| Record ID | harvard_bibliographic_metadata/ab.bib.13.20150123.full.mrc:951447062:1921 |
| Source | harvard_bibliographic_metadata |
| Download Link | /show-records/harvard_bibliographic_metadata/ab.bib.13.20150123.full.mrc:951447062:1921?format=raw |
LEADER: 01921cam a2200409Ii 4500
001 013838027-9
005 20131214023206.0
006 m o d f
008 131025s2013 dcua ob f000 0 eng d
035 0 $aocn861495828
035 $a(FDLP)ocn861495828
040 $aGPO$beng$erda$epn$cGPO$dGPO
074 $a1051-H-41 (online)
086 0 $aY 3.N 88:53/0432
100 1 $aBelaïd, S.,$eauthor.
245 10 $aAnalysis of the test OECD-PKL2 G7.1 with the thermal-hydraulic system code TRACE /$cprepared by: S. Belaïd, J. Freixa, O. Zerkak.
246 3 $aAnalysis of the test Organisation for Economic Co-operation and Development-Primary Coolant Loop Test Facility G7.1 with the thermal-hydraulic system code TRACE
264 1 $aWashington, DC :$bU.S. Nuclear Regulatory Commission,$c2013.
300 $a1 online resource (xiii, 29 pages) :$bcolor illustrations.
336 $atext$2rdacontent
337 $acomputer$2rdamedia
338 $aonline resource$2rdacarrier
490 1 $aInternational agreement report ;$vNUREG/IA-0432
500 $aTitle from title screen (viewed Oct. 25, 2013).
500 $a"September 2013."
504 $aIncludes bibliographical references (page 29).
650 0 $aPressurized water reactors$xEmergency core cooling systems$xTesting.
650 0 $aPressurized water reactors$xEquipment and supplies$xEffect of temperature on$xMeasurement.
650 0 $aNuclear fuel claddings$xEffect of temperature on$xMeasurement.
650 0 $aNuclear power plants$xSafety measures$xTesting.
700 1 $aFreixa, J.,$eauthor.
700 1 $aZerkak, O.,$eauthor.
710 2 $aU.S. Nuclear Regulatory Commission,$eissuing body.
776 08 $iPrint version:$aBelaïd, S.$tAnalysis of the test OECD-PKL2 G7.1 with the thermal-hydraulic system code TRACE$w(OCoLC)861495775
830 0 $aInternational agreement report ;$vNUREG/IA-0432.
988 $a20131116
906 $0OCLC