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Publications by H.S. Moran
An ESTIMATE OF THE NONLEAKAGE PROBABILITY FOR BARE AQUEOUS HOMOGENEOUS U$sup 235$ REACTORS
Modification and Further Development of the Nucleon Transport Code, Ntc.
Related publications
Measurement of the Relative /Sup 235/U Concentration and the Absolute /Sup 235/U Content of Individual HTGR Fuel Particles
Calculation of Resonance Self Shielding in $Sup 235$U
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]
A MULTILEVEL ANALYSIS OF THE $Sup 235$U FISSION CROSS SECTION.
Neutron Multiplicity for Neutron Induced Fission of /Sup 235/U, /Sup 238/U, and /Sup 239/Pu as a Function of Neutron Energy
FEASIBILITY OF Pu$sup 239$-U$sup 235$-Fueled CORES TO PREDICT Pu$sup 239$- FUELED CORE DIMENSIONS
Neutron Methods for Measuring {Sup 235}U Content in UF{sub 6} Gas
Preliminary Fission Product Energy Release Measurements for Thermal Neutron Fission of /Sup 235/U
CRITICAL PARAMETERS FOR POISONED ANNULAR CYLINDERS CONTAINING AQUEOUS SOLUTIONS OF U$sup 23$$sup 5$