Nuclear Science and Engineering / Volume 160 / Number 2 / October 2008 / Pages 149-167
Technical Paper / dx.doi.org/10.13182/NSE160-149
Evaluation of Neutron Cross Sections for a Complete Set of Nd Isotopes
Nuclear Science and Engineering / Volume 160 / Number 2 / October 2008 / Pages 168-189
Technical Paper / dx.doi.org/10.13182/NSE160-168
Reevaluation of Prompt Neutron Emission Multiplicity Distributions for Spontaneous Fission
Nuclear Science and Engineering / Volume 160 / Number 2 / October 2008 / Pages 190-199
Technical Paper / dx.doi.org/10.13182/NSE07-85
Measurement of the 236U(n,f) Cross Section in the Neutron Energy Range from 0.5 eV up to 25 keV
Nuclear Science and Engineering / Volume 160 / Number 2 / October 2008 / Pages 200-206
Technical Paper / dx.doi.org/10.13182/NSE160-200
An Attempt to Improve Empirical Formulas for (n,p) and (n,) Cross Sections
Nuclear Science and Engineering / Volume 160 / Number 2 / October 2008 / Pages 207-216
Technical Paper / dx.doi.org/10.13182/NSE160-207
Nuclear Science and Engineering / Volume 160 / Number 2 / October 2008 / Pages 217-231
Technical Paper / dx.doi.org/10.13182/NSE160-217
Nuclear Science and Engineering / Volume 160 / Number 2 / October 2008 / Pages 232-241
Technical Paper / dx.doi.org/10.13182/NSE160-232
Nuclear Science and Engineering / Volume 160 / Number 2 / October 2008 / Pages 242-252
Technical Paper / dx.doi.org/10.13182/NSE160-242
Resonance Absorption in Materials with Randomly Dispersed Grains
Nuclear Science and Engineering / Volume 160 / Number 2 / October 2008 / Pages 253-260
Technical Paper / dx.doi.org/10.13182/NSE160-253
Scattering Reduction of the Double-Heterogeneity Treatment in Dragon
Nuclear Science and Engineering / Volume 160 / Number 2 / October 2008 / Pages 261-266
Technical Note / dx.doi.org/10.13182/NSE160-261TN