In-pile loop investigations of corrosion of Zircaloy-2 and other possible reactor materials in 0.04 m UO₂SO₄ at 280°C /

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Bibliographic Details
Main Author: Jenks, G. H. (Glenn Herbert), 1916-
Corporate Authors: U.S. Atomic Energy Commission, Oak Ridge National Laboratory
Other Authors: Baker, J. E.
Format: Government Document Book
Language:English
Published: Oak Ridge, Tenn. : Oak Ridge National Laboratory, [1960]
Series:ORNL (Series) ; 2962.
TID ; 4500 17th ed.
UC (Series). Metals, Ceramics, and Materials.
Subjects:

MARC

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100 1 |a Jenks, G. H.  |q (Glenn Herbert),  |d 1916- 
245 1 0 |a In-pile loop investigations of corrosion of Zircaloy-2 and other possible reactor materials in 0.04 m UO₂SO₄ at 280°C /  |c G.H. Jenks, J.E. Baker. 
246 1 |i At head of title:  |a Reactor Chemistry Division 
260 |a Oak Ridge, Tenn. :  |b Oak Ridge National Laboratory,  |c [1960] 
300 |a iii, 43 pages :  |b plates, graphs, tables ;  |c 28 cm. 
336 |a text  |b txt  |2 rdacontent 
337 |a unmediated  |b n  |2 rdamedia 
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490 1 |a ORNL ;  |v 2962 
490 1 |a TID ;  |v 4500 17th ed. 
490 1 |a UC (Series). 25, Metals, Ceramics, and Materials 
500 |a "ORNL-2962." 
500 |a "Contract no. W-7405-eng-26." 
500 |a "Date issued May 5, 1962." 
504 |a Includes bibliographical references (page 41). 
536 |a Operated by Union Carbide Corporation for the U.S. Atomic Energy Commission  |b Contract No. W-7405-eng-26. 
583 1 |a digitized  |c 2015  |h University of North Texas  |l committed to preserve  |2 pda  |5 TXdn.010 
650 0 |a Zircaloy-2  |x Corrosion. 
650 0 |a Nuclear reactors  |x Materials  |x Corrosion. 
700 1 |a Baker, J. E. 
710 2 |a U.S. Atomic Energy Commission 
710 2 |a Oak Ridge National Laboratory. 
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776 0 8 |i Electronic version :  |a Jenks, G.H. (Glenn Herbert), 1916-  |t In-pile loop investigations of corrosion of Zircaloy-2 and other possible reactor materials in 0.04 m UO₂SO₄ at 280°C.  |d Oak Ridge, Tenn. : Oak Ridge National Laboratory, [1960]  |w (OCoLC)911060046 
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