01928nam a2200481Ka 4500005948495MiAaHDL20250726000000.0m d cr bn ---auaua060908s1959 ilua bt f000 0 eng dANL-5945(MiU)990059484950106381sdr-miu.990059484950106381(MiU)MIU01000000000000005948495-goog(OCoLC)71277245(MiU)Aleph005948495KKSKKSANLSRUtOrBLWANLAY 3.At 7:22/ANL-5945Taraba, F. R.The longitudinal distribution of thermal neutron flux in cylindrical fuel specimens during irradiation /by F.R. Taraba and S.H. Paine.Lemont, Ill. :Argonne National Laboratory,1959.25 p. :ill. ;28 cm.texttxtrdacontentcomputercrdamediaonline resourcecrrdacarrierANL/Argonne National Laboratory ;5945"Operated by the University of Chicago under Contract W-31-109-eng-38.""Metallurgy Division Program 6.1.26.""August, 1959""AEC Research and Development Report""(TID-4500, 15th Ed.)""Metallurgy and Ceramics"Includes bibliographical references (p. 21) and abstract.Operated by The University of ChicagoContract No. W-31-109-eng-38Mode of access: Internet.Neutron flux.http://id.loc.gov/authorities/subjects/sh85091209Nuclear physicsMethods.Nuclear fuelsEffect of radiation on.Nuclear fuel elementsEffect of radiation on.Paine, S. H.ANL (Series)http://id.loc.gov/authorities/names/n84747421http://id.loc.gov/rwo/agents/n847474213901507850968700594849520241218062941.020250726000000.020260303165447.02026-03-04T10:02:41Z2026-03-01T18:30:03ZSDR-MIUmiuALMAprepare.pl-004-009BKsdr-miu.990059484950106381MiUSDRGWLA005948495mdp.39015078509687MIU990059484950106381MIUGWLA20260304googlemdp.390150785096871959pdbibUS fed doc