Filters
Results 1 - 10 of 5451
Results 1 - 10 of 5451.
Search took: 0.036 seconds
Sort by: date | relevance |
AbstractAbstract
[en] Published in summary form only
Original Title
Codigo Forist
Secondary Subject
Source
Instituto de Engenharia Nuclear (IEN), Rio de Janeiro, RJ (Brazil); 279 p; 1984; p. 23
Record Type
Miscellaneous
Report Number
Country of publication
LanguageLanguage
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Larson, G.F.
Hanford Engineering Development Lab., Richland, WA (USA)1984
Hanford Engineering Development Lab., Richland, WA (USA)1984
AbstractAbstract
[en] This software package provides a worksheet environment for calculating fire duration and severity based on the method outlined by T.J. Harmathy as presented in his two part paper on compartment fires. This software is intended to aid engineers in designing facilities, ventilation systems, and process systems by allowing combustible loading ''what-ifs'' to be evaluated
Primary Subject
Source
Sep 1984; 42 p; Annual meeting of the American Nuclear Society; Boston, MA (USA); 9-14 Jun 1985; CONF-850610--50; Available from NTIS MF A01; 2 as DE85018213
Record Type
Report
Literature Type
Conference
Report Number
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
No abstract available
Primary Subject
Source
Israel Nuclear Society, Yavne; Israel Health Physics Society; Radiation Research Society of Israel; Israel Society of Nuclear Medicine; 228 p; 1982; p. 124-127; Nuclear Societies of Israel joint annual meeting; Tel Aviv (Israel); 14-15 Dec 1982; Published in summary form only.
Record Type
Miscellaneous
Literature Type
Conference
Report Number
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Mercier, C.
Association Euratom-CEA, Centre d'Etudes Nucleaires de Fontenay-aux-Roses, 92 (France). Groupe de Recherches sur la Fusion Controlee; CEA Centre d'Etudes Nucleaires de Fontenay-aux-Roses, 92 (France). Dept. de Physique du Plasma et de la Fusion Controlee1976
Association Euratom-CEA, Centre d'Etudes Nucleaires de Fontenay-aux-Roses, 92 (France). Groupe de Recherches sur la Fusion Controlee; CEA Centre d'Etudes Nucleaires de Fontenay-aux-Roses, 92 (France). Dept. de Physique du Plasma et de la Fusion Controlee1976
AbstractAbstract
[en] The Fontenay numerical code of toroidal discharges is presented. The empirical rules and transport coefficients used in order to fit the experimental data are explained, and a few examples of application are given. A simplified study of the transport equations in the steady state is presented, it gives precise details about the functional form of the transport coefficients and justifies the empirical coefficients used
[fr]
On presente le code numerique Fontenay des decharges toroidales. On explique les regles empiriques utilisees et les coefficients de transport utilises pour l'ajustement des donnees experimentales et on donne quelques exemples d'application. On presente une etude simplifiee des equations du transport dans l'etat stationnaire qui donne des details precis sur la forme fonctionnelle des coefficients de transport et justifie la forme des coefficients empiriques employesPrimary Subject
Source
Feb 1976; 28 p
Record Type
Report
Report Number
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Donnelly, J.V.
Atomic Energy of Canada Ltd., Chalk River, Ontario. Chalk River Nuclear Labs1985
Atomic Energy of Canada Ltd., Chalk River, Ontario. Chalk River Nuclear Labs1985
AbstractAbstract
[en] FISS is a computer code for use in investigating alternative fuel cycle strategies, performing system simulations accounting for the dynamic effects in growing systems. The changes that have been made to the original FISS program reported in AECL-5814 are described
Primary Subject
Secondary Subject
Source
Nov 1985; 21 p
Record Type
Report
Report Number
Country of publication
Reference NumberReference Number
Related RecordRelated Record
INIS VolumeINIS Volume
INIS IssueINIS Issue
Evans, L.E.
Atomic Energy of Canada Ltd., Chalk River, Ontario. Chalk River Nuclear Labs.1974
Atomic Energy of Canada Ltd., Chalk River, Ontario. Chalk River Nuclear Labs.1974
AbstractAbstract
No abstract available
Primary Subject
Source
Mar 1974; 45 p; Contains computer program description.
Record Type
Report
Report Number
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] Studsvik Nuclear of Sweden has developed a process code that can simulate internal fuel rod behaviour as a function of a nuclear reactor's power history. The Fuel Rod Performance Simulator (FRPS), has two versions: batch and interactive. Interpin, the batch version, produces results as listings or graphs; the interactive code, Simsim, steps through a power history under user control and instantly evaluates and displays the internal state of the fuel rod at each time step. Both run on minicomputers and PCs using EGA graphics. A third version is used as one of the modules in the Studsvik Compact Simulator. Here the FRPS received the dynamic inputs from the simulator. (author)
Primary Subject
Record Type
Journal Article
Journal
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Sitnik, I.M., E-mail: sitnik@sunhe.jinr.ru
Veksler and Baldin Lab., Joint Inst. for Nuclear Research, Dubna (Russian Federation)2010
Veksler and Baldin Lab., Joint Inst. for Nuclear Research, Dubna (Russian Federation)2010
AbstractAbstract
[en] FUMILI renovation-2 (FUMILIM) is suggested which has the following advantages: a more convenient and friendly user interface; no restriction to the number of parameters and experimental points; speed advantage when the number of parameters is high enough; a possibility to define analytically an arbitrary number of parameter derivatives. An additional package of the track reconstruction in straw chambers is suggested. The solution speed for the specific tasks was increased many times in comparison with the previous version of FUMILIM. All programs are written using FORTRAN-77
Primary Subject
Source
2010; 14 p; Also available online: http://www1.jinr.ru/Preprints/2010/101%28E11-2010-101%29.pdf; 6 refs., 3 figs. Submitted to the journal, Computer Physics Communications
Record Type
Report
Report Number
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] Controllers in safety critical systems such as nuclear power plants often use Function Block Diagrams (FBDs) to design embedded software. The design is implemented using programming languages such as C to compile it into particular target hardware. The implementation must have the same behavior with the design and the behavior should be verified explicitly. For example, the pSET (POSAFE-Q Software Engineering Tool) is a loader software to program POSAFE-Q PLC (Programmable Logic Controller) and is developed as a part of the KNICS (Korea Nuclear Instrumentation and Control System R and D Center) project. It uses FBDs to design software of PLC, and generates ANSI-C code to compile it into specific machine code. To verify the equivalence between the FBDs and ANSI-C code, mathematical proof of code generator or a verification tools such as RETRANS can help guarantee the equivalence. Mathematical proof, however, has a weakness that requires high expenditure and repetitive fulfillment whenever the translator is modified. On the other hand, RETRANS reconstructs the generated source code without consideration of the generator. It has also a weakness that the reconstruction of generated code needs additional analysis This paper introduces verification process of behavioral consistency between design and its implementation of the pSET using the HW-CBMC. The HW-CBMC is a formal verification tool, verifying equivalence between hardware and software description. It requires two inputs for checking equivalence, Verilog for hard-ware and ANSI-C for software. In this approach, FBDs are translated into semantically equivalent Verilog pro-gram, and the HW-CBMC verifies equivalence between the Verilog program and the ANSI-C program which is generated from the FBDs
Primary Subject
Source
Korean Nuclear Society, Daejeon (Korea, Republic of); [1 CD-ROM]; May 2011; [2 p.]; 2011 spring meeting of the KNS; Taebaek (Korea, Republic of); 26-27 May 2011; Available from KNS, Daejeon (KR); 5 refs, 2 figs
Record Type
Miscellaneous
Literature Type
Conference
Country of publication
Reference NumberReference Number
Related RecordRelated Record
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
No abstract available
Original Title
Neue Features in FeynArts 3
Primary Subject
Source
2001 spring meeting of Fachverbaende Gravitation und Relativitaetstheorie (GR), Teilchenphysik (T), and Theoretische und Mathematische Grundlagen der Physik (MP) of Deutsche Physikalische Gesellschaft e.V. (DPG) with physics and book exhibition; Fruehjahrstagung 2001 der Fachverbaende Gravitation und Relativitaetstheorie (GR), Teilchenphysik (T), und Theoretische und Mathematische Grundlagen der Physik (MP) der Deutschen Physikalischen Gesellschaft e.V. (DPG) mit Physik- und Buchausstellung; Bonn (Germany); 26-30 Mar 2001
Record Type
Journal Article
Literature Type
Conference
Journal
Verhandlungen der Deutschen Physikalischen Gesellschaft; ISSN 0420-0195;
; CODEN VDPEAZ; v. 36(3); p. 32

Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
1 | 2 | 3 | Next |