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PAKISTAN INSTITUTE OF ENGINEERING AND APPLIED SCIENCES FUNDAMENTALS OF NUCLEAR ENGINEERING Cross-section Practice Problems 1. In a reactor U 3 Si 2 is used as fuel with Uranium enriched to 19.99 weight percent of U-235. The density of fuel is 3.5898 g/ cm 3 . Find the number density of Si, 235 U and 238 U. 2. Natural Uranium contains 99.28 weight percent of U-238 (σ a = 2.71 barns) and 0.72 weight percent of U-235 (σ a = 683 barns). Density of natural Uranium metal is 19 g/cm 3 . Determine the macroscopic and microscopic absorption cross- section of Uranium metal. 3. SS-304 has density of 7.86 g/cm 3 . Its composition by weight is as follows: Carbon-12 0.08% (σ a = 0.0034 b), Chromium-52 19% (σ a = 3.1 b), Nickel-59 10% (σ a = 4.43 b) and remainder is Iron-56 (σ a = 2.55 b). Find the macroscopic absorption cross-section of SS-304.

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Problems regarding nuclear engineering

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  • PAKISTAN INSTITUTE OF ENGINEERING AND APPLIED SCIENCES

    FUNDAMENTALS OF NUCLEAR ENGINEERING

    Cross-section Practice Problems

    1. In a reactor U3Si2 is used as fuel with Uranium enriched to

    19.99 weight percent of U-235. The density of fuel is 3.5898

    g/ cm3. Find the number density of Si, 235U and 238U.

    2. Natural Uranium contains 99.28 weight percent of U-238 (a =

    2.71 barns) and 0.72 weight percent of U-235 (a = 683

    barns). Density of natural Uranium metal is 19 g/cm3.

    Determine the macroscopic and microscopic absorption cross-

    section of Uranium metal.

    3. SS-304 has density of 7.86 g/cm3. Its composition by weight is

    as follows: Carbon-12 0.08% (a = 0.0034 b), Chromium-52

    19% (a = 3.1 b), Nickel-59 10% (a = 4.43 b) and remainder

    is Iron-56 (a = 2.55 b). Find the macroscopic absorption

    cross-section of SS-304.