LEADER 01763nam  2200421Ka 450 
001 9910697704603321
005 20081209120324.0
035   $a(CKB)5470000002391931
035   $a(OCoLC)277230061
035   $a(EXLCZ)995470000002391931
100   $a20081209d2008      ua             0
101 0 $aeng
181   $ctxt$2rdacontent
182   $cc$2rdamedia
183   $acr$2rdacarrier
200 10$aIrradiation-assisted stress corrosion cracking of austenitic stainless steels and alloy 690 from Halden phase-II irradiations$b[electronic resource] /$fprepared by Y. Chen ... [and others]
210  1$a[Washington, D.C.] :$cU.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research,$d[2008]
215   $axviii, 48 pages, 14 unnumbered pages $cdigital, PDF file
300   $aTitle from title screen (viewed on Dec. 8, 2008).
300   $a"Argonne National Laboratory."
300   $a"Date published: September 2008."
300   $a"NUREG/CR-6965."
300   $a"ANL-07/11."
606   $aBoiling water reactors
606   $aNuclear reactors$xMaterials$xStress corrosion
606   $aNuclear reactors$xMaterials$xEffect of radiation on
615  0$aBoiling water reactors.
615  0$aNuclear reactors$xMaterials$xStress corrosion.
615  0$aNuclear reactors$xMaterials$xEffect of radiation on.
700   $aChen$b Y$01333782
712 02$aArgonne National Laboratory.
712 02$aU.S. Nuclear Regulatory Commission.$bOffice of Nuclear Regulatory Research.
801  0$bGPO
801  1$bGPO
906   $aBOOK
912   $a9910697704603321
996   $aIrradiation-assisted stress corrosion cracking of austenitic stainless steels and alloy 690 from Halden phase-II irradiations$93504207
997   $aUNINA