An evaluation of five possible HCR sleeve materials for K Reactor

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The graphite stacks of the K reactors have been distorted to the extent that steel balls from the ball 3X system have entered some of the horizontal control rod channels and have interferred with the proper operation of the control system. One possible method of eliminating this potential hazard and attendant recurring production loss would be to place stationary sleeves around the horizontal control rods. Liners or sleeves in the vertical-ball and rod channels would prevent future leakage of balls into the moderator but would not eliminate the potential for balls already in the moderator to enter the horizontal control … continued below

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7 p.

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Bunch, W. L. & Agar, J. D. November 23, 1960.

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  • Hanford Atomic Products Operation
    Publisher Info: General Electric Co., Richland, WA (United States). Hanford Atomic Products Operation
    Place of Publication: Richland, Washington

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Description

The graphite stacks of the K reactors have been distorted to the extent that steel balls from the ball 3X system have entered some of the horizontal control rod channels and have interferred with the proper operation of the control system. One possible method of eliminating this potential hazard and attendant recurring production loss would be to place stationary sleeves around the horizontal control rods. Liners or sleeves in the vertical-ball and rod channels would prevent future leakage of balls into the moderator but would not eliminate the potential for balls already in the moderator to enter the horizontal control rod channels. For either horizontal or vertical liners it would be desirable to use an uncooled material which could withstand the reactor environment and which would not adversely affect the operation and production capacity of the reactor. The nuclear properties of five different materials have been reviewed to determine the maximum temperature which might be attained by each material when used as an uncooled sleeve, the effect each would have on the reactivity of the reactor, and the effect of each on the control capacity of the horizontal rod system. The five materials considered were: Inconel, a 300 series stainless steel, Zircaloy-2, aluminum oxide, and zirconium silicate.

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7 p.

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OSTI as DE94012424; Paper copy available at OSTI: phone, 865-576-8401, or email, reports@adonis.osti.gov

Other Information: DN: Declassified

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  • November 23, 1960

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  • Nov. 3, 2018, 11:47 a.m.

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  • Nov. 14, 2024, 3:36 a.m.

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Bunch, W. L. & Agar, J. D. An evaluation of five possible HCR sleeve materials for K Reactor, report, November 23, 1960; Richland, Washington. (https://digital.library.unt.edu/ark:/67531/metadc1313221/: accessed September 16, 2026), University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.

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