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  • 1970-1974  (16)
  • 1
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    Probable solar flare doses encountered on an interplanetary mission as calculated by the MCFLARE code (1972)
    In:  CASI
    Details
    Publication Date: 2016-06-07
    Description: The computer program, MCFLARE, uses Monte Carlo methods to simulate solar flare occurrences during an interplanetary space voyage. The total biological dose inside a shielded crew compartment due to the flares encountered during the voyage is determined. The computer program evaluates the doses obtained on a large number of trips having identical trajectories. From these results, a dose D sub p having a probability p of not being exceeded during the voyage can be determined as a function of p for any shield material configuration. To illustrate the use of the code, a trip to Mars and return is calculated, and estimated doses behind several thicknesses of aluminum shield and water shield are presented.
    Keywords: SPACE RADIATION
    Type: Proc. of the Natl. Symp. on Nat. and Manmade Radiation in Space; p 324-328
    Format: application/pdf
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    NASA TECHNICAL REPORTS
  • 2
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    DOPEX-1D2C: A one-dimensional, two-constraint radiation shield optimization code (1973)
    In:  CASI
    Details
    Publication Date: 2019-06-27
    Description: A one-dimensional, two-constraint radiation sheild weight optimization procedure and a computer program, DOPEX-1D2C, is described. The DOPEX-1D2C uses the steepest descent method to alter a set of initial (input) thicknesses of a spherical shield configuration to achieve a minimum weight while simultaneously satisfying two dose-rate constraints. The code assumes an exponential dose-shield thickness relation with parameters specified by the user. Code input instruction, a FORTRAN-4 listing, and a sample problem are given. Typical computer time required to optimize a seven-layer shield is less than 1/2 minute on an IBM 7094.
    Keywords: NUCLEAR ENGINEERING
    Type: NASA-TM-X-2836 , E-7421
    Format: application/pdf
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    NASA TECHNICAL REPORTS
  • 3
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    Application of the method of steepest descent to laminated shield weight optimization with several constraints: Theory (1971)
    In:  CASI
    Details
    Publication Date: 2019-06-27
    Description: The method of steepest descent used in optimizing one-dimensional layered radiation shields is extended to multidimensional, multiconstraint situations. The multidimensional optimization algorithm and equations are developed for the case of a dose constraint in any one direction being dependent only on the shield thicknesses in that direction and independent of shield thicknesses in other directions. Expressions are derived for one-, two-, and three-dimensional cases (one, two, and three constraints). The precedure is applicable to the optimization of shields where there are different dose constraints and layering arrangements in the principal directions.
    Keywords: NUCLEAR ENGINEERING
    Type: NASA-TM-X-2435 , E-6542
    Format: application/pdf
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    NASA TECHNICAL REPORTS
  • 4
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    Effect of angular quadrature on results of two-dimensional space power reactor shield calculations (1971)
    In:  CASI
    Details
    Publication Date: 2019-06-27
    Description: Effect of angular quadrature on results of two dimensional space power reactor shield calculations
    Keywords: NUCLEAR ENGINEERING
    Type: NASA-TM-X-67937 , E-6615
    Format: application/pdf
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    NASA TECHNICAL REPORTS
  • 5
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    Measured and calculated fast neutron spectra in a lead-and-water shielded reactor (1971)
    In:  CASI
    Details
    Publication Date: 2019-06-27
    Description: Comparison of calculated and liquid scintillation measured fast neutron spectra in layered cylindrical shield of UOF2-water solution reactor
    Keywords: NUCLEAR ENGINEERING
    Type: NASA-TM-X-67861 , E-6394
    Format: application/pdf
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    NASA TECHNICAL REPORTS
  • 6
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    NASA-Lewis experiences with multigroup cross sections and shielding calculations. (1972)
    In:  Other Sources
    Details
    Publication Date: 2019-07-13
    Description: Description of the nuclear reactor shield analysis procedures employed at NASA-Lewis Research Center. Emphasis is placed on the generation, use, and testing of multigroup cross-section data. Although coupled neutron and gamma ray cross-section sets are useful in two-dimensional Sn transport calculations, much insight has been gained from examination of uncoupled calculations. These have led to experimental and analytic studies of areas deemed to be of first-order importance to reactor shield calculations. A discussion is given of problems encountered in using multigroup cross sections in the resolved resonance energy range. The addition to ENDF files of calculated and/or measured neutron-energy-dependent capture gamma ray spectra for shielding calculations is questioned for the resonance region. Anomalies inherent in two-dimensional Sn transport calculations which may overwhelm any cross-section discrepancies are illustrated.
    Keywords: NUCLEAR ENGINEERING
    Type: American Nuclear Society, Annual Meeting; Jun 18, 1972 - Jun 22, 1972; Las Vegas, NV
    Format: text
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    NASA TECHNICAL REPORTS
  • 7
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    NASA-Lewis experiences with multigroup cross sections and shielding calculations (1972)
    In:  CASI
    Details
    Publication Date: 2019-07-13
    Description: The nuclear reactor shield analysis procedures employed at NASA-Lewis are described. Emphasis is placed on the generation, use, and testing of multigroup cross section data. Although coupled neutron and gamma ray cross section sets are useful in two dimensional Sn transport calculations, much insight has been gained from examination of uncoupled calculations. These have led to experimental and analytic studies of areas deemed to be of first order importance to reactor shield calculations. A discussion is given of problems encountered in using multigroup cross sections in the resolved resonance energy range. The addition to ENDF files of calculated and/or measured neutron-energy-dependent capture gamma ray spectra for shielding calculations is questioned for the resonance region. Anomalies inherent in two dimensional Sn transport calculations which may overwhelm any cross section discrepancies are illustrated.
    Keywords: NUCLEAR ENGINEERING
    Type: NASA-TM-X-68080 , E-6970 , Am. Nucl. Soc. Meeting; Jun 18, 1972 - Jun 22, 1972; Las Vegas, NV; United States
    Format: application/pdf
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    NASA TECHNICAL REPORTS
  • 8
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    Probable solar flare doses encountered on an interplanetary mission as calculated by the MCFLARE code (1971)
    In:  CASI
    Details
    Publication Date: 2019-06-27
    Description: MCFLARE code to calculate probable flare doses encountered on interplanetary mission
    Keywords: SPACE RADIATION
    Type: NASA-TM-X-52971 , E-4027
    Format: application/pdf
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    NASA TECHNICAL REPORTS
  • 9
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    Measured and calculated fast neutron spectra in a depleted uranium and lithium hydride shielded reactor (1973)
    In:  CASI
    Details
    Publication Date: 2019-06-27
    Description: Measurements of MeV neutron were made at the surface of a lithium hydride and depleted uranium shielded reactor. Four shield configurations were considered: these were assembled progressively with cylindrical shells of 5-centimeter-thick depleted uranium, 13-centimeter-thick lithium hydride, 5-centimeter-thick depleted uranium, 13-centimeter-thick lithium hydride, 5-centimeter-thick depleted uranium, and 3-centimeter-thick depleted uranium. Measurements were made with a NE-218 scintillation spectrometer; proton pulse height distributions were differentiated to obtain neutron spectra. Calculations were made using the two-dimensional discrete ordinates code DOT and ENDF/B (version 3) cross sections. Good agreement between measured and calculated spectral shape was observed. Absolute measured and calculated fluxes were within 50 percent of one another; observed discrepancies in absolute flux may be due to cross section errors.
    Keywords: NUCLEAR ENGINEERING
    Type: NASA-TM-X-2906 , E-7485
    Format: application/pdf
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    NASA TECHNICAL REPORTS
  • 10
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    Multigroup resonance-region cross sections for tungsten and depleted uranium for use in shielding calculations (1970)
    In:  CASI
    Details
    Publication Date: 2019-06-27
    Description: Multigroup resonance region cross sections for tungsten and depleted uranium for use in shielding calculations
    Keywords: NUCLEAR ENGINEERING
    Type: NASA-TM-X-1909 , E-5155
    Format: application/pdf
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    NASA TECHNICAL REPORTS
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