Defect testing of coextruded uranium-zircaloy-II clad fuel material in a 300 C out-of-reactor recirculating water loop: Interim report
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Defect testing of coextruded uranium-zircaloy-II clad fuel material in a 300 C out-of-reactor recirculating water loop: Interim report, report, September 25, 1959; Richland, Washington. (https://digital.library.unt.edu/ark:/67531/metadc1338846/: accessed February 13, 2025), University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.