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Review of physics methodology of ATR safety analysis

Description: At the request of EG G Idaho, the Pacific Northwest Laboratory (PNL) performed a brief review of the physics methods employed in the safety analyses for the Advanced Test Reactor. PNL determined that the general approach used by EG G was sound. Comparisons were made between the EG G results and a simplified PBL model. These demonstrated good agreement. However, the lack of spacial treatment of the moderator density reactivity coefficient and exclusion of the test loops from the reactivity model were identified as potential problems. In addition to these two concerns, a series of more minor observations were offered to assist EG G in their analyses. 2 refs., 2 figs.
Date: September 1, 1991
Creator: Little, W.W. & Heaberlin, S.W.
Partner: UNT Libraries Government Documents Department

1DB, a one-dimensional diffusion code for nuclear reactor analysis

Description: 1DB is a multipurpose, one-dimensional (plane, cylinder, sphere) diffusion theory code for use in reactor analysis. The code is designed to do the following: To compute k{sub eff} and perform criticality searches on time absorption, reactor composition, reactor dimensions, and buckling by means of either a flux or an adjoint model; to compute collapsed microscopic and macroscopic cross sections averaged over the spectrum in any specified zone; to compute resonance-shielded cross sections using data in the shielding factor format; and to compute isotopic burnup using decay chains specified by the user. All programming is in FORTRAN. Because variable dimensioning is employed, no simple restrictions on problem complexity can be stated. The number of spatial mesh points, energy groups, upscattering terms, etc. is limited only by the available memory. The source file contains about 3000 cards. 4 refs.
Date: September 1, 1991
Creator: Little, W.W. Jr. (Pacific Northwest Lab., Richland, WA (United States))
Partner: UNT Libraries Government Documents Department