Evaluating strength and ductility of irradiated zircaloy, task 5

LDR 01482nam a2200409 a 4500
001 003124002
003 MiAaHDL
005 20200505000000.0
006 m d
007 cr bn ---auaua
008 970310s19819999dcua b f000 0 eng d
035 ‡a(MiU)003124002
035 ‡asdr-miu003124002
035 ‡a(OCoLC)8272308
040 ‡aGPO ‡cGPO ‡dEYM
043 ‡an-us---
074 ‡a1051-H-11
086 0 ‡aY 3.N 88:25/1729/v.1-
088 ‡aBMI-2066
088 ‡aNUREG/CR-1729
245 0 0 ‡aEvaluating strength and ductility of irradiated zircaloy, task 5 / ‡cprepared by L.M. Lowry ... [et al.].
260 ‡aWashington, D.C. : ‡bThe Commission, ‡c1981-
300 ‡av. : ‡bill. ; ‡c28 cm.
490 0 ‡aR; ‡v3
500 ‡a"BMI-2066."
500 ‡a"NUREG/CR-1729."
500 ‡a"NRC FIN A4068."
500 ‡a"Date published: May 1981"--Vols. 1, 2.
500 ‡a"Final report"--Vols. 1, 2.
500 ‡a"Battelle Columbus Laboratories"--Vols. 1, 2.
504 ‡aIncludes bibliographical references.
505 1 ‡av. 1. Experimental data -- v. 2. Mathematical-model development.
538 ‡aMode of access: Internet.
650 0 ‡aNuclear reactors ‡xMaterials ‡xTesting.
650 0 ‡aNuclear fuel claddings.
650 0 ‡aMetals ‡xEffect of radiation on.
650 0 ‡aMetals ‡xMechanical properties.
650 0 ‡aZirconium alloys ‡xMechanical properties.
700 1 ‡aLowry, L. M. ‡q(Larry M.)
710 2 ‡aBattelle Memorial Institute. ‡bColumbus Laboratories.
710 2 ‡aU.S. Nuclear Regulatory Commission. ‡bDivision of Reactor Safety Research.
CID ‡a003124002
DAT 0 ‡a20200505040327.0 ‡b20200505000000.0
DAT 1 ‡a20200505090521.0 ‡b2020-05-05T16:17:14Z
DAT 2 ‡a2019-04-14T18:00:02Z
CAT ‡aSDR-MIU ‡dEX LIBRIS - ALEPH ‡lprepare.pl-004-008
FMT ‡aBK
HOL ‡0sdr-miu003124002 ‡aMiU ‡bSDR ‡cMIU ‡pmdp.39015038542786 ‡sMIU ‡zv.2 ‡1003124002
974 ‡bMIU ‡cMIU ‡d20200505 ‡sgoogle ‡umdp.39015038542786 ‡zv.2 ‡rpd ‡qbib ‡tUS fed doc