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001 9910697847003321
005 20081210162826.0
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035   $a(OCoLC)277768868
035   $a(EXLCZ)995470000002392513
100   $a20081210d2007      ua             0
101 0 $aeng
135   $aurcn||||a||||
181   $ctxt$2rdacontent
182   $cc$2rdamedia
183   $acr$2rdacarrier
200 00$aAssessment of eddy current testing for the detection of cracks in cast stainless steel reactor piping components$b[electronic resource] /$fprepared by A.A. Diaz ... [and others]
210  1$aWashington, DC :$cDivision of Fuel, Engineering, and Radiological Research, Division of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission,$d2007.
215   $a1 volume (various pagings) $cdigital, PDF file
300   $aTitle from title screen (viewed on Dec. 10, 2008).
300   $a"Pacific Northwest National Laboratory."
300   $a"Date published: February 2007."
300   $a"NUREG/CR-6929."
300   $a"PNNL-16253."
320   $aIncludes bibliographical references (pages 8-1 - 8-2).
606   $aNuclear power plants$xPiping$xCracking
615  0$aNuclear power plants$xPiping$xCracking.
701   $aDiaz$b Aaron A$01408182
712 02$aU.S. Nuclear Regulatory Commission.$bDivision of Fuel, Engineering, and Radiological Research.
712 02$aPacific Northwest National Laboratory (U.S.)
801  0$bGPO
801  1$bGPO
906   $aBOOK
912   $a9910697847003321
996   $aAssessment of eddy current testing for the detection of cracks in cast stainless steel reactor piping components$93504931
997   $aUNINA