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Sartori, E.H.

Organisation for Economic Co-Operation and Development, Nuclear Energy Agency - OECD/NEA, Le Seine Saint-Germain, 12 boulevard des Iles, F-92130 Issy-les-Moulineaux (France)

Organisation for Economic Co-Operation and Development, Nuclear Energy Agency - OECD/NEA, Le Seine Saint-Germain, 12 boulevard des Iles, F-92130 Issy-les-Moulineaux (France)

AbstractAbstract

[en] 1 - Nature of the physical problem solved: Given a function z = f(x,y) in matrix form, defined on a rectangular mesh-grid, it returns the value of the function, the first and second partial derivatives in an arbitrary point (x',y') inside the rectangular domain. 2 - Method of solution: A bi-cubic spline interpolation method is used; a linear and logarithmic interpolation model is included. 3 - Restrictions on the complexity of the problem: Variable dimensioning is used by storing all data in one array

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Source

30 Apr 1978; [html]; Available on-line: http://www.nea.fr/abs/html/nea-0541.html; Country of input: International Atomic Energy Agency (IAEA); 2 refs.

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Miscellaneous

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Software

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AbstractAbstract

[en] 1 - Nature of the physical problem solved: Deletion, insertion and exchange of data records in the data file 'KEDAK'. Printout of a list of contents of the KEDAK library. Conversion of the KEDAK library from direct access form into card image form and vice versa. 2 - Method of solution: For the universal exchange of the KEDAK library it is necessary to transform the library from direct access form into a sequential form. This sequential form will be exchanged and re-transformed into direct access form

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Source

1 Oct 1979; [html]; Available on-line: http://www.nea.fr/abs/html/nea-0578.html; Country of input: International Atomic Energy Agency (IAEA); 2 refs.

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Miscellaneous

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Software

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Dietrich, R.

Organisation for Economic Co-Operation and Development, Nuclear Energy Agency - OECD/NEA, Le Seine Saint-Germain, 12 boulevard des Iles, F-92130 Issy-les-Moulineaux (France)

Organisation for Economic Co-Operation and Development, Nuclear Energy Agency - OECD/NEA, Le Seine Saint-Germain, 12 boulevard des Iles, F-92130 Issy-les-Moulineaux (France)

AbstractAbstract

[en] 1 - Description of problem or function: ANIPLO-D50 is a computer code which plots results determined using the discrete ordinates neutron and gamma ray transport code ANISN. In particular the space- dependent scalar fluxes and responses such as the dose rate may be plotted. 2 - Method of solution: The input is divided into two parts: - The 'library' data defining the energy group structure, the spatial mesh and giving the scalar flux in the configuration. - The 'problem' data, which is repeated for each plot required, giving the title of the plot and the x and y axes, and the flux to dose conversion factor if dose rates are plotted. Note fluxes and doses (for each energy group and summed over all groups) are plotted against the space variable. The scalar fluxes are read in from cards, output from ANISN when ID1=2. Flexibility is available in the size of the plot, log. or lin. axes, etc. 3 - Restrictions on the complexity of the problem: The maximum number of energy groups is 25. The maximum number of spatial intervals is 400

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Source

1 Apr 1980; [html]; Available on-line: http://www.nea.fr/abs/html/nea-0633.html; Country of input: International Atomic Energy Agency (IAEA); 2 refs.

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Miscellaneous

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Software

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Chwieroth, F.S.; Dodson, J.I.; Johnson, M.B.; Owen, L.W.; Satchler, G.R.

Organisation for Economic Co-Operation and Development, Nuclear Energy Agency - OECD/NEA, Le Seine Saint-Germain, 12 boulevard des Iles, F-92130 Issy-les-Moulineaux (France)

Organisation for Economic Co-Operation and Development, Nuclear Energy Agency - OECD/NEA, Le Seine Saint-Germain, 12 boulevard des Iles, F-92130 Issy-les-Moulineaux (France)

AbstractAbstract

[en] 1 - Description of problem or function: ATHENA4 computes form factors for inelastic scattering calculations, using single-particle wave functions that are eigenstates of motion in either a Woods-Saxon potential well or a harmonic oscillator well. Two-body forces of Gauss, Coulomb, Yukawa, and a sum of cut-off Yukawa radial dependences are available. 2 - Restrictions on the complexity of the problem - Maxima of: 100 wave function components, 10 interaction components, The reduced matrix elements of the one-body multipole operators may be included automatically in the wave function coefficients. Non-local effects on the wave functions may be included in the local energy approximation

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1 Jan 1976; [html]; Available on-line: http://www.nea.fr/abs/html/nesc0417.html; Country of input: International Atomic Energy Agency (IAEA); 2 refs.

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Miscellaneous

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Software

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Perey, F.G.

Organisation for Economic Co-Operation and Development, Nuclear Energy Agency - OECD/NEA, Le Seine Saint-Germain, 12 boulevard des Iles, F-92130 Issy-les-Moulineaux (France)

Organisation for Economic Co-Operation and Development, Nuclear Energy Agency - OECD/NEA, Le Seine Saint-Germain, 12 boulevard des Iles, F-92130 Issy-les-Moulineaux (France)

AbstractAbstract

[en] 1 - Description of problem or function: The dosimetry unfolding problem consists in finding a spectrum which will reproduce a set of measured activities given the dosimetry cross sections. Most currently available dosimetry unfolding codes provide a solution by introducing a trial spectrum which is modified iteratively by means of an algorithm. No or very little information is provided by these codes concerning the 'uncertainties' in their solutions due to input data 'uncertainties'. The relationship of their solution to other possible solutions is not established. STAY-SL does not solve the usual dosimetry unfolding problem in the sense that it provides a statement of the most likely joint probability density function of the group fluxes, i.e. the spectrum, given the joint probability density function of some measured activation, dosimetry cross sections and some a priori input group fluxes. The density functions are assumed to be normal and independent for the three classes of input data. The joint probability density functions of each class of input data except for being normal may be completely arbitrary. With the above restrictions on the density functions of the input data, STAY-SL may be thought of as performing the complete 'error analysis' in the solution to the dosimetry unfolding problem. 2 - Method of solution: STAY-SL uses the least-squares method to obtain its solution. Because the three different types of input data are assumed to have independent probability density functions, in particular the activation data, the Method of solution is extremely fast and requires only the inversion of a small matrix of dimensions equal to the number of activation measurements. This matrix will very seldom be singular; therefore, a solution may almost always be obtained. Although the method is also formally equivalent to a 'dosimetry cross section adjustment', the 'adjusted cross sections' are not solved for. The joint probability density function of the output group fluxes, which is the solution, reflects the uncertainties in the input dosimetry cross sections as given by their input joint probability density function. Because the activation data are assumed to have a probability density function, independent of the other input data, the method is equivalent to an application of Bayes' theorem where the activation data are used tp improve upon some a priori knowledge of the distribution of the spectrum being solved for, given a priori distribution of the dosimetry cross sections. The solution being based upon the least-squares method is the best possible one in the sense that the elements of the output covariance matrix are minimum. 3 - Restrictions on the complexity of the problem: As currently dimensioned, the code can solve for up to 20 activations and 200 group fluxes. These dimensions could easily be changed if desired. Except as stated above concerning the normal distribution law used and independence of the distributions of the three different classes of input data, there are no restrictions to the code. A solution will always be produced, no matter how unlikely the input data, although a warning will be given in the output, provided the matrix being inverted does not approach singularity, in which case the run will be aborted and a diagnostic given. The test for approach to singularity of the matrix is believed to be conservative and could possible be relaxed if ever needed

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1 Mar 1979; [html]; Available on-line: http://www.nea.fr/abs/html/psr-0113.html; Country of input: International Atomic Energy Agency (IAEA); 3 refs.

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Miscellaneous

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Software

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Chen, W. L.; Thompson, D. H.; Shin, Y. W.; Edwards, H. S.

Organisation for Economic Co-Operation and Development, Nuclear Energy Agency - OECD/NEA, Le Seine Saint-Germain, 12 boulevard des Iles, F-92130 Issy-les-Moulineaux (France)

Organisation for Economic Co-Operation and Development, Nuclear Energy Agency - OECD/NEA, Le Seine Saint-Germain, 12 boulevard des Iles, F-92130 Issy-les-Moulineaux (France)

AbstractAbstract

[en] 1 - Description of problem or function: NAHAMMER analyzes short-term pressure-pulse transients in a closed hydraulic system consisting of series or parallel piping, pipe junctions, diameter discontinuities, elbows, junctions of three to six branches, orifices, acoustic impedance discontinuities, dummy junctions, dead ends, and free surfaces in surge tanks. The working fluid is assumed to be sodium without cavitation. 2 - Method of solution: NAHAMMER considers a simplified one-dimensional linear inviscid set of governing equations. Classical fluid-hammer theory was linearized by neglecting the viscosity and recognizing that convective terms are negligible when the ratio of flow velocity to sonic speed is less than 0.01. Numerical solutions are obtained by a simple superposition technique for tracing the waves traveling along each characteristic and for extending the solution from one constant time line to the next. 3 - Restrictions on the complexity of the problem: The program currently provides for maxima of: 50 legs, 120 nodes per leg, 50 junctions, 10 plenums (surge tanks). The assumption of linearity restricts the maximum pressure at any propagating wave front in sodium to about 5800 psi. Calculations are limited to liquid sodium in the absence of cavitation. Friction- free fluid motion maintains its energy within any pipe section, but conventional energy losses based on steady-state incompressible fluid flow are taken into account for elbows, diameter discontinuities, and orifice-like restrictions. To specify a working fluid other than sodium, the source coding must be changed

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Source

1 Jul 1978; [html]; Available on-line: http://www.nea.fr/abs/html/nesc0717.html; Country of input: International Atomic Energy Agency (IAEA); 2 refs.

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Miscellaneous

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Software

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Sorey, M.L.; Lippmann, M.J.

Organisation for Economic Co-Operation and Development, Nuclear Energy Agency - OECD/NEA, Le Seine Saint-Germain, 12 boulevard des Iles, F-92130 Issy-les-Moulineaux (France)

Organisation for Economic Co-Operation and Development, Nuclear Energy Agency - OECD/NEA, Le Seine Saint-Germain, 12 boulevard des Iles, F-92130 Issy-les-Moulineaux (France)

AbstractAbstract

[en] 1 - Description of problem or function: The SCHAFF (Slightly Compressible Heat and Fluid Flow) program was developed for numerical modeling of liquid geothermal systems involving natural convection and hot spring discharge. For one-, two-, or three- dimensional porous media, the single-phase fluid and heat transfer equations are solved interlaced in time, using an integrated finite difference method. The mathematical model describing the physical behavior of hot-water geothermal systems is used to analyze natural or cellular convection in permeable layers heated from below. 2 - Method of solution: The model consists of a set of coupled partial differential equations for heat and mass transfer in porous media and an equation of state relating fluid density to temperature. Simultaneous solution of the flow and energy equations is accomplished by interlacing the solutions in time, first assuming temperatures and fluid densities constant over an interval and solving for new fluid pressure and velocity distributions, then using the new pressure and velocity distributions to compute new temperature and fluid density distributions and so on. These equations are solved numerically using an integrated finite difference method which treats arbitrary nodal configurations in up to three dimensions. The concepts of fluid and thermal time constants as indicators of nodal response times and numerical stability limits is an inherent part of the numerical scheme. 3 - Restrictions on the complexity of the problem: The equations used do not include source terms. With a mass source, such as a recharge or discharge well, the flow field would not necessarily equilibrate within each thermal cycle

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Source

1 Dec 1979; [html]; Available on-line: http://www.nea.fr/abs/html/nesc0802.html; Country of input: International Atomic Energy Agency (IAEA); 2 refs.

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Miscellaneous

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Software

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COMPUTER PROGRAM DOCUMENTATION, COMPUTERIZED SIMULATION, CONFIGURATION, DISTRIBUTION, EQUATIONS OF STATE, FINITE DIFFERENCE METHOD, FLUID FLOW, GEOTHERMAL ENERGY, GEOTHERMAL SYSTEMS, HEAT, HOT SPRINGS, HOT WATER, LIQUIDS, NATURAL CONVECTION, PARTIAL DIFFERENTIAL EQUATIONS, POROUS MATERIALS, PRESSURE DEPENDENCE, S CODES, TEMPERATURE DEPENDENCE, THREE-DIMENSIONAL CALCULATIONS, VELOCITY, WEBSITES

CALCULATION METHODS, COMPUTER CODES, CONVECTION, DIFFERENTIAL EQUATIONS, DOCUMENT TYPES, ENERGY, ENERGY SOURCES, ENERGY TRANSFER, EQUATIONS, FLUIDS, HEAT TRANSFER, HYDROGEN COMPOUNDS, ITERATIVE METHODS, MASS TRANSFER, MATERIALS, MATHEMATICAL SOLUTIONS, NUMERICAL SOLUTION, OXYGEN COMPOUNDS, RENEWABLE ENERGY SOURCES, SIMULATION, THERMAL SPRINGS, WATER, WATER SPRINGS

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Conception and production of a time sharing system for a Mitra-15 CII mini-computer dedicated to APL

Perrin, Rene

Centre d'Etudes Nucleaires de Saclay, Services d'Electronique de Saclay, 91191 Gif-sur-Yvette Cedex (France); Universite de Paris-Sud, centre d'Orsay (France)

Centre d'Etudes Nucleaires de Saclay, Services d'Electronique de Saclay, 91191 Gif-sur-Yvette Cedex (France); Universite de Paris-Sud, centre d'Orsay (France)

AbstractAbstract

[en] The installation of a time-sharing system on a mini-computer poses several interesting problems. These technical problems are especially interesting when the goal is to equitably divide the physical resources of the machine amongst users of a high level, conservational language like APL. Original solutions were necessary to be able to retain the rapidity and performances of the original hard and software. The system has been implemented in such way that several users may simultaneously access logical resources, such as the library zones their read/write requests are managed by semaphores which may also be directly controlled by the APL programmer. (author)

[fr]

L'implantation sur un mini-ordinateur MITRA-15 Cii d'un systeme en temps-partage, permettant a plusieurs usagers l'emploi simultane d'un langage evolue conversationnel tel que l'APL, pose des problemes techniques requerant des solutions originales, adaptees a la configuration du materiel et du logiciel disponible. Les techniques de l'evaluation montrent l'interet d'une telle realisation. Le systeme realise offre un acces reglemente aux ressources physiques de la machine. L'acces simultane aux ressources logiques par plusieurs usagers, bibliotheques par exemple, est regle par le jeu des primitives du type semaphore accessibles au programmeur par des fonctions APL integrees au langage. (auteur)Original Title

Etude et realisation d'un systeme en temps partage pour le langage APL sur miniordinateur Mitra 15 CII

Primary Subject

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Source

28 Oct 1977; Jan 1978; 198 p; FRCEA-TH--3996; 33 refs.; Available from the INIS Liaison Officer for France, see the 'INIS contacts' section of the INIS website for current contact and E-mail addresses: http://www.iaea.org/INIS/contacts/; These Docteur Ingenieur, specialite: electronique, sous-specialite: Traitement de l'Information

Record Type

Report

Literature Type

Thesis/Dissertation

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INIS VolumeINIS Volume

INIS IssueINIS Issue

Emmett, M.B.

Organisation for Economic Co-Operation and Development, Nuclear Energy Agency - OECD/NEA, Le Seine Saint-Germain, 12 boulevard des Iles, F-92130 Issy-les-Moulineaux (France)

Organisation for Economic Co-Operation and Development, Nuclear Energy Agency - OECD/NEA, Le Seine Saint-Germain, 12 boulevard des Iles, F-92130 Issy-les-Moulineaux (France)

AbstractAbstract

[en] 1 - Description of problem or function: INTRIGUE-II-L is an IBM 360 Subroutine Package for making linear, logarithmic and semi-logarithmic graphs using the CALCOMP Plotter. It is a subroutine package which requires a user written main program calling the particular routines required for any given problem. A wide variety of options is available including type of plot, method of presenting data (points only, connected points, histograms, etc.), size of grid and placement or legends. 2 - Method of solution: No special mathematical techniques are used. 3 - Restrictions on the complexity of the problem: There is a data buffer 5000 words long which is ideal for most systems but might require a reduction on a computer with small core size. Users must have the basic CALCOMP plotting routines for their particular CALCOMP configuration

Primary Subject

Source

1 Mar 1977; [html]; Available on-line: http://www.nea.fr/abs/html/psr-0054.html; Country of input: International Atomic Energy Agency (IAEA); 1 ref.

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Miscellaneous

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Software

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Soran, P.D.; MacFarlane, R.E.; Harris, D.R.; LaBauve, R.J.; Hendricks, J.S.; Kidman, R.B.; Weisbin, C.R.; White, J.E.

Organisation for Economic Co-Operation and Development, Nuclear Energy Agency - OECD/NEA, Le Seine Saint-Germain, 12 boulevard des Iles, F-92130 Issy-les-Moulineaux (France)

Organisation for Economic Co-Operation and Development, Nuclear Energy Agency - OECD/NEA, Le Seine Saint-Germain, 12 boulevard des Iles, F-92130 Issy-les-Moulineaux (France)

AbstractAbstract

[en] 1 - Description of problem or function: MINX calculates fine-group averaged infinitely diluted cross sections and self-shielding factors from ENDF/B-IV data. Its primary purpose is to generate a pseudo-composition-independent multigroup library which is input to the SPHINX space-energy collapse program (2) (PSR-0129) through standard CCCC-III (8) interfaces. MINX incorporates and improves upon the resonance capabilities of existing codes such as ETOX (5) (NESC0388) and ENDRUN (9) and the high-order group-to-group transfer matrices of SUPERTOG (10) (PSR-0013) and ETOG (11). Fine group energy boundaries, Legendre expansion order, gross spectral shape component (in the Bondarenko flux model), temperatures and dilutions can all be used specifically. 2 - Method of solution: Infinitely dilute, un-broadened point cross sections are obtained from resolved resonance parameters using a modified version of the RESEND program (3) (NESC0465). The SIGMA1 (4) (IAEA0854) kernel-broadening method is used to Doppler broaden and thin the tabulated linearized pointwise cross sections at 0 K (outside of the unresolved energy region). Effective temperature- dependent self-shielded pointwise cross sections are derived from the formulation in the ETOX code. The primary modification to the ETOX algorithm is associated with the numerical quadrature scheme used to establish the mean values of the fluctuation intervals. The selection of energy mesh points, at which the effective cross sections are calculated, has been modified to include the energy points given in the ENDF/B file or, if the energy-independent formalism was employed, points at half-lethargy intervals. Infinitely dilute group cross sections and self-shielding factors are generated using the Bondarenko flux weighting model with the gross spectral shape under user control. The integral over energy for each group is divided into a set of panels defined by the union of the grid points describing the total cross section, the reaction cross section of interest and the gross spectral shape. The integration scheme actually employed in MINX is adaptive Simpson's procedure for which the initial estimate is based on the unionized grid described above. The computation of elastic and discrete group- to-group matrices is based upon a semi-analytic scheme which treats the rapidly fluctuating cross-section behaviour analytically. Where this laboratory-system-based scheme becomes difficult to implement (e.g., light nuclei, inelastic thresholds), an alternative numerical integration in the center-of mass system is employed. Multigroup transfer matrices for processes in which the outgoing neutron energy and angular distribution is uncoupled are computed by direct numerical integration. 3 - Restrictions on the complexity of the problem: The principal restriction is the computing time available for a given desired accuracy, number of groups, and Legendre order. The paging technique and variable dimensioning make efficient use of available core storage; very large problems have been run with MINX (e.g. a complete 171-group P3 neutron library at ORNL and an extensive 240-group P4 library at LASL)

Primary Subject

Source

1 Nov 1977; [html]; Available on-line: http://www.nea.fr/abs/html/psr-0105.html; Country of input: International Atomic Energy Agency (IAEA); 11 refs.

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Miscellaneous

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Software

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ALGORITHMS, ANGULAR DISTRIBUTION, CALCULATION METHODS, CENTER-OF-MASS SYSTEM, COMPUTER PROGRAM DOCUMENTATION, GROUP CONSTANTS, LABORATORY SYSTEM, LANL, LIGHT NUCLEI, M CODES, MULTIGROUP THEORY, NEUTRONS, NUCLEAR DATA COLLECTIONS, ORNL, RESONANCE, SELF-SHIELDING, TEMPERATURE DEPENDENCE, TOTAL CROSS SECTIONS, WEBSITES

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