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TWO AUXILIARY CODES FOR USE WITH RENUPAK

Description: Two IBM-7090 codes were written to aid the user of the neutron moments method code RENUPAK. One code computes and punches response function input cards for RENUPAK or NIOBE (another neutron transport code). The second code reads RENUPAK flux tapes and prints out a compact edit including dose rate as a function of distance. (auth)
Date: August 10, 1962
Creator: Trubey, D.K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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ANS shielding standards for light-water reactors

Description: The purpose of the American Nuclear Society Standards Subcommittee, ANS-6, Radiation Protection and Shielding, is to develop standards for radiation protection and shield design, to provide shielding information to other standards-writing groups, and to develop standard reference shielding data and test problems. A total of seven published ANS-6 standards are now current. Additional projects of the subcommittee, now composed of nine working groups, include: standard reference data for multigrou… more
Date: January 1, 1982
Creator: Trubey, D. K.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Radiation protection and shielding standards for the 1980s

Description: The American Nuclear Society (ANS) is a standards-writing organization member of the American National Standards Institute (ANSI). The ANS Standards Committee has a subcommittee denoted ANS-6, Radiation Protection and Shielding, whose charge is to develop standards for radiation protection and shield design, to provide shielding information to other standards-writing groups, and to develop standard reference shielding data and test problems. This paper is a progress report of this subcommittee.… more
Date: January 1, 1982
Creator: Trubey, D.K.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Standard reference data for gamma-ray transport in homogeneous media. [PWR; BWR]

Description: An American Nuclear Society Standards Committee Working Group, identified as ANS-6.4.3, is developing a set of evaluated gamma-ray isotropic point-source buildup factors and attenuation coefficients for a standard reference data base. As a first step, a largely unpublished set of buildup factors calculated with the moments method is being evaluated by recalculating key values with Monte Carlo, integral transport, and discrete ordinates methods. Attention is being given to frequently neglected p… more
Date: January 1, 1983
Creator: Trubey, D. K.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Tabulated Values of Scattered Gamma-Ray Fluxes in Water Interpolated From Moments Method Calculations

Description: Tables of scattered gamma-ray fluxes in water that are suitable for integration over source spectra were generated on the IBM-7090 computer by Lagrangian interpolation of moments method results for point isotropic gamma-ray sources. Values of the fluxes were obtained for a consistent set of scattered gamma-ray energies taken in steps of 0.1 Mev from 0.1 to 1.0 Mev and in steps of 0.25 Mev from 0.25 to 10 Mev. One table was obtained for each scattered energy for various values of the source ener… more
Date: July 29, 1963
Creator: Trubey, D. K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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New buildup factor data for point kernel calculations

Description: An American Nuclear Society Standards Committee Working Group, identified as ANS-6.4.3, is developing a set of evaluated gamma-ray isotropic point-source buildup factors and attenuation coefficients for a standard reference data base. As a first step, a largely unpublished set of buildup factors calculated with the moments method has been evaluated by recalculating key values with Monte Carlo, integral transport, and discrete ordinates methods. Attention is being given to frequently-neglected p… more
Date: January 1, 1986
Creator: Trubey, D. K. & Harima, Y.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Specific gamma-ray dose constants for nuclides important to dosimetry and radiological assessment

Description: Tables of specific gamma-ray dose constants (the unshielded gamma-ray dose equivalent rate at 1 m from a point source) have been computed for approximately 500 nuclides important to dosimetry and radiological assessment. The half life, the mean attenuation coefficient, and thickness for a lead shield providing 95% dose equivalent attenuation are also listed.
Date: May 1, 1982
Creator: Unger, L.M. & Trubey, D.K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Specific gamma-ray dose constants for nuclides important to dosimetry and radiological assessment

Description: Tables of specific gamma-ray dose constants (the unshielded gamma-ray dose equivalent rate at 1 m from a point source) have been computed for approximately 500 nuclides important to dosimetry and radiological assessment. The half life, the mean attenuation coefficient, and thickness for a lead shield providing 95% dose equivalent attenuation are also listed.
Date: September 1, 1981
Creator: Unger, L.M. & Trubey, D.K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

DEPOSITION OF GAMMA-RAY HEATING IN STRATIFIED LEAD AND WATER SLABS

Description: Typical results are given from a calculation of the deposition of heat in stratified lead and water slabs caused by a monodirectional, monoenergetic beam of gamma rays incident on the slabs. A total of 512 cases were calculated for infinite slabs with finite thicknesses of 1, 2, 4, and 6 mean free paths; source energies of 1, 3, 8, and 10 Mev, and source angles of incidence which were chosen to give slant slab thicknesses of 1, 2, 3, and 4 times the normal thickness. The results were fitted to … more
Date: July 28, 1958
Creator: Bowman, L. A. & Trubey, D. K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Radiation protection and shielding standards

Description: Radiation protection and shielding standards being prepared by the American Nuclear Society and by the Health Physics Society are reviewed. Major problems which must be resolved are discussed.
Date: January 1, 1977
Creator: Vallario, E. J. & Trubey, D. K.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

A System for Generating Gamma Ray Cross Section Data for Use with the IBM-7090 Computer

Description: A system for generating detailed tables of gamma ray cross section data has been devised for use on the IBM7090 computer. This sy;tem obviates the preparation of large amounts of cross section data. It also provides a scheme for rapid access to these tabulated values. (auth)
Date: May 16, 1962
Creator: Penny, S. K.; Emmett, M. B. & Trubey, D. K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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OGRE-P2, a Monte Carlo Program for Computing Gamma-Ray Leakage From Laminated Slabs With a Distributed Source

Description: A Monte Carlo program OGRE-P2 was written for the IBM-7090 to solve the problem of gamma radiation from a slab of laminated regions composed of various materials. The dose rate is calculated on one side of the slab. (J.R,D.)
Date: August 10, 1962
Creator: Trubey, D. K.; Penny, S. K. & Emmett, M. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Gamma-ray dose at shield-tissue interfaces and buildup factor implications

Description: Buildup factors continue to be widely used for gamma-ray shield design, but there are several problems in application. Shure has pointed out the need for buildup factors to be consistent with the ANSI standard flux-to-dose factors. However, consistent buildup factor data cannot be obtained by simply integrating the ANSI response function over infinite-medium spectra, because this function gives the response at various depths in a tissue phantom for a gamma ray of a certain energy entering the p… more
Date: January 1, 1982
Creator: Trubey, D. K.; Gopinath, D. V. & Subbaiah, K. V.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Recent trends in radiation shielding: a RSIC perspective

Description: The subject of radiation transport and shielding in the nuclear power industry is reviewed, and advances in the state of the art are described. These fall into the areas of computational methods, nuclear cross sections, industry practices, and standards. Computer codes and data available from the Radiation Shielding Information Center (RSIC) representing recent advances are also described.
Date: January 1, 1979
Creator: Trubey, D. K.; Roussin, R. W. & Maskewitz, B. F.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Status of multigroup cross-section data for shielding applications

Description: Multigroup cross-section libraries for shielding applications in formats for direct use in discrete ordinates or Monte Carlo codes have long been a part of the Data Library Collection (DLC) of the Radiation Shielding Information Center (RSIC). In recent years libraries in more flexible and comprehensive formats, which allow the user to derive his own problem-dependent sets, have been added to the collection. The current status of both types is described, as well as projections for adding data l… more
Date: January 1, 1983
Creator: Roussin, R. W.; Maskewitz, B. F. & Trubey, D. K.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Photon cross sections for ENDF/B-VI

Description: The PHOTX library of the National Institute of Standards and Technology will be used as the basis of File 23 (photon cross sections) for ENDF/B-VI. The PHOTX library is based on an experimental data base consisting of 21,000 data points from 512 literature sources for 82 elements. An important difference from earlier compilations is that renormalization of photo-effect cross sections is not performed. 40 refs., 12 figs.
Date: January 1, 1989
Creator: Trubey, D. K.; Berger, M. J. & Hubbell, J. H.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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