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Agathokleous, Evgenios; Kitao, Mitsutoshi; Calabrese, Edward J., E-mail: evgenios@ffpri.affrc.go.jp, E-mail: kitao@ffpri.affrc.go.jp, E-mail: edwardc@schoolph.umass.edu2018
AbstractAbstract
[en] Highlights: • Autophagy is activated in the framework of hormesis. • Low doses of stressors promote health and extend lifespan. • Health can be maximized via calorie restriction and intermittent fasting. • Hormesis can protect against aging diseases and exogenous environmental stresses. • Hormesis provides a perspective for enhancing community health and patient success. It has long been debated whether a little stress may be “good” for you. Extensive evidence has now sufficiently accumulated demonstrating that low doses of a vast range of chemical and physical agents induce protective/beneficial effects while the opposite occurs at higher doses, a phenomenon known as hormesis. Low doses of environmental agents have recently induced autophagy, a critical adaptive response that protects essentially all cell types, as well as being transgenerational via epigenetic mechanisms. These collective findings highlight a generalized and substantial ongoing dose-response transformation with significant implications for disease biology and clinical applications, challenging the history and practice of toxicology and pharmacology along with an appeal to stake holders to reexamine the process of risk assessment, with the goal of optimizing public health rather than simply avoiding harm.
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S0013935118302366; Available from http://dx.doi.org/10.1016/j.envres.2018.04.034; Copyright (c) 2018 Elsevier Inc. All rights reserved.; Country of input: International Atomic Energy Agency (IAEA)
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AbstractAbstract
[en] Probabilistic safety assessment plays an important role in nuclear technology and other branches of industry. This methodological approach allows optimization of installations with regard to their reliability and technical safety both during planning and operation, in a logical and understandable manner. It also lends itself to the assessment of technical safety in the context of licensing procedures. Despite the obvious strongpoints of the procedure, it is still be set with misconceptions, ambiguities and misinterpretations, as one can tell from discussions about PSA and its use in practice. The article is intended to bring to the reader's awareness and, if possible, eliminate these false notions, which curb the practical value of PSA. (orig./MP)
[de]
Die probabilistische Sicherheitsbewertung hat in der Kerntechnik und in anderen Industrien einen bedeutsamen Stellenwert. Mit dieser Methodik lassen sich Anlagen logisch schluessig und gut nachvollziehbar, sowohl im Entwurf als auch bei der Betriebsfuehrung, zuverlaessigkeits- und sicherheitstechnisch optimieren und auch im Genehmigungsverfahren sicherheitstechnisch bewerten. Trotz dieser offensichtlichen Staerken des Verfahrens, ist beim praktischen Umgang mit und in der Diskussion ueber die PSA viel Unverstandenes, Missverstaendnis und Fehlinterpretiertes wahrzunehmen. Der Beitrag soll dazu dienen, solche, den praktischen Nutzen der PSA behindernde Fehleinschaetzungen bewusst zu machen und moeglichst auszuraeumen. (orig./HP)Original Title
Probabilistische Sicherheitsbewertung
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Dogan, B.; Maskell, R.V.; Webster, S.E.
Societe Francaise d'Energie Nucleaire (SFEN), 75 - Paris (France)2001
Societe Francaise d'Energie Nucleaire (SFEN), 75 - Paris (France)2001
AbstractAbstract
[en] The direct industrial need for a validated defect assessment procedure stems from a requirement of safe plant operation with extended component life, and improved decision making processes in run/repair/replace situations. To this end, structural integrity assessment is carried out by the power generation and offshore engineering sectors and finds acceptance world wide. It is also addressed by other industrial sectors including chemical and process engineering. During the last decade, a number of fracture mechanics based low temperature assessment procedures have been developed within Europe and worldwide. Guidelines and methodologies for high temperature assessment also exist within several European countries. This means that there is a significant number of procedures available for use in plants. This report identifies the procedures, for both high and low temperatures, which are most commonly used by EU Thematic Network Project PLAN partners both in their projects and in their respective organisations. It is followed by a comparison of the available defect assessment procedures in the light of recent progress made in collaborative programmes of EC Projects. The present work identifies issues associated with defect assessment procedures, and thus forms a contribution to the assessment of service performance of engineering structures at both low and high temperatures, which is the aim of the PLAN Cluster Task ''Defect Assessment Procedures''. (author)
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2001; [1 p.]; 9. international conference on nuclear engineering; Nice Acropolis (France); 8-12 Apr 2001
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Miscellaneous
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AbstractAbstract
[en] The question arises where there is the limit between the scope of minimizing the residual risk and the residual risk that is accepted. The necessity of minimizing the residual risk is balanced against the acceptable residual risk. (orig.)
[de]
Es stellt sich die Frage nach der Abgrenzung zwischen dem Bereich der Restrisikominimierung und dem hingenommenen Restrisiko. (orig.)Original Title
Zur Regelung der Gefahrenabwehr bei Kernenergieanlagen in der deutschen Rechtsordnung
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Energiewirtschaftliche Tagesfragen; ISSN 0013-743X;
; v. 33(6); p. 392-395

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AbstractAbstract
[en] It is proved that a nodal quartic threefold X containing no planes is Q-factorial if it has at most 12 singular points. An exception here is a quartic with precisely 12 singularities containing a quadric surface. Some geometric constructions relating to such a quartic are presented. Bibliography: 14 titles.
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Available from http://dx.doi.org/10.1070/SM2007v198n08ABEH003878; Country of input: International Atomic Energy Agency (IAEA)
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Journal Article
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Sbornik. Mathematics; ISSN 1064-5616;
; v. 198(8); p. 1165-1174

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Krommes, J.A.
Princeton Plasma Physics Lab., Princeton, NJ (United States). Funding organisation: USDOE Office of Science (United States)2009
Princeton Plasma Physics Lab., Princeton, NJ (United States). Funding organisation: USDOE Office of Science (United States)2009
AbstractAbstract
[en] Recent assertions that guiding-center theory breaks down at second order for 3D magnetic fields with nonzero torsion are argued to be incorrect.
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29 May 2009; 6 p; ACO2-09CH11466; Also available from OSTI as DE00953486; PURL: https://www.osti.gov/servlets/purl/953486-hvFecA/; doi 10.2172/953486
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Report
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AbstractAbstract
[en] This fourth part concerns the radioisotopes and includes: the risks bound to the production and the medical and industrial use of radioisotopes, the regulation of the users of ionizing radiation and the relevance of the experience of nuclear facility operators in litigation, problems relative to the medial, scientific and industrial use of radioelements, standards and rules in the use of radioactive sources in medical sector in Brazil. (N.C.)
Original Title
Radioelements
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Association Internationale du Droit Nucleaire, 75 - Paris (France); 583 p; ISBN 2-908199-10-6;
; 1998; p. 335-416; Congress on the nuclear law: from the 20. to the 21. century; Congres sur le droit nucleaire du 20. au 21. siecle; Tours (France); 14-19 Sep 1997

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Book
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Mueller, K.
Industrieanlagen-Betriebsgesellschaft m.b.H., Ottobrunn (Germany, F.R.). Hauptabteilung Systemstudien; Bundesministerium des Innern, Bonn (Germany, F.R.); Gesellschaft fuer Reaktorsicherheit m.b.H. (GRS), Garching (Germany, F.R.)1983
Industrieanlagen-Betriebsgesellschaft m.b.H., Ottobrunn (Germany, F.R.). Hauptabteilung Systemstudien; Bundesministerium des Innern, Bonn (Germany, F.R.); Gesellschaft fuer Reaktorsicherheit m.b.H. (GRS), Garching (Germany, F.R.)1983
AbstractAbstract
[en] The report on hand presents possible applications of a project planning and coordination system for projects concerning the nuclear fuel cycle, with special regard to waste management. The relevant licencing procedures applied to said projects as well as basic elements of project planning systems, e.g. project structure plan, ''milestone-plan'' and network plan are dealt with in this report. For the licensing procedure under atomic law, a possible project structure is indicated. Furthermore, processes and occurances to be considered in the elaboration of particular network plans are listed. In addition, particulars for the schedules degree of specifications are given. To round up the report, recommendations are given for future lines of proceeding in the introduction of computer-aided information systems for use in projets on the nuclear fuel cycle. (orig.)
[de]
In dem vorliegenden Bericht werden Anwendungsmoeglichkeiten fuer ein Projekt-Planungs- und Steuerungssystem bei Projekten des nuklearen Brennstoffkreislaufes, insbesondere bei der Entsorgung, vorgestellt. Neben einer Darstellung des Ablaufes der wesentlichen Genehmigungsverfahren, die bei den behandelten Projekten zur Anwendung kommen, beschreibt der Bericht die grundlegenden Elemente von Projektplanungssystemen wie Projektstrukturplan, Meilensteinplan und Netzplan. Fuer das atomrechtliche Genehmigungsverfahren wird eine moegliche Projektstruktur angegeben, weiterhin werden Vorgaenge und Ereignisse benannt, die bei der Erarbeitung von Einzelnetzplaenen Beruecksichtigung finden sollten. Ergaenzend dazu werden Angaben fuer den zeitbezogenen Detaillierungsgrad gemacht. Der Bericht schliesst ab mit Empfehlungen zur weiteren Vorgehensweise bei der Einfuehrung eines rechnergestuetzten Informationssystems fuer Projekte des nuklearen Brennstoffkreislaufes. (orig.)Original Title
Untersuchung zum Einsatz von rechnergestuetzten Informationssystemen bei Planung und Steuerung von Projekten des nuklearen Brennstoffkreislaufes
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5 Oct 1983; 46 p; CONTRACT SR 240/80 808 UA 197; 361 9160 00/361 7707 00; Available from Industrieanlagen-Betriebsgesellschaft m.b.H., Ottobrunn (Germany, F.R.); With 1 tab., 7 figs.
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Gegusch, M.
Physical protection of nuclear materials: Experience in regulation, implementation and operations. Proceedings of a conference1998
Physical protection of nuclear materials: Experience in regulation, implementation and operations. Proceedings of a conference1998
AbstractAbstract
[en] The trustworthiness test is an important part of securing nuclear facilities against internal offenders. For performing such a test the supervisory authority, which is the State's physical protection authority, contacts the security offices or authorities regarding persons who work inside the sensitive areas of nuclear power stations - areas containing nuclear material. The trustworthiness test covers the present activities of the employees and gives a prediction for the following five years; after this time the test must be repeated. The trustworthiness test is a prerequisite for a facility to obtain a licence for the use of nuclear material, to hire persons for work in the inner area of a nuclear facility or the hire persons for leading positions. In Germany the content and form of the test as well as the evaluation of the results are regulated in a guideline of the Federal Ministry for the Environment, Nature Conservation and Reactor Safety (BMU) (latest edition in June 1996). The test is performed by the licensing authority or the supervisory authority. the basis of the test is a declaration by the employee concerned, containing personal data and the agreement of the person to the use of the data files by the safety authorities. It the results of the test are positive, the person tested has the possibility to comment on differences or to explain certain facts. The paper presents details of the BMU guideline. (author)
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International Atomic Energy Agency, Vienna (Austria); 527 p; ISBN 92-0-101398-1;
; 1998; p. 305-309; Conference on physical protection of nuclear materials: Experience in regulation, implementation and operations; Vienna (Austria); 10-14 Nov 1997; IAEA-CN--68/16; ISSN 0074-1884;
; 1 tab


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A.T. Watkins
Yucca Mountain Project, Las Vegas, Nevada (United States). Funding organisation: US Department of Energy (United States)1999
Yucca Mountain Project, Las Vegas, Nevada (United States). Funding organisation: US Department of Energy (United States)1999
AbstractAbstract
[en] This design feature (DF) is intended to evaluate the effects of continuous ventilation in the emplacement drifts during preclosure and how the effects, if any, compare to the Viability Assessment (VA) reference design for postclosure long term performance. This DF will be evaluated against a set of criteria provided by the License Application Design Selection (LADS) group. The VA reference design included a continuous ventilation airflow quantity of 0.1 m3/s in the emplacement drifts in the design of the repository subsurface facilities. The effects of this continuous ventilation during the preclosure was considered to have a negligible effect on postclosure performance and therefore is not included during postclosure in the assessment of the long term performance. This DF discusses the effects of continuous ventilation on the emplacement drift environment and surrounding rock conditions during preclosure for three increased airflow quantities. The three cases of continuous ventilation systems are: System A, 1.0 m3/s (Section 8), System B, 5.0 m3/s (Section 9), and System C, 10.0 m3/s (Section 10) in each emplacement drift split. An emplacement drift split is half total length of emplacement drift going from the east or west main to the exhaust main. The difference in each system is the quantity of airflow in the emplacement drifts
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22 Jun 1999; 193 p; MOL.19990621.0145, DC#21990; AC08-91RW00134; Also available from OSTI as DE00759853; PURL: https://www.osti.gov/servlets/purl/759853-J1jP7k/webviewable/; PBD: 22 Jun 1999
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