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100   $a20080804d1994      ua             0
101 0 $aeng
135   $aur|||||||||||
181   $ctxt$2rdacontent
182   $cc$2rdamedia
183   $acr$2rdacarrier
200 10$aEstimation of fracture toughness of cast stainless steels during thermal aging in LWR systems$b[electronic resource] /$fprepared by O.K. Chopra
205   $aRev. 1.
210  1$aWashington, DC :$cDivision of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission,$d1994.
215   $axiii, 54, 12 pages $cdigital, PDF file
300   $aTitle from title screen (viewed on Aug. 4, 2008).
300   $a"Argonne National Laboratory."
300   $a"Date published: August 1994."
300   $a"NUREG/CR-4513."
300   $a"ANL-93/22."
320   $aIncludes bibliographical references (pages 95-105).
606   $aStainless steel$xEffect of temperature on
606   $aStainless steel$xEmbrittlement
606   $aLight water reactors$xMaterials$xEffect of temperature on
606   $aLight water reactors$xMaterials$xEmbrittlement
615  0$aStainless steel$xEffect of temperature on.
615  0$aStainless steel$xEmbrittlement.
615  0$aLight water reactors$xMaterials$xEffect of temperature on.
615  0$aLight water reactors$xMaterials$xEmbrittlement.
700   $aChopra$b O. K$01393760
712 02$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   $a9910698568003321
996   $aEstimation of fracture toughness of cast stainless steels during thermal aging in LWR systems$93476166
997   $aUNINA