAO, IATA and other international organizations as well as a majority of the countries of the world have adopted most sections of the Agency's Regulations for the Safe Transport of Radioactive Material. Although there is an apparent need for shipping radioactive material by mail, some countries allow only domestic shipments and the postal regulations applied in these countries often differs from the international regulations. Only about 25 countries are known to allow international (as well as domestic) shipments. From the discussions and comments at the Seminar, it appears that the option of shipment by post would be advantageous to enhance both the safety and economy of transporting, as well as to increase availability of, radioactive materials. The Agency's Regulations for transport by post as adopted by the UPU and ICAO are considered to provide a high level of safety and ensure a negligible element of risk. A more uniform application of these regulations within UPU Member States should be encouraged. The competent authority for implementation of the other parts of the Agency's Regulations in each of the Member States should be invited to advise the Postal Administrators and assist in applying the requirements to national as well as international postal shipments

Safe Detection System for Hydrogen Leaks

Energy Technology Data Exchange (ETDEWEB)

Lieberman, Robert A. [Intelligent Optical Systems, Inc., Torrance, CA (United States); Beshay, Manal [Intelligent Optical Systems, Inc., Torrance, CA (United States)

2012-02-29

Hydrogen is an "environmentally friendly" fuel for future transportation and other applications, since it produces only pure ("distilled") water when it is consumed. Thus, hydrogen-powered vehicles are beginning to proliferate, with the total number of such vehicles expected to rise to nearly 100,000 within the next few years. However, hydrogen is also an odorless, colorless, highly flammable gas. Because of this, there is an important need for hydrogen safety monitors that can warn of hazardous conditions in vehicles, storage facilities, and hydrogen production plants. To address this need, IOS has developed a unique intrinsically safe optical hydrogen sensing technology, and has embodied it in detector systems specifically developed for safety applications. The challenge of using light to detect a colorless substance was met by creating chemically-sensitized optical materials whose color changes in the presence of hydrogen. This reversible reaction provides a sensitive, reliable, way of detecting hydrogen and measuring its concentration using light from low-cost LEDs. Hydrogen sensors based on this material were developed in three completely different optical formats: point sensors ("optrodes"), integrated optic sensors ("optical chips"), and optical fibers ("distributed sensors") whose entire length responds to hydrogen. After comparing performance, cost, time-to-market, and relative market need for these sensor types, the project focused on designing a compact optrode-based single-point hydrogen safety monitor. The project ended with the fabrication of fifteen prototype units, and the selection of two specific markets: fuel cell enclosure monitoring, and refueling/storage safety. Final testing and development of control software for these markets await future support.

Fusion-reactor blanket and coolant material compatibility

International Nuclear Information System (INIS)

Jeppson, D.W.; Keough, R.F.

1981-01-01

Fusion reactor blanket and coolant compatibility tests are being conducted to aid in the selection and design of safe blanket and coolant systems for future fusion reactors. Results of scoping compatibility tests to date are reported for blanket material and water interactions at near operating temperatures. These tests indicate the quantitative hydrogen release, the maximum temperature and pressures produced and the rates of interactions for selected blanket materials

Influencing behaviour for safe working environments

OpenAIRE

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

2011-01-01

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

Now, It's Your Turn: How You Can Take Medicine Safely

Science.gov (United States)

... turn Javascript on. Feature: Taking Medicines Safely Now, It's Your Turn: How You Can Take Medicine Safely ... medicine. The pharmacist has filled the prescription. Now it's up to you to take the medicine safely. ...

Covered Storage. Design Manual 32.2.

Science.gov (United States)

1982-06-01

laboratories, snack bars, stairways, etc., are covered in the PBS Mechanical and Elec’rical Engineering Handbook and/or the Illuminating Engineering...laid. Scuttles shall be gasketed and fitted with inside and outside locks. d. Doors. Active cargo doors shall be gasketed by means of extruded

Canyon transfer neutron absorber to fissile material ratio analysis. Revision 1

International Nuclear Information System (INIS)

Clemmons, J.S.

1994-01-01

Waste tank fissile material and non-fissile material estimates are used to evaluate criticality safety for the existing sludge inventory and batches of sludge sent to Extended Sludge Processing (ESP). This report documents the weight ratios of several non-fissile waste constituents to fissile waste constituents from canyon reprocessing waste streams. Weight ratios of Fe, Mn, Al, Mi, and U-238 to fissile material are calculated from monthly loss estimates from the F and H Canyon Low Heat Waste (LHW) and High Heat Waste (HHW) streams. The monthly weight ratios for Fe, Mn and U-238 are then compared to calculated minimum safe weight ratios. Documented minimum safe weight ratios for Al and Ni to fissile material are currently not available. Total mass data for the subject sludge constituents is provided along with scatter plots of the monthly weight ratios for each waste stream

Intraarterial digital subtraction angiography of peripheral arteries with isotonic contrast material

International Nuclear Information System (INIS)

Yashiro, Naobumi; Itai, Yuji; Ohtomo, Kuni; Furui, Shigeru; Iio, Masahiro

1984-01-01

Intraarterial digital subtraction angiography (IADSA) of peripheral arteries with isotonic contrast material, which was prepared by diluting meglumine amidotrizoate (65% Angiografin), was performed in ten patients. In six, both IADSA and conventional screen-film arteriography were performed for comparison. Painless peripheral arteriography was achieved by IADSA with isotonic contrast material. Five IADSAs were safely done on an outpatient basis. Visualization of arteries by IADSA was satisfactory, but the details of smaller arteries were better shown by screen-film arteriography. Visualization of faint stains was better in IADSA. The authors believe that IADSA with isotonic contrast material is a method of choice for the diagnosis of vascular diseases and tumorous conditions of extremities, as well as for the purpose of preoperative vascular mapping. It is safely performed with smaller dose of contrast material on outpatient basis, and with less discomfort and cost for the patient. (author)

Test of Seal System for Flexible Pipe End Fitting

DEFF Research Database (Denmark)

Banke, Lars; Jensen, Thomas Gregers

1999-01-01

The purpose of the end fitting seal system is to ensure leak proof termination of flexible pipes. The seal system of an NKT end fitting normally consists of a number of ring joint gaskets mounted in a steel sleeve on the outside of the polymeric inner liner of the pipe. The seal system is activated...... by compression of the gaskets, thus using the geometry to establish a seal towards the inner liner of the pipe and the steel sleeve of the end fitting. This paper describes how the seal system of an end fitting can be tested using an autoclave. By regulating temperature and pressure, the seal system can...... be tested up to 130oC and 51.7 MPa. Pressure, temperature and the mechanical behaviours of the pipe are measured for use in further research. The set-up is used to test the efficiency of the seal system as function of parameters such as cross sectional shapes of the gaskets, tolerances between gaskets...

Is nuclear power safe enough

Energy Technology Data Exchange (ETDEWEB)

Andresen, A F [Institutt for Atomenergi, Kjeller (Norway)

1979-01-01

The lecture formed a commentary on the report of the Norwegian Government's Commission on Nuclear power Safety which was published in October 1978. It was introductorily pointed out that 'safe' and 'safety' are not in themselves meaningful terms and that the probability of an occurrence is the real measure. The main items in the Commission's report have been core meltdown, releases during reprocessing, waste disposal, plutonium diversion and environmental impacts. The 21 members of the Commission were unanimous in 7 of the 8 chapters. In chapter 2, 'Summary and Conclusions', 3 members dissented from the majority opinion, that, subject to certain conditions, nuclear power was a safe and acceptable source of energy.

A 'simple anterior fish excluder' (SAFE for mitigating penaeid-trawl bycatch.

Directory of Open Access Journals (Sweden)

Matthew J McHugh

Full Text Available Various plastic strips and sheets (termed 'simple anterior fish excluders'-SAFEs were positioned across the openings of penaeid trawls in attempts at reducing the unwanted bycatches of small teleosts. Initially, three SAFEs (a single wire without, and with small and large plastic panels were compared against a control (no SAFE on paired beam trawls. All SAFEs maintained targeted Metapenaeus macleayi catches, while the largest plastic SAFE significantly reduced total bycatch by 51% and the numbers of Pomatomus saltatrix, Mugil cephalus and Herklotsichthys castelnaui by up to 58%. A redesigned SAFE ('continuous plastic' was subsequently tested (against a control on paired otter trawls, significantly reducing total bycatch by 28% and P. saltatrix and H. castelnaui by up to 42%. The continuous-plastic SAFE also significantly reduced M. macleayi catches by ~7%, but this was explained by ~5% less wing-end spread, and could be simply negated through otter-board refinement. Further work is required to refine the tested SAFEs, and to quantify species-specific escape mechanisms. Nevertheless, the SAFE concept might represent an effective approach for improving penaeid-trawl selectivity.

Interim guidance for the safe transport of reprocessed uranium

International Nuclear Information System (INIS)

1994-06-01

Increasingly reprocessed uranium is being used for the fabrication of nuclear fuel elements. Different intermediate reprocessing steps are carried out at different locations. Therefore, transportation of uranium material is necessary. Due to the difference in isotope composition of reprocessed uranium then unirradiated uranium a doubt is casted on the presumption that packages used for the transport of unirradiated uranium are automatically suitable for reprocessed uranium compounds. The Standing Advisory Group on the Safe Transport of Radioactive Material (SAGSTRAM) recommended that the issue be reviewed by consultants and that a document be developed that would give guidance to users of the Regulations. This TECDOC is the result of the endeavors of the experts convened at two Consultants Services meetings. It contains guidance on the provisions in the current Regulations as well as proposals for changes to the new Revised Edition whose publication is planned for 1996. This document demonstrates that under the present Transport Regulations it is possible in most cases to ship reprocessed uranium compounds in the same packages as unirradiated uranium compounds. In few cases a more stringent package type is required. 8 refs, 22 figs, 19 tabs

Combined SAFE/SNAP approach to safeguards evaluation

International Nuclear Information System (INIS)

Engi, D.; Chapman, L.D.; Grant, F.H.; Polito, J.

1980-01-01

Generally, the scope of a safeguards evaluation model can efficiently address one of two issues, (1) global safeguards effectiveness, or (2) vulnerability analysis for individual scenarios. The Safeguards Automated Facility Evaluation (SAFE) focuses on (1) while the Safeguards Network Analysis Procedure (SNAP) is directed at (2). SAFE addresses (1) in that it considers the entire facility, i.e., the composite system of hardware and human components, in one global analysis. SNAP addresses (2) by providing a safeguards modeling symbology sufficiently flexible to represent quite complex scenarios from the standpoint of hardware interfaces while also accounting for a rich variety of human decision making. A combined SAFE/SNAP approach to the problem of safeguards evaluation is described and illustrated through an example

The regulatory framework concerning the safe transport of radioactive material in the European Union

International Nuclear Information System (INIS)

Schwarz, G.; Ridder, K.

2002-01-01

Radioactive materials of natural and manmade origins are employed worldwide in many areas, such as medicine, research, energy generation, and industry. As a consequence of the special nature and the properties of radioactive substances, irregular handling and use of such materials entails hazards. This is why special safety and protection provisions have been made in the interest of protecting health, life, property, and the environment from such hazards. The development and use of harmonized goals of protection and standards of safety is essential to free trade and the exchange of goods and services within the European Union and worldwide. The national and international institutions and organizations responsible for the protection and safety of transports of radioactive materials, including the European Union and its member countries, early on recognized the need for harmonized safety standards and criteria for transports of dangerous goods and developed an appropriate system of standards of safety and protection and a comprehensive set of tools for monitoring and checking observance of these standards. These tools have been laid down in a system of legally binding agreements, regulations, directives etc., or in recommendations, for the fifteen EU member states. The article presents this system of legally binding agreements, regulations, and recommendations, respectively, which covers the protection and safety of national and international transports of radioactive materials. (orig.) [de

LACK OF AWARENESS ABOUT SAFE BLOOD IN PAKISTANI POPULATION

Directory of Open Access Journals (Sweden)

Muhammad Usman

2014-12-01

Full Text Available Blood transfusion is a life saving procedure in various transfusion-dependent life threatening conditions and donation of safe blood is a prerequisite for achieving this goal. This study was designed to evaluate the awareness regarding “safe blood” in Pakistani population. This study was conducted at a large scale through a population survey. The test population was divided into two groups i.e. general population and students. The Performa was designed for a general and student population and included 20 questions related to awareness of safe blood. A total of 4900 individuals belonging to different ethnic groups were included in this population survey. Results of social survey were analyzed by using Usman and Moin awareness chart. Results of this study revealed profound unawareness about safe blood in Pakistani population. This study found lack of awareness about safe blood as a major factor that is playing a vital role in the propagation of blood borne diseases in Pakistan. To secure the recipients from blood borne complications through blood donation, it is necessary to create effective awareness about safe blood in Pakistani population.

Safe-haven CDS Premia

DEFF Research Database (Denmark)

Klingler, Sven; Lando, David

We argue that Credit Default Swap (CDS) premia for safe-haven sovereigns, like Germany and the United States, are driven to a large extent by regulatory requirements under which derivatives dealing banks have an incentive to buy CDS to hedge counterparty credit risk of their counterparties. We...

Swimming Safely (A Cup of Health with CDC)

Centers for Disease Control (CDC) Podcasts

In the summertime, families will be flocking to pools for relaxation and relief from the heat. A few simple precautions can help ensure a safe day in the water. In this podcast, Michele Hlavsa discusses ways to stay safe at the pool.

How safe are nuclear plants? How safe should they be?

International Nuclear Information System (INIS)

Kouts, H.

1988-01-01

It has become customary to think about safety of nuclear plants in terms of risk as defined by the WASH-1400 study that some of the implications for the non-specialist escape our attention. Yet it is known that a rational program to understand safety, to identify unsafe events, and to use this kind of information or analysis to improve safety, requires us to use the methods of quantitative risk assessment. How this process can be made more understandable to a broader group of nontechnical people and how can a wider acceptance of the results of the process be developed have been questions under study and are addressed in this report. These are questions that have been struggled with for some time in the world of nuclear plant safety. The Nuclear Regulatory Commission examined them for several years as it moved toward developing a position on safety goals for nuclear plants, a requirement that had been assigned it by Congress. Opinion was sought from a broad spectrum of individuals, within the field of nuclear power and outside it, on the topic that was popularly called, ''How safe is safe enough?'' Views were solicited on the answer to the question and also on the way the answer should be framed when it was adopted. This report discusses the public policy and its implementation

Ergonomics: safe patient handling and mobility.

Science.gov (United States)

Hallmark, Beth; Mechan, Patricia; Shores, Lynne

2015-03-01

This article reviews and investigates the issues surrounding ergonomics, with a specific focus on safe patient handling and mobility. The health care worker of today faces many challenges, one of which is related to the safety of patients. Safe patient handling and mobility is on the forefront of the movement to improve patient safety. This article reviews the risks associated with patient handling and mobility, and informs the reader of current evidence-based practice relevant to this area of care. Copyright © 2015 Elsevier Inc. All rights reserved.

Be-safe travel, a web-based geographic application to explore safe-route in an area

Science.gov (United States)

Utamima, Amalia; Djunaidy, Arif

2017-08-01

In large cities in developing countries, the various forms of criminality are often found. For instance, the most prominent crimes in Surabaya, Indonesia is 3C, that is theft with violence (curas), theft by weighting (curat), and motor vehicle theft (curanmor). 3C case most often occurs on the highway and residential areas. Therefore, new entrants in an area should be aware of these kind of crimes. Route Planners System or route planning system such as Google Maps only consider the shortest distance in the calculation of the optimal route. The selection of the optimal path in this study not only consider the shortest distance, but also involves other factors, namely the security level. This research considers at the need for an application to recommend the safest road to be passed by the vehicle passengers while drive an area. This research propose Be-Safe Travel, a web-based application using Google API that can be accessed by people who like to drive in an area, but still lack of knowledge of the pathways which are safe from crime. Be-Safe Travel is not only useful for the new entrants, but also useful for delivery courier of valuables goods to go through the safest streets.

Fail-safe computer-based plant protection systems

International Nuclear Information System (INIS)

Keats, A.B.

1983-01-01

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

Safe handling of radiation sources

International Nuclear Information System (INIS)

Abd Nasir Ibrahim; Azali Muhammad; Ab Razak Hamzah; Abd Aziz Mohamed; Mohammad Pauzi Ismail

2004-01-01

This chapter discussed the subjects related to the safe handling of radiation sources: type of radiation sources, method of use: transport within premises, transport outside premises; Disposal of Gamma Sources

Strategies and challenges for safe injection practice in developing countries.

Science.gov (United States)

Gyawali, Sudesh; Rathore, Devendra Singh; Shankar, P Ravi; Kumar, Kc Vikash

2013-01-01

Injection is one of the important health care procedures used globally to administer drugs. Its unsafe use can transmit various blood borne pathogens. This article aims to review the history and status of injection practices, its importance, interventions and the challenges for safe injection practice in developing countries. The history of injections started with the discovery of syringe in the early nineteenth century. Safe injection practice in developed countries was initiated in the early twentieth century but has not received adequate attention in developing countries. The establishment of "Safe Injection Global Network (SIGN)" was an milestone towards safe injection practice globally. In developing countries, people perceive injection as a powerful healing tool and do not hesitate to pay more for injections. Unsafe disposal and reuse of contaminated syringe is common. Ensuring safe injection practice is one of the greatest challenges for healthcare system in developing countries. To address the problem, interventions with active involvement of a number of stakeholders is essential. A combination of educational, managerial and regulatory strategies is found to be effective and economically viable. Rational and safe use of injections can save many lives but unsafe practice threatens life. Safe injection practice is crucial in developing countries. Evidence based interventions, with honest commitment and participation from the service provider, recipient and community with aid of policy makers are required to ensure safe injection practice.

Effective and Safe Ships

DEFF Research Database (Denmark)

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

1996-01-01

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

Application of Pyrolysis - Gas Chromatography/Mass Spectrometry in Failure Analysis in the Automotive Industry

OpenAIRE

Kusch, Peter (Dr.)

2015-01-01

This book chapter describes application examples of gas chromatography/mass spectrometry and pyrolysis – gas chromatography/mass spectrometry in failure analysis for the identification of chemical materials like mineral oils and nitrile rubber gaskets. Furthermore, failure cases demanding identification of polymers/copolymers in fouling on the compressor wall of a car air conditioner and identification of fouling on the surface of a bearing race from the automotive industry are demonstr...

Doorways III: Teacher Reference Materials. On School-Related Gender-Based Violence Prevention and Response

Science.gov (United States)

US Agency for International Development, 2009

2009-01-01

The Doorways training program was designed by the U.S. Agency for International Development (USAID)-funded Safe Schools Program (Safe Schools) to enable teachers, community members and students to prevent and respond to school-related gender-based violence (SRGBV). This booklet, "Doorways III: Teacher Reference Materials on School-Related…

Analysis of Methods of Determining the Safe Ship Trajectory

Directory of Open Access Journals (Sweden)

Jozef Lisowski

2016-07-01

Full Text Available The paper describes six methods of optimal and game theory and artificial neural network for synthesis of safe control in collision situations at sea. The application of optimal and game control algorithms to determine the own ship safe trajectory during the passing of other encountered ships in good and restricted visibility at sea is presented. The comparison of the safe ship control in collision situation: multi-step matrix non-cooperative and cooperative games, multi-stage positional non-cooperative and cooperative games have been introduced. The considerations have been illustrated with examples of computer simulation of the algorithms to determine safe of own ship trajectories in a navigational situation during passing of eight met ships.

Transport of radioactive materials

Energy Technology Data Exchange (ETDEWEB)

NONE

1960-04-15

The increasing use of radioactive substances, not only in reactor operations but also in medicine, industry and other fields, is making the movement of these materials progressively wider, more frequent and larger in volume. Although regulations for the safe transport of radioactive materials have been in existence for many years, it has now become necessary to modify or supplement the existing provisions on an international basis. It is essential that the regulations should be applied uniformly by all countries. It is also desirable that the basic regulations should be uniform for all modes of transport so as to simplify the procedures to be complied with by shippers and carriers

National and international nuclear material monitoring

International Nuclear Information System (INIS)

Waddoups, I.G.

1996-01-01

The status of nuclear materials in both the U.S. and Former Soviet Union is changing based upon the execution of agreements relative to weapons materials production and weapon dismantlement. The result of these activities is that a considerably different emphasis is being placed on how nuclear materials are viewed and utilized. Even though much effort is being expended on the final disposition of these materials, the interim need for storage and security of the material is increasing. Both safety and security requirements exist to govern activities when these materials are placed in storage. These requirements are intended to provide confidence that the material is not being misused and that the storage operations are conducted safely. Both of these goals can be significantly enhanced if technological monitoring of the material is performed. This paper will briefly discuss the traditional manual methods of U.S. and international material monitoring and then present approaches and technology that are available to achieve the same goals under the evolving environment

Development of E-Learning Materials for Machining Safety Education

Science.gov (United States)

Nakazawa, Tsuyoshi; Mita, Sumiyoshi; Matsubara, Masaaki; Takashima, Takeo; Tanaka, Koichi; Izawa, Satoru; Kawamura, Takashi

We developed two e-learning materials for Manufacturing Practice safety education: movie learning materials and hazard-detection learning materials. Using these video and sound media, students can learn how to operate machines safely with movie learning materials, which raise the effectiveness of preparation and review for manufacturing practice. Using these materials, students can realize safety operation well. Students can apply knowledge learned in lectures to the detection of hazards and use study methods for hazard detection during machine operation using the hazard-detection learning materials. Particularly, the hazard-detection learning materials raise students‧ safety consciousness and increase students‧ comprehension of knowledge from lectures and comprehension of operations during Manufacturing Practice.

Local Safety Toolkit: Enabling safe communities of opportunity

CSIR Research Space (South Africa)

Holtmann, B

2010-08-31

Full Text Available remain inadequate to achieve safety. The Local Safety Toolkit supports a strategy for a Safe South Africa through the implementation of a model for a Safe Community of Opportunity. The model is the outcome of work undertaken over the course of the past...

Are EU Banks Safe?

NARCIS (Netherlands)

R.J. Theissen (Roel)

2013-01-01

markdownabstract__Abstract__ What exactly are the rules banks are subject to, and are they fit for purpose? These are the two questions addressed in this book ‘Are EU banks safe?’ and its descriptive companion book ‘EU banking supervision’. The full rulebook on banks is difficult to find

Combined SAFE/SNAP approach to safeguards evaluation

International Nuclear Information System (INIS)

Engi, D.; Chapman, L.D.; Grant, F.H.; Polito, J.

1980-01-01

The scope of a safeguards evaluation model can efficiently address one of two issues: (1) global safeguards effectiveness or (2) vulnerability analysis for individual scenarios. The Safeguards Automated Facility Evaluation (SAFE) focuses on the first issue, while the Safeguards Network Analysis Procedure (SNAP) is directed towards the second. A combined SAFE/SNAP approach to the problem of safeguards evaluation is described and illustrated through an example. 4 refs

A Privacy Analysis of Google and Yandex Safe Browsing

OpenAIRE

Gerbet , Thomas; Kumar , Amrit; Lauradoux , Cédric

2015-01-01

Google and Yandex Safe Browsing are popular services included in many webbrowsers to prevent users from visiting phishing or malware website links. If Safe Browsing servicesprotect their users from losing private information, they also require that their servers receivebrowsing information on the very same users. In this paper, we present an analysis of Googleand Yandex Safe Browsing services from a privacy perspective. We quantify the privacy providedby these services by analyzing the possib...

New performance data for {open_quotes}Emery 3002{close_quotes} and {open_quotes}Emery 3004,{close_quotes} two Army-approved safe materials to replace DOP in mask and filter testing

Energy Technology Data Exchange (ETDEWEB)

Carlon, H.R.; Guelta, M.A. [Army Edgewood Research, Development and Engineering Center, Aberdeen Proving Ground, MD (United States)

1995-02-01

At the 22nd Conference in Denver, we reported that the U.S. Army Surgeon General (SGJ) had approved our developmental material {open_quotes}Emery 3004{close_quotes} as a safe replacement for the suspected carcinogen DOP (dioctyl phthalate) in mask and filter testing throughout the Army. Subsequently the SG approved a second, less viscous material, {open_quotes}Emery 3002,{close_quotes} for similar applications. We have measured the viscosities and surface tensions of these liquids over a wide range of temperatures, and have initiated liquid breakup studies through Laskin and two-fluid nozzles. New measurements have been carried out with both liquids, e.g. using the ATI, Inc., TDA-4A cold generator to disperse aerosols for which droplet size distributions were measured using the TSI, Inc., Differential Mobility Particle Sizer (DMPS). Among the findings were that Emery 3004 performs much like DOP in the TDA-4A, with some possible advantages, while Emery 3002 in the TDA-4A produces mean droplet diameters about one-half those of Emery 3004 or DOP. This suggests that Emery 3002 could yield more rigorous filter tests with a smaller consumption of material. New laboratory results will be summarized. Sources of the {open_quotes}Emery{close_quotes} materials will be discussed since the production facility formerly operated by Emery is now run by the Ethyl Corporation and the source products are now known as {open_quotes}Ethylflo 192{close_quotes} (Emery 3002) and{open_quotes}Ethylflo 194{close_quotes} (Emery 3004).

Quantum Digital Signatures for Unconditional Safe Authenticity Protection of Medical Documentation

Directory of Open Access Journals (Sweden)

Arkadiusz Liber

2015-12-01

Full Text Available Modern medical documentation appears most often in an online form which requires some digital methods to ensure its confidentiality, integrity and authenticity. The document authenticity may be secured with the use of a signature. A classical handwritten signature is directly related to its owner by his/her psychomotor character traits. Such a signature is also connected with the material it is written on, and a writing tool. Because of these properties, a handwritten signature reflects certain close material bonds between the owner and the document. In case of modern digital signatures, the document authentication has a mathematical nature. The verification of the authenticity becomes the verification of a key instead of a human. Since 1994 it has been known that classical digital signature algorithms may not be safe because of the Shor’s factorization algorithm. To implement the modern authenticity protection of medical data, some new types of algorithms should be used. One of the groups of such algorithms is based on the quantum computations. In this paper, the analysis of the current knowledge status of Quantum Digital Signature protocols, with its basic principles, phases and common elements such as transmission, comparison and encryption, was outlined. Some of the most promising protocols for signing digital medical documentation, that fulfill the requirements for QDS, were also briefly described. We showed that, a QDS protocol with QKD components requires the equipment similar to the equipment used for a QKD, for its implementation, which is already commercially available. If it is properly implemented, it provides the shortest lifetime of qubits in comparison to other protocols. It can be used not only to sign classical messages but probably it could be well adopted to implement unconditionally safe protection of medical documentation in the nearest future, as well.

The problems and suggestions on supervision of the radioactive material transport

International Nuclear Information System (INIS)

Cao Fangfang; Que Ji; Zhang Min; Pan Yuting

2012-01-01

The developing background and importance of the rules on supervision of the radioactive material transport are discussed in the paper. Based on the existing problems found in the process of implementing the rule 'Regulations for the safe transport of Radioactive Material', some countermeasures are proposed. (authors)

Safe corridors for K-wiring in phalangeal fractures

Directory of Open Access Journals (Sweden)

C Rex

2015-01-01

Conclusion: K-wiring through the safe corridor has proved to yield the best clinical results because of least tethering of soft tissues as evidenced by performing "on-table active finger movement test" at the time of surgery. We strongly recommend K-wiring through safe portals in all phalangeal fractures.

Safety requirements and feedback of commonly used material handling equipment

International Nuclear Information System (INIS)

Pathak, M.K.

2009-01-01

Different types of cranes, hoists, chain pulley blocks are the most commonly used material handling equipment in industry along with attachments like chains, wire rope slings, d-shackles, etc. These equipment are used at work for transferring loads from one place to another and attachments are used for anchoring, fixing or supporting the load. Selection of the correct equipment, identification of the equipment planning of material handling operation, examination/testing of the equipment, education and training of the persons engaged in operation of the material handling equipment can reduce the risks to safety of people in workplace. Different safety systems like boom angle indicator, overload tripping device, limit switches, etc. should be available in the cranes for their safe use. Safety requirement for safe operation of material handling equipment with emphasis on different cranes and attachments particularly wire rope slings and chain slings have been brought out in this paper. An attempt has also been made to bring out common nature of deficiencies observed during regulatory inspection carried out by AERB. (author)

Safe and Effective Ag Nanoparticles Immobilized Antimicrobial NanoNonwovens

DEFF Research Database (Denmark)

Song, Jie; Chen, Menglin; Regina, Viduthalai R.

2012-01-01

and possibility of introduction of secondary pollution. Here, we present a novel strategy to produce a safe and effective antimicrobial nanononwoven material by immobilizing AgNPs on a rigid polymer nanofibrous matrix through simple co-electrospinning of pre-prepaired AgNPs and polystyrene (PS). Distribution...... of the AgNPs on the surface of PS fibers was achieved by tuning fiber diameters during electrospinning. Atomic force microscopy (AFM) analysis revealed that the AgNPs distributed at the fiber surface were still covered by a layer of polymer, which inhibited their antimicrobial activity. UV/ozone treatment...... was thus employed to degrade the polymer coating without loosening the AgNPs, resulting in an active antimicrobial nonwoven against Gram-positive Staphylococcus xylosus. The mechanism based on cellular uptake of silver ions via close contact to the surface of AgNPs is proposed. The novel nanononwoven...

Plutonium inventories for stabilization and stabilized materials

Energy Technology Data Exchange (ETDEWEB)

Williams, A.K.

1996-05-01

The objective of the breakout session was to identify characteristics of materials containing plutonium, the need to stabilize these materials for storage, and plans to accomplish the stabilization activities. All current stabilization activities are driven by the Defense Nuclear Facilities Safety Board Recommendation 94-1 (May 26, 1994) and by the recently completed Plutonium ES&H Vulnerability Assessment (DOE-EH-0415). The Implementation Plan for accomplishing stabilization of plutonium-bearing residues in response to the Recommendation and the Assessment was published by DOE on February 28, 1995. This Implementation Plan (IP) commits to stabilizing problem materials within 3 years, and stabilizing all other materials within 8 years. The IP identifies approximately 20 metric tons of plutonium requiring stabilization and/or repackaging. A further breakdown shows this material to consist of 8.5 metric tons of plutonium metal and alloys, 5.5 metric tons of plutonium as oxide, and 6 metric tons of plutonium as residues. Stabilization of the metal and oxide categories containing greater than 50 weight percent plutonium is covered by DOE Standard {open_quotes}Criteria for Safe Storage of Plutonium Metals and Oxides{close_quotes} December, 1994 (DOE-STD-3013-94). This standard establishes criteria for safe storage of stabilized plutonium metals and oxides for up to 50 years. Each of the DOE sites and contractors with large plutonium inventories has either started or is preparing to start stabilization activities to meet these criteria.

Physical protection of radioactive material in transport

International Nuclear Information System (INIS)

1975-01-01

Safety in the transport of radioactive material is ensured by enclosing the material, when necessary, in packaging which prevents its dispersal and which absorbs to any adequate extent any radiation emitted by the material. Transport workers, the general public and the environment are thus protected against the harmful effects of the radioactive material. The packaging also serves the purpose of protecting its contents against the effects of rough handling and mishaps under normal transport conditions, and against the severe stresses and high temperatures that could be encountered in accidents accompanied by fires. If the radioactive material is also fissile, special design features are incorporated to prevent any possibility of criticality under normal transport conditions and in accidents. The safe transport requirements are designed to afford protection against unintentional opening of packages in normal handling and transport conditions and against damage in severe accident conditions; whereas the physical protection requirements are designed to prevent intentional opening of packages and deliberate damage. This clearly illustrates the difference in philosophical approach underlying the requirements for safe transport and for physical protection during transport. This difference in approach is, perhaps, most easily seen in the differing requirements for marking of consignments. While safety considerations dictate that packages be clearly labelled, physical protection considerations urge restraint in the use of special labels. Careful consideration must be given to such differences in approach in any attempt to harmonize the safety and physical protection aspects of transport. (author)

Alcohol use and safe drinking

Science.gov (United States)

... this page: //medlineplus.gov/ency/article/001944.htm Alcohol use and safe drinking To use the sharing features on this page, please enable JavaScript. Alcohol use involves drinking beer, wine, or hard liquor. ...

Dukovany NPP - Safely 16 TERA

International Nuclear Information System (INIS)

Vlcek, J.

2008-01-01

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

Setting priorities for safe motherhood interventions in resource-scarce settings.

Science.gov (United States)

Prata, Ndola; Sreenivas, Amita; Greig, Fiona; Walsh, Julia; Potts, Malcolm

2010-01-01

Guide policy-makers in prioritizing safe motherhood interventions. Three models (LOW, MED, HIGH) were constructed based on 34 sub-Saharan African countries to assess the relative cost-effectiveness of available safe motherhood interventions. Cost and effectiveness data were compiled and inserted into the WHO Mother Baby Package Costing Spreadsheet. For each model we assessed the percentage in maternal mortality reduction after implementing all interventions, and optimal combinations of interventions given restricted budgets of US$ 0.50, US$ 1.00, US$ 1.50 per capital maternal health expenditures respectively for LOW, MED, and HIGH models. The most cost-effective interventions were family planning and safe abortion (fpsa), antenatal care including misoprostol distribution for postpartum hemorrhage prevention at home deliveries (anc-miso), followed by sepsis treatment (sepsis) and facility-based postpartum hemorrhage management (pph). The combination of interventions that avert the greatest number of maternal deaths should be prioritized and expanded to cover the greatest number of women at risk. Those which save the most number of lives in each model are 'fpsa, anc-miso' and 'fpsa, sepsis, safe delivery' for LOW; 'fpsa, anc-miso' and 'fpsa, sepsis, safe delivery' for MED; and 'fpsa, anc-miso, sepsis, eclampsia treatment, safe delivery' for HIGH settings. Safe motherhood interventions save a significant number of newborn lives.

Code of Practice for the safe transport of radioactive substances 1990

International Nuclear Information System (INIS)

1990-01-01

This Federal Code revises an earlier Code on the same subject issued in 1982 and was formulated under the Environment Protection (Nuclear Codes) Act 1978. The purpose of the Code is to establish uniform safety standards, applicable throughout the Commonwealth of Australia, to provide for the protection of persons and the environment, against any dangers associated with the transport of radioactive substances. The Code uses as a basis the IAEA Regulations for the Safe Transport of Radioactive Materials. This new edition takes into account the 1985 Edition of the Regulations incorporating the 1988 Supplement and provides, furthermore, that radiation protection standards will also be subject to recommendations of the Australian National Health and Medical Research Council [fr

On the safe of pesticides in controlling the terrestrial mollusc pests

Directory of Open Access Journals (Sweden)

A. Panigrahi

1993-06-01

Full Text Available The preferred food items of the slugs Laevicaulis alte and the snails Achatina fulica were used to prepare 'poison baits'by injecting the pesticides 'Rogor'and 'Nuvan'to kill these mollusc pests. The 'poison baits'prepared with Thrichosanthes dioica and Lycopersicum esculentum were accepted by 100% individuals of both the species irrespective of the pesticides used. In all cases the slug and the snail individuals died within a considerable length of time following consuption of the bait. The importance of using 'poison bait'lies not only with the sure success in killing the pests but also with the 'safe use'of toxic materials in order to avoid environmental hazards.

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

Energy Technology Data Exchange (ETDEWEB)

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

2013-07-01

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

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

International Nuclear Information System (INIS)

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

2013-01-01

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

Safe Youth. Safe Schools.

Science.gov (United States)

... Concussion ABCs A child can take a spill, knock his/her head, and get a concussion in any number of school settings ranging from the hallway, the playground, the cafeteria, in school sports activities, and beyond. This flexible set of materials ...

Vitamin D status, bone mineral density and mental health in young Australian women: the Safe-D study

Directory of Open Access Journals (Sweden)

Emma T. Callegari

2015-11-01

Full Text Available Background. Vitamin D deficiency has been associated with both poor bone health and mental ill-health. More recently, a number of studies have found individuals with depressive symptoms tend to have reduced bone mineral density. To explore the interrelationships between vitamin D status, bone mineral density and mental-ill health we are assessing a range of clinical, behavioural and lifestyle factors in young women (Part A of the Safe-D study. Design and methods. Part A of the Safe-D study is a cross-sectional study aiming to recruit 468 young females aged 16-25 years living in Victoria, Australia, through Facebook advertising. Participants are required to complete an extensive, online questionnaire, wear an ultra-violet dosimeter for 14 consecutive days and attend a study site visit. Outcome measures include areal bone mineral measures at the lumbar spine, total hip and whole body, as well as soft tissue composition using dual energy x-ray absorptiometry. Trabecular and cortical volumetric bone density at the tibia is measured using peripheral quantitative computed tomography. Other tests include serum 25-hydroxyvitamin D, serum biochemistry and a range of health markers. Details of mood disorder/s and depressive and anxiety symptoms are obtained by self-report. Cutaneous melanin density is measured by spectrophotometry. Expected impact. The findings of this cross-sectional study will have implications for health promotion in young women and for clinical care of those with vitamin D deficiency and/or mental ill-health. Optimising both vitamin D status and mental health may protect against poor bone health and fractures in later life.

How safe is safe?

International Nuclear Information System (INIS)

Hughes, C.F.; Flood, M.

1996-01-01

60 and 70 degree convexo-concave valve. Nine hundred and one valves were implanted in Australia. Twelve strut fractures were reported. Two other patients have been explanted and have demonstrated 'single leg separation'. This particular problem was only investigated when two patients died of a fractured valve in the same hospital on the same day. A retrospective study of all known patients in Australia has shown poor follow up, lack of knowledge and indeed lack of interest in device failure modes. Consequently, the Australian and New Zealand Heart Valve Registry was established to track all implanted valves and to notify physicians of any new information. This is perhaps the first device-specific register in Australia. The safety of individual devices is often not known by manufacturers, regulators and clinicians alike. No follow up is available and large volume long term studies are yet to be implemented for the majority of devices. Without such studies and without mandatory problem reporting, the relative safety of medical devices will continue to be measured by banner headlines, sensational TV 'grabs' and protracted law suits. At present, only schemes such as the Problem Reporting Scheme can tell us (albeit vaguely) 'how safe is safe'

Regulation of Transportation of Radioactive Material in Indonesia

International Nuclear Information System (INIS)

Nirwono, Muttaqin Margo; Choi, Kwang Sik

2011-01-01

1.1. Background Indonesia is a biggest archipelago country with 17,508 islands in 33 provinces. In transportation Indonesia has large number of airports, railways, roadways, waterways, and merchant marines. Since nuclear and radiation utilizations are expanding on whole country, the mobilization of these is usually placed outside of controlled facilities, in the public domain, and often entails movement between countries. The Indonesian Nuclear Energy Regulatory Agency (BAPETEN) is responsible for supervision and also authorization of the transport of radioactive material (TRM). TRM is the specific movement of a radioactive material consignment from origin to destination by public transportation (road or rail, water and air). This study aims to determine whether national regulation is harmonized with international practice in ensuring safety and security of TRM. The finding of this study will provide recommendation for enhancement of regulation on TRM. 1.2. Regulation of TRM in Indonesia Government Regulation (GR) No. 26, 2002 on the Safe Transport of Radioactive Material is implemented pursuant to Act 10, 1997 on Nuclear Energy. This GR was repealed GR 13, 1975 on TRM. The GR 26 consist of 16 chapters and 39 articles, included licensing: authority and responsibilities: packaging: radiation protection programme; training: quality assurance programme: type and activity limit of radioactive materials: radioactive materials with other dangerous properties: emergency preparedness: administrative sanction: and penal provisions. Principally, this GR adopted IAEA-TS-R-1, 'Regulations for the Safe Transport of Radioactive Material', 1996's Edition

R&D for Safety Codes and Standards: Materials and Components Compatibility

Energy Technology Data Exchange (ETDEWEB)

San Marchi, Christopher W. [Sandia National Laboratories (SNL-CA), Livermore, CA (United States)

2014-08-01

A principal challenge to the widespread adoption of hydrogen infrastructure is the lack of quantifiable data on its safety envelope and concerns about additional risk from hydrogen. To convince regulatory officials, local fire marshals, fuel suppliers, and the public at large that hydrogen refueling is safe for consumer use, the risk to personnel and bystanders must be quantified and minimized to an acceptable level. Such a task requires strong confidence in the safety performance of high pressure hydrogen systems. Developing meaningful materials characterization and qualification methodologies in addition to enhancing understanding of performance of materials is critical to eliminating barriers to the development of safe, low-cost, high-performance high-pressure hydrogen systems for the consumer environment.

Technical considerations in materials management policy development

International Nuclear Information System (INIS)

Avci, H.; Goldberg, M.

1996-01-01

Under the Materials-in-Inventory (MIN) initiative, US DOE intends to develop policies to ensure that materials are managed and use efficiently, cost-effectively, and safely throughout DOE. The MIN initiative covers depleted uranium, scrap metals, chemicals, explosives, spent nuclear fuel, lead, alkali metals, etc.; by far the largest component is depleted uranium hexafluoride (DUF6). A technically defensible approach has been developed and is being used to select a long-term management strategy for DOE's DUF6 inventory. The same approach can be adapted to management of other materials in inventory that have the potential to be reutilized

Safe motherhood at risk?

Science.gov (United States)

Thompson, A

1996-12-01

Health professionals' negative attitudes toward clients often exacerbate the problems women face in terms of health status and access to health care. Thus, the health professionals can themselves be obstacles to women seeking the health care they need. A key challenge to midwives, in addition to providing technically competent services, is gaining insight into the people for whom they are responsible so that childbirth traditions are treated with respect and women are offered dignity. Safe motherhood requires intersectoral collaboration. Many innovative approaches to safe motherhood are based on the community's participation in planning services that meet the needs of women. Other approaches are based on decentralization of services. For example, a large university teaching hospital in Lusaka, Zambia, set up birthing centers around the city to take the pressure off the hospital. Midwives head up these centers, which are close to the women's homes. Decentralization of delivery services has improved the physical and emotional outcomes for mothers and newborns. Midwives must be prepared to articulate concerns about inequalities and deficiencies in the health care system in order to persuade the government to change. Women, including midwives, need to form multidisciplinary alliances to work together to effect change. The front-line workers in maternity care are midwives. They should adopt the following strategies to become even more effective in their efforts to make motherhood safer. They should listen to what women say about their needs. They should scale services to a manageable, human scale. They should learn the skills to become politically active advocates. They should work with other midwives, women, leaders, and other professional groups. Motherhood can be safe when women have more control over their own decision making, the education to liberate themselves to make their own decisions, and access to skilled care.

Safe Management of natural Occurring radionuclides Materials (NORM) from Petroleum Industry in Egypt

International Nuclear Information System (INIS)

El-Hussany, B.S.

2015-01-01

The isolation of radioactive waste from the environment becomes a real problem need to solve in the last half century. Waste management system is created for safe isolation of the waste. Radioactive waste management including all activities, administrative and operational, That are involved in the handling, conditioning, transport, storage and disposal of radioactive wastes. In petroleum and gas industries there are many wastes containing natural occurring radioactive waste (NORM). The concentration of NORM is increased during the different processes. Accumulation of NORM in these areas makes hazard effects on the workers and on the environment. In Egypt, there are many oil and gas industries in different areas of the republic. Most of these exploration sites containing large amounts of NORM waste. The management of this waste is remained unclear for many companies. Some companies have storage designs for the waste. Others are stored the waste on the working site on land without barriers. Additionally final destination of these wastes is not decided. The improper management of this waste lead to hazard effects to workers in the present time and to public in the future. The present work studies the NORM waste management, from petroleum industry, in Egypt. Strategy of NORM is proposed. NORM waste management steps (system) is also proposed, Incineration and deoiling processes for the treatment of NORM waste are compered. Also in this study, human intrusion scenarios were studied for two NORM storage designs, A) above-ground and B) under-ground bunkers

Chemical transformations of chlorophyll and its application in the design of a new generation of environmentally safe dyes

International Nuclear Information System (INIS)

Berezin, Boris D; Rumyantseva, Svetlana V; Moryganov, Andrey P; Berezin, Mikhail B

2004-01-01

Chemical transformations of chlorophyll and physicochemical properties of its derivatives are considered. These compounds can be used in the design of a new generation of chlorophyll- and porphyrin-based dyes environmentally more safe than currently used arene dyes and possessing renewable sources of raw materials. The first results on the use of chlorophyll derivatives for dyeing wool, acetate fibres and cotton are reported.

Chemical transformations of chlorophyll and its application in the design of a new generation of environmentally safe dyes

Energy Technology Data Exchange (ETDEWEB)

Berezin, Boris D; Rumyantseva, Svetlana V; Moryganov, Andrey P; Berezin, Mikhail B [Institute of Solution Chemistry, Russian Academy of Sciences, Ivanovo (Russian Federation)

2004-02-28

Chemical transformations of chlorophyll and physicochemical properties of its derivatives are considered. These compounds can be used in the design of a new generation of chlorophyll- and porphyrin-based dyes environmentally more safe than currently used arene dyes and possessing renewable sources of raw materials. The first results on the use of chlorophyll derivatives for dyeing wool, acetate fibres and cotton are reported.

Safe and easy power injection of contrast material through a central line

International Nuclear Information System (INIS)

Rogalla, P.; Meiri, N.; Hamm, M.B.; Thoeni, R.F.; Goldberg, H.I.

1998-01-01

Power-assisted injection of contrast material into an antecubital vein is commonly used in CT and has been proven superior to manual injection. Power-assisted injection through a central line bares the risk of rupturing the line because manual control over the pressure applied by the power injector is lacking. We present a simple safety device which allows manual control of the pressure by means of an interposed three-way stopcock combined with a small syringe for pressure equalization. (orig.)

Doorways II: Community Counselor Reference Materials. On School-Related Gender-Based Violence Prevention and Response

Science.gov (United States)

US Agency for International Development, 2009

2009-01-01

The Doorways training program was designed by the U.S. Agency for International Development (USAID)-funded Safe Schools Program (Safe Schools) to enable teachers, community members and students to prevent and respond to school-related gender-based violence (SRGBV). This booklet, "Doorways II: Community Counselor Reference Materials on…

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

International Nuclear Information System (INIS)

Hernalsteen, P.

1993-01-01

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

Education and training in nuclear materials

International Nuclear Information System (INIS)

Falcon, S.; Marco, M.

2014-01-01

CIEMAT participates in the European project Matisse (Materials Innovations for a Safe and Sustainable nuclear in Europe) belonging to FP7, whose main objective is to promote the link between the respective national research programs through networking and integration of activities for innovation in materials for advanced nuclear systems, sharing among partners best practices and implementation of training tools and efficient communication. The draft four years, from 2013 to 2017, includes aspects such as the interaction between infrastructure, R and D programs and postgraduate education and training. (Author)

Materials and Components Technology Division research summary, 1991

International Nuclear Information System (INIS)

1991-04-01

This division has the purpose of providing a R and D capability for design, fabrication, and testing of high-reliability materials, components, and instrumentation. Current divisional programs are in support of the Integral Fast Reactor, life extension for light water reactors, fuels development for the new production reactor and research and test reactors, fusion reactor first-wall and blanket technology, safe shipment of hazardous materials, fluid mechanics/materials/instrumentation for fossile energy systems, and energy conservation and renewables (including tribology, high- temperature superconductivity). Separate abstracts have been prepared for the data base

Materials and Components Technology Division research summary, 1991

Energy Technology Data Exchange (ETDEWEB)

1991-04-01

This division has the purpose of providing a R and D capability for design, fabrication, and testing of high-reliability materials, components, and instrumentation. Current divisional programs are in support of the Integral Fast Reactor, life extension for light water reactors, fuels development for the new production reactor and research and test reactors, fusion reactor first-wall and blanket technology, safe shipment of hazardous materials, fluid mechanics/materials/instrumentation for fossile energy systems, and energy conservation and renewables (including tribology, high- temperature superconductivity). Separate abstracts have been prepared for the data base.

The laser micro-machining system for diamond anvil cell experiments and general precision machining applications at the High Pressure Collaborative Access Team.

Science.gov (United States)

Hrubiak, Rostislav; Sinogeikin, Stanislav; Rod, Eric; Shen, Guoyin

2015-07-01

We have designed and constructed a new system for micro-machining parts and sample assemblies used for diamond anvil cells and general user operations at the High Pressure Collaborative Access Team, sector 16 of the Advanced Photon Source. The new micro-machining system uses a pulsed laser of 400 ps pulse duration, ablating various materials without thermal melting, thus leaving a clean edge. With optics designed for a tight focus, the system can machine holes any size larger than 3 μm in diameter. Unlike a standard electrical discharge machining drill, the new laser system allows micro-machining of non-conductive materials such as: amorphous boron and silicon carbide gaskets, diamond, oxides, and other materials including organic materials such as polyimide films (i.e., Kapton). An important feature of the new system is the use of gas-tight or gas-flow environmental chambers which allow the laser micro-machining to be done in a controlled (e.g., inert gas) atmosphere to prevent oxidation and other chemical reactions in air sensitive materials. The gas-tight workpiece enclosure is also useful for machining materials with known health risks (e.g., beryllium). Specialized control software with a graphical interface enables micro-machining of custom 2D and 3D shapes. The laser-machining system was designed in a Class 1 laser enclosure, i.e., it includes laser safety interlocks and computer controls and allows for routine operation. Though initially designed mainly for machining of the diamond anvil cell gaskets, the laser-machining system has since found many other micro-machining applications, several of which are presented here.

The laser micro-machining system for diamond anvil cell experiments and general precision machining applications at the High Pressure Collaborative Access Team

International Nuclear Information System (INIS)

Hrubiak, Rostislav; Sinogeikin, Stanislav; Rod, Eric; Shen, Guoyin

2015-01-01

We have designed and constructed a new system for micro-machining parts and sample assemblies used for diamond anvil cells and general user operations at the High Pressure Collaborative Access Team, sector 16 of the Advanced Photon Source. The new micro-machining system uses a pulsed laser of 400 ps pulse duration, ablating various materials without thermal melting, thus leaving a clean edge. With optics designed for a tight focus, the system can machine holes any size larger than 3 μm in diameter. Unlike a standard electrical discharge machining drill, the new laser system allows micro-machining of non-conductive materials such as: amorphous boron and silicon carbide gaskets, diamond, oxides, and other materials including organic materials such as polyimide films (i.e., Kapton). An important feature of the new system is the use of gas-tight or gas-flow environmental chambers which allow the laser micro-machining to be done in a controlled (e.g., inert gas) atmosphere to prevent oxidation and other chemical reactions in air sensitive materials. The gas-tight workpiece enclosure is also useful for machining materials with known health risks (e.g., beryllium). Specialized control software with a graphical interface enables micro-machining of custom 2D and 3D shapes. The laser-machining system was designed in a Class 1 laser enclosure, i.e., it includes laser safety interlocks and computer controls and allows for routine operation. Though initially designed mainly for machining of the diamond anvil cell gaskets, the laser-machining system has since found many other micro-machining applications, several of which are presented here

21 CFR 178.3130 - Antistatic and/or anti-fogging agents in food-packaging materials.

Science.gov (United States)

2010-04-01

...-packaging materials. 178.3130 Section 178.3130 Food and Drugs FOOD AND DRUG ADMINISTRATION, DEPARTMENT OF.../or anti-fogging agents in food-packaging materials. The substances listed in paragraph (b) of this section may be safely used as antistatic and/or antifogging agents in food-packaging materials, subject to...

Standards for safe operation of research reactors

International Nuclear Information System (INIS)

1996-01-01

The safety of research reactors is based on many factors such as suitable choice of location, design and construction according to the international standards, it also depends on well trained and qualified operational staff. These standards determine the responsibilities of all who are concerned with the research reactors safe operation, and who are responsible of all related activities in all the administrative and technical stages in a way that insures the safe operation of the reactor

Asymptotically Safe Standard Model Extensions arXiv