Development of Uranium Nitride-Stainless Steel Dispersion Fuel Elements

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In research in support of the GCRE, procedures for the fabrication of stainless steel-clad flat-plate fuel elements having a core of 28 w/o UN dispersed in an iron-18 w/o chromium--14 w/o nickel--2.5 w/o molybdenum matrix were developed. The preparation of UN and its compatibility with the components of the matrix alloy were studied. The UN for the program was prepared by nitriding uranium metal at 850 C and then dissociating the U/sub 2/N/sub 3/ produced to UN in a vacuum at 1300 C. In compatibility studies, UN reacted with nickel alone at 1800 F, but no reaction with nickel was … continued below

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22 pages

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Paprocki, S. J.; Keller, D. L.; Cunningham, G. W. & Foulds Jr., A. K. July 31, 1959.

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Description

In research in support of the GCRE, procedures for the fabrication of stainless steel-clad flat-plate fuel elements having a core of 28 w/o UN dispersed in an iron-18 w/o chromium--14 w/o nickel--2.5 w/o molybdenum matrix were developed. The preparation of UN and its compatibility with the components of the matrix alloy were studied. The UN for the program was prepared by nitriding uranium metal at 850 C and then dissociating the U/sub 2/N/sub 3/ produced to UN in a vacuum at 1300 C. In compatibility studies, UN reacted with nickel alone at 1800 F, but no reaction with nickel was observed when the other matrix components were also present. The effects of fabricational variables were evaluated by metallographic examination, longitudinal and transverse tensile tests, bend tests, and corrosion tests. Studies indicated that minus 200 plus 325-mesh UN dispersed in a minus 325-mesh elemental-powder matrix rolled green vith a 30 per cent initial reduction at 2100 F and then annealed 3 hr at 2300 F produced the best fuel core. (auth)

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22 pages

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  • Other Information: Orig. Receipt Date: 31-DEC-59

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Office of Scientific & Technical Information Technical Reports

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  • July 31, 1959

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  • Oct. 15, 2017, 10:09 p.m.

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  • Jan. 12, 2021, 12:50 p.m.

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Paprocki, S. J.; Keller, D. L.; Cunningham, G. W. & Foulds Jr., A. K. Development of Uranium Nitride-Stainless Steel Dispersion Fuel Elements, report, July 31, 1959; Columbus, Ohio. (https://digital.library.unt.edu/ark:/67531/metadc1021039/: accessed March 5, 2024), University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.

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