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Yamakoshi, Hisao

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 program or function: SMART calculates radiation dose rate at the center of each cask surface by using characteristic functions for radiation shielding ability and for radiation current back-scattered from cask wall and cask cavity of each cask, once cask-type is specified. 2 - Method of solution: Matrix Calculation

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18 Aug 1989; [html]; Available on-line: http://www.nea.fr/abs/html/nea-1046.html; Country of input: International Atomic Energy Agency (IAEA); 2 refs.

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Miscellaneous

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Kienzler, 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 program or function: The theoretical model was designed to calculate the leaching of radionuclides and the corrosion of cemented waste forms in contact with water or brine. The model computes both the behaviour of specimens in laboratory- scale experiments and provides a forecast of the behaviour of waste forms in the case of an accidental drowning of a repository. The mathematical formalism describes leaching and corrosion on the basis of diffusion and dissolution processes and of the chemical reactions by the corrosion. 2 - Method of solution: Crank-Nicolson difference formalism. 3 - Restrictions on the complexity of the problem: 1000 spatial increments

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29 Jan 1990; [html]; Available on-line: http://www.nea.fr/abs/html/nea-1067.html; Country of input: International Atomic Energy Agency (IAEA); 2 refs.

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BUILDING MATERIALS, CHEMICAL REACTIONS, COMPUTER CODES, DISSOLUTION, DOCUMENT TYPES, ENVIRONMENTAL TRANSPORT, ISOTOPES, MANAGEMENT, MASS TRANSFER, MATERIALS, RADIOACTIVE MATERIALS, RADIOACTIVE WASTE MANAGEMENT, RADIOACTIVE WASTES, SEPARATION PROCESSES, STORAGE, WASTE MANAGEMENT, WASTE STORAGE, WASTES

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Kobayashi, K.; Buckel, G.; Kuefner, K.

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 program or function: Reactivity, mean generation time and effective delayed neutron fraction can be calculated by exact or first order perturbation theory. Criticality factor corrected for the isotope dependence of the prompt fission spectrum and the difference between the delayed neutron spectrum and the prompt fission spectra can also be calculated. 2 - Method of solution: Direct and adjoint angular fluxes for unperturbed and perturbed cases are taken from the discrete ordinate code, and the reactivity etc. are calculated by the perturbation theory. 3 - Restrictions on the complexity of the problem: Only two-dimensional regular triangular geometry is considered. There is no restriction for the number of energy groups. The size of a problem is restricted by the available maximum region of the computer memory. At present only down-scattering and a Sn approximation up to N=8 is allowed

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9 May 1989; [html]; Available on-line: http://www.nea.fr/abs/html/nea-1155.html; Country of input: International Atomic Energy Agency (IAEA); 1 ref.

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Software

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Leach, S.J.; Pryke, D.C.

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] A - Description of program or function: NEARSOL models the aqueous speciation and solubility of actinides under near-field conditions for disposal using a simple thermodynamic approach. B - Method of solution: The program draws information from a thermodynamic data base consisting of solubility products and complex formation constants for all known species, and standard electrode potentials, at 25 C, corrected for ionic strength effects. By minimising the free energy of the system through a series of iterations, a precipitating solid phase is predicted which limits the solubility, and the concentration of the main aqueous species are calculated as a function of pH. Initially the program evaluates only hydroxide and carbonate species, but the effect of sulphate, phosphate and fluoride anions can also be included. The program is simple to use, requiring inputs of: 1. Actinide(s); 2. pH range; 3. Ionic strength; 4. Redox conditions; 5. Ligand concentrations. Functions are included to calculate the distribution of the protonated and un-protonated forms of carbonate and phosphate and the value of Eh as a function of pH under disposal conditions as required. The program can further evaluate the role of free calcium ions. C - Restrictions on the complexity of the problem: None

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12 Jun 1989; [html]; Available on-line: http://www.nea.fr/abs/html/nea-1158.html; Country of input: International Atomic Energy Agency (IAEA); 4 refs.

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Miscellaneous

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Software

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CARBON COMPOUNDS, CHARGED PARTICLES, COMPUTER CODES, DISPERSIONS, DOCUMENT TYPES, ELEMENTS, ENERGY, FLUORINE COMPOUNDS, HALIDES, HALOGEN COMPOUNDS, HOMOGENEOUS MIXTURES, HYDROGEN COMPOUNDS, IONS, MANAGEMENT, METALS, MIXTURES, OXYGEN COMPOUNDS, PHOSPHORUS COMPOUNDS, PHYSICAL PROPERTIES, RADIOACTIVE WASTE MANAGEMENT, SOLUTIONS, STORAGE, SULFUR COMPOUNDS, THERMODYNAMIC PROPERTIES, WASTE MANAGEMENT, WASTE STORAGE

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Hanson, R.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 program or function: PC-BLAS is a highly optimized version of the Basic Linear Algebra Subprograms (BLAS), a standardized set of 38 routines that perform low-level operations on vectors of numbers in single- and double-precision real and complex arithmetic. Routines are included to find the index of the largest component of a vector, apply a Givens or modified Givens rotation, multiply a vector by a constant, determine the Euclidean length, perform a dot product, swap and copy vectors, and find the norm of a vector. 2 - Restrictions on the complexity of the problem: The number of components in any vector and the spacing or stride between their entries must not exceed 32,767 (2

^{15}-1). PC-BLAS will not work with an 80286 CPU operating in 'protected' modePrimary Subject

Source

28 Jun 1989; [html]; Available on-line: http://www.nea.fr/abs/html/nesc9617.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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Pariseau, W.G.; Golis, M.

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 program or function: UTAH-2 is a two-dimensional, thermomechanical finite-element program designed to analyze elastic, elastic-plastic, and elastic brittle response in anisotropic geologic media. Both constant strain triangles and quadrilateral elements composed of four constant strain triangles are used. The yield function for either elastic-plastic or elastic-brittle response is an extended von Mises criteria for geologic media with anisotropic strength properties. Additionally, the yield function considers the effects of confining pressure. UTAH-2 is able to consider temperature dependence of material properties. The elastic and plastic moduli as well as the thermal expansion coefficients can vary with temperature based on a polynomial fit of experimental data. UTAH-2 is intended for use in analyzing stress and displacement fields associated with repository excavation, canister emplacement, salt over short time periods and in other geological media for any time scale; for evaluating room stability and generating boundary conditions (stress fields) used in canister sleeve studies; for analyzing bedded sedimentary regions; and for sensitivity and stability studies where temperature dependence of material properties may be a factor. 2 - Restrictions on the complexity of the problem: UTAH2 is not appropriate for use in fully three-dimensional problems and cannot be used for long-term studies in salt where creep deformation becomes dominant. UTAH2 does not analyze creep behavior or take individual fractures into account

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Source

6 Jun 1989; [html]; Available on-line: http://www.nea.fr/abs/html/nesc9848.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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ANISOTROPY, BOUNDARY CONDITIONS, COMPUTER PROGRAM DOCUMENTATION, CONTAINERS, CREEP, DEFORMATION, DEPOSITS, EXCAVATION, FINITE ELEMENT METHOD, FRACTURES, POLYNOMIALS, POSITIONING, ROCKS, SALT DEPOSITS, SALTS, STABILITY, STRAINS, STRESSES, TEMPERATURE DEPENDENCE, THERMAL EXPANSION, THERMOPLASTICS, THREE-DIMENSIONAL CALCULATIONS, TRANSIENTS, TWO-DIMENSIONAL CALCULATIONS, U CODES, WEBSITES

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Huyakorn, P.; Golis, 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 program or function: FTRANS (Fractured flow and Transport of Radionuclides) is a two-dimensional finite-element code designed to simulate ground-water flow and transport of radioactive nuclides in a fractured porous return medium. FTRANS takes into account fluid interactions between the fractures and porous matrix blocks, advective-dispersive transport in the fractures and diffusion in the porous matrix blocks, and chain reactions of radionuclide components. It has the capability to model the fractured system using either the dual-porosity or the discrete- fracture modeling approach or a combination of both. FTRANS can be used to perform two-dimensional near-field or far-field predictive analyses of ground-water flow and to perform risk assessments of radionuclide transport from nuclear waste repository subsystems to the biosphere. 2 - Restrictions on the complexity of the problem: Although FTRANS does cannot account for deformation processes which can affect the flow capacity and velocity field

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21 Aug 1987; [html]; Available on-line: http://www.nea.fr/abs/html/nesc9860.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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Atwoods, C.L.; Mathews, 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] Description of program or function: ANYOLS is a stepwise program which fits data using ordinary or weighted least squares. Variables are selected for the model in a stepwise way based on a user- specified input criterion or a user-written subroutine. The order in which variables are entered can be influenced by user-defined forcing priorities. Instead of stepwise selection, ANYOLS can try all possible combinations of any desired subset of the variables. Automatic output for the final model in a stepwise search includes plots of the residuals, 'studentized' residuals, and leverages; if the model is not too large, the output also includes partial regression and partial leverage plots. A data set may be re-used so that several selection criteria can be tried. Flexibility is increased by allowing the substitution of user-written subroutines for several default subroutines

Primary Subject

Source

3 Jan 1986; [html]; Available on-line: http://www.nea.fr/abs/html/nesc9977.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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Burdick, G.R.; Marshall, N.H.; Wilson, J.R.; Rasmuson, D.M.; Shepherd, J.C.; Marshall, N.H.; Fitch, L.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: The COMCAN fault tree analysis codes are designed to analyze complex systems, such as nuclear plants for common causes of failure. A common cause event, or common mode failure, is a secondary cause that could contribute to the failure of more than one component and violates the assumption of independence. Analysis of such events is an integral part of system reliability and safety analysis. A significant common cause event is a secondary cause common to all basic events in one or more minimal cut sets. Minimal cut sets containing events from components sharing a common location or a common link are called common cause candidates. Components share a common location if no barrier insulates any one of them from the secondary cause. A common link is a dependency among components which cannot be removed by a physical barrier (e.g., a common energy source or common maintenance instructions). 2 - Method of solution: The COMCAN programs search the fault tree minimal cut sets for shared susceptibility to various secondary events (common causes) and common links between components. In the case of common causes, a location check may also be performed to determine whether barriers to the common cause exist between components. The programs can locate common manufacturers of components having events in the same minimal cut set. A relative rankling scheme for secondary event susceptibility is included in the programs. 3 - Restrictions on the complexity of the problem: COMCAN is limited to the analysis of fault tree minimal cut sets produced by other programs while COMCAN3 is an independent program, utilizing the fault tree code FATRAM, which is incorporated as a program module, for a thorough analysis of the fault tree for sources of common cause failures

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20 Jan 1986; [html]; Available on-line: http://www.nea.fr/abs/html/nesc0704.html; Country of input: International Atomic Energy Agency (IAEA); 6 refs.

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Miscellaneous

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Software

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Publication YearPublication Year

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INIS VolumeINIS Volume

INIS IssueINIS Issue

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Goldberg, F.F.

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 SAMPLE program uses Monte Carlo simulation to compute the mean, standard deviation, probability range, and distribution for the function y=f(x(1), x(2),...x (k)) given that the distributions of x(1), x(2),...x(k) are known and the functional dependence of y on the x's is known. 2 - Method of solution: The program repeatedly samples from the independent variable distributions and for each sample computes the corresponding value of the dependent variable y as defined by the user- supplied FORTRAN function. The sampling is repeated n times with n determined by the user. The resulting values of y are sorted in ascending order to obtain the percentiles of the distribution of y. 3 - Restrictions on the complexity of the problem: The program permits normal, log-normal, and log-uniform distribution types to be specified for the input variables, and all of the input variables must have the same distribution type. Other distribution types and changes allowing each variable to have any of the distribution types could easily to added

Primary Subject

Source

2 Aug 1988; [html]; Available on-line: http://www.nea.fr/abs/html/nesc0879.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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