Nuclear Science and Engineering / Volume 162 / Number 3 / July 2009 / Pages 215-233
Technical Paper / dx.doi.org/10.13182/NSE162-215
Nuclear Science and Engineering / Volume 162 / Number 3 / July 2009 / Pages 234-252
Technical Paper / dx.doi.org/10.13182/NSE162-234
Measurement of the Thermal Absorption Cross Section in Lucite Using Fermi Age Theory
Nuclear Science and Engineering / Volume 162 / Number 3 / July 2009 / Pages 253-260
Technical Paper / dx.doi.org/10.13182/NSE162-253
Steady-State Thermal-Hydraulic Analysis of the Oregon State University TRIGA Reactor Using RELAP5-3D
Nuclear Science and Engineering / Volume 162 / Number 3 / July 2009 / Pages 261-274
Technical Paper / dx.doi.org/10.13182/NSE08-63
Nuclear Science and Engineering / Volume 162 / Number 3 / July 2009 / Pages 275-281
Technical Paper / dx.doi.org/10.13182/NSE162-275
Analysis of Pebble-Fueled Zone Modeling Influence on High-Temperature Reactor Core Calculations
Nuclear Science and Engineering / Volume 162 / Number 3 / July 2009 / Pages 282-298
Technical Note / dx.doi.org/10.13182/NSE162-282
Some Notes on the Definition of Performance Parameters for Reactors and Fuel Cycles
Nuclear Science and Engineering / Volume 162 / Number 3 / July 2009 / Pages 299-306
Technical Note / dx.doi.org/10.13182/NSE162-299
Numerical Stability of Existing Monte Carlo Burnup Codes in Cycle Calculations of Critical Reactors
Nuclear Science and Engineering / Volume 162 / Number 3 / July 2009 / Pages 307-311
Technical Note / dx.doi.org/10.13182/NSE08-69TN
Absolute Total np and pp Cross-Section Determinations
Nuclear Science and Engineering / Volume 162 / Number 3 / July 2009 / Pages 312-318
Technical Note / dx.doi.org/10.13182/NSE162-312