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101 0 $aeng
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181   $ctxt$2rdacontent
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200 10$aTRAC-PF1/MOD1 post-test calculations of the OECD LOFT experiment LP-SB-3 /$fprepared by E. J. Allen, A. P. Neill
210  1$aWashington, DC :$cOffice of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission,$dApril 1990.
215   $a1 online resource (112 unnumbered pages) $cillustrations
225 1 $aInternational agreement report ;$vNUREG/IA-0022
300   $a"United Kingdom Atomic Energy Authority."
300   $a"April 1990."
300   $a"Prepared as part of the Agreement on Research Participation and Technical Exchange under the International Thermal-Hydraulic Code Assessment and Application Program (ICAP)."
300   $a"AEEW-R 2275"--Bibliographic data sheet.
300   $a"Technical"--Bibliographic data sheet.
320   $aIncludes bibliographical references (pages 14-15).
517 3 $aTRAC PF1/MOD1 post test calculations of the OECD LOFT experiment LP-SB-3
606   $aLOFT (Nuclear reactor safety test facility)$xExperiments
606   $aPressurized water reactors$xLoss of coolant$xComputer programs
606   $aHydraulic transients$xSimulation methods
615  0$aLOFT (Nuclear reactor safety test facility)$xExperiments.
615  0$aPressurized water reactors$xLoss of coolant$xComputer programs.
615  0$aHydraulic transients$xSimulation methods.
700   $aAllen$b E. J.$01411930
702   $aNeill$b A. P.
712 02$aU.S. Nuclear Regulatory Commission.$bOffice of Nuclear Regulatory Research,
801  0$bOCLCE
801  1$bOCLCE
801  2$bOCLCQ
801  2$bOCLCO
801  2$bOCLCQ
801  2$bGPO
906   $aBOOK
912   $a9910707645003321
996   $aTRAC-PF1$93504177
997   $aUNINA