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Odrinsky, A. P., E-mail: odra@mail333.com
AbstractAbstract
[en] The features of the DLTS detection of defects with retrappability of thermally excited carriers due to a large value of effective capture cross section are considered. Indications allowing identification of the implementation of the given model are found.
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Copyright (c) 2011 Pleiades Publishing, Ltd.; Country of input: International Atomic Energy Agency (IAEA)
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Journal Article
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Bauer, T.H.; Wright, A.E.; Robinson, W.R.; Klickman, A.E.
Argonne National Lab., IL (USA)
Argonne National Lab., IL (USA)
AbstractAbstract
[en] Results and analyses are reported for TREAT in-pile transient overpower tests of margin to cladding failure and pre-failure axial expansion of metallic fuel. In all cases the power rise was exponential on an 8 s period until either incipient or actual cladding failure was achieved. Test fuel included EBR-II driver fuel and ternary alloy, the reference fuel of the Intergral Fast Reactor concept. Test pin burnup spanned the widest range available. The nature of the observed cladding failure and resultant fuel dispersals is described. Simple models are presented which describe observed cladding failures and pre-failure axial expansions yet are general enough to apply to all metal fuel types
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1988; 6 p; Safety of next generation power reactors; Seattle, WA (USA); 1-6 May 1988; Available from NTIS, PC A02/MF A01 as TI88010042
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Report
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Conference
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ACCIDENTS, AIR COOLED REACTORS, ENERGY SOURCES, ENRICHED URANIUM REACTORS, EXPERIMENTAL REACTORS, FUELS, GAS COOLED REACTORS, GRAPHITE MODERATED REACTORS, HOMOGENEOUS REACTORS, MATERIALS, REACTOR ACCIDENTS, REACTOR MATERIALS, REACTORS, RESEARCH AND TEST REACTORS, SOLID HOMOGENEOUS REACTORS, TEST FACILITIES, TEST REACTORS, THERMAL REACTORS
Publication YearPublication Year
Reference NumberReference Number
INIS VolumeINIS Volume
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Bovalini, R.; D'Auria, F.; Mazzini, M.; Vigni, P.
Univ. of Pisa (Italy)
Research Facilities for the Future of Nuclear Energy
Univ. of Pisa (Italy)
Research Facilities for the Future of Nuclear Energy
AbstractAbstract
[en] After outlining main characteristics of PIPER-ONE facility (a BWR thermalhydraulic simulator) the paper describes the results already achieved, as well as research perspectives
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Ait Abderrahim, H. (ed.); Centre d'Etude de l'Energie Nucleaire, Mol (Belgium); 557 p; 1996; p. 314-321; Research Facilities for the Future of Nuclear Energy; Brussels (Belgium); 4-6 Jun 1996; Available from World Scientific Publishing Co. Pte. Ltd., P O Box 128, Farrer Road, Singapore 912805
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Book
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Conference
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Aartsen, M. G.; Ackermann, M.; Adams, J.; Aguilar, J. A.; Ahlers, M.
Lawrence Berkeley National Laboratory (LBNL), Berkeley, CA (United States). National Energy Research Scientific Computing Center (NERSC). Funding organisation: USDOE Office of Science - SC (United States)
Lawrence Berkeley National Laboratory (LBNL), Berkeley, CA (United States). National Energy Research Scientific Computing Center (NERSC). Funding organisation: USDOE Office of Science - SC (United States)
AbstractAbstract
No abstract available
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OSTIID--1564007; AC02-05CH11231; Available from https://www.osti.gov/servlets/purl/1564007; DOE Accepted Manuscript full text, or the publishers Best Available Version will be available free of charge after the embargo period
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Journal Article
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Physical Review Letters; ISSN 0031-9007;
; v. 122(5); vp

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External URLExternal URL
AbstractAbstract
No abstract available
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5. particle accelerator conference; San Francisco, California, USA; 5 Mar 1973; See CONF-730310--.
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Journal Article
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Conference
Journal
IEEE (Inst. Elec. Electron. Eng.), Trans. Nucl. Sci; v. NS-20(3); p. 960-962
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Sim, Suk ku; Kim, Hee Kyung; Kim, Hee Cheol
Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)
Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)
AbstractAbstract
[en] TASS 1.0 is consisted of two parts. First part analyze the reactor transients and calculates system parameters during the transients. This part comprises the program of the primary and secondary thermal hydraulic model, the core model, the transfer model, the protection and the control system. The second part is the TASS executive routine. This part provides an operating system for TASS. The user can execute TASS with above models interactively through the TASS executive routine. But TASS executive routine is very large and the function is restricted. The development of GRIS( Graphical Routines for Interactive Simulation) was initiated to overcome the limitation of the TASS executive routine. TASS-NPA was developed based on GRIS. TASS-NPA simulation can be performed on Windows 95 and Window Nt of IBM Pc. The verification of the TASS-NPA function was performed with the Feed Water Line Break of Kori 3/4. (Author). 6 refs., 3 tabs., 26 figs
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Mar 1999; 42 p
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Report
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Horak, C.; Purvis, E. III
Unusual occurrences during LMFR operation. Proceedings of a technical committee meeting
Unusual occurrences during LMFR operation. Proceedings of a technical committee meeting
AbstractAbstract
[en] An examination has been made of how the currently available computing capabilities could be used to reduce Liquid Metal Fast Reactor design, manufacturing, and construction cost. While the examination focused on computer analyses some other promising means to reduce costs were also examined. (author)
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International Atomic Energy Agency, Vienna (Austria); 253 p; ISSN 1011-4289;
; Oct 2000; p. 229-240; Technical committee meeting on unusual occurrences during LMFR operation; Vienna (Austria); 9-13 Nov 1998; 12 figs

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Abo, S.; Mizutani, M.; Nakayama, K.; Takaoka, T.; Iwamatsu, T.; Yamaguchi, Y.; Maegawa, S.; Nishimura, T.; Kinomura, A.; Horino, Y.; Takai, M., E-mail: takai@rcem.osaka-u.ac.jp
AbstractAbstract
[en] Suppression of the floating body effects in partially depleted SOI-MOSFETs (silicon-on-insulator metal oxide semiconductor field effect transistors) with and without body contact electrodes has been investigated using nuclear microprobes with currents of 5-250 pA. Transient SOI-MOSFET behavior with and without body contact electrodes during ion irradiation by three-dimensional computer simulation has also been compared with that using nuclear microprobes. The floating body effects were observed in SOI-MOSFETs without body contact electrodes by nuclear microprobe irradiation, while those were suppressed in the SOI-MOSFETs with body contacts
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S0168583X0100489X; Copyright (c) 2001 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.; Country of input: International Atomic Energy Agency (IAEA)
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Journal Article
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Nuclear Instruments and Methods in Physics Research. Section B, Beam Interactions with Materials and Atoms; ISSN 0168-583X;
; CODEN NIMBEU; v. 181(1-4); p. 320-323

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AbstractAbstract
No abstract available
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Published in summary form only; Letter-to-the-editor.
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Journal of Nuclear Materials; ISSN 0022-3115;
; v. 107(2/3); p. 331-333

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AbstractAbstract
[en] Transient testing is critical for understanding how new fuels perform in accident conditions such as transient overpower and/or under cooling events. In February of 2014, The U.S. Department of Energy (DOE) determined that a Finding of No Significant Impact (FONSI) was appropriate for the resumption of transient testing of nuclear fuels and materials. At that point, work began on the restart of the Transient Reactor Test Facility (TREAT), which was the DOE preferred alternative for reestablishing transient testing capability for nuclear fuels and materials in the U.S. Significant progress has been made in the restart of TREAT for transient testing since the FONSI in 2014. The progress made since 2014 towards restarting TREAT and the current status is documented in this summary. (author)
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2016 ANS Winter Meeting and Nuclear Technology Expo; Las Vegas, NV (United States); 6-10 Nov 2016; Country of input: France; 2 refs.; available from American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (US)
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Transactions of the American Nuclear Society; ISSN 0003-018X;
; v. 115; p. 1393-1396

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ACCIDENTS, AIR COOLED REACTORS, ENERGY SOURCES, ENRICHED URANIUM REACTORS, EXPERIMENTAL REACTORS, FUELS, GAS COOLED REACTORS, GRAPHITE MODERATED REACTORS, HOMOGENEOUS REACTORS, MATERIALS, REACTOR ACCIDENTS, REACTOR LIFE CYCLE, REACTOR MATERIALS, REACTORS, RESEARCH AND TEST REACTORS, SOLID HOMOGENEOUS REACTORS, START-UP, TEST FACILITIES, TEST REACTORS, THERMAL REACTORS
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