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Forwards response to request for addl info to support core physics review of Canadian (CANDU)-3 reactor design dtd 930127.

Accession Number: ML20034D797

Date Released: Friday, October 25, 2024

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• ML20034D796 - Forwards response to request for addl info to support core physics review of Canadian (CANDU)-3 reactor design dtd 930127. (2 page(s), 2/22/1993)
• ML20034D800 - Errata to AECL-1101, "Effective Cross Section Values For Well-Moderated Thermal Reactor Spectra." (50 page(s), 11/1/1960)
• ML20034D806 - "Average Nuclide Composition in Irradiated Natural Uranium Metal Fuel Rods." (49 page(s), 9/30/1964)
• ML20034D809 - "Natural-Uranium Heavy-Water Lattices,Experiment & Theory." (35 page(s), 9/30/1958)
• ML20034D812 - "Calculation of Effective Resonance Integral For Multiple, UO-2 Rods W/Various Coolants." (18 page(s), 1/31/1958)
• ML20034D813 - Calculation of Thermal Utilization By Collision Probability Method Including Scattering & Sources in Annuli Surrounding Fuel." (25 page(s), 10/31/1961)
• ML20034D815 - "Neutron Capture By Long Cylindrical Bodies Surrounded By Predominantly Scattering Media." (64 page(s), 4/30/1959)
• ML20034D816 - "Method of Calculating Neutron Absorptions & Flux Spectra at Epithermal Energies." (60 page(s), 5/31/1964)