Neutronic data in support of space nuclear propulsion

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The thermophysical properties of lithium hydride ({sup 7}LiH), particularly small density (0.775 gm/cc), high melting point (688 C) and relatively high hydrogen atomic number density makes it an attractive material for use as a neutron moderator and shield (for LiH) in space nuclear thermal propulsion. However, the unavailability of neutronic cross section data in the thermal energy range for {sup 7}LiH in the ENDF/B library necessitated the generation of the relevant data which is required in criticality studies and for the determination of temperature-dependent feedback coefficients in the moderator and fuel regions. Here, the scattering kernel data for {sup 7}LiH ... continued below

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4 p.

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Mughabghab, S.; Schmidt, E. & Ludewig, H. July 1, 1997.

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Description

The thermophysical properties of lithium hydride ({sup 7}LiH), particularly small density (0.775 gm/cc), high melting point (688 C) and relatively high hydrogen atomic number density makes it an attractive material for use as a neutron moderator and shield (for LiH) in space nuclear thermal propulsion. However, the unavailability of neutronic cross section data in the thermal energy range for {sup 7}LiH in the ENDF/B library necessitated the generation of the relevant data which is required in criticality studies and for the determination of temperature-dependent feedback coefficients in the moderator and fuel regions. Here, the scattering kernel data for {sup 7}LiH have been generated for the first time in the temperature range 50--1,000 K. This is based on a phonon distribution function derived from both experimental data and theoretical calculations. A detailed study of the variation of the moderator temperature coefficient {alpha}{sub m}(T) with temperature, T, is carried out for a typical space nuclear reactor of the particle bed type. It is established that the moderator temperature coefficient is proportional to T{sup {minus}1.65} where T is the moderator temperature in Kelvin units.

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4 p.

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INIS; OSTI as DE97006750

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  • International conference on nuclear data for science and technology, Trieste (Italy), 20-24 May 1997

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  • Other: DE97006750
  • Report No.: BNL--64419
  • Report No.: CONF-970512--6
  • Grant Number: AC02-76CH00016
  • Office of Scientific & Technical Information Report Number: 495776
  • Archival Resource Key: ark:/67531/metadc676916

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Office of Scientific & Technical Information Technical Reports

Reports, articles and other documents harvested from the Office of Scientific and Technical Information.

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  • July 1, 1997

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  • July 25, 2015, 2:21 a.m.

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  • Nov. 9, 2015, 8:12 p.m.

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Mughabghab, S.; Schmidt, E. & Ludewig, H. Neutronic data in support of space nuclear propulsion, article, July 1, 1997; Upton, New York. (digital.library.unt.edu/ark:/67531/metadc676916/: accessed December 15, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.