Filters
Results 1 - 10 of 12381
Results 1 - 10 of 12381.
Search took: 0.031 seconds
| Sort by: date | relevance |
[en] This paper presents an overview of modelling features of the first revision of the V2.1 major version of the European severe accident integral code ASTEC which has been set-up by IRSN and delivered to the ASTEC worldwide community end of 2016. After some generalities concerning the software structure and the packaging of ASTEC V2.1 revision 1, the phenomena addressed by the different modules constitutive of ASTEC are detailed. Finally, perspectives as concerns the development of future versions of ASTEC V2.1 at IRSN are outlined. (author)
Source
International Atomic Energy Agency, Nuclear Power Technology Development Section, Vienna (Austria); [1 CD-ROM]; ISBN 978-92-0-102919-5; 
; ISSN 1011-4289; ; Jul 2019; p. 217-231; IAEA Technical Meeting on the Status and Evaluation of Severe Accident Simulation Codes for Water Cooled Reactors; Vienna (Austria); 9-12 Oct 2017; Also available on-line: https://www.iaea.org/publications/13536/status-and-evaluation-of-severe-accident-simulation-codes-for-water-cooled-reactors?supplementary=63997 and on 1 CD-ROM attached to the printed IAEA-TECDOC-1872; Enquiries should be addressed to IAEA, Marketing and Sales Unit, Publishing Section, E-mail: sales.publications@iaea.org; Web site: http://www.iaea.org/books; 23 refs., 2 figs.
; ISSN 1011-4289; ; Jul 2019; p. 217-231; IAEA Technical Meeting on the Status and Evaluation of Severe Accident Simulation Codes for Water Cooled Reactors; Vienna (Austria); 9-12 Oct 2017; Also available on-line: https://www.iaea.org/publications/13536/status-and-evaluation-of-severe-accident-simulation-codes-for-water-cooled-reactors?supplementary=63997 and on 1 CD-ROM attached to the printed IAEA-TECDOC-1872; Enquiries should be addressed to IAEA, Marketing and Sales Unit, Publishing Section, E-mail: sales.publications@iaea.org; Web site: http://www.iaea.org/books; 23 refs., 2 figs.
[en] Conclusion: IVR is one of important severe accident management strategies of CAP1400. The purpose of IVR-ERVC experiments is to obtain CHF at RPV lower head and research its relevant mechanism. IVR-ERVC experiment facility was designed and built with a series of improvements. Insights achieved in IVR-ERVC experiments contribute to IVR evaluation, design improvement and safety review of CAP1400.
Source
International Atomic Energy Agency, Safety Assessment Section, Vienna (Austria); vp; ISBN 978-92-0-106320-5; ; ISSN 1011-4289; ; May 2020; 40 p; Technical Meeting on Phenomenology and Technologies Relevant to In-Vessel Melt Retention and Ex-Vessel Corium Cooling; Shanghai (China); 17-21 Oct 2016; Also available on-line: https://www.iaea.org/publications/13576/in-vessel-melt-retention-and-ex-vessel-corium-cooling; Enquiries should be addressed to IAEA, Marketing and Sales Unit, Publishing Section, E-mail: sales.publications@iaea.org; Web site: http://www.iaea.org/books
; ISSN 1011-4289; ; May 2020; 40 p; Technical Meeting on Phenomenology and Technologies Relevant to In-Vessel Melt Retention and Ex-Vessel Corium Cooling; Shanghai (China); 17-21 Oct 2016; Also available on-line: https://www.iaea.org/publications/13576/in-vessel-melt-retention-and-ex-vessel-corium-cooling; Enquiries should be addressed to IAEA, Marketing and Sales Unit, Publishing Section, E-mail: sales.publications@iaea.org; Web site: http://www.iaea.org/books
[en] The experience from the last 40 years has shown that severe accidents can subject electrical and instrumentation and control (I&C) equipment to environmental conditions exceeding the equipment’s original design basis assumptions. Severe accident conditions can then cause rapid degradation or damage to various degrees up to complete failure of such equipment. This publication provides the technical basis to consider when assessing the capability of electrical and I&C equipment to perform reliably during a severe accident. It provides examples of calculation tools to determine the environmental parameters as well as examples and methods that Member States can apply to assess equipment reliability.
Source
Jul 2017; 127 p; ISBN 978-92-0-104917-9; ; ISSN 1011-4289; ; Also available on-line: http://www-pub.iaea.org/MTCD/Publications/PDF/TE-1818_web.pdf; Enquiries should be addressed to IAEA, Marketing and Sales Unit, Publishing Section, E-mail: sales.publications@iaea.org; Web site: http://www.iaea.org/books; Refs., figs., tabs.
; ISSN 1011-4289; ; Also available on-line: http://www-pub.iaea.org/MTCD/Publications/PDF/TE-1818_web.pdf; Enquiries should be addressed to IAEA, Marketing and Sales Unit, Publishing Section, E-mail: sales.publications@iaea.org; Web site: http://www.iaea.org/books; Refs., figs., tabs.
[en] Recent literature has included many papers on the costs of nuclear accidents. The French Nuclear Energy Society (SFEN) considered that it had become relevant to help establish a structured analysis, so that studies can be compared and some meaning given to results which appear often very different. In this document, we address the economic consequences of a severe nuclear accident occurring within a nuclear power plant, i.e. an accident classified as level 6 or 7 on the International Nuclear Event Scale (INES). This paper explains the main factors used to calculate the costs of accidents. It reviews the notion of overall cost, which is generally established in a not fully consistent way. It also suggests organizing the results of studies according to their characteristics and the questions they set out to answer. It shows current limitations of studies in which the probability of occurrence of the accidents whose consequences are being studied is not calculated or even addressed in a qualitative way. (author)
Source
Societe Francaise d'Energie Nucleaire - SFEN, 103 rue Reaumur, 75002 Paris (France); 2455 p; ISBN 978-1-4951-6286-2; ; 2015; p. 212-217; GLOBAL 2015: Nuclear fuel cycle for a low-carbon future; Paris (France); 21-24 Sep 2015; Available (USB stick) from: SFEN, 103 rue Reaumur, 75002 Paris (France); 20 refs.
; 2015; p. 212-217; GLOBAL 2015: Nuclear fuel cycle for a low-carbon future; Paris (France); 21-24 Sep 2015; Available (USB stick) from: SFEN, 103 rue Reaumur, 75002 Paris (France); 20 refs.
[en] Experimental study on the thermal fragmentation of melt, including Sn, Pb and Sn-Pb alloy, has been carried out based on the SSFT (Small-Scale Fragmentation Tests) facility. The effects of the melt properties, release distance, initial melt temperature, and coolant temperature on the thermal fragmentation have been studied. By analyzing the debris characteristics and the distribution, several specific thermal fragmentation mechanisms have been given, corresponding to different parameters. Finally, a partition map of thermal fragmentation mechanisms has been drawn based on the previous work. (authors)
Journal
Nuclear Power Engineering; ISSN 0258-0926; ; v. 37(2); p. 171-174
; v. 37(2); p. 171-174
[en] Response activities are important parts of both safety and security activities as a layer of defence, if prevention activities fail and deviation from compliance has been detected. Three levels of response can be differentiated based on the expected occurrence frequency of the event, its actual or potential consequences, and the scope of the involvement of various organizations. The operative level response to most frequently occurring, the least serious events requires efforts mainly from the operator by strictly following the routine procedures developed in advance; however, their repetition may attract the attention of the regulator and initiate enforcement actions. Examples for such events are the anticipated operational occurrences, expected failures of equipment, false and nuisance alarms, certain less serious unintentional or intentional human errors. Joint response with the involvement of more internal organizational units and competent authorities is needed to manage more serious events, which still have no unacceptable radiological consequences. Such events are accidents within and beyond the design basis, security events within the design basis threat. The response actions to those events are developed in advance and described in detail in the emergency operating procedures, severe accident management guidelines and the security contingency plans. The third and most severe level of response is needed, if unacceptable radiological consequences may or do appear on-site and off-site the facility, when the emergency response plans and if appropriate the contingency plans shall be implemented. (author)
Source
International Atomic Energy Agency, Division of Nuclear Security, Vienna (Austria); [1 CD-ROM]; ISBN 978-92-0-107017-3; ; Sep 2017; 6 p; International Conference on Nuclear Security: Commitments and Actions; Vienna (Austria); 5-9 Dec 2016; IAEA-CN--244/141; ISSN 0074-1884; ; Also available on-line: http://www-pub.iaea.org/books/iaeabooks/12238/International-Conference-on-Nuclear-Security-Commitments-and-Actions and on 1 CD-ROM attached to the printed STI/PUB/1794 from IAEA, Marketing and Sales Unit, Publishing Section, E-mail: sales.publications@iaea.org; Web site: http://www.iaea.org/books; Includes PowerPoint presentation; 7 refs., 1 tab.
; Sep 2017; 6 p; International Conference on Nuclear Security: Commitments and Actions; Vienna (Austria); 5-9 Dec 2016; IAEA-CN--244/141; ISSN 0074-1884; ; Also available on-line: http://www-pub.iaea.org/books/iaeabooks/12238/International-Conference-on-Nuclear-Security-Commitments-and-Actions and on 1 CD-ROM attached to the printed STI/PUB/1794 from IAEA, Marketing and Sales Unit, Publishing Section, E-mail: sales.publications@iaea.org; Web site: http://www.iaea.org/books; Includes PowerPoint presentation; 7 refs., 1 tab.
| 1 | 2 | 3 | Next |