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Publications by R.W. Knoll
Measurement of the Relative /Sup 235/U Concentration and the Absolute /Sup 235/U Content of Individual HTGR Fuel Particles
Related publications
Improved Material Accounting for Plutonium Processing Facilities and a /Sup 235/U-HTGR Fuel Fabrication Facility
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]
Calculation of Resonance Self Shielding in $Sup 235$U
A MULTILEVEL ANALYSIS OF THE $Sup 235$U FISSION CROSS SECTION.
Neutron Methods for Measuring {Sup 235}U Content in UF{sub 6} Gas
Measurement of the Neutron-Induced Fission Cross-Section of /Sup 243/Am Relative to /Sup 235/U From 0. 1 MeV to 30 MeV
FEASIBILITY OF Pu$sup 239$-U$sup 235$-Fueled CORES TO PREDICT Pu$sup 239$- FUELED CORE DIMENSIONS
Neutron Multiplicity for Neutron Induced Fission of /Sup 235/U, /Sup 238/U, and /Sup 239/Pu as a Function of Neutron Energy
An ESTIMATE OF THE NONLEAKAGE PROBABILITY FOR BARE AQUEOUS HOMOGENEOUS U$sup 235$ REACTORS
