LEADER 01948oam 2200469I 450 001 9910705784403321 005 20170706111130.0 035 $a(CKB)5470000002452560 035 $a(OCoLC)992976621 035 $a(EXLCZ)995470000002452560 100 $a20170706j201705 ua 0 101 0 $aeng 135 $aur||||||||||| 181 $ctxt$2rdacontent 182 $cc$2rdamedia 183 $acr$2rdacarrier 200 10$aDevelopment of a statistical testing approach for quantifying safety-related digital system on demand failure probability /$fprepared by Tsong-Lun Chu [and nine others]. 210 1$aWashington, DC :$cUnited States Nuclear Regulatory Commission, Office of Nuclear Regulatory Research,$dMay 2017. 215 $a1 online resource (various pagings) $cillustrations 300 $a"Manuscript completed: December 2015; date published: May 2017." 300 $a"NUREG/CR-7234." 300 $a"Brookhaven National Laboratory; Idaho National Laboratory." 300 $a"Ming Li, NRC project manager." 606 $aNuclear power plants$xSafety measures$vSoftware 606 $aBoiling water reactors$xAnalysis$xComputer programs 606 $aNuclear power plants$xComputer programs 606 $aComputer software$xReliability 606 $aSoftware failures 615 0$aNuclear power plants$xSafety measures 615 0$aBoiling water reactors$xAnalysis$xComputer programs. 615 0$aNuclear power plants$xComputer programs. 615 0$aComputer software$xReliability. 615 0$aSoftware failures. 700 $aChu$b Tsong-Lun$01407839 712 02$aU.S. Nuclear Regulatory Commission.$bDivision of Risk Analysis, 801 0$bGPO 801 1$bGPO 801 2$bGPO 906 $aBOOK 912 $a9910705784403321 996 $aDevelopment of a statistical testing approach for quantifying safety-related digital system on demand failure probability$93522555 997 $aUNINA