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Wallace, O.J.
Bettis Atomic Power Lab., West Mifflin, Pa. (USA)1976
Bettis Atomic Power Lab., West Mifflin, Pa. (USA)1976
AbstractAbstract
[en] SPAR1 calculates exact gamma-ray fluxes from uniform sources with the shapes of slabs, disks, lines, cylinders, truncated cones, toroids and spheres. Gamma-ray dose rates and energy absorption rates may also be obtained by including in the program input data gamma-ray buildup factors expressed in Taylor exponential coefficient form. SPAR1 will calculate fast neutron dose rates and thermal neutron fluxes in those cases where the use of neutron removal cross sections is valid. All 3-D sources having curved surfaces (cylinders, spheres, and toroids) may have both curved and slab shields intervening between the source and the detector point. The treatment of cylindrical volume sources allows the detector point to be arbitrarily located, and a finite cylindrical shield may be considered. A cylindrical surface source option is also included. In all cases, uniform source strength, laminar shields, and the validity of the point kernel are assumed. It is always possible to formally integrate over at least one dimension of a three-dimensional source, leaving a non-singular integrand to be numerically evaluated over at most two dimensions. This numeric integration is done using Gauss-Lengendre quadranumeric. SPAR1 is designed to furnish quick answers to simple shielding problems such as those encountered in scoping studies and in answering urgent questions, and thus to save engineering time. This program is written in FORTRAN IV and is designed to run on a CDC-6600
Original Title
Uniform sources--slabs, disks, lines, cylinders, truncated cones, toroids, spheres, in FORTRAN IV for CDC-6600
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Jun 1976; 154 p; Available from NTIS. $6.75.
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Wallace, O.J.
Bettis Atomic Power Lab., Pittsburgh, Pa. (USA)1974
Bettis Atomic Power Lab., Pittsburgh, Pa. (USA)1974
AbstractAbstract
No abstract available
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Jun 1974; 58 p
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Report
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Wallace, O.J.
Bettis Atomic Power Lab., West Mifflin, PA (USA)1981
Bettis Atomic Power Lab., West Mifflin, PA (USA)1981
AbstractAbstract
[en] Hand calculations of radiation flux and dose rates are often useful in evaluating radiation shielding and in determining the scope of a problem. The flux formulas appropriate to such calculations are almost always based on the point kernel and allow for at most the consideration of laminar slab shields. These formulas often require access to tables of values of integral functions for effective use. Flux formulas and function tables appropriate to calculations involving homogeneous source regions with the shapes of lines, disks, slabs, truncated cones, cylinders, and spheres are presented. Slab shields may be included in most of these calculations, and the effect of a cylindrical shield surrounding a cylindrical source may be estimated. Detector points may be located axially, laterally, or interior to a cylindrical source. Line sources may be tilted with respect to a slab shield. All function tables are given for a wide range of arguments
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Source
Jun 1981; 180 p; Available from NTIS., PC A09/MF A01
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Report
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Numerical Data
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ABSORPTION, ATTENUATION, BUILDUP, COMPILED DATA, CONFIGURATION, CONICAL CONFIGURATION, CYLINDERS, DOSE RATES, EQUATIONS, GAMMA RADIATION, IRON, KERNELS, LEAD, NEUTRON TRANSPORT, NEUTRONS, NUMERICAL DATA, NUMERICAL SOLUTION, PHOTON TRANSPORT, POINT KERNELS, RADIATION DOSES, RADIATION FLUX, SELF-ABSORPTION, SHIELDING, SHIELDING MATERIALS, SLABS, SPHERES, WATER
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Wallace, O.J.
Bettis Atomic Power Lab., West Mifflin, Pa. (USA)1976
Bettis Atomic Power Lab., West Mifflin, Pa. (USA)1976
AbstractAbstract
[en] A special coordinate system based on the work of H. Ono and A. Tsuro has been used to derive exact semi-analytic formulas for the flux from cylindrical, spherical, toroidal, rectangular, annular and truncated cone volume sources; from cylindrical, spherical, truncated cone, disk and rectangular surface sources; and from curved and tilted line sources. In most of the cases where the source is curved, shields of the same curvature are allowed in addition to the standard slab shields; cylindrical shields are also allowed in the rectangular volume source flux formula. An especially complete treatment of a cylindrical volume source is given, in which dose points may be arbitrarily located both within and outside the source, and a finite cylindrical shield may be considered. Detector points may also be specified as lying within spherical and annular source volumes. The integral functions encountered in these formulas require at most two-dimensional numeric integration in order to evaluate the flux values. The classic flux formulas involving only slab shields and slab, disk, line, sphere and truncated cone sources become some of the many special cases which are given in addition to the more general formulas mentioned above
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Jun 1976; 193 p; Available from NTIS. $7.50.
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Report
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Wallace, O.J.
Westinghouse Electric Corp., West Mifflin, PA (United States). Bettis Atomic Power Lab. Funding organisation: USDOE, Washington, DC (United States)1994
Westinghouse Electric Corp., West Mifflin, PA (United States). Bettis Atomic Power Lab. Funding organisation: USDOE, Washington, DC (United States)1994
AbstractAbstract
[en] An exact semi-analytic formula for the flux from a rectangular surface source with a slab shield has been derived and the required function table has been calculated. This formula is the basis for an algorithm which gives a good approximation for the flux from a rectangular volume source. No other hand calculation method for this source geometry is available in the literature
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Source
9 Nov 1994; 14 p; International conference on mathematics and computations, reactor physics, and environmental analyses; Portland, OR (United States); 30 Apr - 4 May 1995; CONF-950420--11; CONTRACT AC11-93PN38195; Also available from OSTI as DE95003030; NTIS; US Govt. Printing Office Dep
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Report
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Conference
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Wallace, O.J.
Westinghouse Electric Corp., West Mifflin, PA (United States). Bettis Atomic Power Lab. Funding organisation: USDOE, Washington, DC (United States)1994
Westinghouse Electric Corp., West Mifflin, PA (United States). Bettis Atomic Power Lab. Funding organisation: USDOE, Washington, DC (United States)1994
AbstractAbstract
[en] A semi-analytic approximate formula for the flux at a point outside the radial and axial extensions of a cylindrical source with an intervening slab shield perpendicular to the source axis has been derived, based on the work of Ono and Tsuro. The required function tables are available, and a detailed analysis of the error as a function of problem geometry has been calculated, so that this formula has a wide area of application. No other approximate calculation method for this case is available in the literature
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1994; 6 p; Winter meeting of the American Nuclear Society; Washington, DC (United States); 13-18 Nov 1994; CONF-941102--20; CONTRACT AC11-93PN38195; Also available from OSTI as DE94017143; NTIS; US Govt. Printing Office Dep
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Wallace, O.J.
Westinghouse Electric Corp., West Mifflin, PA (United States). Bettis Atomic Power Lab. Funding organisation: USDOE, Washington, DC (United States)1992
Westinghouse Electric Corp., West Mifflin, PA (United States). Bettis Atomic Power Lab. Funding organisation: USDOE, Washington, DC (United States)1992
AbstractAbstract
[en] Hand calculation methods for radiation shielding problems continue to be useful for scoping studies, for checking the results from sophisticated computer simulations and in teaching shielding personnel. This paper presents two algorithms which give improved results for hand calculations of the flux at a lateral detector point from a cylindrical source with an intervening slab shield parallel to the cylinder axis. The first algorithm improves the accuracy of the approximate flux flux formula of Ono and Tsuro so that results are always conservative and within a factor of two. The second algorithm uses the first algorithm and the principle of superposition of sources to give a new approximate method for finding the flux at a detector point outside the axial and radial extensions of a cylindrical source. A table of error ratios for this algorithm versus an exact calculation for a wide range of geometry parameters is also given. There is no other hand calculation method for the geometric configuration of the second algorithm available in the literature
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Source
1992; 7 p; Joint American Nuclear Society (ANS)/European Nuclear Society (ENS) international meeting on fifty years of controlled nuclear chain reaction: past, present, and future; Chicago, IL (United States); 15-20 Nov 1992; CONF-921102--63; CONTRACT AC11-93PN38195; Also available from OSTI as DE94002524; NTIS; US Govt. Printing Office Dep
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AbstractAbstract
[en] Hand-calculation methods involving semianalytic approximations of exact flux formulas continue to be useful in shielding calculations because they enable shield design personnel to make quick estimates of dose rates, check calculations made be more exact and time-consuming methods, and rapidly determine the scope of problems. They are also a valuable teaching tool. The most useful approximate flux formula is that for the flux at a lateral detector point from a cylindrical source with an intervening slab shield. Such an approximate formula is given by Rockwell. An improved formula for this case is given by Ono and Tsuro. Shure and Wallace also give this formula together with function tables and a detailed survey of its accuracy. The second section of this paper provides an algorithm for significantly improving the accuracy of the formula of Ono and Tsuro. The flux at a detector point outside the radial and axial extensions of a cylindrical source, again with an intervening slab shield, is another case of interest, but nowhere in the literature is this arrangement of source, shield, and detector point treated. In the third section of this paper, an algorithm for this case is given, based on superposition of sources and the algorithm of Section II. 6 refs., 1 fig., 1 tab
Primary Subject
Source
Joint American Nuclear Society (ANS)/European Nuclear Society (ENS) international meeting on fifty years of controlled nuclear chain reaction: past, present, and future; Chicago, IL (United States); 15-20 Nov 1992; CONF-921102--
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Journal Article
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AbstractAbstract
No abstract available
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Journal Article
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Nuclear Science and Engineering; v. 56(1); p. 84-94
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AbstractAbstract
[en] Coefficients have been determined for the Taylor two-exponential representation of the Eisenhauer-Simmons gamma-ray buildup factors in ordinary concrete. 7 tables
Original Title
15 keV to 15 MeV
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Journal Article
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Nuclear Science and Engineering; v. 62(4); p. 736-770
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