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Griffiths, J.
Atomic Energy of Canada Ltd., Chalk River, Ontario. Chalk River Nuclear Labs1978
Atomic Energy of Canada Ltd., Chalk River, Ontario. Chalk River Nuclear Labs1978
AbstractAbstract
[en] The TESHOM code and its associated data format is widely used to provide input data for lattice codes. Through TESHOM one data deck can be used to provide input to the LATREP, WIMS and POWDERPUFS lattice codes. The data format is described in detail, some of the principles behind the design of the code and its limitations are noted. (author)
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Source
Oct 1978; 21 p
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Report
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Reuss, Paul.
CEA Centre d'Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France). Service d'Etudes des Reacteurs et de Mathematiques Appliquees1981
CEA Centre d'Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France). Service d'Etudes des Reacteurs et de Mathematiques Appliquees1981
AbstractAbstract
[en] The search of tendencies is an application of the mean squares method. Its objective is the better possible evaluation of the basic data used in the calculations from the comparison between measurements of integral characteristics and the corresponding theoretical results. This report presents the minimization which allows the estimation of the basic data and, above all, the methods which are necessary for the critical analysis of the obtained results
[fr]
La recherche de tendances est une application de la methode des moindres carres. Son objectif est de chercher a determiner avec le plus de precision possible les valeurs des donnees a la base des calculs a partir de la comparaison entre des mesures de grandeurs integrales et les resultats theoriques correspondants. Ce rapport presente la minimisation permettant l'evaluation des donnees de base et surtout les methodes necessaires a l'analyse critique des resultats obtenusOriginal Title
La methode de recherche de tendances
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Aug 1981; 118 p
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Report
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Mitenkova, E.F.; Pasynkov, I.G.; Uskova, T.I.
Gosudarstvennyj Komitet po Ispol'zovaniyu Atomnoj Ehnergii SSSR, Moscow. Inst. Atomnoj Ehnergii1979
Gosudarstvennyj Komitet po Ispol'zovaniyu Atomnoj Ehnergii SSSR, Moscow. Inst. Atomnoj Ehnergii1979
AbstractAbstract
[en] Problems of organization of text libraries in the Dubna monitoring system are considered. Posibilities guaranteeing a convenient operation with text libraries in the TLIBR system are described. An operation session in this system is presented as an example. A standard operation mode in the system assumes a performance of the following operations: access, sort, copying and output of text segments to a terminal (ADPD)
Original Title
Programmnye sredstva dlya organizatsii tekstovykh bibliotek v monitornoj sisteme ''Dubna''
Primary Subject
Source
1979; 19 p; 16 refs.
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Report
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Collier, W.D.
UKAEA Risley Nuclear Power Development Establishment1981
UKAEA Risley Nuclear Power Development Establishment1981
AbstractAbstract
[en] A large number of simple test cases have been set up to test so far as possible all the facilities available in TAU. Wherever possible the results are compared with analytical solutions. Comparisons are also made with HEATRAN and ANSYS. (author)
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Source
Mar 1981; 125 p
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Report
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AbstractAbstract
[en] RCP model is a component model of TASS/SMR-S code that is describing hydraulic effects of RCP. So the RCP model should be capable of analysis for forced circulation of coolant and pump coast down. Totally 10 cases of test for pump coast-down, 3 cases among them have been analyzed with TASS/SMR-S code. With the computational analysis, RCP model of the code will be verified
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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); 2 refs, 4 figs, 1 tab
Record Type
Miscellaneous
Literature Type
Conference
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Hoffmann, Alain.
CEA Centre d'Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France). Service des Etudes Mecaniques et Thermiques1975
CEA Centre d'Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France). Service des Etudes Mecaniques et Thermiques1975
AbstractAbstract
[en] A plasticity model was introduced and is now operational in the TEDEL programme (piping and framework). At the moment it allows for either regular loading or cyclic loading under isotropic hardening conditions. The dynamic module allows the study of dynamic-plastic problems (such as accidents on a piping system). It can accept several types of material characterized by traction curves which may be of any form. Instructions are also given for the use of a new option (variable) by which the displacement values laid down for different load situations may be modified
[fr]
Un modele de plasticite a ete introduit et est maintenant operationnel dans le programme TEDEL (tuyauteries et charpentes). Il permet d'effectuer soit des chargements monotones, soit cycliques en ecrouissage isotrope pour le moment. Le module synamique permet l'etude de probleme dynamiques-plastiques (tels que des accidents sur un systeme de tuyauteries). Il est possible d'entrer plusieurs types de materiaux caracterises par les courbes de traction qui peuvent etre de forme quelconque. On donne egalement le mode d'emploi d'une nouvelle option (variable) permettant de modifier les valeurs des deplacements imposes pour differents cas de chargeOriginal Title
Programme TEDEL. Notice de la partie ''plasticite''
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May 1975; 17 p; First supplement to the CEA-N--1751 report.
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Report
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Heighway, E.A.
Atomic Energy of Canada Ltd., Chalk River, Ontario. Chalk River Nuclear Labs1980
Atomic Energy of Canada Ltd., Chalk River, Ontario. Chalk River Nuclear Labs1980
AbstractAbstract
[en] A second order beam transport design code with parametric optimization is described. The code analyzes the transport of charged particle beams through a user defined magnet system. The magnet system parameters are varied (within user defined limits) until the properties of the transported beam and/or the system transport matrix match those properties requested by the user. The code uses matrix formalism to represent the transport elements and optimization is achieved using the variable metric method. Any constraints that can be expressed algebraically may be included by the user as part of his design. Instruction in the use of the program is given. (auth)
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Jul 1980; 65 p
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Report
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AbstractAbstract
[en] According to wide-spread experience in many industries, a procedure is one of the most effective countermeasures to reduce the possibility of human related problems. Unfortunately, a systematic framework to evaluate the complexity of procedural tasks seems to be very scant. For this reason, the TACOM measure, which can quantify the complexity of procedural tasks, has been developed. In this study, the appropriateness of the TACOM measure is investigated by comparing TACOM scores regarding the procedural tasks of high speed train drivers with the associated workload scores measured by the NASA-TLX technique. As a result, it is observed that there is a meaningful correlation between the TACOM scores and the associated NASA-TLX scores. Therefore, it is expected that the TACOM measure can properly quantify the complexity of procedural tasks
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Source
54 refs, 8 figs, 5 tabs
Record Type
Journal Article
Journal
Nuclear Engineering and Technology; ISSN 1738-5733;
; v. 42(1); p. 115-124

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AbstractAbstract
No abstract available
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Aug 1974; 95 p
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Report
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Vigil, J.C.; Knight, T.D.
Los Alamos Scientific Lab., NM (USA)1981
Los Alamos Scientific Lab., NM (USA)1981
AbstractAbstract
[en] TRAC is being developed at the Los Alamos National Laboratory to provide an advanced systems code for light-water reactor accident analysis. The released TRAC versions (P1, P1A, and PD2) were intended primarily as benchmark codes for large-break loss-of-coolant accidents but PD2 has been applied successfully to TMI-type transients and other small-break transients. A fast-running version, PFl, is currently under development to address more efficiently and accurately these types of transients. All of the released versions have been subjected to testing against separate-effects, system-effects, and integral experiments covering a wide range of scales. Assessment results indicate that PD2 does a credible job overall; needed improvements are being addressed in PFl and in modifications to PD2
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1981; 13 p; Simulation methods for nuclear power systems conference; Tucson, AZ, USA; Jan 1981; CONF-810113--2; Available from NTIS., PC A02/MF A01
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Report
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