Filters
Results 1 - 10 of 1959
Results 1 - 10 of 1959.
Search took: 0.031 seconds
Sort by: date | relevance |
Gubbins, M.E.; Sherwin, J.
UKAEA Reactor Group, Winfrith. Atomic Energy Establishment1973
UKAEA Reactor Group, Winfrith. Atomic Energy Establishment1973
AbstractAbstract
No abstract available
Primary Subject
Source
Nov 1973; 31 p
Record Type
Report
Report Number
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] A visual system (Wimput) which helps WIMSD4 code users in the preparation of its input date file is presented. The program Wimput was written in C language for PC microcomputers. The user's manual is included. (Author)
Primary Subject
Record Type
Journal Article
Journal
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Taubman, C.J.; Lawrence, J.H.
UKAEA Atomic Energy Establishment, Winfrith1981
UKAEA Atomic Energy Establishment, Winfrith1981
AbstractAbstract
[en] A new version of WMSD4 has been produced on the IBM 3033 computer at Harwell. The program has been completely recompiled using the enhanced H-extended compiler and several modifications have been made. Also the line printer output has been redirected from dataset reference number 7 to dataset reference number 6 and the working space previously identified by dataset reference number 6 has been reidentified by a new dataset reference number 12. The catalogued procedure has been rewritten to deal with the dataset changes. (author)
Primary Subject
Source
Feb 1981; 7 p
Record Type
Report
Report Number
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Strickland, R.D.
Rockwell International Corp., Richland, WA (USA). Rockwell Hanford Operations1986
Rockwell International Corp., Richland, WA (USA). Rockwell Hanford Operations1986
AbstractAbstract
[en] WAC-173-303 is a Washington State Department of Ecology regulation that specifies a procedure to designate potentially toxic wastes. A computer program, WACI, has been developed to automate some of the screening test that are mandated by the regulation. The first part of the computer program name refers to WAC-173-303 and the ''I'' refers to the program as the first version. The program provides for both list designation and criteria designation as defined in WAC-173-303. This document consists of the design requirements for the program, the hardware components of the system, the vendor supplied software used by the system, the computer program description, computer program validation, the computer program listing, and the user manual
Primary Subject
Source
Jun 1986; 180 p; Available from NTIS, PC A09/MF A01 as DE86015431
Record Type
Report
Report Number
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Fujita, Shigeki; Baba, Osamu; Suzuki, Takehiro.
Japan Atomic Energy Research Inst., Tokyo1988
Japan Atomic Energy Research Inst., Tokyo1988
AbstractAbstract
[en] WAGEN is a computer code for the generation of artificial Earthquake Ground Motions utilized for the aseismic design of nuclear power facilities. WAGEN is developed on the basis of the procedure proposed by Dr. Ohsaki. An artificial earthquake ground motion generated in such a way that the response spectrum shows good fitting to the design response spectrum. This report presents main features, numerical procedure, manual of the code and an example of usage. (author)
Primary Subject
Secondary Subject
Source
Oct 1988; 24 p
Record Type
Report
Report Number
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] The method of artificial viscosity was originally designed by von Neumann and Richtmyer for calculating the propagation of waves in materials that were hydrodynamic and rate-independent (e.g., ideal gas law). However, hydrocodes (such as WONDY) based on this method continue to expand their repertoire of material laws even unto material laws that are rate-dependent (e.g., Maxwell's material law). Restrictions on the timestep required for stability with material laws that are rate-dependent can be considerably more severe than restrictions of the Courant-Friedrichs-Lewy (CFL) type that are imposed in these hydrocodes. These very small timesteps can make computations very expensive. An alternative is to go ahead and integrate the conservation laws with the usual CFL timestep while subcycling (integrating with a smaller timestep) the integration of the stress-rate equation. If the subcycling is done with a large enough number of subcycles (i.e., with a small enough subcycle timestep), then the calculation is stable. Specifically, the number of subcycles must be one greater than the ratio of the CFL timestep to the relaxation time of the material
Primary Subject
Record Type
Journal Article
Journal
Mathematics of Computation; ISSN 0025-5718;
; v. 36(155); p. 69-78

Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Donnelly, J.V.
Atomic Energy of Canada Ltd., Pinawa, MB (Canada). Whiteshell Nuclear Research Establishment1988
Atomic Energy of Canada Ltd., Pinawa, MB (Canada). Whiteshell Nuclear Research Establishment1988
AbstractAbstract
[en] The Atomic Energy of Canada Limited (AECL) version of the lattice cell code WIMS has been validated for pin-cell lattice calculation using ENDF/B-V nuclear data. In the evaluation, the resonance treatment in WIMS was determined to be sufficiently accurate for the configurations of current interest within AECL. In the analysis of thermal benchmark lattices, WIMS was found to be in good agreement with experiment and more rigorous calculations. 25 refs
Primary Subject
Secondary Subject
Source
1988; 61 p
Record Type
Report
Report Number
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] A new version of the lattice-cell code WIMSD, WIMSD-5A, has been developed on the request of NEA Data Bank in close co-operation with British specialists from AEA Technology, Winfrith. To this version of the code modifications enabling treatment of tubular fuel elements have been introduced. In the present paper the applied algorithm of modifications has been described and the errors introduced by the lack of correct approach to tubular elements have been estimated. Representative results obtained by the old code version and its associate library have been compared to those calculated by the new version of the code and its '86' library. These comparative results are presented for reactor lattices with M6 and WWR-M2 tubular fuels. (author). 6 figs, 7 tabs
Primary Subject
Record Type
Journal Article
Journal
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Mustafa, M; Nethaway, D R.
Lawrence Livermore National Laboratory (LLNL), Livermore, CA (United States). Funding organisation: USDOE Office of Defense Programs (United States)1999
Lawrence Livermore National Laboratory (LLNL), Livermore, CA (United States). Funding organisation: USDOE Office of Defense Programs (United States)1999
AbstractAbstract
[en] In this document we list the experimental data that were used to make up the major cross- section sets that we use in the Watusi code to calculate the amount of detector activation in device tests. In order to use experimental data to make up a cross-section set, it is often necessary to extrapolate the cross sections down to either the threshold energy or to 0.01 keV, and to extrapolate up to 20 MeV. We then fit the data to a function so that we can get a smoothed set of interpolated values at up to 321 energy points. The combined data are then processed with the Hiroshima code into flux-weighted, group-averaged cross sections for use with the output from the different physics design codes. We typically use the standard 53 or 175 energy group structures. In a recent companion memo 1 we described the make up of all of the cross-section sets in detail, giving references to both the experimental data and the theoretical calculations that were used. The following sections have the experimental data, in the form of energy-cross section pairs, for the titanium, chromium, bromine, krypton, yttrium, zirconium, iodine, europium, lutetium, and bismuth sets. The other cross-section sets are not directly based on enough experimental data to warrant their listing here. Many of the reactions used in these sets are based on calculated cross sections. In making these calculations certain parameters are sometimes adjusted so that the calculated cross sections match experimental data. In some of these cases we have made a further normalization to give a closer agreement to selected experimental data, and such normalizations are noted in this document. In other cases no further normalization was made. In Table 1 we summarize the reactions for which we present the experimental data given in Tables 2-46. In Figs. 1-35 we show plots of the experimental data together with the actual excitation functions used in the cross-section sets. Some reactions in the current sets are based on preliminary experimental data for which final results are now available. In those cases we show both the preliminary and the final data on the same plots. We expect to find only a few percent change in the calculated activation when we switch to the final experimental data
Primary Subject
Source
9 Feb 1999; 987 Kilobytes; CONTRACT W-7405-ENG-48; Available from OSTI; NTIS; URL:http://www.llnl.gov/tid/lof/documents/pdf/235139.pdf; US Govt. Printing Office Dep; DP0102011
Record Type
Report
Report Number
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Grote, D.P.; Friedman, A.; Haber, I.; Fawley, W.; Luc Vay, J.
Lawrence Livermore National Lab., CA (United States). Funding organisation: USDOE, Washington, DC (United States)1997
Lawrence Livermore National Lab., CA (United States). Funding organisation: USDOE, Washington, DC (United States)1997
AbstractAbstract
[en] The development of a high current, heavy-ion beam driver for inertial confinement fusion requires a detailed understanding of the behavior of the beam, including effects of the strong self-fields. The necessity of including the self-fields of the beam makes particle-in-cell (PIC) simulation techniques ideal, and for this reason, the multi-dimensional PIC/accelerator code WARP has been developed. WARP has been used extensively to study the creation and propagation of ion beams both in experiments and for the understanding of basic beam physics. An overview of the structure of the code will be presented along with a discussion of features that make the code an effective tool in the understanding of space-charge dominated beam behavior. Much development has been done on WARP increasing its flexibility and generality. Major additions include a generalized field description, an efficient steady-state modelling technique, a transverse slice model with a bending algorithm, further improvement of the parallel processing version, and capabilities for linking to chamber transport codes. With these additions, the capability of modeling a large scale accelerator from end-to-end comes closer to reality
Primary Subject
Source
7 Nov 1997; 11 p; 12. international symposium on heavy-ion inertial fusion; Heidelberg (Germany); 17-22 Sep 1997; CONF-9709166--; CONTRACT W-7405-ENG-48; ALSO AVAILABLE FROM OSTI AS DE98051473; NTIS; INIS; US GOVT. PRINTING OFFICE DEP
Record Type
Report
Literature Type
Conference
Report Number
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
1 | 2 | 3 | Next |