An empirical prediction of temperature gradients in moderator graphite within operating nuclear reactors

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100 1 ‡aCarter, Robert L.
245 1 3 ‡aAn empirical prediction of temperature gradients in moderator graphite within operating nuclear reactors / ‡cby Robert L. Carter.
260 ‡aCanoga Park, California : ‡bAtomics International, ‡c[1962]
300 ‡avi, 44 pages : ‡billustrations ; ‡c28 cm.
336 ‡atext ‡btxt ‡2rdacontent
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490 0 ‡aNAA (Series) ; ‡vSR-6616
490 0 ‡aAEC research and development report
500 ‡a"NAA-SR-6616 ; Reactor technology."
500 ‡a"Contract AT(11-1)-GEN-8 ; Issued: Feb 15 1962."
504 ‡aIncludes bibliographical references (page 44).
538 ‡aMode of access: Internet.
650 7 ‡aSodium graphite reactors. ‡2fast ‡0(OCoLC)fst01124068
650 7 ‡aGraphite ‡xThermal properties. ‡2fast ‡0(OCoLC)fst00946674
650 0 ‡aSodium graphite reactors.
650 0 ‡aGraphite ‡xThermal properties.
710 2 ‡aNorth American Aviation. ‡bAtomics International Division.
710 2 ‡aU.S. Atomic Energy Commission.
730 0 ‡aTechnical Report Archive & Image Library (TRAIL)
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