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971015s1978 dcua b f000 0 eng d |
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‡a(MiU)990031872380106381
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‡asdr-miu.990031872380106381
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‡a(OCoLC)37747964
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‡z(MiU)Aleph003187238
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‡aEYM
‡cEYM
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⊔ |
‡a1051-H-11
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‡aY 3.N 88:25/0079
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‡aNUREG/CR-0079
|
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0 |
‡aCritical experiments, measurements, and analyses to establish a crack arrest methodology for nuclear pressure vessel steels :
‡bquarterly report, January - March 1977 /
‡cG.T. Hahn and others, Battelle Columbus Laboratories.
|
260 |
⊔ |
⊔ |
‡aWashington, D.C. :
‡bDivision of Reactor Safety Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission ;
‡aSpringfield, Va. :
‡bAvailable from National Technical Information Service,
‡c1978.
|
300 |
⊔ |
⊔ |
‡a1 v. (various pagings) :
‡bill. ;
‡c28 cm.
|
490 |
0 |
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‡aR ;
‡v5
|
500 |
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‡a"Date published: May 1978."
|
500 |
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‡aPrepared under contract no. AT(49-24)-0293.
|
500 |
⊔ |
⊔ |
‡a"NUREG/CR-0079."
|
504 |
⊔ |
⊔ |
‡aIncludes bibliographical references.
|
538 |
⊔ |
⊔ |
‡aMode of access: Internet.
|
650 |
⊔ |
0 |
‡aNuclear reactors
‡xSafety measures.
|
650 |
⊔ |
0 |
‡aNuclear pressure vessels
‡xTesting.
|
650 |
⊔ |
0 |
‡aFracture mechanics.
|
650 |
⊔ |
0 |
‡aSteel
‡xFracture.
|
650 |
⊔ |
0 |
‡aNuclear pressure vessels
‡xCracking.
|
700 |
1 |
⊔ |
‡aHahn, G. T.
‡q(George T.)
|
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⊔ |
‡aU.S. Nuclear Regulatory Commission.
‡bDivision of Reactor Safety Research.
|
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2 |
⊔ |
‡aBattelle Memorial Institute.
‡bColumbus Laboratories.
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‡a003187238
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‡bMIU
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‡d20230617
‡sgoogle
‡umdp.39015041105928
‡y1978
‡rpd
‡qbib
‡tUS fed doc--NTIS: pubdate < 2018
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