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Volume 180

Number 2

A New Molybdenum Production Element for Implementation in TRIGA Reactors: Thermal-Hydraulic Characterization

W. R. Marcum, P. Y. Byfield, S. R. Reese

Nuclear Science and Engineering / Volume 180 / Number 2 / June 2015 / Pages 123-140

Technical Paper / dx.doi.org/10.13182/NSE14-93

Study of Critical Heat Flux in Natural Convection–Cooled TRIGA Reactors with Single Annulus and Rod Bundle Geometries

Jun Yang, Michael Scott Greenwood, Matthew De Angelis, Michael Avery, Mark Anderson, Michael Corradini, James Matos, Floyd Dunn, Earl Feldman

Nuclear Science and Engineering / Volume 180 / Number 2 / June 2015 / Pages 141-153

Technical Paper / dx.doi.org/10.13182/NSE14-45

Global Control of H-Infinity Multimodel System with Gap Metric and Self-Stability for Load-Following Nuclear Reactor Core

Gang Li

Nuclear Science and Engineering / Volume 180 / Number 2 / June 2015 / Pages 154-171

Technical Paper / dx.doi.org/10.13182/NSE13-87

Determination of Turbulent Mixing Rate for Single-Phase Flow in Simulated Subchannels of a Natural-Circulation Pressure Tube–Type BWR

M. P. Sharma, A. K. Nayak

Nuclear Science and Engineering / Volume 180 / Number 2 / June 2015 / Pages 172-181

Technical Paper / dx.doi.org/10.13182/NSE14-102

Validation of the Legendre Expansion of the Collision Law for Light Water Reactor Calculations

Ansar Calloo, Jean-François Vidal, Romain Le Tellier, Gérald Rimpault

Nuclear Science and Engineering / Volume 180 / Number 2 / June 2015 / Pages 182-198

Technical Paper / dx.doi.org/10.13182/NSE14-57

Monte Carlo Fission Matrix Acceleration Method with Limited Inner Iteration

Liujun Pan, Ruihong Wang, Song Jiang

Nuclear Science and Engineering / Volume 180 / Number 2 / June 2015 / Pages 199-208

Technical Paper / dx.doi.org/10.13182/NSE14-73

Temperature Majorant Cross Sections in Monte Carlo Neutron Tracking

Tuomas Viitanen, Jaakko Leppänen

Nuclear Science and Engineering / Volume 180 / Number 2 / June 2015 / Pages 209-223

Technical Paper / dx.doi.org/10.13182/NSE14-46

The Infinite Medium Green’s Function of Monoenergetic Neutron Transport Theory via Fourier Transform

B. D. Ganapol

Nuclear Science and Engineering / Volume 180 / Number 2 / June 2015 / Pages 224-246

Technical Paper / dx.doi.org/10.13182/NSE14-55

 
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