Mixed Sorption Models and Isotherms of the Cesium-Rubidium-Graphite System at High Temperatures
Nuclear Science and Engineering / Volume 50 / Number 2 / February 1973 / Pages 91-97
Technical Paper / dx.doi.org/10.13182/NSE73-A23232
The Neutron-Induced Gamma-Ray Reactions in Sodium-23 in the Energy Range 4.85 ≤ En ≤ 7.5 MeV
Nuclear Science and Engineering / Volume 50 / Number 2 / February 1973 / Pages 98-107
Technical Paper / dx.doi.org/10.13182/NSE73-A23233
The Energy Spectrum of Prompt Neutrons from the Fission of Uranium-235 by 0.40-MeV Neutrons
Nuclear Science and Engineering / Volume 50 / Number 2 / February 1973 / Pages 108-114
Technical Paper / dx.doi.org/10.13182/NSE73-A23234
Nuclear Science and Engineering / Volume 50 / Number 2 / February 1973 / Pages 115-126
Technical Paper / dx.doi.org/10.13182/NSE73-2
Criticality of Plutonium Nitrate Solutions Containing Borated Raschig Rings
Nuclear Science and Engineering / Volume 50 / Number 2 / February 1973 / Pages 127-134
Technical Paper / dx.doi.org/10.13182/NSE73-A23236
Improved Integral Transport Theory by Means of Space Polynomial Approximations
Nuclear Science and Engineering / Volume 50 / Number 2 / February 1973 / Pages 135-146
Technical Paper / dx.doi.org/10.13182/NSE73-A23237
Higher Flux Mode Effects in Xenon Spatial Oscillations
Nuclear Science and Engineering / Volume 50 / Number 2 / February 1973 / Pages 147-152
Technical Paper / dx.doi.org/10.13182/NSE73-A23238
Optimal Fuel Enrichment Distribution in Fast Reactors
Nuclear Science and Engineering / Volume 50 / Number 2 / February 1973 / Pages 153-163
Technical Paper / dx.doi.org/10.13182/NSE73-A23239
An Integral Formulation of the Neutron Scattering Moments for Monatomic Gases
Nuclear Science and Engineering / Volume 50 / Number 2 / February 1973 / Pages 164-169
Technical Note / dx.doi.org/10.13182/NSE73-A23240
Neutron Multiplicity Distributions in the Spontaneous Fission of 244Cm, 248Cm, and 252Cf
Nuclear Science and Engineering / Volume 50 / Number 2 / February 1973 / Pages 169-171
Technical Note / dx.doi.org/10.13182/NSE73-A23241
Average Neutron Cross Sections in the Unresolved Resonance Range
Nuclear Science and Engineering / Volume 50 / Number 2 / February 1973 / Pages 171-173
Technical Note / dx.doi.org/10.13182/NSE73-A23242
Nuclear Science and Engineering / Volume 50 / Number 2 / February 1973 / Pages 173-176
Technical Note / dx.doi.org/10.13182/NSE73-A23243
Correlating the Ratio of the Peak-to-Average Power in a Reactor with Quadrant Power Distributions
Nuclear Science and Engineering / Volume 50 / Number 2 / February 1973 / Pages 176-179
Technical Note / dx.doi.org/10.13182/NSE73-A23244