350 MW(t) MHTGR preassembly and modularization

International Nuclear Information System (INIS)

Venkatesh, M.C.; Jones, G.; Dilling, D.A.; Parker, W.J.

1991-05-01

The Modular High Temperature Gas Cooled Reactor (MHTGR) provides a safe and economical nuclear power option for the world's electrical generation needs by the turn of the century. The proposed MHTGR plant is composed of four 350 MW(t) prismatic core reactor modules, coupled to a 2(2 x 1) turbine generator producing a net plant electrical output of 538 MW(e). Each of the four reactor module is located in a below-ground level concrete silo, and consists of a reactor vessel and a steam generator vessel interconnected by a cross duct vessel. The modules, along with the service buildings, are contained within a Nuclear Island (NI). The turbine generators and power generation facilities are in the non-nuclear Energy Conversion Area (ECA). The MHTGR design reduces cost and improves schedule by maximizing shop fabrication, minimizing field fit up of the Reactor Internals components and modularizing the NI ampersand ECA facilities. 3 refs., 6 figs., 2 tabs

Systems engineering requirements impacting MHTGR circulator design

International Nuclear Information System (INIS)

Chi, H.W.; Baccaglini, G.M.; Potter, R.C.; Shenoy, A.S.

1988-01-01

At the initiation of the MHTGR program, an important task involved translating the plant users' requirements into design conditions. This was particularly true in the case of the heat transport and shutdown cooling systems since these embody many components. This paper addresses the two helium circulators in these systems. An integrated approach is being used in the development of design and design documentation for the MHTGR plant. It is an organized and systematic development of plant functions and requirements, determined by top-down design, performance, and cost trade-off studies and analyses, to define the overall plant systems, subsystems, components, and human actions. These studies, that led to the identification of the major design parameters for the two circulators, are discussed in this paper. This includes the performance information, steady state and transient data, and the various interface requirements. The design of the circulators used in the MHTGR is presented. (author). 1 ref., 17 figs

Utility/user requirements for the MHTGR desalination plant

International Nuclear Information System (INIS)

Brown, S.J.; Snyder, G.M.

1989-01-01

This paper describes the approach used by Gas-Cooled Reactor Associates (GCRA) and the Metropolitan Water District of Southern California (MWD) in developing Utility/User (U/U) Requirements for the Modular High Temperature Gas-cooled Reactor (MHTGR) Desalination Plant. This is a cogeneration plant that produces fresh water from seawater, and electricity. The U/U requirements for the reference MHTGR plant are used except for those changes necessary to: provide low-grade heat to a seawater desalination process, enable siting in a Southern California coastal area, take advantage of reduced weather extremes where substantial cost reductions are expected, and use seawater cooling instead of a cooling tower. The resulting requirements and the differences from the reference MHTGR requirements are discussed. The nuclear portion of the design is essentially the same as that for the reference MHTGR design. The major differences occur in the turbine-generator and condenser, and for the most part, the design parameters for the reference plant are found to be conservative for the desalination plant. The most important difference in requirements is in the higher seismic levels required for a Southern California site, which requires reassessment and possible modification of the design of some reference plant equipment for use in the desalination plant. (author). 5 refs, 1 tab

A Differential-Algebraic Model for the Once-Through Steam Generator of MHTGR-Based Multimodular Nuclear Plants

Directory of Open Access Journals (Sweden)

Zhe Dong

2015-01-01

Full Text Available Small modular reactors (SMRs are those fission reactors whose electrical output power is no more than 300 MWe. SMRs usually have the inherent safety feature that can be applicable to power plants of any desired power rating by applying the multimodular operation scheme. Due to its strong inherent safety feature, the modular high temperature gas-cooled reactor (MHTGR, which uses helium as coolant and graphite as moderator and structural material, is a typical SMR for building the next generation of nuclear plants (NGNPs. The once-through steam generator (OTSG is the basis of realizing the multimodular scheme, and modeling of the OTSG is meaningful to study the dynamic behavior of the multimodular plants and to design the operation and control strategy. In this paper, based upon the conservation laws of mass, energy, and momentum, a new differential-algebraic model for the OTSGs of the MHTGR-based multimodular nuclear plants is given. This newly-built model can describe the dynamic behavior of the OTSG in both the cases of providing superheated steam and generating saturated steam. Numerical simulation results show the feasibility and satisfactory performance of this model. Moreover, this model has been applied to develop the real-time simulation software for the operation and regulation features of the world first underconstructed MHTGR-based commercial nuclear plant—HTR-PM.

Prospects of power conversion technology of direct-cycle helium gas turbine for MHTGR

International Nuclear Information System (INIS)

Li Yong; Zhang Zuoyi

1999-01-01

The modular high temperature gas cooled reactor (MHTGR) is a modern passively safe reactor. The reactor and helium gas turbine may be combined for high efficiency's power conversion, because MHTGR has high outlet temperature up to 950 degree C. Two different schemes are planed separately by USA and South Africa. the helium gas turbine methodologies adopted by them are mainly based on the developed heavy duty industrial and aviation gas turbine technology. The author introduces the differences of two technologies and some design issues in the design and manufacture. Moreover, the author conclude that directly coupling a closed Brayton cycle gas turbine concept to the passively safe MHTGR is the developing direction of MHTGR due to its efficiency which is much higher than that of using steam turbine

Summary of utility/user requirements for and assessment of the MHTGR

International Nuclear Information System (INIS)

Mears, L.D.; Hoffman, D.P.

1992-01-01

Through Gas-Cooled Reactor Associates (GCRA), utilities provide end-user requirements, conduct ongoing technical and economic assessments and participate in the development of deployment strategies for the Modular High Temperature Gas-Cooled Reactor (MHTGR). It is GCRA's goal that the MHTGR be established as an attractive nuclear option for safe, reliable and economic energy supply with limited ownership risks. This report describes the rationale for the key GCRA requirements and presents a summary economic assessment of the reference, 4 module steam cycle design. (author)

An economic assessment of the U.S. MHTGR design

International Nuclear Information System (INIS)

Mears, L.D.

1991-01-01

US utilities and users have established an economic goal for the US MHTGR reference plant design which is the development of a design that has an evaluated economic advantage of at least 10% in the 30 year levelized busbar cost of electricity relative to a comparable sized, state-of-the-art coal fired plant while requiring equivalent institutional resources and posing equivalent financial risks. The term ''equivalent institutional resources'' means that approximately the same level of qualified personnel and organizational capability, functioning within similar corporate cultures, is required to successfully procure, license, operate, maintain and decommission the plants. The term ''equivalent financial risks'' means that approximately the same level of uncertainty exists for receiving an adequate return on investment, such that investors will be equally likely to invest in the MHTGR or coal plants. This paper presents a summary of the background, approach, and the current estimate for the US reference MHTGR electric generating plant. The plant is composed of two power building blocks producing a total output of 538 MW(e). Each building block consists of two reactor modules and one turbine-generator set. Additional economic results are given for a cogeneration application with a seawater desalination plant. (author)

The role of the MHTGR in coal gasification processes

International Nuclear Information System (INIS)

McDonald, C.F.

1988-01-01

The nation will likely become more and more dependent on natural gas and while this will stimulate new exploration and increased production, the time will surely come when global depletion of this resource will require the use of synthetic natural gas (SNG) to support the established nationwide infrastructure. The U.S. is estimated to have coal reserves nearing 500 billion tons that are mineable on an economic base. The Modular High Temperature Gas-Cooled Reactor (MHTGR) steam cycle plant can play an important role in the process of producing SNG from coal to supplement natural gas supplies. Coal-to-gas plants need heat (predominantly steam) and electricity for operation. This energy can be supplied by combustion of coal (autothermal process), but this results in a loss of more than 40% of the coal energy input. From the resource conservation standpoint, using an MHTGR heat source is attractive since much of the valuable fossil raw material can be substituted by clean nuclear energy. Also, air pollution is lowered drastically. This paper highlights how a near-term steam cycle MHTGR plant, based on proven technology and operating in a cogeneration mode, could be coupled with existing coal gasification processes to meet the projected increase in gas consumption in an environmentally acceptable manner

Exploitation of the very high temperature capability of the MHTGR to meet national energy needs after the year 2000

International Nuclear Information System (INIS)

McDonald, C.F.

1986-01-01

This paper addresses potential applications for the modular high-temperature gas-cooled reactor (MHTGR) to meet projected national energy needs early in the 21st century. The MHTGR reactor core is capable of up to 1000 0 C operation, which will evolve from the steam cycle base, together with the development of materials and components for elevated temperature service. The paper highlights roles of the advanced MHTGR for very high efficiency power generation and synthetic fuel production. Particular emphasis is put on the projected role of the MHTGR in the production of synthetic natural gas (SNG) that will be needed in several decades when natural gas resources are depleted

Helium compressor aerodynamic design considerations for MHTGR circulators

International Nuclear Information System (INIS)

McDonald, C.F.

1988-01-01

Compressor aerodynamic design considerations for both the main and shutdown cooling circulators in the Modular High-Temperature Gas-Cooled Reactor (MHTGR) plant are addressed in this paper. A major selection topic relates to the impeller type (i.e., axial or radial flow), and the aerothermal studies leading to the selection of optimum parameters are discussed. For the conceptual designs of the main and shutdown cooling circulators, compressor blading geometries were established and helium gas flow paths defined. Both circulators are conservative by industrial standards in terms of aerodynamic and structural loading, and the blade tip speeds are particularly modest. Performance characteristics are presented, and the designs embody margin to ensure that pressure-rise growth potential can be accomodated should the circuit resistance possibly increase as the plant design advances. The axial flow impeller for the main circulator is very similar to the Fort St. Vrain (FSV) helium compressor which performs well. A significant technology base exists for the MHTGR plant circulators, and this is highlighted in the paper. (author). 15 refs, 16 figs, 12 tabs

Considerations in the development of safety requirements for innovative reactors: Application to modular high temperature gas cooled reactors

International Nuclear Information System (INIS)

2003-08-01

Member States of the IAEA have frequently requested this organization to assess, at the conceptual stage, the safety of the design of nuclear reactors that rely on a variety of technologies and are of a high degree of innovation. However, to date, for advanced and innovative reactors and for reactors with characteristics that are different from those of existing light water reactors, widely accepted design standards and rules do not exist. This TECDOC is an outcome of the efforts deployed by the IAEA to develop a general approach for assessing the safety of the design of advanced and innovative reactors, and of all reactors in general including research reactors, with characteristics that differ from those of light water reactors. This publication puts forward a method for safety assessment that is based on the well established and accepted principle of defence in depth. The need to develop a general approach for assessing the safety of the design of reactors that applies to all kinds of advanced reactors was emphasized by the request to the IAEA by South Africa to review the safety of the South African pebble bed modular reactor. This reactor, as other modular high temperature gas cooled reactors (MHTGRs), adopts very specific design features such as the use of coated particle fuel. The characteristics of the fuel deeply affect the design and the safety of the plant, thereby posing several challenges to traditional safety assessment methods and to the application of existing safety requirements that have been developed primarily for water reactors. In this TECDOC, the MHTGR has been selected as a case study to demonstrate the viability of the method proposed. The approach presented is based on an extended interpretation of the concept of defence in depth and its link with the general safety objectives and fundamental safety functions as set out in 'Safety of Nuclear Power Plants: Design', IAEA Safety Standards No. NS-R.1, issued by the IAEA in 2000. The objective

Modeling and performance of the MHTGR [Modular High-Temperature Gas-Cooled Reactor] reactor cavity cooling system

International Nuclear Information System (INIS)

Conklin, J.C.

1990-04-01

The Reactor Cavity Cooling System (RCCS) of the Modular High- Temperature Gas-Cooled Reactor (MHTGR) proposed by the U.S. Department of Energy is designed to remove the nuclear afterheat passively in the event that neither the heat transport system nor the shutdown cooling circulator subsystem is available. A computer dynamic simulation for the physical and mathematical modeling of and RCCS is described here. Two conclusions can be made form computations performed under the assumption of a uniform reactor vessel temperature. First, the heat transferred across the annulus from the reactor vessel and then to ambient conditions is very dependent on the surface emissivities of the reactor vessel and RCCS panels. These emissivities should be periodically checked to ensure the safety function of the RCCS. Second, the heat transfer from the reactor vessel is reduced by a maximum of 10% by the presence of steam at 1 atm in the reactor cavity annulus for an assumed constant in the transmission of radiant energy across the annulus can be expected to result in an increase in the reactor vessel temperature for the MHTGR. Further investigation of participating radiation media, including small particles, in the reactor cavity annulus is warranted. 26 refs., 7 figs., 1 tab

Draft pre-application safety evaluation report for the modular high-temperature gas-cooled reactor

International Nuclear Information System (INIS)

Williams, P.M.; King, T.L.; Wilson, J.N.

1989-03-01

This draft safety evaluation report (SER) presents the preliminary results of a pre-application design review for the standard modular high-temperature gas-cooled reactor (MHTGR) (Project 672). The MHTGR conceptual design was submitted by the U.S. Department of Energy (DOE) in accordance with the U.S. Nuclear Regulatory Commission(NRC) 'Statement of Policy for the Regulation of Advanced Nuclear Power Plants' (51 FR 24643), which provides for early Commission review and interaction. The standard MHTGR consists of four identical reactor modules, each with a thermal output of 350 MWt, coupled with two steam turbine-generator sets to produce a total plant electrical output of 540 MWe. The reactors are helium cooled and graphite moderated and utilize ceramically coated particle-type nuclear fuel. The design includes passive reactor-shutdown and decay-heat-removal features. The staff and its contractors at the Oak Ridge National Laboratory and the Brookhaven National Laboratory have reviewed this design with emphasis on those unique provisions in the design that accomplish the key safety functions of reactor shutdown, decay-heat removal, and containment of radioactive material. This report presents the NRC staff's technical evaluation of those features in the MHTGR design important to safety, including their proposed research and testing needs. In addition this report presents the criteria proposed by the NRC staff to judge the acceptability of the MHTGR design and, where possible, includes statements on the potential of the MHTGR to meet these criteria. However, it should be recognized that final conclusions in all matters discussed in this report require approval by the Commission. Final determination on the acceptability of the MHTGR standard design is contingent on receipt and evaluation of additional information requested from DOE pertaining to the adequacy of the containment design and on the following: (1) satisfactory resolution of open safety issues identified

46 CFR 26.03-1 - Safety orientation.

Science.gov (United States)

2010-10-01

... 46 Shipping 1 2010-10-01 2010-10-01 false Safety orientation. 26.03-1 Section 26.03-1 Shipping... Requirements § 26.03-1 Safety orientation. (a) Before getting underway on any uninspected passenger vessel, the... this subpart engaged in tender service at yacht clubs and marinas, and vessels being demonstrated for a...

Targeting of GIT1 by miR-149* in breast cancer suppresses cell proliferation and metastasis in vitro and tumor growth in vivo

Directory of Open Access Journals (Sweden)

Dong Y

2017-12-01

Full Text Available Yan Dong,1,* Cai Chang,2,* Jingtian Liu,3 Jinwei Qiang4 1Department of Ultrasonography, Jinshan Hospital, 2Department of Ultrasonography, Cancer Center, 3Department of General Surgery, 4Department of Radiology, Jinshan Hospital, Fudan University, Shanghai, China *These authors contributed equally to this work Abstract: Breast cancer remains a major cause of cancer-related death in women worldwide. Dysregulation of microRNAs (miRNAs is involved in the initiation and progression of breast cancer. Moreover, it was found that GIT1 was widely involved in the development of many human cancers. Herein, we aimed to investigate the expression changes of miR-149* and GIT1 and the functional effects of miR-149*/GIT1 link in breast cancer. Quantitative reverse transcription-polymerase chain reaction (qRT-PCR and Western blot (WB were used to examine the expression levels of miR-149* and GIT1. Dual luciferase reporter assay was utilized to confirm the target interaction between miR-149* and GIT1. The biological functions, including cell proliferation, invasion, and migration, of miR-149* and GIT1 were determined by MTT assay and Transwell assays, respectively. Eventually, the tumor xenograft model in nude mice injected with stable transfected MDA-MB-231 cells was established to verify the effects of miR-149* and GIT1 on tumor growth. Our results showed that miR-149* expression was decreased, whereas GIT1 expression was increased in clinical samples of breast cancer. Based on the inverse expression trend between miR-149* and GIT1, we further demonstrated that miR-149* indeed directly targets GIT1. Subsequently, it was observed that inhibition of miR-149* significantly promoted cell proliferation, invasion, and migration, but the ability of cell proliferation, invasion, and migration was obviously declined after silencing of GIT1 in MDA-MB-231 cells transfected with miR-149* mimic and/or si-GIT1. Finally, it was also found that elevated miR-149* decelerated

An international assessment of the gas tubine MHTGR

International Nuclear Information System (INIS)

Penfield, S.R.; Kerr, H.T.; Schleicher, R.W.

1992-01-01

The potential for gas turbine applications of the MHTGR has been addressed in a recent evaluation sponsored by the Empire State electric Energy Research Corporation (ESEERCO), the US Department of Energy (DOE), Oak Ridge National Laboratory (ORNL) and Gas-Cooled Reactor Associates (GCRA). Additional support for the evaluation was provided by representatives of the French. German and Japanese nuclear communities. The results of this internationally based gas turbine evaluation are the subject of this paper

Present status of MHTGR program in USA

International Nuclear Information System (INIS)

Millunzi, A.

1990-01-01

The U.S. Department of Energy (DOE) Modular High-Temperature Gas-Cooled Reactor (MHTGR) program has produced a conceptual design which has been reviewed by the U.S. Nuclear Regulatory Commission (NRC). The results of the review were generally favorable, and the program team has now moved into the preliminary design phase. The program team consists of a nuclear island engineering (NIE) team, an energy conversion area (ECA) team, a design integration organization, and a technology development team. Utility user requirements are provided by a utility organization which also participates in design and programmatic review/evaluations. This paper will review the direction and accomplishments of each participating organization. (author)

Present status of MHTGR program in USA

International Nuclear Information System (INIS)

Rittenhouse, P.L.

1989-01-01

The U.S. Department of Energy (DOE) Modular High-Temperature Gas-Cooled Reactor (MHTGR) program has produced a conceptual design which has been reviewed by the U.S. Nuclear Regulatory Commission (NRC). The results of the review were generally favorable, and the program team has now moved into the preliminary design phase. The program team consists of a nuclear island engineering (NIE) team, an energy conversion area (ECA) team, a design integration organization, and a technology development team. Utility user requirements are provided by a utility organization which also participates in design and programmatic reviews/evaluations. This paper will review the direction and accomplishments of each participating organization. (orig.)

Evaluation of MHTGR fuel reliability

International Nuclear Information System (INIS)

Wichner, R.P.; Barthold, W.P.

1992-07-01

Modular High-Temperature Gas-Cooled Reactor (MHTGR) concepts that house the reactor vessel in a tight but unsealed reactor building place heightened importance on the reliability of the fuel particle coatings as fission product barriers. Though accident consequence analyses continue to show favorable results, the increased dependence on one type of barrier, in addition to a number of other factors, has caused the Nuclear Regulatory Commission (NRC) to consider conservative assumptions regarding fuel behavior. For this purpose, the concept termed ''weak fuel'' has been proposed on an interim basis. ''Weak fuel'' is a penalty imposed on consequence analyses whereby the fuel is assumed to respond less favorably to environmental conditions than predicted by behavioral models. The rationale for adopting this penalty, as well as conditions that would permit its reduction or elimination, are examined in this report. The evaluation includes an examination of possible fuel-manufacturing defects, quality-control procedures for defect detection, and the mechanisms by which fuel defects may lead to failure

RELAP5-3D Results for Phase I (Exercise 2) of the OECD/NEA MHTGR-350 MW Benchmark

Energy Technology Data Exchange (ETDEWEB)

Gerhard Strydom

2012-06-01

The coupling of the PHISICS code suite to the thermal hydraulics system code RELAP5-3D has recently been initiated at the Idaho National Laboratory (INL) to provide a fully coupled prismatic Very High Temperature Reactor (VHTR) system modeling capability as part of the NGNP methods development program. The PHISICS code consists of three modules: INSTANT (performing 3D nodal transport core calculations), MRTAU (depletion and decay heat generation) and a perturbation/mixer module. As part of the verification and validation activities, steady state results have been obtained for Exercise 2 of Phase I of the newly-defined OECD/NEA MHTGR-350 MW Benchmark. This exercise requires participants to calculate a steady-state solution for an End of Equilibrium Cycle 350 MW Modular High Temperature Reactor (MHTGR), using the provided geometry, material, and coolant bypass flow description. The paper provides an overview of the MHTGR Benchmark and presents typical steady state results (e.g. solid and gas temperatures, thermal conductivities) for Phase I Exercise 2. Preliminary results are also provided for the early test phase of Exercise 3 using a two-group cross-section library and the Relap5-3D model developed for Exercise 2.

9 CFR 149.6 - Slaughter facilities.

Science.gov (United States)

2010-01-01

... 9 Animals and Animal Products 1 2010-01-01 2010-01-01 false Slaughter facilities. 149.6 Section... AGRICULTURE LIVESTOCK IMPROVEMENT VOLUNTARY TRICHINAE CERTIFICATION PROGRAM § 149.6 Slaughter facilities. Only slaughter facilities that are under continuous inspection by the Food Safety and Inspection Service or under...

Innovative safety features of the modular HTGR

International Nuclear Information System (INIS)

Silady, F.A.; Simon, W.A.

1992-04-01

In this document the innovative safety features of the MHTGR are reviewed by examining the safety response to events challenging the functions relied on to retain radionuclides within the coated fuel particles. A broad range of challenges to core heat removal are examined, including a loss of helium pressure and a simultaneous loss of forced cool of the core

The Modular High-Temperature Gas-Cooled Reactor (MHTGR) in the US

International Nuclear Information System (INIS)

Neylan, A.J.; Graf, D.V.; Millunzi, A.C.

1987-08-01

The MHTGR is an advanced nuclear reactor concept being developed in the USA under a cooperative program involving the US Government, the nuclear industry, and the utilities. As its objective, this program is developing a safe, reliable, and economic nuclear power option for the USA and the other nations of the world to consider in meeting their individual nationalistic electrical generation or process heat needs by the turn of the century. The design is based on a concept of modularization that can meet the various power needs by combining any number of 350 MW(t) reactor modules in parallel with a selected number of turbine plants in a variety of arrangements. Basic HTGR features of ceramic fuel, helium coolant, and graphite are sized and configured to provide a low power density core with passive safety features such that no operator action or external source of power is needed for the plant to meet 10CFR100 or Protective Action Guidelines limits at the 425 m site boundary. This precludes the necessity to plan for the evacuation or sheltering of the public during any licensing basis event. The safe behavior of the reactor plant is not dependent upon operator action and it is insensitive to operator error. The Conceptual Design is presently being vigorously reviewed by the US Nuclear Regulatory Commission (NRC). A safety evaluation report and a licensability statement are scheduled for issuance by the NRC in January 1988. 2 refs., 5 figs., 1 tab

Distributivity of the algebra of regular open subsets of .beta. R / R

Czech Academy of Sciences Publication Activity Database

Balcar, Bohuslav; Hrušák, M.

2005-01-01

Roč. 149, č. 1 (2005), s. 1-7 ISSN 0166-8641 R&D Projects: GA ČR(CZ) GA201/03/0933; GA ČR(CZ) GA201/02/0857 Institutional research plan: CEZ:AV0Z10190503 Keywords : distributivity of Boolean algebras * cardinal invariants of the continuum * Čech-Stone compactification Subject RIV: BA - General Mathematics Impact factor: 0.297, year: 2005

MHTGR steam generator on-line heat balance, instrumentation and function

International Nuclear Information System (INIS)

Klapka, R.E.; Howard, W.W.; Etzel, K.T.; Basol, M.; Karim, N.U.

1991-09-01

Instrumentation is used to measure the Modular High Temperature Gas-Cooled Reactor (MHTGR) steam generator dissimilar metal weld temperature during start-up testing. Additional instrumentation is used to determine an on-line heat balance which is maintained during the 40 year module life. In the process of calibrating the on-line heat balance, the helium flow is adjusted to yield the optimum boiling level in the steam generator relative to the dissimilar metal weld. After calibration is complete the weld temperature measurement is non longer required. The reduced boiling level range results in less restrictive steam generator design constraints

INL Results for Phases I and III of the OECD/NEA MHTGR-350 Benchmark

Energy Technology Data Exchange (ETDEWEB)

Gerhard Strydom; Javier Ortensi; Sonat Sen; Hans Hammer

2013-09-01

The Idaho National Laboratory (INL) Very High Temperature Reactor (VHTR) Technology Development Office (TDO) Methods Core Simulation group led the construction of the Organization for Economic Cooperation and Development (OECD) Modular High Temperature Reactor (MHTGR) 350 MW benchmark for comparing and evaluating prismatic VHTR analysis codes. The benchmark is sponsored by the OECD's Nuclear Energy Agency (NEA), and the project will yield a set of reference steady-state, transient, and lattice depletion problems that can be used by the Department of Energy (DOE), the Nuclear Regulatory Commission (NRC), and vendors to assess their code suits. The Methods group is responsible for defining the benchmark specifications, leading the data collection and comparison activities, and chairing the annual technical workshops. This report summarizes the latest INL results for Phase I (steady state) and Phase III (lattice depletion) of the benchmark. The INSTANT, Pronghorn and RattleSnake codes were used for the standalone core neutronics modeling of Exercise 1, and the results obtained from these codes are compared in Section 4. Exercise 2 of Phase I requires the standalone steady-state thermal fluids modeling of the MHTGR-350 design, and the results for the systems code RELAP5-3D are discussed in Section 5. The coupled neutronics and thermal fluids steady-state solution for Exercise 3 are reported in Section 6, utilizing the newly developed Parallel and Highly Innovative Simulation for INL Code System (PHISICS)/RELAP5-3D code suit. Finally, the lattice depletion models and results obtained for Phase III are compared in Section 7. The MHTGR-350 benchmark proved to be a challenging simulation set of problems to model accurately, and even with the simplifications introduced in the benchmark specification this activity is an important step in the code-to-code verification of modern prismatic VHTR codes. A final OECD/NEA comparison report will compare the Phase I and III

Database and modeling assessments of the CANDU 3, PIUS, ALMR, and MHTGR designs

International Nuclear Information System (INIS)

Carlson, D.E.; Meyer, R.O.

1994-01-01

As part of the research program to support the preapplication reviews of the CANDU 3, PIUS, ALMR, and MHTGR designs, the NRC has completed preliminary assessments of databases and modeling capabilities. To ensure full coverage of all four designs, a detailed assessment methodology was developed that follows the broad logic of the NRC's Code Scaling, Applicability, and Uncertainty (CSAU) methodology. This paper describes the methodology of the database assessments and presents examples of the assessment process using preliminary results for the ALMR design

Efficacy and safety of QVA149 compared to the concurrent administration of its monocomponents indacaterol and glycopyrronium: the BEACON study

Directory of Open Access Journals (Sweden)

Dahl R

2013-10-01

Full Text Available Ronald Dahl,1 Dalal Jadayel,2 Vijay KT Alagappan,3 Hungta Chen,3 Donald Banerji31Department of Dermatology, Allergy Centre, Odense University Hospital, Odense, Denmark; 2Novartis Horsham Research Centre, Horsham, UK; 3Novartis Pharmaceuticals Corporation, East Hanover, NJ, USAIntroduction: The BEACON study evaluated the efficacy and safety of QVA149, a once-daily dual bronchodilator containing a fixed-dose combination of the long-acting β2-agonist (LABA indacaterol and long-acting muscarinic antagonist (LAMA glycopyrronium (NVA237, in development for the treatment of patients with chronic obstructive pulmonary disease (COPD, compared with the free-dose concurrent administration of indacaterol plus glycopyrronium (IND+GLY.Methods: In this multicenter, double-blind, parallel group study, patients with stage II or stage III COPD (Global initiative for chronic Obstructive Lung Disease [GOLD] 2010 were randomized (1:1 to once-daily QVA149 (110 µg indacaterol/50 µg glycopyrronium or concurrent administration of indacaterol (150 µg and glycopyrronium (50 µg via the Breezhaler® device (Novartis AG, Basel, Switzerland for 4 weeks. The primary endpoint was to evaluate the noninferiority of QVA149 as compared with concurrent administration of IND+GLY, for trough forced expiratory volume in 1 second (FEV1 after 4 weeks of treatment. The other assessments included FEV1 area under the curve from 0 to 4 hours (AUC0–4 hours at day 1 and week 4, symptom scores, rescue medication use, safety, and tolerability over the 4-week study period.Results: Of 193 patients randomized, 187 (96.9% completed the study. Trough FEV1 at week 4 for QVA149 and IND+GLY was 1.46 L ± 0.02 and 1.46 L ± 0.18, respectively. The FEV1 AUC0–4 hours at day 1 and week 4 were similar between the two treatment groups. Both treatment groups had a similar reduction in symptom scores and rescue medication use for the 4-week treatment period. Overall, 25.6% of patients in QVA149 group

Conceptual design of helium gas turbine for MHTGR-GT

International Nuclear Information System (INIS)

Matsuo, E.; Tsutsumi, M.; Ogata, K.; Nomura, S.

1996-01-01

Conceptual designs of the direct-cycle helium gas turbine for a practical unit (450 MWt) and an experimental unit (1200kWt) of MHTGR were conducted and the results as shown below were obtained. The power conversion vessel for this practical unit can further be downsized to an outside diameter of 7.4m and a height of 22m as compared with the conventional design examples. Comparison of the conceptual designs of helium gas turbines using single-shaft type employing the axial-flow compressor and twin-shaft type employing the centrifugal compressor shows that the former provides advantages in terms of structure and control designs whereas the latter offers a higher efficiency. In order to determine which of them should be selected, a further study to investigate various aspects of safety features and startup characteristics will be needed. Either of the two types can provide a cycle efficiency of 46 to 48%. The third mode natural frequencies of the twin-shart type's low-pressure rotational shaft and the single shaft type are below the designed rotational speed, but their vibrational controls are made available using the magnetic bearing system. Elevation of the natural frequency for the twin-shaft type would be possible by altering the arrangements of its shafting configuration. As compared with the earlier conceptual designs, the overall systems configuration can be made simpler and more compact; five stages of turbines for the single-shaft type and seven stages of turbines for the twin-shaft type employing one shaft for the low-pressure compressor and the power turbine and; 26 stages of compressors for the axial-flow type with the single shaft system and five stages of compressors for the centrifugal type with the twin-shaft system. 9 refs, 12 figs, 4 tabs

Potential applications of high temperature helium

International Nuclear Information System (INIS)

Schleicher, R.W. Jr.; Kennedy, A.J.

1992-09-01

This paper discusses the DOE MHTGR-SC program's recent activity to improve the economics of the MHTGR without sacrificing safety performance and two potential applications of high temperature helium, the MHTGR gas turbine plant and a process heat application for methanol production from coal

The way to solve the safety problems of nuclear power

International Nuclear Information System (INIS)

Qian Jihui; Zhang Senru

1991-01-01

Based on the safety problems that the current water cooled reactor nuclear power plants have the potential danger of core melt, the paper comments upon the safety behaviors of the advanced reactors (AP-600, SIR) and passive safety reactors (PIUS, MHTGR). According to design and user's requirements for next generation water cooled reactor, the paper put forward a new concept about self safety U-ZrH reactor (SUR) which is able to solve the safety problems for water cooled reactor nuclear power plant and become a development direction for world water cooled reactor nuclear power plants. This type of reactor has been studied in NPIC (Nuclear Power Institute of China)

Comparison of the PHISICS/RELAP5-3D Ring and Block Model Results for Phase I of the OECD MHTGR-350 Benchmark

Energy Technology Data Exchange (ETDEWEB)

Gerhard Strydom

2014-04-01

The INL PHISICS code system consists of three modules providing improved core simulation capability: INSTANT (performing 3D nodal transport core calculations), MRTAU (depletion and decay heat generation) and a perturbation/mixer module. Coupling of the PHISICS code suite to the thermal hydraulics system code RELAP5-3D has recently been finalized, and as part of the code verification and validation program the exercises defined for Phase I of the OECD/NEA MHTGR 350 MW Benchmark were completed. This paper provides an overview of the MHTGR Benchmark, and presents selected results of the three steady state exercises 1-3 defined for Phase I. For Exercise 1, a stand-alone steady-state neutronics solution for an End of Equilibrium Cycle Modular High Temperature Reactor (MHTGR) was calculated with INSTANT, using the provided geometry, material descriptions, and detailed cross-section libraries. Exercise 2 required the modeling of a stand-alone thermal fluids solution. The RELAP5-3D results of four sub-cases are discussed, consisting of various combinations of coolant bypass flows and material thermophysical properties. Exercise 3 combined the first two exercises in a coupled neutronics and thermal fluids solution, and the coupled code suite PHISICS/RELAP5-3D was used to calculate the results of two sub-cases. The main focus of the paper is a comparison of the traditional RELAP5-3D “ring” model approach vs. a much more detailed model that include kinetics feedback on individual block level and thermal feedbacks on a triangular sub-mesh. The higher fidelity of the block model is illustrated with comparison results on the temperature, power density and flux distributions, and the typical under-predictions produced by the ring model approach are highlighted.

Innovative safety features of the modular HTGR

International Nuclear Information System (INIS)

Silady, F.A.; Simon, W.A.

1992-01-01

The Modular High Temperature Gas-Cooled Reactor (MHTGR) is an advanced reactor concept under development through a cooperative program involving the US Government, the nuclear industry, and the utilities. Near-term development is focused on electricity generation. The top-level safety requirement is that the plant's operation not disturb the normal day-to-day activities of the public. Quantitatively, this requires that the design meet the US Environmental Protection Agency's Protective Action Guides at the site boundary and hence preclude the need for sheltering or evacuation of the public. To meet these stringent safety requirements and at the same time provide a cost competitive design requires the innovative use of the basic high temperature gas-cooled reactor features of ceramic fuel, helium coolant, and a graphite moderator. The specific fuel composition and core size and configuration have been selected to the use the natural characteristics of these materials to develop significantly higher margins of safety. In this document the innovative safety features of the MHTGR are reviewed by examining the safety response to events challenging the functions relied on to retain radionuclides within the coated fuel particles. A broad range of challenges to core heat removal are examined, including a loss of helium pressure of a simultaneous loss of forced cooling of the core. The challenges to control of heat generation consider not only the failure to insert the reactivity control systems but also the withdrawal of control rods. Finally, challenges to control of chemical attack of the ceramic-coated fuel are considered, including catastrophic failure of the steam generator, which allows water ingress, or failure of the pressure vessels, which allows air ingress. The plant's response to these extreme challenges is not dependent on operator action, and the events considered encompass conceivable operator errors

New Multi-group Transport Neutronics (PHISICS) Capabilities for RELAP5-3D and its Application to Phase I of the OECD/NEA MHTGR-350 MW Benchmark

Energy Technology Data Exchange (ETDEWEB)

Gerhard Strydom; Cristian Rabiti; Andrea Alfonsi

2012-10-01

PHISICS is a neutronics code system currently under development at the Idaho National Laboratory (INL). Its goal is to provide state of the art simulation capability to reactor designers. The different modules for PHISICS currently under development are a nodal and semi-structured transport core solver (INSTANT), a depletion module (MRTAU) and a cross section interpolation (MIXER) module. The INSTANT module is the most developed of the mentioned above. Basic functionalities are ready to use, but the code is still in continuous development to extend its capabilities. This paper reports on the effort of coupling the nodal kinetics code package PHISICS (INSTANT/MRTAU/MIXER) to the thermal hydraulics system code RELAP5-3D, to enable full core and system modeling. This will enable the possibility to model coupled (thermal-hydraulics and neutronics) problems with more options for 3D neutron kinetics, compared to the existing diffusion theory neutron kinetics module in RELAP5-3D (NESTLE). In the second part of the paper, an overview of the OECD/NEA MHTGR-350 MW benchmark is given. This benchmark has been approved by the OECD, and is based on the General Atomics 350 MW Modular High Temperature Gas Reactor (MHTGR) design. The benchmark includes coupled neutronics thermal hydraulics exercises that require more capabilities than RELAP5-3D with NESTLE offers. Therefore, the MHTGR benchmark makes extensive use of the new PHISICS/RELAP5-3D coupling capabilities. The paper presents the preliminary results of the three steady state exercises specified in Phase I of the benchmark using PHISICS/RELAP5-3D.

Preliminary safety information document for the standard MHTGR. Volume 4

Energy Technology Data Exchange (ETDEWEB)

None

1986-01-01

This report contains information concerning: operational radionuclide control; occupational radiation protection, conduct of operations; initial test program; safety analysis; technical specifications; and quality assurance. (JDB)

41 CFR 101-26.4901-149 - Standard Form 149, U.S. Government National Credit Card.

Science.gov (United States)

2010-07-01

... 41 Public Contracts and Property Management 2 2010-07-01 2010-07-01 true Standard Form 149, U.S. Government National Credit Card. 101-26.4901-149 Section 101-26.4901-149 Public Contracts and Property... 149, U.S. Government National Credit Card. Note: The form illustrated in § 101-26.4901-149 is filed as...

Nonlinear Power-Level Control of the MHTGR Only with the Feedback Loop of Helium Temperature

Directory of Open Access Journals (Sweden)

Zhe Dong

2013-02-01

Full Text Available Power-level control is a crucial technique for the safe, stable and efficient operation of modular high temperature gas-cooled nuclear reactors (MHTGRs, which have strong inherent safety features and high outlet temperatures. The current power-level controllers of the MHTGRs need measurements of both the nuclear power and the helium temperature, which cannot provide satisfactory control performance and can even induce large oscillations when the neutron sensors are in error. In order to improve the fault tolerance of the control system, it is important to develop a power-level control strategy that only requires the helium temperature. The basis for developing this kind of control law is to give a state-observer of the MHTGR a relationship that only needs the measurement of helium temperature. With this in mind, a novel nonlinear state observer which only needs the measurement of helium temperature is proposed. This observer is globally convergent if there is no disturbance, and has the L2 disturbance attenuation performance if the disturbance is nonzero. The separation principle of this observer is also proven, which denotes that this observer can recover the performance of both globally asymptotic stabilizers and L2 disturbance attenuators. Then, a new dynamic output feedback power-level control strategy is established, which is composed of this observer and the well-built static state-feedback power-level control based upon iterative dissipation assignment (IDA-PLC. Finally, numerical simulation results show the high performance and feasibility of this newly-built dynamic output feedback power-level controller.

Coupling of Modular High-Temperature Gas-Cooled Reactor with Supercritical Rankine Cycle

Directory of Open Access Journals (Sweden)

Shutang Zhu

2008-01-01

Full Text Available This paper presents investigations on the possible combination of modular high-temperature gas-cooled reactor (MHTGR technology with the supercritical (SC steam turbine technology and the prospective deployments of the MHTGR SC power plant. Energy conversion efficiency of steam turbine cycle can be improved by increasing the main steam pressure and temperature. Investigations on SC water reactor (SCWR reveal that the development of SCWR power plants still needs further research and development. The MHTGR SC plant coupling the existing technologies of current MHTGR module design with operation experiences of SC FPP will achieve high cycle efficiency in addition to its inherent safety. The standard once-reheat SC steam turbine cycle and the once-reheat steam cycle with life-steam have been studied and corresponding parameters were computed. Efficiencies of thermodynamic processes of MHTGR SC plants were analyzed, while comparisons were made between an MHTGR SC plant and a designed advanced passive PWR - AP1000. It was shown that the net plant efficiency of an MHTGR SC plant can reach 45% or above, 30% higher than that of AP1000 (35% net efficiency. Furthermore, an MHTGR SC plant has higher environmental competitiveness without emission of greenhouse gases and other pollutants.

workplace safety management as correlates of wellbeing among

African Journals Online (AJOL)

User

2017-12-28

Dec 28, 2017 ... workers safety training (r=.062, p>.05), design of equipment (r= -.03, p>.05) and ... approach to safety and health issues by members of organization (Supervisors, ... Based Maintenance TBM); the basic elementary tasks of collecting ... statutory practice and structures for inspecting the safety condition of ...

17 CFR 149.102 - Application.

Science.gov (United States)

2010-04-01

... 17 Commodity and Securities Exchanges 1 2010-04-01 2010-04-01 false Application. 149.102 Section 149.102 Commodity and Securities Exchanges COMMODITY FUTURES TRADING COMMISSION ENFORCEMENT OF... COMMISSION § 149.102 Application. This part applies to all programs or activities conducted by the agency. ...

Level structure of 149Nd. The decay of 149Pr

International Nuclear Information System (INIS)

Pinston, J.A.; Roussille, R.; Sadler, G.; Tenten, W.; Bocquet, J.P.; Pfeiffer, B.; Warner, D.D.

1977-01-01

The decay of 149 Pr (Tsub(1/2) = 2.2 min) has been studied using the two fission product separators JOSEF and LOHENGRIN to produce the 149 Pr nucleus. A level scheme for 149 Nd has been established. The β-branching of log ft values for the excited levels were deduced from the analysis of γ-intensity balances. Furthermore, the spins and parities for most of the excited states observed were obtained from the comparison between the present work, the neutron capture results and the pick-up reactions. The positive parity levels have been described with the Nilsson model with Coriolis and ΔN = 2 interactions included. The properties of the negative parity states cannot be explained as easily; however, it has been attempted to extract the structure of the ground state and the first excited states. (orig.) [de

CANDU Safety R&D Status, Challenges, and Prospects in Canada

Directory of Open Access Journals (Sweden)

W. Shen

2015-01-01

Full Text Available In Canada, safe operation of CANDU (CANada Deuterium Uranium; it is a registered trademark of Atomic Energy of Canada Limited reactors is supported by a full-scope program of nuclear safety research and development (R&D in key technical areas. Key nuclear R&D programs, facilities, and expertise are maintained in order to address the unique features of the CANDU as well as generic technology areas common to CANDU and LWR (light water reactor. This paper presents an overview of the CANDU safety R&D which includes background, drivers, current status, challenges, and future directions. This overview of the Canadian nuclear safety R&D programs includes those currently conducted by the COG (CANDU Owners Group, AECL (Atomic Energy of Canada Limited, Candu Energy Inc., and the CNSC (Canadian Nuclear Safety Commission and by universities via UNENE (University Network of Excellence in Nuclear Engineering sponsorship. In particular, the nuclear safety R&D program related to the emerging CANDU ageing issues is discussed. The paper concludes by identifying directions for the future nuclear safety R&D.

Self-stability analysis of MHTGRs: A shifted-ectropy based approach

International Nuclear Information System (INIS)

Dong Zhe

2012-01-01

Highlights: ► In this paper, self-stability of the MHTGR is analyzed from a physical viewpoint. ► A shifted-ectropy method for self-stability analysis of general thermodynamic systems is established. ► Then it is proved theoretically that the equilibriums of the MHTGR are globally asymptotically stable. ► Numerical verification results are consistent with the theoretical result. - Abstract: Because of the strong inherent safety, the modular high temperature gas-cooled nuclear reactor (MHTGR) has been seen as the chosen technology for the next generation of nuclear power plants (NPPs). Self-stability of a nuclear reactor, which is the ability that the reactor state can converge to an equilibrium point without control input, has great meaning in designing control and operation strategies for the NPPs based on MHTGR technology. In this paper, self-stability of the MHTGR is analyzed from a physical viewpoint. A shifted-ectropy method for analyzing the stability of the equilibriums of general thermodynamic systems is firstly established. Based upon this approach, it is proved theoretically that the equilibriums of the MHTGR dynamics are globally asymptotically stable. Numerical simulation results, which illustrate the MHTGR self-stability feature directly, are consistent with the theoretical result.

9 CFR 149.4 - Spot audit.

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2010-01-01

... 9 Animals and Animal Products 1 2010-01-01 2010-01-01 false Spot audit. 149.4 Section 149.4... LIVESTOCK IMPROVEMENT VOLUNTARY TRICHINAE CERTIFICATION PROGRAM § 149.4 Spot audit. (a) In addition to regularly scheduled site audits, certified production sites will be subject to spot audits. (1) Random spot...

9 CFR 149.3 - Site audit.

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2010-01-01

... 9 Animals and Animal Products 1 2010-01-01 2010-01-01 false Site audit. 149.3 Section 149.3... LIVESTOCK IMPROVEMENT VOLUNTARY TRICHINAE CERTIFICATION PROGRAM § 149.3 Site audit. (a) General. (1) The producer must contact a QAV or QVMO to request a site audit. A list of available QAVs may be obtained by...

17 CFR 149.140 - Employment.

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2010-04-01

... 17 Commodity and Securities Exchanges 1 2010-04-01 2010-04-01 false Employment. 149.140 Section... COMMISSION § 149.140 Employment. No qualified handicapped person shall, on the basis of handicap, be subjected to discrimination in employment under any program or activity conducted by the agency. The...

45 CFR 149.300 - General reimbursement rules.

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2010-10-01

... 45 Public Welfare 1 2010-10-01 2010-10-01 false General reimbursement rules. 149.300 Section 149... REQUIREMENTS FOR THE EARLY RETIREE REINSURANCE PROGRAM Reimbursement Methods § 149.300 General reimbursement rules. Reimbursement under this program is conditioned on provision of accurate information by the...

45 CFR 149.200 - Use of reimbursements.

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2010-10-01

... 45 Public Welfare 1 2010-10-01 2010-10-01 false Use of reimbursements. 149.200 Section 149.200 Public Welfare DEPARTMENT OF HEALTH AND HUMAN SERVICES REQUIREMENTS RELATING TO HEALTH CARE ACCESS REQUIREMENTS FOR THE EARLY RETIREE REINSURANCE PROGRAM Use of Reimbursements § 149.200 Use of reimbursements...

Future Development of Modular HTGR in China after HTR-PM

International Nuclear Information System (INIS)

Zhang Zuoyi; Wang, Haitao; Dong Yujie; Li Fu

2014-01-01

The modular high temperature gas-cooled reactor (MHTGR) is an inherently safe nuclear energy technology for efficient electricity generation and process heat applications. The MHTGR is promising in China as it may replace fossil fuels in broader energy markets. In line with China’s long-term development plan of nuclear power, the Institute of Nuclear and New Energy Technology (INET) of Tsinghua University developed and designed a MHTGR demonstration plant, named high-temperature gas-cooled reactor-pebble bed module (HTR-PM). The HTR-PM came into the construction phase at the end of 2012. The HTR-PM aims to demonstrate safety, economic potential and modularization technologies towards future commercial applications. Based on experiences obtained from the HTR-PM project with respect to design, manufacture, construction, licensing and project management, a further step aiming to promote commercialization and market applications of the MHTGR is expected. To this purpose, INET is developing a commercialized MHTGR named HTR-PM600 and a conceptual design is under way accordingly. HTR-PM600 is a pebble-bed MHTGR power generation unit with a six-pack of 250MWth reactor modules. The objective is to cogenerate electricity and process heat flexibly and economically in order to meet a variety of market needs. The design of HTR-PM600 closely follows HTR-PM with respect to safety features, system configuration and plant layout. HTR-PM600 has the six modules feeding one steam turbine to generate electricity with capacity to extract high temperature steam from various interfaces of the turbine for further process heat applications. A standard plant consists of two HTR-PM600 units. Based on the economic information of HTR-PM, a preliminary study is carried out on the economic prospect of HTR-PM600. (author)

High temperature gas cooled reactors in China

International Nuclear Information System (INIS)

He Jiachen; Qian Jihui

1989-01-01

China has plentiful energy resources, but it is unevenly distributed geographically. 60% of coal resources are concentrated in North China, 71% of hydro-power resources in the hardly accessible Southwest China, whereas the densely populated and highly industrialized 15 provinces/municipalities along the coast, yielding 73% of the gross national product, posses only 10% of national energy resources, which makes our railway system hard pressed. In fact, about 40% of the railway transport and 50% of the main waterway transport are committed to fuel. Yet the needs of energy in the coastal regions cannot be met. To develop nuclear power is a naturally expected approach to solving energy problems in China, particularly in the near term for the coastal regions, where the demand of electricity increases sharply and fuel transport from other regions is already tense. Chinese nuclear circle is interested in MHTGR due to the following reasons. 1. Small capacity of MHTGR is suitable for small power grid in certain areas. 2. Chinese manufacturers are able to provide whole package of conventional island of MHTGR nuclear power plant. 3. Multipurpose MHTGR is attractive for Chinese heavy industries. 4. MHTGR nuclear power plant can be built in suburbs due to inherent safety features. Regarding the users' requirements in China, it can be summarised as: 1. Mature technologies and easy to get license from nuclear safety authority. 2. Emergency zone as small as possible, even unnecessary. 3. 200-300 MWe size desirable. 4. Big portion of domestic share in engineering and component supply. 5. Slightly higher electricity price than coal fired. 6. Investment and favourable financing conditions from overseas. 7. Reimbursement of hard currency by countertrade. At present, four working groups, including users, manufacturers and nuclear industry circle, have been established for performing independent feasibility study on building MHTGR demonstration nuclear power plant in China. (author)

45 CFR 149.100 - Amount of reimbursement.

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2010-10-01

... 45 Public Welfare 1 2010-10-01 2010-10-01 false Amount of reimbursement. 149.100 Section 149.100... REQUIREMENTS FOR THE EARLY RETIREE REINSURANCE PROGRAM Reinsurance Amounts § 149.100 Amount of reimbursement... reimbursement in the amount of 80 percent of the costs for health benefits (net of negotiated price concessions...

27 CFR 28.149 - Losses.

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2010-04-01

... 27 Alcohol, Tobacco Products and Firearms 1 2010-04-01 2010-04-01 false Losses. 28.149 Section 28... Exportation, Use as Supplies on Vessels and Aircraft, or Transfer to a Foreign-Trade Zone § 28.149 Losses. When there has been a loss of beer or beer concentrate while in transit from the brewery to a port for...

40 CFR 1.49 - Office of Water.

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2010-07-01

... 40 Protection of Environment 1 2010-07-01 2010-07-01 false Office of Water. 1.49 Section 1.49... INFORMATION Headquarters § 1.49 Office of Water. The Office of Water, under the supervision of the Assistant Administrator for Water who serves as the principal adviser to the Administrator in matters pertaining to water...

28 CFR 35.149 - Discrimination prohibited.

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2010-07-01

... 28 Judicial Administration 1 2010-07-01 2010-07-01 false Discrimination prohibited. 35.149 Section... STATE AND LOCAL GOVERNMENT SERVICES Program Accessibility § 35.149 Discrimination prohibited. Except as... subjected to discrimination by any public entity. ...

Non-CpG island promoter hypomethylation and miR-149 regulate the expression of SRPX2 in colorectal cancer

DEFF Research Database (Denmark)

Oster, Bodil; Linnet, Lene; Christensen, Lise Lotte

2012-01-01

Gene silencing by DNA hypermethylation of CpG islands is a well-characterized phenomenon in cancer. The effect of hypomethylation in particular of non-CpG island genes is much less well described. By genome-wide screening, we identified 105 genes in microsatellite stable (MSS) colorectal adenocar......Gene silencing by DNA hypermethylation of CpG islands is a well-characterized phenomenon in cancer. The effect of hypomethylation in particular of non-CpG island genes is much less well described. By genome-wide screening, we identified 105 genes in microsatellite stable (MSS) colorectal...... of non-CpG island-associated promoters deregulate gene expression nearly as frequent as do CpG-island hypermethylation. The hypomethylation of SRPX2 is focal and not part of a large block. Furthermore, it often translates to an increased expression level, which may be modulated by miR-149....

Short and long-term safety of the 2009 AS03-adjuvanted pandemic vaccine.

Directory of Open Access Journals (Sweden)

Gaston De Serres

Full Text Available This study assessed the short and the long term safety of the 2009 AS03 adjuvanted monovalent pandemic vaccine through an active web-based electronic surveillance. We compared its safety profile to that of the seasonal trivalent inactivated influenza vaccine (TIV for 2010-2011.Health care workers (HCW vaccinated in 2009 with the pandemic vaccine (Arepanrix ® from GSK or HCW vaccinated in 2010 with the 2010-2011 TIV were invited to participate in a web-based active surveillance of vaccine safety. They completed two surveys the day-8 survey covered the first 7 days post-vaccination and the day-29 survey covered events occurring 8 to 28 days after vaccination. Those who reported a problem were called by a nurse to obtain details. The main outcome was the occurrence of a new health problem or the worsening of an existing health condition that resulted in a medical consultation or work absenteeism. For the pandemic vaccine, a six-month follow-up for the occurrence of serious adverse events (SAE was conducted. Among the 6242 HCW who received the pandemic vaccine, 440 (7% reported 468 events compared to 328 of the 7645 HCW (4.3% who reported 339 events after the seasonal vaccine. The 2009 pandemic vaccine was associated with significantly more local reactions than the 2010-2011 seasonal vaccine (1% vs. 0.03%, p<0.001. Paresthesia was reported by 7 HCW (0.1% after the pandemic vaccine but by none after the seasonal vaccine. For the pandemic vaccine, no clustering of SAE was found in the 6 month follow-up.The 2009 pandemic vaccine seems to have a good safety profile, similar to the 2010-2011 TIV, with the exception of local reactions. This surveillance was adequately powered to identify AE associated with an excess risk ≥1 per 1000 vaccinations but is insufficient to detect rare AE.ClinicalTrials.gov NCT01289418, NCT01318876.

45 CFR 2490.149 - Program accessibility: Discrimination prohibited.

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2010-10-01

.... 2490.149 Section 2490.149 Public Welfare Regulations Relating to Public Welfare (Continued) JAMES MADISON MEMORIAL FELLOWSHIP FOUNDATION ENFORCEMENT OF NONDISCRIMINATION ON THE BASIS OF HANDICAP IN PROGRAMS OR ACTIVITIES CONDUCTED BY THE JAMES MADISON MEMORIAL FELLOWSHIP FOUNDATION § 2490.149 Program...

19 CFR 201.149 - Program accessibility: Discrimination prohibited.

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2010-04-01

.... 201.149 Section 201.149 Customs Duties UNITED STATES INTERNATIONAL TRADE COMMISSION GENERAL RULES OF... Conducted by the U.S. International Trade Commission § 201.149 Program accessibility: Discrimination... agency's facilities are inaccessible to or unusable by handicapped persons, be denied the benefits of, be...

Folate Receptor Targeted Alpha-Therapy Using Terbium-149

CERN Document Server

Müller, Cristina; Haller, Stephanie; Dorrer, Holger; Köster, Ulli; Johnston, Karl; Zhernosekov, Konstantin; Türler, Andreas; Schibli, Roger

2014-01-01

Terbium-149 is among the most interesting therapeutic nuclides for medical applications. It decays by emission of short-range α-particles (Eα = 3.967 MeV) with a half-life of 4.12 h. The goal of this study was to investigate the anticancer efficacy of a 149Tb-labeled DOTA-folate conjugate (cm09) using folate receptor (FR)-positive cancer cells in vitro and in tumor-bearing mice. 149Tb was produced at the ISOLDE facility at CERN. Radiolabeling of cm09 with purified 149Tb resulted in a specific activity of ~1.2 MBq/nmol. In vitro assays performed with 149Tb-cm09 revealed a reduced KB cell viability in a FR-specific and activity concentration-dependent manner. Tumor-bearing mice were injected with saline only (group A) or with 149Tb-cm09 (group B: 2.2 MBq; group C: 3.0 MBq). A significant tumor growth delay was found in treated animals resulting in an increased average survival time of mice which received 149Tb-cm09 (B: 30.5 d; C: 43 d) compared to untreated controls (A: 21 d). Analysis of blood parameters rev...

Software Project Management Plan for the Integrated Systems Code (ISC) of New Production Reactor -- Modular High Temperature Gas Reactor

International Nuclear Information System (INIS)

Taylor, D.

1990-11-01

The United States Department of Energy (DOE) has selected the Modular High Temperature Gas-Cooled Reactor (MHTGR) as one of the concepts for the New Production Reactor (NPR). DOE has also established several Technical Working Groups (TWG's) at the national laboratories to provide independent design confirmation of the NPR-MHTGR design. One of those TWG's is concerned with Thermal Fluid Flow (TFF) and analysis methods to provide independent design confirmation of the NPR-MHTGR. Analysis methods are also needed for operational safety evaluations, performance monitoring, sensitivity studies, and operator training. The TFF Program Plan includes, as one of its principal tasks, the development of a computer program (called the Integrated Systems Code, or ISC). This program will provide the needed long-term analysis capabilities for the MHTGR and its subsystems. This document presents the project management plan for development of the ISC. It includes the associated quality assurance tasks, and the schedule and resource requirements to complete these activities. The document conforms to the format of ANSI/IEEE Std. 1058.1-1987. 2 figs

Description and exploitation of benchmarks involving 149Sm, a fission product taking part of the burn up credit in spent fuels

International Nuclear Information System (INIS)

Anno, J.; Poullot, G.

1995-01-01

Up to now, there was no benchmark to validate the Fission Products (FPs) cross sections in criticality safety calculations. The protection and nuclear safety institute (IPSN) has begun an experimental program on 6 FPs ( 103 Rh, 133 Cs, 143 Nd, 149 Sm, 152 Sm, and 155 Gd daughter of 155 Eu) giving alone a decrease of reactivity equal to half the whole FPs in spent fuels (except Xe and I). Here are presented the experiments with the 149 Sm and the results obtained with the APOLLO I-MORET III calculations codes. 11 experiments are carried out in a zircaloy tank of 3.5 1 containing slightly nitric acid solutions of Samarium (96,9% in weight of 149S m) at 0.1048 -0.2148 - 0.6262 g/l concentrations. It was placed in the middle of arrays of UO 2 rods (4.742 % U5 weight %) at square pitch of 13 mm. The underwater height of the rods is the critical parameter. In addition, 7 experiments were performed with the same apparatus with water and boron proving a good experimental representativeness and a good accuracy of the calculations. As the reactivity worth of the Sm tank is between 2000 and 6000 10 -5 , the benchmarks are well representative and the cumulative absorption ratios show that 149 Sm is well qualified under 1 eV. (authors). 8 refs., 7 figs., 6 tabs

41 CFR 51-10.149 - Program accessibility: Discrimination prohibited.

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2010-07-01

...: Discrimination prohibited. 51-10.149 Section 51-10.149 Public Contracts and Property Management Other Provisions Relating to Public Contracts COMMITTEE FOR PURCHASE FROM PEOPLE WHO ARE BLIND OR SEVERELY DISABLED 10... FOR PURCHASE FROM PEOPLE WHO ARE BLIND OR SEVERELY DISABLED § 51-10.149 Program accessibility...

Safety approach and R and D program for future french sodium-cooled fast reactors

International Nuclear Information System (INIS)

Beils, Stephane; Carluec, Bernard; Devictor, Nicolas; Fiorini, Gian Luigi; Sauvage, Jean Francois

2011-01-01

This paper presents briefly the safety approach as well as the R and D program that is underway to support the deployment of future French Sodium-Cooled fast Reactors (SFRs): A) Safety objectives and principles for future reactors. The content of the first section reflects the works of AREVA, CEA, and EDF concerning the safety orientations for the future reactors. The availability of such orientations and requirements for the SFRs has to allow introducing and managing the process that will lead to the detailed definition of the safety approach, to the selection of the corresponding safety options, and to the identification and motivation of the supporting R and D. B) Strategy and roadmap in support of the R and D for future SFRs. This section describes the R and D program led jointly by CEA, EDF, and AREVA, which has been developed with the objectives to be able to preliminarily define, by 2012, the safety orientations for the future SFRs, and to deduce from them the characteristics of the ASTRID prototype. (author)

Safety management of a complex R and D ground operating system

Science.gov (United States)

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

1975-01-01

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

Phenomena identification ranking table and knowledge base gaps and needs for the modular high-temperature gas-cooled reactor

International Nuclear Information System (INIS)

Tokuhiro, Akira; Potirniche, Gabriel; Rink, Karl

2009-01-01

The U.S. is developing a modular high-temperature gas-cooled reactor (MHTGR) under the Next Generation Nuclear Plant (NGNP); also known as the Very High Temperature Reactor (VHTR). The generic MHTGR is a graphite-moderated, gas-cooled reactor (GCR) of either a prismatic modular (block-type, PMR) or pebble-bed (PBR) core configuration. The pebble-bed design requires new attention with respect to neutronics, materials, thermal hydraulic, safety and licensing relative to the set of phenomena and engineering analyses associated with the current fleet of legacy LWRs. In fact, the relative knowledge and experiential base on gas reactors is small in comparison to the LWR. There is a dated body of knowledge from some 25+ years ago on GCRs; recently there is a renewed interest. Thus in the present design and development phase of the NGNP/VHTR, there are relevant thermohydraulic safety issues surrounding the MHTGR with issues impacting foremost the design review process. A common phenomena with respect to PMR and PBR core design, is that concerning 'graphite dust' and its interaction and transport with potential fission products (FP) that may be present within the graphite and subsequently in the primary system. The nature of the graphite and FPs, when circulated or transported in the primary, and possibly beyond, is of concern as potentially an relevant 'source term' (radionuclide inventory) of the MHTGR. Based on NUREG/CR-6944, Volumes 1-5, the author briefly describes the state-of-the art knowledge base on graphite dust and FP transport with respect to the anticipated design of the MHTGR. In addition, from the Phenomena Identification and Ranking Tables (PIRTs) developed in these reports we concurrently identify and describe 'gaps and needs' of the knowledge base. That is, we also present the knowledge base gaps and needs with respect to the following: 1) R and D needs relative to PIRTs, 2) (experimental) database needs relative to PIRTs, and 3) simulation and modeling

Safety evaluation of liquid radioactive effluents treatment system in a BWR reactor, through the LIQM03 code

International Nuclear Information System (INIS)

Zorrilla R, S.H.

1978-01-01

In this work we made a safety evaluation of the liquid radioactive effluents system in a plant using a BWR similar to that now installed in Laguna Verde. For that purpose, the computation program ORIGENwas modified, in order to keep up to date and adapt it to the PDP 10 computer, which is operating at the Computation Department of the Nuclear Center of Mexico, the code LIQM03 was the result of this modification. As usual in this work we dealt with problems which were solved opportunely, now we have at our disposal the code LIQM03 which will be in the future a very useful tool for this kind of evaluations. (author)

33 CFR 149.409 - How many fire extinguishers are needed?

Science.gov (United States)

2010-07-01

... 33 Navigation and Navigable Waters 2 2010-07-01 2010-07-01 false How many fire extinguishers are needed? 149.409 Section 149.409 Navigation and Navigable Waters COAST GUARD, DEPARTMENT OF HOMELAND... Fire Protection Equipment Firefighting Requirements § 149.409 How many fire extinguishers are needed...

Description and exploitation of benchmarks involving {sup 149}Sm, a fission product taking part of the burn up credit in spent fuels

Energy Technology Data Exchange (ETDEWEB)

Anno, J.; Poullot, G. [CEA Centre d`Etudes de Fontenay-aux-Roses, 92 (France). Inst. de Protection et de Surete Nucleaire; Fouillaud, P.; Grivot, P. [CEA Centre d`Etudes de Valduc, 21 - Is-sur-Tille (France)

1995-12-31

Up to now, there was no benchmark to validate the Fission Products (FPs) cross sections in criticality safety calculations. The protection and nuclear safety institute (IPSN) has begun an experimental program on 6 FPs ({sup 103}Rh, {sup 133}Cs, {sup 143}Nd, {sup 149}Sm, {sup 152}Sm, and {sup 155}Gd daughter of {sup 155}Eu) giving alone a decrease of reactivity equal to half the whole FPs in spent fuels (except Xe and I). Here are presented the experiments with the {sup 149}Sm and the results obtained with the APOLLO I-MORET III calculations codes. 11 experiments are carried out in a zircaloy tank of 3.5 1 containing slightly nitric acid solutions of Samarium (96,9% in weight of {sup 149S}m) at 0.1048 -0.2148 - 0.6262 g/l concentrations. It was placed in the middle of arrays of UO{sub 2} rods (4.742 % U5 weight %) at square pitch of 13 mm. The underwater height of the rods is the critical parameter. In addition, 7 experiments were performed with the same apparatus with water and boron proving a good experimental representativeness and a good accuracy of the calculations. As the reactivity worth of the Sm tank is between 2000 and 6000 10{sup -5}, the benchmarks are well representative and the cumulative absorption ratios show that {sup 149}Sm is well qualified under 1 eV. (authors). 8 refs., 7 figs., 6 tabs.

33 CFR 149.412 - How many fire axes are needed?

Science.gov (United States)

2010-07-01

... 33 Navigation and Navigable Waters 2 2010-07-01 2010-07-01 false How many fire axes are needed? 149.412 Section 149.412 Navigation and Navigable Waters COAST GUARD, DEPARTMENT OF HOMELAND SECURITY... Protection Equipment Firefighting Requirements § 149.412 How many fire axes are needed? Each manned deepwater...

Helium circulator design concepts for the modular high temperature gas-cooled reactor (MHTGR) plant

International Nuclear Information System (INIS)

McDonald, C.F.; Nichols, M.K.; Kaufman, J.S.

1988-01-01

Two helium circulators are featured in the Modular High-Temperature Gas-Cooled Reactor (MHTGR) power plant - (1) the main circulator, which facilitates the transfer of reactor thermal energy to the steam generator, and (2) a small shutdown cooling circulator that enables rapid cooling of the reactor system to be realized. The 3170 kW(e) main circulator has an axial flow compressor, the impeller being very similar to the unit in the Fort St. Vrain (FSV) plant. The 164 kW(e) shutdown cooling circulator, the design of which is controlled by depressurized conditions, has a radial flow compressor. Both machines are vertically oriented, have submerged electric motor drives, and embody rotors that are supported on active magnetic bearings. As outlined in this paper, both machines have been conservatively designed based on established practice. The circulators have features and characteristics that have evolved from actual plant operating experience. With a major goal of high reliability, emphasis has been placed on design simplicity, and both machines are readily accessible for inspection, repair, and replacement, if necessary. In this paper, conceptual design aspects of both machines are discussed, together with the significant technology bases. As appropriate for a plant that will see service well into the 21st century, new and emerging technologies have been factored into the design. Examples of this are the inclusion of active magnetic bearings, and an automated circulator condition monitoring system. (author). 18 refs, 20 figs, 13 tabs

Addressing safety liabilities of TfR bispecific antibodies that cross the blood-brain barrier.

Science.gov (United States)

Couch, Jessica A; Yu, Y Joy; Zhang, Yin; Tarrant, Jacqueline M; Fuji, Reina N; Meilandt, William J; Solanoy, Hilda; Tong, Raymond K; Hoyte, Kwame; Luk, Wilman; Lu, Yanmei; Gadkar, Kapil; Prabhu, Saileta; Ordonia, Benjamin A; Nguyen, Quyen; Lin, Yuwen; Lin, Zhonghua; Balazs, Mercedesz; Scearce-Levie, Kimberly; Ernst, James A; Dennis, Mark S; Watts, Ryan J

2013-05-01

Bispecific antibodies using the transferrin receptor (TfR) have shown promise for boosting antibody uptake in brain. Nevertheless, there are limited data on the therapeutic properties including safety liabilities that will enable successful development of TfR-based therapeutics. We evaluate TfR/BACE1 bispecific antibody variants in mouse and show that reducing TfR binding affinity improves not only brain uptake but also peripheral exposure and the safety profile of these antibodies. We identify and seek to address liabilities of targeting TfR with antibodies, namely, acute clinical signs and decreased circulating reticulocytes observed after dosing. By eliminating Fc effector function, we ameliorated the acute clinical signs and partially rescued a reduction in reticulocytes. Furthermore, we show that complement mediates a residual decrease in reticulocytes observed after Fc effector function is eliminated. These data raise important safety concerns and potential mitigation strategies for the development of TfR-based therapies that are designed to cross the blood-brain barrier.

12 CFR 410.149 - Program accessibility: Discrimination prohibited.

Science.gov (United States)

2010-01-01

... 12 Banks and Banking 4 2010-01-01 2010-01-01 false Program accessibility: Discrimination prohibited. 410.149 Section 410.149 Banks and Banking EXPORT-IMPORT BANK OF THE UNITED STATES ENFORCEMENT OF NONDISCRIMINATION ON THE BASIS OF HANDICAP IN PROGRAMS OR ACTIVITIES CONDUCTED BY EXPORT-IMPORT BANK OF THE UNITED...

7 CFR 1260.149 - Powers of the Board.

Science.gov (United States)

2010-01-01

... 7 Agriculture 10 2010-01-01 2010-01-01 false Powers of the Board. 1260.149 Section 1260.149 Agriculture Regulations of the Department of Agriculture (Continued) AGRICULTURAL MARKETING SERVICE (MARKETING... thereof, in any interest-bearing account or certificate of deposit of a bank that is a member of the...

Results of a study of innovative reactors. A report by a working group of the PINK PROGRAMME

Energy Technology Data Exchange (ETDEWEB)

Jehee, J N.T. [Netherlands Energy Research Foundation (ECN), Petten (Netherlands); Swanenburg de Veye, R J [Netherlands Energy Research Foundation (ECN), Petten (Netherlands); Bueno de Mesquita, K G [Hoogovens Technical Services, Ijmuiden (Netherlands); Eendebak, B T [Keuring van Electrotechnische Materialen NV, Arnhem (Netherlands); Mheen, W.A.G. van der [Keuring van Electrotechnische Materialen NV, Arnhem (Netherlands); Essen, D van [NUCON Nuclear Technology BV, Amsterdam (Netherlands); Lievense, K [NUCON Nuclear Technology BV, Amsterdam (Netherlands)

1993-07-01

In the opinion of the working group, the gas-cooled reactor modules, i.e. the MHTGR and the HTR-M, offer the highest degree of inherent safety. This view is based on the high thermal and chemical stability of coated fuel particles as well as helium coolant and the very high safety margin between core operating conditions and fuel failure limit. Despite the potential flammability of the graphite, it is impossible to envisage any credible accident scenario that could result in a major release of radioactive material to the reactor building or the environment. The HTR-M can be favourably distinguished from the MHTGR regarding its potential to cope with reactivity accidents. Thanks to the continuously refuelled core, inadvertent withdrawal of neutron absorber rods only creates a small increase in reactivity. (orig./HP).

Results of a study of innovative reactors. A report by a working group of the PINK PROGRAMME

International Nuclear Information System (INIS)

Jehee, J.N.T.; Swanenburg de Veye, R.J.; Bueno de Mesquita, K.G.; Eendebak, B.T.; Mheen, W.A.G. van der; Essen, D. van; Lievense, K.

1993-07-01

In the opinion of the working group, the gas-cooled reactor modules, i.e. the MHTGR and the HTR-M, offer the highest degree of inherent safety. This view is based on the high thermal and chemical stability of coated fuel particles as well as helium coolant and the very high safety margin between core operating conditions and fuel failure limit. Despite the potential flammability of the graphite, it is impossible to envisage any credible accident scenario that could result in a major release of radioactive material to the reactor building or the environment. The HTR-M can be favourably distinguished from the MHTGR regarding its potential to cope with reactivity accidents. Thanks to the continuously refuelled core, inadvertent withdrawal of neutron absorber rods only creates a small increase in reactivity. (orig./HP)

Fission product plateout and liftoff in the MHTGR primary system: A review

International Nuclear Information System (INIS)

Wichner, R.P.

1991-04-01

A review is presented of the technical basis for predicting radioactivity release resulting from depressurization of an MHTGR primary system. Consideration is restricted to so called dry events with no involvement of the steam system. The various types of deposition mechanisms effective for iodine, cesium, strontium, and silver are discussed in terms of their chemical characteristics and the nature of the materials in the primary system. Emphasis is given to iodine behavior, including means for estimating the quantity available for release, the types of plateout locations in the primary system, and the effect of dust on distribution and release. The behavior of fission products cesium, strontium, and silver in such accidents is presented qualitatively. A major part of the review deals with expected dust levels, types, and transport. Available information on the level and nature of dust in the HTGR primary system is reviewed. A summary is presented of dust deposition and liftoff mechanisms. It was concluded that recent approaches to dust liftoff modeling, based on turbulent burst concepts for removal from surfaces, probably offer advantages over the current shear ratio approach. This study concludes that iodine releases from dry depressurization events are likely to be extremely low, on the order of millicuries, due to a predictably low degree of chemical desorption, a low degree of dust liftoff, and a low involvement of iodine with dust. It was also concluded that deposition mechanisms controlling the distribution of fission product material in the primary system, and hence also controlling the degree of liftoff, depend strongly on the chemical nature of the individual elements. Therefore contrary to the current practice, both plateout and liftoff models should reflect those unique chemical and physical properties. 56 refs., 16 figs., 23 tabs

Progress of IRSN R&D on ITER Safety Assessment

Science.gov (United States)

Van Dorsselaere, J. P.; Perrault, D.; Barrachin, M.; Bentaib, A.; Gensdarmes, F.; Haeck, W.; Pouvreau, S.; Salat, E.; Seropian, C.; Vendel, J.

2012-08-01

The French "Institut de Radioprotection et de Sûreté Nucléaire" (IRSN), in support to the French "Autorité de Sûreté Nucléaire", is analysing the safety of ITER fusion installation on the basis of the ITER operator's safety file. IRSN set up a multi-year R&D program in 2007 to support this safety assessment process. Priority has been given to four technical issues and the main outcomes of the work done in 2010 and 2011 are summarized in this paper: for simulation of accident scenarios in the vacuum vessel, adaptation of the ASTEC system code; for risk of explosion of gas-dust mixtures in the vacuum vessel, adaptation of the TONUS-CFD code for gas distribution, development of DUST code for dust transport, and preparation of IRSN experiments on gas inerting, dust mobilization, and hydrogen-dust mixtures explosion; for evaluation of the efficiency of the detritiation systems, thermo-chemical calculations of tritium speciation during transport in the gas phase and preparation of future experiments to evaluate the most influent factors on detritiation; for material neutron activation, adaptation of the VESTA Monte Carlo depletion code. The first results of these tasks have been used in 2011 for the analysis of the ITER safety file. In the near future, this R&D global programme may be reoriented to account for the feedback of the latter analysis or for new knowledge.

Utility/user requirements for the modular high temperature gas-cooled reactor

International Nuclear Information System (INIS)

Boyer, V.S.; Kendall, J.M.; Gotschall, H.L.

1989-01-01

This paper describes the approach used by Gas-Cooled Reactor Associates (GCRA) in developing Utility/User Requirements for the Modular High Temperature Gas-cooled Reactor (MHTGR). As representatives of the Utility/User industry, it is GCRA's goal that the MHTGR concept be established as an attractive nuclear option offering competitive economics and limited ownership risks. Commercially deployed MHTGR systems should then compete favorably in a mixed-fuel economy with options using fossil, other nuclear and other non-fossil sources. To achieve this goal, the design of the MHTGR plant must address the problems experienced by the U.S. industrial infrastructure during deployment of the first generation of nuclear plants. Indeed, it is GCRA's intent to utilize the characteristics of MHTGR technology for the development of a nuclear alternative that poses regulatory, financial and operational demands on the Owner/Operator that are, in aggregate, comparable to those encountered with non-nuclear options. The dominant risks faced by U.S. Utilities with current nuclear plants derive from their operational complexity and the degree of regulatory involvement in virtually all aspects of utility operations. The MHTGR approach of using ceramic fuel coatings to contain fission products provides the technical basis for simplification of the plant and stabilization of licensing requirements and thus the opportunity for reducing the risks of nuclear plant ownership. The paper describes the rationale for the selection of key requirements for public safety, plant size and performance, operations and maintenance, investment protection, economics and siting in the context of a risk management philosophy. It also describes the ongoing participation of the Utility/User in interpreting requirements, conducting program and design reviews and establishing priorities from the Owner/Operator perspective. (author). 7 refs, 1 fig

Safety management of a complex R&D ground operating system

Science.gov (United States)

Connors, J.; Mauer, R. A.

1975-01-01

Report discusses safety program implementation for large R&D operating system. Analytical techniques are defined and suggested as tools for identifying potential hazards and determining means to effectively control or eliminate hazards.

Inherent safety characteristics of innovative reactors

International Nuclear Information System (INIS)

Heil, J.A.

1995-11-01

The added safety value of innovative or third generation reactor designs has been evaluated in order to determine the most suitable candidate for Dutch government funded research and development support. To this end, four innovative reactor concepts, viz. PIUS (Process Inherent Ultimate Safety), PRISM (Power Reactor Innovative Small), HTR-M (High Temperature Reactor Module) and MHTGR (Modular High Temperature Gas-cooled Reactor), have been studied and their passive and inherent safety characteristics have been outlined. Also the outlook for further technological and industrial development has been considered. The results of the study confirm the perspective of the innovative reactors for reduced dependence on active safety provisions and for a further reduced vulnerability to technical failures and human errors. The accident responses to generic accident initiators, viz. reactivity and cooling accidents, and also to reactor specific accidents show that neither active safety systems nor short term operator actions are required for maintaining the reactor core in a controlled and coolable condition. Whether this gives rise to a higher total safety of the innovative reactor designs, compared to evolutionary or advanced reactors, cannot be concluded. Supplementary experimental and analytical analyses of reactor specific accidents are required to be able to assess the safety of these innovative designs in a more quantitative manner. It is believed that the safety case of innovative reactors, which are less dependent on active safety systems, can be communicated with the general public in a more transparent way. Considering the perspective for further technological and industrial development it is not expected that any of the considered innovative reactor concepts will become commercially available within the next one to two decades. However, they could be made available earlier if they would receive sufficient financial backing. Considering the added safety perspectives

40 CFR 61.149 - Standard for waste disposal for asbestos mills.

Science.gov (United States)

2010-07-01

... 40 Protection of Environment 8 2010-07-01 2010-07-01 false Standard for waste disposal for asbestos mills. 61.149 Section 61.149 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED... Standard for Asbestos § 61.149 Standard for waste disposal for asbestos mills. Each owner or operator of...

45 CFR 149.320 - Universe of claims that must be submitted.

Science.gov (United States)

2010-10-01

... 45 Public Welfare 1 2010-10-01 2010-10-01 false Universe of claims that must be submitted. 149.320 Section 149.320 Public Welfare DEPARTMENT OF HEALTH AND HUMAN SERVICES REQUIREMENTS RELATING TO HEALTH... Universe of claims that must be submitted. (a) Claims submitted for an early retiree, as defined in § 149.2...

Safety and Efficacy of an Artificial Tear Containing 0.3% Hyaluronic Acid in the Management of Moderate-to-Severe Dry Eye Disease.

Science.gov (United States)

López-de la Rosa, Alberto; Pinto-Fraga, José; Blázquez Arauzo, Francisco; Urbano Rodríguez, Rubén; González-García, María J

2017-11-01

To evaluate the safety and efficacy of a new 0.3% hyaluronic acid artificial tear compared with 0.9% saline solution (0.9% NaCl) in moderate-to-severe dry eye patients after 1 month's use. A total of 16 patients with moderate-to-severe dry eye were included in this crossover study. After a 1-week washout period, patients used the experimental (Visaid 0.3%) or control solution (0.9% NaCl), selected randomly, applying three to eight drops daily for a month. After another washout period, patients used the other solution in the same way. Percentage of change (ΔY) was calculated and analyzed for (1) safety variables: visual acuity, intraocular pressure, and ophthalmoscopy evaluation; (2) efficacy variable: Ocular Surface Disease Index (OSDI) questionnaire; and (3) secondary variables: biomicroscopy findings, fluorescein corneal staining, lissamine green conjunctival staining, tear breakup time (TBUT), contrast sensitivity, Schirmer test, and subject satisfaction. There were no significant differences in the safety parameters for either solution. After using Visaid 0.3%, patients showed significant improvements in OSDI score (ΔY: -9.66%±10.90), tarsal hyperemia (ΔY: -16.67%±27.89), corneal staining extension (ΔY: -34.90%±42.41), TBUT (ΔY: 13.98%±26.19), and subjective satisfaction (ΔY: 38.06%±47.06). When using 0.9% NaCl, Schirmer test results were significantly worse (ΔY: -11.47%±19.27). A significant difference between the 2 solutions was found in TBUT (ΔY: 13.98%±26.19 vs. 10.15%±42.34, respectively; P=0.0214). Visaid 0.3% is a safe product with some benefits over 0.9% NaCl in reducing ocular symptoms and improving some ocular signs in patients with moderate-to-severe dry eye.

R&D Challenges for SFR Design and Safety Analysis – Opportunities for International Cooperations

International Nuclear Information System (INIS)

Devictor, Nicolas

2013-01-01

Examples of R&D challenges related to safety have been presented. For any domain, R&D activities includes modelling, codes development and their V&V process, with the support of experimental programs. The success in the R&D will help the safety case and the acceptability of SFR. Some of these activities are relevant for international cooperation especially benchmarks and sharing of experimental facilities. This last point could take benefit of recent catalogues experimental facilities (already operational or in project), for example from the TAREF Task Force of OECD/NEA and the European project ADRIANA

34 CFR 300.149 - SEA responsibility for general supervision.

Science.gov (United States)

2010-07-01

... 34 Education 2 2010-07-01 2010-07-01 false SEA responsibility for general supervision. 300.149 Section 300.149 Education Regulations of the Offices of the Department of Education (Continued) OFFICE OF SPECIAL EDUCATION AND REHABILITATIVE SERVICES, DEPARTMENT OF EDUCATION ASSISTANCE TO STATES FOR THE EDUCATION OF CHILDREN WITH DISABILITIES State...

33 CFR 149.655 - What are the requirements for helicopter fueling facilities?

Science.gov (United States)

2010-07-01

... helicopter fueling facilities? 149.655 Section 149.655 Navigation and Navigable Waters COAST GUARD... EQUIPMENT Design and Equipment Helicopter Fueling Facilities § 149.655 What are the requirements for helicopter fueling facilities? Helicopter fueling facilities must comply with 46 CFR 108.489 or an equivalent...

27 CFR 24.149 - Corporate surety.

Science.gov (United States)

2010-04-01

... OF THE TREASURY LIQUORS WINE Establishment and Operations Bonds and Consents of Surety § 24.149.... Copies may be obtained from the Audit Staff, Financial Management Service, Department of the Treasury...

33 CFR 149.323 - What are the requirements for first aid kits?

Science.gov (United States)

2010-07-01

... first aid kits? 149.323 Section 149.323 Navigation and Navigable Waters COAST GUARD, DEPARTMENT OF... Lifesaving Equipment Manned Deepwater Port Requirements § 149.323 What are the requirements for first aid kits? (a) Each manned deepwater port must have an industrial first aid kit, approved by an appropriate...

45 CFR 149.41 - Consequences of Non-Compliance, Fraud, or Similar Fault.

Science.gov (United States)

2010-10-01

... Fault. 149.41 Section 149.41 Public Welfare DEPARTMENT OF HEALTH AND HUMAN SERVICES REQUIREMENTS... Eligible Employment-Based Plans § 149.41 Consequences of Non-Compliance, Fraud, or Similar Fault. Upon failure to comply with the requirements of this part, or if fraud, waste, and abuse, or similar fault are...

7 CFR 762.149 - Liquidation.

Science.gov (United States)

2010-01-01

... for judgment; (A) If the borrower has converted loan security, the lender will determine whether... of the disposition of loan security and its proceeds; (iii) A copy of the loan ledger indicating loan... SPECIAL PROGRAMS GUARANTEED FARM LOANS § 762.149 Liquidation. (a) Mediation. When it has been determined...

33 CFR 149.580 - What are the requirements for a radar beacon?

Science.gov (United States)

2010-07-01

... 33 Navigation and Navigable Waters 2 2010-07-01 2010-07-01 false What are the requirements for a radar beacon? 149.580 Section 149.580 Navigation and Navigable Waters COAST GUARD, DEPARTMENT OF... Navigation Miscellaneous § 149.580 What are the requirements for a radar beacon? (a) A radar beacon (RACON...

Dispersion of carbon nanotubes for application in cement composites

Czech Academy of Sciences Publication Activity Database

Foldyna, Josef; Foldyna, Vladimír; Zeleňák, Michal

2016-01-01

Roč. 149, č. 149 (2016), s. 94-99 E-ISSN 1877-7058 R&D Projects: GA MŠk(CZ) LO1406; GA MŠk ED2.1.00/03.0082; GA ČR GA15-23219S Institutional support: RVO:68145535 Keywords : carbon nanotubes * dispersion * sonication * pulsating water jet * impact pressure Subject RIV: JQ - Machines ; Tools http://www. science direct.com/ science /article/pii/S1877705816311511

Dispersion of carbon nanotubes for application in cement composites

Czech Academy of Sciences Publication Activity Database

Foldyna, Josef; Foldyna, Vladimír; Zeleňák, Michal

2016-01-01

Roč. 149, č. 149 (2016), s. 94-99 E-ISSN 1877-7058 R&D Projects: GA MŠk(CZ) LO1406; GA MŠk ED2.1.00/03.0082; GA ČR GA15-23219S Institutional support: RVO:68145535 Keywords : carbon nanotubes * dispersion * sonication * pulsating water jet * impact pressure Subject RIV: JQ - Machines ; Tools http://www.sciencedirect.com/science/article/pii/S1877705816311511

Development of a detailed core flow analysis code for prismatic fuel reactors

International Nuclear Information System (INIS)

Bennett, R.G.

1990-01-01

The detailed analysis of the core flow distribution in prismatic fuel reactors is of interest for modular high-temperature gas-cooled reactor (MHTGR) design and safety analyses. Such analyses involve the steady-state flow of helium through highly cross-connected flow paths in and around the prismatic fuel elements. Several computer codes have been developed for this purpose. However, since they are proprietary codes, they are not generally available for independent MHTGR design confirmation. The previously developed codes do not consider the exchange or diversion of flow between individual bypass gaps with much detail. Such a capability could be important in the analysis of potential fuel block motion, such as occurred in the Fort St. Vrain reactor, or for the analysis of the conditions around a flow blockage or misloaded fuel block. This work develops a computer code with fairly general-purpose capabilities for modeling the flow in regions of prismatic fuel cores. The code, called BYPASS solves a finite difference control volume formulation of the compressible, steady-state fluid flow in highly cross-connected flow paths typical of the MHTGR

25 CFR 170.149 - How do tribes identify transit needs?

Science.gov (United States)

2010-04-01

... 25 Indians 1 2010-04-01 2010-04-01 false How do tribes identify transit needs? 170.149 Section 170... ROADS PROGRAM Indian Reservation Roads Program Policy and Eligibility Transit Facilities § 170.149 How do tribes identify transit needs? Tribes identify transit needs during the tribal transportation...

A review of reactor physics uncertainties and validation requirements for the modular high-temperature gas-cooled reactor

International Nuclear Information System (INIS)

Baxter, A.M.; Lane, R.K.; Hettergott, E.; Lefler, W.

1991-01-01

The important, safety-related, physics parameters for the low-enriched Modular High-Temperature gas-Cooled Reactor (MHTGR) such as control rod worth, shutdown margins, temperature coefficients, and reactivity worths, are considered, and estimates are presented of the uncertainties in the calculated values of these parameters. The basis for the uncertainty estimate in several of the important calculated parameters is reviewed, including the available experimental data used in obtaining these estimates. Based on this review, the additional experimental data needed to complete the validation of the methods used to calculate these parameters is presented. The role of benchmark calculations in validating MHTGR reactor physics data is also considered. (author). 10 refs, 5 figs, 3 tabs

45 CFR 149.610 - Secretary's authority to reopen and revise a reimbursement determination.

Science.gov (United States)

2010-10-01

... reimbursement determination. 149.610 Section 149.610 Public Welfare DEPARTMENT OF HEALTH AND HUMAN SERVICES... of Data Inaccuracies § 149.610 Secretary's authority to reopen and revise a reimbursement determination. (a) The Secretary may reopen and revise a reimbursement determination upon the Secretary's own...

European BWR R and D cluster for innovative passive safety systems

International Nuclear Information System (INIS)

Hicken, E.F.; Lensa, W. von

1996-01-01

The main technological innovation trends for future nuclear power plants tend towards a broader use of passive safety systems for the prevention, mitigation and managing of severe accident scenarios. Several approaches have been undertaken in a number of European countries to study and demonstrate the feasibility and charateristics of innovative passive safety systems. The European BWR R and D Cluster combines those experimental and analytical efforts that are mainly directed to the introduction of passive safety systems into boiling water reactor technology. The Cluster is grouped around thermohydraulic test facilities in Europe for the qualification of innovative BWR safety systems, also taking into account especially the operating experience of the nuclear power plant Dodewaard and other BWRs, which already incorporated some passive safety features. The background, the objectives, the structure of the project and the work programme are presented in this paper as well as an outline of the significance of the expected results. (orig.) [de

33 CFR 149.125 - What are the requirements for the malfunction detection system?

Science.gov (United States)

2010-07-01

... malfunction detection system? 149.125 Section 149.125 Navigation and Navigable Waters COAST GUARD, DEPARTMENT... Pollution Prevention Equipment § 149.125 What are the requirements for the malfunction detection system? (a... Commandant (CG-5) will evaluate proposed leak-detection systems for natural gas on an individual basis. ...

Radiochemical separation of Tb-149 after tandem accelerator production

International Nuclear Information System (INIS)

Sarkar, S.R.

1996-01-01

Full text: Terbium-149 is produced by the heavy ion induced reaction of the type 142 Nd( 12 C,5n) 149 Dy→ 149 Tb. This work concerns the separation of terbium from neodymium target, and other lanthanides produced by secondary reactions on neodymium target. Firstly, anion-exchange separation is carried out at room temperature using acid-alcohol media (90% methanol-10% 5M nitric acid) as eluent. But the separation is not satisfactory. To achieve satisfactory separation, cation exchange separation is performed under pressure at room temperature using 0.1 6M α-hydroxyisobutyric acid of pH 5 as eluent. The pressure is exerted from a nitrogen gas cylinder. The simplicity and efficacy of this method for the separation of terbium are discussed in comparison with the commercially available high performance liquid chromatography system

The design, safety and project development status of the modular high temperature gas-cooled reactor in the United States

International Nuclear Information System (INIS)

Mears, L.D.; Dean, R.A.

1987-01-01

The cooperative government and industry Modular High Temperature Gas-Cooled Reactor (MHTGR) Program in the United States has advanced a 350 MW(t) plant design through the conceptual development stage. The system incorporates an annular core of prismatic fuel elements within a steel pressure vessel connected, in a side-by-side arrangement, by a concentric duct to a second steel vessel containing a steam generator and helium coolant circulator. The reference plant design consists of four reactor modules installed in separate below-grade silos, providing steam to two conventional turbine generators. The nominal net plant output is 540 MW(e). The small reactor system takes unique advantage of the high temperature capability of the refractory coated fuel and the large thermal inertia of the graphite moderator to provide a design capable of withstanding a complete loss of active core cooling without causing excessive core heatup and significant release of fission products from the fuel. Present program activities are concentrated on interactions with the Nuclear Regulatory Commission aimed at obtaining a Licensability Statement. A project initiative to build a prototype plant which would demonstrate the MHTGR-unique licensing process, plant performance, costs and schedule plus establish an industrial infrastructure to proceed with follow-on commercial MHTGR plants by the turn of the century, is being undertaken by the utility/vendor participants (author)

Efficacy and safety of icotinib in Chinese patients with advanced non-small cell lung cancer after failure of chemotherapy.

Science.gov (United States)

Shao, Lan; Zhang, Beibei; He, Chunxiao; Lin, Baochai; Song, Zhengbo; Lou, Guangyuan; Yu, Xinmin; Zhang, Yiping

2014-01-01

The preclinical experiments and several clinical studies showed icotinib, an oral epidermal growth factor receptor (EGFR) tyrosine kinase inhibitor, in Chinese patients with advanced non-small cell lung cancer (NSCLC) who failed previous chemotherapy. We performed a retrospective study of the efficacy and safety of icotinib monotherapy in a different and more recent sample of Chinese patients. The clinical data of 149 patients with advanced NSCLC who were admitted to Zhejiang Cancer Hospital from August 1, 2011 to July 31, 2012 were retrospectively analyzed. All patients were given icotinib treatment after the failure of previous chemotherapy. Univariate and multivariate analyses were conducted based on the Kaplan Meier method and Cox proportional hazards model. The objective response rate was 33/149 and disease control rate was 105/149. No complete response occurred. Median progression free survival (PFS) with icotinib treatment was 5.03 months (95% CI: 3.51 to 6.55). Median overall survival was 12.3 months (95% CI: 10.68 to 13.92). Multivariate analysis showed that the mutation of EGFR and one regimen of prior chemotherapy were significantly associated with longer PFS. At least one drug related adverse event was observed in 65.8% (98/149) of patients, but mostly grade 1 or 2 and reversible and none grade 4 toxicity. Icotinib monotherapy is an effective and well tolerated regimen for Chinese patients with NSCLC after the failure of chemotherapy. It is a promising agent and further study with icotinib in properly conducted trials with larger patient samples and other ethnic groups is warranted.

R and D perspectives on the advanced nuclear safety regulation system

International Nuclear Information System (INIS)

Lee, Chang Ju; Ahn, Sang Kyu; Park, Jong Seuk; Chung, Dae Wook; Han, Sang Hoon; Lee, Jung Won

2009-01-01

As current licensing process is much desired to be optimized both plant safety and regulatory efficiency, an advanced safety regulation such as risk informed regulation has been come out. Also, there is a need to have a future oriented safety regulation since a lot of new reactors are conceptualized. Keeping pace with these needs, since early 2007, Korean government has launched a new project for preparing an advanced and future oriented nuclear safety regulation system. In order to get practical achievements, the project team sets up such specific research objectives for the development of: implementation program for graded regulation using risk and performance information; multi purpose PSA models for regulatory uses; a technology neutral regulatory framework for future innovative reactors; evaluation procedure of proliferation resistance; and, performance based fire hazard analysis method and evaluation system. This paper introduces major R and D outputs of this project, and provides some perspectives for achieving effectiveness and efficiency of the nuclear regulation system in Korea

R and D perspectives on the advanced nuclear safety regulation system

Energy Technology Data Exchange (ETDEWEB)

Lee, Chang Ju; Ahn, Sang Kyu; Park, Jong Seuk; Chung, Dae Wook [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of); Han, Sang Hoon; Lee, Jung Won [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2009-04-15

As current licensing process is much desired to be optimized both plant safety and regulatory efficiency, an advanced safety regulation such as risk informed regulation has been come out. Also, there is a need to have a future oriented safety regulation since a lot of new reactors are conceptualized. Keeping pace with these needs, since early 2007, Korean government has launched a new project for preparing an advanced and future oriented nuclear safety regulation system. In order to get practical achievements, the project team sets up such specific research objectives for the development of: implementation program for graded regulation using risk and performance information; multi purpose PSA models for regulatory uses; a technology neutral regulatory framework for future innovative reactors; evaluation procedure of proliferation resistance; and, performance based fire hazard analysis method and evaluation system. This paper introduces major R and D outputs of this project, and provides some perspectives for achieving effectiveness and efficiency of the nuclear regulation system in Korea.

Dicty_cDB: SSE149 [Dicty_cDB

Lifescience Database Archive (English)

Full Text Available SS (Link to library) SSE149 (Link to dictyBase) - - - Contig-U01658-1 | Contig-U165... library) Clone ID SSE149 (Link to dictyBase) Atlas ID - NBRP ID - dictyBase ID - Link to Contig Contig-U016...58-1 | Contig-U16509-1 Original site URL http://dictycdb.biol.tsukuba.ac.jp/CSM/S...g significant alignments: (bits) Value N D16417 |D16417.1 Dictyostelium discoideum mRNA. 64 1e-17 2 AC100496...egans clone T13G4, complete sequence. 36 5.0 2 BM028890 |BM028890.1 IpSkn01670 Skin cDNA library Ictalurus p

75 FR 3471 - International Conference on Harmonisation; Guidance on M3(R2) Nonclinical Safety Studies for the...

Science.gov (United States)

2010-01-21

...] International Conference on Harmonisation; Guidance on M3(R2) Nonclinical Safety Studies for the Conduct of... the availability of a guidance entitled ``M3(R2) Nonclinical Safety Studies for the Conduct of Human... auspices of the International Conference on Harmonisation of Technical Requirements for Registration of...

Worldwide advanced nuclear power reactors with passive and inherent safety: What, why, how, and who

International Nuclear Information System (INIS)

Forsberg, C.W.; Reich, W.J.

1991-09-01

The political controversy over nuclear power, the accidents at Three Mile Island (TMI) and Chernobyl, international competition, concerns about the carbon dioxide greenhouse effect and technical breakthroughs have resulted in a segment of the nuclear industry examining power reactor concepts with PRIME safety characteristics. PRIME is an acronym for Passive safety, Resilience, Inherent safety, Malevolence resistance, and Extended time after initiation of an accident for external help. The basic ideal of PRIME is to develop power reactors in which operator error, internal sabotage, or external assault do not cause a significant release of radioactivity to the environment. Several PRIME reactor concepts are being considered. In each case, an existing, proven power reactor technology is combined with radical innovations in selected plant components and in the safety philosophy. The Process Inherent Ultimate Safety (PIUS) reactor is a modified pressurized-water reactor, the Modular High Temperature Gas-Cooled Reactor (MHTGR) is a modified gas-cooled reactor, and the Advanced CANDU Project is a modified heavy-water reactor. In addition to the reactor concepts, there is parallel work on super containments. The objective is the development of a passive ''box'' that can contain radioactivity in the event of any type of accident. This report briefly examines: why a segment of the nuclear power community is taking this new direction, how it differs from earlier directions, and what technical options are being considered. A more detailed description of which countries and reactor vendors have undertaken activities follows. 41 refs

Pulseshape characteristics of a 300 $\\mu$m PR03 R-measuring VELO sensor read out with a Beetle1.3 chip

CERN Document Server

Palacios, A; Buytaert, J; Borel, J; Collins, P; Eckstein, D; Eklund, L; Ferro-Luzzi, M; Jans, E; Ketel, T; Petrie, D; Pivk, M; Tobin, M

2005-01-01

The signal-to-noise, overspill and undershoot characteristics of a VELO module equipped with Beetle1.3 read-out chips have been measured using 120 GeV pions from the SPS test beam facility at CERN. The module consists of a PR03 n-on-n 300 $\\mu$m R measuring prototype sensor and a fully populated K03 hybrid. Results are presented for a single Beetle1.3 chip with a variety of chip parameter settings controlling the pre-amplifier and shaper currents and feedback voltages, with the objective of establishing the performance of the module and understanding its dependence on the read-out chip settings.

Long-term safety evaluation of bimatoprost ophthalmic solution 0.03%: a pooled analysis of six double-masked, randomized, active-controlled clinical trials

Directory of Open Access Journals (Sweden)

Wirta D

2011-06-01

Full Text Available David Wirta1, Amanda M VanDenburgh2, Emily Weng3, Scott M Whitcup4, Sef Kurstjens5, Frederick C Beddingfield III4,61Private Practice, Newport Beach, CA, USA; 2Clinical Development, 3Biostatistics, 4Research and Development, 5Global Drug Development, Allergan, Inc, Irvine, CA, USA; 6Department of Medicine, Division of Dermatology, David Geffen School of Medicine, UCLA, Los Angeles, CA, USABackground: Bimatoprost ophthalmic solution 0.03% was approved in the US for reducing intraoccular pressure (IOP based on two double-masked, active-controlled clinical trials. Four additional long-term studies (≥ 12months were conducted; however, the aggregate safety profile of the six studies has not been reported.Methods: Adverse events (AEs were pooled from six double-masked, active-controlled, long-term clinical trials in which subjects received bimatoprost 0.03% once daily (QD or twice daily (BID as an eyedrop. AE terms were converted to MedDRA (V.11.0 Preferred Terms and analyzed.Results: In total, 1409 patients received more than one dose of bimatoprost 0.03% QD or BID. Most AEs were mild in severity and reported by 86.7% (QD and 94.8% (BID of subjects (≤ 12 months of treatment. AEs reported through month 12 (aggregate incidence of ≥ 5% were conjunctival hyperemia, increased eyelash growth, eye pruritus, periocular skin hyperpigmentation, eye irritation, dry eye, and hypertrichosis. AE onset was generally reported within four months of treatment. The cumulative incidence of common AEs in the QD treatment group at 24–48 months was similar to that measured at 12 months of treatment.Conclusion: Bimatoprost 0.03% has a favorable safety and tolerability profile as characterized by six long-term studies. Common AEs were due to the known pharmacological activity of bimatoprost and reversible with treatment cessation.Keywords: intraocular pressure, eyelids, pharmacology, clinical trial, medical treatment

Application of probabilistic methods to safety R and D and design choices

International Nuclear Information System (INIS)

Gavigan, F.X.; Griffith, J.D.

1977-01-01

The Liquid Metal Fast Breeder Reactor (LMFBR) safety program is committed to identifying and exploiting areas in which probabilistic methods can be developed and used in making reactor safety R and D choices and optimizing designs of safety systems. Emphasis will be placed on a positive approach of solidifying and expanding our knowledge. This will provide the groundwork for a consensus on FBR risk. The management structure which will be used is based on a mechanistic approach to an LMFBR Core Disruptive Accident (CDA) with risk partitioned into ''Lines of Assurance,'' i.e., independent, phenomenologically-based barriers which will impede or mitigate the progression and consequences of accident sequences. Quantitative determination of the probability of breach of these barriers through the completion of work identified for each Line of Assurance will allow the quantification of the contribution to risk reduction associated with the success of each barrier. This process can lead to better use of resources by channeling R and D in directions which promise the greatest potential for reducing risk and by identifying an orderly approach to the development and demonstration of design features which will keep LMFBR risks at an acceptable level

The USERDA transport R and D program for environment and safety

International Nuclear Information System (INIS)

Sisler, J.A.

1976-01-01

This paper describes the U.S. Energy Research and Development Administration's (ERDA) transportation environment and safety research and development program for energy fuels and wastes, including background, current activities, and future plans. It will serve as an overview and integrating factor for the several related technical papers to be presented at this meeting which will enlarge on the detail of specific projects. The transportation R and D program provides for the environmental and safety review of transport systems and procedures; standards development; and package, vehicle, and systems testing for nuclear materials transport. A primary output of the program is the collection, processing, and dissemination of transport environment and safety data, shipment statistics, and technical information. Special transport projects which do not easily fit elsewhere in ERDA are usually done as a part of this program. (author)

Benthic data from bottom grabs from Prince William Sound in support of Exxon Valdez Oil Spill Restoration Project from the R/V DAVIDSON and R/V BIG VALLEY from 03 July 1990 to 25 June of 1991 (NODC Accession 0000447)

Data.gov (United States)

National Oceanic and Atmospheric Administration, Department of Commerce — Benthic samples and other data were collected from the R/V DAVIDSON and R/V BIG VALLEY from the Prince William Sound from 03 July 1990 to 25 June of 1991 . Data were...

Proposed Advanced Reactor Adaptation of the Standard Review Plan NUREG-0800 Chapter 4 (Reactor) for Sodium-Cooled Fast Reactors and Modular High-Temperature Gas-Cooled Reactors

Energy Technology Data Exchange (ETDEWEB)

Belles, Randy [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Poore, III, Willis P. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Brown, Nicholas R. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Flanagan, George F. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Holbrook, Mark [Idaho National Lab. (INL), Idaho Falls, ID (United States); Moe, Wayne [Idaho National Lab. (INL), Idaho Falls, ID (United States); Sofu, Tanju [Argonne National Lab. (ANL), Argonne, IL (United States)

2017-03-01

This report proposes adaptation of the previous regulatory gap analysis in Chapter 4 (Reactor) of NUREG 0800, Standard Review Plan (SRP) for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR [Light Water Reactor] Edition. The proposed adaptation would result in a Chapter 4 review plan applicable to certain advanced reactors. This report addresses two technologies: the sodium-cooled fast reactor (SFR) and the modular high temperature gas-cooled reactor (mHTGR). SRP Chapter 4, which addresses reactor components, was selected for adaptation because of the possible significant differences in advanced non-light water reactor (non-LWR) technologies compared with the current LWR-based description in Chapter 4. SFR and mHTGR technologies were chosen for this gap analysis because of their diverse designs and the availability of significant historical design detail.

33 CFR 149.321 - How many ring life buoys must be on each deepwater port?

Science.gov (United States)

2010-07-01

... 33 Navigation and Navigable Waters 2 2010-07-01 2010-07-01 false How many ring life buoys must be on each deepwater port? 149.321 Section 149.321 Navigation and Navigable Waters COAST GUARD... EQUIPMENT Lifesaving Equipment Manned Deepwater Port Requirements § 149.321 How many ring life buoys must be...

Safety and efficacy of Profermin(R) to induce remission in ulcerative colitis

DEFF Research Database (Denmark)

Krag, Aleksander; Israelsen, Hans; von Ryberg, Bjørn

2012-01-01

AIM: To test the efficacy and safety of Profermin(R) in inducing remission in patients with active ulcerative colitis (UC). METHODS: The study included 39 patients with mild to moderate UC defined as a Simple Clinical Colitis Activity Index (SCCAI) > 4 and < 12 (median: 7.5), who were treated ope...

Contribution of the Tyr-1 in Plantaricin149a to Disrupt Phospholipid Model Membranes

Directory of Open Access Journals (Sweden)

Georgina Tonarelli

2013-06-01

Full Text Available Plantaricin149a (Pln149a is a cationic antimicrobial peptide, which was suggested to cause membrane destabilization via the carpet mechanism. The mode of action proposed to this antimicrobial peptide describes the induction of an amphipathic α-helix from Ala7 to Lys20, while the N-terminus residues remain in a coil conformation after binding. To better investigate this assumption, the purpose of this study was to determine the contributions of the Tyr1 in Pln149a in the binding to model membranes to promote its destabilization. The Tyr to Ser substitution increased the dissociation constant (KD of the antimicrobial peptide from the liposomes (approximately three-fold higher, and decreased the enthalpy of binding to anionic vesicles from −17.2 kcal/mol to −10.2 kcal/mol. The peptide adsorption/incorporation into the negatively charged lipid vesicles was less effective with the Tyr1 substitution and peptide Pln149a perturbed the liposome integrity more than the analog, Pln149S. Taken together, the peptide-lipid interactions that govern the Pln149a antimicrobial activity are found not only in the amphipathic helix, but also in the N-terminus residues, which take part in enthalpic contributions due to the allocation at a lipid-aqueous interface.

38 CFR 17.149 - Sensori-neural aids.

Science.gov (United States)

2010-07-01

... 38 Pensions, Bonuses, and Veterans' Relief 1 2010-07-01 2010-07-01 false Sensori-neural aids. 17... Prosthetic, Sensory, and Rehabilitative Aids § 17.149 Sensori-neural aids. (a) Notwithstanding any other provision of this part, VA will furnish needed sensori-neural aids (i.e., eyeglasses, contact lenses...

Reactor R ampersand D programs tough to eliminate; just ask NRC staff

International Nuclear Information System (INIS)

Lane, E.

1993-01-01

Even if the Clinton administration succeeds in eliminating funding for the advanced liquid metal reactor (ALMR) and modular high-temperature gas reactor (MHTGR) in the fiscal year 1994 budget, it will not wipe out the programs entirely as shown by a recent exchange of letters between the Nuclear Regulatory Commission and the Energy Department. This article examines the political and bureaucratic maneuverings involved in the funding of nuclear power projects

Saturated Adaptive Output-Feedback Power-Level Control for Modular High Temperature Gas-Cooled Reactors

Directory of Open Access Journals (Sweden)

Zhe Dong

2014-11-01

Full Text Available Small modular reactors (SMRs are those nuclear fission reactors with electrical output powers of less than 300 MWe. Due to its inherent safety features, the modular high temperature gas-cooled reactor (MHTGR has been seen as one of the best candidates for building SMR-based nuclear plants with high safety-level and economical competitive power. Power-level control is crucial in providing grid-appropriation for all types of SMRs. Usually, there exists nonlinearity, parameter uncertainty and control input saturation in the SMR-based plant dynamics. Motivated by this, a novel saturated adaptive output-feedback power-level control of the MHTGR is proposed in this paper. This newly-built control law has the virtues of having relatively neat form, of being strong adaptive to parameter uncertainty and of being able to compensate control input saturation, which are given by constructing Lyapunov functions based upon the shifted-ectropies of neutron kinetics and reactor thermal-hydraulics, giving an online tuning algorithm for the controller parameters and proposing a control input saturation compensator respectively. It is proved theoretically that input-to-state stability (ISS can be guaranteed for the corresponding closed-loop system. In order to verify the theoretical results, this new control strategy is then applied to the large-range power maneuvering control for the MHTGR of the HTR-PM plant. Numerical simulation results show not only the relationship between regulating performance and control input saturation bound but also the feasibility of applying this saturated adaptive control law practically.

Environmental Assessment for Repair of Airfield Pavement and Lighting, Runway 03R/21L Travis Air Force Base, Fairfield, California. Revision

Science.gov (United States)

2009-12-01

substandard: 211450 SM PROJECT: Repair Runway 03R-21L pavements, airfield lighting, fiber optic communication lines , markers, and drainage systems...bottomed swales, or basalt flow depression pools in unplowed grasslands. The fairy shrimp has been collected from early December to early May. It can...pool types where the species has been found include Northern Hardpan, Northern Claypan, Northern Volcanic Mud Flow, and Northern Basalt Flow vernal

Safety and immunogenicity of a split-virion AS03A-adjuvanted A/Indonesia/05/2005 (H5N1 vaccine in Taiwanese adults

Directory of Open Access Journals (Sweden)

Pan-Chyr Yang

2012-06-01

Conclusion: Administration of two doses of the AS03A-adjuvanted H5N1 prepandemic influenza vaccine was found to be highly immunogenic in adults with a clinically acceptable safety profile. The ability to confer cross-clade protective immunity makes it a suitable option for mitigation of the morbidity and mortality of outbreaks and pandemics due to H5N1 and drifted strains.

Challenges in safety regulation of R and D activities for advanced technologies in DAE units

International Nuclear Information System (INIS)

Shukla, Dinesh Kumar

2016-01-01

DAE is engaged in intensive research and developmental activities, especially for advanced technologies such as accelerators, lasers, supercomputers, advanced materials and instrumentation. The starting point of an R and D project might be a hypothesis to be tested, problem to be solved, or the performance of an item to be improved, and there may be many possible solutions and technologies that could be used. R and D is quite different from designing, constructing, operating a plant. In these, precisely described result can be defined from the beginning and can be described in design specifications, process descriptions and procedures. However, while established procedures may be available to begin an R and D project, deviation from these procedures may occur often as a legitimate component of the conduct of R and D. Nevertheless, the R and D activities have to be performed in a manner which provides assurance that safety requirements are adequately addressed. Hence, the regulatory approach for enforcing the safety regulation in such facilities is also not as rigid as those for an operating industry. This paper is aimed to discuss some of the key challenges in regulating such R and D activities and also attempts to suggest a way forward. (author)

Integrating psychosocial safety climate in the JD-R model: a study amongst Malaysian workers

OpenAIRE

Idris, Mohd A.; Dollard, Maureen F.; Winefield, Anthony H.

2011-01-01

Orientation: Job characteristics are well accepted as sources of burnout and engagement amongst employees; psychosocial safety climate may precede work conditions. Research purpose: We expanded the Job Demands and Resources (JD-R) model by proposing psychosocial safety climate (PSC) as a precursor to job demands and job resources. As PSC theoretically influences the working environment, the study hypothesized that PSC has an impact on performance via both health erosion (i.e. burnout) and ...

42 CFR 84.149 - Type C supplied-air respirator, demand and pressure demand class; minimum requirements.

Science.gov (United States)

2010-10-01

... 42 Public Health 1 2010-10-01 2010-10-01 false Type C supplied-air respirator, demand and pressure demand class; minimum requirements. 84.149 Section 84.149 Public Health PUBLIC HEALTH SERVICE, DEPARTMENT... OF RESPIRATORY PROTECTIVE DEVICES Supplied-Air Respirators § 84.149 Type C supplied-air respirator...

Comparison of xenon-135 and samarium-149 poisoning in the Miniature Neutron Source Reactor

International Nuclear Information System (INIS)

Khattab, K.

2005-05-01

The Xe-135 equilibrium reactivity was calculated previously using the WIMSD4 and CITATION codes to estimate the fission product poisoning factor in the Syrian Miniature Neutron Source Reactor (MNSR). The fission product poisoning factor was used to calculate the Xe-135 concentrations and reactivities during the reactor operation, at saturation, and after shutdown. The fission product poisoning factor is used in this study to calculate the Sm-149 concentrations and reactivities during the reactor operation, at saturation, and after shutdown. The results are compared with Xe-135 concentrations and reactivities which were calculated before. The Xe-135 concentration increases versus the reactor operation time and reaches 2.836*10 13 atoms/cm 3 after 6 hours, where the Sm-149 concentration reaches 0.745*10 12 atoms/cm 3 . The Xe-135 and Sm-149 reactivities reach -0.451 and -0.256*10 -3 mk respectively after 6 hours of the reactor operation time. It is found that the Xe-135 and Sm-149 reactivities do not reach the equilibrium reactivities during typical reactor daily operating time. The Xe-235 concentration and reactivity are increased and reach to maximum values after 30000 second from the reactor shut down. Its maximum reactivity is -0.903 mk. Hence, the Xe-235 generates -0.452 mk extra reactivity after the reactor shutdown. The Sm-149 concentration and reactivates are increased after the reactor shut down. The Sm-149 reactivity reaches -0.249*10 -2 mk after 100000 second from the reactor shut down, and the Sm-149 introduces -2.231*10 -3 mk extra reactivity after the reactor shut down. Finally, the amount of Sm-149 accumulated in the reactor core after 1, 2, 5, and 10 years of the reactor operation time are: 3.995*10 -3 , 7.694*10 -3 , 17.226*10 -3 , and 2.892*10 -2 grams respectively. (Author)

Management Systems and Safety Culture in the Nuclear Energy Sector (ISO 9001 & GS-R-3)

International Nuclear Information System (INIS)

Smetnik, A.; Murlis, D.

2016-01-01

Nowadays, the enterprises of the Rosatom State Nuclear Energy Corporation that provides products and services to foreign customers should rely on the requirements to the management systems established by the IAEA Standard GS-R-3 “The management system for facilities and activities”. This results from the fact that in order to enter foreign markets, Russian suppliers have to meet foreign requirements related to quality assurance, protection of the environment, nuclear and radiation safety, etc. For instance, the Finnish customer “Fennovoima” requires full compliance of the management systems of the Russian companies involved in the construction of the Hanhikivi-1 NPP with the GS-R-3 Standard. ISO 9001 quality management systems were widely implemented in the nuclear industry enterprises in Russia. The assessment of compliance of the quality management systems with the established requirements is carried out by the certification bodies. The same relates to the environmental management systems that are implemented at the majority of nuclear industry facilities in Russia. But due to their uniqueness and associated significant risks, the nuclear industry enterprises have to meet current safety requirements and principles established in the IAEA Safety Standards, such as safety culture and risk management.

Crack growth in thermally sprayed ceramic coatings

Czech Academy of Sciences Publication Activity Database

Kroupa, František; Náhlík, Luboš; Knésl, Zdeněk

2004-01-01

Roč. 49, č. 2 (2004), s. 149-168 ISSN 0001-7043 R&D Projects: GA ČR GP106/04/P084; GA ČR GA101/03/0331 Institutional research plan: CEZ:AV0Z2043910 Keywords : ceramic coatings, fracture mechanics, crack extension Subject RIV: JH - Ceramics, Fire-Resistant Materials and Glass

Interaction of antimicrobial peptide Plantaricin149a and four analogs with lipid bilayers and bacterial membranes

Directory of Open Access Journals (Sweden)

José Luiz de Souza Lopes

2013-12-01

Full Text Available The amidated analog of Plantaricin149, an antimicrobial peptide from Lactobacillus plantarum NRIC 149, directly interacts with negatively charged liposomes and bacterial membranes, leading to their lysis. In this study, four Pln149-analogs were synthesized with different hydrophobic groups at their N-terminus with the goal of evaluating the effect of the modifications at this region in the peptide's antimicrobial properties. The interaction of these peptides with membrane models, surface activity, their hemolytic effect on red blood cells, and antibacterial activity against microorganisms were evaluated. The analogs presented similar action of Plantaricin149a; three of them with no hemolytic effect (< 5% until 0.5 mM, in addition to the induction of a helical element when binding to negative liposomes. The N-terminus difference between the analogs and Plantaricin149a retained the antibacterial effect on S. aureus and P. aeruginosa for all peptides (MIC50 of 19 µM and 155 µM to Plantaricin149a, respectively but resulted in a different mechanism of action against the microorganisms, that was bactericidal for Plantaricin149a and bacteriostatic for the analogs. This difference was confirmed by a reduction in leakage action for the analogs. The lytic activity of Plantaricin149a is suggested to be a result of the peptide-lipid interactions from the amphipathic helix and the hydrophobic residues at the N-terminus of the antimicrobial peptide.

33 CFR 149.310 - What are the muster and embarkation requirements for survival craft?

Science.gov (United States)

2010-07-01

... embarkation requirements for survival craft? 149.310 Section 149.310 Navigation and Navigable Waters COAST... and embarkation requirements for survival craft? Muster and embarkation arrangements for survival craft must comply with 46 CFR 108.540. ...

Unigene BLAST: CBRC-DMEL-03-0012 [SEVENS

Lifescience Database Archive (English)

Full Text Available CBRC-DMEL-03-0012 gnl|UG|Dm#S40593121 DMG1C.2_1.G07.C1 MODENCODE_DM_A Drosophila melanogaster cDNA clone DMG...1-chr3R.3.082.a, mRNA sequence /clone=DMG1-chr3R.3.082.a /gb=EW713160 /gi=156142114 /ug=Dm.27906 /len=1533 0.64 34% ...

Unigene BLAST: CBRC-DMEL-03-0057 [SEVENS

Lifescience Database Archive (English)

Full Text Available CBRC-DMEL-03-0057 gnl|UG|Dm#S40593060 DMG1C.3_1.C08.C1 MODENCODE_DM_A Drosophila melanogaster cDNA clone DMG...1-chr3R.5.051.a, mRNA sequence /clone=DMG1-chr3R.5.051.a /gb=EW713099 /gi=156142053 /ug=Dm.27239 /len=1584 6e-13 25% ...

Unigene BLAST: CBRC-DMEL-03-0039 [SEVENS

Lifescience Database Archive (English)

Full Text Available CBRC-DMEL-03-0039 gnl|UG|Dm#S40593060 DMG1C.3_1.C08.C1 MODENCODE_DM_A Drosophila melanogaster cDNA clone DMG...1-chr3R.5.051.a, mRNA sequence /clone=DMG1-chr3R.5.051.a /gb=EW713099 /gi=156142053 /ug=Dm.27239 /len=1584 7e-31 40% ...

Unigene BLAST: CBRC-DMEL-03-0045 [SEVENS

Lifescience Database Archive (English)

Full Text Available CBRC-DMEL-03-0045 gnl|UG|Dm#S40593060 DMG1C.3_1.C08.C1 MODENCODE_DM_A Drosophila melanogaster cDNA clone DMG...1-chr3R.5.051.a, mRNA sequence /clone=DMG1-chr3R.5.051.a /gb=EW713099 /gi=156142053 /ug=Dm.27239 /len=1584 1e-23 38% ...

Unigene BLAST: CBRC-DMEL-03-0071 [SEVENS

Lifescience Database Archive (English)

Full Text Available CBRC-DMEL-03-0071 gnl|UG|Dm#S40593121 DMG1C.2_1.G07.C1 MODENCODE_DM_A Drosophila melanogaster cDNA clone DMG...1-chr3R.3.082.a, mRNA sequence /clone=DMG1-chr3R.3.082.a /gb=EW713160 /gi=156142114 /ug=Dm.27906 /len=1533 3e-07 47% ...

33 CFR 149.305 - What are the survival craft requirements for temporary personnel?

Science.gov (United States)

2010-07-01

... 33 Navigation and Navigable Waters 2 2010-07-01 2010-07-01 false What are the survival craft... EQUIPMENT Lifesaving Equipment Manned Deepwater Port Requirements § 149.305 What are the survival craft... complement exceeds the capacity of the survival craft required under § 149.304 of this subpart, the port must...

Modulator of intracellular Ca2+, thapsigargin, interferes with in vitro secretion of cytokines and nitric oxide

Czech Academy of Sciences Publication Activity Database

Kmoníčková, Eva; Kutinová-Canová, N.; Farghali, H.; Holý, Antonín

2006-01-01

Roč. 149, č. 2 (2006), s. 321-324 ISSN 1213-8118 R&D Projects: GA ČR GA305/05/2425; GA ČR GA305/03/1470; GA MŠk 1M0508 Institutional research plan: CEZ:AV0Z50390512; CEZ:AV0Z40550506 Keywords : Thapsigargin * IL-10 * Rantes Subject RIV: FR - Pharmacology ; Medidal Chemistry

Source region of volcanism and seismicity pattern beneath Central American volcanoes

Czech Academy of Sciences Publication Activity Database

Špičák, Aleš; Hanuš, Václav; Vaněk, Jiří

2005-01-01

Roč. 236, 1/2 (2005), s. 149-172 ISSN 0077-7749 R&D Projects: GA ČR GA205/03/1203; GA AV ČR IAA3012303 Institutional research plan: CEZ:AV0Z30120515 Keywords : Central America * subduction * convergent plate margins Subject RIV: DC - Siesmology, Volcanology, Earth Structure Impact factor: 0.721, year: 2005

49 CFR 28.149 - Program accessibility: Discrimination prohibited.

Science.gov (United States)

2010-10-01

... 49 Transportation 1 2010-10-01 2010-10-01 false Program accessibility: Discrimination prohibited... § 28.149 Program accessibility: Discrimination prohibited. Except as otherwise provided in § 28.150, no... otherwise be subjected to discrimination under any program or activity conducted by the Department. ...

32 CFR 1699.149 - Program accessibility: discrimination prohibited.

Science.gov (United States)

2010-07-01

... 32 National Defense 6 2010-07-01 2010-07-01 false Program accessibility: discrimination prohibited... CONDUCTED BY SELECTIVE SERVICE SYSTEM § 1699.149 Program accessibility: discrimination prohibited. Except as... participation in, or otherwise be subject to discrimination under any program or activity conducted by the...

How the nuclear safety team conducts emergency exercises at the IEA-R1 reactor

International Nuclear Information System (INIS)

Vaz, Antonio C.A.; Silva, Davilson G.; Toyoda, Eduardo Y.; Santia, Paulo S.; Conti, Thadeu N.; Semmler, Renato; Carvalho, Ricardo N.

2015-01-01

This work introduces the Diagram of Emergency Exercise Coordination designed by the Nuclear Safety Team for better Emergency Exercise coordination. The Nuclear Safety Team was created with the mission of avoiding, preventing and mitigating the causes and effects of accidents at the IEA-R1. The facility where we conduct our work is located in an area of a huge population, what increases the responsibility of our mission: conducting exercises and training are part of our daily activities. During the Emergency Exercise, accidents ranked 0-4 on INES (International Nuclear Events Scale) are simulated and involve: Police Department, Fire Department, workers, people from the community, and others. In the last exercise held in June 2014, the scenario contemplated a terrorist organization action that infiltrated in a group of students who were visiting the IEA-R1, tried to steal fresh fuel element to fabricate a dirty bomb. Emergency procedures and plans, timeline and metrics of the actions were applied to the Emergency Exercise evaluation. The next exercise will be held in November, with the simulation of the piping of the primary cooling circuit rupture, causing the emptying of the pool and the lack of cooling of the fuel elements in the reactor core: this will be the scenario. The skills acquired and the systems improvement have been very important tools for the reactor operation safety and the Nuclear Safety Team is making technical efforts so that these Emergency Exercises may be applied to other nuclear and radiological facilities. Equally important for the process of improving nuclear safety is the emphasis placed on implementing quality improvements to the human factor in the nuclear safety area, a crucial element that is often not considered by those outside the nuclear sector. Surely, the Diagram of Emergency Exercise Coordination application will improve and facilitate the organization, coordination and evaluation tasks. (author)

How the nuclear safety team conducts emergency exercises at the IEA-R1 reactor

Energy Technology Data Exchange (ETDEWEB)

Vaz, Antonio C.A.; Silva, Davilson G.; Toyoda, Eduardo Y.; Santia, Paulo S.; Conti, Thadeu N.; Semmler, Renato; Carvalho, Ricardo N., E-mail: acavaz@ipen.br, E-mail: dgsilva@ipen.br, E-mail: eytoyoda@ipen.br, E-mail: psantia@ipen.br, E-mail: tnconti@ipen.br, E-mail: rsemmler@ipen.b, E-mail: rncarval@ipen.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

2015-07-01

This work introduces the Diagram of Emergency Exercise Coordination designed by the Nuclear Safety Team for better Emergency Exercise coordination. The Nuclear Safety Team was created with the mission of avoiding, preventing and mitigating the causes and effects of accidents at the IEA-R1. The facility where we conduct our work is located in an area of a huge population, what increases the responsibility of our mission: conducting exercises and training are part of our daily activities. During the Emergency Exercise, accidents ranked 0-4 on INES (International Nuclear Events Scale) are simulated and involve: Police Department, Fire Department, workers, people from the community, and others. In the last exercise held in June 2014, the scenario contemplated a terrorist organization action that infiltrated in a group of students who were visiting the IEA-R1, tried to steal fresh fuel element to fabricate a dirty bomb. Emergency procedures and plans, timeline and metrics of the actions were applied to the Emergency Exercise evaluation. The next exercise will be held in November, with the simulation of the piping of the primary cooling circuit rupture, causing the emptying of the pool and the lack of cooling of the fuel elements in the reactor core: this will be the scenario. The skills acquired and the systems improvement have been very important tools for the reactor operation safety and the Nuclear Safety Team is making technical efforts so that these Emergency Exercises may be applied to other nuclear and radiological facilities. Equally important for the process of improving nuclear safety is the emphasis placed on implementing quality improvements to the human factor in the nuclear safety area, a crucial element that is often not considered by those outside the nuclear sector. Surely, the Diagram of Emergency Exercise Coordination application will improve and facilitate the organization, coordination and evaluation tasks. (author)

Multi-particle excitations in the superdeformed {sup 149}Gd nucleus

Energy Technology Data Exchange (ETDEWEB)

Flibotte, S. [Strasbourg-1 Univ., 67 (France). Centre de Recherches Nucleaires]|[Department of Physics and Astronomy, McMaster, University, Hamilton ON L8S 4M1 (Canada)]|[AECL Research, Chalk River Laboratories, Chalk River ON K0J 1J0 (Canada); Hackman, G. [Department of Physics and Astronomy, McMaster, University, Hamilton ON L8S 4M1 (Canada); Ragnarsson, I. [Department of Mathematical Physics, Lund institute of Technology, Box 118 S-221, Lund (Sweden); Theisen, C. [Strasbourg-1 Univ., 67 (France). Centre de Recherches Nucleaires; Andrews, H.R. [AECL Research, Chalk River Laboratories, Chalk River ON K0J 1J0 (Canada); Ball, G.C. [AECL Research, Chalk River Laboratories, Chalk River ON K0J 1J0 (Canada); Beausang, C.W. [Oliver Lodge Laboratory, University of Liverpool, Liverpool L69 3BX (United Kingdom); Beck, F.A. [Strasbourg-1 Univ., 67 (France). Centre de Recherches Nucleaires; Belier, G. [Strasbourg-1 Univ., 67 (France). Centre de Recherches Nucleaires; Bentley, M.A. [Staffordshire University, Stoke on Trent (United Kingdom); Byrski, T. [Strasbourg-1 Univ., 67 (France). Centre de Recherches Nucleaires; Curien, D. [Strasbourg-1 Univ., 67 (France). Centre de Recherches Nucleaires; France, G. de [Strasbourg-1 Univ., 67 (France). Centre de Recherches Nucleaires; Disdier, D. [Strasbourg-1 Univ., 67 (France). Centre de Recherches Nucleaires; Duchene, G. [Strasbourg-1 Univ., 67 (France). Centre de Recherches Nucleaires; Haas, B. [Strasbourg-1 Univ., 67 (France). Centre de Recherches Nucleaires; Haslip, D.S. [Department of Physics and Astronomy, McMaster, University, Hamilton ON L8S 4M1 (Canada); Janzen, V.P. [Department of Physics and Astronomy, McMaster, University, Hamilton ON L8S 4M1 (Canada)]|[AECL Research, Chalk River Laboratories, Chalk River ON K0J 1J0 (Canada); Jones, P.M. [Oliver Lodge Laboratory, University of Liverpool, Liverpool L69 3BX (United Kingdom); Kharraja, B.

1995-02-20

Six rotational bands built on superdeformed intrinsic configurations have been observed in the {sup 149}Gd nucleus with the Eurogam spectrometer. Orbital configuration assignments have been suggested on the basis of their effective alignments calculated with the Nilsson-Strutinsky cranking model. Most of the excited bands have identical partners in neighboring nuclei including one case differing by four mass units. Measurements of feeding patterns indicate that the {sup 149}Gd yrast superdeformed band is fed over a wider range of angular momentum than other yrast superdeformed bands in this mass region whereas weaker excited bands in the same nucleus are populated in narrower spin windows. ((orig.))

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

Science.gov (United States)

2010-08-06

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

cis-Chlorobenzene Dihydrodiol Dehydrogenase (TcbB) from Pseudomonas sp. Strain P51, Expressed in Escherichia coli DH5α(pTCB149), Catalyzes Enantioselective Dehydrogenase Reactions

OpenAIRE

Raschke, Henning; Fleischmann, Thomas; Van Der Meer, Jan Roelof; Kohler, Hans-Peter E.

1999-01-01

cis-Chlorobenzene dihydrodiol dehydrogenase (CDD) from Pseudomonas sp. strain P51, cloned into Escherichia coli DH5α(pTCB149) was able to oxidize cis-dihydrodihydroxy derivatives (cis-dihydrodiols) of dihydronaphthalene, indene, and four para-substituted toluenes to the corresponding catechols. During the incubation of a nonracemic mixture of cis-1,2-indandiol, only the (+)-cis-(1R,2S) enantiomer was oxidized; the (−)-cis-(S,2R) enantiomer remained unchanged. CDD oxidized both enantiomers of ...

10 CFR 1705.03 - Systems of records notification.

Science.gov (United States)

2010-01-01

... Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD PRIVACY ACT § 1705.03 Systems of records notification. (a) Public notice. The Board has published in the Federal Register its systems of records. The Office of the Federal Register biennially compiles and publishes all systems of records maintained by all Federal...

Optimization problems with equilibrium constraints and their numerical solution

Czech Academy of Sciences Publication Activity Database

Kočvara, Michal; Outrata, Jiří

Roč. 101 , č. 1 (2004), s. 119-149 ISSN 0025-5610 R&D Projects: GA AV ČR IAA1075005 Grant - others:BMBF(DE) 03ZOM3ER Institutional research plan: CEZ:AV0Z1075907 Keywords : optimization problems * MPEC * MPCC Subject RIV: BA - General Mathematics Impact factor: 1.016, year: 2004

LANTERN: a randomized study of QVA149 versus salmeterol/fluticasone combination in patients with COPD

Directory of Open Access Journals (Sweden)

Zhong N

2015-06-01

Full Text Available Nanshan Zhong,1 Changzheng Wang,2 Xiangdong Zhou,3 Nuofu Zhang,1 Michael Humphries,4 Linda Wang,4 Chau Thach,5 Francesco Patalano,6 Donald Banerji5On behalf of the LANTERN Investigators 1State Key Laboratory of Respiratory Diseases, First Affiliated Hospital, Guangzhou Medical University, Guangzhou, Guangdong, 2Institute of Respiratory Disease, Xin Qiao Hospital, 3Department of Respiratory Medicine, Southwest Hospital, Third Military Medical University, Chongqing City, Chongqing, 4Beijing Novartis Pharma Co. Ltd., Shanghai, People’s Republic of China; 5Novartis Pharmaceuticals Corporation, East Hanover, NJ, USA; 6Novartis Pharma AG, Basel, SwitzerlandBackground: The current Global initiative for chronic Obstructive Lung Disease (GOLD treatment strategy recommends the use of one or more bronchodilators according to the patient’s airflow limitation, their history of exacerbations, and symptoms. The LANTERN study evaluated the effect of the long-acting β2-agonist (LABA/long-acting muscarinic antagonist (LAMA dual bronchodilator, QVA149 (indacaterol/glycopyrronium, as compared with the LABA/inhaled corticosteroid, salmeterol/fluticasone (SFC, in patients with moderate-to-severe COPD with a history of ≤1 exacerbation in the previous year.Methods: In this double-blind, double-dummy, parallel-group study, 744 patients with moderate-to-severe COPD with a history of ≤1 exacerbations in the previous year were randomized (1:1 to QVA149 110/50 µg once daily or SFC 50/500 µg twice daily for 26 weeks. The primary endpoint was noninferiority of QVA149 versus SFC for trough forced expiratory volume in 1 second (FEV1 at week 26.Results: Overall, 676 patients completed the study. The primary objective of noninferiority between QVA149 and SFC in trough FEV1 at week 26 was met. QVA149 demonstrated statistically significant superiority to SFC for trough FEV1 (treatment difference [∆]=75 mL; P<0.001. QVA149 demonstrated a statistically significant

Monitoring of Acoustic Emission During the Disintegration of Rock

Czech Academy of Sciences Publication Activity Database

Tripathi, R.; Srivastava, M.; Hloch, Sergej; Adamčík, P.; Chattopadhyaya, S.; Das, A. K.

2016-01-01

Roč. 149, č. 149 (2016), s. 481-488 E-ISSN 1877-7058. [International Conference on Manufacturing Engineering and Materials, ICMEM 2016. Nový Smokovec, 06.06.2016-10.06.2016] R&D Projects: GA MŠk ED2.1.00/03.0082; GA MŠk(CZ) LO1406 Institutional support: RVO:68145535 Keywords : acoustic emission * rock disintegration * waterjet Subject RIV: JQ - Machines ; Tools http://www.sciencedirect.com/science/article/pii/S1877705816312127

Potential of using water jet peening as a surface treatment process for welded\

Czech Academy of Sciences Publication Activity Database

Srivastava, M.; Tripathi, R.; Hloch, Sergej; Chattopadhyaya, S.; Dixit, A. R.

2016-01-01

Roč. 149, č. 149 (2016), s. 472-480 E-ISSN 1877-7058. [International Conference on Manufacturing Engineering and Materials, ICMEM 2016. Nový Smokovec, 06.06.2016-10.06.2016] R&D Projects: GA MŠk ED2.1.00/03.0082; GA MŠk(CZ) LO1406 Institutional support: RVO:68145535 Keywords : water jet * peening * residual stress Subject RIV: JQ - Machines ; Tools http://www.sciencedirect.com/science/article/pii/S1877705816312097

Optical study of SrAl1.7B0.3O4:Eu, R (R=Nd, Dy) pigments with long-lasting phosphorescence for industrial uses

International Nuclear Information System (INIS)

Sanchez-Benitez, J.; Andres, A. de; Marchal, M.; Cordoncillo, E.; Regi, M.V.; Escribano, P.

2003-01-01

We have studied and compared the optical properties of SrAl 1.7 B 0.3 O 4 :Eu, R (R=Nd, Dy) pigments that present long-lasting phosphorescence obtained by different synthesis techniques. Samples obtained by ceramic methods, in our laboratories and by an industrial process, present better phosphorescent properties than those obtained by sol-gel technique. Raman spectra show that grinding produces severe damage of the lattice. We have obtained and analyzed the Eu 3+ crystal field luminescence indicating that Eu 3+ is found in quite different sites comparing ceramic and sol-gel samples. Codoping, with Nd or Dy is necessary in order to reduce the Eu 3+ content, in all cases. The green luminescence band, obtained under UV illumination, can be fitted to two and three components in ceramic and sol-gel samples, respectively, due to different Eu 2+ sites. Eu-Dy samples present the longest and the most efficient phosphorescence. The time evolution of the afterglow is well described by a t -1 law, up to about 2 h, indicating that the recombination process is achieved by electron-hole tunneling

The study of 90 deg. gamma ray production cross sections for interactions of 14.9 Mev neutrons with C, Al, V, Fe, Co, Nb samples

International Nuclear Information System (INIS)

Tang Lin; Yan Yiming; Zhou Hongyu; Wen Shenlin; Wang Qi; Sun Shuxu; Ding Xiaoji; Wang Wanhong

1987-04-01

The (n,xr) reactions have been studied for incident neutron energy 14.9 Mev and for the samples C, Al, V, Fe, Co and Nb. The pulsed beam Time-of-Flight technique was adopted to discriminate neutrons and de-excitation r-rays and to improve the background conditions of the experiment. 90 deg. differential gamma production cross sections as the results of experiments are presented. Due to very low background many new r-rays peaks have been obtained. (author). 14 refs, 12 figs, 1 tab

Prevention and Reduction of Atrophic Acne Scars with Adapalene 0.3%/Benzoyl Peroxide 2.5% Gel in Subjects with Moderate or Severe Facial Acne: Results of a 6-Month Randomized, Vehicle-Controlled Trial Using Intra-Individual Comparison.

Science.gov (United States)

Dréno, Brigitte; Bissonnette, Robert; Gagné-Henley, Angélique; Barankin, Benjamin; Lynde, Charles; Kerrouche, Nabil; Tan, Jerry

2018-04-01

Very few clinical trials have investigated the effect of topical acne treatment on scarring. Our objective was to evaluate the efficacy of adapalene 0.3%/benzoyl peroxide 2.5% gel (A0.3/BPO2.5) in atrophic acne scar formation in patients with acne. In this multicenter, randomized, investigator-blinded, vehicle-controlled study, subjects with moderate or severe facial acne (Investigator's Global Assessment [IGA] score 3 or 4; ≥ 25 inflammatory lesions; ten or more atrophic acne scars) applied A0.3/BPO2.5 or vehicle daily per half face for 24 weeks. Subjects with acne requiring systemic treatment were excluded. Assessments included investigator atrophic acne scar count, Scar Global Assessment (SGA), acne lesion count, IGA, skin roughness and skin texture, subject self-assessment of clinical acne-related scars and satisfaction questionnaire, tolerability, and safety. Included subjects (n = 67) had mainly moderate acne (92.5% IGA 3); mean scores at baseline were approximately 40 acne lesions and 12 scars per half face. By week 24, the change from baseline in total scar count was - 15.5% for A0.3/BPO2.5 versus  + 14.4% for vehicle (approximately 30% difference), with a mean of 9.5 scars versus 13.3 per half face, respectively (p vehicle (p vehicle (p vehicle side, most commonly skin irritation (14.9 vs. 6%, respectively). Topical A0.3/BPO2.5 prevented and reduced atrophic scar formation. Scar count increased with vehicle (+ 14.4%) but decreased with A0.3/BPO2.5 (- 15.5%) over 24 weeks. ClinicalTrials.gov identifier NCT02735421.

03 Wessels 03.pmd

African Journals Online (AJOL)

Tienie01

12 Jun 2006 ... benadering definieer. Maria Edgeworth (1767-1849) het byvoorbeeld na 'n realistiese uitbeelding van haar samelewing gestreef en word as 'n belangrike invloed op beide Sir Walter Scott se historiese werke en Jane Austen se sosiale romans beskou. (Albei skrywers het haar bewonder en. 03 Wessels 03.

7 CFR 929.149 - Determination of sales history.

Science.gov (United States)

2010-01-01

... 7 Agriculture 8 2010-01-01 2010-01-01 false Determination of sales history. 929.149 Section 929... Determination of sales history. A sales history for each grower shall be computed by the Committee in the following manner. (a) For each grower with acreage with 7 or more years of sales history, a new sales...

33 CFR 149.416 - What are the requirements for a dry chemical fire suppression system?

Science.gov (United States)

2010-07-01

... the requirements for a dry chemical fire suppression system? Each natural gas deepwater port must be... dry chemical fire suppression system? 149.416 Section 149.416 Navigation and Navigable Waters COAST GUARD, DEPARTMENT OF HOMELAND SECURITY (CONTINUED) DEEPWATER PORTS DEEPWATER PORTS: DESIGN, CONSTRUCTION...

Inherently safe reactors

International Nuclear Information System (INIS)

Maartensson, Anders

1992-01-01

A rethinking of nuclear reactor safety has created proposals for new designs based on inherent and passive safety principles. Diverging interpretations of these concepts can be found. This article reviews the key features of proposed advanced power reactors. An evaluation is made of the degree of inherent safety for four different designs: the AP-600, the PIUS, the MHTGR and the PRISM. The inherent hazards of today's most common reactor principles are used as reference for the evaluation. It is concluded that claims for the new designs being inherently, naturally or passively safe are not substantiated by experience. (author)

45 CFR 149.315 - Reimbursement conditioned upon available funds.

Science.gov (United States)

2010-10-01

... 45 Public Welfare 1 2010-10-01 2010-10-01 false Reimbursement conditioned upon available funds... TO HEALTH CARE ACCESS REQUIREMENTS FOR THE EARLY RETIREE REINSURANCE PROGRAM Reimbursement Methods § 149.315 Reimbursement conditioned upon available funds. Notwithstanding a sponsor's compliance with...

The R and D issues necessary to achieve the safety design of commercialized liquid-metal cooled fast reactors

International Nuclear Information System (INIS)

Shoji, Kotake; Koji, Dozaki; Shigenobu, Kubo; Yoshio, Shimakawa; Hajime, Niwa; Masakazu, Ichimiya

2002-01-01

Within the framework of the feasibility study on commercialized fast reactor cycle systems (hereafter described as F/S), the safety design principle is investigated and several kinds of design studies are now in progress. Among the designs for liquid-metal cooled fast reactor (LMR), the advanced loop type sodium cooled fast reactor (FR) is one of the promising candidate as future commercialized LMR. In this paper, the safety related research and development (R and D) issues necessary to achieve the safety design are described along the defence-in-depth principle, taking account of not only the system characteristics of the advanced loop concepts but also design studies and R and D experiences so far. Safety issues related to the hypothetical core disruptive accidents (CDA) are emphasized both from the prevention and mitigation. A re-criticality free core concept with a special fuel assembly is pursued by performing both analytical and experimental efforts, in order to realize the rational design and to establish easy-to-understand safety logic. Sodium related issues are also given to ensure plant availability and to enhance the acceptability to the public. (authors)

16 CFR 14.9 - Requirements concerning clear and conspicuous disclosures in foreign language advertising and...

Science.gov (United States)

2010-01-01

... conspicuous disclosures in foreign language advertising and sales materials. 14.9 Section 14.9 Commercial... and conspicuous disclosures in foreign language advertising and sales materials. The Federal Trade...” disclosure of certain information in an advertisement or sales material in a newspaper, magazine, periodical...

Safety of DOE nuclear facilities. Hearings before the Subcommittee on Energy and Power of the Committee on Energy and Commerce, House of Representatives, One Hundredth Congress, First Session, H.R. 783, H.R. 2047 and H.R. 3123, November 5 and 19, 1987

International Nuclear Information System (INIS)

Anon.

1988-01-01

H.R. 783 is a bill to require the Secretary of Energy to ensure the compliance of certain operations of the Department of Energy (DOE) with Federal environmental standards and for other purposes. H.R. 2047 is a bill to establish a Defense Nuclear Facilities Safety Agency in order to provide for increased standards of safety with respect to radioactive emissions resulting from activities carried out at nuclear facilities of DOE. H.R. 3123 is a bill to create an independent oversight board to ensure the safety of United States Government nuclear facilities, to apply the provisions of OSHA to certain DOE nuclear facilities, to clarify the jurisdiction and powers of Government agencies dealing with nuclear wastes, to ensure independent research on the effects of radiation on human beings, and for other purposes

Phase II, randomized, open, controlled study of AS03-adjuvanted H5N1 pre-pandemic influenza vaccine in children aged 3 to 9 years: follow-up of safety and immunogenicity persistence at 24 months post-vaccination.

Science.gov (United States)

Díez-Domingo, Javier; Baldó, José-María; Planelles-Catarino, Maria Victoria; Garcés-Sánchez, María; Ubeda, Isabel; Jubert-Rosich, Angels; Marès, Josep; Garcia-Corbeira, Pilar; Moris, Philippe; Teko, Maurice; Vanden Abeele, Carline; Gillard, Paul

2015-03-01

An AS03-adjuvanted H5N1 influenza vaccine elicited broad and persistent immune responses with an acceptable safety profile up to 6 months following the first vaccination in children aged 3-9 years. In this follow-up of the Phase II study, we report immunogenicity persistence and safety at 24 months post-vaccination in children aged 3-9 years. The randomized, open-label study assessed two doses of H5N1 A/Vietnam/1194/2004 influenza vaccine (1·9 μg or 3·75 μg hemagglutinin antigen) formulated with AS03A or AS03B (11·89 mg or 5·93 mg tocopherol, respectively). Control groups received seasonal trivalent influenza vaccine. Safety was assessed prospectively and included potential immune-mediated diseases (pIMDs). Immunogenicity was assessed by hemagglutination-inhibition assay 12 and 24 months after vaccination; cross-reactivity and cell-mediated responses were also assessed. (NCT00502593). The safety population included 405 children. Over 24 months, five events fulfilled the criteria for pIMDs, of which four occurred in H5N1 vaccine recipients, including uveitis (n = 1) and autoimmune hepatitis (n = 1), which were considered to be vaccine-related. Overall, safety profiles of the vaccines were clinically acceptable. Humoral immune responses at 12 and 24 months were reduced versus those observed after the second dose of vaccine, although still within the range of those observed after the first dose. Persistence of cell-mediated immunity was strong, and CD4(+) T cells with a TH 1 profile were observed. Two doses of an AS03-adjuvanted H5N1 influenza vaccine in children showed low but persistent humoral immune responses and a strong persistence of cell-mediated immunity, with clinically acceptable safety profiles up to 24 months following first vaccination. © 2014 The Authors. Influenza and Other Respiratory Viruses Published by John Wiley & Sons Ltd.

Opportunistic nature of the mammalian microsporidia: experimental transmission of Trachipleistophora extenrec (Fungi: Microsporidia) between mammalian and insect hosts

Czech Academy of Sciences Publication Activity Database

Vávra, Jiří; Kamler, M.; Modrý, David; Koudela, Břetislav

2011-01-01

Roč. 108, č. 6 (2011), 1565-1573 ISSN 0932-0113 R&D Projects: GA ČR GD524/03/H133; GA ČR GA524/07/1003 Institutional research plan: CEZ:AV0Z60220518 Keywords : NOSEMA-ALGERAE * BRACHIOLA-ALGERAE * AIDS PATIENT * HOMINIS * INFECTION * PATHOGEN * DIPTERA * ULTRASTRUCTURE * CULICIDAE * SEQUENCES Subject RIV: GJ - Animal Vermins ; Diseases, Veterinary Medicine Impact factor: 2.149, year: 2011

Molecular evidence for the existence of cryptic species assemblages of several myxosporeans (Myxozoa)

Czech Academy of Sciences Publication Activity Database

Bartošová, Pavla; Fiala, Ivan

2011-01-01

Roč. 108, č. 3 (2011), s. 573-583 ISSN 0932-0113 R&D Project s: GA AV ČR KJB600960701; GA ČR GD524/03/H133; GA MŠk LC522 Institutional research plan: CEZ:AV0Z60220518 Keywords : SUBUNIT RIBOSOMAL-RNA * RUTILUS-RUTILUS LINNAEUS * LIFE -CYCLE * PHYLOGENY Subject RIV: EB - Genetics ; Molecular Biology Impact factor: 2.149, year: 2011

The role of chloride in deoxycorticosterone hypertension: selective sodium loading by diet or drinking fluid

Czech Academy of Sciences Publication Activity Database

Kuneš, Jaroslav; Zicha, Josef; Jelínek, Jiří

2004-01-01

Roč. 53, č. 2 (2004), s. 149-154 ISSN 0862-8408 R&D Projects: GA ČR GA305/03/0769; GA MŠk LN00A069 Institutional research plan: CEZ:AV0Z5011922 Keywords : sodium * chloride * DOCA-salt hypertension Subject RIV: FA - Cardiovascular Diseases incl. Cardiotharic Surgery Impact factor: 1.140, year: 2004

Prevalence and intensity of infections in the lymnaeid snail Omphiscola glabra experimentally infected with Fasciola hepatica, Fascioloides magna and Paramphistomum daubneyi

Czech Academy of Sciences Publication Activity Database

Dreyfuss, G.; Novobilský, A.; Vignoles, P.; Bellet, V.; Koudela, Břetislav; Rondelaud, D.

2007-01-01

Roč. 81, č. 1 (2007), s. 7-12 ISSN 0022-149X R&D Projects: GA ČR GD524/03/H133 Institutional research plan: CEZ:AV0Z60220518 Keywords : digenean infections of lymnaeid snail * intermediate host * free rediae and cercariae Subject RIV: EB - Genetics ; Molecular Biology Impact factor: 1.155, year: 2007

47 CFR 25.149 - Application requirements for ancillary terrestrial components in the mobile-satellite service...

Science.gov (United States)

2010-10-01

... 47 Telecommunication 2 2010-10-01 2010-10-01 false Application requirements for ancillary terrestrial components in the mobile-satellite service networks operating in the 1.5./1.6 GHz, 1.6/2.4 GHz and 2 GHz mobile-satellite service. 25.149 Section 25.149 Telecommunication FEDERAL COMMUNICATIONS...

Surface integrity evaluation of brass CW614N after impact of acoustically\

Czech Academy of Sciences Publication Activity Database

Lehocká, D.; Klich, Jiří; Foldyna, Josef; Hloch, Sergej; Hvizdoš, P.; Fides, M.; Botko, F.; Cárach, J.

2016-01-01

Roč. 149, č. 149 (2016), s. 236-244 E-ISSN 1877-7058. [International Conference on Manufacturing Engineering and Materials, ICMEM 2016. Nový Smokovec, 06.06.2016-10.06.2016] R&D Projects: GA MŠk(CZ) LO1406; GA MŠk ED2.1.00/03.0082 Institutional support: RVO:68145535 Keywords : pulsating water jet * surface integrity * mass material removal * brass * nanoindentation Subject RIV: JQ - Machines ; Tools http://www.sciencedirect.com/science/article/pii/S1877705816311705

Consequence Analysis of the MHTGR and PBMR

International Nuclear Information System (INIS)

Jeong, Jong Tae; Yang, Joon Eon; Lee, Won Jae

2006-01-01

The probabilistic safety assessment of the VHTR design provides a systematic analysis to identify and quantify all risks that the plant imposes to the operators, general public, and the environment and thus demonstrates compliance to regulatory risk criteria. During the preliminary conceptual design of VHTR in Korea, both block- and pebble type-fuel are considered. Therefore, the consequence analysis of VHTR using both types of fuel were made in order to obtain the basic insights for the classification of events and the formation of the PSA framework of the VHTR

Metholology for the selection of LWR safety R and D projects. Phase I, status report

International Nuclear Information System (INIS)

El-Sheikh, K.A.

1980-03-01

The objective of the LWR R and D Selection Methodology Program is to develop and demonstrate an R and D selection methodology appropriate for LWR safety technology. This report documents the development work from the program beginning in April, 1979 to the end of Fiscal Year 1979. The scope of work for this period included three tasks; methodology review (Task 1), measures development (Task 2), and methodology development for the first phase of application (Task 3). The accomplishments of these tasks are presented

Application of safety checklist to the analysis of the IEA-R1 reactor water retreatment system

International Nuclear Information System (INIS)

Sauer, Maria Eugenia Lago Jacques; Sara Neto, Antonio Jorge; Lima, Toni Carlos Caboclo de; Ribeiro, Maria Alice Morato

2005-01-01

In 1999, the management of the IEA-R1 Research Reactor (pool type - 5 MWth), located at IPEN/CNEN-SP, started the evaluation of the Reactor Pool Water Retreatment System to identify operational aspects, which could compromise the operators safety. The purpose was to identify and propose enhancements to the system which would be installed to substitute for the existing one. This process was conducted through a qualitative study of the system in operation. This study was carried out by a team composed of specialists in reactor operation, systems maintenance and radiological protection, and one safety analyst. The study consisted, basically, in local inspections to verify the physical and operational conditions of each equipment / component as well as aspects related to maintenance activities of the system. The process control and the operator procedures associated with the retreatment of the reactor pool water were also reviewed. The methodology adopted to develop the study was based in process hazard analysis technique named Safety Checklist. This paper presents a summary of this study and the main results obtained. Some operational and safety problems identified, the prevention and/or correction means to avoid them, and the recommendations and suggestions that have been implemented to the new design of the IEA-R1 Reactor Water Retreatment System, whose installation was concluded in 2003, are also presented. (author)

Hydro-abrasive disintegration of alloy Monel K-500 – the influence of technological and abrasive factors on the surface quality

Czech Academy of Sciences Publication Activity Database

Cárach, J.; Hloch, Sergej; Hlaváček, Petr; Gombár, M.; Klichová, Dagmar; Botko, F.; Mital, D.; Lehocká, D.

2016-01-01

Roč. 149, č. 149 (2016), s. 17-23 E-ISSN 1877-7058. [International Conference on Manufacturing Engineering and Materials, ICMEM 2016. Nový Smokovec, 06.06.2016-10.06.2016] R&D Projects: GA MŠk ED2.1.00/03.0082; GA MŠk(CZ) LO1406 Institutional support: RVO:68145535 Keywords : hydroabrasive disintegration * Alloy Monel K-500 * rotating workpiece * roughness parameters * material removal rate Subject RIV: JQ - Machines ; Tools http://www.sciencedirect.com/science/article/pii/S1877705816311328

Voltametrické stanovení genotoxických dinitronaftalenů pomocí meniskem modifikované stříbrné pevné amalgámové elektrody

Czech Academy of Sciences Publication Activity Database

Daňhel, A.; Pecková, K.; Čížek, K.; Barek, J.; Josypčuk, Bohdan; Navrátil, Tomáš

2007-01-01

Roč. 101, č. 2 (2007), s. 144-149 ISSN 0009-2770 R&D Projects: GA MŠk(CZ) LC06035; GA MPO 1H-PK/42; GA ČR GA203/03/0182 Institutional research plan: CEZ:AV0Z40400503 Keywords : polycyclic aromatic hydrocarbons * trace amounts * detector Subject RIV: CF - Physical ; Theoretical Chemistry Impact factor: 0.683, year: 2007

The modular high-temperature gas-cooled reactor - a new production reactor

International Nuclear Information System (INIS)

Nulton, J.D.

1990-01-01

One of the reactor concepts being considered for application as a new production reactor (NPR) is a 350-MW(thermal) modular high-temperature gas-cooled reactor (MHTGR). The proposed MHTGR-NPR is based on the design of the commercial MHTGR and is being developed by a team that includes General Atomics and Combustion Engineering. The proposed design includes four modules combined into a production block that includes a shared containment, a spent-fuel storage facility, and other support facilities. The MHTGR has a helium-cooled, graphite-moderated, graphite-reflected annular core formed from prismatic graphite fuel blocks. The MHTGR fuel consists of highly enriched uranium oxycarbide (UCO) microsphere fuel particles that are coated with successive layers of pyrolytic carbon (PyC) and silicon carbide (SiC). Tritium-producing targets consist of enriched 6 Li aluminate microsphere target particles that are coated with successive layers of PyC and SiC similar to the fuel microspheres. Normal reactivity control is implemented by articulated control rods that can be inserted into channels in the inner and outer reflector blocks. Shutdown heat removal is accomplished by a single shutdown heat exchanger and electric motor-driven circulator located in the bottom of the reactor vessel. Current plans are to stack spent fuel elements in dry, helium-filled, water-cooled wells and store them for ∼1 yr before reprocessing. All phases of MHTGR fuel reprocessing have been demonstrated

Economic characteristics of a smaller, simpler reactor

International Nuclear Information System (INIS)

LaBar, M.; Bowers, H.

1988-01-01

Reduced load growth and heightened concern with economic risk has led to an expressed utility preference for smaller capacity additions. The Modular High Temperature Reactor (MHTGR) plant has been developed as a small, simple plant that has limited financial risk and is economically competitive with comparatively sized coal plants. Competitive economics is achieved by the simplifications made possible in a small MHTGR, reduction in the quantity of nuclear grade construction and design standardization and certification. Assessments show the MHTGR plant to have an economic advantage over coal plants for plant sizes from 270 MWe to 1080 MWe. Financial risk is limited by small unit sizes and short lead times that allow incremental deployment. Evaluations show the MHTGR incremental deployment capability to reduce negative cash flows by almost a factor of 2 relative to that required by a single large nuclear plant

Safety Training: places available in April

CERN Multimedia

2012-01-01

There are places available in the forthcoming Safety courses. For updates and registrations, please refer to the Safety Training Catalogue. April 2012 (alphabetical order) Noise - Understanding the risks 18-APR-12, 10.00 – 12.30, in French Conduite de chariots élévateurs / Driving of forklifts 23-APR-12 to 24-APR-12, 09.00 – 17.30, in French (with possibility to have the handouts in English) First-aiders – Basic course 23-APR-12 to 24-APR-12, 08.30 – 17.30 and 08.30 – 12.30 (total: one day and a half), in French First Aiders - Refresher Course 24-APR-12, 13.30 – 17.30, in French Habilitation électrique personnel non électricien / Habilitation électrique for non electricians 02-APR-12 to 03-APR-12, 09.00 – 17.30 and 09.00 – 12.30 (total: one day and a half), in French Manipulation d’extincteurs : exercices sur feux réels / Use of fire extinguisher ...

An Artificial Neural Network Compensated Output Feedback Power-Level Control for Modular High Temperature Gas-Cooled Reactors

Directory of Open Access Journals (Sweden)

Zhe Dong

2014-02-01

Full Text Available Small modular reactors (SMRs could be beneficial in providing electricity power safely and also be viable for applications such as seawater desalination and heat production. Due to its inherent safety features, the modular high temperature gas-cooled reactor (MHTGR has been seen as one of the best candidates for building SMR-based nuclear power plants. Since the MHTGR dynamics display high nonlinearity and parameter uncertainty, it is necessary to develop a nonlinear adaptive power-level control law which is not only beneficial to the safe, stable, efficient and autonomous operation of the MHTGR, but also easy to implement practically. In this paper, based on the concept of shifted-ectropy and the physically-based control design approach, it is proved theoretically that the simple proportional-differential (PD output-feedback power-level control can provide asymptotic closed-loop stability. Then, based on the strong approximation capability of the multi-layer perceptron (MLP artificial neural network (ANN, a compensator is established to suppress the negative influence caused by system parameter uncertainty. It is also proved that the MLP-compensated PD power-level control law constituted by an experientially-tuned PD regulator and this MLP-based compensator can guarantee bounded closed-loop stability. Numerical simulation results not only verify the theoretical results, but also illustrate the high performance of this MLP-compensated PD power-level controller in suppressing the oscillation of process variables caused by system parameter uncertainty.

Assessment of research and development (R and D) needs in LPG safety and environmental control

Energy Technology Data Exchange (ETDEWEB)

DeSteese, J.G.

1982-05-01

The report characterizes the LPG industry covering all operations from production to end use, reviews current knowledge of LPG release phenomenology, summarizes the status of current LPG release prevention and control methodology, and identifies any remaining safety and environmental problems and recommends R and D strategies that may mitigate these problems. (ACR)

Xe-135 and Sm-149 Isotopic Evolution Analysis Xesamo code; Analisis de la Evolucion Isotopica del Xe-135 y Sm-149. Programa Xesamo

Energy Technology Data Exchange (ETDEWEB)

Caro, R; Gallego, J; Martinez Fanegas, R

1977-07-01

In this report the time evolution analysis of the nuclides concentration Xe-135 and Sm-149 as a function of the neutron flux is carried out. The neutron flux may be any function of time. It is analyzed as well the reactivity changes associated with the xenon and samarium concentration variations. (Author) 5 refs.

Draft report: a selection methodology for LWR safety R and D programs and proposals

International Nuclear Information System (INIS)

Husseiny, A.A.; Ritzman, R.L.

1980-03-01

The results of work done to develop a methodology for selecting LWR safety R and D programs and proposals is described. A critical survey of relevant decision analysis methods is provided including the specifics of multiattribute utility theory. This latter method forms the basis of the developed selection methodology. Details of the methodology and its use are provided along with a sample illustration of its application

Draft report: a selection methodology for LWR safety R and D programs and proposals

Energy Technology Data Exchange (ETDEWEB)

Husseiny, A. A.; Ritzman, R. L.

1980-03-01

The results of work done to develop a methodology for selecting LWR safety R and D programs and proposals is described. A critical survey of relevant decision analysis methods is provided including the specifics of multiattribute utility theory. This latter method forms the basis of the developed selection methodology. Details of the methodology and its use are provided along with a sample illustration of its application.

Modernization of Safety and Control Instrumentation of the IEA-R1 Research Reactor

Energy Technology Data Exchange (ETDEWEB)

De Carvalho, P.V., E-mail: paulov@ien.gov.br [Institute of Nuclear Engineering (IEN), National Nuclear Energy Commission (CNEN), Rio de Janeiro (Brazil)

2014-08-15

The research reactor IEA-R1 located in the Institute of Energy and Nuclear Research (IPEN), São Paulo, Brazil, obtained its first criticality on 16 September 1957 and since then has served the scientific and medical community in the performance of experiments in applied nuclear physics, as well as the provision of radioisotopes for production of radiopharmaceuticals. The reactor produces radioisotopes {sup 82}Br and {sup 41}Ar for special processes in industrial inspection and {sup 192}Ir and {sup 198}Au as sources of radiation used in brachytherapy, {sup 153}Sm for pain relief in patients with bone metastasis, and calibrated sources of {sup 133}Ba, {sup 137}Cs, {sup 57}Co, {sup 60}Co, {sup 241}Am and {sup 152}Eu used in medical clinics and hospitals practicing nuclear medicine and research laboratories. Services are offered in regular non-destructive testing by neutron radiography, neutron irradiation of silicon for phosphorous doping and other various irradiations with neutrons. The reactor is responsible for producing approximately 70% of radiopharmaceutical {sup 131}I used in Brazil, which saves about US$ 800 000 annually for the country. After more than 50 years of use, most of its equipment and systems have been modernized, and recently the reactor power was increased to 5 MW in order to enhance radioisotope production capability. However, the control room and nuclear instrumentation system used for reactor safety have operated more than 30 years and require constant maintenance. Many equipment and electronic components are obsolete, and replacements are not available in the market. The modernization of the nuclear safety and control instrumentation systems of IEA-R1 is being carried out with consideration for the internationally recognized criteria for safety and reliable reactor operations and the latest developments in nuclear electronic technology. The project for the new reactor instrumentation system specifies three wide range neutron monitoring

Photocycle dynamics of the E149A mutant of cryptochrome 3 from Arabidopsis thaliana.

Science.gov (United States)

Zirak, P; Penzkofer, A; Moldt, J; Pokorny, R; Batschauer, A; Essen, L-O

2009-11-09

The E149A mutant of the cryDASH member cryptochrome 3 (cry3) from Arabidopsis thaliana was characterized in vitro by optical absorption and emission spectroscopic studies. The mutant protein non-covalently binds the chromophore flavin adenine dinucleotide (FAD). In contrast to the wild-type protein it does not bind N5,N10-methenyl-5,6,7,8-tetrahydrofolate (MTHF). Thus, the photo-dynamics caused by FAD is accessible without the intervening coupling with MTHF. In dark adapted cry3-E149A, FAD is present in the oxidized form (FAD(ox)), semiquinone form (FADH(.)), and anionic hydroquinone form (FAD(red)H(-)). Blue-light photo-excitation of previously unexposed cry3-E149A transfers FAD(ox) to the anionic semiquinone form (FAD()(-)) with a quantum efficiency of about 2% and a back recovery time of about 10s (photocycle I). Prolonged photo-excitation leads to an irreversible protein re-conformation with structure modification of the U-shaped FAD and enabling proton transfer. Thus, a change in the photocycle dynamics occurs with photo-conversion of FAD(ox) to FADH(.), FADH(.) to FAD(red)H(-), and thermal back equilibration in the dark (photocycle II). The photocycle dynamics of cry3-E149A is compared with the photocycle behaviour of wild-type cry3 and other photo-sensory cryptochromes.

Flight test report: Focke wulf PIAGGIO P149D-TP

CSIR Research Space (South Africa)

Barker, D

2015-12-01

Full Text Available It’s a story of following one’s dream. Belonging to Werner Heiml, ZU-SFP originated from Germany where it was used as a basic trainer in the Luftwaffe. The P149D was originally developed and manufactured by Piaggio & Co, Italy, in 1953...

In vitro analysis of the invasive phenotype of SUM 149, an inflammatory breast cancer cell line

Directory of Open Access Journals (Sweden)

Dharmawardhane Suranganie F

2005-04-01

Full Text Available Abstract Background Inflammatory breast cancer (IBC is the most lethal form of locally invasive breast cancer known. However, very little information is available on the cellular mechanisms responsible for manifestation of the IBC phenotype. To understand the unique phenotype of IBC, we compared the motile and adhesive interactions of an IBC cell line, SUM 149, to the non-IBC cell line SUM 102. Results Our results demonstrate that both IBC and non-IBC cell lines exhibit similar adhesive properties to basal lamina, but SUM 149 showed a marked increase in adhesion to collagen I. In vitro haptotaxis assays demonstrate that SUM 149 was less invasive, while wound healing assays show a less in vitro migratory phenotype for SUM 149 cells relative to SUM 102 cells. We also demonstrate a role for Rho and E-cadherin in the unique invasive phenotype of IBC. Immunoblotting reveals higher E-cadherin and RhoA expression in the IBC cell line but similar RhoC expression. Rhodamine phalloidin staining demonstrates increased formation of actin stress fibers and larger focal adhesions in SUM 149 relative to the SUM 102 cell line. Conclusion The observed unique actin and cellular architecture as well as the invasive and adhesive responses to the extracellular matrix of SUM 149 IBC cells suggest that the preference of IBC cells for connective tissue, possibly a mediator important for the vasculogenic mimicry via tubulogenesis seen in IBC pathological specimens. Overexpression of E-cadherin and RhoA may contribute to passive dissemination of IBC by promoting cell-cell adhesion and actin cytoskeletal structures that maintain tissue integrity. Therefore, we believe that these findings indicate a passive metastatic mechanism by which IBC cells invade the circulatory system as tumor emboli rather than by active migratory mechanisms.

SAFETY BULLETIN TIS 2002-03 GLASS DOORS

CERN Multimedia

2002-01-01

Be careful! What happened?   Unsignaled reinforced glass.   Signaled safety glass.   A visitor recently hurt his leg when he walked into a glass door which shattered from the impact. This door was made of reinforced glass, a material which is inappropriate for this kind of use as it is too fragile. Indeed, it shatters into sharp splinters which can cause serious injury. Furthermore, the door was not easily visible (badly lit, no warning signs, ...). Corrective measures Just after the accident: glass doors were signed to make them more visible; replacement of dangerous glass panes planned for 2003. What preventive measures can be taken against this kind of accident? If you are in charge of projects and works: In the call for tender, specify the acceptable shock resistance level of the glass pane; Before the door is mounted, insist on receiving technical documentation and/or certificate of conformity from the supplier; If in doubt, ask advice from the TIS/GS sa...

The modular high-temperature gas-cooled reactor: A cost/risk competitive nuclear option

International Nuclear Information System (INIS)

Gotschall, H.L.

1994-01-01

The business risks of nuclear plant ownership are identified as a constraint on the expanded use of nuclear power. Such risks stem from the exacting demands placed on owner/operator organizations of current plants to demonstrate ongoing compliance with safety regulations and the resulting high costs for operation and maintenance. This paper describes the Modular High-Temperature Gas-Cooled Reactor (MHTGR) design, competitive economics, and approach to reducing the business risks of nuclear plant ownership

Reference modular High Temperature Gas-Cooled Reactor Plant: Concept description report

International Nuclear Information System (INIS)

1986-10-01

This report provides a summary description of the Modular High Temperature Gas-Cooled Reactor (MHTGR) concept and interim results of assessments of costs, safety, constructibility, operability, maintainability, and availability. Conceptual design of this concept was initiated in October 1985 and is scheduled for completion in 1987. Participating industrial contractors are Bechtel National, Inc. (BNI), Stone and Webster Engineering Corporation (SWEC), GA Technologies, Inc. (GA), General Electric Co. (GE), and Combustion Engineering, Inc

Reference modular High Temperature Gas-Cooled Reactor Plant: Concept description report

Energy Technology Data Exchange (ETDEWEB)

1986-10-01

This report provides a summary description of the Modular High Temperature Gas-Cooled Reactor (MHTGR) concept and interim results of assessments of costs, safety, constructibility, operability, maintainability, and availability. Conceptual design of this concept was initiated in October 1985 and is scheduled for completion in 1987. Participating industrial contractors are Bechtel National, Inc. (BNI), Stone and Webster Engineering Corporation (SWEC), GA Technologies, Inc. (GA), General Electric Co. (GE), and Combustion Engineering, Inc. (C-E).

Safety, efficacy and pharmacokinetics of rVIII-SingleChain in children with severe hemophilia A: results of a multicenter clinical trial.

Science.gov (United States)

Stasyshyn, O; Djambas Khayat, C; Iosava, G; Ong, J; Abdul Karim, F; Fischer, K; Veldman, A; Blackman, N; St Ledger, K; Pabinger, I

2017-04-01

Essentials rVIII-SingleChain is a novel recombinant factor VIII with covalently bonded heavy and light chains. Efficacy, safety and pharmacokinetics were studied in pediatric patients with severe hemophilia A. Across all prophylaxis regimens, the median annualized spontaneous bleeding rate was 0.00. rVIII-SingleChain showed excellent hemostatic efficacy and a favorable safety profile. Background rVIII-SingleChain is a novel B-domain truncated recombinant factor VIII (rFVIII) comprised of covalently bonded FVIII heavy and light chains, demonstrating a high binding affinity to von Willebrand factor. Objectives This phase III study investigated the safety, efficacy and pharmacokinetics of rVIII-SingleChain in previously treated pediatric patients hemophilia A. Patients/Methods Patients could be assigned to prophylaxis or on-demand therapy by the investigator. For patients assigned to prophylaxis, the treatment regimen and dose were based on the bleeding phenotype. For patients receiving on-demand therapy, dosing was guided by World Federation of Hemophilia recommendations. The primary endpoint was treatment success, defined as a rating of 'excellent' or 'good' on the investigator's clinical assessment of hemostatic efficacy for all treated bleeding events. Results The study enrolled 84 patients (0 to 50 EDs. In the 347 bleeds treated and evaluated by the investigator, hemostatic efficacy was rated as excellent or good in 96.3%. The median annualized spontaneous bleeding rate was 0.00 (Q1, Q3: 0.00, 2.20), and the median annualized bleeding rate was 3.69 (Q1, Q3: 0.00, 7.20) across all prophylaxis regimens. No participant developed an inhibitor. Conclusions rVIII-SingleChain is a novel rFVIII molecule showing excellent hemostatic efficacy and a favorable safety profile in a clinical study in children hemophilia A. © 2017 The Authors. Journal of Thrombosis and Haemostasis published by Wiley Periodicals, Inc. on behalf of International Society on Thrombosis and

The 0.3-kb fragment containing the R-U5-5'leader sequence of Friend murine leukemia virus influences the level of protein expression from spliced mRNA.

Science.gov (United States)

Choo, Yeng Cheng; Seki, Yohei; Machinaga, Akihito; Ogita, Nobuo; Takase-Yoden, Sayaka

2013-04-19

A neuropathogenic variant of Friend murine leukemia virus (Fr-MLV) clone A8 induces spongiform neurodegeneration when infected into neonatal rats. Studies with chimeras constructed from the A8 virus and the non-neuropathogenic Fr-MLV clone 57 identified a 0.3-kb KpnI-AatII fragment containing a R-U5-5'leader sequence as an important determinant for inducing spongiosis, in addition to the env gene of A8 as the primary determinant. This 0.3-kb fragment contains a 17-nucleotide difference between the A8 and 57 sequences. We previously showed that the 0.3-kb fragment influences expression levels of Env protein in both cultured cells and rat brain, but the corresponding molecular mechanisms are not well understood. Studies with expression vectors constructed from the full-length proviral genome of Fr-MLV that incorporated the luciferase (luc) gene instead of the env gene found that the vector containing the A8-0.3-kb fragment yielded a larger amount of spliced luc-mRNA and showed higher expression of luciferase when compared to the vector containing the 57-0.3-kb fragment. The amount of total transcripts from the vectors, the poly (A) tail length of their mRNAs, and the nuclear-cytoplasm distribution of luc-mRNA in transfected cells were also evaluated. The 0.3-kb fragment did not influence transcription efficiency, mRNA polyadenylation or nuclear export of luc-mRNA. Mutational analyses were carried out to determine the importance of nucleotides that differ between the A8 and 57 sequences within the 0.3-kb fragment. In particular, seven nucleotides upstream of the 5'splice site (5'ss) were found to be important in regulating the level of protein expression from spliced messages. Interestingly, these nucleotides reside within the stem-loop structure that has been speculated to limit the recognition of 5'ss. The 0.3-kb fragment containing the R-U5-5'leader sequence of Fr-MLV influences the level of protein expression from the spliced-mRNA by regulating the splicing

A comparative study of Ro 03-8799: racemic mixture and enantiomers

International Nuclear Information System (INIS)

Newman, H.F.V.; Bleehen, N.M.; Workman, P.; Dunphy, E.P.; Dische, S.; Saunders, M.I.; Des Rochers, C.; Lenox-Smith, I.; Smithen, C.E.

1986-01-01

The maximum single dose of the 2-nitroimidazole hypoxic cell radiosensitiser Ro 03-8799 is limited to 1 g/m 2 by the occurrence of a well characterised acute syndrome of sweating, nausea and mental changes. In an attempt to increase the tolerable dose, the clinical toxicity of the racemic mixture was compared with that of the R- and S-enantiomers of Ro 03-8799. Twelve patients received escalating alternate doses of racemic mixture and R- or S-enantiomer, the dose levels being 0.25 g/m 2 , 0.5 g/m 2 , 0.75 g/m 2 and 1.0 g/m 2 . Careful monitoring of the acute syndrome failed to demonstrate any consistent differences between racemic mixture and either enantiomer. This would suggest that the toxicity is not mediated via any specific central nervous system receptor. It is concluded that separation of Ro 03-8799 into its enantiomers will not enable a clinically useful increase in dosage. (author)

ETSON views on R and D priorities for implementation of the 2014 Euratom Directive on safety of nuclear installations

Energy Technology Data Exchange (ETDEWEB)

Van Dorsselaere, Jean-Pierre [IRSN/PSN, Saint-Paul-lez-Durance (France); Mustoe, Jeremy; Power, Steve [Amec Foster Wheeler RSD, Birchwood Park, Warrington (United Kingdom); Adorni, Martina [Bel V, Brussels (Belgium); Schaffrath, Andreas [Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) gGmbH, Garching (Germany); Nieminen, Anna [VTT Technical Research Centre of Finland Ltd. (Finland)

2016-11-15

Following the Fukushima-Daiichi accident in 2011, the Council Directive 2014/87/Euratom has reinforced the previous 2009 Directive that had established a Community framework for the safety of nuclear installations. In particular, one new article introduces a high-level EU-wide safety objective of preventing accidents through defence- in-depth and avoiding radioactive releases outside a nuclear installation. For achieving this objective, the research necessary outcomes are mainly a better knowledge of the involved physical phenomena and its capitalization in methodologies and tools such as simulation codes. ETSON, the European Technical Safety Organisation Network, had already identified in its Position Paper in 2011 the main R and D priorities. The present paper underlines that most of these priorities, with a few updates due to progress of knowledge, remain consistent with the objectives of this new Directive. And it illustrates the ETSON involvement through examples of on-going or planned R and D national and international projects.

The development of technologies of safety analysis for LMR ('03)

International Nuclear Information System (INIS)

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

2004-03-01

The developmental objectives of the project, 'The development of safety analysis techniques in LMR', are the code development for the subchannel blockage analysis, the code development for the system transient analysis, the code development for the HCDA(Hypothetical Core Disruptive Accident) analysis, the preliminary safety analysis for KALIMER-600 equipped with the components of new concepts, and the establishment of data base. The purpose of the analysis for subchannel blockage in the subassembly of LMR is to represent quantitatively that the maximum damage due to the accident is within the safety criteria. The computational program should be developed to simulate the thermal hydraulic phenomena and to verify the safety of LMR for the accident. For the purpose, the hybrid scheme has been implemented into the MATRA-LMR code based on the upwind scheme to analyze the various flow fields occurred in the subchannel blockage accident. The turbulent mixing models using the CFX code were assessed to compute more precisely the heat transfer between subchannels. Through this assessment, empirical correction factors of 1.7 for the heat conduction, 0.006 for the turbulent mixing coefficient were obtained. The distributed resistance model instead of wire forcing function has been developed to represent the more exact flow field due to wire-wrap. Other models, such as heat conductor model and various turbulent mixing model, have been implemented into the MATRA-LMR. The ORNL THORS 19-Pin FFM-5B tests have been assessed to validate above new models using the improved MATRA-LMR. The results using MATRA-LMR were well agreed with the experimental data. The subchannel blockage accidents which assumed to be occurred at the three locations for the conceptual plant of KALIMER-600 have been analysed according to blockage size using the MATRA-LMR code. The results of calculations for the design basis events which 6 subchannels were blocked showed the margins of the 290 7.dog. C up to the

New Safety rules

CERN Multimedia

Safety Commission

2008-01-01

The revision of CERN Safety rules is in progress and the following new Safety rules have been issued on 15-04-2008: Safety Procedure SP-R1 Establishing, Updating and Publishing CERN Safety rules: http://cern.ch/safety-rules/SP-R1.htm; Safety Regulation SR-S Smoking at CERN: http://cern.ch/safety-rules/SR-S.htm; Safety Regulation SR-M Mechanical Equipment: http://cern.ch/safety-rules/SR-M.htm; General Safety Instruction GSI-M1 Standard Lifting Equipment: http://cern.ch/safety-rules/GSI-M1.htm; General Safety Instruction GSI-M2 Standard Pressure Equipment: http://cern.ch/safety-rules/GSI-M2.htm; General Safety Instruction GSI-M3 Special Mechanical Equipment: http://cern.ch/safety-rules/GSI-M3.htm. These documents apply to all persons under the Director General’s authority. All Safety rules are available at the web page: http://www.cern.ch/safety-rules The Safety Commission

Beta-delayed proton activities: 147Dy and 149Er

International Nuclear Information System (INIS)

Toth, K.S.; Moltz, D.M.; Schloemer, E.C.; Cable, M.D.; Avignone, F.T. III; Ellis-Akovali, Y.A.

1984-01-01

The present paper discusses mainly the β-delayed proton spectra of 147 Dy and of the hitherto unknown isotope, 149 Er. However, following the submittal of the abstract for this conference we have now observed delayed protons following the decay of 145 Dy. Additionally, we have identified a 0.5-s delayed-proton emitter and tentatively assign it to the new isotope, 151 Yb

Safety and persistence of the humoral and cellular immune responses induced by 2 doses of an AS03-adjuvanted A(H1N1)pdm09 pandemic influenza vaccine administered to infants, children and adolescents: Two open, uncontrolled studies.

Science.gov (United States)

Garcia-Sicilia, José; Arístegui, Javier; Omeñaca, Félix; Carmona, Alfonso; Tejedor, Juan C; Merino, José M; García-Corbeira, Pilar; Walravens, Karl; Bambure, Vinod; Moris, Philippe; Caplanusi, Adrian; Gillard, Paul; Dieussaert, Ilse

2015-01-01

In children, 2 AS03-adjuvanted A(H1N1)pdm09 vaccine doses given 21 days apart were previously shown to induce a high humoral immune response and to have an acceptable safety profile up to 42 days following the first vaccination. Here, we analyzed the persistence data from 2 open-label studies, which assessed the safety, and humoral and cell-mediated immune responses induced by 2 doses of this vaccine. The first study was a phase II, randomized trial conducted in 104 children aged 6-35 months vaccinated with the A(H1N1)pdm09 vaccine containing 1.9 µg haemagglutinin antigen (HA) and AS03B (5.93 mg tocopherol) and the second study, a phase III, non-randomized trial conducted in 210 children and adolescents aged 3-17 years vaccinated with the A(H1N1)pdm09 vaccine containing 3.75 µg HA and AS03A (11.86 mg tocopherol). Approximately one year after the first dose, all children with available data were seropositive for haemagglutinin inhibition and neutralising antibody titres, but a decline in geometric mean antibody titres was noted. The vaccine induced a cell-mediated immune response in terms of antigen-specific CD4(+) T-cells, which persisted up to one year post-vaccination. The vaccine did not raise any safety concern, though these trials were not designed to detect rare events. In conclusion, 2 doses of the AS03-adjuvanted A(H1N1)pdm09 vaccine at 2 different dosages had a clinically acceptable safety profile, and induced high and persistent humoral and cell-mediated immune responses in children aged 6-35 months and 3-17 years. These studies have been registered at www.clinicaltrials.gov NCT00971321 and NCT00964158.

A new million-channel analyzer for complex nuclear spectroscopy studies and its application in measurements of the β decay of 149Pr

International Nuclear Information System (INIS)

Tenten, W.

1978-11-01

A million-channel analyzer with CAMAC instrumentation and PDP-11 control computer was developed and tested using the case of the β decay of 149 Pr and the γ decays of 149 Nd. A level scheme for 149 Nd was developed. (WL) [de

75 FR 53701 - Clinical Studies of Safety and Effectiveness of Orphan Products Research Project Grant (R01...

Science.gov (United States)

2010-09-01

... DEPARTMENT OF HEALTH AND HUMAN SERVICES Food and Drug Administration [Docket No. FDA-2010-N-0394] Clinical Studies of Safety and Effectiveness of Orphan Products Research Project Grant (R01); Correction AGENCY: Food and Drug Administration, HHS. ACTION: Notice; correction. SUMMARY: The Food and Drug...

Numerical Simulation of Fatigue Crack Growth in Hip Implants

Czech Academy of Sciences Publication Activity Database

Colic, K.; Sedmak, A.; Grbovic, A.; Burzić, M.; Hloch, Sergej; Sedmak, S.

2016-01-01

Roč. 149, č. 149 (2016), s. 229-235 E-ISSN 1877-7058. [International Conference on Manufacturing Engineering and Materials, ICMEM 2016. Nový Smokovec, 06.06.2016-10.06.2016] R&D Projects: GA MŠk ED2.1.00/03.0082; GA MŠk(CZ) LO1406 Institutional support: RVO:68145535 Keywords : biomedical application design * extended finite element method (XFEM) * Ti-6Al-4V alloy * stress intensity factor (SIF) * fatigue crack growth Subject RIV: JQ - Machines ; Tools http://www.sciencedirect.com/science/article/pii/S1877705816311699

76 FR 69324 - Office of Hazardous Materials Safety; Notice of Delays in Processing of Special Permits Applications

Science.gov (United States)

2011-11-08

... Memphis, TN. 11984-R Heritage 4 03-31-2012 Transport, LLC, Indianapolis, IN. 5112-R U.S. Department 4 03.... 8445-R Heritage 4 03-31-2012 Transport, LLC, Indianapolis, IN. 4850-R Accurate 4 03-31-2012 Energetic... Letters), Basking Ridge, NJ. 7594-R Bromine 4 03-31-2012 Compounds, Ltd., Beer Sheva, UT. 9623-R Buckley...

Food safety evaluation for R-proteins introduced by biotechnology: A case study of VNT1 in late blight protected potatoes.

Science.gov (United States)

Habig, Jeffrey W; Rowland, Aaron; Pence, Matthew G; Zhong, Cathy X

2018-06-01

Resistance genes (R-genes) from wild potato species confer protection against disease and can be introduced into cultivated potato varieties using breeding or biotechnology. The R-gene, Rpi-vnt1, which encodes the VNT1 protein, protects against late blight, caused by Phytophthora infestans. Heterologous expression and purification of active VNT1 in quantities sufficient for regulatory biosafety studies was problematic, making it impractical to generate hazard characterization data. As a case study for R-proteins, a weight-of-evidence, tiered approach was used to evaluate the safety of VNT1. The hazard potential of VNT1 was identified from relevant safety information including history of safe use, bioinformatics, mode of action, expression levels, and dietary intake. From the assessment it was concluded that Tier II hazard characterization was not needed. R-proteins homologous to VNT1 and identified in edible crops, have a history of safe consumption. VNT1 does not share sequence identity with known allergens. Expression levels of R-proteins are generally low, and VNT1 was not detected in potato varieties expressing the Rpi-vnt1 gene. With minimal hazard and negligible exposure, the risks associated with consumption of R-proteins in late blight protected potatoes are exceedingly low. R-proteins introduced into potatoes to confer late blight protection are safe for consumption. Copyright © 2018 Elsevier Inc. All rights reserved.

33 CFR 149.313 - How must survival craft be arranged?

Science.gov (United States)

2010-07-01

... 33 Navigation and Navigable Waters 2 2010-07-01 2010-07-01 false How must survival craft be... Equipment Manned Deepwater Port Requirements § 149.313 How must survival craft be arranged? The operator must arrange survival craft so that they meet the requirements of 46 CFR 108.525 (a) and § 108.530 and...

Xe-135 and Sm-149 Isotopic Evolution Analysis Xesamo code

International Nuclear Information System (INIS)

Caro, R.; Gallego, J.; Martinez Fanegas, R.

1977-01-01

In this report the time evolution analysis of the nuclides concentration Xe-135 and Sm-149 as a function of the neutron flux is carried out. The neutron flux may be any function of time. It is analyzed as well the reactivity changes associated with the xenon and samarium concentration variations. (Author) 5 refs

Safety Risk Knowledge Elicitation in Support of Aeronautical R and D Portfolio Management: A Case Study

Science.gov (United States)

Shih, Ann T.; Ancel, Ersin; Jones, Sharon Monica; Reveley, Mary S.; Luxhoj, James T.

2012-01-01

Aviation is a problem domain characterized by a high level of system complexity and uncertainty. Safety risk analysis in such a domain is especially challenging given the multitude of operations and diverse stakeholders. The Federal Aviation Administration (FAA) projects that by 2025 air traffic will increase by more than 50 percent with 1.1 billion passengers a year and more than 85,000 flights every 24 hours contributing to further delays and congestion in the sky (Circelli, 2011). This increased system complexity necessitates the application of structured safety risk analysis methods to understand and eliminate where possible, reduce, and/or mitigate risk factors. The use of expert judgments for probabilistic safety analysis in such a complex domain is necessary especially when evaluating the projected impact of future technologies, capabilities, and procedures for which current operational data may be scarce. Management of an R&D product portfolio in such a dynamic domain needs a systematic process to elicit these expert judgments, process modeling results, perform sensitivity analyses, and efficiently communicate the modeling results to decision makers. In this paper a case study focusing on the application of an R&D portfolio of aeronautical products intended to mitigate aircraft Loss of Control (LOC) accidents is presented. In particular, the knowledge elicitation process with three subject matter experts who contributed to the safety risk model is emphasized. The application and refinement of a verbal-numerical scale for conditional probability elicitation in a Bayesian Belief Network (BBN) is discussed. The preliminary findings from this initial step of a three-part elicitation are important to project management practitioners as they illustrate the vital contribution of systematic knowledge elicitation in complex domains.

Nordic Nuclear Safety Research 1994 - 2008: From standardized 4-year classics to customized R and B

International Nuclear Information System (INIS)

Bennerstedt, T.N.O.

2011-10-01

This is a presentation of NKS (Nordic Nuclear Safety Research), its work and achievements in the years 1994 - 2008, during which the author served as Nordic secretary and (later) as coordinator. NKS and the Nordic perspective are briefly introduced together with the NKS support structure, organization and administration: Owners, Board, Nordic secretary, Bureau and Secretariat. The author then embarks on a journey through the modern history of NKS work. The last two of the six fixed 4-year programs are described as regards planning, contents, project work, administration, dissemination of results, evaluations and conclusions. The trip continues to the land of R and B and the present (2011) structure of two general frameworks, namely, NKS-R: reactor safety, and NKS-B: emergency preparedness; each consisting of a set of flexible activities; hence, R and B. The reasoning behind this makeover is touched upon together with the new organization and simpler administration that developed. Major activities and the produced results are introduced and the evaluations summarized. The author's own conclusions and recommendations are followed by a short and subjective list of references. In a number of appendices some important background material has been compiled: bullet point versions of minutes of Owners Group and Board meetings; economic contributions and budgets; the NKS policy document; an overview of all NKS programs and evaluations; lists of R and B activities and funding; the author's personal remarks; a list of some NKS documents (other than technical reports and minutes); and a list of acronyms used in this report. (Author)

Nordic Nuclear Safety Research 1994 - 2008: From standardized 4-year classics to customized R and B

Energy Technology Data Exchange (ETDEWEB)

Bennerstedt, T N.O. [TeknoTelje HB, Torhamn (Sweden)

2011-10-15

This is a presentation of NKS (Nordic Nuclear Safety Research), its work and achievements in the years 1994 - 2008, during which the author served as Nordic secretary and (later) as coordinator. NKS and the Nordic perspective are briefly introduced together with the NKS support structure, organization and administration: Owners, Board, Nordic secretary, Bureau and Secretariat. The author then embarks on a journey through the modern history of NKS work. The last two of the six fixed 4-year programs are described as regards planning, contents, project work, administration, dissemination of results, evaluations and conclusions. The trip continues to the land of R and B and the present (2011) structure of two general frameworks, namely, NKS-R: reactor safety, and NKS-B: emergency preparedness; each consisting of a set of flexible activities; hence, R and B. The reasoning behind this makeover is touched upon together with the new organization and simpler administration that developed. Major activities and the produced results are introduced and the evaluations summarized. The author's own conclusions and recommendations are followed by a short and subjective list of references. In a number of appendices some important background material has been compiled: bullet point versions of minutes of Owners Group and Board meetings; economic contributions and budgets; the NKS policy document; an overview of all NKS programs and evaluations; lists of R and B activities and funding; the author's personal remarks; a list of some NKS documents (other than technical reports and minutes); and a list of acronyms used in this report. (Author)

Nordic Nuclear Safety Research 1994 - 2008: From standardized 4-year classics to customized R and B

Energy Technology Data Exchange (ETDEWEB)

Bennerstedt, T.N.O. (TeknoTelje HB, Torhamn (Sweden))

2011-10-15

This is a presentation of NKS (Nordic Nuclear Safety Research), its work and achievements in the years 1994 - 2008, during which the author served as Nordic secretary and (later) as coordinator. NKS and the Nordic perspective are briefly introduced together with the NKS support structure, organization and administration: Owners, Board, Nordic secretary, Bureau and Secretariat. The author then embarks on a journey through the modern history of NKS work. The last two of the six fixed 4-year programs are described as regards planning, contents, project work, administration, dissemination of results, evaluations and conclusions. The trip continues to the land of R and B and the present (2011) structure of two general frameworks, namely, NKS-R: reactor safety, and NKS-B: emergency preparedness; each consisting of a set of flexible activities; hence, R and B. The reasoning behind this makeover is touched upon together with the new organization and simpler administration that developed. Major activities and the produced results are introduced and the evaluations summarized. The author's own conclusions and recommendations are followed by a short and subjective list of references. In a number of appendices some important background material has been compiled: bullet point versions of minutes of Owners Group and Board meetings; economic contributions and budgets; the NKS policy document; an overview of all NKS programs and evaluations; lists of R and B activities and funding; the author's personal remarks; a list of some NKS documents (other than technical reports and minutes); and a list of acronyms used in this report. (Author)

Multi-purpose nuclear heat source for advanced gas-cooled reactor plants

International Nuclear Information System (INIS)

McDonald, C.F.

1993-01-01

Nuclear power has the potential to be the ultimate green technology in that it could eliminate the need for burning fossil fuels with their polluting combustion products and greenhouse gases. This view is shared by many technologists, but it may be a generation before the public becomes convinced, and that will involve overcoming many safety, institutional, financial, and technical impediments. This paper addresses only the latter topic; a major theme being that for nuclear power to truly be a green technology and significantly benefit society, it must meet the needs of the full energy spectrum. Specifically, it must satisfy energy needs beyond just the electricity generating sector by today's nuclear plants. By virtue of its high temperature capability, the Modular High Temperature Gas-Cooled Reactor (MHTGR) is the only type of reactor that has the potential to meet the wide range of energy needs that will emerge in the future. This paper discusses the nuclear heat source that gives the MHTGR multi-purpose capability, which is recognized today, but will not be implemented until early in the next century

Residues Phe103 and Phe149 are critical for the co-chaperone activity of Bacillus licheniformis GrpE.

Science.gov (United States)

Lin, Min-Guan; Chi, Meng-Chun; Chen, Bo-En; Wang, Tzu-Fan; Lo, Huei-Fen; Lin, Long-Liu

2015-01-01

A tryptophan-free Bacillus licheniformis nucleotide exchange factor (BlGrpE) and its Trp mutants (F70W, F103W, F149W, F70/103W, F70/149W, F103/149W and F70/103/149W) were over-expressed and purified to near homogeneity. Simultaneous addition of B. licheniformis DnaJ, NR-peptide and individual variants synergistically stimulated the ATPase activity of a recombinant DnaK (BlDnaK) from the same bacterium by 3.1-14.7-fold, which are significantly lower than the synergistic stimulation (18.9-fold) of BlGrpE. Protein-protein interaction analysis revealed that Trp mutants relevant to amino acid positions 103 and 149 lost the ability to bind BlDnaK. Circular dichroism measurements indicate that F70W displayed a comparable level of secondary structure to that of BlGrpE, and the wild-type protein and the Trp mutants as well all experienced a reversible behavior of thermal denaturation. Guanidine hydrochloride (GdnHCl)-induced unfolding transition for BlGrpE was calculated to be 1.25 M corresponding to ΔG(N-U) of 4.29 kcal/mol, whereas the unfolding transitions of mutant proteins were in the range of 0.77-1.31 M equivalent to ΔG(N-U) of 2.41-4.14 kcal/mol. Taken together, the introduction of tryptophan residue, especially at positions 103 and 149, into the primary structure of BlGrpE has been proven to be detrimental to structural integrity and proper function of the protein. Copyright © 2014 Elsevier B.V. All rights reserved.

R and D on performance assessment of a potential LILW repository

Energy Technology Data Exchange (ETDEWEB)

Hwang, Yong Soo; Lee, Sung Hee; Han, Kyung Won; Lee, Y M

2001-01-01

In this technical report Important issues and assessment methods related to post-closure safety of a proposed repository has been discussed, regarding LILW disposal. At first, to summarize the new proposal on the amendment of the MOST Notice 96-16, KAERI set up the overall directions on future R and D over performance assessment. In addition relevant overseas project such as Finnish POSIVA's VLJ repository project was thoroughly reviewed along with the recent progress of the gas generation and migration R and D. In the post-closure safety analysis of the VLJ repository, in addition to the normal evolution scenario, several disturbed evolution and accident scenarios have been analysed. The groundwater flow analysis and the biosphere analysis have been evaluated. The result of the safety analysis show that radiation doses of any significance are caused only if a well is bored in the vicinity of the repository or if the groundwater discharge spot is inhabited and used for cultivation. in the reference scenario the maximum expectation value of the individual dose rate is 0.03 mSv/a. in the realistic scenario the maximum expectation value of the dose rate is 0.0002 mSv/a In general gas generation sources are represented by radioactive gases and non-radioactive gases. The amount of radioactive gases is little that it does not make a significant influence on the safety of LILW repository, however non-radioactive gases can cause safety problem. As mentioned above, gas of LILW generated by corrosion and microbiology and their production rate can be estimated by computer simulation and long-term experiment.

R and D on performance assessment of a potential LILW repository

Energy Technology Data Exchange (ETDEWEB)

Hwang, Yong Soo; Lee, Sung Hee; Han, Kyung Won; Lee, Y. M

2001-01-01

In this technical report Important issues and assessment methods related to post-closure safety of a proposed repository has been discussed, regarding LILW disposal. At first, to summarize the new proposal on the amendment of the MOST Notice 96-16, KAERI set up the overall directions on future R and D over performance assessment. In addition relevant overseas project such as Finnish POSIVA's VLJ repository project was thoroughly reviewed along with the recent progress of the gas generation and migration R and D. In the post-closure safety analysis of the VLJ repository, in addition to the normal evolution scenario, several disturbed evolution and accident scenarios have been analysed. The groundwater flow analysis and the biosphere analysis have been evaluated. The result of the safety analysis show that radiation doses of any significance are caused only if a well is bored in the vicinity of the repository or if the groundwater discharge spot is inhabited and used for cultivation. in the reference scenario the maximum expectation value of the individual dose rate is 0.03 mSv/a. in the realistic scenario the maximum expectation value of the dose rate is 0.0002 mSv/a In general gas generation sources are represented by radioactive gases and non-radioactive gases. The amount of radioactive gases is little that it does not make a significant influence on the safety of LILW repository, however non-radioactive gases can cause safety problem. As mentioned above, gas of LILW generated by corrosion and microbiology and their production rate can be estimated by computer simulation and long-term experiment.

International benchmark study of advanced thermal hydraulic safety analysis codes against measurements on IEA-R1 research reactor

Energy Technology Data Exchange (ETDEWEB)

Hainoun, A., E-mail: pscientific2@aec.org.sy [Atomic Energy Commission of Syria (AECS), Nuclear Engineering Department, P.O. Box 6091, Damascus (Syrian Arab Republic); Doval, A. [Nuclear Engineering Department, Av. Cmdt. Luis Piedrabuena 4950, C.P. 8400 S.C de Bariloche, Rio Negro (Argentina); Umbehaun, P. [Centro de Engenharia Nuclear – CEN, IPEN-CNEN/SP, Av. Lineu Prestes 2242-Cidade Universitaria, CEP-05508-000 São Paulo, SP (Brazil); Chatzidakis, S. [School of Nuclear Engineering, Purdue University, West Lafayette, IN 47907 (United States); Ghazi, N. [Atomic Energy Commission of Syria (AECS), Nuclear Engineering Department, P.O. Box 6091, Damascus (Syrian Arab Republic); Park, S. [Research Reactor Design and Engineering Division, Basic Science Project Operation Dept., Korea Atomic Energy Research Institute (Korea, Republic of); Mladin, M. [Institute for Nuclear Research, Campului Street No. 1, P.O. Box 78, 115400 Mioveni, Arges (Romania); Shokr, A. [Division of Nuclear Installation Safety, Research Reactor Safety Section, International Atomic Energy Agency, A-1400 Vienna (Austria)

2014-12-15

Highlights: • A set of advanced system thermal hydraulic codes are benchmarked against IFA of IEA-R1. • Comparative safety analysis of IEA-R1 reactor during LOFA by 7 working teams. • This work covers both experimental and calculation effort and presents new out findings on TH of RR that have not been reported before. • LOFA results discrepancies from 7% to 20% for coolant and peak clad temperatures are predicted conservatively. - Abstract: In the framework of the IAEA Coordination Research Project on “Innovative methods in research reactor analysis: Benchmark against experimental data on neutronics and thermal hydraulic computational methods and tools for operation and safety analysis of research reactors” the Brazilian research reactor IEA-R1 has been selected as reference facility to perform benchmark calculations for a set of thermal hydraulic codes being widely used by international teams in the field of research reactor (RR) deterministic safety analysis. The goal of the conducted benchmark is to demonstrate the application of innovative reactor analysis tools in the research reactor community, validation of the applied codes and application of the validated codes to perform comprehensive safety analysis of RR. The IEA-R1 is equipped with an Instrumented Fuel Assembly (IFA) which provided measurements for normal operation and loss of flow transient. The measurements comprised coolant and cladding temperatures, reactor power and flow rate. Temperatures are measured at three different radial and axial positions of IFA summing up to 12 measuring points in addition to the coolant inlet and outlet temperatures. The considered benchmark deals with the loss of reactor flow and the subsequent flow reversal from downward forced to upward natural circulation and presents therefore relevant phenomena for the RR safety analysis. The benchmark calculations were performed independently by the participating teams using different thermal hydraulic and safety

Can Patient Safety Incident Reports Be Used to Compare Hospital Safety? Results from a Quantitative Analysis of the English National Reporting and Learning System Data.

Science.gov (United States)

Howell, Ann-Marie; Burns, Elaine M; Bouras, George; Donaldson, Liam J; Athanasiou, Thanos; Darzi, Ara

2015-01-01

The National Reporting and Learning System (NRLS) collects reports about patient safety incidents in England. Government regulators use NRLS data to assess the safety of hospitals. This study aims to examine whether annual hospital incident reporting rates can be used as a surrogate indicator of individual hospital safety. Secondly assesses which hospital characteristics are correlated with high incident reporting rates and whether a high reporting hospital is safer than those lower reporting hospitals. Finally, it assesses which health-care professionals report more incidents of patient harm, which report more near miss incidents and what hospital factors encourage reporting. These findings may suggest methods for increasing the utility of reporting systems. This study used a mix methods approach for assessing NRLS data. The data were investigated using Pareto analysis and regression models to establish which patients are most vulnerable to reported harm. Hospital factors were correlated with institutional reporting rates over one year to examine what factors influenced reporting. Staff survey findings regarding hospital safety culture were correlated with reported rates of incidents causing harm; no harm and death to understand what barriers influence error disclosure. 5,879,954 incident reports were collected from acute hospitals over the decade. 70.3% of incidents produced no harm to the patient and 0.9% were judged by the reporter to have caused severe harm or death. Obstetrics and Gynaecology reported the most no harm events [OR 1.61(95%CI: 1.12 to 2.27), p<0.01] and pharmacy was the hospital location where most near-misses were captured [OR 3.03(95%CI: 2.04 to 4.55), p<0.01]. Clinicians were significantly more likely to report death than other staff [OR 3.04(95%CI: 2.43 to 3.80) p<0.01]. A higher ratio of clinicians to beds correlated with reduced rate of harm reported [RR = -1.78(95%Cl: -3.33 to -0.23), p = 0.03]. Litigation claims per bed were

77 FR 46764 - Clinical Studies of Safety and Effectiveness of Orphan Products Research Project Grant (R01)

Science.gov (United States)

2012-08-06

...] Clinical Studies of Safety and Effectiveness of Orphan Products Research Project Grant (R01) AGENCY: Food... per year. B. Research Objectives The goal of FDA's OPD grant program is to support the clinical... (OPD) grant program. The goal of FDA's OPD grant program is to support the clinical development of...

DECOLORIZATION OF AZO DYES AND MINERALIZATION OF PHENANTHRENE BY TRAMETES SP. AS03 ISOLATED FROM INDONESIAN MANGROVE FOREST

Directory of Open Access Journals (Sweden)

Asep Hidayat

2014-04-01

Full Text Available Textile industry contributes the most disposals of synthetic dyes, and about 40% of textile dyes has been generating high amount of colored wastewater. Polycyclic aromatic hydrocarbons (PAHs, such as phenanthrene, is a group of organic compounds, that structurally comprised of two or more benzene rings, which persist in air, water, and soil. The organic pollutants of dyes and PAHs have adversely effects the food chain and are potentially toxic, mutagenic, and carcinogenic to the environment. The objective of this research is to screen and investigate the potential fungus from mangrove forest to degrade azo dyes and phenanthrene.  In this study, fungi were collected from mangrove forest in Riau Province – Sumatra – Indonesia. Previously, Trametes sp. AS03 is one of the fungi isolated from mangrove forest in Riau Province, that was able to decolorize Remazol Brilliant Blue R (RBBR. The capability of Trametes sp. AS03 to decolorize four azo dyes, Remazol B. Violet (V5, Levafix Orange E3GA (Or64, Levafix B. Red E-6BA (R159, and Sumifix S. Scarlet 2GF (R222, were further evaluated. The result shows that Trametes sp. AS03 decolorized 91, 60, 48, and 31 of V5, R222, R159, and Or64, respectively. By showing its capability to decolorize some of the dyes, Trametes sp. AS03 was used to break down phenanthrene. AS03 degraded more than 70% of phenanthrene in 15 days.

Magnetic properties and magnetocaloric effect in the HoNi1−xCuxIn (x=0, 0.1, 0.3, 0.4) intermetallic compounds

International Nuclear Information System (INIS)

Mo, Zhao-Jun; Shen, Jun; Yan, Li-Qin; Tang, Cheng-Chun; He, Xiao-Nan; Zheng, Xinqi; Wu, Jian-Feng; Sun, Ji-Rong; Shen, Bao-Gen

2014-01-01

The magnetic properties and magnetocaloric effect (MCE) in HoNi 1−x Cu x In (x=0, 0.1, 0.3, 0.4) compounds have been investigated. With the substitution of Cu for Ni, the Ho magnetic moment will cant from the c-axis, and form a complicated magnetic structure. These compounds exhibit two successive magnetic transitions with the increase in temperature. The large reversible magnetocaloric effects have been observed in HoNi 1−x Cu x In compounds around T ord , with no thermal and magnetic hysteresis loss. The large reversible isothermal magnetic entropy change (−ΔS M ) is 20.2 J/kg K and the refrigeration capacity (RC) reaches 356.7 J/kg for field changes of 5 T for HoNi 0.7 Cu 0.3 In. Especially, the value of −ΔS M (12.5 J/kg K) and the large RC (132 J/kg) are observed for field changes of 2 T for HoNi 0.9 Cu 0.1 In. Additionally, the values of RC are improved to 149 J/K for the field changes of 2 T due to a wide temperature span for the mix of HoNi 0.9 Cu 0.1 In and HoNi 0.7 Cu 0.3 In compounds with the mass ratio of 1:1. These compounds with excellent MCE are expected to have effective applications in magnetic refrigeration around 20 K. - Highlights: • For magnetic-field changes of 2 T, the values of RC are improved to 149 J/K. • MCEs of these compounds show no thermal and magnetic hysteresis. • Compounds show two successive magnetic transitions with the increase in temperature. • With the substitution of Cu for Ni, compounds form a complicated magnetic structure

Pilot, randomized study assessing safety, tolerability and efficacy of simplified LPV/r maintenance therapy in HIV patients on the 1 PI-based regimen.

Science.gov (United States)

Cahn, Pedro; Montaner, Julio; Junod, Patrice; Patterson, Patricia; Krolewiecki, Alejandro; Andrade-Villanueva, Jaime; Cassetti, Isabel; Sierra-Madero, Juan; Casiró, Arnaldo David; Bortolozzi, Raul; Lupo, Sergio Horacio; Longo, Nadia; Rampakakis, Emmanouil; Ackad, Nabil; Sampalis, John S

2011-01-01

To compare the efficacy and safety of an individualized treatment-simplification strategy consisting of switching from a highly-active anti-retroviral treatment (HAART) with a ritonavir-boosted protease inhibitor (PI/r) and 2 nucleoside reverse-transcriptase inhibitors (NRTIs) to lopinavir/ritonavir (LPV/r) monotherapy, with intensification by 2 NRTIs if necessary, to that of continuing their HAART. This is a one-year, randomized, open-label, multi-center study in virologically-suppressed HIV-1-infected adults on their first PI/r-containing treatment, randomized to either LPV/r-monotherapy or continue their current treatment. Treatment efficacy was determined by plasma HIV-1 RNA viral load (VL), time-to-virologic rebound, patient-reported outcomes (PROs) and CD4+T-cell-count changes. Safety was assessed with the incidence of treatment-emergent adverse events (AE). Forty-one patients were randomized to LPV/r and 39 to continue their HAART. No statistically-significant differences between the two study groups in demographics and baseline characteristics were observed. At day-360, 71(39:LPV/r;32:HAART) patients completed treatment, while 9(2:LPV/r;7:HAART) discontinued. In a Last Observation Carried Forward Intent-to-Treat analysis, 40(98%) patients on LPV/r and 37(95%) on HAART had VL<200 copies/mL (P = 0.61). Time-to-virologic rebound, changes in PROs, CD4+ T-cell-count and VL from baseline, also exhibited no statistically-significant between-group differences. Most frequent AEs were diarrhea (19%), headache (18%) and influenza (16%). Four (10%) patients on LPV/r were intensified with 2 NRTIs, all regaining virologic control. Eight serious AEs were reported by 5(2:LPV/r;3:HAART) patients. At day-360, virologic efficacy and safety of LPV/r appears comparable to that of a PI+2NRTIs HAART. These results suggest that our individualized, simplified maintenance strategy with LPV/r-monotherapy and protocol-mandated NRTI re-introduction upon viral rebound, in

Pilot, randomized study assessing safety, tolerability and efficacy of simplified LPV/r maintenance therapy in HIV patients on the 1 PI-based regimen.

Directory of Open Access Journals (Sweden)

Pedro Cahn

Full Text Available To compare the efficacy and safety of an individualized treatment-simplification strategy consisting of switching from a highly-active anti-retroviral treatment (HAART with a ritonavir-boosted protease inhibitor (PI/r and 2 nucleoside reverse-transcriptase inhibitors (NRTIs to lopinavir/ritonavir (LPV/r monotherapy, with intensification by 2 NRTIs if necessary, to that of continuing their HAART.This is a one-year, randomized, open-label, multi-center study in virologically-suppressed HIV-1-infected adults on their first PI/r-containing treatment, randomized to either LPV/r-monotherapy or continue their current treatment. Treatment efficacy was determined by plasma HIV-1 RNA viral load (VL, time-to-virologic rebound, patient-reported outcomes (PROs and CD4+T-cell-count changes. Safety was assessed with the incidence of treatment-emergent adverse events (AE.Forty-one patients were randomized to LPV/r and 39 to continue their HAART. No statistically-significant differences between the two study groups in demographics and baseline characteristics were observed. At day-360, 71(39:LPV/r;32:HAART patients completed treatment, while 9(2:LPV/r;7:HAART discontinued. In a Last Observation Carried Forward Intent-to-Treat analysis, 40(98% patients on LPV/r and 37(95% on HAART had VL<200 copies/mL (P = 0.61. Time-to-virologic rebound, changes in PROs, CD4+ T-cell-count and VL from baseline, also exhibited no statistically-significant between-group differences. Most frequent AEs were diarrhea (19%, headache (18% and influenza (16%. Four (10% patients on LPV/r were intensified with 2 NRTIs, all regaining virologic control. Eight serious AEs were reported by 5(2:LPV/r;3:HAART patients.At day-360, virologic efficacy and safety of LPV/r appears comparable to that of a PI+2NRTIs HAART. These results suggest that our individualized, simplified maintenance strategy with LPV/r-monotherapy and protocol-mandated NRTI re-introduction upon viral rebound, in

Role of the central R&D laboratories of an international group in the field of Food-Feed Safety

Directory of Open Access Journals (Sweden)

Kovari Katalin

2000-09-01

Full Text Available With increased globalisation and more frequent crises within food/feed industry, public concern over food safety will remain at its present level and may even increase. The crushing/refining industry is likely to face further problems in the future. The recently established Food/Feed Safety Coordination Committee will be able to deal with any new crises at group level (communication, action organisation, in close cooperation with R&D, which in turn will provide the scientific background, analytical results, proposals for technical solutions and continuous monitoring, for any given situation.

Informal Progress Report Contract Number: DE-FG03-02NA00074/A000

International Nuclear Information System (INIS)

Brune, Carl R.; Grimes, Steven M.

2003-01-01

OAK B127 We report on work performed under contract DE-FG03-03NA00074 since January 1,2003. The research is in the area of low energy nuclear reactions and nuclear structure. The progress on research on level densities and improvement to R-Matrix calculations are presented. The preparations to begin high resolution experiments on p-shell nuclei are reviewed

Immunogenicity and Safety of a Trivalent Inactivated Influenza Vaccine in Children 6 Months to 17 Years of Age, Previously Vaccinated with an AS03-Adjuvanted A(H1N1)Pdm09 Vaccine: Two Open-label, Randomized Trials.

Science.gov (United States)

Vesikari, Timo; Richardus, Jan Hendrik; Berglund, Johan; Korhonen, Tiina; Flodmark, Carl-Erik; Lindstrand, Ann; Silfverdal, Sven Arne; Bambure, Vinod; Caplanusi, Adrian; Dieussaert, Ilse; Roy-Ghanta, Sumita; Vaughn, David W

2015-07-01

During the influenza pandemic 2009-2010, an AS03-adjuvanted A(H1N1)pdm09 vaccine was used extensively in children 6 months of age and older, and during the 2010-2011 influenza season, the A(H1N1)pdm09 strain was included in the seasonal trivalent inactivated influenza vaccine (TIV) without adjuvant. We evaluated the immunogenicity and safety of TIV in children previously vaccinated with the AS03-adjuvanted A(H1N1)pdm09 vaccine. Healthy children were randomized (1:1) to receive TIV or a control vaccine. Children were aged 6 months to 9 years (n = 154) and adolescents 10-17 years (n = 77) when they received AS03-adjuvanted A(H1N1)pdm09 vaccine at least 6 months before study enrolment. Hemagglutination inhibition (HI) and neutralizing antibody responses against the A(H1N1)pdm09 strain were evaluated before (day 0) and at day 28 and month 6 after study vaccination. Reactogenicity was assessed during the 7 day postvaccination period, and safety was assessed for 6 months. At day 0, >93.9% of all children had HI titers ≥1:40 for the A(H1N1)pdm09 strain, which increased to 100% at both day 28 and month 6 in the TIV group. Between days 0 and 28, HI antibody geometric mean titers against A(H1N1)pdm09 increased by 9-fold and 4-fold in children 6 months to 9 years of age and 10-17 years of age, respectively. AS03-adjuvanted A(H1N1)pdm09 vaccine-induced robust immune responses in children that persisted into the next season, yet were still boosted by TIV containing A(H1N1)pdm09. The reactogenicity and safety profile of TIV did not appear compromised by prior receipt of AS03-adjuvanted A(H1N1)pdm09 vaccine.

33 CFR 149.303 - What survival craft and rescue boats may be used on a manned deepwater port?

Science.gov (United States)

2010-07-01

... 33 Navigation and Navigable Waters 2 2010-07-01 2010-07-01 false What survival craft and rescue boats may be used on a manned deepwater port? 149.303 Section 149.303 Navigation and Navigable Waters... craft and rescue boats may be used on a manned deepwater port? (a) Each survival craft on a manned...

An overview of the safety pharmacology career of Dr. C.R. Hassler.

Science.gov (United States)

Hawk, M A; Pugsley, M K; Vinci, T; Wallery, J; Hassler, C R; Hamlin, R L

2017-09-01

Each year the Safety Pharmacology Society (SPS) recognizes an investigator who has had a marked impact upon the discipline. The 2016 recipient of the SPS Distinguished Service Award (DSA) was Dr. Craig R. Hassler. Dr. Hassler is one of the founding members of the SPS and has been actively engaged in physiological research for over 46years. Dr. Hassler delivered a talk entitled "My 43Years at Battelle Memorial Institute" to meeting attendees. In this article an overview is provided of the illustrious career of Dr. Hassler along with an account of the numerous animal models that were developed at Battelle under his guidance over the years. Copyright © 2017 Elsevier Inc. All rights reserved.

26 CFR 1.149(d)-1A - Limitations on advance refundings.

Science.gov (United States)

2010-04-01

... savings test. If any separate issue in a multipurpose issue increases the aggregate present value debt service savings on the entire multipurpose issue or reduces the present value debt service losses on that... 26 Internal Revenue 2 2010-04-01 2010-04-01 false Limitations on advance refundings. 1.149(d)-1A...

Synthesis and Preliminary Biological Evaluations of Fluorescent or 149Promethium Labeled Trastuzumab-Polyethylenimine

Directory of Open Access Journals (Sweden)

Jonathan Fitzsimmons

2015-12-01

Full Text Available Background: Radioimmunotherapy utilize a targeting antibody coupled to a therapeutic isotope to target and treat a tumor or disease. In this study we examine the synthesis and cell binding of a polymer scaffold containing a radiotherapeutic isotope and a targeting antibody. Methods: The multistep synthesis of a fluorescent or 149Promethium-labeled Trastuzumab-polyethyleneimine (PEI, Trastuzumab, or PEI is described. In vitro uptake, internalization and/or the binding affinity to the Her2/neu expressing human breast adenocarcinoma SKBr3 cells was investigated with the labeled compounds. Results: Fluorescent-labeled Trastuzumab-PEI was internalized more into cells at 2 and 18 h than fluorescent-labeled Trastuzumab or PEI. The fluorescent-labeled Trastuzumab was concentrated on the cell surface at 2 and 18 h and the labeled PEI had minimal uptake. DOTA-PEI was prepared and contained an average of 16 chelates per PEI; the compound was radio-labeled with 149Promethium and conjugated to Trastuzumab. The purified 149Pm-DOTA-PEI-Trastuzumab had a radiochemical purity of 96.7% and a specific activity of 0.118 TBq/g. The compound demonstrated a dissociation constant for the Her2/neu receptor of 20.30 ± 6.91 nM. Conclusion: The results indicate the DOTA-PEI-Trastuzumab compound has potential as a targeted therapeutic carrier, and future in vivo studies should be performed.

The development of technologies of safety analysis for LMR ('03)

Energy Technology Data Exchange (ETDEWEB)

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

2004-03-01

The developmental objectives of the project, 'The development of safety analysis techniques in LMR', are the code development for the subchannel blockage analysis, the code development for the system transient analysis, the code development for the HCDA(Hypothetical Core Disruptive Accident) analysis, the preliminary safety analysis for KALIMER-600 equipped with the components of new concepts, and the establishment of data base. The purpose of the analysis for subchannel blockage in the subassembly of LMR is to represent quantitatively that the maximum damage due to the accident is within the safety criteria. The computational program should be developed to simulate the thermal hydraulic phenomena and to verify the safety of LMR for the accident. For the purpose, the hybrid scheme has been implemented into the MATRA-LMR code based on the upwind scheme to analyze the various flow fields occurred in the subchannel blockage accident. The turbulent mixing models using the CFX code were assessed to compute more precisely the heat transfer between subchannels. Through this assessment, empirical correction factors of 1.7 for the heat conduction, 0.006 for the turbulent mixing coefficient were obtained. The distributed resistance model instead of wire forcing function has been developed to represent the more exact flow field due to wire-wrap. Other models, such as heat conductor model and various turbulent mixing model, have been implemented into the MATRA-LMR. The ORNL THORS 19-Pin FFM-5B tests have been assessed to validate above new models using the improved MATRA-LMR. The results using MATRA-LMR were well agreed with the experimental data. The subchannel blockage accidents which assumed to be occurred at the three locations for the conceptual plant of KALIMER-600 have been analysed according to blockage size using the MATRA-LMR code. The results of calculations for the design basis events which 6 subchannels were blocked showed the margins of the 290 7.dog. C

O původu a hybridizaci polyploidních pýrů - na stopě netušených předků

Czech Academy of Sciences Publication Activity Database

Mahelka, Václav

2013-01-01

Roč. 61, č. 4 (2013), s. 149-153 ISSN 0044-4812 R&D Projects: GA ČR GA13-04454S Institutional support: RVO:67985939 Keywords : hybridization * polyploidization * Triticeae Subject RIV: EF - Botanics

AP1000{sup R} nuclear power plant safety overview for spent fuel cooling

Energy Technology Data Exchange (ETDEWEB)

Gorgemans, J.; Mulhollem, L.; Glavin, J.; Pfister, A.; Conway, L.; Schulz, T.; Oriani, L.; Cummins, E.; Winters, J. [Westinghouse Electric Company LLC, 1000 Westinghouse Drive, Cranberry Township, PA 16066 (United States)

2012-07-01

The AP1000{sup R} plant is an 1100-MWe class pressurized water reactor with passive safety features and extensive plant simplifications that enhance construction, operation, maintenance, safety and costs. The AP1000 design uses passive features to mitigate design basis accidents. The passive safety systems are designed to function without safety-grade support systems such as AC power, component cooling water, service water or HVAC. Furthermore, these passive features 'fail safe' during a non-LOCA event such that DC power and instrumentation are not required. The AP1000 also has simple, active, defense-in-depth systems to support normal plant operations. These active systems provide the first level of defense against more probable events and they provide investment protection, reduce the demands on the passive features and support the probabilistic risk assessment. The AP1000 passive safety approach allows the plant to achieve and maintain safe shutdown in case of an accident for 72 hours without operator action, meeting the expectations provided in the U.S. Utility Requirement Document and the European Utility Requirements for passive plants. Limited operator actions are required to maintain safe conditions in the spent fuel pool via passive means. In line with the AP1000 approach to safety described above, the AP1000 plant design features multiple, diverse lines of defense to ensure spent fuel cooling can be maintained for design-basis events and beyond design-basis accidents. During normal and abnormal conditions, defense-in-depth and other systems provide highly reliable spent fuel pool cooling. They rely on off-site AC power or the on-site standby diesel generators. For unlikely design basis events with an extended loss of AC power (i.e., station blackout) or loss of heat sink or both, spent fuel cooling can still be provided indefinitely: - Passive systems, requiring minimal or no operator actions, are sufficient for at least 72 hours under all

275 Candidates and 149 Validated Planets Orbiting Bright Stars in K2 Campaigns 0–10

DEFF Research Database (Denmark)

Mayo, Andrew W.; Vanderburg, Andrew; Latham, David W.

2018-01-01

Since 2014, NASA’s K2 mission has observed large portions of the ecliptic plane in search of transiting planets and has detected hundreds of planet candidates. With observations planned until at least early 2018, K2 will continue to identify more planet candidates. We present here 275 planet...... candidates observed during Campaigns 0–10 of the K2 mission that are orbiting stars brighter than 13 mag (in Kepler band) and for which we have obtained high-resolution spectra ( R = 44,000). These candidates are analyzed using the vespa package in order to calculate their false-positive probabilities (FPP......). We find that 149 candidates are validated with an FPP lower than 0.1%, 39 of which were previously only candidates and 56 of which were previously undetected. The processes of data reduction, candidate identification, and statistical validation are described, and the demographics of the candidates...

In vivo radiochemical properties of Tb-149: A new radiolanthanide for targeted cancer therapy

International Nuclear Information System (INIS)

Allen, B.J.; Beyer, G.J.; Morel, C.H.; Aleksandrova, Y.; Jahn, S.

1996-01-01

Full text: 149 Tb (4.15 h) decays by the emission of both 3.9 MeV alpha particles (17% branching) and positrons (4% branch), and uniquely combines both therapeutic and PET diagnostic properties. In this paper we report the production route, systemic studies of radio-lanthanides with ethylenediaminetetra methylene phosphonate (EDTMP) ligand, and the first 149 Tb phantom studies using PET. The radio-lanthanides used in this study were produced at the ISOLDE (isotope separator on-line) facility at CERN. They are produced carrier free, isotopically and chemically separated (isobaric separation using cation exchange chromatography) in a form suitable for protein labelling. Batches up to 20 mCi of 1 4 9T b are available. We have established relationships between biokinetics, EDTMP concentration, and the ionic radius of the radiolanthanide used. The tumour to liver ratio in mice reaches a maximum value at 1 mM 10 mM and decreases from 10 by almost two decades according to the ionic radius of the lanthanide. For Tb, a tumour to liver ratio of 5 can be obtained, similar to Gd. No significant differences in the uptake in bone for all lanthanides in the EDTMP system were observed. A fast blood clearance allows clear bone images to be obtained via PET at 60-90 min post-injection, as shown with rabbits using 142 Sm-EDTMP. The first phantom PET studies with 149 Tb are also reported. We conclude that the fast biokinetics and the alpha decay mode open up new possibilities for a more efficient endo-radionuclide therapy using EDTMP. The high purity of the 149T b (isotopically separated and carrier free) produced in this way makes it very suitable for the labelling of octretides

SU-E-T-599: Patient Safety Enhancements Through a Study of R&V System Override Data

Energy Technology Data Exchange (ETDEWEB)

Hendrickson, K; Vimolchalao, S [University of Washington, Seattle, WA (United States)

2015-06-15

Purpose: Record and verify (R&V) software systems include safety checks that compare actual machine parameters with prescribed values for a patient’s treatment, such as treatment couch position, linac, energy, and MUs. The therapist is warned of a mismatch with a pop-up and prompted to approve an override in order to continue without changes. Override approval is often legitimate, but the pop-up can also genuinely indicate a problem that would Result in the wrong treatment. When there are numerous pop-up warnings, human nature leads us to approve any override without careful reading, undermining the effectiveness of the safety mechanism. Methods: Override data was collected from our R&V system for all patients treated between October 8 and 29, 2012, on four linacs and entered into a spreadsheet. Additional data collected included treatment technique, disease site, immobilization, time, linac, and whether localization images were obtained. Data were analyzed using spreadsheet tools to reveal trends, patterns and associations that might suggest appropriate process changes that could decrease the total number of overrides. Results: 76 out of 113 patients had overrides. Out of the 944 treatments, 599 override items were generated. The majority were due to couch positions. 74 of the 84 overrides on a linac equipped with a 6D couch were due to the use of the rotational corrections and the fact that the 6D couch control does not communicate with the R&V system; translations required to rotate the couch appear to the R&V system as translations outside the tolerance range. Conclusion: Many findings were interesting but did not suggest a process change. Proposed process changes include creating site-specific instead of just technique-specific tolerance tables for couch shifts. Proposed improvements to the vendor are to facilitate direct communication between the 6D couch and the R&V system to eliminate those override warnings related to lack of communication.

78 FR 16045 - Safety Advisory: Unauthorized Marking of Compressed Gas Cylinders

Science.gov (United States)

2013-03-13

... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration [Docket No. PHMSA-2013-0019; Notice No. 13-03] Safety Advisory: Unauthorized Marking of Compressed Gas Cylinders AGENCY: Pipeline and Hazardous Materials Safety Administration (PHMSA), DOT. ACTION: Safety Advisory...

PHISICS/RELAP5-3D RESULTS FOR EXERCISES II-1 AND II-2 OF THE OECD/NEA MHTGR-350 BENCHMARK

Energy Technology Data Exchange (ETDEWEB)

Strydom, Gerhard [Idaho National Laboratory

2016-03-01

The Idaho National Laboratory (INL) Advanced Reactor Technologies (ART) High-Temperature Gas-Cooled Reactor (HTGR) Methods group currently leads the Modular High-Temperature Gas-Cooled Reactor (MHTGR) 350 benchmark. The benchmark consists of a set of lattice-depletion, steady-state, and transient problems that can be used by HTGR simulation groups to assess the performance of their code suites. The paper summarizes the results obtained for the first two transient exercises defined for Phase II of the benchmark. The Parallel and Highly Innovative Simulation for INL Code System (PHISICS), coupled with the INL system code RELAP5-3D, was used to generate the results for the Depressurized Conduction Cooldown (DCC) (exercise II-1a) and Pressurized Conduction Cooldown (PCC) (exercise II-2) transients. These exercises require the time-dependent simulation of coupled neutronics and thermal-hydraulics phenomena, and utilize the steady-state solution previously obtained for exercise I-3 of Phase I. This paper also includes a comparison of the benchmark results obtained with a traditional system code “ring” model against a more detailed “block” model that include kinetics feedback on an individual block level and thermal feedbacks on a triangular sub-mesh. The higher spatial fidelity that can be obtained by the block model is illustrated with comparisons of the maximum fuel temperatures, especially in the case of natural convection conditions that dominate the DCC and PCC events. Differences up to 125 K (or 10%) were observed between the ring and block model predictions of the DCC transient, mostly due to the block model’s capability of tracking individual block decay powers and more detailed helium flow distributions. In general, the block model only required DCC and PCC calculation times twice as long as the ring models, and it therefore seems that the additional development and calculation time required for the block model could be worth the gain that can be

Status of nuclear safety R ampersand D in the US

International Nuclear Information System (INIS)

Bari, R.A.

1993-01-01

The status of nuclear safety research and development in the US is presented with particular emphasis on work performed by Brookhaven National Laboratory. The nuclear safety program in the US encompasses safety of the current generation of operating commercial reactors, safety-related design of the next generation of advanced reactors, and safety activities for the reactors owned by the US Department of Energy. The broad topical areas of safety research include (but are not limited to) severe accidents, reliability/risk assessment, human performance, thermal-hydraulics, plant aging, seismic, and structural studies

Pilot, Randomized Study Assessing Safety, Tolerability and Efficacy of Simplified LPV/r Maintenance Therapy in HIV Patients on the 1st PI-Based Regimen

Science.gov (United States)

Cahn, Pedro; Montaner, Julio; Junod, Patrice; Patterson, Patricia; Krolewiecki, Alejandro; Andrade-Villanueva, Jaime; Cassetti, Isabel; Sierra-Madero, Juan; Casiró, Arnaldo David; Bortolozzi, Raul; Lupo, Sergio Horacio; Longo, Nadia; Rampakakis, Emmanouil; Ackad, Nabil; Sampalis, John S.

2011-01-01

Objectives To compare the efficacy and safety of an individualized treatment-simplification strategy consisting of switching from a highly-active anti-retroviral treatment (HAART) with a ritonavir-boosted protease inhibitor (PI/r) and 2 nucleoside reverse-transcriptase inhibitors (NRTIs) to lopinavir/ritonavir (LPV/r) monotherapy, with intensification by 2 NRTIs if necessary, to that of continuing their HAART. Methods This is a one-year, randomized, open-label, multi-center study in virologically-suppressed HIV-1-infected adults on their first PI/r-containing treatment, randomized to either LPV/r-monotherapy or continue their current treatment. Treatment efficacy was determined by plasma HIV-1 RNA viral load (VL), time-to-virologic rebound, patient-reported outcomes (PROs) and CD4+T-cell-count changes. Safety was assessed with the incidence of treatment-emergent adverse events (AE). Results Forty-one patients were randomized to LPV/r and 39 to continue their HAART. No statistically-significant differences between the two study groups in demographics and baseline characteristics were observed. At day-360, 71(39:LPV/r;32:HAART) patients completed treatment, while 9(2:LPV/r;7:HAART) discontinued. In a Last Observation Carried Forward Intent-to-Treat analysis, 40(98%) patients on LPV/r and 37(95%) on HAART had VL<200copies/mL (P = 0.61). Time-to-virologic rebound, changes in PROs, CD4+ T-cell-count and VL from baseline, also exhibited no statistically-significant between-group differences. Most frequent AEs were diarrhea (19%), headache (18%) and influenza (16%). Four (10%) patients on LPV/r were intensified with 2 NRTIs, all regaining virologic control. Eight serious AEs were reported by 5(2:LPV/r;3:HAART) patients. Conclusion At day-360, virologic efficacy and safety of LPV/r appears comparable to that of a PI+2NRTIs HAART. These results suggest that our individualized, simplified maintenance strategy with LPV/r-monotherapy and protocol-mandated NRTI re

Pharmacokinetic/Toxicity Properties of the New Anti-Staphylococcal Lead Compound SK-03-92

Directory of Open Access Journals (Sweden)

William R. Schwan

2015-11-01

Full Text Available Because of the potential of a new anti-staphylococcal lead compound SK-03-92 as a topical antibiotic, a patch, or an orally active drug, we sought to determine its safety profile and oral bioavailability. SK-03-92 had a high IC50 (125 μg/mL in vitro against several mammalian cell lines, and mice injected intraperiteonally at the highest dose did not exhibit gross toxicity (e.g., altered gait, ungroomed, significant weight loss. Single dose (100 μg/g pharmacokinetic (PK analysis with formulated SK-03-92 showed that peak plasma concentration (1.64 μg/mL was achieved at 20–30 min. Oral relative bioavailability was 8%, and the drug half-life was 20–30 min, demonstrating that SK-03-92 is likely not a candidate for oral delivery. Five-day and two-week PK analyses demonstrated that SK-03-92 plasma levels were low. Multi-dose analysis showed no gross adverse effects to the mice and a SK-03-92 peak plasma concentration of 2.12 μg/mL with the presence of significant concentrations of breakdown products 15 min after dosing. SK-03-92 appeared to be very safe based on tissue culture and mouse gross toxicity determinations, but the peak plasma concentration suggests that a pro-drug of SK-03-92 or preparation of analogs of SK-03-92 with greater bioavailability and longer half-lives are warranted.

The structure at 2.5 Å resolution of human basophilic leukemia-expressed protein BLES03

International Nuclear Information System (INIS)

Bitto, Eduard; Bingman, Craig A.; Robinson, Howard; Allard, Simon T. M.; Wesenberg, Gary E.; Phillips, George N. Jr

2005-01-01

The crystal structure of the 27.5 kDa BLES03 protein was determined at 2.5 Å resolution. Despite having an undetectable sequence relationship, the structure adopts a fold similar to that of eukaryotic initiation factor 4E with minor variations. The crystal structure of the human basophilic leukemia-expressed protein (BLES03, p5326, Hs.433573) was determined by single-wavelength anomalous diffraction and refined to an R factor of 18.8% (R free = 24.5%) at 2.5 Å resolution. BLES03 shows no detectable sequence similarity to any functionally characterized proteins using state-of-the-art sequence-comparison tools. The structure of BLES03 adopts a fold similar to that of eukaryotic transcription initiation factor 4E (eIF4E), a protein involved in the recognition of the cap structure of eukaryotic mRNA. In addition to fold similarity, the electrostatic surface potentials of BLES03 and eIF4E show a clear conservation of basic and acidic patches. In the crystal lattice, the acidic amino-terminal helices of BLES03 monomers are bound within the basic cavity of symmetry-related monomers in a manner analogous to the binding of mRNA by eIF4E. Interestingly, the gene locus encoding BLES03 is located between genes encoding the proteins DRAP1 and FOSL1, both of which are involved in transcription initiation. It is hypothesized that BLES03 itself may be involved in a biochemical process that requires recognition of nucleic acids

Experiment data report for semiscale MOD-1 tests S-03-A, S-03-B, S-03-C, and S-03-D (reflood heat transfer tests)

International Nuclear Information System (INIS)

1976-05-01

Recorded test data are presented for Tests S-03-A, S-03-B, S-03-C, and S-03-D of the Semiscale Mod-1 reflood heat transfer series (Test Series 3). The tests conducted in this series are separate effects core reflood tests performed to determine the reflood heat transfer characteristics of the 5.5 foot Mod-1 rod bundle. Tests S-03-A through S-03-D were forced-feed reflood tests in which the reflood rate was held constant during each test. The tests were conducted to investigate the effects on system response resulting from variations in operating conditions of pressure, temperature, core power, reflood coolant, subcooling, and peak heater rod thermocouple temperature at reflood initiation. Test S-03-A was conducted from an initial system temperature of about 230 0 F at a pressure of 20 psia. Tests S-03-B through S-03-D were conducted from an initial system temperature of about 290 0 F at a pressure of 60 psia. In all four tests, reflood coolant was injected directly into the core barrel by means of a specially designed core inlet manifold. The electrically heated core was used in the pressure vessel to simulate the effects of a nuclear core during reflood. All four tests were conducted with a flat radial power profile. During reflood, core power was reduced from the initial level according to the American Nuclear Society (ANS) decay heat curve plus 20 percent for pressurized water reactor (PWR) core decay heat. The cold leg broken loop piping was open to the pressure suppression system (PSS). A separate steam supply system connected to the PSS was controlled to maintain constant pressure during the tests

Situation analysis of physical independence of the equipment and safety circuits of Almaraz NPP regarding R.G. 1.75 rev.3 (2005)

International Nuclear Information System (INIS)

Seijas Portela, S.

2010-01-01

Situation analysis of physical independence of the electrical equipment and circuits CN safety Almaraz about R.G. 1.75 rev. 3. (2005) The aim of this paper is to present the work done in the analysis of the physical separation of redundant safety electrical equipment (emergency diesel generators, medium voltage, electrical cabinets, etc.) and physical separation of circuits and electrical conduits.

Atrial fibrillation detection and R-wave synchronization by Metrix implantable atrial defibrillator - Implications for long-term efficacy and safety

NARCIS (Netherlands)

Tse, HF; Lau, CP; Sra, JS; Crijns, HJGM; Edvardsson, N; Kacet, S; Wyse, DG

1999-01-01

Background-The long-term efficacy of atrial fibrillation (AF) detection and R-wave synchronization are critical safety requirements for the development of an implantable atrial defibrillator (LAD) for treatment of AF. Methods and Results The long-term efficacy of the Metrix IAD for AF detection and

Reliability database of IEA-R1 Brazilian research reactor: Applications to the improvement of installation safety

International Nuclear Information System (INIS)

Oliveira, P.S.P.; Tondin, J.B.M.; Martins, M.O.; Yovanovich, M.; Ricci Filho, W.

2010-01-01

In this paper the main features of the reliability database being developed at Ipen-Cnen/SP for IEA-R1 reactor are briefly described. Besides that, the process for collection and updating of data regarding operation, failure and maintenance of IEA-R1 reactor components is presented. These activities have been conducted by the reactor personnel under the supervision of specialists in Probabilistic Safety Analysis (PSA). The compilation of data and subsequent calculation are based on the procedures defined during an IAEA Coordinated Research Project which Brazil took part in the period from 2001 to 2004. In addition to component reliability data, the database stores data on accident initiating events and human errors. Furthermore, this work discusses the experience acquired through the development of the reliability database covering aspects like improvements in the reactor records as well as the application of the results to the optimization of operation and maintenance procedures and to the PSA carried out for IEA-R1 reactor. (author)

Herança da resistência do Híbrido de Timor UFV 443-03 à ferrugem-do-cafeeiro Inheritance of coffee leaf rust resistance in Timor Hybrid UFV 443-03

Directory of Open Access Journals (Sweden)

Alexandre Sandri Capucho

2009-03-01

Full Text Available O objetivo deste trabalho foi caracterizar a herança da resistência do Híbrido de Timor UFV 443-03 à ferrugem-do-cafeeiro (Hemileia vastatrix. Para isso, a raça II e o patótipo 001 de ferrugem foram inoculados em 246 plantas da população F2, 115 plantas do retrocruzamento suscetível (RC S e 87 plantas do retrocruzamento resistente (RC R, originadas do cruzamento entre o genótipo suscetível cv. Catuaí Amarelo IAC 64 e a fonte de resistência Híbrido de Timor UFV 443-03. Para ambos os inóculos, a cv. Catuaí Amarelo IAC 64 foi suscetível, enquanto o Híbrido de Timor UFV 443-03, a planta representante da geração F1 e as plantas do RC R foram resistentes. As plantas F2, quando inoculadas com a raça II, apresentaram dois padrões de segregação significativos: 15:1 e 61:3. A herança da resistência foi confirmada pela inoculação das plantas do RC S, que segregaram na proporção de 3:1, padrão esperado para herança condicionada por dois genes. A hipótese de segregação 7:1 para três genes foi rejeitada. Resultados semelhantes foram obtidos para o patótipo 001. Dois genes dominantes e independentes conferem a resistência genética do Híbrido de Timor UFV 443-03 à raça II e ao patótipo 001 de H. vastatrix.The aim of this work was to characterize the resistance inheritance of the Timor Hybrid UFV 443-03 to coffee leaf rust (Hemileia vastatrix. For this, the race II and pathotype 001 of coffee leaf rust were inoculated in 246 F2 plants, 115 susceptible backcrossing (BCS plants, and 87 resistant backcrossing (BC R plants, derived from the crossing between the susceptible genotype 'Catuaí Amarelo' IAC 64 and the resistance source Timor Hybrid UFV 443-03. For both inoculums, the 'Catuaí Amarelo' IAC 64 was susceptible, while the Timor Hybrid, the plant representing F1 generation, and the BC R plants were resistant. The F2 plants inoculated with race II presented two significant segregation ratios: 15:1 and 61:3. The

Tank safety screening data quality objective. Revision 1

Energy Technology Data Exchange (ETDEWEB)

Hunt, J.W.

1995-04-27

The Tank Safety Screening Data Quality Objective (DQO) will be used to classify 149 single shell tanks and 28 double shell tanks containing high-level radioactive waste into safety categories for safety issues dealing with the presence of ferrocyanide, organics, flammable gases, and criticality. Decision rules used to classify a tank as ``safe`` or ``not safe`` are presented. Primary and secondary decision variables used for safety status classification are discussed. The number and type of samples required are presented. A tabular identification of each analyte to be measured to support the safety classification, the analytical method to be used, the type of sample, the decision threshold for each analyte that would, if violated, place the tank on the safety issue watch list, and the assumed (desired) analytical uncertainty are provided. This is a living document that should be evaluated for updates on a semiannual basis. Evaluation areas consist of: identification of tanks that have been added or deleted from the specific safety issue watch lists, changes in primary and secondary decision variables, changes in decision rules used for the safety status classification, and changes in analytical requirements. This document directly supports all safety issue specific DQOs and additional characterization DQO efforts associated with pretreatment and retrieval. Additionally, information obtained during implementation can assist in resolving assumptions for revised safety strategies, and in addition, obtaining information which will support the determination of error tolerances, confidence levels, and optimization schemes for later revised safety strategy documentation.

Output feedback dissipation control for the power-level of modular high-temperature gas-cooled reactors

International Nuclear Information System (INIS)

Dong, Z.

2011-01-01

Because of its strong inherent safety features and the high outlet temperature, the modular high temperature gas-cooled nuclear reactor (MHTGR) is the chosen technology for a new generation of nuclear power plants. Such power plants are being considered for industrial applications with a wide range of power levels, thus power-level regulation is very important for their efficient and stable operation. Exploiting the large scale asymptotic closed-loop stability provided by nonlinear controllers, a nonlinear power-level regulator is presented in this paper that is based upon both the techniques of feedback dissipation and well-established backstepping. The virtue of this control strategy, i.e., the ability of globally asymptotic stabilization, is that it takes advantage of the inherent zero-state detectability property of the MHTGR dynamics. Moreover, this newly built power-level regulator is also robust towards modeling uncertainty in the control rod dynamics. If modeling uncertainty of the control rod dynamics is small enough to be omitted, then this control law can be simplified to a classical proportional feedback controller. The comparison of the control performance between the newly-built power controller and the simplified controller is also given through numerical study and theoretical analysis. (author)

The design status of the United States Department of Energy modular high temperature gas cooled reactor

International Nuclear Information System (INIS)

Mills, Raymond R. Jr.

1990-01-01

The U.S. Department of Energy's Modular High Temperature Gas Cooled Reactor (MHTGR) is being designed using a systems engineering approach referred to as the integrated approach. The top level requirement for the plant is that it provides safe, reliable, economical energy. The safety requirements are established by the U.S. Licensing Authorities, principally the Nuclear Regulatory Commission. The reliability and economic requirements associated with the top level functions have been established in close coordination and cooperation with the electrical utilities and other potential users, and the nuclear supply industry. The integrated approach uses functional analysis to define the functions and sub-functions for the plant and to identify quantitatively how the various functions must be fulfilled. The top four functions associated with the MHTGR are: maintain safe plant operation; maintain plant protection; maintain control of radionuclide release; maintain emergency preparedness. In addition to meeting all U.S. Regulatory Requirements this advanced reactor concept is being designed to meet the following requirements: do not require sheltering or evacuating of anyone outside the plant boundary of 425 meters as a result of normal or abnormal plant operation; do not require operator action in order to accomplish the above sheltering and evacuation objectives and the design must be insensitive to operator errors; utilize inherent characteristics of materials to develop passive safety features; provide very long times for corrective actions following the initiation of an abnormal event before plant damage would be incurred

33 CFR 149.304 - What type and how many survival craft and rescue boats must a manned deepwater port have?

Science.gov (United States)

2010-07-01

... 33 Navigation and Navigable Waters 2 2010-07-01 2010-07-01 false What type and how many survival craft and rescue boats must a manned deepwater port have? 149.304 Section 149.304 Navigation and... What type and how many survival craft and rescue boats must a manned deepwater port have? (a) Except as...

Pairing phase transition and thermodynamical quantities in 148,149Sm

International Nuclear Information System (INIS)

Razavi, R.; Behkami, A.N.; Dehghani, V.

2014-01-01

The nuclear level densities and entropies in 148,149 Sm have been calculated in the framework of the superconducting theory that includes modified nuclear pairing gap. For modified pairing gap parameter the smooth transition from the BCS to the Fermi type distributions is used. By applying modified pairing gap, the extracted S-shaped heat capacity as a function of nuclear temperature exhibits a physical and smoother behavior instead of the singular behavior predicted by the BCS equations at critical temperature

New Production Reactors Program: Report to the Congress by the Secretary of Energy

International Nuclear Information System (INIS)

1990-01-01

In August 1988, DOE issued a report to Congress announcing the Department's proposal for assuring future tritium production capacity through the building of new facilities, specifically, a preferred duality strategy that calls for the design and construction of a new, up-to-date heavy water reactor (HWR) at the Savannah River Site in South Carolina; and, at the same time, to proceed with the design and construction of a modular high-temperature gas-cooled reactor (MHTGR) plant to be located at the Idaho National Engineering Laboratory in Idaho. As a contingency, the Department is developing a light water reactor (LWR) tritium target for possible use in the partially completed WNP-1 reactor located on the Hanford Site, near Richland, Washington. The Secretary created the Office of New Production Reactors (NP) to accomplish the following mission: To provide new production reactor capacity on an urgent schedule for an assured supply of nuclear materials, primarily tritium, to maintain the Nation's nuclear deterrent capability. The organizational philosophy of the Program calls for strong central control with increased safety, environmental, and quality assurance oversight. In addition to separate Engineering Technology Offices for HWR, MHTGR, and LWR that will maintain technical control throughout the life of the Program, the NP Director has created oversight Offices for Safety and Quality and for Environment. An NP Project Management Office will be established at each of the three project sites with the Project Officer reporting directly to the Director of NP. Safety, Quality, and Environmental Field Representatives will be located on-site at the Project Management Offices to serve as a ''resident'' for the Headquarters' Office to whom they will report

Evaluation of national and foreign design and application concepts for small-sized high-temperature reactors

International Nuclear Information System (INIS)

Hahn, L.; Nockenberg, B.

1990-03-01

There are currently the design types Modular HTR, MHTGR, HTTR, HTR-500, and GHR. The different design concepts are explained and are analysed with regard to their application potentials in Germany and abroad, their export into developing countries, their general and specific safety aspects, the relevant fuel cycle aspects (fuel supply and spent fuel management), and the resulting problems arising in connection with the principle of non-proliferation. In the concluding section of the report, misgivings are stated as to possible military applications of this reactor type. (DG) [de

cis-chlorobenzene dihydrodiol dehydrogenase (TcbB) from Pseudomonas sp. strain P51, expressed in Escherichia coli DH5alpha(pTCB149), catalyzes enantioselective dehydrogenase reactions.

Science.gov (United States)

Raschke, H; Fleischmann, T; Van Der Meer, J R; Kohler, H P

1999-12-01

cis-Chlorobenzene dihydrodiol dehydrogenase (CDD) from Pseudomonas sp. strain P51, cloned into Escherichia coli DH5alpha(pTCB149) was able to oxidize cis-dihydrodihydroxy derivatives (cis-dihydrodiols) of dihydronaphthalene, indene, and four para-substituted toluenes to the corresponding catechols. During the incubation of a nonracemic mixture of cis-1,2-indandiol, only the (+)-cis-(1R,2S) enantiomer was oxidized; the (-)-cis-(S,2R) enantiomer remained unchanged. CDD oxidized both enantiomers of cis-1,2-dihydroxy-1,2,3, 4-tetrahydronaphthalene, but oxidation of the (+)-cis-(1S,2R) enantiomer was delayed until the (-)-cis-(1R,2S) enantiomer was completely depleted. When incubated with nonracemic mixtures of para-substituted cis-toluene dihydrodiols, CDD always oxidized the major enantiomer at a higher rate than the minor enantiomer. When incubated with racemic 1-indanol, CDD enantioselectively transformed the (+)-(1S) enantiomer to 1-indanone. This stereoselective transformation shows that CDD also acted as an alcohol dehydrogenase. Additionally, CDD was able to oxidize (+)-cis-(1R,2S)-dihydroxy-1, 2-dihydronaphthalene, (+)-cis-monochlorobiphenyl dihydrodiols, and (+)-cis-toluene dihydrodiol to the corresponding catechols.

cis-Chlorobenzene Dihydrodiol Dehydrogenase (TcbB) from Pseudomonas sp. Strain P51, Expressed in Escherichia coli DH5α(pTCB149), Catalyzes Enantioselective Dehydrogenase Reactions

Science.gov (United States)

Raschke, Henning; Fleischmann, Thomas; Van Der Meer, Jan Roelof; Kohler, Hans-Peter E.

1999-01-01

cis-Chlorobenzene dihydrodiol dehydrogenase (CDD) from Pseudomonas sp. strain P51, cloned into Escherichia coli DH5α(pTCB149) was able to oxidize cis-dihydrodihydroxy derivatives (cis-dihydrodiols) of dihydronaphthalene, indene, and four para-substituted toluenes to the corresponding catechols. During the incubation of a nonracemic mixture of cis-1,2-indandiol, only the (+)-cis-(1R,2S) enantiomer was oxidized; the (−)-cis-(S,2R) enantiomer remained unchanged. CDD oxidized both enantiomers of cis-1,2-dihydroxy-1,2,3,4-tetrahydronaphthalene, but oxidation of the (+)-cis-(1S,2R) enantiomer was delayed until the (−)-cis-(1R,2S) enantiomer was completely depleted. When incubated with nonracemic mixtures of para-substituted cis-toluene dihydrodiols, CDD always oxidized the major enantiomer at a higher rate than the minor enantiomer. When incubated with racemic 1-indanol, CDD enantioselectively transformed the (+)-(1S) enantiomer to 1-indanone. This stereoselective transformation shows that CDD also acted as an alcohol dehydrogenase. Additionally, CDD was able to oxidize (+)-cis-(1R,2S)-dihydroxy-1,2-dihydronaphthalene, (+)-cis-monochlorobiphenyl dihydrodiols, and (+)-cis-toluene dihydrodiol to the corresponding catechols. PMID:10583971

Cis-Chlorobenzene dihydrodiol dehydrogenase (TcbB) from Pseudomonas sp. strain P51, expressed in Escherichia coli DH5{alpha}(pTCB149), catalyzes enantioselective dehydrogenase reactions

Energy Technology Data Exchange (ETDEWEB)

Raschke, H.; Fleischmann, T.; Meer, J.R. van der; Kohler, H.P.E.

1999-12-01

cis-Chlorobenzene dihydrodiol dehydrogenase (CDD) from Pseudomonas sp. strain P51, cloned into Escherichia coli DH5{alpha}(pTCB149) was able to oxidize cis-dihydrodihydroxy derivatives (cis-dihydrodiols) of dihydronaphthalene, indene, and four para-substituted toluenes to the corresponding catechols. During the incubation of a nonracemic mixture of cis-1,2-indandiol, only the (+)-cis-(1R,2S) enantiomer was oxidized; the (-)-cis-(S,2R) enantiomer remained unchanged, CDD oxidized both enantiomers of cis-1,2-dihydroxy-1,2,3,4-tetrahydronaphthalene, but oxidation of the (+)-cis-(1S,2R) enantiomer was delayed until the (-)-cis-(1R,2S) enantiomer was completely depleted. When incubated with nonracemic mixtures of para-substituted cis-toluene dihydrodiols, CDD always oxidized the major enantiomer at a higher rate than the minor enantiomer. When incubated with racemic 1-indanol, CDD enantioselectively transformed the (+)-(1S) enatiomer to 1-indanone. This stereoselective transformation shows that CDD also acted as an alcohol dehydrogenase. Additionally, CDD was able to oxidize (+)-cis-(1R,2S)-dihydroxy-1,2-dihydronaphthalene, (+)-cis-monochlorobiphenyl dihydrodiols, and (+)-cis-toluene dihydrodiol to the corresponding catechols.

Spent fuel storage criticality safety

Energy Technology Data Exchange (ETDEWEB)

Amin, E M; Elmessiry, A M [National center of nuclear safety and radiation control atomic energy authority, (Egypt)

1995-10-01

The safety aspects of the spent fuel storage pool of the Egyptian test and research reactor one (ET-R R-1) has to be assessed as part of a general overall safety evaluation to be included in a safety analysis report (SAR) for this reactor. The present work treats the criticality safety of the spent fuel storage pool. Conservative calculations based on using fresh fuel has been performed, as well as less conservative using burned fuel. The calculations include cross library generation for burned and fresh fuel for the ET-R R-1 fuel type. The WIMS-D 4 code has been used in library generation and burn up calculation the critically calculations are performed using the one dimensional transport code (ANISN) and the two dimensional diffusion code (DIXY2). The possibility of increasing the storage efficiency either by insertion of absorber sheets of soluble boron salts or by reduction of fuel rod separation has been studied. 8 figs., 2 tabs.

Spent fuel storage criticality safety

International Nuclear Information System (INIS)

Amin, E.M.; Elmessiry, A.M.

1995-01-01

The safety aspects of the spent fuel storage pool of the Egyptian test and research reactor one (ET-R R-1) has to be assessed as part of a general overall safety evaluation to be included in a safety analysis report (SAR) for this reactor. The present work treats the criticality safety of the spent fuel storage pool. Conservative calculations based on using fresh fuel has been performed, as well as less conservative using burned fuel. The calculations include cross library generation for burned and fresh fuel for the ET-R R-1 fuel type. The WIMS-D 4 code has been used in library generation and burn up calculation the critically calculations are performed using the one dimensional transport code (ANISN) and the two dimensional diffusion code (DIXY2). The possibility of increasing the storage efficiency either by insertion of absorber sheets of soluble boron salts or by reduction of fuel rod separation has been studied. 8 figs., 2 tabs

Radiation Safety Culture in Medicine AFROSAFE_R_A_D

International Nuclear Information System (INIS)

Nyabanda, R.

2017-01-01

Ionizing radiation that include X-rays and Gamma rays Radio waves, infrared and visible light carries sufficient energy to free electrons from atoms or molecules. Becquerel first person to discover evidence of radioactivity, who shared a Nobel Prize for physics in 1903 with Marie and Pierre Curie. Prof Sievert and Louis Harold Gray are the Medical physicists who had major contribution in the study of the biological effects of radiation. Ionizing radiation causes displacement of an electron which can inflict damage on DNA either directly or indirectly. A radiation-safety campaign developed by the radiation health workers in Africa. Radiosensitive organs is highest in cells which are highly mitotic or undifferentiated. E.g basal epidermis, bone marrow, thymus, gonads, and lens cells. Relatively low radiosensitivity in muscle, bones, and nervous system tissues. A radiation-safety campaign developed by the radiation health workers in Africa. AFROSAFE Strategies Strengthen radiation protection of patients, health workers and public, Promote safe and appropriate use of ionizing radiation in medicine. Foster improvement of the benefit-risk dialogue with patients and the public. Enhance the safety and quality of radiological procedures in medicine, Promote safety in radiological equipment and facilities and Promote research in radiation protection and safety

ITER safety

International Nuclear Information System (INIS)

Raeder, J.; Piet, S.; Buende, R.

1991-01-01

As part of the series of publications by the IAEA that summarize the results of the Conceptual Design Activities for the ITER project, this document describes the ITER safety analyses. It contains an assessment of normal operation effluents, accident scenarios, plasma chamber safety, tritium system safety, magnet system safety, external loss of coolant and coolant flow problems, and a waste management assessment, while it describes the implementation of the safety approach for ITER. The document ends with a list of major conclusions, a set of topical remarks on technical safety issues, and recommendations for the Engineering Design Activities, safety considerations for siting ITER, and recommendations with regard to the safety issues for the R and D for ITER. Refs, figs and tabs

An Overview of INEL Fusion Safety R&D Facilities

Science.gov (United States)

McCarthy, K. A.; Smolik, G. R.; Anderl, R. A.; Carmack, W. J.; Longhurst, G. R.

1997-06-01

The Fusion Safety Program at the Idaho National Engineering Laboratory has the lead for fusion safety work in the United States. Over the years, we have developed several experimental facilities to provide data for fusion reactor safety analyses. We now have four major experimental facilities that provide data for use in safety assessments. The Steam-Reactivity Measurement System measures hydrogen generation rates and tritium mobilization rates in high-temperature (up to 1200°C) fusion relevant materials exposed to steam. The Volatilization of Activation Product Oxides Reactor Facility provides information on mobilization and transport and chemical reactivity of fusion relevant materials at high temperature (up to 1200°C) in an oxidizing environment (air or steam). The Fusion Aerosol Source Test Facility is a scaled-up version of VAPOR. The ion-implanta-tion/thermal-desorption system is dedicated to research into processes and phenomena associated with the interaction of hydrogen isotopes with fusion materials. In this paper we describe the capabilities of these facilities.

Association of Safety Culture with Surgical Site Infection Outcomes.

Science.gov (United States)

Fan, Caleb J; Pawlik, Timothy M; Daniels, Tania; Vernon, Nora; Banks, Katie; Westby, Peggy; Wick, Elizabeth C; Sexton, J Bryan; Makary, Martin A

2016-02-01

Hospital workplace culture may have an impact on surgical outcomes; however, this association has not been established. We designed a study to evaluate the association between safety culture and surgical site infection (SSI). Using the Hospital Survey on Patient Safety Culture and National Healthcare Safety Network definitions, we measured 12 dimensions of safety culture and colon SSI rates, respectively, in the surgical units of Minnesota community hospitals. A Pearson's r correlation was calculated for each of 12 dimensions of surgical unit safety culture and SSI rate and then adjusted for surgical volume and American Society of Anesthesiologists (ASA) classification. Seven hospitals participated in the study, with a mean survey response rate of 43%. The SSI rates ranged from 0% to 30%, and surgical unit safety culture scores ranged from 16 to 92 on a scale of 0 to 100. Ten dimensions of surgical unit safety culture were associated with colon SSI rates: teamwork across units (r = -0.96; 95% CI [-0.76, -0.99]), organizational learning (r = -0.95; 95% CI [-0.71, -0.99]), feedback and communication about error (r = -0.92; 95% CI [-0.56, -0.99]), overall perceptions of safety (r = -0.90; 95% CI [-0.45, -0.99]), management support for patient safety (r = -0.90; 95% CI [-0.44, -0.98]), teamwork within units (r = -0.88; 95% CI [-0.38, -0.98]), communication openness (r = -0.85; 95% CI [-0.26, -0.98]), supervisor/manager expectations and actions promoting safety (r = -0.85; 95% CI [-0.25, -0.98]), non-punitive response to error (r = -0.78; 95% CI [-0.07, -0.97]), and frequency of events reported (r = -0.76; 95% CI [-0.01, -0.96]). After adjusting for surgical volume and ASA classification, 9 of 12 dimensions of surgical unit safety culture were significantly associated with lower colon SSI rates. These data suggest an important role for positive safety and teamwork culture and engaged hospital management in producing high-quality surgical

The effect of Bi substitution on the microstructure and magnetic properties of the Sr0.4Ba0.3La0.3Fe12−xBixO19 hexagonal ferrites

International Nuclear Information System (INIS)

Yang, Yujie; Wang, Fanhou; Liu, Xiansong; Shao, Juxiang; Feng, Shuangjiu; Huang, Duohui; Li, Mingling

2017-01-01

Bi 3+ ions doped M-type hexaferrites, Sr 0.4 Ba 0.3 La 0.3 Fe 12−x Bi x O 19 (0≤x≤0.7), were prepared by the ceramic process. The phase components of the magnetic powders were investigated by X-ray diffraction. The results show that a single magnetoplumbite phase is obtained for the magnetic powders with x from 0 to 0.2, and BiFeO 3 as a second phase appears when Bi content (x)≥0.3. The micrographs of the sintered magnets were observed by a field emission scanning electron microscopy. The sintered magnets are formed of hexagonal-shaped crystals. The magnetic properties of the sintered magnets were measured at room temperature by a permanent magnetic measuring system. The remanence (B r ) first increases with x from 0 to 0.2, and then decreases when Bi content (x)≥0.2. The intrinsic coercivity (H cj ) and magnetic induction coercivity (H cb ) firstly decrease quickly with x from 0 to 0.1, and then increase linearly when Bi content (x)≥0.1. The maximum energy product [(BH) max ] increases with x from 0 to 0.3, and then decreases when Bi content (x)≥0.3. The ratio H k /H cj ratio first increases with Bi content (x) from 0 to 0.4. And the H k /H cj ratio decreases when x≥0.4. - Highlights: • Sr 0.4 Ba 0.3 La 0.3 Fe 12−x Bi x O 19 (0≤x≤0.7) hexaferrites were prepared by the ceramic process. • A single magnetoplumbite phase is obtained for the magnetic powders with x from 0 to 0.2. • B r first increases with x from 0 to 0.2, and then decreases when x≥0.2. • H cj and H cb firstly decrease quickly with x from 0 to 0.1, and then increase linearly when x≥0.1.

R and D on support to ITER safety assessment

International Nuclear Information System (INIS)

Van Dorsselaere, J.P.; Perrault, D.; Barrachin, M.; Bentaib, A.; Bez, J.; Cortes, P.; Seropian, C.; Tregoures, N.; Vendel, J.

2009-01-01

After performing its first ITER safety assessment in 2002 on behalf of the French 'Autorite de Surete Nucleaire (ASN)', the French 'Institut de Radioprotection et de Surete Nucleaire (IRSN)' is now analysing the new ITER Fusion facility safety file. The operator delivered this file to the ASN as part of its request for a creation decree, legally necessary before building works can begin on the site. The IRSN first task in following ITER throughout its lifetime is to study the safety approach adopted by the operator and the associated issues. Such a challenging new technology calls for further in-house expertise and so in parallel a R and D program has been set up to support this safety assessment process, now and in the next years. Its main objectives are to identify the key parameters for mastering some risks (that would have been insufficiently justified by the operator) and to perform some verifications with methods and codes independent from the operator's ones. Priority has been given to four technical issues (others could be investigated in the future, like the behaviour of activated corrosion products). The first issue concerns the simulation of accident sequences with the help of the ASTEC European system code, developed by IRSN (jointly with its German counterpart, the GRS) for severe accidents in Pressurised Water Reactors. A preliminary analysis showed that most of its physical models are already applicable, e.g., for thermal-hydraulics in accidents caused by water or air ingress into the vacuum vessel (VV) or dust transport. Work has started in 2008 on some model adaptations, for instance oxidation of VV first wall materials by steam or air, and on validation on the ITER-specific ICE and LOVA experiments. Other model improvements are planned in the next years, as feedback from the work done for the other technical issues and from the code validation. The second issue concerns the risk of gas explosion due to concentrations of hydrogen and carbon

Gas-cooled breeder reactor safety

Energy Technology Data Exchange (ETDEWEB)

Chermanne, J.; Burgsmueller, P. [Societe Belge pour l' Industrie Nucleaire, Brussels

1981-01-15

The European Association for the Gas-cooled Breeder Reactor (G B R A), set-up in 1969 prepared between 1972 and 1974 a 1200 MWe Gas-cooled Breeder Reactor (G B R) commercial reference design G B R 4. It was then found necessary that a sound and neutral appraisal of the G B R licenseability be carried out. The Commission of the European Communities (C E C) accepted to sponsor this exercise. At the beginning of 1974, the C E C convened a group of experts to examine on a Community level, the safety documents prepared by the G B R A. A working party was set-up for that purpose. The experts examined a ''Preliminary Safety Working Document'' on which written questions and comments were presented. A ''Supplement'' containing the answers to all the questions plus a detailed fault tree and reliability analysis was then prepared. After a final study of this document and a last series of discussions with G B R A representatives, the experts concluded that on the basis of the evidence presented to the Working Party, no fundamental reasons were identified which would prevent a Gas-cooled Breeder Reactor of the kind proposed by the G B R A achieving a satisfactory safety status. Further work carried out on ultimate accident have confirmed this conclusion. One can therefore claim that the overall safety risk associated with G B R s compares favourably with that of any other reactor system.

Efficacy and safety of rVIII-SingleChain: results of a phase 1/3 multicenter clinical trial in severe hemophilia A

Science.gov (United States)

Mahlangu, Johnny; Kuliczkowski, Kazimierz; Karim, Faraizah Abdul; Stasyshyn, Oleksandra; Kosinova, Marina V.; Lepatan, Lynda Mae; Skotnicki, Aleksander; Boggio, Lisa N.; Klamroth, Robert; Oldenburg, Johannes; Hellmann, Andrzej; Santagostino, Elena; Baker, Ross I.; Fischer, Kathelijn; Gill, Joan C.; P’Ng, Stephanie; Chowdary, Pratima; Escobar, Miguel A.; Khayat, Claudia Djambas; Rusen, Luminita; Bensen-Kennedy, Debra; Blackman, Nicole; Limsakun, Tharin; Veldman, Alex; St. Ledger, Katie

2016-01-01

Recombinant VIII (rVIII)-SingleChain is a novel B-domain–truncated recombinant factor VIII (rFVIII), comprised of covalently bonded factor VIII (FVIII) heavy and light chains. It was designed to have a higher binding affinity for von Willebrand factor (VWF). This phase 1/3 study investigated the efficacy and safety of rVIII-SingleChain in the treatment of bleeding episodes, routine prophylaxis, and surgical prophylaxis. Participants were ≥12 years of age, with severe hemophilia A (endogenous FVIII <1%). The participants were allocated by the investigator to receive rVIII-SingleChain in either an on-demand or prophylaxis regimen. Of the 175 patients meeting study eligibility criteria, 173 were treated with rVIII-SingleChain, prophylactically (N = 146) or on-demand (N = 27). The total cumulative exposure was 14 306 exposure days (EDs), with 120 participants reaching ≥50 EDs and 52 participants having ≥100 EDs. Hemostatic efficacy was rated by the investigator as excellent or good in 93.8% of the 835 bleeds treated and assessed. Across all prophylaxis regimens, the median annualized spontaneous bleeding rate was 0.00 (Q1, Q3: 0.0, 2.4) and the median overall annualized bleeding rate (ABR) was 1.14 (Q1, Q3: 0.0, 4.2). Surgical hemostasis was rated as excellent/good in 100% of major surgeries by the investigator. No participant developed FVIII inhibitors. In conclusion, rVIII-SingleChain is a novel rFVIII molecule showing excellent hemostatic efficacy in surgery and in the control of bleeding events, low ABR in patients on prophylaxis, and a favorable safety profile in this large clinical study. This trial was registered at www.clinicaltrials.gov as #NCT01486927. PMID:27330001

A randomized, phase 1/2 trial of the safety, tolerability, and immunogenicity of bivalent rLP2086 meningococcal B vaccine in healthy infants.

Science.gov (United States)

Martinon-Torres, Federico; Gimenez-Sanchez, Francisco; Bernaola-Iturbe, Enrique; Diez-Domingo, Javier; Jiang, Qin; Perez, John L

2014-09-08

Neisseria meningitidis serogroup B (MnB) is a major cause of invasive meningococcal disease in infants. A conserved, surface-exposed lipoprotein, LP2086 (a factor H-binding protein [fHBP]), is a promising MnB vaccine target. A bivalent, recombinant vaccine targeting the fHBP (rLP2086) of MnB was developed. This phase 1/2 clinical study was designed to assess the immunogenicity, safety, and tolerability of a 4-dose series of the rLP2086 vaccine at 20-, 60-, 120-, or 200-μg dose levels in vaccine-naive infants when given with routine childhood vaccines. The study was to consist of two phases: a single-blind sentinel phase and an open-label full enrollment phase. During the sentinel phase, randomization of subjects to the next higher dose was delayed pending a 14-day safety review of dose 1 of the preceding dose cohort. The full enrollment phase was to occur after completion of the sentinel phase. Local reactions were generally mild and adverse events infrequent; however, after only 46 infants were randomized into the study, fever rates were 64% and 90% in subjects receiving one 20- or 60-μg rLP2086 dose, respectively. Most fevers were group and 1 subject in the 60-μg group experienced fevers >39.0°C; no fevers were >40.0°C. Due to these high fever rates, the study was terminated early. No immunogenicity data were collected. This report discusses the safety and acceptability of rLP2086 in infants after one 20- or 60-μg dose. Due to the high fever rate experienced in the 20- and 60-μg groups, rLP2086 in the current formulation may not be acceptable for infants. Copyright © 2014. Published by Elsevier Ltd.

Experimental Conditions: SE3_S02_M03_D03 [Metabolonote[Archive

Lifescience Database Archive (English)

Full Text Available SE3_S02_M03_D03 SE3 Comparison of fruit metabolites among tomato varieties 1 SE3_S0...2 Solanum lycopersicum House Momotaro fruit SE3_S02_M03 6.7 mg [MassBase ID] MDLC1_25531 SE3_MS1 LC-FT-ICR-M

Application of safety checklist to the analysis of the IEA-R1 reactor water retreatment system; Utilizacao do checklist de seguranca na analise do sistema de retratamento de agua do reator IEA-R1

Energy Technology Data Exchange (ETDEWEB)

Sauer, Maria Eugenia Lago Jacques; Sara Neto, Antonio Jorge; Lima, Toni Carlos Caboclo de; Ribeiro, Maria Alice Morato [Instituto de Pesquisas Energeticas e Nucleares (IPEN), Sao Paulo, SP (Brazil)]. E-mail: melsauer@ipen.br

2005-07-01

In 1999, the management of the IEA-R1 Research Reactor (pool type - 5 MWth), located at IPEN/CNEN-SP, started the evaluation of the Reactor Pool Water Retreatment System to identify operational aspects, which could compromise the operators safety. The purpose was to identify and propose enhancements to the system which would be installed to substitute for the existing one. This process was conducted through a qualitative study of the system in operation. This study was carried out by a team composed of specialists in reactor operation, systems maintenance and radiological protection, and one safety analyst. The study consisted, basically, in local inspections to verify the physical and operational conditions of each equipment / component as well as aspects related to maintenance activities of the system. The process control and the operator procedures associated with the retreatment of the reactor pool water were also reviewed. The methodology adopted to develop the study was based in process hazard analysis technique named Safety Checklist. This paper presents a summary of this study and the main results obtained. Some operational and safety problems identified, the prevention and/or correction means to avoid them, and the recommendations and suggestions that have been implemented to the new design of the IEA-R1 Reactor Water Retreatment System, whose installation was concluded in 2003, are also presented. (author)

Helium production cross section Measurement of Pb and Sn for 14.9 MeV neutrons

Energy Technology Data Exchange (ETDEWEB)

Takao, Yoshiyuki; Fujimoto, Toshihiro; Ozaki, Shuji; Muramasu, Masatomo; Nakashima, Hideki [Kyushu Univ., Fukuoka (Japan); Kanda, Yukinori; Ikeda, Yujiro

1998-03-01

Helium production cross sections of lead and tin for 14.9 MeV neutrons were measured by helium accumulation method. Lead and tin samples were irradiated with FNS, an intense d-T neutron source of JAERI. The amount of helium produced in the samples by the neutron irradiation was measured with the Helium Atoms Measurement System (HAMS) at Kyushu University. As the samples contained a small amount of helium because of their small helium production cross sections at 14.9 MeV, the samples were evaporated by radiation from a tungsten filament to decrease background gases at helium measurement. Uncertainties of the present results were less than {+-}4.4%. The results were compared with other experimental data in the literature and also compared with the evaluated values in JENDL-3.2. (author)

Multiparticle excitations and identical bands in the superdeformed 149Gd nucleus

International Nuclear Information System (INIS)

Flibotte, S.; Hackman, G.; Theisen, C.; Andrews, H.R.; Ball, G.C.; Beausang, C.W.; Beck, F.A.; Belier, G.; Bentley, M.A.; Byrski, T.; Curien, D.; de France, G.; Disdier, D.; Duchene, G.; Fallon, P.; Haas, B.; Janzen, V.P.; Jones, P.M.; Kharraja, B.; Kuehner, J.A.; Lisle, J.C.; Merdinger, J.C.; Mullins, S.M.; Paul, E.S.; Prevost, D.; Radford, D.C.; Rauch, V.; Smith, J.F.; Styczen, J.; Twin, P.J.; Vivien, J.P.; Waddington, J.C.; Ward, D.; Zuber, K.

1993-01-01

Eight superdeformed rotational bands have been observed in the 149 Gd nucleus. Several excited bands have partners in neighboring nuclei which differ by up to four nucleons, with nearly identical dynamic moments of inertia and quantized γ-ray phasing. These observations cannot be easily explained by theoretical models including an intrinsic scaling with mass of the moment of inertia. A paired backbend and an interaction due to an accidental degeneracy between two superdeformed levels have also been observed

NCBI nr-aa BLAST: CBRC-GGAL-03-0034 [SEVENS

Lifescience Database Archive (English)

Full Text Available CBRC-GGAL-03-0034 ref|NP_036916.1| cannabinoid receptor 1 (brain) [Rattus norvegicu...s] sp|P20272|CNR1_RAT Cannabinoid receptor 1 (CB1) (CB-R) (Brain-type cannabinoid receptor) emb|CAA39332.1| CB1 cann...abinoid receptor [Rattus norvegicus] gb|AAA99067.1| neuronal cannabinoid receptor gb|EDL98589.1| cann...abinoid receptor 1 (brain) [Rattus norvegicus] prf||1613453A cannabinoid receptor NP_036916.1 0.0 93% ...

NCBI nr-aa BLAST: CBRC-MDOM-03-0034 [SEVENS

Lifescience Database Archive (English)

Full Text Available CBRC-MDOM-03-0034 ref|ZP_05988476.1| putative competence protein EC [Mannheimia hae...molytica serotype A2 str. BOVINE] ref|ZP_05990926.1| putative competence protein EC [Mannheimia haemolytica ...serotype A2 str. OVINE] gb|EEY11140.1| putative competence protein EC [Mannheimia haemolytica serotype A2 st...r. OVINE] gb|EEY13570.1| putative competence protein EC [Mannheimia haemolytica serotype A2 str. BOVINE] ZP_05988476.1 0.63 23% ...

NCBI nr-aa BLAST: CBRC-MDOM-03-0119 [SEVENS

Lifescience Database Archive (English)

Full Text Available CBRC-MDOM-03-0119 ref|ZP_05988476.1| putative competence protein EC [Mannheimia hae...molytica serotype A2 str. BOVINE] ref|ZP_05990926.1| putative competence protein EC [Mannheimia haemolytica ...serotype A2 str. OVINE] gb|EEY11140.1| putative competence protein EC [Mannheimia haemolytica serotype A2 st...r. OVINE] gb|EEY13570.1| putative competence protein EC [Mannheimia haemolytica serotype A2 str. BOVINE] ZP_05988476.1 0.22 25% ...

An improved slow neutron spectrometer at nuclear research reactor et-r r-1. Vol. 2

Energy Technology Data Exchange (ETDEWEB)

Abu El-Ela, M A [Reactor and Neutron Physics, Nuclear Research Center, AEA, Cairo (Egypt)

1996-03-01

An improved slow neutron selector has been aligned at channel number 6 of the nuclear research reactor ET-R R-1 Inshas. The flight path is 4 meter. The collimator-rotor-collimator system has the dimensions 0.3 x 2.5 x 70 cm with the rotor diameter 16 cm and 3 slits of 0.3 x 2.5 cm cross section. The rotor rotation rate varies between 600 r.p.m. the counting system has one of the best modern high electronic advanced technology time analyzer with minimum dwell time 2 sec, 8192 channels and a double detector inputs of TTL and NEG NIM standard pulses. The analyzer external triggering signals are of TTL standard type. A special design {sup 3} He detector for time of flight spectrometry has been used in the SNS. The reactor bare thermal neutron spectrum has been successfully measured, to show good agreement with the previous data. 6 figs.

Phase I study of safety and immunogenicity of an Escherichia coli-derived recombinant protective antigen (rPA) vaccine to prevent anthrax in adults.

Science.gov (United States)

Brown, Bruce K; Cox, Josephine; Gillis, Anita; VanCott, Thomas C; Marovich, Mary; Milazzo, Mark; Antonille, Tanya Santelli; Wieczorek, Lindsay; McKee, Kelly T; Metcalfe, Karen; Mallory, Raburn M; Birx, Deborah; Polonis, Victoria R; Robb, Merlin L

2010-11-05

The fatal disease caused by Bacillus anthracis is preventable with a prophylactic vaccine. The currently available anthrax vaccine requires a lengthy immunization schedule, and simpler and more immunogenic options for protection against anthrax are a priority for development. In this report we describe a phase I clinical trial testing the safety and immunogenicity of an anthrax vaccine using recombinant Escherichia coli-derived, B. anthracis protective antigen (rPA). A total of 73 healthy adults ages 18-40 were enrolled and 67 received 2 injections separated by 4 weeks of either buffered saline placebo, or rPA formulated with or without 704 µg/ml Alhydrogel® adjuvant in increasing doses (5, 25, 50, 100 µg) of rPA. Participants were followed for one year and safety and immunologic data were assessed. Tenderness and warmth were the most common post-injection site reactions. No serious adverse events related to the vaccine were observed. The most robust humoral immune responses were observed in subjects receiving 50 µg of rPA formulated with Alhydrogel® with a geometric mean concentration of anti-rPA IgG antibodies of 283 µg/ml and a toxin neutralizing geometric 50% reciprocal geometric mean titer of 1061. The highest lymphoproliferative peak cellular response (median Lymphocyte Stimulation Index of 29) was observed in the group receiving 25 µg Alhydrogel®-formulated rPA. The vaccine was safe, well tolerated and stimulated a robust humoral and cellular response after two doses. ClinicalTrials.gov NCT00057525.

Report of the review committee on evaluation of the R and D subjects in the field of nuclear safety research

International Nuclear Information System (INIS)

2000-09-01

On the basis of the JAERI's Basic Guidelines for the Research Evaluation Methods and the Practices Manuals of the Institution Evaluation Committee and Research Evaluation Committee, the Ad Hoc Review Committee on Nuclear Safety Research composed of twelve experts was set up under the Research Evaluation Committee of the JAERI in order to review the R and D subjects to be implemented for five years starting in FY2000 in the Nuclear Safety Research Center (Department of Reactor Safety Research, Department of Fuel Cycle Safety Research and Department of Safety Research Technical Support). The Ad Hoc Review Committee meeting was held on January 20, 2000. According to the review methods including review items, points of review and review criteria, determined by the Research Evaluation Committee, the review was conducted based on the research plan documents submitted in advance and presentations by the Department Directors. The review report was submitted to the Research Evaluation Committee for further review and discussions in its meeting held on August 31, 2000. The Research Evaluation Committee recognized the review results as appropriate. This report describes the review results. (author)

Integrating psychosocial safety climate in the JD-R model: A study amongst Malaysian workers

Directory of Open Access Journals (Sweden)

Mohd A. Idris

2011-05-01

Research purpose: We expanded the Job Demands and Resources (JD-R model by proposing psychosocial safety climate (PSC as a precursor to job demands and job resources. As PSC theoretically influences the working environment, the study hypothesized that PSC has an impact on performance via both health erosion (i.e. burnout and motivational pathways (i.e. work engagement. Motivation for the study: So far, integration of PSC in the JD-R model is only tested in a Western context (i.e. Australia. We tested the emerging construct of PSC in Malaysia, an Eastern developing country in the Asian region. Research design, approach and method: A random population based sample was derived using household maps provided by Department of Statistics, Malaysia; 291 employees (response rate 50.52% from the State of Selangor, Malaysia participated. Cross-sectional data were analysed using structural equation modelling. Main findings: We found that PSC was negatively related to job demands and positively related to job resources. Job demands, in turn, predicted burnout (i.e. exhaustion and cynicism, whereas job resources predicted engagement. Both burnout and engagement were associated with performance. Bootstrapping showed significant indirect effects of PSC on burnout via job demands, PSC on performance via burnout and PSC on performance via the resources-engagement pathway. Practical/managerial implications: Our findings are consistent with previous research that suggests that PSC should be a target to improve working conditions and in turn reduce burnout and improve engagement and productivity. Contribution/value-add: These findings suggest that JD-R theory may be expanded to include PSC as an antecedent and that the expanded JD-R model is largely valid in an Eastern, developing economy setting.

Global metabolic analyses identify key differences in metabolite levels between polymyxin-susceptible and polymyxin-resistant Acinetobacter baumannii.

Science.gov (United States)

Maifiah, Mohd Hafidz Mahamad; Cheah, Soon-Ee; Johnson, Matthew D; Han, Mei-Ling; Boyce, John D; Thamlikitkul, Visanu; Forrest, Alan; Kaye, Keith S; Hertzog, Paul; Purcell, Anthony W; Song, Jiangning; Velkov, Tony; Creek, Darren J; Li, Jian

2016-02-29

Multidrug-resistant Acinetobacter baumannii presents a global medical crisis and polymyxins are used as the last-line therapy. This study aimed to identify metabolic differences between polymyxin-susceptible and polymyxin-resistant A. baumannii using untargeted metabolomics. The metabolome of each A. baumannii strain was measured using liquid chromatography-mass spectrometry. Multivariate and univariate statistics and pathway analyses were employed to elucidate metabolic differences between the polymyxin-susceptible and -resistant A. baumannii strains. Significant differences were identified between the metabolic profiles of the polymyxin-susceptible and -resistant A. baumannii strains. The lipopolysaccharide (LPS) deficient, polymyxin-resistant 19606R showed perturbation in specific amino acid and carbohydrate metabolites, particularly pentose phosphate pathway (PPP) and tricarboxylic acid (TCA) cycle intermediates. Levels of nucleotides were lower in the LPS-deficient 19606R. Furthermore, 19606R exhibited a shift in its glycerophospholipid profile towards increased abundance of short-chain lipids compared to the parent polymyxin-susceptible ATCC 19606. In contrast, in a pair of clinical isolates 03-149.1 (polymyxin-susceptible) and 03-149.2 (polymyxin-resistant, due to modification of lipid A), minor metabolic differences were identified. Notably, peptidoglycan biosynthesis metabolites were significantly depleted in both of the aforementioned polymyxin-resistant strains. This is the first comparative untargeted metabolomics study to show substantial differences in the metabolic profiles of the polymyxin-susceptible and -resistant A. baumannii.

Ultrafast photodynamics of the indoline dye D149 adsorbed to porous ZnO in dye-sensitized solar cells.

Science.gov (United States)

Rohwer, Egmont; Richter, Christoph; Heming, Nadine; Strauch, Kerstin; Litwinski, Christian; Nyokong, Tebello; Schlettwein, Derck; Schwoerer, Heinrich

2013-01-14

We investigate the ultrafast dynamics of the photoinduced electron transfer between surface-adsorbed indoline D149 dye and porous ZnO as used in the working electrodes of dye-sensitized solar cells. Transient absorption spectroscopy was conducted on the dye in solution, on solid state samples and for the latter in contact to a I(-)/I(3)(-) redox electrolyte typical for dye-sensitized solar cells to elucidate the effect of each component in the observed dynamics. D149 in a solution of 1:1 acetonitrile and tert-butyl alcohol shows excited-state lifetimes of 300±50 ps. This signature is severely quenched when D149 is adsorbed to ZnO, with the fastest component of the decay trace measured at 150±20 fs due to the charge-transfer mechanism. Absorption bands of the oxidized dye molecule were investigated to determine regeneration times which are in excess of 1 ns. The addition of the redox electrolyte to the system results in faster regeneration times, of the order of 1 ns. Copyright © 2013 WILEY-VCH Verlag GmbH & Co. KGaA, Weinheim.

Magnitude and reactivity consequences of accidental moisture ingress into the Modular High-Temperature Gas-Cooled Reactor core

International Nuclear Information System (INIS)

Smith, O.L.

1992-01-01

Accidental admission of moisture into the primary system of a Modular High-Temperature Gas-Cooled Reactor (MHTGR) has been identified in US Department of Energy-sponsored studies as an important safety concern. The work described here develops an analytical methodology to quantify the pressure and reactivity consequences of steam-generator tube rupture and other moistureingress-related incidents. Important neutronic and thermohydraulic processes are coupled with reactivity feedback and safety and control system responses. Rate and magnitude of steam buildup are found to be dominated by major system features such as break size in comparison with safety valve capacity and reliability, while being less sensitive to factors such as heat transfer coefficients. The results indicate that ingress transients progress at a slower pace than previously predicted by bounding analyses, with milder power overshoots and more time for operator or automatic corrective actions

33 CFR 149.697 - What are the requirements for a noise level survey?

Science.gov (United States)

2010-07-01

... and Equipment Noise Limits § 149.697 What are the requirements for a noise level survey? (a) A survey... measured over 12 hours to derive a time weighted average (TWA) using a sound level meter and an A-weighted filter or equivalent device. (c) If the noise level throughout a space is determined to exceed 85 db(A...

Measurement and analysis of abrasive particles velocities in AWSJ

Czech Academy of Sciences Publication Activity Database

Zeleňák, Michal; Foldyna, Josef; Linde, M.; Pude, F.; Rentsch, T.; Fernolendt, J.; Poort, H. U.

2016-01-01

Roč. 149, July 2016 (2016), s. 77-86 E-ISSN 1877-7058. [International Conference on Manufacturing Engineering and Materials, ICMEM 2016. Nový Smokovec, 06.06.2016-10.06.2016] R&D Projects: GA MŠk(CZ) LO1406; GA MŠk ED2.1.00/03.0082 Institutional support: RVO:68145535 Keywords : AWSJ * PIV * LIF Subject RIV: JQ - Machines ; Tools http://www.sciencedirect.com/science/article/pii/S1877705816311493

33 CFR 149.419 - Can the water supply for the helicopter deck fire protection system be part of a fire water system?

Science.gov (United States)

2010-07-01

... 33 Navigation and Navigable Waters 2 2010-07-01 2010-07-01 false Can the water supply for the... § 149.419 Can the water supply for the helicopter deck fire protection system be part of a fire water system? (a) The water supply for the helicopter deck fire protection system required under § 149.420 or...

Safety-related Innovative Nuclear Reactor Technology Elements R and D (SINTER) Network and Global HTGR R and D Network (GHTRN). Strategic benefits of international networking

International Nuclear Information System (INIS)

Von Lensa, W.

1998-01-01

Action on 'Safety-related Innovative Nuclear Reactor Technology Elements - R and D - (SINTER) Network' both aim at the identification of priority items for sustainable innovations of nuclear technologies and work-shared European collaboration structures. Such an approach can also be realised for future R and D on HTGR-related R and D under the umbrella of the IAEA as already proposed by the 'International Working Group on Gas-Cooled Reactors (IWGGCR)' in 1996 and illustrated in this paper for the construction of a 'Global HTGR R and D Network (GHTRN)'. 3 refs

Output Feedback Dissipation Control for the Power-Level of Modular High-Temperature Gas-Cooled Reactors

Directory of Open Access Journals (Sweden)

Zhe Dong

2011-11-01

Full Text Available Because of its strong inherent safety features and the high outlet temperature, the modular high temperature gas-cooled nuclear reactor (MHTGR is the chosen technology for a new generation of nuclear power plants. Such power plants are being considered for industrial applications with a wide range of power levels, thus power-level regulation is very important for their efficient and stable operation. Exploiting the large scale asymptotic closed-loop stability provided by nonlinear controllers, a nonlinear power-level regulator is presented in this paper that is based upon both the techniques of feedback dissipation and well-established backstepping. The virtue of this control strategy, i.e., the ability of globally asymptotic stabilization, is that it takes advantage of the inherent zero-state detectability property of the MHTGR dynamics. Moreover, this newly built power-level regulator is also robust towards modeling uncertainty in the control rod dynamics. If modeling uncertainty of the control rod dynamics is small enough to be omitted, then this control law can be simplified to a classical proportional feedback controller. The comparison of the control performance between the newly-built power controller and the simplified controller is also given through numerical study and theoretical analysis.

Modeling and Simulation of the Multi-module High Temperature Gas-cooled Reactor

International Nuclear Information System (INIS)

Liu Dan; Sun Jun; Sui Zhe; Xu Xiaolin; Ma Yuanle; Sun Yuliang

2014-01-01

The modular high temperature gas-cooled reactor (MHTGR) is characterized with the inherent safety. To enhance its economic benefit, the capital cost of MHTGR can be decreased by combining more reactor modules into one unit and realize the batch constructions in the concept of modularization. In the research and design of the multi-module reactors, one difficulty is to clarify the coupling effects of different modules in operating the reactors due to the shared feed water and main steam systems in the secondary loop. In the advantages of real-time simulation and coupling calculations of different modules and sub-systems, the operation of multi-module reactors can be studied and analyzed to understand the range and extent of the coupling effects. In the current paper; the engineering simulator for the multi-module reactors was realized and able to run in high performance computers, based on the research experience of the HTR-PM engineering simulator. The models were detailed introduced including the primary and secondary loops. The steady state of full power operation was demonstrated to show the good performance of six-module reactors. Typical dynamic processes, such as adjusting feed water flow rates and shutting down one reactor; were also tested to study the coupling effects in multi-module reactors. (author)

Prediction of high-energy (> 0.3 MeV) substorm-related magnetospheric particles

International Nuclear Information System (INIS)

Baker, D.N.; Belian, R.D.; Higbie, P.R.; Hones, E.W. Jr.

1979-01-01

Measurements both at 6.6 R/sub E/ and in the plasma sheet (greater than or equal to 18 R/sub E/) show that high energy substorm-accelerated particles occur preferentially when the solar wind speed (V/sub sw/) is high. Virtually no > 0.3 MeV protons, for example, are observed in association with substorms that occur when V/sub sw/ is 700 km/sec. These results suggest that realtime monitoring of interplanetary conditions could allow simple, effective prediction of high energy magnetospheric particle disturbances. 7 references

41 CFR 109-38.801 - Obtaining SF 149, U.S. Government National Credit Card.

Science.gov (United States)

2010-07-01

.... Government National Credit Card. 109-38.801 Section 109-38.801 Public Contracts and Property Management..., U.S. Government National Credit Card § 109-38.801 Obtaining SF 149, U.S. Government National Credit Card. DOE offices electing to use national credit cards shall request the assignment of billing address...

An oven control system based on MCU MSP430F149

International Nuclear Information System (INIS)

Jing Lan; Zhu Haijun; Liu Caihong; Liu Yali; Gao Shiwei; Chinese Academia of Sciences, Beijing

2004-01-01

This paper introduces the structure, principle and feature of new generation of 16 bit and Flash-type microcontroller which belongs to the Texas Instruments MSP430F149 series with low power consumption and high performance. Details of the hardware structure and analysis software of the oven control system based on the microcontroller are expatiated. this systerm has the characteristics of strong function, simple struction, high reliability, strong noise resistances, no peripheral chip etc. The requirements of the temperature measurement and control system are fulfilled. (authors)

Safety of Nuclear Power Plants: Design. Specific Safety Requirements (Spanish Edition)

International Nuclear Information System (INIS)

2012-01-01

This publication is a revision of Safety Requirements No. NS-R-1, Safety of Nuclear Power Plants: Design. It establishes requirements applicable to the design of nuclear power plants and elaborates on the safety objective, safety principles and concepts that provide the basis for deriving the safety requirements that must be met for the design of a nuclear power plant. It will be useful for organizations involved in the design, manufacture, construction, modification, maintenance, operation and decommissioning of nuclear power plants, as well as for regulatory bodies. Contents: 1. Introduction; 2. Applying the safety principles and concepts; 3. Management of safety in design; 4. Principal technical requirements; 5. General plant design; 6. Design of specific plant systems.

Safety of Nuclear Power Plants: Design. Specific Safety Requirements (Russian Edition)

International Nuclear Information System (INIS)

2012-01-01

This publication is a revision of Safety Requirements No. NS-R-1, Safety of Nuclear Power Plants: Design. It establishes requirements applicable to the design of nuclear power plants and elaborates on the safety objective, safety principles and concepts that provide the basis for deriving the safety requirements that must be met for the design of a nuclear power plant. It will be useful for organizations involved in the design, manufacture, construction, modification, maintenance, operation and decommissioning of nuclear power plants, as well as for regulatory bodies. Contents: 1. Introduction; 2. Applying the safety principles and concepts; 3. Management of safety in design; 4. Principal technical requirements; 5. General plant design; 6. Design of specific plant systems.

Novelties in design and construction of the advanced reactors

International Nuclear Information System (INIS)

Acosta Ezcurra, T.; Garcia Rodriguez, B.M.

1996-01-01

The advanced pressurized water reactors (APWR), advanced boiling water reactors (ABWR), advanced liquid metal reactors (ALMR), and modular high temperature gas-cooled reactors (MHTGR), as well as heavy water reactors (AHWR), are analyzed taking into account those characteristics which make them less complex, but safer than their current homologous ones. This fact simplifies their construction which reduces completion periods and costs, increasing safety and protection of the plants. It is demonstrated how the accumulated operational experience allows to find more standardized designs with some enhancement in the material and component technology and thus achieve also a better use of computerized systems

Production of 149Tb in deep inelastic transfer reactions: an approach to the angular momentum of fragments

International Nuclear Information System (INIS)

Rivet, M.F.; Bimbot, R.; Gardes, D.; Fleury, A.; Hubert, F.; Llabador, Y.

1978-01-01

The excitation functions for deep inelastic reactions in which two to six charges are transferred from 40 Ar and 63 Cu ions to rare earth targets have been measured using activation techniques, the observed radionuclides being 150 Dy, 151 Dy and 149 gTb. From the comparison of the curves relative to 149 gTb and those relative to 150 Dy, 151 Dy, it was deduced that the low spin isomer 149 gTb was produced with significant probability for low incident energies. Using data from (heavy ions, xn) reactions, it was possible to attribute this production to the deexcitation of Tb fragments formed in deep inelastic transfers with angular momenta lower than 9n. This result is in good agreement with the angular momentum calculations performed under the hypothesis that the initial angular momentum window leading to deep inelastic reactions is situated between the critical angular momentum for fusion and that corresponding to grazing collisions. As far as Cu induced reactions are concerned, both hypothesis of rolling and sticking are consistent with the experimental data. For Ar induced reactions, the results indicate that the stage of sticking is not reached when the incident energy is lower than 200 MeV

Bimatoprost 0.03% preservative-free ophthalmic solution versus bimatoprost 0.03% ophthalmic solution (Lumigan) for glaucoma or ocular hypertension: a 12-week, randomised, double-masked trial

Science.gov (United States)

Day, Douglas G; Walters, Thomas R; Schwartz, Gail F; Mundorf, Thomas K; Liu, Charlie; Schiffman, Rhett M; Bejanian, Marina

2013-01-01

Background/Aim To evaluate efficacy and safety of bimatoprost 0.03% preservative-free (PF) ophthalmic solution versus bimatoprost 0.03% (Lumigan) ophthalmic solution for glaucoma or ocular hypertension. Methods In this double-masked, parallel-group study, patients were randomised to bimatoprost PF or bimatoprost for 12 weeks. The primary analysis for non-inferiority was change from baseline in worse eye intraocular pressure (IOP) in the per-protocol population at week 12. For equivalence, it was average eye IOP in the intent-to-treat population at each time point at weeks 2, 6 and 12. Results 597 patients were randomised (bimatoprost PF, n=302 and bimatoprost, n=295). The 95% CI upper limit for worse eye IOP change from baseline was <1.5 mm Hg at each week 12 time point, meeting prespecified non-inferiority criteria. The 95% CI upper limit for the treatment difference for average IOP was 0.69 mm Hg and the lower limit was −0.50 mm Hg at all follow-up time points (hours 0, 2 and 8 at weeks 2, 6 and 12), meeting equivalence criteria. Both treatments showed decreases in mean average eye IOP at all follow-up time points (p<0.001), were safe and well tolerated. Conclusions Bimatoprost PF is non-inferior and equivalent to bimatoprost in its ability to reduce IOP-lowering with a safety profile similar to bimatoprost. PMID:23743437

7 CFR 905.149 - Procedure for permitting growers to ship tree run citrus fruit.

Science.gov (United States)

2010-01-01

... Fruit § 905.149 Procedure for permitting growers to ship tree run citrus fruit. (a) Tree run citrus fruit. Tree run citrus fruit as referenced in this section is defined in the Florida Department of... grower shall apply to ship tree run fruit using a Grower Tree Run Certificate Application, furnished by...

47 CFR 95.201 - (R/C Rule 1) What is the Radio Control (R/C) Radio Service?

Science.gov (United States)

2010-10-01

... 47 Telecommunication 5 2010-10-01 2010-10-01 false (R/C Rule 1) What is the Radio Control (R/C...) SAFETY AND SPECIAL RADIO SERVICES PERSONAL RADIO SERVICES Radio Control (R/C) Radio Service General Provisions § 95.201 (R/C Rule 1) What is the Radio Control (R/C) Radio Service? The R/C Service is a private...

The electrodeposition of 149Sm targets for (n,α) studies

International Nuclear Information System (INIS)

Ingelbrecht, C.; Ambeck-Madsen, J.; Teipel, K.; Robouch, P.; Arana, G.; Pomme, S.

1999-01-01

A method of electrodeposition from ethanol was developed for the production of 149 Sm targets of area 50x60 mm 2 to be used for (n,α) experiments. Targets of 60 μg cm -2 Sm were obtained with a Sm yield of 50% and a Sm mass fraction of 35% after calcination of the layers at 450 deg. C. Target substrates were 20 μm aluminium foils mounted on brass frames. A water cooling jig was constructed to protect the glue used for mounting during the calcination process. The layers were characterized by inductively coupled plasma source mass spectrometry (ICP-MS) and by neutron activation analysis (NAA)

Speaking up behaviors and safety climate in an Austrian university hospital.

Science.gov (United States)

Schwappach, David; Sendlhofer, Gerald; Häsler, Lynn; Gombotz, Veronika; Leitgeb, Karina; Hoffmann, Magdalena; Jantscher, Lydia; Brunner, Gernot

2018-04-26

To analyze speaking up behavior and safety climate with a validated questionnaire for the first time in an Austrian university hospital. Survey amongst healthcare workers (HCW). Data were analyzed using descriptive statistics, Cronbach's alpha was calculated as a measure of internal consistencies of scales. Analysis of variance and t-tests were used. The survey was conducted in 2017. About 2.149 HCW from three departments were asked to participate. To measure speaking up behavior and safety climate. To explore psychological safety, encouraging environment and resignation towards speaking up. About 859 evaluable questionnaires were returned (response rate: 40%). More than 50% of responders perceived specific concerns about patient safety within the last 4 weeks and observed a potential error or noticed rule violations. For the different items, between 16% and 42% of HCW reported that they remained silent though concerns for safety. In contrast, between 96% and 98% answered that they did speak up in certain situations. The psychological safety for speaking up was lower for HCW with a managerial function (P speak up (P speaking up behaviors for the first time in an Austrian university hospital. Only moderately frequent concerns were in conflict with frequent speaking up behaviors. These results clearly show that a paradigm shift is needed to increase speaking up culture.

Coordinated Control Design for the HTR-PM Plant: From Theoretic Analysis to Simulation Verification

International Nuclear Information System (INIS)

Dong Zhe; Huang Xiaojin

2014-01-01

HTR-PM plant is a two-modular nuclear power plant based on pebble bed modular high temperature gas-cooled reactor (MHTGR), and adopts operation scheme of two nuclear steam supplying systems (NSSSs) driving one turbine. Here, an NSSS is composed of an MHTGR, a once-through steam generator (OTSG) and some connecting pipes. Due to the coupling effect induced by two NSSSs driving one common turbine and that between the MHTGR and OTSG given by common helium flow, it is necessary to design a coordinated control for the safe, stable and efficient operation of the HTR-PM plant. In this paper, the design of the feedback loops and control algorithms of the coordinated plant control law is firstly given. Then, the hardware-in-loop (HIL) system for verifying the feasibility and performance of this control strategy is introduced. Finally, some HIL simulation results are given, which preliminarily show that this coordinated control law can be implemented practically. (author)

Magnetization of R.sub.2./sub.Fe.sub.13.6./sub.Si.sub.3.4./sub. (R = U, Lu) single crystals under pressure

Czech Academy of Sciences Publication Activity Database

Andreev, Alexander V.; Kolomiets, A. V.; Goto, T.

2005-01-01

Roč. 387, - (2005), s. 60-64 ISSN 0925-8388 R&D Projects: GA ČR(CZ) GA202/03/0550; GA MŠk(CZ) ME 680 Keywords : uranium intermetallics * R 2 T 17 * magnetic anisotropy * pressure effects Subject RIV: BM - Solid Matter Physics ; Magnetism Impact factor: 1.370, year: 2005

Test Results of the LARP Nb$_3$Sn Quadrupole HQ03a

CERN Document Server

DiMarco, J; Anerella, M; Bajas, H; Chlachidze, G; Borgnolutti, F; Bossert, R; Cheng, D W; Dietderich, D; Felice, H; Pan, H; Ferracin, P; Ghosh, A; Godeke, A; Hafalia, A R; Marchevsky, M; Orris, D; Ravaioli, E; Sabbi, G; Salmi, T; Schmalzle, J; Stoynev, S; Strauss, T; Sylvester, C; Tartaglia, M; Todesco, E; Wanderer, P; Wang, X R; Yu, M

2016-01-01

The US LHC Accelerator Research Program (LARP) has been developing $Nb_3Sn$ quadrupoles of progressively increasing performance for the high luminosity upgrade of the Large Hadron Collider. The 120 mm aperture High-field Quadrupole (HQ) models are the last step in the R&D; phase supporting the development of the new IR Quadrupoles (MQXF). Three series of HQ coils were fabricated and assembled in a shell-based support structure, progressively optimizing the design and fabrication process. The final set of coils consistently applied the optimized design solutions, and was assembled in the HQ03a model. This paper reports a summary of the HQ03a test results, including training, mechanical performance, field quality and quench studies.

Survey of the Patient Safety Culture in the Clinics and Hospitals of Chabahar, Iran

Directory of Open Access Journals (Sweden)

Fereydoon Laal

2017-07-01

Results:In total, 255.85 subjects were enrolled in the study and equally divided into three groups (33.3%. The minimum and maximum work experience was one and 27 years, respectively. Among the participants, 116 cases (45.49% were female, and 139 cases (54.50% were male. Mean total score of the patient safety culture was 149.87±25.20. The lowest and highest scores were observed in the dimensions of ‘non-punitive response to errors’ (3.23±9.11 and ‘teamwork within units’ (3.86±15.41, respectively. The results indicated a significant difference between the three study groups in terms of the patient safety culture (P

Safety design

International Nuclear Information System (INIS)

Kunitomi, Kazuhiko; Shiozawa, Shusaku

2004-01-01

JAERI established the safety design philosophy of the HTTR based on that of current reactors such as LWR in Japan, considering inherent safety features of the HTTR. The strategy of defense in depth was implemented so that the safety engineering functions such as control of reactivity, removal of residual heat and confinement of fission products shall be well performed to ensure safety. However, unlike the LWR, the inherent design features of the high-temperature gas-cooled reactor (HTGR) enables the HTTR meet stringent regulatory criteria without much dependence on active safety systems. On the other hand, the safety in an accident typical to the HTGR such as the depressurization accident initiated by a primary pipe rupture shall be ensured. The safety design philosophy of the HTTR considers these unique features appropriately and is expected to be the basis for future Japanese HTGRs. This paper describes the safety design philosophy and safety evaluation procedure of the HTTR especially focusing on unique considerations to the HTTR. Also, experiences obtained from an HTTR safety review and R and D needs for establishing the safety philosophy for the future HTGRs are reported

MIGRATION '03: 9th International Conference on Chemistry and Migration Behavior of Actinides and Fission Products in the Geosphere

International Nuclear Information System (INIS)

Kim, Geon Young; Hahn, Pil Soo; Kang, Moon Ja; Baik, Min Hoon; Kim, Seung

2003-12-01

The objectives of this report are overview of the chemistry and migration behavior of actinide for the HLW disposal safety assessment and to summarise the present status of actinide science and future developments. Actinides in HLW are very toxic and long-life time radionuclides. Therefore, the understanding of their characteristics and reaction behaviors in the deep subsurface environment is necessary for improving the reliability of HLW disposal safety assessment. This report presents an overview of the recent developments in the fundamental chemistry of actinides and fission products in natural aquifer systems, their interactions and migration in the geosphere, and the processes involved in modeling their geochemical behavior for the high level radioactive waste management. In addition, the thesis presented in MIGRATION '03 conference were described briefly. Actinide science in relation to the HLW disposal management can be classified into three main subjects; aquatic chemistry of actinides and fission products, migration behavior of radionuclides and geochemical and transport modeling. The radionuclides leached from waste forms are intruded into human environment along the groundwater flowing in the fracture around the waster disposal facility. To analyze and predict such radionuclide migration phenomena, the data that were obtained from well defined condition are required. Data obtained from studies on the chemical behaviors of actinide elements and fission products in the groundwater are essential in the safety assessment of HLW management. This report is intended to suggest the direction of R and D in actinide chemistry for the national program of HLW management in future

Prioritization of R and D programs on probabilistic reactor safety

International Nuclear Information System (INIS)

Husseiny, A.A.

1982-01-01

An interactive computer code based on the multiattribute utility theory has been developed with graphic capabilities to use in selection of probabilistic reactor safety RandD programs. Utility values and proper graphic representation are made through lottery games on the computer terminal. The code is applied to prioritize a set of RandD programs on LWR safety based on attributes including regulatory issues, institutional issues and operation problems. The methodology is described here in detail with its applications. Some of the input includes statistical distributions and subjective judgments on institutional issues. The flexibility of the approach provides a tool for decision makers whether on individual or group level to assess LWR safety priorities and continuously update their strategies

SGHWR fuel performance, safety and reliability

International Nuclear Information System (INIS)

Pickman, D.O.; Inglis, G.H.

1977-01-01

The design principles involved in fuel pins and elements need to take account of the sometimes conflicting requirements of performance, safety and reliability. The principal factors involved in this optimisation are discussed and it is shown from fuel irradiation experience in the Winfrith S.G.H.W.R. that the necessary bias toward safety has not resulted in a reliability level lower than that shown by other successful water reactor designs. Reliability has important economic implications and has to be paid for. By a detailed evaluation of S.G.H.W.R. fuel defects it is shown that very few defects can be shown to be related to design, rating or burn-up. This demonstrates that economic aspects have not over-ridden necessary criteria that must be met to achieve the desirable reliability level. It is possible that large-scale experience with S.G.H.W.R. fuel may eventually demonstrate that the balance is too much in favour of reliability and consideration may be given to whether design changes favouring economy could be achieved without compromising safety. The safety criteria applied to S.G.H.W.R. fuel are designed to avoid any possibility of a temperature runaway in any credible accident situation. The philosophy and supporting experimental work programme are outlined and the fuel design features which particularly contribute to maximising safety margins are outlined. Reference is made to new 60 pin fuel element to be used in the commercial S.G.H.W.R.'s and how it compares in design and performance aspects with the 36 pin element that has been used to date in the Winfrith S.G.H.W.R

Graphite development for gas-cooled reactors in the USA

International Nuclear Information System (INIS)

Burchell, T.D.

1991-01-01

This document discusses Modular High-Temperature Gas-Cooled Reactor (MHTGR) graphite activities in the USA which currently include the following research and development tasks: coke examination; effects of irradiation; variability of physical properties (mechanical, thermal-physical, and fracture); fatigue behavior, oxidation behavior; NDE techniques; structural design criteria; and carbon-carbon composite control rod clad materials. These tasks support nuclear grade graphite manufacturing technology including nondestructive examination of billets and components. Moreover, data shall be furnished to support design and licensing of graphite components for the MHTGR

Summary of tank information relating salt well pumping to flammable gas safety issues

International Nuclear Information System (INIS)

Caley, S.M.; Mahoney, L.A.; Gauglitz, P.A.

1996-09-01

The Hanford Site has 149 single-shell tanks (SSTs) containing radioactive wastes that are complex mixes of radioactive and chemical products. Active use of these SSTs was phased out completely by November 1980, and the first step toward final disposal of the waste in the SSTs is interim stabilization, which involves removing essentially all of the drainable liquid from the tank. Stabilization can be achieved administratively, by jet pumping to remove drainable interstitial liquid, or by supernatant pumping. To date, 116 tanks have been declared interim stabilized; 44 SSTs have had drainable liquid removed by salt well jet pumping. Of the 149 SSTs, 19 are on the Flammable Gas Watch List (FGWL) because the waste in these tanks is known or suspected, in all but one case, to generate and retain mixtures of flammable gases, including; hydrogen, nitrous oxide, and ammonia. Salt well pumping to remove the drainable interstitial liquid from these SSTs is expected to cause the release of much of the retained gas, posing a number of safety concerns. The scope of this work is to collect and summarize information, primarily tank data and observations, that relate salt well pumping to flammable gas safety issues. While the waste within FGWL SSTs is suspected offering flammable gases, the effect of salt well pumping on the waste behavior is not well understood. This study is being conducted for the Westinghouse Hanford Company as part of the Flammable Gas Project at the Pacific Northwest National Laboratory (PNNL). Understanding the historical tank behavior during and following salt well pumping will help to resolve the associated safety issues

Pharmacokinetics and metabolism of (R,R)-methoxyfenoterol in rat.

Science.gov (United States)

Siluk, D; Mager, D E; Kim, H S; Wang, Y; Furimsky, A M; Ta, A; Iyer, L V; Green, C E; Wainer, I W

2010-03-01

(R,R)-fenoterol (Fen), a beta(2)-adrenoceptor agonist, is under clinical investigation in the treatment of congestive heart disease. The pharmacokinetics and metabolism of the 4-methoxyphenyl derivative of (R,R)-Fen, (R,R)-MFen, have been determined following intravenous and oral administration to the rat and compared with corresponding results obtained with (R,R)-Fen. Results from the study suggest that (R,R)-MFen can offer pharmacokinetic and metabolic advantages in comparison to an earlier (R,R)-Fen. The oral administration revealed that the net exposure of (R,R)-MFen was about three-fold higher than that of (R,R)-Fen (7.2 versus 2.3 min x nmol ml(-1)), while intravenous administration proved that the clearance was significantly reduced, 48 versus 146 ml min(-1) kg(-1), the T(1/2) was significantly longer, 152.9 versus 108.9 min, and the area under the curve (AUC) was significantly increased, 300 versus 119 min x nmol ml(-1). (R,R)-MFen was primarily cleared by glucuronidation associated with significant presystemic glucuronidation of the compound. After intravenous and oral administration of (R,R)-MFen, (R,R)-Fen and (R,R)-Fen-G were detected in the urine samples indicating that (R,R)-MFen was O-demethylated and subsequently conjugated to (R,R)-Fen-G. The total (R,R)-Fen and (R,R)-Fen-G as a percentage of the dose after intravenous administration was 3.6%, while after oral administration was 0.3%, indicating that only a small fraction of the drug escaped presystemic glucuronidation and was available for O-demethylation. The glucuronidation pattern was confirmed by the results from in vitro studies where incubation of (R,R)-MFen with rat hepatocytes produced (R,R)-MFen-G, (R,R)-Fen and (R,R)-Fen-G, while incubation with rat intestinal microsomes only resulted in the formation of (R,R)-MFen-G.

An observer-blind, randomized, multi-center trial assessing long-term safety and immunogenicity of AS03-adjuvanted or unadjuvanted H1N1/2009 influenza vaccines in children 10-17 years of age.

Science.gov (United States)

Poder, Airi; Simurka, Pavol; Li, Ping; Roy-Ghanta, Sumita; Vaughn, David

2014-02-19

Vaccination is an effective strategy to prevent influenza. This observer-blind, randomized study in children 10-17 years of age assessed whether the hemagglutination inhibition (HI) antibody responses elicited by H1N1/2009 vaccines adjuvanted with AS03 (an adjuvant system containing α-tocopherol and squalene in an oil-in-water emulsion) or without adjuvant, met the European regulatory immunogenicity criteria at Days 21 and 182. Three hundred and ten healthy children were randomized (3:3:3:5) to receive one dose of 3.75 μg hemagglutinin (HA) AS03A-adjuvanted vaccine, one or two doses of 1.9 μg HA AS03B-adjuvanted vaccine, or one dose of 15 μg HA pandemic vaccine. All children received a booster dose of the allocated vaccine at Day 182. Serum samples were tested for HI antibody response at Days 21, 42, 182 and 189. All vaccination regimens elicited HI antibody responses that met the European regulatory criteria at Days 21 and 42. HI antibody responses fulfilling European regulatory criteria were still observed six months after the first vaccine dose in all study vaccines groups. Two doses of 1.9 μg HA AS03B-adjuvanted vaccine elicited the strongest HI antibody response throughout the study. The non-adjuvanted 15 μg HA vaccine elicited a lower HI antibody response than the AS03-adjuvanted vaccines. At Day 189, the European regulatory criteria were met for all vaccines with baseline HI antibody titers as reference. An anamnestic response for all vaccines was suggested at Day 189, based on the rapid increase in HI antibody geometric mean titers (1.5-2.5-fold increase). Injection site reactogenicity was higher following the AS03-adjuvanted vaccines compared with the non-adjuvanted vaccine. No safety concerns were identified for any study vaccine. All study vaccines elicited HI antibody responses that persisted at purported protective levels through six months after vaccination and fulfilled the European regulatory criteria. Copyright © 2013 The Authors. Published

40 CFR 192.03 - Monitoring.

Science.gov (United States)

2010-07-01

... 40 Protection of Environment 24 2010-07-01 2010-07-01 false Monitoring. 192.03 Section 192.03... of Residual Radioactive Materials from Inactive Uranium Processing Sites § 192.03 Monitoring. A groundwater monitoring plan shall be implemented, to be carried out over a period of time commencing upon...

NCBI nr-aa BLAST: CBRC-AGAM-03-0089 [SEVENS

Lifescience Database Archive (English)

Full Text Available CBRC-AGAM-03-0089 ref|NP_610301.1| CG1358-PA, isoform A [Drosophila melanogaster] r...ef|NP_724584.1| CG1358-PB, isoform B [Drosophila melanogaster] ref|NP_724585.1| CG1358-PC, isoform C [Drosophila mela...nogaster] gb|AAF59224.1| CG1358-PA, isoform A [Drosophila melanogaster] gb|AAL39287.1| GH15861p [Drosophila mela...nogaster] gb|AAM71101.1| CG1358-PB, isoform B [Drosophila melanogast...er] gb|AAM71102.1| CG1358-PC, isoform C [Drosophila melanogaster] NP_610301.1 5e-79 44% ...

Feeding of the superdeformed yrast band in sup 149 Gd

Energy Technology Data Exchange (ETDEWEB)

Haas, B.; Vivien, J.P.; Beck, F.A.; Benet, P.; Byrski, T.; Curien, D.; Duchene, G.; Gehringer, C.; Merdinger, J.C.; Romain, P. (Strasbourg-1 Univ., 67 (France). Centre de Recherches Nucleaires); Basu, S.K. (Strasbourg-1 Univ., 67 (France). Centre de Recherches Nucleaires Bhabha Atomic Research Centre, Calcutta (India). Variable Energy Cyclotron Centre); Kluge, H. (Strasbourg-1 Univ., 67 (France). Centre de Recherches Nucleaires Hahn-Meitner-Institut Berlin GmbH (Germany, F.R.)); Santos, D. (Strasbourg-1 Univ., 67 (France). Centre de Recherches Nucleaires Consejo Nacional de Investigaciones Cientificas y Tecnicas, Buenos Aires (Argentina)); Flibotte, S. (Hahn-Meitner-Institut Berlin GmbH (Germany, F.R.)); Gascon, J.; Taras, P. (Montreal Univ., Quebec (Canada). Lab. de Physique Nucleaire); Bozek, E.; Zuber, K. (Institute of Nuclear Physics, Krakow (Poland))

1990-08-02

The feeding pattern of the superdeformed yrast band in {sup 149}Gd has been found to remain essentially the same, using the {sup 124}Sn+{sup 30}Si reaction at beam energies of 150, 155 and 160 MeV leading to different input angular momenta and excitation energies in the compound nuclear system. This similarity as well as the relative yields of the superdeformed states as a function of beam energy may be understood in terms of the nuclear level density dependence on deformation and the onset of fission. In addition, it has been shown that, at all three beam energies, the selection of high-energy gamma rays does not enhance the yield of the superdeformed yrast states. (orig.).

Magnetically tunable alternating current electrical properties of x La0.7Sr0.3MnO3–(1 − x) ErMnO3 (x = 0.1, 0.3, and 0.5) multiferroic nanocomposite

International Nuclear Information System (INIS)

Debnath, Rajesh; Dey, P.; Singh, Swati; Roy, J. N.; Mandal, S. K.; Nath, T. K.

2015-01-01

Detailed magnetically tunable ac electrical properties of x La 0.7 Sr 0.3 MnO 3 (LSMO)–(1 − x) ErMnO 3 (EMO) (x = 0.1, 0.3, and 0.5) multiferroic nanocomposites have been studied at 300 K in presence of varying magnetic field (H appl ), applied both in parallel and perpendicular configuration with respect to the measuring electric field. AC electrical properties have exhibited significant variation with H appl for all composites, whereas for parallel configuration of H appl such effect is very feeble for x = 0.3 composite. We have attributed this anisotropic behavior to the demagnetization effect in the sample. In contrast, for x = 0.1 and 0.5 composites, no such anisotropy effect is experimentally evidenced. Impedance and real part of impedance have been found to decrease with H appl at low frequency (f) region. We attribute this observation to the depinning of the magnetic domain walls from the grain boundaries pinning centers and thereby enhancing the spin dependent transport in the composite. For x = 0.3 composite, Nyquist plots have been fitted considering dominant contributions of LSMO and EMO grain boundaries and the interface region between them. However, for x = 0.1 composite, it corresponds to EMO grain boundaries and grain boundary interface region. The relaxation frequency (f R ) is observed to shift at higher/lower f region in perpendicular/parallel configuration of H appl for x = 0.3 composite. This opposite variation of f R s with H appl for perpendicular and parallel configurations has been attributed to two competing factors of H appl induced enhancement of inductive part and H appl enhanced spin dependent transport causing fast relaxation processes in the sample. For x = 0.1 composite, in both configurations of H appl , f R s is shifting towards high f region, which has been discussed in terms of dominant role of spin dependent transport

33 CFR 64.03 - Scope.

Science.gov (United States)

2010-07-01

... 33 Navigation and Navigable Waters 1 2010-07-01 2010-07-01 false Scope. 64.03 Section 64.03... STRUCTURES, SUNKEN VESSELS AND OTHER OBSTRUCTIONS General § 64.03 Scope. (a) Except as provided in paragraph... jurisdiction of the United States and, on the high seas, structures owned or operated by persons subject to the...

Maturing safety in the UK

International Nuclear Information System (INIS)

Debenham, A.; Kovan, D.

1994-01-01

AEA Technology provides UK nuclear industry with technical services and R+D support, concentrating on plant performance, safety and environmental issues. Today, safety has a new set of priorities, reflected by a more demanding regulatory regime which takes account of concerns such as human factors, severe accidents, risks during plant outages, the need for improving safety culture, etc

MIGRATION '03: 9th International Conference on Chemistry and Migration Behavior of Actinides and Fission Products in the Geosphere

Energy Technology Data Exchange (ETDEWEB)

Kim, Geon Young; Hahn, Pil Soo; Kang, Moon Ja; Baik, Min Hoon; Kim, Seung

2003-12-15

The objectives of this report are overview of the chemistry and migration behavior of actinide for the HLW disposal safety assessment and to summarise the present status of actinide science and future developments. Actinides in HLW are very toxic and long-life time radionuclides. Therefore, the understanding of their characteristics and reaction behaviors in the deep subsurface environment is necessary for improving the reliability of HLW disposal safety assessment. This report presents an overview of the recent developments in the fundamental chemistry of actinides and fission products in natural aquifer systems, their interactions and migration in the geosphere, and the processes involved in modeling their geochemical behavior for the high level radioactive waste management. In addition, the thesis presented in MIGRATION '03 conference were described briefly. Actinide science in relation to the HLW disposal management can be classified into three main subjects; aquatic chemistry of actinides and fission products, migration behavior of radionuclides and geochemical and transport modeling. The radionuclides leached from waste forms are intruded into human environment along the groundwater flowing in the fracture around the waster disposal facility. To analyze and predict such radionuclide migration phenomena, the data that were obtained from well defined condition are required. Data obtained from studies on the chemical behaviors of actinide elements and fission products in the groundwater are essential in the safety assessment of HLW management. This report is intended to suggest the direction of R and D in actinide chemistry for the national program of HLW management in future.

Safety and reliability criteria

International Nuclear Information System (INIS)

O'Neil, R.

1978-01-01

Nuclear power plants and, in particular, reactor pressure boundary components have unique reliability requirements, in that usually no significant redundancy is possible, and a single failure can give rise to possible widespread core damage and fission product release. Reliability may be required for availability or safety reasons, but in the case of the pressure boundary and certain other systems safety may dominate. Possible Safety and Reliability (S and R) criteria are proposed which would produce acceptable reactor design. Without some S and R requirement the designer has no way of knowing how far he must go in analysing his system or component, or whether his proposed solution is likely to gain acceptance. The paper shows how reliability targets for given components and systems can be individually considered against the derived S and R criteria at the design and construction stage. Since in the case of nuclear pressure boundary components there is often very little direct experience on which to base reliability studies, relevant non-nuclear experience is examined. (author)

Molecular footprints reveal the impact of the protective HLA-A*03 allele in hepatitis C virus infection.

LENUS (Irish Health Repository)

Fitzmaurice, Karen

2012-02-01

BACKGROUND AND AIMS: CD8 T cells are central to the control of hepatitis C virus (HCV) although the key features of a successful CD8 T cell response remain to be defined. In a cohort of Irish women infected by a single source, a strong association between viral clearance and the human lecucocyte (HLA)-A*03 allele has been described, and the aim of this study was to define the protective nature of the associated CD8 T cell response. METHODS: A sequence-led approach was used to identify HLA-A*03-restricted epitopes. We examine the CD8 T cell response associated with this gene and address the likely mechanism underpinning this protective effect in this special cohort, using viral sequencing, T cell assays and analysis of fitness of viral mutants. RESULTS: A strong \\'HLA footprint\\' in a novel NS3 epitope (TVYHGAGTK) was observed. A lysine (K) to arginine (R) substitution at position 9 (K1088R) was seen in a significant number of A*03-positive patients (9\\/12) compared with the control group (1\\/33, p=0.0003). Threonine (T) was also substituted with alanine (A) at position 8 (T1087A) more frequently in A*03-positive patients (6\\/12) compared with controls (2\\/33, p=0.01), and the double substitution of TK to AR was also observed predominantly in HLA-A*03-positive patients (p=0.004). Epitope-specific CD8 T cell responses were observed in 60% of patients three decades after exposure and the mutants selected in vivo impacted on recognition in vitro. Using HCV replicons matched to the viral sequences, viral fitness was found to be markedly reduced by the K1088R substitution but restored by the second substitution T1087A. CONCLUSIONS: It is proposed that at least part of the protective effect of HLA-A*03 results from targeting of this key epitope in a functional site: the requirement for two mutations to balance fitness and escape provides an initial host advantage. This study highlights the potential protective impact of common HLA-A alleles against persistent

Safety Training: places available in April 2014

CERN Multimedia

Safety Training team, HSE Unit

2014-01-01

There are places available in the forthcoming Safety courses. For updates and registrations, please refer to the Safety Training Catalogue (see here).   April 2014 (alphabetical order) ATEX Habilitation - Level 2 03-APR-14 to 04-APR-14, 9.00 – 17.30, in French Cryogenic Safety - Level 1 10-APR-14, 10.00 – 12.00, in English Electrical Palett Truck – Driving 15-APR-14, 8.30 – 12.30, in French (hand-outs in English for non-French-speaking participants) Fire Extinguisher 09-APR-14, 10.30 – 12.00, in French 16-APR-14, 10.30 – 12.00, in English 23-APR-14, 10.30 – 12.00, in English First Aider - Level 1 – Initial 03-APR-14, 8.30 – 17.30, in French 10-APR-14, 8.30 – 17.30, in English 16-APR-14, 8.30 – 17.30, in English 24-APR-14, 8.30 – 17.30, in English First Aider - Level 1 – Refresher 17-APR-14, 8.30 – 12.30, in English 17-APR-14, 13.30 – 17.30, in...

Using the Job Demands-Resources model to investigate risk perception, safety climate and job satisfaction in safety critical organizations.

Science.gov (United States)

Nielsen, Morten Birkeland; Mearns, Kathryn; Matthiesen, Stig Berge; Eid, Jarle

2011-10-01

Using the Job Demands-Resources model (JD-R) as a theoretical framework, this study investigated the relationship between risk perception as a job demand and psychological safety climate as a job resource with regard to job satisfaction in safety critical organizations. In line with the JD-R model, it was hypothesized that high levels of risk perception is related to low job satisfaction and that a positive perception of safety climate is related to high job satisfaction. In addition, it was hypothesized that safety climate moderates the relationship between risk perception and job satisfaction. Using a sample of Norwegian offshore workers (N = 986), all three hypotheses were supported. In summary, workers who perceived high levels of risk reported lower levels of job satisfaction, whereas this effect diminished when workers perceived their safety climate as positive. Follow-up analyses revealed that this interaction was dependent on the type of risks in question. The results of this study supports the JD-R model, and provides further evidence for relationships between safety-related concepts and work-related outcomes indicating that organizations should not only develop and implement sound safety procedures to reduce the effects of risks and hazards on workers, but can also enhance other areas of organizational life through a focus on safety. © 2011 The Authors. Scandinavian Journal of Psychology © 2011 The Scandinavian Psychological Associations.

42 CFR 413.149 - Depreciation: Allowance for depreciation on assets financed with Federal or public funds.

Science.gov (United States)

2010-10-01

... 42 Public Health 2 2010-10-01 2010-10-01 false Depreciation: Allowance for depreciation on assets... SKILLED NURSING FACILITIES Capital-Related Costs § 413.149 Depreciation: Allowance for depreciation on assets financed with Federal or public funds. (a) Principle. Depreciation is allowed on assets financed...

Jefferson Lab IEC 61508/61511 Safety PLC Based Safety System

International Nuclear Information System (INIS)

Mahoney, Kelly; Robertson, Henry

2009-01-01

This paper describes the design of the new 12 GeV Upgrade Personnel Safety System (PSS) at the Thomas Jefferson National Accelerator Facility (TJNAF). The new PSS design is based on the implementation of systems designed to meet international standards IEC61508 and IEC 61511 for programmable safety systems. In order to meet the IEC standards, TJNAF engineers evaluated several SIL 3 Safety PLCs before deciding on an optimal architecture. In addition to hardware considerations, software quality standards and practices must also be considered. Finally, we will discuss R and D that may lead to both high safety reliability and high machine availability that may be applicable to future accelerators such as the ILC.

Bimatoprost 0.03%/timolol 0.5% preservative-free ophthalmic solution versus bimatoprost 0.03%/timolol 0.5% ophthalmic solution (Ganfort) for glaucoma or ocular hypertension: a 12-week randomised controlled trial

Science.gov (United States)

Goldberg, Ivan; Gil Pina, Rafael; Lanzagorta-Aresti, Aitor; Schiffman, Rhett M; Liu, Charlie; Bejanian, Marina

2014-01-01

Aim To compare the efficacy and safety of single-dose bimatoprost 0.03%/timolol 0.5% preservative-free (PF) ophthalmic solution with bimatoprost 0.03%/timolol 0.5% ophthalmic solution in patients with open-angle glaucoma or ocular hypertension. Methods In this multicentre, randomised, parallel-group study, patients were randomised to bimatoprost/timolol PF or bimatoprost/timolol once daily in the morning for 12 weeks. Primary efficacy endpoints, reflecting differing regional regulatory requirements, included change from baseline in worse eye intraocular pressure (IOP) in the per-protocol population at week 12, and the average eye IOP at weeks 2, 6 and 12 in the intent-to-treat population. Results 561 patients were randomised (278 to bimatoprost/timolol PF; 283 to bimatoprost/timolol); 96.3% completed the study. Both treatment groups showed statistically and clinically significant mean decreases from baseline in worse eye IOP and in average eye IOP at all follow-up time points (p<0.001). Bimatoprost/timolol PF met all pre-established criteria for non-inferiority and equivalence to bimatoprost/timolol. Ocular adverse events were similar between treatment groups, with conjunctival hyperaemia being the most frequent. Most were mild or moderate in severity. Conclusions Bimatoprost/timolol PF demonstrated non-inferiority and equivalence in IOP lowering compared with bimatoprost/timolol, with no significant differences in safety and tolerability. Trial registration number NCT01177098. PMID:24667994

Magnetic ordering in Sc{sub 2}CoSi{sub 2}-type R{sub 2}FeSi{sub 2} (R=Gd, Tb) and R{sub 2}CoSi{sub 2} (R=Y, Gd–Er) compounds

Energy Technology Data Exchange (ETDEWEB)

Morozkin, A.V., E-mail: morozkin@tech.chem.msu.ru [Department of Chemistry, Moscow State University, Leninskie Gory, House 1, Building 3, GSP-2, Moscow 119992 (Russian Federation); Knotko, A.V. [Department of Chemistry, Moscow State University, Leninskie Gory, House 1, Building 3, GSP-2, Moscow 119992 (Russian Federation); Yapaskurt, V.O. [Department of Petrology, Geological Faculty, Moscow State University, Leninskie Gory, Moscow 119992 (Russian Federation); Pani, M. [Department of Chemistry, University of Genova, Via Dodecaneso 31, 16146 Genova (Italy); Institute SPIN-CNR, C. Perrone 24, 16152 Genova (Italy); Nirmala, R. [Indian Institute of Technology Madras, Chennai 600036 (India); Quezado, S.; Malik, S.K. [Departamento de Física Teórica e Experimental, Universidade Federal do Rio Grande do Norte, Natal 59082-970 (Brazil)

2016-09-01

Magnetic and magnetocaloric properties of Sc{sub 2}CoSi{sub 2}-type R{sub 2}TSi{sub 2} (R=Gd–Er, T=Fe, Co) compounds have been studied using magnetization data. These indicate the presence of mixed ferromagnetic and antiferromagnetic interactions in these compounds. One observes a ferromagnetic transition followed by an antiferromagnetic order and a further possible spin-reorientation transition at low temperatures. Compared to Gd{sub 2}{Fe, Co}Si{sub 2}, the Tb{sub 2}FeSi{sub 2} and {Tb–Er}{sub 2}CoSi{sub 2} compounds exhibit remarkable hysteresis (for e.g. Tb{sub 2}FeSi{sub 2} shows residual magnetization M{sub res}/Tb=2.45 μ{sub B}, coercive field H{sub coer}=14.9 kOe, and critical field H{sub crit}~5 kOe at 5 K) possibly due to the magnetocrystalline anisotropy of the rare earth. The R{sub 2}{Fe, Co}Si{sub 2} show relatively small magnetocaloric effect (i.e. isothermal magnetic entropy change, ΔS{sub m}) around the magnetic transition temperature: the maximal value of MCE is demonstrated by Ho{sub 2}CoSi{sub 2} (ΔS{sub m}=−8.1 J/kg K at 72 K and ΔS{sub m}=−9.4 J/kg K at 23 K in field change of 50 kOe) and Er{sub 2}CoSi{sub 2} (ΔS{sub m}=−13.6 J/kg K at 32 K and ΔS{sub m}=−8.4 J/kg K at 12 K in field change of 50 kOe). - Highlights: • {Gd–Er}{sub 2}{Fe, Co}Si{sub 2} show high-temperature ferromagnetic-type transitions. • {Gd–Er}{sub 2}{Fe, Co}Si{sub 2} show low-temperature spin-reorientation transitions. • Tb{sub 2}FeSi{sub 2} and {Tb–Er}{sub 2}CoSi{sub 2} compounds exhibit low-temperature hysteresis. • Tb{sub 2}FeSi{sub 2} shows M{sub res}/Tb=2.45 μ{sub B}, H{sub coer}=14.9 kOe and H{sub crit} ~5 kOe at 5 K • Considerable magnetocaloric effect is exhibited by Ho{sub 2}CoSi{sub 2} and Er{sub 2}CoSi{sub 2}.

National nuclear power planning of China and advanced reactor

International Nuclear Information System (INIS)

Qian Jihui

1990-01-01

The necessity of investigation on the trends of advanced reactor technology all over the world is elabrated while China is going to set up its long-term national nuclear power programme. In author's opinion, thermal reactor power plants will have a quite long period development in the next century and a new trend of second generation NPPs might emerge in the beginning of next century. These new generation advanced reactors are characterized with new design concepts based on the inherent or passive safety features. Among them, most promising ones are those of AP-600 and MHTGR. Chinese experts are paying special attention to and closely following these two directions

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

Energy Technology Data Exchange (ETDEWEB)

1985-07-01

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

Thermal analysis and safety information for metal nanopowders by DSC

Energy Technology Data Exchange (ETDEWEB)

Tseng, J.M.; Huang, S.T. [Institute of Safety and Disaster Prevention Technology, Central Taiwan University of Science and Technology, 666, Buzih Road, Beitun District, Taichung 40601, Taiwan, ROC (China); Duh, Y.S.; Hsieh, T.Y.; Sun, Y.Y. [Department of Safety Health and Environmental Engineering, National United University, Miaoli, Taiwan, ROC (China); Lin, J.Z. [Institute of Safety and Disaster Prevention Technology, Central Taiwan University of Science and Technology, 666, Buzih Road, Beitun District, Taichung 40601, Taiwan, ROC (China); Wu, H.C. [Institute of Occupational Safety and Health, Council of Labor Affairs, Taipei, Taiwan, ROC (China); Kao, C.S., E-mail: jcsk@nuu.edu.tw [Department of Safety Health and Environmental Engineering, National United University, Miaoli, Taiwan, ROC (China)

2013-08-20

Highlights: • Metal nanopowders are common and frequently employed in industry. • Nano iron powder experimental results of T{sub o} were 140–150 °C. • Safety information can benefit relevant metal powders industries. - Abstract: Metal nanopowders are common and frequently employed in industry. Iron is mostly applied in high-performance magnetic materials and pollutants treatment for groundwater. Zinc is widely used in brass, bronze, die casting metal, alloys, rubber, and paints, etc. Nonetheless, some disasters induced by metal powders are due to the lack of related safety information. In this study, we applied differential scanning calorimetry (DSC) and used thermal analysis software to evaluate the related thermal safety information, such as exothermic onset temperature (T{sub o}), peak of temperature (T{sub p}), and heat of reaction (ΔH). The nano iron powder experimental results of T{sub o} were 140–150 °C, 148–158 °C, and 141–149 °C for 15 nm, 35 nm, and 65 nm, respectively. The ΔH was larger than 3900 J/g, 5000 J/g, and 3900 J/g for 15 nm, 35 nm, and 65 nm, respectively. Safety information can benefit the relevant metal powders industries for preventing accidents from occurring.

NCBI nr-aa BLAST: CBRC-GGAL-03-0036 [SEVENS

Lifescience Database Archive (English)

Full Text Available CBRC-GGAL-03-0036 ref|NP_000854.1| 5-hydroxytryptamine (serotonin) receptor 1B [Hom...o sapiens] ref|NP_001009102.1| 5-hydroxytryptamine (serotonin) receptor 1B [Pan troglodytes] sp|P28222|5HT1B...HT-1B) (Serotonin receptor 1B) (5-HT1B) gb|AAA58675.1| serotonin 1Db receptor gb|AAA36029.1| serotonin recep...tor gb|AAA36030.1| 5-hyroxytryptamine 1D receptor dbj|BAA01763.1| serotonin 1B receptor [Homo sapiens] gb|AAA60316.1| serotonin... 1D receptor emb|CAB51537.1| 5-hydroxytryptamine (serotonin) r

Production and separation of terbium-149 and terbium-152 for targeted cancer therapy

International Nuclear Information System (INIS)

Sarkar, S.; Leigh, J.

1997-01-01

This work reports the production and separation of useful quantities of 149 , 152 Tb from natural neodymium ( nat Nd) and 141 Pr for in vitro studies by bombarding the targets with 12 C projectiles. The physical, chemical and nuclear properties of radionuclides determine their efficacy in therapy and diagnosis. Tb-149 is an alpha-emitter with a half-life of 4.1h and 152 Tb is a positron emitter with a half-life of 17.5 h. Both of the isotopes have suitable gamma emission with good branching ratio suggesting their application to diagnosis apart from therapy. Alpha-emitters are effective in controlling cancer because of their short range and high Relative Biological Effectiveness. Long-lived positron emitters are effective in studying physiological function in positron emission tomography other than therapy. The aim of this work is to optimise the production and carrier free separation of terbium. Because of the presence of other stable isotopes in nat Nd, a number of other lanthanides are produced by secondary reactions during the production of terbium. In order to remove the secondary products, α-hydroxyisobutyric acid of pH 5 was used as eluent. satisfactory separation of terbium was achieved and demonstrate that useful quantities of 144,152 Tb can be produced by Tandem accelerator from 141 Pr and nat Nd targets

2018-03-20T18:48:07Z https://www.ajol.info/index.php/index/oai oai ...

African Journals Online (AJOL)

article/55754 2018-03-20T18:48:07Z ajrh:ART Poor parenting: Teenagers' views on adolescent pregnancies in Eastern Uganda Sekiwunga, R Whyte, SR Parental care, adolescent pregnancies, Uganda In Uganda teenage pregnancy is ...

Safety Training: places available in June 2013

CERN Multimedia

Isabelle CUSATO, HSE Unit

2013-01-01

There are places available in the forthcoming Safety courses. For updates and registrations, please refer to the Safety Training Catalogue.   June 2013 (alphabetical order) First Aiders - Basic Course 13-JUN-13, 8.15 – 17.30, in English First Aiders - Refresher Course 06-JUN-13, 8.15 – 12.30, in French 06-JUN-13, 13.15 – 17.30, in French Habilitation ATEX niveau 1 (Habilitation ATEX level 1) 28-JUN-13, 9.00 – 17.30, in French Habilitation électrique personnel électricien basse et haute tensions (habilitation électrique for electricians in low and high voltage) 10-JUN-13 to 13-JUN-13, 9.00 – 17.30, in English Habilitation électrique personnel non électricien (habilitation électrique for non electricians) 03-JUN-13 (afternoon) to 04-JUN-13 (full day), 9.00 – 17.30, in English Laser Experts 03-JUN-13 to 04-JUN-13, 9.00 – 17.30, in English Laser Users 28-JUN-...

Job demands, job resources and safety outcomes: The roles of emotional exhaustion and safety compliance.

Science.gov (United States)

Li, Feng; Jiang, Li; Yao, Xiang; Li, YongJuan

2013-03-01

The aim of this study was to assess the effectiveness of the job demands-resources (JD-R) model in explaining the relationship of job demands and resources with safety outcomes (i.e., workplace injuries and near-misses). We collected self-reported data from 670 crude oil production workers from three sub-companies of a major oilfield company in China. The results of a structural equation analysis indicated that job demands (psychological and physical demands) and job resources (decision latitude, supervisor support and coworker support) could affect emotional exhaustion and safety compliance, and thus influence the occurrence of injuries and near-misses. The implications of the present findings regarding both the JD-R model and occupational safety research were discussed. Copyright © 2012 Elsevier Ltd. All rights reserved.

Integrated plant safety assessment systematic evaluation program. R.E. Ginna Nuclear Power Plant, Rochester Gas and Electric Corporation, Docket No. 50-244

International Nuclear Information System (INIS)

1982-05-01

The Systematic Evaluation Program was initiated in February 1978 by the US Nuclear Regulatory Commission to review the designs of older operating nuclear reactor plants to reconfirm and document their safety. The review provides (1) an assessment of how these plants compare with current licensing safety requirements relating to selected issues, (2) a basis for deciding on how these differences should be resolved in an integrated plant review, and (3) a documented evaluation of plant safety. This report documents the review of the R.E. Ginna Nuclear Power Plant (located in Wayne County near Rochester, NY), one of ten plants reviewed under Phase II of this program, and indicates how 137 topics selected for review under Phase I of the program were addressed. Equipment and procedural changes have been identified as a result of the review. It is expected that this report will be one of the bases in considering the issuance of a full-term operating license in place of the existing provisional operating license

Waste Tank Safety Screening Module: An aspect of Hanford Site tank waste characterization

International Nuclear Information System (INIS)

Hill, J.G.; Wood, T.W.; Babad, H.; Redus, K.S.

1994-01-01

Forty-five (45) of the 149 Hanford single-shell tanks have been designated as Watch-List tanks for one or more high-priority safety issues, which include significant concentrations of organic materials, ferrocyanide salts, potential generation of flammable gases, high heat generation, criticality, and noxious vapor generation. While limited waste characterization data have been acquired on these wastes under the original Tri-Party Agreement, to date all of the tank-by-tank assessments involved in these safety issue designations have been based on historical data rather than waste on data. In response to guidance from the Defense Nuclear Facilities Safety Board (DNFSB finding 93-05) and related direction from the US Department of Energy (DOE), Westinghouse Hanford Company, assisted by Pacific Northwest Laboratory, designed a measurements-based screening program to screen all single-shell tanks for all of these issues. This program, designated the Tank Safety Screening Module (TSSM), consists of a regime of core, supernatant, and auger samples and associated analytical measurements intended to make first-order discriminations of the safety status on a tank-by-tank basis. The TSSM combines limited tank sampling and analysis with monitoring and tank history to provide an enhanced measurement-based categorization of the tanks relative to the safety issues. This program will be implemented beginning in fiscal year (FY) 1994 and supplemented by more detailed characterization studies designed to support safety issue resolution

Crime, perceived safety, and physical activity: A meta-analysis.

Science.gov (United States)

Rees-Punia, Erika; Hathaway, Elizabeth D; Gay, Jennifer L

2018-06-01

Perceived safety from crime and objectively-measured crime rates may be associated with physical inactivity. The purpose of this meta-analysis is to estimate the odds of accumulating high levels of physical activity (PA) when the perception of safety from crime is high and when objectively-measured crime is high. Peer-reviewed studies were identified through PubMed, Web of Science, ProQuest Criminal Justice, and ScienceDirect from earliest record through 2016. Included studies measured total PA, leisure-time PA, or walking in addition to perceived safety from crime or objective measures of crime. Mean odds ratios were aggregated with random effects models, and meta-regression was used to examine effects of potential moderators: country, age, and crime/PA measure. Sixteen cross-sectional studies yielded sixteen effects for perceived safety from crime and four effects for objective crime. Those reporting feeling safe from crime had a 27% greater odds of achieving higher levels of physical activity (OR=1.27 [1.08, 1.49]), and those living in areas with higher objectively-measured crime had a 28% reduced odds of achieving higher levels of physical activity (OR=0.72 [0.61, 0.83]). Effects of perceived safety were highly heterogeneous (I 2 =94.09%), but explored moderators were not statistically significant, likely because of the small sample size. Despite the limited number of effects suitable for aggregation, the mean association between perceived safety and PA was significant. As it seems likely that perceived lack of safety from crime constrains PA behaviors, future research exploring moderators of this association may help guide public health recommendations and interventions. Copyright © 2017 Elsevier Inc. All rights reserved.

R&D for Safety Codes and Standards: Materials and Components Compatibility

Energy Technology Data Exchange (ETDEWEB)

Somerday, Brian P. [Sandia National Lab. (SNL-CA), Livermore, CA (United States); LaFleur, Chris [Sandia National Lab. (SNL-CA), Livermore, CA (United States); Marchi, Chris San [Sandia National Lab. (SNL-CA), Livermore, CA (United States)

2015-08-01

This project addresses the following technical barriers from the Safety, Codes and Standards section of the 2012 Fuel Cell Technologies Office Multi-Year Research, Development and Demonstration Plan (section 3.8): (A) Safety data and information: limited access and availability (F) Enabling national and international markets requires consistent RCS (G) Insufficient technical data to revise standards.

The RETRAN-03 computer code

International Nuclear Information System (INIS)

Paulsen, M.P.; McFadden, J.H.; Peterson, C.E.; McClure, J.A.; Gose, G.C.; Jensen, P.J.

1991-01-01

The RETRAN-03 code development effort is designed to overcome the major theoretical and practical limitations associated with the RETRAN-02 computer code. The major objectives of the development program are to extend the range of analyses that can be performed with RETRAN, to make the code more dependable and faster running, and to have a more transportable code. The first two objectives are accomplished by developing new models and adding other models to the RETRAN-02 base code. The major model additions for RETRAN-03 are as follows: implicit solution methods for the steady-state and transient forms of the field equations; additional options for the velocity difference equation; a new steady-state initialization option for computer low-power steam generator initial conditions; models for nonequilibrium thermodynamic conditions; and several special-purpose models. The source code and the environmental library for RETRAN-03 are written in standard FORTRAN 77, which allows the last objective to be fulfilled. Some models in RETRAN-02 have been deleted in RETRAN-03. In this paper the changes between RETRAN-02 and RETRAN-03 are reviewed

Relationship between general safety requirements and safety culture in the improvement of safe operation of I.N.R. TRIGA reactor facilities

International Nuclear Information System (INIS)

Ciocanescu, M.; Preda, M.; Chiritescu, M.; Dumitru, M.

1996-01-01

Acquiring of the basic principles of ''safety culture'' by a large number of profesionals in the nuclear field drew the attention of the decision factors in the INR managerial structure, who decided to promote certain practical actions at each level in order to improve nuclear safety. Starting from the ''Republican Standards for Nuclear Safety'' issued by CSEN in 1975, where general safety criteria are defined for nuclear reactors and NPPs, the specialists at the TRIGA reactor originated and implemented a coherent and secure system to ensure nuclear safety over all steps of nuclear activities: research, conception, execution, commissioning and operation. This system has been continuosly corrected so that now it is completely integrated in a modern safety system. The paper presents the way in which a modern system for nuclear safety at the TRIGA reactor has been implemented and developed, in accordance to specific criteria and requirements imposed by related National Regulations and with the principles of safety culture. Starting from the definition of specific responsabilities, there are presented the internal stipulations and practical actions at all levels in order to enhance nuclear safety. (orig.)

Safety and risk assessment of ceramide 3 in cosmetic products.

Science.gov (United States)

Choi, Seul Min; Lee, Byung-Mu

2015-10-01

Ceramide 3 is used mainly as a moisturizer in various cosmetic products. Although several safety studies on formulations containing pseudo-ceramide or ceramide have been conducted at the preclinical and clinical levels for regulatory approval, no studies have evaluated the systemic toxicity of ceramide 3. To address this issue, we conducted a risk assessment and comprehensive toxicological review of ceramide and pseudo-ceramide. We assumed that ceramide 3 is present in various personal and cosmetic products at concentrations of 0.5-10%. Based on previously reported exposure data, the margin of safety (MOS) was calculated for product type, use pattern, and ceramide 3 concentration. Lipsticks with up to 10% ceramide 3 (MOS = 4111) are considered safe, while shampoos containing 0.5% ceramide 3 (MOS = 148) are known to be safe. Reported MOS values for body lotion applied to the hands (1% ceramide 3) and back (5% ceramide 3) were 103 and 168, respectively. We anticipate that face cream would be safe up to a ceramide 3 concentration of 3% (MOS = 149). Collectively, the MOS approach indicated no safety concerns for cosmetic products containing less than 1% ceramide 3. Copyright © 2015 Elsevier Ltd. All rights reserved.

Nuclear Safety R and D Programs and trend in the U. S. Utility Industry

International Nuclear Information System (INIS)

Kim, Jong Hyun

1992-01-01

First of all, the deterministic approach to safety analysis, which had dominated safety research in the earlier years, has given much ground to probabilistic approach. Secondly, human factors analysis has become an important part of safety research. Third, safety research relevant to reliability, or safety combined with reliability, are gradually taking place of purely safety-oriented or stand-alone safety research. More and more nuclear utilities in the U. S. are integrating safety with reliability. This evolution is in part due to the successful completion of major safety testing and analyses of deterministic nature, and partially due to the utility industry's desire to harvest synergistic nature, and partially due to the utility industry's desire to harvest synergistic results by combining safety with reliability, as the utility industry is more and more concerned about reducing operation and maintenance costs by enhancing reliability while maintaining plant safety. Nuclear safety is a complex and comprehensive concept, defying a simple categorization or interpretation. Thus, research and development in nuclear safety is necessarily diverse, and the program areas and trend presented in this paper are not meant to be all inclusive. For instance, there are some other active areas that were not mentioned, such as seismic risk assessment program and others. Nuclear safety research and development activities have undergone a perceptible shift of emphasis in recent years. They have become more focused and product-oriented. Also, except for the severe accident analysis, the emphasis on prevention and mitigation of accident, rather than analyzing the consequences of accident, is very much in evidence; that is, reliability-based technologies using PIRA methodology, and upgrading of instrumentation and control technologies are in the main stream of activities

H.R. 3521: Nuclear Facilities Occupational Safety Improvement Act of 1989. Introduced in the House of Representatives, One Hundredth First Congress, First Session, October 25, 1989

International Nuclear Information System (INIS)

Anon.

1989-01-01

Bill H.R.3521 was introduced in the House of Representatives of the United States on October 25, 1989. The purpose of this Act and the amendments made by this Act are to improve and enforce standards for employee health and safety at Department of Energy nuclear facilities. Congress finds that worker health and safety at Department of Energy nuclear facilities could be made substantially safer by applying standards developed by experts in the field of occupational health and safety. A section-by-section analysis makes up most of the report with emphasis on the following: application of OSHA to DOE nuclear facilities; cooperation with inspections and investigations; transfer and allocation of appropriations and personnel; worker training requirements; performance of NIOSH functions at DOE nuclear facilities; medical examinations of employees; and labor-management health and safety committees at DOE nuclear facilities

46 CFR 151.03-19 - Environment.

Science.gov (United States)

2010-10-01

... 46 Shipping 5 2010-10-01 2010-10-01 false Environment. 151.03-19 Section 151.03-19 Shipping COAST GUARD, DEPARTMENT OF HOMELAND SECURITY (CONTINUED) CERTAIN BULK DANGEROUS CARGOES BARGES CARRYING BULK LIQUID HAZARDOUS MATERIAL CARGOES Definitions § 151.03-19 Environment. This term refers to the atmosphere...

Targeted alpha therapy in vivo: direct evidence for single cancer cell kill using 149Tb-rituximab

International Nuclear Information System (INIS)

Beyer, G.J.; Soloviev, D.; Buchegger, F.; Miederer, M.; Vranjes-Duric, S.; Comor, J.J.; Kuenzi, G.; Hartley, O.; Senekowitsch-Schmidtke, R.

2004-01-01

This study demonstrates high-efficiency sterilisation of single cancer cells in a SCID mouse model of leukaemia using rituximab, a monoclonal antibody that targets CD20, labelled with terbium-149, an alpha-emitting radionuclide. Radio-immunotherapy with 5.5 MBq labelled antibody conjugate (1.11 GBq/mg) 2 days after an intravenous graft of 5.10 6 Daudi cells resulted in tumour-free survival for >120 days in 89% of treated animals. In contrast, all control mice (no treatment or treated with 5 or 300 μg unlabelled rituximab) developed lymphoma disease. At the end of the study period, 28.4%±4% of the long-lived daughter activity remained in the body, of which 91.1% was located in bone tissue and 6.3% in the liver. A relatively high daughter radioactivity concentration was found in the spleen (12%±2%/g), suggesting that the killed cancer cells are mainly eliminated through the spleen. This promising preliminary in vivo study suggests that targeted alpha therapy with 149 Tb is worthy of consideration as a new-generation radio-immunotherapeutic approach. (orig.)

Bimatoprost 0.03%/timolol 0.5% preservative-free ophthalmic solution versus bimatoprost 0.03%/timolol 0.5% ophthalmic solution (Ganfort) for glaucoma or ocular hypertension: a 12-week randomised controlled trial.

Science.gov (United States)

Goldberg, Ivan; Gil Pina, Rafael; Lanzagorta-Aresti, Aitor; Schiffman, Rhett M; Liu, Charlie; Bejanian, Marina

2014-07-01

To compare the efficacy and safety of single-dose bimatoprost 0.03%/timolol 0.5% preservative-free (PF) ophthalmic solution with bimatoprost 0.03%/timolol 0.5% ophthalmic solution in patients with open-angle glaucoma or ocular hypertension. In this multicentre, randomised, parallel-group study, patients were randomised to bimatoprost/timolol PF or bimatoprost/timolol once daily in the morning for 12 weeks. Primary efficacy endpoints, reflecting differing regional regulatory requirements, included change from baseline in worse eye intraocular pressure (IOP) in the per-protocol population at week 12, and the average eye IOP at weeks 2, 6 and 12 in the intent-to-treat population. 561 patients were randomised (278 to bimatoprost/timolol PF; 283 to bimatoprost/timolol); 96.3% completed the study. Both treatment groups showed statistically and clinically significant mean decreases from baseline in worse eye IOP and in average eye IOP at all follow-up time points (p<0.001). Bimatoprost/timolol PF met all pre-established criteria for non-inferiority and equivalence to bimatoprost/timolol. Ocular adverse events were similar between treatment groups, with conjunctival hyperaemia being the most frequent. Most were mild or moderate in severity. Bimatoprost/timolol PF demonstrated non-inferiority and equivalence in IOP lowering compared with bimatoprost/timolol, with no significant differences in safety and tolerability. NCT01177098. Published by the BMJ Publishing Group Limited. For permission to use (where not already granted under a licence) please go to http://group.bmj.com/group/rights-licensing/permissions.

19 CFR 212.03 - Proceedings covered.

Science.gov (United States)

2010-04-01

... 19 Customs Duties 3 2010-04-01 2010-04-01 false Proceedings covered. 212.03 Section 212.03 Customs Duties UNITED STATES INTERNATIONAL TRADE COMMISSION INVESTIGATIONS OF UNFAIR PRACTICES IN IMPORT TRADE IMPLEMENTATION OF THE EQUAL ACCESS TO JUSTICE ACT General Provisions § 212.03 Proceedings covered. (a) The Act...

Magnetically tunable alternating current electrical properties of x La{sub 0.7}Sr{sub 0.3}MnO{sub 3}–(1 − x) ErMnO{sub 3} (x = 0.1, 0.3, and 0.5) multiferroic nanocomposite

Energy Technology Data Exchange (ETDEWEB)

Debnath, Rajesh; Dey, P.; Singh, Swati; Roy, J. N.; Mandal, S. K., E-mail: saniitkgp2007@gmail.com [Department of Physics, National Institute of Technology Agartala, Tripura 799046 (India); Nath, T. K. [Department of Physics and Meteorology, Indian Institute of Technology Kharagpur, Kharagpur 721302, West Bengal (India)

2015-07-28

Detailed magnetically tunable ac electrical properties of x La{sub 0.7}Sr{sub 0.3}MnO{sub 3} (LSMO)–(1 − x) ErMnO{sub 3} (EMO) (x = 0.1, 0.3, and 0.5) multiferroic nanocomposites have been studied at 300 K in presence of varying magnetic field (H{sub appl}), applied both in parallel and perpendicular configuration with respect to the measuring electric field. AC electrical properties have exhibited significant variation with H{sub appl} for all composites, whereas for parallel configuration of H{sub appl} such effect is very feeble for x = 0.3 composite. We have attributed this anisotropic behavior to the demagnetization effect in the sample. In contrast, for x = 0.1 and 0.5 composites, no such anisotropy effect is experimentally evidenced. Impedance and real part of impedance have been found to decrease with H{sub appl} at low frequency (f) region. We attribute this observation to the depinning of the magnetic domain walls from the grain boundaries pinning centers and thereby enhancing the spin dependent transport in the composite. For x = 0.3 composite, Nyquist plots have been fitted considering dominant contributions of LSMO and EMO grain boundaries and the interface region between them. However, for x = 0.1 composite, it corresponds to EMO grain boundaries and grain boundary interface region. The relaxation frequency (f{sub R}) is observed to shift at higher/lower f region in perpendicular/parallel configuration of H{sub appl} for x = 0.3 composite. This opposite variation of f{sub R}s with H{sub appl} for perpendicular and parallel configurations has been attributed to two competing factors of H{sub appl} induced enhancement of inductive part and H{sub appl} enhanced spin dependent transport causing fast relaxation processes in the sample. For x = 0.1 composite, in both configurations of H{sub appl}, f{sub R}s is shifting towards high f region, which has been discussed in terms of dominant role of spin dependent transport.

Safety considerations and countermeasures against fire and explosion at an HTGR-hydrogen production system. Proposal of safety design concept

International Nuclear Information System (INIS)

Nishihara, T.; Hada, K.; Shibata, T.; Shiozawa, S.

1996-01-01

Establishment of safety design concept and countermeasures against fire and explosion accidents is among key safety-related issues in an HTGR-hydrogen production system. We propose the different safety design concepts depending upon the origin of fire and explosion which may happen in the HTGR-hydrogen production plant. Against fire and explosion originated outside the reactor building (R/B), namely in the area of hydrogen production plant, the safety design concept is primarily to take a safe distance for preventing the damage on safety-related items or a proof wall if necessary. Because the hydrogen production plant is designed in the same safety level as a conventional chemical plant. The safe distance is proposed to limit an incident overpressure to 10 kPa so as not to suffer any damage on the items and to limit a wall-averaged temperature of concrete structures of the R/B to 175degC according to the current regulation. On the other hand, against a potential possibility of explosion originated inside the R/B, the safety design concept is to minimize the possibility of explosion low enough to assume no occurrence inside the R/B. That is, the measure is to exclude a simultaneous failure of a secondary helium piping and an endothermic chemical reactor. Furthermore, in severe accident condition in which the explosion may be postulated a priori, an incidental overpressure of explosion inside the reactor containment vessel (C/V) should be limited so as not to fail the C/V through restricting the amount of combustible gas ingress into the C/V by means of a combination of C/V isolation valve installed in the helium piping and emergency shut off valve in the process feed gas line. (author)

46 CFR 151.03-39 - Ocean.

Science.gov (United States)

2010-10-01

... HAZARDOUS MATERIAL CARGOES Definitions § 151.03-39 Ocean. A designation for all vessels normally navigating the waters of any ocean or the Gulf of Mexico more than 20 nautical miles offshore. ... 46 Shipping 5 2010-10-01 2010-10-01 false Ocean. 151.03-39 Section 151.03-39 Shipping COAST GUARD...

CHANGING THE SAFETY CULTURE IN HANFORD TANK FARMS

Energy Technology Data Exchange (ETDEWEB)

BERRIOCHOA MV; ALCALA LJ

2009-01-06

In 2000 the Hanford Tank Farms had one of the worst safety records in the Department of Energy Complex. By the end of FY08 the safety performance of the workforce had turned completely around, resulting in one of the best safety records in the DOE complex for operations of its kind. This paper describes the variety of programs and changes that were put in place to accomplish such a dramatic turn-around. The U.S. Department of Energy's 586-square-mile Hanford Site in Washington State was established during World War II as part of the Manhattan Project to develop nuclear materials to end the war. For the next several decades it continued to produce plutonium for the nation's defense, leaving behind vast quantities of radioactive and chemical waste. Much of this waste, 53,000,000 gallons, remains stored in 149 aging single-shell tanks and 28 newer double-shell tanks. One of the primary objectives at Hanford is to safely manage this waste until it can be prepared for disposal, but this has not always been easy. These giant underground tanks, many of which date back to the beginning of the Manhattan Project, range in size from 55,000 gallons up to 1.1 million gallons, and are buried beneath 10 feet of soil near the center of the site. Up to 67 of the older single-shell tanks have leaked as much as one million gallons into the surrounding soil. Liquids from the single-shell tanks were removed by 2003 but solids remain in the form of saltcake, sludges and a hardened heel at the bottom of some tanks. The Department of Energy's Office of River Protection was established to safely manage this waste until it could be prepared for disposal. For most of the last seven years the focus has been on safely retrieving waste from the 149 aging single-shell and moving it to the newer double-shell tanks. Removing waste from the tanks is a difficult and complex task. The tanks were made to put waste in, not take it out. Because of the toxic nature of the waste, both

Selection methodology for LWR safety R and D programs and proposals. Volume III. User's manual for the multi-attribute utility package (MAUP)

International Nuclear Information System (INIS)

Hale, M.; Turnage, J.J.; Husseiny, A.A.; Ritzman, R.L.

1981-02-01

The computer program which was developed to apply the multi-attribute utility (MAU) methodology to the selection of LWR safety R and D programs and proposals is described. An overview of the MAU method is presented, followed by a description of the steps incorporated in developing individual modules for use in the multi-attribute utility package (MAUP). Each module is described complete with usage information and an example of computer output

Safety Training: places available in July - August 2013

CERN Multimedia

Isabelle CUSATO, HSE Unit

2013-01-01

There are places available in the forthcoming Safety courses. For updates and registrations, please refer to the Safety Training Catalogue.   July - August 2013 (alphabetical order) Conduite de plates-formes élévatrices mobiles de personnel (PEMP) (Cherry-picker training) 01-JUL-13 to 02-JUL-13, 8.30 – 17.30, in French First-Aiders – Basic Course 31-JUL-13, 8.15 – 17.30, in English Habilitation électrique personnel électricien basse tension (electrical habilitation for low voltage) 01-JUL-13 to 03-JUL-13, 9.00 – 17.30, in French (with handouts in English) Pontier-élingueur (Crane training) 03-JUL-13 to 04-JUL-13, 8.30 – 17.30, in French (with handouts in English) Radiological Protection - Controlled Radiation Area - Course A for CERN employees and CERN associates 11-JUL-13, 8.30 – 17.00, in English 11-JUL-13, 8.30 – 17.00, in French 12-JUL-13, 8.30 – 17.00, i...

Safety Training: places available in July - August 2013

CERN Multimedia

Isabelle CUSATO, HSE Unit

2013-01-01

There are places available in the forthcoming Safety courses. For updates and registrations, please refer to the Safety Training Catalogue.   July - August 2013 (alphabetical order) Conduite de plates-formes élévatrices mobiles de personnel (PEMP) (Cherry-picker training) 01-JUL-13 to 02-JUL-13, 8.30 – 17.30, in French First-Aiders – Basic Course 31-JUL-13, 8.15 – 17.30, in English Habilitation électrique personnel électricien basse tension (electrical habilitation for low voltage) 01-JUL-13 to 03-JUL-13, 9.00 – 17.30, in French (with handouts in English) Pontier-élingueur (Crane training) 03-JUL-13 to 04-JUL-13, 8.30 – 17.30, in French (with handouts in English) Radiological Protection - Controlled Radiation Area - Course A for CERN employees and CERN associates 11-JUL-13, 8.30 – 17.00, in English 11-JUL-13, 8.30 – 17.00, in French 12-JUL-13, 8.30 – 17.00, in...

Safety of Nuclear Power Plants: Commissioning and Operation. Specific Safety Requirements

International Nuclear Information System (INIS)

2017-01-01

This publication is a revision of IAEA Safety Standards Series No. NS-R-2, Safety of Nuclear Power Plants: Operation, and has been extended to cover the commissioning stage. It describes the requirements to be met to ensure the safe commissioning, operation, and transition from operation to decommissioning of nuclear power plants. Over recent years there have been developments in areas such as long term operation of nuclear power plants, plant ageing, periodic safety review, probabilistic safety analysis review and risk informed decision making processes. It became necessary to revise the IAEA’s Safety Requirements in these areas and to correct and/or improve the publication on the basis of feedback from its application by both the IAEA and its Member States. In addition, the requirements are governed by, and must apply, the safety objective and safety principles that are established in the IAEA Safety Standards Series No. SF-1, Fundamental Safety Principles. A review of Safety Requirements publications, initiated in 2011 following the accident in the Fukushima Daiichi nuclear power plant in Japan, revealed no significant areas of weakness but resulted in a small set of amendments to strengthen the requirements and facilitate their implementation. These are contained in the present publication.

Common basis of establishing safety standards and other safety decision-making levels for different sources of health risk

International Nuclear Information System (INIS)

Demin, V.F.

2002-01-01

Current approaches in establishing safety standards and other decision-making levels for different sources of health risk are critically analysed. To have a common basis for this decision-making a specific risk index R is recommended. In the common sense R is quantitatively defined as LLE caused by the annual exposure to the risk source considered: R = annual exposure, damage (LLE) from the exposure unit. This common definition is also rewritten in specific forms for a set of different risk sources (ionising radiation, chemical pollutants, etc): for different risk sources the exposure can be measured with different quantities (the probability of death, the exposure dose, etc.). R is relative LLE: LLE in years referred to 1 year under the risk. The dimension of this value is [year/year]. In the statistical sense R is conditionally the share of the year, which is lost due to exposure to a risk source during this year. In this sense R can be called as the relative damage. Really lifetime years are lost after the exposure. R can be in some conditional sense considered as a dimensionless quantity. General safety standards R n for the public and occupational workers have been suggested in terms of this index: R n = 0.0007 and 0.01 accordingly. Secondary safety standards are derived for a number of risk sources (ionising radiation, environmental chemical pollutants, etc). Values of R n are chosen in such a way that to have the secondary radiation BSS being equivalent to the current one's. Other general and derived levels for safety decision-making are also proposed including the de-minimus levels. Their possible dependence on the national or regional health-demographic data (HDD) is considered. Such issues as the ways of the integration and averaging of risk indices considered through the national or regional HDD for different risk sources and the use of non-threshold linear exposure - response relationships for ionising radiation and chemical pollutants are analysed

Impact of Delayed Whole Blood Processing Time on Plasma Levels of miR-1 and miR-423-5p up to 24 Hours.

Science.gov (United States)

Borges, Danielle Pazzotti; Cunha-Neto, Edecio; Bocchi, Edimar A; Rigaud, Vagner Oliveira Carvalho

2018-03-21

Circulating cell-free miRNAs hold great promise as a new class of biomarkers due to their high stability in body fluids and association with disease stages. However, even using sensitive and specific methods, technical challenges are associated with miRNA analysis in body fluids. A major source of variation in plasma and serum is the potential cell-derived miRNA contamination from hemolysis. To evaluate the effect of the delayed whole blood processing time on the concentrations of miR-1 and -423-5p. Ten blood samples were incubated for 0, 3 and 24 hours at room temperature prior processing into plasma. For each time point, hemolysis was assessed in plasma by UV spectrophotometry at 414nm wavelength (λ414). Circulating levels of miR-1 and -423-5p were measured by RT-qPCR; miR-23a and -451 were also analyzed as controls. A significant hemolysis was observed only after 24h (λ414 0.3±0.02, plevels were observed up to 24h of storage at room temperature (Ct 31.5±0.5 to 31.8±0.6for miR-1, p=0.989; and 29.01±0.3 to 29.04±0.3, p=0.614 for -423-5p). No correlation was observed between hemolysis and levels of miR-1 and -423-5p. Our data indicate the storage of whole blood samples at room temperature for up to 24h prior their processing into plasma does not appear to have a significant impact on miR-1 and -423-5p concentrations. Copyright© Bentham Science Publishers; For any queries, please email at epub@benthamscience.org.

Nuclear safety research project. Annual report 1995

International Nuclear Information System (INIS)

Hueper, R.

1996-08-01

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

Formulating Human Resources Development Strategies for Nuclear R and D, Safety and Security

International Nuclear Information System (INIS)

Min, B. J.; Kim, M. K.; Son, M. Y.

2010-05-01

Enforced by the recent launch of the 4th National Power Expansion Plan and the 1st Basic Plan for National Energy Policy with an ambitious goal of achieving 'Low CO2 Emission and Green Growth', a rapid expansion of nuclear technology development has been reemphasized. In addition, the nation, being a potential exporter of nuclear power plants and nuclear technologies strives to explore their exports markets. In response, it is inevitable to set the priority in human resource development (HRD) as nuclear technology development both requires and fosters HRD which in turn, enables to meet the successful implementation of nuclear power expansion. A continuous, consistent and well-managed programme of HRD is crucial to assure continuity over time in the needed capacities, skills and knowledge, and to establish and maintain a cadre of manpower variously trained in different nuclear-related skills and educated in nuclear relevant fields. The objective of the study is to conduct comprehensive quantitative analyses to estimate future human resources requirements, particularly in the field of nuclear R and D, safety and security in order to establish an appropriate long-term nuclear HRD plan

Safety profiles of Tripterygium wilfordii Hook F: a systematic review and meta-analysis

Directory of Open Access Journals (Sweden)

Chi Zhang

2016-11-01

Full Text Available Objective: Tripterygium wilfordii Hook F (TwHF is a widely used and effective treatment for inflammatory diseases. There have been concerns about its toxicity but no adequate synthesis of the evidence for adverse events (AEs. We aimed to undertake a clinically informative, systematic safety profile of TwHF.Methods: We undertook a systematic review and meta-analysis of experimental studies and observational studies. We searched electronic databases and conference abstracts. Safety outcomes were rates of common AEs. Results: We screened 4,137 abstracts for eligibility and included 594 studies in the analysis. The overall incidence of AEs was 26.7% (95% CI 24.8%, 28.8% in 23,256 TwHF users. The estimates did vary markedly when stratified by specific study types. The incidence of gastrointestinal symptoms, adverse reproductive outcomes, adverse skin reactions, hematologic events and cardiovascular events were 13.3% (95%CI 11.9%, 14.9%, 11.7% (95% CI 10.3%, 13.3%, 7.8% (95%CI 6.3%-9.5%, 6.5% (95%CI 5.7%-7.4% and 4.9% (95%CI 1.6%, 14.3%, respectively. The prevalence of irregular menstruation (IM was increased in patients taking TwHF compared with those given control (odds ratio [OR] 4.65, 95% CI 3.08 to 7.03. TwHF use has lower risk of weight gain (OR 0.12 [95%CI 0.04 to 0.39] and hair loss (OR 0.37 [95% CI 0.18 to 0.78]. Furthermore, long-term aspirin use (> 6 months has a higher AEs incidence (31.0% [95% CI 24.5%-38.5%].Conclusion: Our findings suggest that more than one in four patients who were taking TwHF had experienced AEs. A clear need exists for improved understanding of contributing risk factors, as well as of prevention and management strategies to improve patients' tolerance for TwHF.

77 FR 24257 - Railroad Safety Advisory Committee (RSAC); Working Group Activity Update

Science.gov (United States)

2012-04-23

... publication. Contact: Steve Clay, (202) 493-6259. Task 06-03--Medical Standards for Safety-Critical Personnel... 97-2--(Completed) Evaluating the extent to which environmental, sanitary, and other working...

Licensing of the proposed PBMR-SA

International Nuclear Information System (INIS)

Clapisson, G.A.; Henderson, N.R.; Hill, T.F.; Keenan, N.H.; Metcalf, P.E.; Mysenkov, A.

1997-01-01

This paper describes the preliminary criteria, which are intended to be used by the South African regulatory authority (CNS), for licensing of the ESKOM proposed - South African high temperature gas-cooled Pebble Bed Modular Reactor (PBMR-SA). The CNS intends to apply the existing CNS licensing approach together with some international design criteria used for advanced reactors as well as international experience gained from the safety evaluation of the MHTGR, THTR, etc. A major requirement to this type of reactor is that it should comply with the current CNS risk criteria and provide, as a minimum, the same degree of protection to the operator, public and environment that is required for the current generation of nuclear reactors. (author)

Use of a temperature-initiated passive cooling system (TIPACS) for the modular high-temperature gas-cooled reactor cavity cooling system (RCCS)

International Nuclear Information System (INIS)

Forsberg, C.W.; Conklin, J.; Reich, W.J.

1994-04-01

A new type of passive cooling system has been invented (Forsberg 1993): the Temperature-Initiated Passive Cooling System (TIPACS). The characteristics of the TIPACS potentially match requirements for an improved reactor-cavity-cooling system (RCCS) for the modular high-temperature gas-cooled reactor (MHTGR). This report is an initial evaluation of the TIPACS for the MHTGR with a Rankines (steam) power conversion cycle. Limited evaluations were made of applying the TIPACS to MHTGRs with reactor pressure vessel temperatures up to 450 C. These temperatures may occur in designs of Brayton cycle (gas turbine) and process heat MHTGRs. The report is structured as follows. Section 2 describes the containment cooling issues associated with the MHTGR and the requirements for such a cooling system. Section 3 describes TIPACS in nonmathematical terms. Section 4 describes TIPACS's heat-removal capabilities. Section 5 analyzes the operation of the temperature-control mechanism that determines under what conditions the TIPACS rejects heat to the environment. Section 6 addresses other design and operational issues. Section 7 identifies uncertainties, and Section 8 provides conclusions. The appendixes provide the detailed data and models used in the analysis

Use of a temperature-initiated passive cooling system (TIPACS) for the modular high-temperature gas-cooled reactor cavity cooling system (RCCS)

Energy Technology Data Exchange (ETDEWEB)

Forsberg, C.W.; Conklin, J.; Reich, W.J.

1994-04-01

A new type of passive cooling system has been invented (Forsberg 1993): the Temperature-Initiated Passive Cooling System (TIPACS). The characteristics of the TIPACS potentially match requirements for an improved reactor-cavity-cooling system (RCCS) for the modular high-temperature gas-cooled reactor (MHTGR). This report is an initial evaluation of the TIPACS for the MHTGR with a Rankines (steam) power conversion cycle. Limited evaluations were made of applying the TIPACS to MHTGRs with reactor pressure vessel temperatures up to 450 C. These temperatures may occur in designs of Brayton cycle (gas turbine) and process heat MHTGRs. The report is structured as follows. Section 2 describes the containment cooling issues associated with the MHTGR and the requirements for such a cooling system. Section 3 describes TIPACS in nonmathematical terms. Section 4 describes TIPACS`s heat-removal capabilities. Section 5 analyzes the operation of the temperature-control mechanism that determines under what conditions the TIPACS rejects heat to the environment. Section 6 addresses other design and operational issues. Section 7 identifies uncertainties, and Section 8 provides conclusions. The appendixes provide the detailed data and models used in the analysis.

Preliminary safety design analysis of KALIMER

Energy Technology Data Exchange (ETDEWEB)

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

1999-03-01

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

Railing for safety: job demands, job control, and safety citizenship role definition.

Science.gov (United States)

Turner, Nick; Chmiel, Nik; Walls, Melanie

2005-10-01

This study investigated job demands and job control as predictors of safety citizenship role definition, that is, employees' role orientation toward improving workplace safety. Data from a survey of 334 trackside workers were framed in the context of R. A. Karasek's (1979) job demands-control model. High job demands were negatively related to safety citizenship role definition, whereas high job control was positively related to this construct. Safety citizenship role definition of employees with high job control was buffered from the influence of high job demands, unlike that of employees with low job control, for whom high job demands were related to lower levels of the construct. Employees facing both high job demands and low job control were less likely than other employees to view improving safety as part of their role orientation. Copyright (c) 2005 APA, all rights reserved.

Fast reactor safety program. Progress report, January-March 1980

International Nuclear Information System (INIS)

1980-05-01

The goal of the DOE LMFBR Safety Program is to provide a technology base fully responsive to safety considerations in the design, evaluation, licensing, and economic optimization of LMFBRs for electrical power generation. A strategy is presented that divides safety technology development into seven program elements, which have been used as the basis for the Work Breakdown Structure (WBS) for the Program. These elements include four lines of assurance (LOAs) involving core-related safety considerations, an element supporting non-core-related plant safety considerations, a safety R and D integration element, and an element for the development of test facilities and equipment to be used in Program experiments: LOA-1 (prevent accidents); LOA-2 (limit core damage); LOA-3 (maintain containment integrity); LOA-4 (attenuate radiological consequences); plant considerations; R and D integration; and facility development

Surface characterization, in vitro and in vivo biocompatibility of Mg-0.3Sr-0.3Ca for temporary cardiovascular implant

Energy Technology Data Exchange (ETDEWEB)

Bornapour, M., E-mail: mandana.bornapour@mail.mcgill.ca [Light Metals and Advanced Magnesium Materials, Mining and Materials Engineering, McGill University, Montreal, Qc, H3A 0C5 (Canada); Biointerface Lab, Mining and Materials Engineering, McGill University, Montreal, Qc H3A 0C5 (Canada); Mahjoubi, H. [Biointerface Lab, Mining and Materials Engineering, McGill University, Montreal, Qc H3A 0C5 (Canada); Vali, H. [Department of Anatomy and Cell Biology, McGill University, Montreal, Qc, H3A 0C7 (Canada); Shum-Tim, D. [Department of Cardiac Surgery and Surgical Research, McGill University, Montreal, Qc H3G 1A1 (Canada); Cerruti, M. [Biointerface Lab, Mining and Materials Engineering, McGill University, Montreal, Qc H3A 0C5 (Canada); Pekguleryuz, M. [Light Metals and Advanced Magnesium Materials, Mining and Materials Engineering, McGill University, Montreal, Qc, H3A 0C5 (Canada)

2016-10-01

Magnesium-based alloys are attractive candidate materials for medical applications. Our earlier work showed that the ternary Mg-0.3Sr-0.3Ca alloy exhibits slower degradation rates than both binary Mg-Sr and Mg-Ca alloys. The ternary alloy immersed in simulated body fluid (SBF) forms a compact surface layer of corrosion products that we hypothesized to be a Sr-substituted hydroxyapatite (HA). The main objectives of the current work are to understand the bio-degradation mechanism of Mg-0.3Sr-0.3Ca, to identify the exact nature of its protective layer and to evaluate the in vitro and in vivo biocompatibility of the alloy for cardiovascular applications. To better simulate the physiological environment, the alloy was immersed in SBF which was daily refreshed. Raman spectroscopy and X-Ray photoelectron spectroscopy (XPS) confirmed the formation of a thin, Sr-substituted HA layer at the interface between the alloy and the corrosion products. In vitro biocompatibility evaluated via indirect cytotoxicity assays using HUVECs showed no toxicity effect and ions extracted from Mg-0.3Sr-0.3Ca in fact increased the viability of HUVECs after one week. In vivo tests were performed by implanting a tubular Mg-0.3Sr-0.3Ca stent along with a WE43 control stent into the right and left femoral artery of a dog. Post implantation and histological analyses showed no thrombosis in the artery with Mg-0.3Sr-0.3Ca stent after 5 weeks of implantation while the artery implanted with WE43 stent was extensively occluded and thrombosed. Microscopic observation of the Mg-0.3Sr-0.3Ca implant-tissue interface confirmed the in situ formation of Sr-substituted HA on the surface during in vivo test. These results show that the interfacial layer protects the surface of the Mg-0.3Sr-0.3Ca alloy both in vitro and in vivo, and is the key factor in the bio-corrosion resistance of the alloy. - Highlights: • The surface active elements of Sr and Ca alter the corrosion of Mg alloy in SBF • Sr

Surface characterization, in vitro and in vivo biocompatibility of Mg-0.3Sr-0.3Ca for temporary cardiovascular implant

International Nuclear Information System (INIS)

Bornapour, M.; Mahjoubi, H.; Vali, H.; Shum-Tim, D.; Cerruti, M.; Pekguleryuz, M.

2016-01-01

Magnesium-based alloys are attractive candidate materials for medical applications. Our earlier work showed that the ternary Mg-0.3Sr-0.3Ca alloy exhibits slower degradation rates than both binary Mg-Sr and Mg-Ca alloys. The ternary alloy immersed in simulated body fluid (SBF) forms a compact surface layer of corrosion products that we hypothesized to be a Sr-substituted hydroxyapatite (HA). The main objectives of the current work are to understand the bio-degradation mechanism of Mg-0.3Sr-0.3Ca, to identify the exact nature of its protective layer and to evaluate the in vitro and in vivo biocompatibility of the alloy for cardiovascular applications. To better simulate the physiological environment, the alloy was immersed in SBF which was daily refreshed. Raman spectroscopy and X-Ray photoelectron spectroscopy (XPS) confirmed the formation of a thin, Sr-substituted HA layer at the interface between the alloy and the corrosion products. In vitro biocompatibility evaluated via indirect cytotoxicity assays using HUVECs showed no toxicity effect and ions extracted from Mg-0.3Sr-0.3Ca in fact increased the viability of HUVECs after one week. In vivo tests were performed by implanting a tubular Mg-0.3Sr-0.3Ca stent along with a WE43 control stent into the right and left femoral artery of a dog. Post implantation and histological analyses showed no thrombosis in the artery with Mg-0.3Sr-0.3Ca stent after 5 weeks of implantation while the artery implanted with WE43 stent was extensively occluded and thrombosed. Microscopic observation of the Mg-0.3Sr-0.3Ca implant-tissue interface confirmed the in situ formation of Sr-substituted HA on the surface during in vivo test. These results show that the interfacial layer protects the surface of the Mg-0.3Sr-0.3Ca alloy both in vitro and in vivo, and is the key factor in the bio-corrosion resistance of the alloy. - Highlights: • The surface active elements of Sr and Ca alter the corrosion of Mg alloy in SBF • Sr

GUNSCHIP/GUNPUC03

Data.gov (United States)

Social Security Administration — GUNSCHIP and GUNPUC03 are general utility programs that read and retrieve NUMIDENT data. Many Social Security Administration on-line applications use these utilities...

40 CFR 191.03 - Standards.

Science.gov (United States)

2010-07-01

...) Management and storage of spent nuclear fuel or high-level or transuranic radioactive wastes at all... and storage of spent nuclear fuel or high-level or transuranic radioactive wastes at all facilities... 40 Protection of Environment 24 2010-07-01 2010-07-01 false Standards. 191.03 Section 191.03...

2017-10-28T00:19:03Z https://www.ajol.info/index.php/all/oai oai:ojs ...

African Journals Online (AJOL)

article/27942 2017-10-28T00:19:03Z wajm:ART A preliminary survey of central nervous system tumors in Tema, Ghana Andrews, NB; Tema International Neuro Center (T. I.N) Nath-Bita Hospital, Tema, Ghana Ramesh, R; Tema International ...

Surface characterization, in vitro and in vivo biocompatibility of Mg-0.3Sr-0.3Ca for temporary cardiovascular implant.

Science.gov (United States)

Bornapour, M; Mahjoubi, H; Vali, H; Shum-Tim, D; Cerruti, M; Pekguleryuz, M

2016-10-01

Magnesium-based alloys are attractive candidate materials for medical applications. Our earlier work showed that the ternary Mg-0.3Sr-0.3Ca alloy exhibits slower degradation rates than both binary Mg-Sr and Mg-Ca alloys. The ternary alloy immersed in simulated body fluid (SBF) forms a compact surface layer of corrosion products that we hypothesized to be a Sr-substituted hydroxyapatite (HA). The main objectives of the current work are to understand the bio-degradation mechanism of Mg-0.3Sr-0.3Ca, to identify the exact nature of its protective layer and to evaluate the in vitro and in vivo biocompatibility of the alloy for cardiovascular applications. To better simulate the physiological environment, the alloy was immersed in SBF which was daily refreshed. Raman spectroscopy and X-Ray photoelectron spectroscopy (XPS) confirmed the formation of a thin, Sr-substituted HA layer at the interface between the alloy and the corrosion products. In vitro biocompatibility evaluated via indirect cytotoxicity assays using HUVECs showed no toxicity effect and ions extracted from Mg-0.3Sr-0.3Ca in fact increased the viability of HUVECs after one week. In vivo tests were performed by implanting a tubular Mg-0.3Sr-0.3Ca stent along with a WE43 control stent into the right and left femoral artery of a dog. Post implantation and histological analyses showed no thrombosis in the artery with Mg-0.3Sr-0.3Ca stent after 5weeks of implantation while the artery implanted with WE43 stent was extensively occluded and thrombosed. Microscopic observation of the Mg-0.3Sr-0.3Ca implant-tissue interface confirmed the in situ formation of Sr-substituted HA on the surface during in vivo test. These results show that the interfacial layer protects the surface of the Mg-0.3Sr-0.3Ca alloy both in vitro and in vivo, and is the key factor in the bio-corrosion resistance of the alloy. Copyright © 2016 Elsevier B.V. All rights reserved.

Level densities and γ-strength functions in 148,149Sm

International Nuclear Information System (INIS)

Siem, S.; Guttormsen, M.; Ingeberg, K.; Melby, E.; Rekstad, J.; Schiller, A.; Voinov, A.

2002-01-01

The level densities and γ-strength functions of the weakly deformed 148 Sm and 149 Sm nuclei have been extracted. The temperature versus excitation energy curve, derived within the framework of the microcanonical ensemble, shows structures, which we associate with the breakup of Cooper pairs. The nuclear heat capacity is deduced within the framework of both the microcanonical and canonical ensembles. We observe negative heat capacity in the microcanonical ensemble whereas the canonical heat capacity exhibits an S shape as a function of temperature, both signals of a phase transition. The structures in the γ-strength functions are discussed in terms of the pygmy resonance and the scissors mode built on excited states. The samarium results are compared with data for the well-deformed 161,162 Dy, 166,167 Er, and 171,172 Yb isotopes and with data from (n,γ) experiments and giant dipole resonance studies

The gas turbine-modular helium reactor (GT-MHR), high efficiency, cost competitive, nuclear energy for the next century

International Nuclear Information System (INIS)

Zgliczynski, J.B.; Silady, F.A.; Neylan, A.J.

1994-04-01

The Gas Turbine-Modular Helium Reactor (GT-MHR) is the result of coupling the evolution of a small passively safe reactor with key technology developments in the US during the last decade: large industrial gas turbines, large active magnetic bearings, and compact, highly effective plate-fin heat exchangers. The GT-MHR is the only reactor concept which provides a step increase in economic performance combined with increased safety. This is accomplished through its unique utilization of the Brayton cycle to produce electricity directly with the high temperature helium primary coolant from the reactor directly driving the gas turbine electrical generator. This cannot be accomplished with another reactor concept. It retains the high levels of passive safety and the standardized modular design of the steam cycle MHTGR, while showing promise for a significant reduction in power generating costs by increasing plant net efficiency to a remarkable 47%

Nuclear Protection and Safety Institute R and D activities in the field of plant ageing

Energy Technology Data Exchange (ETDEWEB)

Deletre, G; Henry, J Y; Miannay, D; Olivera, J J; Horowitz, H; Barrachin, B

1991-11-01

A part of the work carried out by the CEA's Nuclear Protection and Safety Institute (IPSN) is devoted to revealing possible modifications in nuclear reactor materials under the combined effects of time, temperature and irradiation. The current R and D programme being carried out by the IPSN in collaboration with various specialized CEA departments concentrates on three main fields: - Reactor coolant system materials, - Polymerbased materials, - Coatings and paintings used inside pressurized water reactor containments. These activities are, of course, part of a much wider context which includes operating experience feedback, particularly as regards deterioration already observed in pressurized water reactors; this deterioration is usually the result of phenomena which were overlooked or inadequately studied at the design stage (corrosion, erosion, vibratory or thermal fatigue, cavitation, etc.). With his perspective in view, the IPSN is also undertaking a number of activities to develop powerful inspection methods and increase the effectiveness of preventive maintenance programmes.

Nuclear Protection and Safety Institute R and D activities in the field of plant aging

International Nuclear Information System (INIS)

Deletre, G.; Henry, J.Y.; Miannay, D.; Olivera, J.J.; Horowitz, H.; Barrachin, B.

1991-01-01

A part of the work carried out by the CEA's Nuclear Protection and Safety Institute (IPSN) is devoted to revealing possible modifications in nuclear reactor materials under the combined effects of time, temperature and irradiation. The current R and D programme being carried out by the IPSN is collaboration with various specialized CEA departments concentrates on three main fields: Reactor coolant system materials, Polymerbased materials, Coatings and paintings used inside pressurized water reactor containments. These activities are, of course, part of a much wider context which includes operating experience feedback, particularly as regards deterioration already observed in pressurized water reactors; this deterioration is usually the result of phenomena which were overlooked or inadequately studied at the design stage (corrosion, erosion, vibratory or thermal fatigue, cavitation, etc). With this perspective in view, the IPSN is also undertaking a number of activities to develop powerful inspection methods and increase the effectiveness of preventive maintenance programmes. (author)

36 CFR 902.03 - Definitions.

Science.gov (United States)

2010-07-01

... Avenue Development Corporation Act of 1972, Pub. L. 92-578, 86 Stat. 1266 (40 U.S.C. 871 et seq.), as... 902.03 Parks, Forests, and Public Property PENNSYLVANIA AVENUE DEVELOPMENT CORPORATION FREEDOM OF INFORMATION ACT Applicability and Policy § 902.03 Definitions. As used in this part— (a) Act means section 552...

Crystallization and preliminary X-ray study of a (2R,3R)-2,3-butanediol dehydrogenase from Bacillus coagulans 2-6.

Science.gov (United States)

Miao, Xiangzhi; Huang, Xianhui; Zhang, Guofang; Zhao, Xiufang; Zhu, Xianming; Dong, Hui

2013-10-01

(2R,3R)-2,3-Butanediol dehydrogenase (R,R-BDH) from Bacillus coagulans 2-6 is a zinc-dependent medium-chain alcohol dehydrogenase. Recombinant R,R-BDH with a His6 tag at the C-terminus was expressed in Escherichia coli BL21 (DE3) cells and purified by Ni2+-chelating affinity and size-exclusion chromatography. Crystals were grown by the hanging-drop vapour-diffusion method at 289 K. The crystallization condition consisted of 8%(v/v) Tacsimate pH 4.6, 18%(w/v) polyethylene glycol 3350. The crystal diffracted to 2.8 Å resolution in the orthorhombic space group P2₁2₁2₁, with unit-cell parameters a=88.35, b=128.73, c=131.03 Å.

R and D directions for the development of CANDU reactors

International Nuclear Information System (INIS)

Torgerson, D.F.

1998-01-01

Full text: AECL is carrying out a comprehensive R and D programme to advance all aspects of CANDU reactor technology. These programs are focusing on three main strategic directions: improved economics, enhanced safety, and fuel cycle flexibility. R and D areas include fuel cycle development, heavy water technology, fuel channel development, safety technology, control and instrumentation, reactor chemistry, systems and components, and health and environment. In each case, the R and D programs have short, medium, and long-term goals to achieve the overall strategic directions. Most of the programs seek to further develop and exploit some of the unique characteristics of pressurized heavy water reactors. Examples of this include high neutron economy and on-power fueling which allow several different fuel cycles, the presence of large water heat sinks for enhanced safety, and modular components that can be easily replaced for plant life extension. This presentation reviews AECL's product development directions and the R and D programs that have been begun for their development

76 FR 77549 - Colorado River Indian Tribes-Amendment to Health & Safety Code, Article 2. Liquor

Science.gov (United States)

2011-12-13

... Health & Safety Code, Article 2. Liquor AGENCY: Bureau of Indian Affairs, Interior. ACTION: Notice. SUMMARY: This notice publishes the amendment to the Colorado River Tribal Health and Safety Code, Article... Code, Article 2, Liquor by Ordinance No. 10-03 on December 13, 2010. This notice is published in...

46 CFR 151.03-38 - Nondestructive testing.

Science.gov (United States)

2010-10-01

... CARRYING BULK LIQUID HAZARDOUS MATERIAL CARGOES Definitions § 151.03-38 Nondestructive testing. Nondestructive testing includes ultrasonic examination, liquid penetrant examination, magnetic particle... 46 Shipping 5 2010-10-01 2010-10-01 false Nondestructive testing. 151.03-38 Section 151.03-38...

Dicty_cDB: FC-AI03 [Dicty_cDB

Lifescience Database Archive (English)

Full Text Available FC (Link to library) FC-AI03 (Link to dictyBase) - - - Contig-U15833-1 FC-AI03P (Li...nk to Original site) FC-AI03F 690 FC-AI03Z 651 FC-AI03P 1341 - - Show FC-AI03 Library FC (Link to library) Clone ID FC-AI...nal site URL http://dictycdb.biol.tsukuba.ac.jp/CSM/FC/FC-AI/FC-AI03Q.Seq.d/ Representative seq. ID FC-AI...03P (Link to Original site) Representative DNA sequence >FC-AI03 (FC-AI03Q) /CSM/FC/FC-AI/FC-AI...li*l*ivtlskv*qswyqvfcslmrftcwi*nv fht*ivhwsqhwhql*flqpivaiv*skapitifnlhmaslwif*ivl*sfvpfhiitmk sfkfspfvpqlki

Status of the safety concept and safety demonstration for an HLW repository in salt. Summary report

Energy Technology Data Exchange (ETDEWEB)

Bollingerfehr, W.; Buhmann, D.; Filbert, W.; and others

2013-12-15

Salt formations have been the preferred option as host rocks for the disposal of high level radioactive waste in Germany for more than 40 years. During this period comprehensive geological investigations have been carried out together with a broad spectrum of concept and safety related R and D work. The behaviour of an HLW repository in salt formations, particularly in salt domes, has been analysed in terms of assessment of the total system performance. This was first carried out for concepts of generic waste repositories in salt and, since 1998, for a repository concept with specific boundary conditions, taking the geology of the Gorleben salt dome as an example. Suitable repository concepts and designs were developed, the technical feasibility has been proven and operational and long-term safety evaluated. Numerical modelling is an important input into the development of a comprehensive safety case for a waste repository. Significant progress in the development of numerical tools and their application for long-term safety assessment has been made in the last two decades. An integrated approach has been used in which the repository concept and relevant scientific and engineering data are combined with the results from iterative safety assessments to increase the clarity and the traceability of the evaluation. A safety concept that takes full credit of the favourable properties of salt formations was developed in the course of the R and D project ISIBEL, which started in 2005. This concept is based on the safe containment of radioactive waste in a specific part of the host rock formation, termed the containment providing rock zone, which comprises the geological barrier, the geotechnical barriers and the compacted backfill. The future evolution of the repository system will be analysed using a catalogue of Features, Events and Processes (FEP), scenario development and numerical analysis, all of which are adapted to suit the safety concept. Key elements of the

Validation of the French national health insurance information system as a tool in vaccine safety assessment: application to febrile convulsions after pediatric measles/mumps/rubella immunization.

Science.gov (United States)

Hanf, Matthieu; Quantin, Catherine; Farrington, Paddy; Benzenine, Eric; Hocine, N Mounia; Velten, Michel; Tubert-Bitter, Pascale; Escolano, Sylvie

2013-12-02

In the French national health insurance information system (SNIIR-AM), routine records of health claimed reimbursements are linked to hospital admissions for the whole French population. The main focus of this work is the usability of this system for vaccine safety assessment programme. Self-controlled case series analyses were performed using an exhaustive SNIIR-AM extraction of French children aged less than 3 years, to investigate the relationship between MMR immunization and children hospitalizations for febrile convulsions, a well-documented rare adverse event, over 2009-2010. The results suggest a significant increase of febrile convulsions during the 6-11 days period following any MMR immunization (IRR=1.49, 95% CI=1.22, 1.83; p=0.0001) and no increase 15-35 days post any MMR immunization (IRR=1.03, 95% CI=0.89, 1.18; p=0.72). These results are in accordance with other results obtained from large epidemiologic studies, which suggest the usability of the SNIIR-AM as a relevant database to study the occurrence of adverse events associated with immunization. For future use, results associated with risk of convulsion during the day of vaccination should nevertheless be considered with particular caution. Copyright © 2013 Elsevier Ltd. All rights reserved.

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

International Nuclear Information System (INIS)

Hu, L.

2016-01-01

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

Nuclear safety research project (PSF). 1999 annual report

International Nuclear Information System (INIS)

Muehl, B.

2000-08-01

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

Experiment to evaluate software safety

International Nuclear Information System (INIS)

Soubies, B.; Henry, J.Y.

1994-01-01

The process of licensing nuclear power plants for operation consists of mandatory steps featuring detailed examination of the instrumentation and control system by the safety authorities, including softwares. The criticality of these softwares obliges the manufacturer to develop in accordance with the IEC 880 standard 'Computer software in nuclear power plant safety systems' issued by the International Electronic Commission. The evaluation approach, a two-stage assessment is described in detail. In this context, the IPSN (Institute of Protection and Nuclear Safety), the technical support body of the safety authority uses the MALPAS tool to analyse the quality of the programs. (R.P.). 4 refs

Methyltransferase Erm(37) Slips on rRNA to Confer Atypical Resistance in Mycobacterium tuberculosis

Czech Academy of Sciences Publication Activity Database

Madsen, Ch. T.; Jakobsen, L.; Buriánková, Karolína; Doucet-Populaire, F.; Perdonet, J. L.; Douthwaite, S.

2005-01-01

Roč. 280, č. 47 (2005), s. 38942-38947 ISSN 0021-9258 R&D Projects: GA ČR GA310/03/0292 Institutional research plan: CEZ:AV0Z50200510 Keywords : methyltransferase erm * mycobacterium tuberculosis * rRNA Subject RIV: EE - Microbiology, Virology Impact factor: 5.854, year: 2005

APROSYS: future safety needs actions today

NARCIS (Netherlands)

Schijndel-de Nooij, M. van

2008-01-01

Secondary (or passive) safety constitutes one of the most important strategies to reduce the traffic trauma problem. The European R&D needs in this field are partially dealt with in a large European co-operative R&D project called APROSYS (Advanced Protection Systems) supported by the European

Safety of Nuclear Power Plants: Design. Specific Safety Requirements (Russian Edition); Bezopasnost' atomnykh ehlektrostantsij: proektirovanie. Konkretnye trebovaniya bezopasnosti

Energy Technology Data Exchange (ETDEWEB)

NONE

2012-04-15

This publication is a revision of Safety Requirements No. NS-R-1, Safety of Nuclear Power Plants: Design. It establishes requirements applicable to the design of nuclear power plants and elaborates on the safety objective, safety principles and concepts that provide the basis for deriving the safety requirements that must be met for the design of a nuclear power plant. It will be useful for organizations involved in the design, manufacture, construction, modification, maintenance, operation and decommissioning of nuclear power plants, as well as for regulatory bodies. Contents: 1. Introduction; 2. Applying the safety principles and concepts; 3. Management of safety in design; 4. Principal technical requirements; 5. General plant design; 6. Design of specific plant systems.

46 CFR 151.03-21 - Filling density.

Science.gov (United States)

2010-10-01

... 46 Shipping 5 2010-10-01 2010-10-01 false Filling density. 151.03-21 Section 151.03-21 Shipping COAST GUARD, DEPARTMENT OF HOMELAND SECURITY (CONTINUED) CERTAIN BULK DANGEROUS CARGOES BARGES CARRYING BULK LIQUID HAZARDOUS MATERIAL CARGOES Definitions § 151.03-21 Filling density. The ratio, expressed as...

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

International Nuclear Information System (INIS)

Yoshikawa, Hidekazu

2004-01-01

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

Safety of Nuclear Power Plants: Commissioning and Operation

International Nuclear Information System (INIS)

2011-01-01

The safety of a nuclear power plant is ensured by means of proper site selection, design, construction and commissioning, and the evaluation of these, followed by proper management, operation and maintenance of the plant. In a later phase, a proper transition to decommissioning is required. The organization and management of plant operations ensures that a high level of safety is achieved through the effective management and control of operational activities. This publication is a revision of the Safety Requirements publication Safety of Nuclear Power Plants: Operation, which was issued in 2000 as IAEA Safety Standards Series No. NS-R-2. The purpose of this revision was to restructure Safety Standards Series No. NS-R-2 in the light of new operating experience and new trends in the nuclear industry; to introduce new requirements that were not included in Safety Standards Series No. NS-R-2 on the operation of nuclear power plants; and to reflect current practices, new concepts and technical developments. This update also reflects feedback on the use of the standards, both from Member States and from the IAEA's safety related activities. The publication is presented in the new format for Safety Requirements publications. The present publication reflects the safety principles of the Fundamental Safety Principles. It has been harmonized with IAEA Safety Standards Series No. GS-R-3 on The Management System for Facilities and Activities. Guidance on the fulfilment of the safety requirements is provided in supporting Safety Guides. The terminology used in this publication is defined and explained in the IAEA Safety Glossary. The objective of this publication is to establish the requirements which, in the light of experience and the present state of technology, must be satisfied to ensure the safe operation of nuclear power plants. These requirements are governed by the safety objective and safety principles that are established in the Fundamental Safety Principles. This

46 CFR 148.03-7 - During transport.

Science.gov (United States)

2010-10-01

... 46 Shipping 5 2010-10-01 2010-10-01 false During transport. 148.03-7 Section 148.03-7 Shipping COAST GUARD, DEPARTMENT OF HOMELAND SECURITY (CONTINUED) DANGEROUS CARGOES CARRIAGE OF SOLID HAZARDOUS MATERIALS IN BULK Minimum Transportation Requirements § 148.03-7 During transport. During the transport of a...

46 CFR 4.03-7 - Chemical test.

Science.gov (United States)

2010-10-01

... 46 Shipping 1 2010-10-01 2010-10-01 false Chemical test. 4.03-7 Section 4.03-7 Shipping COAST GUARD, DEPARTMENT OF HOMELAND SECURITY PROCEDURES APPLICABLE TO THE PUBLIC MARINE CASUALTIES AND INVESTIGATIONS Definitions § 4.03-7 Chemical test. The term chemical test means a scientifically recognized test...

46 CFR 26.03-10 - Signaling light.

Science.gov (United States)

2010-10-01

... 46 Shipping 1 2010-10-01 2010-10-01 false Signaling light. 26.03-10 Section 26.03-10 Shipping COAST GUARD, DEPARTMENT OF HOMELAND SECURITY UNINSPECTED VESSELS OPERATIONS Special Operating Requirements § 26.03-10 Signaling light. All vessels of over 150 gross tons, when engaged on an international...

Modernization of control instrumentation and security of reactor IAN - R1

International Nuclear Information System (INIS)

Gonzalez, J. M.

1993-01-01

The program to modernize IAN-R1 research reactor control and safety instrumentation has been carried out considering two main aspects: updating safety philosophy requirements and acquiring the newest reactor control instrumentation controlled by computer, following the present criteria internationally recognized, for safety and reliable reactor operations and the latest developments of nuclear electronic technology. The new IAN-R1 reactor instrumentation consist of two wide range neutron monitoring channels, commanded by microprocessor a data acquisition system and reactor control, (controlled by computers). The reactor control desk is providing through two displays; all safety and control signals to the reactor operators; furthermore some signals like reactor power, safety and period signals are also showed on digital bar graphics, which are hard wired directly from the neutron monitoring channels

Escherichia coli ArgR mutants defective in cer/Xer recombination, but not in DNA binding.

Science.gov (United States)

Sénéchal, Hélène; Delesques, Jérémy; Szatmari, George

2010-04-01

The Escherichia coli arginine repressor (ArgR) is an L-arginine-dependent DNA-binding protein that controls the expression of the arginine biosynthetic genes and is required as an accessory factor for Xer site-specific recombination at cer and related recombination sites in plasmids. We used the technique of pentapeptide scanning mutagenesis to isolate a series of ArgR mutants that were considerably reduced in cer recombination, but were still able to repress an argA::lacZ fusion. DNA sequence analysis showed that all of the mutants mapped to the same nucleotide, resulting in a five amino acid insertion between residues 149 and 150 of ArgR, corresponding to the end of the alpha6 helix. A truncated ArgR containing a stop codon at residue 150 displayed the same phenotype as the protein with the five amino acid insertion, and both mutants displayed sequence-specific DNA-binding activity that was L-arginine dependent. These results show that the C-terminus of ArgR is more important in cer/Xer site-specific recombination than in DNA binding.

Reliability and Maintainability Engineering - A Major Driver for Safety and Affordability

Science.gov (United States)

Safie, Fayssal M.

2011-01-01

The United States National Aeronautics and Space Administration (NASA) is in the midst of an effort to design and build a safe and affordable heavy lift vehicle to go to the moon and beyond. To achieve that, NASA is seeking more innovative and efficient approaches to reduce cost while maintaining an acceptable level of safety and mission success. One area that has the potential to contribute significantly to achieving NASA safety and affordability goals is Reliability and Maintainability (R&M) engineering. Inadequate reliability or failure of critical safety items may directly jeopardize the safety of the user(s) and result in a loss of life. Inadequate reliability of equipment may directly jeopardize mission success. Systems designed to be more reliable (fewer failures) and maintainable (fewer resources needed) can lower the total life cycle cost. The Department of Defense (DOD) and industry experience has shown that optimized and adequate levels of R&M are critical for achieving a high level of safety and mission success, and low sustainment cost. Also, lessons learned from the Space Shuttle program clearly demonstrated the importance of R&M engineering in designing and operating safe and affordable launch systems. The Challenger and Columbia accidents are examples of the severe impact of design unreliability and process induced failures on system safety and mission success. These accidents demonstrated the criticality of reliability engineering in understanding component failure mechanisms and integrated system failures across the system elements interfaces. Experience from the shuttle program also shows that insufficient Reliability, Maintainability, and Supportability (RMS) engineering analyses upfront in the design phase can significantly increase the sustainment cost and, thereby, the total life cycle cost. Emphasis on RMS during the design phase is critical for identifying the design features and characteristics needed for time efficient processing

Preliminary mini experiments on leaching of glass. A report of the situation 1979-03-15

International Nuclear Information System (INIS)

Blomqvist, G.

1979-04-01

The work performed within a project concerning preliminary mini experiments on the leaching of glass up to 1979-03-15 is summarized. It is shown that steady states are not obtained during one month for the investigated elements (Na, Cs, Sr, B) while the concentration of Ca in the leachate decreases to almost zero. The solubility of glass seems to be dependent on the volume. (E.R.)

Effect of amino acid sequence variations at position 149 on the fusogenic activity of the subtype B avian metapneumovirus fusion protein.

Science.gov (United States)

Yun, Bingling; Gao, Yanni; Liu, Yongzhen; Guan, Xiaolu; Wang, Yongqiang; Qi, Xiaole; Gao, Honglei; Liu, Changjun; Cui, Hongyu; Zhang, Yanping; Gao, Yulong; Wang, Xiaomei

2015-10-01

The entry of enveloped viruses into host cells requires the fusion of viral and cell membranes. These membrane fusion reactions are mediated by virus-encoded glycoproteins. In the case of avian metapneumovirus (aMPV), the fusion (F) protein alone can mediate virus entry and induce syncytium formation in vitro. To investigate the fusogenic activity of the aMPV F protein, we compared the fusogenic activities of three subtypes of aMPV F proteins using a TCSD50 assay developed in this study. Interestingly, we found that the F protein of aMPV subtype B (aMPV/B) strain VCO3/60616 (aMPV/vB) was hyperfusogenic when compared with F proteins of aMPV/B strain aMPV/f (aMPV/fB), aMPV subtype A (aMPV/A), and aMPV subtype C (aMPV/C). We then further demonstrated that the amino acid (aa) residue 149F contributed to the hyperfusogenic activity of the aMPV/vB F protein. Moreover, we revealed that residue 149F had no effect on the fusogenic activities of aMPV/A, aMPV/C, and human metapneumovirus (hMPV) F proteins. Collectively, we provide the first evidence that the amino acid at position 149 affects the fusogenic activity of the aMPV/B F protein, and our findings will provide new insights into the fusogenic mechanism of this protein.

Progress report I.R.S.N. 2003

International Nuclear Information System (INIS)

2003-01-01

This report is divided in six chapters. The first one is devoted to the safety of civil installations, transport and radioactive wastes. In this chapter we find the safety of PWR type reactors, the safety of Cabri reactor, ITER tokamak, the storage of radioactive waste and the criticality of packages with actinides. The second chapter concerns the protection of man and environment, we find the radiation monitoring of workers, the medical management of irradiated personnel, the radiation protection of nuclear power plants. The third chapter is relative to the national defense. The fourth chapter tackles the international relations and the part taken by I.R.S.N. in the Europe construction. The fifth chapter gives the contribution to public information, communication and training. The sixth and last chapter explains the quality policy at I.R.S.N. and how the management is made by a quality option. (N.C.)

ITER safety challenges and opportunities

International Nuclear Information System (INIS)

Piet, S.J.

1992-01-01

This paper reports on results of the Conceptual Design Activity (CDA) for the International Thermonuclear Experimental Reactor (ITER) suggest challenges and opportunities. ITER is capable of meeting anticipated regulatory dose limits, but proof is difficult because of large radioactive inventories needing stringent radioactivity confinement. Much research and development (R ampersand D) and design analysis is needed to establish that ITER meets regulatory requirements. There is a further oportunity to do more to prove more of fusion's potential safety and environmental advantages and maximize the amount of ITER technology on the path toward fusion power plants. To fulfill these tasks, three programmatic challenges and three technical challenges must be overcome. The first step is to fund a comprehensive safety and environmental ITER R ampersand D plan. Second is to strengthen safety and environment work and personnel in the international team. Third is to establish an external consultant group to advise the ITER Joint Team on designing ITER to meet safety requirements for siting by any of the Parties. The first of three key technical challenges is plasma engineering - burn control, plasma shutdown, disruptions, tritium burn fraction, and steady state operation. The second is the divertor, including tritium inventory, activation hazards, chemical reactions, and coolant disturbances. The third technical challenge is optimization of design requirements considering safety risk, technical risk, and cost

Safety-evaluation report related to renewal of the operating license for the Texas A and M University Research Reactor. Docket No. 50-128, License R-83

International Nuclear Information System (INIS)

1983-03-01

This Safety Evaluation Report for the application filed by the Texas A and M University (Texas A and M) for a renewal of operating license number R-83 to continue to operate a research reactor has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is owned and operated by the Texas Engineering and Experiment Station of the Texas A and M University and is located on the campus in College Station, Brazos County, Texas. The staff concludes that the TRIGA reactor facility can continue to be operated by Texas A and M University without endangering the health and safety of the public

Safety of Nuclear Power Plants: Commissioning and Operation. Specific Safety Requirements (Arabic Edition)

International Nuclear Information System (INIS)

2017-01-01

This publication is a revision of IAEA Safety Standards Series No. NS-R-2, Safety of Nuclear Power Plants: Operation, and has been extended to cover the commissioning stage. It describes the requirements to be met to ensure the safe commissioning, operation, and transition from operation to decommissioning of nuclear power plants. Over recent years there have been developments in areas such as long term operation of nuclear power plants, plant ageing, periodic safety review, probabilistic safety analysis review and risk informed decision making processes. It became necessary to revise the IAEA’s Safety Requirements in these areas and to correct and/or improve the publication on the basis of feedback from its application by both the IAEA and its Member States. In addition, the requirements are governed by, and must apply, the safety objective and safety principles that are established in the IAEA Safety Standards Series No. SF-1, Fundamental Safety Principles. A review of Safety Requirements publications, initiated in 2011 following the accident in the Fukushima Daiichi nuclear power plant in Japan, revealed no significant areas of weakness but resulted in a small set of amendments to strengthen the requirements and facilitate their implementation. These are contained in the present publication.

Safety Training: places available in October 2013

CERN Multimedia

Isabelle CUSATO, HSE Unit

2013-01-01

There are places available in the forthcoming Safety courses. For updates and registrations, please refer to the Safety Training Catalogue.   October 2013 (alphabetical order) Habilitation ATEX niveau 1 (ATEX habilitation level 1) 08-OCT-13, 9.00 – 17.30, in French Conduite de plates-formes élévatrices mobiles de personnel (PEMP) (Driving cherry-pickers) 21-OCT-13 to 22-OCT-13, 08.30 – 17.30, in French with handouts in English Ergonomics - Applying ergonomic principles in the workplace 03-OCT-13, 9.00 – 12.00, in English Être TSO au CERN (Being a TSO at CERN) 29-OCT-13 to 31-OCT-13, 9.00 – 17.30, in French Self-Rescue Mask Training 01-OCT-13, 10.30 – 12.30, in French 03-OCT-13, 10.30 – 12.30, in English 04-OCT-13, 8.30 – 10.30, in English 08-OCT-13, 10.30 – 12.30, in French 09-OCT-13, 10.30 – 12.30, in English 15-OCT-13, 10.30 – 12.30, in French 17-OCT-13, 10.30...

Safety and immunogenicity of rVSVΔG-ZEBOV-GP Ebola vaccine in adults and children in Lambaréné, Gabon: A phase I randomised trial

NARCIS (Netherlands)

Agnandji, Selidji T.; Fernandes, José F.; Bache, Emmanuel B.; Obiang Mba, Régis M.; Brosnahan, Jessica S.; Kabwende, Lumeka; Pitzinger, Paul; Staarink, Pieter; Massinga-Loembe, Marguerite; Krähling, Verena; Biedenkopf, Nadine; Fehling, Sarah Katharina; Strecker, Thomas; Clark, David J.; Staines, Henry M.; Hooper, Jay W.; Silvera, Peter; Moorthy, Vasee; Kieny, Marie-Paule; Adegnika, Akim A.; Grobusch, Martin P.; Becker, Stephan; Ramharter, Michael; Mordmüller, Benjamin; Lell, Bertrand; Krishna, Sanjeev; Kremsner, Peter G.

2017-01-01

The rVSVΔG-ZEBOV-GP vaccine prevented Ebola virus disease when used at 2 × 107 plaque-forming units (PFU) in a trial in Guinea. This study provides further safety and immunogenicity data. A randomised, open-label phase I trial in Lambaréné, Gabon, studied 5 single intramuscular vaccine doses of 3 ×

WE-G-BRA-03: Developing a Culture of Patient Safety Utilizing the National Radiation Oncology Incident Learning System (ROILS)

Energy Technology Data Exchange (ETDEWEB)

Hasson, B; Workie, D; Geraghty, C [Anne Arundel Medical Center, Annapolis, MD (United States)

2015-06-15

Purpose: To transition from an in-house incident reporting system to a ROILS standards system with the intent to develop a safety focused culture in the Department and enroll in ROILS. Methods: Since the AAPM Safety Summit (2010) several safety and reporting systems have been implemented within the Department. Specific checklists and SBAR reporting systems were introduced. However, the active learning component was lost due to reporting being viewed with distrust and possible retribution.To Facilitate introducing ROILS each leader in the Department received a copy of the ROILS participation guide. Four specific tasks were assigned to each leader: develop a reporting tree, begin the ROILS based system, facilitate adopting ROILS Terminology, and educate the staff on expectations of safety culture. Next, the ROILS questions were broken down into area specific questions (10–15) per departmental area. Excel spreadsheets were developed for each area and setup for error reporting entries. The Role of the Process Improvement Committee (PI) has been modified to review and make recommendations based on the ROILS entries. Results: The ROILS based Reporting has been in place for 4 months. To date 64 reports have been entered. Since the adoption of ROILS the reporting of incidents has increased from 2/month to 18/month on average. Three reports had a dosimetric effect on the patient (<5%) dose variance. The large majority of entries have been Characterized as Processes not followed or not sure how to Characterize, and Human Behavior. Conclusion: The majority of errors are typo’s that create confusion. The introduction of the ROILS standards has provided a platform for making changes to policies that increase patient safety. The goal is to develop a culture that sees reporting at a national level as a safe and effective way to improve our safety, and to dynamically learn from other institutions reporting.

WE-G-BRA-03: Developing a Culture of Patient Safety Utilizing the National Radiation Oncology Incident Learning System (ROILS)

International Nuclear Information System (INIS)

Hasson, B; Workie, D; Geraghty, C

2015-01-01

Purpose: To transition from an in-house incident reporting system to a ROILS standards system with the intent to develop a safety focused culture in the Department and enroll in ROILS. Methods: Since the AAPM Safety Summit (2010) several safety and reporting systems have been implemented within the Department. Specific checklists and SBAR reporting systems were introduced. However, the active learning component was lost due to reporting being viewed with distrust and possible retribution.To Facilitate introducing ROILS each leader in the Department received a copy of the ROILS participation guide. Four specific tasks were assigned to each leader: develop a reporting tree, begin the ROILS based system, facilitate adopting ROILS Terminology, and educate the staff on expectations of safety culture. Next, the ROILS questions were broken down into area specific questions (10–15) per departmental area. Excel spreadsheets were developed for each area and setup for error reporting entries. The Role of the Process Improvement Committee (PI) has been modified to review and make recommendations based on the ROILS entries. Results: The ROILS based Reporting has been in place for 4 months. To date 64 reports have been entered. Since the adoption of ROILS the reporting of incidents has increased from 2/month to 18/month on average. Three reports had a dosimetric effect on the patient (<5%) dose variance. The large majority of entries have been Characterized as Processes not followed or not sure how to Characterize, and Human Behavior. Conclusion: The majority of errors are typo’s that create confusion. The introduction of the ROILS standards has provided a platform for making changes to policies that increase patient safety. The goal is to develop a culture that sees reporting at a national level as a safe and effective way to improve our safety, and to dynamically learn from other institutions reporting

Safety-related LWR research. Annual report 1993

International Nuclear Information System (INIS)

Hueper, R.

1994-06-01

The reactor safety R and D work of the Karlsruhe Nuclear Research Centre (KfK) has been part of the Nuclear Safety Research Project (PSF) since 1990. The present annual report 1993 summarizes the results on LWR safety. The research tasks are coordinated in agreement with internal and external working groups. The contributions to this report correspond to the status at the end of 1993. (orig./HP) [de

Occupational Health and Safety Management and Turnover Intention in the Ghanaian Mining Sector.

Science.gov (United States)

Amponsah-Tawiah, Kwesi; Ntow, Michael Akomeah Ofori; Mensah, Justice

2016-03-01

The mining industry is considered as one of the most dangerous and hazardous industries and the need for effective and efficient occupational health and safety management is critical to safeguard workers and the industry. Despite the dangers and hazards present in the mining industry, only few studies have focused on how occupational health and safety and turnover intentions in the mines. The study suing a cross-sectional survey design collected quantitative data from the 255 mine workers that were conveniently sampled from the Ghanaian mining industry. The data collection tools were standardized questionnaires that measured occupational health and safety management and turnover intentions. These scales were also pretested before their usage in actual data collection. The correlation coefficient showed that a negative relationship existed between dimensions of occupational health and safety management and turnover intention; safety leadership (r = -0.33, p safety facilities and equipment (r = -0.32, p safety procedure (r = -0.27, p safety leadership and safety facility were significant predictors of turnover intention, (β = -0.28, p safety leadership in ensuring the effective formulation of policies and supervision of occupational health and safety at the workplace. The present study demonstrates that safety leadership is crucial in the administration of occupational health and safety and reducing turnover intention in organizations.

Development of RETRAN-03/MOV code for thermal-hydraulic analysis of nuclear reactor under moving conditions

International Nuclear Information System (INIS)

Kim, Hak Jae; Park, Goon Cherl

1996-01-01

Nuclear ship reactors have several; features different from land-based PWR's. Especially, effects of ship motions on reactor thermal-hydraulics and good load following capability for abrupt load changes are essential characteristics of nuclear ship reactors. This study modified the RETRAN-03 to analyze the thermal-hydraulic transients under three-dimensional ship motions, named RETRAN-03/MOV in order to apply to future marine reactors. First Japanese nuclear ship MUTSU reactor have been analyzed under various ship motions to verify this code. Calculations have been performed under rolling,heaving and stationary inclination conditions during normal operation. Also, the natural circulation has been analyzed, which can provide the decay heat removed to ensure the passive safety of marine reactors. As results, typical thermal-hydraulic characteristics of marine reactors such as flow rate oscillations and S/G water level oscillations have been successfully simulated at various conditions. 7 refs., 11 figs. (author)

High field induced magnetic transitions in the Y0.7E r0.3F e2D4.2 deuteride

Science.gov (United States)

Paul-Boncour, V.; Guillot, M.; Isnard, O.; Hoser, A.

2017-09-01

The influence of the partial Er for Y substitution on the crystal structure and magnetic properties of YF e2D4.2 has been investigated by high field magnetization and neutron diffraction experiments. Y0.7E r0.3F e2D4.2 compound crystallizes in the same monoclinic structure as YF e2D4.2 described in P c (P1c1) space group with D atoms located in 18 different tetrahedral interstitial sites. A cell volume contraction of 0.6% is observed upon Er substitution, inducing large modification of the magnetic properties. Electronic effect of D insertion as well as lowering of crystal symmetry are important factors determining the magnetic properties of Fe sublattice, which evolves towards more delocalized behavior and modifying the Er-Fe exchange interactions. In the ground state, the Er and Fe moments are arranged ferrimagnetically within the plane perpendicular to the monoclinic b axis and with average moments mEr=6.4 (3 ) μBEr-1 and mFe=2.0 (1 ) μBFe-1 at 10 K. Upon heating, mEr decreases progressively until TEr=55 K . Between 55 K and 75 K, the Fe sublattice undergoes a first-order ferromagnetic-antiferromagnetic (FM-AFM) transition with a cell volume contraction due to the itinerant metamagnetic behavior of one Fe site. In the AFM structure, mFe decreases until the Néel temperature TN=125 K . At high field, two different types of field induced transitions are observed. The Er moments become parallel to the Fe one and saturates to the E r3 + free ion value, leading to an unusual field induced FM arrangement at a transition field BTrans of only 78 kG below 30 K. Then above TM0=66 K , an AFM-FM transition of the Fe sublattice, accompanied by a cell volume increase is observed. BTrans increases linearly versus temperature and with a larger d BTrans/d T slope than for YF e2D4.2 . This has been explained by the additional contribution of Er induced moments above BTrans.

Synthesis and characterization by diffraction of X-Ray and impedance spectroscopy the ferroelectric ceramic Ti0.4Fe0.3Nb0.3O2 (TFNO) with additions of Bi2O3

International Nuclear Information System (INIS)

Sousa, D.G.; Sales, A.J.M.; Carneiro, J.C.S.; Sancho, E.O.; Sombra, A.S.B.; Sales, J.C.

2012-01-01

The ceramic Ti 0.4F e 0.3 Nb 0. 3O 2 (TFNO), was synthesized through of the solid-state reaction technique. The oxides were mixed for 7h and calcined at 1075 deg C for 4h. Phase TFNO was confirmed via X-ray diffraction technique (XRD) and Rietveld refinement. Were made additions of 6% and 8% of Bi 2 O 3 to the calcined powder, that after the pressing and sintering at 1125 deg C, were submitted to analysis by XRD and impedance spectroscopy study. The X-ray diffraction technique confirm a rutile-type structure [TiO2 (tP6) ] to calcined powder and to presence of two phases, Ti0.4Fe0.3Nb0.3O2 (TFNO tetragonal-rutile P 42/m n m(136)) and Bi1.721Fe1.056Nb1.134O7 (BFNO cubic F d -3 m Z(227)), for samples sintered. The impedance spectroscopy reveal in 240°C, to TFNO with addition of 8% at 100 KHz, the following results: σ' = 0,0452(Ω.m) -1 ; ε r ' = 9613 e tgδ = 0,83556. (author)

Performance of balanced bellows safety relief valves

International Nuclear Information System (INIS)

Lai, Y.S.

1992-01-01

By the nature of its design, the set point and lift of a conventional spring loaded safety relief valve are sensitive to back pressure. One way to reduce the adverse effects of the back pressure on the safety relief valve function is to install a balanced bellows in a safety relief valve. The metallic bellows has a rather wide range of manufacturing tolerance which makes the design of the bellows safety relief valve very complicated. The state-of-the-art balanced bellows safety relief valve can only substantially minimize, but cannot totally eliminate the back pressure effects on its set point and relieving capacity. Set point change is a linear function of the back pressure to the set pressure ratio. Depending on the valve design, the set point correction factor can be either greater or smaller than unity. There exists an allowable back pressure and critical back pressure for each safety relief valve. When total back pressure exceeds the R a , the relieving capacity will be reduced mainly resulting from the valve lift being reduced by the back pressure and the capacity reduction factor should be applied in valve sizing. Once the R c is exceeded, the safety relief valve becomes unstable and loses its over pressure protection capability. The capacity reduction factor is a function of system overpressure, but their relationship is non-linear in nature. (orig.)

r ben hassine - Bulletin of Materials Science | Indian Academy of ...

Indian Academy of Sciences (India)

Home; Journals; Bulletin of Materials Science. R BEN HASSINE. Articles written in Bulletin of Materials Science. Volume 40 Issue 1 February 2017 pp 79-85. Effect of Co substitution on the physicochemical properties of La 0.67 Sr 0.22 Ba 0.11 Mn 1 − x Co x O 3 compounds ( 0 ≤ x ≤ 0.3 ) · W CHERIF R BEN HASSINE J A ...

Long-term safety of growth hormone replacement therapy after childhood medulloblastoma and PNET: it is time to set aside old concerns.

Science.gov (United States)

Indini, Alice; Schiavello, Elisabetta; Biassoni, Veronica; Bergamaschi, Luca; Magni, Maria Chiara; Puma, Nadia; Chiaravalli, Stefano; Pallotti, Federica; Seregni, Ettore; Diletto, Barbara; Pecori, Emilia; Gandola, Lorenza; Poggi, Geraldina; Massimino, Maura

2017-01-01

To assess the long-term safety of administering growth hormone (GH) in patients with GH deficiency due to treatment for childhood medulloblastoma and primitive neuroectodermal tumor (PNET). Data were retrospectively retrieved on children receiving GH supplementation, assessing their disease-free and overall survival outcomes and risk of secondary malignancies using Kaplan-Meier and Cox models. Overall 65 children were consecutively collected from May 1981 to April 2013. All patients had undergone craniospinal irradiation (total dose 18-39 Gy), and subsequently received GH for a median (interquartile range, IQR) of 81 (50.6-114.9) months. At a median (IQR) of 122.4 months (74.4-149.5) after the end of their adjuvant cancer treatment, two patients (3 %) experienced recurrent disease and 8 (12.3 %) developed secondary malignancies, all but one of them (an osteosarcoma) related to radiation exposure and occurring within the radiation fields. There was no apparent correlation between the administration of GH replacement therapy (or its duration) and primary tumor relapse or the onset of secondary malignancies [HR: 1.01 (95 % CI: 0.98, 1.03) for every additional 12 months of GH supplementation; p = 0.36). At univariate analysis, the large cell or anaplastic medulloblastoma subtype, metastases and myeloablative chemotherapy correlated with a higher risk of secondary malignancies (p < 0.1), but multivariate analysis failed to identify any factors independently associated with this risk. Our data supports once more the safety of long-term GH replacement therapy in children treated for medulloblastoma/PNET, previously reported in larger data sets. The neurooncology community now need to warrant large-scale meta-analyses or international prospective trials in order to consolidate our knowledge of factors other than GH, such as genetic predisposition, high-grade/metastatic disease, high-dose chemotherapy and era of treatment, in promoting the occurrence of

Subcutaneously administered Menopur(R, a new highly purified human menopausal gonadotropin, causes significantly fewer injection site reactions than Repronex(R in subjects undergoing in vitro fertilization

Directory of Open Access Journals (Sweden)

Somkuti Stephen

2005-11-01

Full Text Available Abstract Background The safety and tolerability of a new highly purified, urine-derived human menopausal gonadotropin (hMG preparation [Menopur(R] was compared with a currently available hMG [Repronex (R] in women undergoing in vitro fertilization (IVF. Methods This was a randomized, open-label, parallel-group, multicenter study conducted in subjects undergoing IVF. Women (N = 125, 18–39 years of age, underwent pituitary down-regulation with leuprolide acetate beginning 7 days prior to onset of menses and continuing up to the day before hCG administration. Subjects were randomized to receive subcutaneous (SC Menopur (R (n = 61 or Repronex (R SC (n = 64 for a maximum of 12 days. All adverse events (AEs were recorded and subject self-assessments of injection site reactions were recorded in a daily diary. Results Significantly fewer subjects in the Menopur (R group reported injection site reactions (P Conclusion Menopur (R SC offers a greater safety and tolerability profile compared to Repronex (R SC.

Commissioning of research reactors. Safety guide

International Nuclear Information System (INIS)

2006-01-01

The objective of this Safety Guide is to provide recommendations on meeting the requirements for the commissioning of research reactors on the basis of international best practices. Specifically, it provides recommendations on fulfilling the requirements established in paras 6.44 and 7.42-7.50 of International Atomic Energy Agency, Safety of Research Reactors, IAEA Safety Standards Series No. NS-R-4, IAEA, Vienna (2005) and guidance and specific and consequential recommendations relating to the recommendations presented in paras 615-621 of International Atomic Energy Agency, Safety in the Utilization and Modification of Research Reactors, Safety Series No. 35-G2, IAEA, Vienna (1994) and paras 228-229 of International Atomic Energy Agency, Safety Assessment of Research Reactors and Preparation of the Safety Analysis Report, Safety Series No. 35-G1, IAEA, Vienna (1994). This Safety Guide is intended for use by all organizations involved in commissioning for a research reactor, including the operating organization, the regulatory body and other organizations involved in the research reactor project

Converse Theorems for Safety and Barrier Certificates

Czech Academy of Sciences Publication Activity Database

Ratschan, Stefan

Online 11 January 2018. (2018) ISSN 0018-9286 R&D Projects: GA ČR GA15-14484S Institutional support: RVO:67985807 Keywords : Safety * Robustness * Radio frequency * Differential equations * Tools * Computer science * Controllability Subject RIV: IN - Informatics, Computer Science Impact factor: 4.270, year: 2016

Regulatory control of radiation sources. Safety guide

International Nuclear Information System (INIS)

2004-01-01

The basic requirements for the protection of persons against exposure to ionizing radiation and for the safety of radiation sources were established in the International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources (the Basic Safety Standards), jointly sponsored by the Food and Agriculture Organization of the United Nations (FAO), the International Atomic Energy Agency (IAEA), the International Labour Organization (ILO), the OECD Nuclear Energy Agency (OECD/ NEA), the Pan American Health Organization (PAHO) and the World Health Organization (WHO) (the Sponsoring Organizations). The application of the Basic Safety Standards is based on the presumption that national infrastructures are in place to enable governments to discharge their responsibilities for radiation protection and safety. Requirements relating to the legal and governmental infrastructure for the safety of nuclear facilities and sources of ionizing radiation, radiation protection, the safe management of radioactive waste and the safe transport of radioactive material are established in the Safety Requirements on Legal and Governmental Infrastructure for Nuclear, Radiation, Radioactive Waste and Transport Safety, Safety Standards Series No. GS-R-1. This Safety Guide, which is jointly sponsored by the FAO, the IAEA, the International Labour Office, the PAHO and the WHO, gives detailed guidance on the key elements for the organization and operation of a national regulatory infrastructure for radiation safety, with particular reference to the functions of the national regulatory body that are necessary to ensure the implementation of the Basic Safety Standards. The Safety Guide is based technically on material first published in IAEA-TECDOC-10671, which was jointly sponsored by the FAO, the IAEA, the OECD/NEA, the PAHO and the WHO. The requirements established in GS-R-1 have been taken into account. The Safety Guide is oriented towards national

Health and safety plan for operations performed for the Environmental Restoration Program. Task, OU 1-03 and OU 4-10 Track 2 investigations

Energy Technology Data Exchange (ETDEWEB)

Trippet, W.A. II [IT Corp., (United States); Reneau, M.; Morton, S.L. [EG and G Idaho, Inc., Idaho Falls, ID (United States)

1992-04-01

This document constitutes the generic health and safety plan for the Environmental Restoration Program (ERP). It addresses the health and safety requirements of the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA); Occupational Safety and Health Administration (OSHA) 29 CFR 1910.120 standard; and EG&G Idaho, Inc. This plan is a guide to individuals who must complete a health and safety plan for a task performed for the EPR. It contains a task specific addendum that, when completed, specifically addresses task specific health and safety issues. This health and safety plan reduces the time it takes to write a task specific health and safety plan by providing discussions of requirements, guidance on where specific information is located, and specific topics in the Addendum that must be discussed at a task level. This format encourages a complete task specific health and safety plan and a standard for all health and safety plans written for ERP.

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.

Safety and Health Division achievements during 40 years

International Nuclear Information System (INIS)

Noriah Mod Ali

2012-01-01

During her speech, presenter outlined several issues regarding on establishment of Safety and Health Division since 40 years. This division contain of 3 sub unit; Physical Safety Group, Medical Physic Group and Non-ionizing Radiation group (NIR). The objectives of this division to implement R and D activities and services regarding safety and radiological health also non-radiological to ensure public safety, environment and asset suit with obligations established by authorities, IAEA standards and regulations.(author)

Safety update on the use of recombinant activated factor VII in approved indications.

Science.gov (United States)

Neufeld, Ellis J; Négrier, Claude; Arkhammar, Per; Benchikh el Fegoun, Soraya; Simonsen, Mette Duelund; Rosholm, Anders; Seremetis, Stephanie

2015-06-01

This updated safety review summarises the large body of safety data available on the use of recombinant activated factor VII (rFVIIa) in approved indications: haemophilia with inhibitors, congenital factor VII (FVII) deficiency, acquired haemophilia and Glanzmann's thrombasthenia. Accumulated data up to 31 December 2013 from clinical trials as well as post-marketing data (registries, literature reports and spontaneous reports) were included. Overall, rFVIIa has shown a consistently favourable safety profile, with no unexpected safety concerns, in all approved indications. No confirmed cases of neutralising antibodies against rFVIIa have been reported in patients with congenital haemophilia, acquired haemophilia or Glanzmann's thrombasthenia. The favourable safety profile of rFVIIa can be attributed to the recombinant nature of rFVIIa and its localised mechanism of action at the site of vascular injury. Recombinant FVIIa activates factor X directly on the surface of activated platelets, which are present only at the site of injury, meaning that systemic activation of coagulation is avoided and the risk of thrombotic events (TEs) thus reduced. Nonetheless, close monitoring for signs and symptoms of TE is warranted in all patients treated with any pro-haemostatic agent, including rFVIIa, especially the elderly and any other patients with concomitant conditions and/or predisposing risk factors to thrombosis. Copyright © 2015 Elsevier Ltd. All rights reserved.

Development of an Asymbiotic Reference Line for Pea cv. Bohatýr by De Novo Mutagenesis

Czech Academy of Sciences Publication Activity Database

Novák, Karel; Šlajs, Martin; Biedermannová, Eva; Vondrys, Josef

2005-01-01

Roč. 45, - (2005), s. 1837-1843 ISSN 0011-183X R&D Projects: GA ČR GA521/00/0937; GA ČR GA521/03/0192 Institutional research plan: CEZ:AV0Z50200510 Keywords : mutagenesis * bohatýr * nitrogen fixation Subject RIV: EE - Microbiology, Virology Impact factor: 0.925, year: 2005

Eighth ITER technical meeting on safety and environment

International Nuclear Information System (INIS)

Gordon, C.; Raeder, J.

2000-01-01

From November 27 to 30, 2000 the Eighth ITER Technical Meeting on Safety and Environment was held by the ITER Joint Central Team (JCT) at the Garching Joint Work Site, which also hosts the ITER Safety, Environment and Health Group (SEHG). At this meeting, safety experts from the Home Teams (HT) worked together with the SEHG members towards the following main objectives: review of Generic Site Safety Report (GSSR) results and drafts; review of the Plant Design Description (PDD) summary of safety; update on the status of the R and D tasks contributing to GSSR

Flow around a horizontal cylinder and its effect on local scour in an open channel

Czech Academy of Sciences Publication Activity Database

Vlasák, Pavel; Chára, Zdeněk

1999-01-01

Roč. 363, - (1999), s. 51-60 ISSN 0867-7964. [Conference on "Safety and Durability of Hydrotechnic Structures" /2./. Kamien Slaski, 03.11.1999-05.11.1999] R&D Projects: GA AV ČR IAA2060701; GA ČR GA103/97/0860 Subject RIV: BK - Fluid Dynamics

NEA activities in safety and regulation

International Nuclear Information System (INIS)

Stadie, K.B.

1983-01-01

The NEA programme on Safety and Regulations is briefly reviewed. It encompasses four main areas - nuclear safety technology; nuclear licensing; radiation protection; and waste management - with three principal objectives: to promote exchanges of technical information in order to enlarge the data base for national decision making; to improve co-ordination of national R and D activities with emphasis on international standard problem exercises, and to promote international projects; to develop common technical, administrative and legal approaches to improve compatibility of safety and regulatory practices

Human papillomavirus 16/18 AS04-adjuvanted cervical cancer vaccine: immunogenicity and safety in 15-25 years old healthy Korean women

OpenAIRE

Kim, Seung Cheol; Song, Yong Sang; Kim, Young-Tae; Kim, Young Tak; Ryu, Ki-Sung; Gunapalaiah, Bhavyashree; Bi, Dan; Bock, Hans L; Park, Jong-Sup

2011-01-01

Objective The study assessed the immunogenicity and safety of human papillomavirus (HPV)-16/18 AS04-adjuvanted cervical cancer vaccine in healthy Korean women aged 15-25 years. Methods Phase IIIB, double-blind, randomised (2:1), multi-centre trial was conducted in Korea from June 2007 to March 2008. The study enrolled 225 women in the HPV (N=149) and placebo (N=76) groups who received three doses of HPV-16/18 AS04-adjuvanted vaccine or placebo (aluminium hydroxide) administered intramuscularl...

22 CFR 231.03 - The Guarantee.

Science.gov (United States)

2010-04-01

... 22 Foreign Relations 1 2010-04-01 2010-04-01 false The Guarantee. 231.03 Section 231.03 Foreign Relations AGENCY FOR INTERNATIONAL DEVELOPMENT ARAB REPUBLIC OF EGYPT LOAN GUARANTEES ISSUED UNDER THE EMERGENCY WARTIME SUPPLEMENTAL APPROPRIATIONS ACT OF 2003, PUBLIC LAW 108-11-STANDARD TERMS AND CONDITIONS...

40 CFR 413.03 - Monitoring requirements.

Science.gov (United States)

2010-07-01

... 40 Protection of Environment 28 2010-07-01 2010-07-01 true Monitoring requirements. 413.03 Section 413.03 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) EFFLUENT GUIDELINES AND... for total toxic organics (TTO), I certify that, to the best of my knowledge and belief, no dumping of...

Safety, feasibility and efficacy of a rapid ART initiation in pregnancy ...

African Journals Online (AJOL)

Safety, feasibility and efficacy of a rapid ART initiation in pregnancy pilot programme in Cape Town, South Africa. S Black, R Zulliger, L Myer, R Marcus, S Jeneker, R Taliep, D Pienaar, R Wood, L-G Bekker ...

Situation analysis of physical independence of the equipment and safety circuits of Almaraz NPP regarding R.G. 1.75 rev.3 (2005); Analisis de la situacion de la independencia fisica de los equipos y circuitos electricos de seguridad de C. N. Almaraz respecto a la R. G. 1.75 rev 3 (2005)

Energy Technology Data Exchange (ETDEWEB)

Seijas Portela, S.

2010-07-01

Situation analysis of physical independence of the electrical equipment and circuits CN safety Almaraz about R.G. 1.75 rev. 3. (2005) The aim of this paper is to present the work done in the analysis of the physical separation of redundant safety electrical equipment (emergency diesel generators, medium voltage, electrical cabinets, etc.) and physical separation of circuits and electrical conduits.

Molecular cloning and anti-invasive activity of cathepsin L propeptide-like protein from Calotropis procera R. Br. against cancer cells.

Science.gov (United States)

Kwon, Chang Woo; Yang, Hee; Yeo, SuBin; Park, Kyung-Min; Jeong, Ae Jin; Lee, Ki Won; Ye, Sang-Kyu; Chang, Pahn-Shick

2018-12-01

Cathepsin L of cancer cells has been shown to play an important role in degradation of extracellular matrix for metastasis. In order to reduce cell invasion, cathepsin L propeptide-like proteins which are classified as the I29 family in the MEROPS peptidase database were characterized from Calotropis procera R. Br., rich in cysteine protease. Of 19 candidates, the cloned and expressed recombinant SnuCalCp03-propeptide (rSnuCalCp03-propeptide) showed a low nanomolar K i value of 2.3 ± 0.2 nM against cathepsin L. A significant inhibition of tumor cell invasion was observed with H1975, HT29, MDA-BM-231, PANC1, and PC3 with a 76, 67, 67, 63, and 79% reduction, respectively, in invasion observed in the presence of 400 nM of the rSnuCalCp03-propeptide. In addition, thermal and pH study showed rSnuCalCp03-propeptide consisting of secondary structures was stable at a broad range of temperatures (30-70 °C) and pH (2-10, except for 5 which is close to the isoelectric point of 5.2).

A high precision n-p scattering measurement at 14.9 MeV

Directory of Open Access Journals (Sweden)

Kornilov N.V.

2017-01-01

Full Text Available The n-p scattering angular distribution was measured with 14.9 MeV incident neutrons using the traditional time-of-flight technique with neutron-gamma discrimination. The scattering angle varied from 20o to 65o (laboratory system in 5o incremental steps. The efficiency of the neutron detectors was measured in the energy range 2–9 MeV relative to the 252Cf-standard, and was calculated using Monte Carlo methods in the 2–14 MeV energy range. Two methods of analysis were applied for experimental and simulated data: a traditional approach with a fixed threshold, and a dynamic threshold approach. The present data agree with the ENDF/B-VII evaluation for the shape of n-p angular distribution within about 1.5%.

ERGONOMICS AND ROAD SAFETY

NARCIS (Netherlands)

BROOKHUIS, K; BROWN, [No Value

1992-01-01

Modifications to the design of vehicles and road infrastructures have improved road safety significantly over the past decades, but all such developments depend upon user acceptance and institutional backing for their success. New R&D programmes combining ergonomic and engineering approaches are

Advances in industrial ergonomics and safety II

Energy Technology Data Exchange (ETDEWEB)

Das, B [ed.; Technical University of Nova Scotia, Halifax, NS (Canada). Dept. of Industrial Engineering

1990-01-01

135 papers were presented at the conference in 20 sessions with the following headings: aging and industrial performance; back injury and rehabilitation; bioinstrumentation and electromyography; cumulative trauma disorders; engineering anthropometry; equipment design and ergonomics; human computer interaction; human performance and worker satisfaction; human strength and testing; industrial accidents and prevention; industrial biomechanics; injuries in health care; manual materials handling; noise and vibration effects; occupational health and safety; robotics and agricultural machinery safety; statistics and modelling in ergonomics; work environment; workplace safety analysis; and workstation design. Papers are included entitled: A model for analyzing mining machine illumination systems' by R.L. Unger, A.F. Glowacki and E.W. Rossi, 'Ergonomic design guidelines for underground coal mining equipment by E.J. Conway and R. Unger, and Hot work environment and human strain - a relation proposed by K. Bhattacharya and S. Raja.

Advances in industrial ergonomics and safety II

Energy Technology Data Exchange (ETDEWEB)

Das, B. (ed.) (Technical University of Nova Scotia, Halifax, NS (Canada). Dept. of Industrial Engineering)

1990-01-01

135 papers were presented at the conference in 20 sessions with the following headings: aging and industrial performance; back injury and rehabilitation; bioinstrumentation and electromyography; cumulative trauma disorders; engineering anthropometry; equipment design and ergonomics; human computer interaction; human performance and worker satisfaction; human strength and testing; industrial accidents and prevention; industrial biomechanics; injuries in health care; manual materials handling; noise and vibration effects; occupational health and safety; robotics and agricultural machinery safety; statistics and modelling in ergonomics; work environment; workplace safety analysis; and workstation design. Papers are included entitled: A model for analyzing mining machine illumination systems' by R.L. Unger, A.F. Glowacki and E.W. Rossi, 'Ergonomic design guidelines for underground coal mining equipment by E.J. Conway and R. Unger, and Hot work environment and human strain - a relation proposed by K. Bhattacharya and S. Raja.

2018-03-19T03:09:40Z https://www.ajol.info/index.php/all/oai oai:ojs ...

African Journals Online (AJOL)

article/83194 2018-03-19T03:09:40Z joafss:ART Urban forests and sustainable livelihoods in port Harcourt City, Nigeria Larinde, SL Ogunniyan, DJ Biodiversity conservation; sustainable development; urbanization; urban forestry Depletion of the ...

46 CFR 199.03 - Relationship to international standards.

Science.gov (United States)

2010-10-01

... 46 Shipping 7 2010-10-01 2010-10-01 false Relationship to international standards. 199.03 Section 199.03 Shipping COAST GUARD, DEPARTMENT OF HOMELAND SECURITY (CONTINUED) LIFESAVING APPLIANCES AND ARRANGEMENTS LIFESAVING SYSTEMS FOR CERTAIN INSPECTED VESSELS General § 199.03 Relationship to international...

Simple synthesis of graphene nanocomposites MgO-rGO and Fe2O3-rGO for multifunctional applications

Science.gov (United States)

Abdel-Aal, Seham K.; Ionov, Andrey; Mozhchil, R. N.; Naqvi, Alim H.

2018-05-01

Hummer's method was used to prepare graphene oxide (GO) by chemical exfoliation of graphite. Simple precipitation method was used for the preparation of hybrid nanocomposites MgO-rGO and Fe2O3-rGO. A 0.3 Molar of corresponding metal nitrate solution and GO solution are used for the preparation process. XRD, FT-IR, and XPS were used to characterize the prepared nanocomposites. The reduction of GO into reduced rGO in the formed nanocomposites was confirmed. Morphological characterization showed the formation of needle-shaped nanocrystals of MgO successfully grown on graphene nanosheet with average crystallite size 8.4 nm. Hematite nanocomposite Fe2O3-rGO forms rod-shaped crystals with average crystallite size 27.5 nm. The saturation magnetization observed for Fe2O3-rGO is less than reported value for the pure Fe2O3 nanoparticles. Thermal properties of as-prepared hybrid nanocomposites MgO-rGO and Fe2O3-rGO showed thermal stability of the prepared nanocomposite over long range of temperature.

Illumination and Voltage Dependence of Electrical Characteristics of Au/0.03 Graphene-Doped PVA/n-Si Structures via Capacitance/Conductance-Voltage Measurements

International Nuclear Information System (INIS)

Sahar, Alialy; Şlemsettin, Altındal; Ahmet, Kaya; İ, Uslu

2015-01-01

Au/n-Si (MS) structures with a high dielectric interlayer (0.03 graphene-doped PVA) are fabricated to investigate the illumination and voltage effects on electrical and dielectric properties by using capacitance-voltage (C-V) and conductance-voltage (G/ω-V) measurements at room temperature and at 1 MHz. Some of the main electrical parameters such as concentration of doping atoms (N D ), barrier height (ϕ B (C - V)), depletion layer width (W D ) and series resistance (R s ) show fairly large illumination dispersion. The voltage-dependent profile of surface states (N ss ) and resistance of the structure (R i ) are also obtained by using the dark-illumination capacitance (C dark -C ill ) and Nicollian-Brews methods, respectively. For a clear observation of changes in electrical parameters with illumination, the values of N D , W D , ϕ B (C - V) and R s are drawn as a function of illumination intensity. The values of N D and W D change almost linearly with illumination intensity. On the other hand, R s decreases almost exponentially with increasing illumination intensity whereas ϕ B (C - V) increases. The experimental results suggest that the use of a high dielectric interlayer (0.03 graphene-doped PVA) considerably passivates or reduces the magnitude of the surface states. The large change or dispersion in main electrical parameters can be attributed to generation of electron-hole pairs in the junction under illumination and to a good light absorption. All of these experimental results confirm that the fabricated Au/0.03 graphene-doped PVA/n-Si structure can be used as a photodiode or a capacitor in optoelectronic applications. (paper)

46 CFR 133.03 - Relationship to international standards.

Science.gov (United States)

2010-10-01

... 46 Shipping 4 2010-10-01 2010-10-01 false Relationship to international standards. 133.03 Section 133.03 Shipping COAST GUARD, DEPARTMENT OF HOMELAND SECURITY (CONTINUED) OFFSHORE SUPPLY VESSELS LIFESAVING SYSTEMS General § 133.03 Relationship to international standards. This subpart and subpart B of...

2018-03-28T03:12:24Z https://www.ajol.info/index.php/all/oai oai:ojs ...

African Journals Online (AJOL)

article/68491 2018-03-28T03:12:24Z wsa:ART Characterisation of the inorganic chemistry of surface waters in South Africa Huizenga, JM Inorganic water chemistry, inorganic chemistry index, South Africa, surface waters The main purpose of this ...

Safety of Nuclear Power Plants: Design. Specific Safety Requirements (Spanish Edition); Seguridad de las centrales nucleares: Diseno. Requisitos de seguridad especificos

Energy Technology Data Exchange (ETDEWEB)

NONE

2012-04-15

This publication is a revision of Safety Requirements No. NS-R-1, Safety of Nuclear Power Plants: Design. It establishes requirements applicable to the design of nuclear power plants and elaborates on the safety objective, safety principles and concepts that provide the basis for deriving the safety requirements that must be met for the design of a nuclear power plant. It will be useful for organizations involved in the design, manufacture, construction, modification, maintenance, operation and decommissioning of nuclear power plants, as well as for regulatory bodies. Contents: 1. Introduction; 2. Applying the safety principles and concepts; 3. Management of safety in design; 4. Principal technical requirements; 5. General plant design; 6. Design of specific plant systems.

Validating the Danish adaptation of the World Health Organization's International Classification for Patient Safety classification of patient safety incident types

DEFF Research Database (Denmark)

Mikkelsen, Kim Lyngby; Thommesen, Jacob; Andersen, Henning Boje

2013-01-01

Objectives Validation of a Danish patient safety incident classification adapted from the World Health Organizaton's International Classification for Patient Safety (ICPS-WHO). Design Thirty-three hospital safety management experts classified 58 safety incident cases selected to represent all types.......513 (range: 0.193–0.804). Kappa and ICC showed high correlation (r = 0.99). An inverse correlation was found between the prevalence of type and inter-rater reliability. Results are discussed according to four factors known to determine the inter-rater agreement: skill and motivation of raters; clarity...

Modular high-temperature gas-cooled reactor simulation using parallel processors

International Nuclear Information System (INIS)

Ball, S.J.; Conklin, J.C.

1989-01-01

The MHPP (Modular HTGR Parallel Processor) code has been developed to simulate modular high-temperature gas-cooled reactor (MHTGR) transients and accidents. MHPP incorporates a very detailed model for predicting the dynamics of the reactor core, vessel, and cooling systems over a wide variety of scenarios ranging from expected transients to very-low-probability severe accidents. The simulations routines, which had originally been developed entirely as serial code, were readily adapted to parallel processing Fortran. The resulting parallelized simulation speed was enhanced significantly. Workstation interfaces are being developed to provide for user (operator) interaction. In this paper the benefits realized by adapting previous MHTGR codes to run on a parallel processor are discussed, along with results of typical accident analyses

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African Journals Online (AJOL)

article/53157 2018-03-29T05:36:03Z ijbcs:ART Biodiversity and ethnobotanical potentials of plant species of University of Agriculture Makurdi Wildlife Park and Ikwe Games Reserve, Benue State, Nigeria Jimoh, S.O Debisi, L Ikyaagba, E.T Plant ...

7 CFR 1540.2 - Definitions.

Science.gov (United States)

2010-01-01

... 7 Agriculture 10 2010-01-01 2010-01-01 false Definitions. 1540.2 Section 1540.2 Agriculture Regulations of the Department of Agriculture (Continued) FOREIGN AGRICULTURAL SERVICE, DEPARTMENT OF..., 146.91, 147.03 through 147.33, 147.50 through 149.21 and 149.50 of the TSUS; (5) Fresh cut flowers...

Proceedings of the seminar on nuclear safety research and the workshop on reactor safety research

International Nuclear Information System (INIS)

2001-07-01

The seminar on the nuclear safety research was held on November 20, 2000 according to the start of new five year safety research plan (FY2001-2005: established by Nuclear Safety Commission) with 79 participants. In the seminar, Commissioner Dr. Kanagawa gave the outline of the next five year safety research plan. Following this presentation, progresses and future scopes of safety researches in the fields of reactor facility, fuel cycle facility, radioactive waste and environmental impact on radiation at Japan Atomic Energy Research Institute (JAERI) were reported. After the seminar, the workshop on reactor safety research was held on November 21-22, 2000 with 141 participants. In the workshop, four sessions titled safety of efficient and economic utilization of nuclear fuel, safety related to long-term utilization of power reactors, research on common safety-related issues and toward further improvement of nuclear safety were organized and, outcomes and future perspectives in these wide research R and D in the related area at other organizations including NUPEC, JAPEIC and Kansai Electric Power Co. was presented in each session. This report compiles outlines of the presentations and used materials in the seminar and the workshop to form the proceedings for the both meetings. (author)

Safety philosophy and licensing practice in different member states of IAEA: Germany, F.R

International Nuclear Information System (INIS)

Lahner, K.

1981-01-01

The safety philosophy, as the basis of the design of a NPP, will be shown under the aspects of general design rules, requirements by law, reactor safety commission and nuclear or conventional technical standards. Then a discussion of the licensing practise in the Federal Republic of Germany and in the USA will follow for the different stages of conceptual design, construction and operation with special consideration of the example of the NPP Muelheim-Kaerlich. The interrelation between designer and licensing authority, reactor safety commission and technical consultants will be taken into account. (orig./RW)

Reactor safety research - results and perspectives

International Nuclear Information System (INIS)

Banaschik, M.

1989-01-01

The work performed so far is an essential contribution to the determination of the safety margins of nuclear facilities and their systems and to the further development of safety engineering. The further development of safety engineering involves a shift of emphasis in reactor safety research towards event sequences beyond the design basis. The aim of this shift in emphasis is the further development of the preventive level. This is based on the fact that the conservative design of the operating and safety systems involves and essential safety potential. The R and D work is intended to help develop accident management measures and to take the plant back into the safe state even after severe accidents. In this context, it is necessary to make full use of the safety margins of the plant and to include the operating systems for coping with accidents. As a result of the aims, the research work approaches operating and plant-specific processes. (orig./DG) [de