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Neutronics code VALE for two-dimensional triagonal (hexagonal) and three-dimensional geometries

Description: This report documents the computer code VALE designed to solve multigroup neutronics problems with the diffusion theory approximation to neutron transport for a triagonal arrangement of mesh points on planes in two- and three-dimensional geometry. This code parallels the VENTURE neutronics code in the local computation system, making exposure and fuel management capabilities available. It uses and generates interface data files adopted in the cooperative effort sponsored by Reactor Physics RRT … more
Date: August 1, 1981
Creator: Vondy, D.R. & Fowler, T.B.
Partner: UNT Libraries Government Documents Department
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Reference test problems for the VENTURE neutronics and related computer codes

Description: Sixteen problems were selected which collectively use many of the options and different calculational paths implemented in the VENTURE diffusion theory neutronics computer program. The input data requirements and key results are presented. This set of problems can be used as an essential part of validation testing of an implementation of, or modification to, the VENTURE and related codes.
Date: August 1, 1977
Creator: Vondy, D. R. & Fowler, T. B.
Partner: UNT Libraries Government Documents Department
open access

A two-dimensional, semi-analytic expansion method for nodal calculations

Description: Most modern nodal methods used today are based upon the transverse integration procedure in which the multi-dimensional flux shape is integrated over the transverse directions in order to produce a set of coupled one-dimensional flux shapes. The one-dimensional flux shapes are then solved either analytically or by representing the flux shape by a finite polynomial expansion. While these methods have been verified for most light-water reactor applications, they have been found to have difficulty… more
Date: August 1, 1995
Creator: Palmtag, S.P.
Partner: UNT Libraries Government Documents Department
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