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Cullen, D.E.
International Atomic Energy Agency, Vienna (Austria). Nuclear Data Section1981
International Atomic Energy Agency, Vienna (Austria). Nuclear Data Section1981
AbstractAbstract
[en] This document contains the summary documentation for the ENDF/B pre-processing codes: LINEAR, RECENT, SIGMA1, GROUPIE, EVALPLOT, MERGER, DICTION, CONVERT. This summary documentation is merely a copy of the comment cards that appear at the beginning of each programme; these comment cards always reflect the latest status of input options, etc. For the latest published documentation on the methods used in these codes see UCRL-50400, Vol.17 parts A-E, Lawrence Livermore Laboratory (1979)
Primary Subject
Source
Dec 1981; 49 p
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Report
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DayDay, N.
International Atomic Energy Agency, Vienna (Austria). Nuclear Data Section1980
International Atomic Energy Agency, Vienna (Austria). Nuclear Data Section1980
AbstractAbstract
[en] A description and operating instructions are supplied for the following ENDF/B-V Processing Programs: CHECKER, CRECT, STNDRD, FIZCON, PSYCHE, RESEND, INTER, INTEND, SUMRIZ, PLOTEF, LSTFCV, RIGEL. These programs can be obtained on magnetic tape, free of charge, from the IAEA Nuclear Data Section. (author)
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Source
Jul 1980; 19 p
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Report
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INIS IssueINIS Issue
Thomas, C.R.; de Saussure, G.; Marable, J.H.
Oak Ridge National Lab., TN (USA)1981
Oak Ridge National Lab., TN (USA)1981
AbstractAbstract
[en] A two-month survey of nuclear fuel-cycle models was undertaken. This report presents the information forthcoming from the survey. Of the nearly thirty codes reviewed in the survey, fifteen of these codes have been identified as potentially useful in fulfilling the tasks of the Nuclear Energy Analysis Division (NEAD) as defined in their FY 1981-1982 Program Plan. Six of the fifteen codes are given individual reviews. The individual reviews address such items as the funding agency, the author and organization, the date of completion of the code, adequacy of documentation, computer requirements, history of use, variables that are input and forecast, type of reactors considered, part of fuel cycle modeled and scope of the code (international or domestic, long-term or short-term, regional or national). The report recommends that the Model Evaluation Team perform an evaluation of the EUREKA uranium mining and milling code
Primary Subject
Source
Apr 1981; 59 p; Available from NTIS., PC A04/MF A01
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Report
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AbstractAbstract
No abstract available
Primary Subject
Source
International Atomic Energy Agency, Vienna (Austria); p. 403-416; 1973; Panel on neutron nuclear data evaluation; Vienna, Austria; 30 Aug 1971
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Report
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Conference
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AbstractAbstract
No abstract available
Original Title
Software-Entwicklungen
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Source
Hahn-Meitner-Institut fuer Kernforschung Berlin G.m.b.H. (Germany, F.R.). Bereich Kern- und Strahlenphysik; 193 p; 1982; p. 85-88; Published in summary form only.
Record Type
Report
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Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Cullen, D.E.
International Atomic Energy Agency, Vienna (Austria). Nuclear Data Section1983
International Atomic Energy Agency, Vienna (Austria). Nuclear Data Section1983
AbstractAbstract
[en] This is the summary documentation for the 1983 version of the ENDF/B Pre-Processing Codes LINEAR, RECENT, SIGMA1, GROUPIE, EVALPLOT, MERGER, DICTION, COMPLOT, CONVERT. This summary documentation is merely a copy of the comment cards that appear at the beginning of each programme; these comment cards always reflect the latest status of input options, etc
Primary Subject
Secondary Subject
Source
Jun 1983; vp
Record Type
Report
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Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Julies, R.E.
University of the Western Cape, Bellville (South Africa)1984
University of the Western Cape, Bellville (South Africa)1984
AbstractAbstract
[en] The success of the nuclear shell model in explaining many aspects of nuclear structure has led to the rapid development of the underlying theory and techniques for calculating nuclear properties. The digital computer made it possible to do nuclear shell-model calculations. The unconventional technique embodied in the Glasgow shell-model programme, has led to the development of a new shell-model code, called 'OXSHELL'. Both codes employ m-scheme Slater determinant basis states in the second quantization formalism. Nany-particle wave functions can very conveniently be represented in a computer since each bit of a computer word, characterized by a given set of quantum numbers, represents a particular single-particle state, with the values 1 and 0 that a bit can have indicating occupancy or not. These bit patterns are easily operated on by the appropriate creation and annihilation operators of the second quantization formalism, automatically taking antisymmetry into account. The great advantage of this technique, however, is that it does not require large sets of coefficients of fractional parentage. Various computer programs were developed for shell-model calculations
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Source
Nov 1984; 91 p; Available from the Registrar, University of the Western Cape, Private Bag X17, Bellville, 7530, South Africa; Thesis (M.Sc.).
Record Type
Miscellaneous
Literature Type
Thesis/Dissertation
Country of publication
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McLaughlin, K.
International Atomic Energy Agency, Vienna (Austria). Nuclear Data Section1984
International Atomic Energy Agency, Vienna (Austria). Nuclear Data Section1984
AbstractAbstract
[en] A description and operating instructions are supplied for the following ENDF/B-V Processing Programs: CHECKER, CRECT, STNDRD, FIZCON, PSYCHE, RESEND, INTER, INTEND, SUMRIZ, PLOTEF, LSTFCV, RIGEL. These programs can be obtained on magnetic tape, free of charge, from the IAEA Nuclear Data Section. (author)
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Secondary Subject
Source
Mar 1984; 16 p
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Report
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Reference NumberReference Number
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Dunn, F.E.; Malloy, D.J.; Mohr, D.
Argonne National Lab., IL (USA)1987
Argonne National Lab., IL (USA)1987
AbstractAbstract
[en] A wide range of thermal hydraulics computer codes have been developed by various organizations in the US. These codes cover an extensive range of purposes from within-assembly-wise pin temperature calculations to plant wide transient analysis. The codes are used for static analysis, for analysis of protected anticipated transients, and for analysis of a wide range of unprotected transients for the more recent inherently safe LMR designs. Some of these codes are plant-specific codes with properties of a specific plant built into them. Other codes are more general and can be applied to a number of plants or designs. These codes, and the purposes for which they have been used, are described
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Source
27 Apr 1987; 13 p; American Nuclear Society international meeting on advances in reactor physics, mathematics and computation; Paris (France); 27-30 Apr 1987; Available from NTIS, PC A02/MF A01 as DE87004952
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Report
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Conference
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AbstractAbstract
No abstract available
Original Title
Ein integriertes modulares Abbrandsystem mit hierarchischen Datenstrukturen
Primary Subject
Source
Deutsches Atomforum e.V., Bonn (F.R. Germany); p. 78-81; 1975; ZAED; Leopoldshafen, F.R. Germany; Reactor conference; Nuernberg, F.R. Germany; 8 Apr 1975; AED-CONF--75-001-019; 2 figs.; 4 refs. Short communication only.
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Book
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Conference
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