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Publications by P.L. Reeder
Neutron Methods for Measuring {Sup 235}U Content in UF{sub 6} Gas
Related publications
Neutron Multiplicity for Neutron Induced Fission of /Sup 235/U, /Sup 238/U, and /Sup 239/Pu as a Function of Neutron Energy
Measurement of the Relative /Sup 235/U Concentration and the Absolute /Sup 235/U Content of Individual HTGR Fuel Particles
Neutron Inelastic-Scattering Cross Sections of /Sup 232/Th, /Sup 233/U, /Sup 235/U, /Sup 238/U, /Sup 239/Pu and /Sup 240/Pu. [LMFBR]
Preliminary Fission Product Energy Release Measurements for Thermal Neutron Fission of /Sup 235/U
Calculation of Resonance Self Shielding in $Sup 235$U
NEUTRON FLUX MEASUREMENTS IN URANIUM METAL EXPONENTIAL COLUMNS OF 6.53 PERCENT AND 9.12 PERCENT $Sup 235$U.
Computer Programs for Developing Source Terms for a UF{sub 6} Dispersion Model to Simulate Postulated UF{sub 6} Releases From Buildings
Investigation of Breached Depleted UF{sub 6} Cylinders
FEASIBILITY OF Pu$sup 239$-U$sup 235$-Fueled CORES TO PREDICT Pu$sup 239$- FUELED CORE DIMENSIONS
