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‡aPNL-3709
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‡aNUREG/CR-1950
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‡aData report for the NRC/PNL Halden Assembly IFA-432 :
‡bApril 1978-May 1980 /
‡cprepared by E.R. Bradley [and others] ; prepared for Division of Reactor Safety Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission.
|
260 |
⊔ |
⊔ |
‡aWashington, D.C. :
‡bThe Commission :
‡bAvailable from GPO Sales Program, Division of Technical Information and Document Control, U.S. Nuclear Regulatory Commission ;
‡aSpringfield, Va. :
‡bNational Technical Information Service,
‡c1981.
|
300 |
⊔ |
⊔ |
‡a1 v. (various pagings) :
‡bill. ;
‡c28 cm
|
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⊔ |
⊔ |
‡atext
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‡a"PNL-3709."
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⊔ |
⊔ |
‡a"NUREG/CR-1950."
|
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⊔ |
⊔ |
‡a"NRC FIN B2043."
|
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⊔ |
⊔ |
‡a"Date published: April 1981."
|
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⊔ |
⊔ |
‡a"Pacific Northwest Laboratory."
|
504 |
⊔ |
⊔ |
‡aIncludes bibliographies.
|
538 |
⊔ |
⊔ |
‡aMode of access: Internet.
|
650 |
⊔ |
0 |
‡aEmergency core cooling systems
‡xTesting.
|
650 |
⊔ |
0 |
‡aNuclear fuel rods
‡xThermal properties
‡xTesting.
|
650 |
⊔ |
0 |
‡aPressurized water reactors
‡xTesting.
|
700 |
1 |
⊔ |
‡aBradley, E. R.
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⊔ |
‡aPacific Northwest Laboratory.
‡0http://id.loc.gov/authorities/names/n78095819
‡1http://id.loc.gov/rwo/agents/n78095819
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⊔ |
‡aU.S. Nuclear Regulatory Commission.
‡bDivision of Reactor Safety Research.
‡0http://id.loc.gov/authorities/names/n79111611
‡1http://id.loc.gov/rwo/agents/n79111611
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‡aData report for the N.R.C./P.N.L. Halden Assembly IFA-432.
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