Recycling-Independent Core Design for the ENHS Fuel Self-Sustaining Reactor
Nuclear Science and Engineering / Volume 161 / Number 1 / January 2009 / Pages 1-21
Technical Paper / dx.doi.org/10.13182/NSE162-01
Application of hp Adaptivity to the Multigroup Diffusion Equations
Nuclear Science and Engineering / Volume 161 / Number 1 / January 2009 / Pages 22-48
Technical Paper / dx.doi.org/10.13182/NSE161-22
Nuclear Science and Engineering / Volume 161 / Number 1 / January 2009 / Pages 49-67
Technical Paper / dx.doi.org/10.13182/NSE161-49
Reducing Parasitic Thermal Neutron Absorption in Graphite Reactors by 30%
Nuclear Science and Engineering / Volume 161 / Number 1 / January 2009 / Pages 68-77
Technical Paper / dx.doi.org/10.13182/NSE161-68
Nuclear Science and Engineering / Volume 161 / Number 1 / January 2009 / Pages 78-89
Technical Paper / dx.doi.org/10.13182/NSE07-49
Calculation and Evaluations for n + 54,56,57,58,natFe Reactions
Nuclear Science and Engineering / Volume 161 / Number 1 / January 2009 / Pages 90-110
Technical Paper / dx.doi.org/10.13182/NSE161-90
The Fast Fission Factor Revisited
Nuclear Science and Engineering / Volume 161 / Number 1 / January 2009 / Pages 111-118
Technical Paper / dx.doi.org/10.13182/NSE161-111
Nuclear Science and Engineering / Volume 161 / Number 1 / January 2009 / Pages 119-124
Technical Note / dx.doi.org/10.13182/NSE161-119
External Neutron Drive for Subcritical Reactors
Nuclear Science and Engineering / Volume 161 / Number 1 / January 2009 / Pages 125-129
Technical Note / dx.doi.org/10.13182/NSE161-125