LEADER 01821nam  2200433Ka 450 
001 9910697212103321
005 20080804120223.0
035   $a(CKB)5470000002386805
035   $a(OCoLC)237787622
035   $a(EXLCZ)995470000002386805
100   $a20080804d1990      ua             0
101 0 $aeng
181   $ctxt$2rdacontent
182   $cc$2rdamedia
183   $acr$2rdacarrier
200 10$aInitial assessment of the mechanisms and significance of low-temperature embrittlement of cast stainless steels in LWR systems$b[electronic resource] /$fprepared by O.K. Chopra, A. Sather
210  1$aWashington, DC :$cDivision of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission,$d1990.
215   $a1 volume (various pagings) $cdigital, PDF file
300   $aTitle from title screen (viewed on Aug. 4, 2008).
300   $a"Argonne National Laboratory."
300   $a"Date published: August 1990."
300   $a"NUREG/CR-5385."
300   $a"ANL-89/17."
606   $aSteel, Cast$xEffect of temperature on$xTesting
606   $aLight water reactors$xMaterials$xFatigue
606   $aStainless steel$xFatigue
615  0$aSteel, Cast$xEffect of temperature on$xTesting.
615  0$aLight water reactors$xMaterials$xFatigue.
615  0$aStainless steel$xFatigue.
700   $aChopra$b O. K$01393760
701   $aSather$b A$01396777
712 02$aU.S. Nuclear Regulatory Commission.$bOffice of Nuclear Regulatory Research.$bDivision of Engineering.
712 02$aArgonne National Laboratory.
801  0$bGPO
801  1$bGPO
906   $aBOOK
912   $a9910697212103321
996   $aInitial assessment of the mechanisms and significance of low-temperature embrittlement of cast stainless steels in LWR systems$93457431
997   $aUNINA