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‡aY 3.At 7:22/NAA-SR-6616
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‡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.
|
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⊔ |
⊔ |
‡atext
‡btxt
‡2rdacontent
|
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⊔ |
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‡aunmediated
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‡aAEC research and development report
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⊔ |
⊔ |
‡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.
|
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⊔ |
7 |
‡aSodium graphite reactors.
‡2fast
‡0(OCoLC)fst01124068
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‡aGraphite
‡xThermal properties.
‡2fast
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‡aSodium graphite reactors.
|
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⊔ |
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‡aGraphite
‡xThermal properties.
|
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⊔ |
‡aNorth American Aviation.
‡bAtomics International Division.
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⊔ |
‡aU.S. Atomic Energy Commission.
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‡aTechnical Report Archive & Image Library (TRAIL)
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