Volume 153
Number 1
Nuclear Science and Engineering / Volume 153 / Number 1 / May 2006 / Pages 1-7
Technical Paper / dx.doi.org/10.13182/NSE06-A2589
Nuclear Science and Engineering / Volume 153 / Number 1 / May 2006 / Pages 8-25
Technical Paper / dx.doi.org/10.13182/NSE06-A2590
Calculation of the Prompt Neutron Lifetime in the NBSR
Nuclear Science and Engineering / Volume 153 / Number 1 / May 2006 / Pages 26-32
Technical Paper / dx.doi.org/10.13182/NSE06-4
Photonuclear Physics in Radiation Transport - III: Actinide Cross Sections and Spectra
Nuclear Science and Engineering / Volume 153 / Number 1 / May 2006 / Pages 33-40
Technical Paper / dx.doi.org/10.13182/NSE06-A2592
Nuclear Science and Engineering / Volume 153 / Number 1 / May 2006 / Pages 41-45
Technical Paper / dx.doi.org/10.13182/NSE153-41
Collision Probabilities in r-
-z Geometry
Nuclear Science and Engineering / Volume 153 / Number 1 / May 2006 / Pages 46-59
Technical Paper / dx.doi.org/10.13182/NSE06-A2594
The Statistics of the Number of Neutron Collisions Prior to Absorption
Nuclear Science and Engineering / Volume 153 / Number 1 / May 2006 / Pages 60-68
Technical Paper / dx.doi.org/10.13182/NSE06-A2595
Space-Time Correction for Reactivity Determination in Source-Driven Subcritical Systems
Nuclear Science and Engineering / Volume 153 / Number 1 / May 2006 / Pages 69-89
Technical Paper / dx.doi.org/10.13182/NSE06-A2596
The Smallest Thermal Nuclear Reactor
Nuclear Science and Engineering / Volume 153 / Number 1 / May 2006 / Pages 90-92
Technical Paper / dx.doi.org/10.13182/NSE06-A2597
Nuclear Science and Engineering / Volume 153 / Number 1 / May 2006 / Pages 93-97
Computer Code Abstract / dx.doi.org/10.13182/NSE05-06CCA
