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Volume 168

Number 1 | Number 2 | Number 3

Number 1

Neutronic Feasibility Assessment of Liquid Salt-Cooled Pebble Bed Reactors

Massimiliano Fratoni, Ehud Greenspan

Nuclear Science and Engineering / Volume 168 / Number 1 / May 2011 / Pages 1-22

Detailed Design of 242mAm Breeding in Pressurized Water Reactors

Leonid Golyand, Yigal Ronen, Eugene Shwageraus

Nuclear Science and Engineering / Volume 168 / Number 1 / May 2011 / Pages 23-36

Newton's Method for the Computation of k-Eigenvalues in SN Transport Applications

Daniel F. Gill, Yousry Y. Azmy, James S. Warsa, Jeffery D. Densmore

Nuclear Science and Engineering / Volume 168 / Number 1 / May 2011 / Pages 37-58

An Analysis of Reflector Homogenization Techniques for Full Core Diffusion Calculations

Charlotte Sandrin, Richard Sanchez, Florence Dolci

Nuclear Science and Engineering / Volume 168 / Number 1 / May 2011 / Pages 59-72

Number 2

Improved Derivation of Multigroup Effective Cross Section for Heterogeneous System by Equivalence Theory

Akio Yamamoto, Tomohiro Endo, Hiroki Koike

Nuclear Science and Engineering / Volume 168 / Number 2 / June 2011 / Pages 75-92

Technical Paper / dx.doi.org/10.13182/NSE10-50

Application of Time-Dependent Neutron Transport Theory to High-Temperature Reactors of Pebble Bed Type

Bismark Tyobeka, Andreas Pautz, Kostadin Ivanov

Nuclear Science and Engineering / Volume 168 / Number 2 / June 2011 / Pages 93-114

Technical Paper

On the Accuracy of a Common Monte Carlo Surface Flux Grazing Approximation

Jeffrey A. Favorite, Ashley D. Thomas, Thomas E. Booth

Nuclear Science and Engineering / Volume 168 / Number 2 / June 2011 / Pages 115-127

Technical Paper / dx.doi.org/10.13182/NSE09-72

Perspectives on Advanced Simulation for Nuclear Reactor Safety Applications

J. Kelly, M. Corradini, R. Budnitz, M. Pilch

Nuclear Science and Engineering / Volume 168 / Number 2 / June 2011 / Pages 128-137

Technical Paper

Calculation of the Void Fraction and Void Coefficient in an Aqueous Homogeneous Reactor

M. M. R. Williams

Nuclear Science and Engineering / Volume 168 / Number 2 / June 2011 / Pages 138-150

Technical Paper

Calculation and Analysis of Neutron-Induced Reactions on 59Co up to 200 MeV

Yue Zhang, Yinlu Han, Hairui Guo, Qingbiao Shen

Nuclear Science and Engineering / Volume 168 / Number 2 / June 2011 / Pages 151-163

Technical Paper

Measuring (n, f) Cross Sections of Short-Lived States

J. I. Katz

Nuclear Science and Engineering / Volume 168 / Number 2 / June 2011 / Pages 164-171

Technical Paper

Tritium Battery with Solid Dielectric

A. Kavetskiy, G. Yakubova, S. M. Yousaf, K. Bower

Nuclear Science and Engineering / Volume 168 / Number 2 / June 2011 / Pages 172-179

Technical Paper

Interpolation of Temperature-Dependent Nuclide Data in MCNP

J. V. Donnelly

Nuclear Science and Engineering / Volume 168 / Number 2 / June 2011 / Pages 180-184

Technical Note

Number 3

Evaluation of Dynamic Pressures from Steam Explosions Applied to Advanced Light Water Reactors

Michael L. Corradini, James P. Blanchard, Carl J. Martin

Nuclear Science and Engineering / Volume 168 / Number 3 / July 2011 / Pages 185-196

Technical Paper

Geometric Convergence of Adaptive Monte Carlo Algorithms for Radiative Transport Problems Based on Importance Sampling Methods

Rong Kong, Jerome Spanier

Nuclear Science and Engineering / Volume 168 / Number 3 / July 2011 / Pages 197-225

Technical Paper / Geometric Convergence of Adaptive Monte Carlo Algorithms for Radiative Transport Problems Based on Importance Sampling Methods

Adjoint-Weighted Tallies for k-Eigenvalue Calculations with Continuous-Energy Monte Carlo

Brian C. Kiedrowski, Forrest B. Brown, Paul P. H. Wilson

Nuclear Science and Engineering / Volume 168 / Number 3 / July 2011 / Pages 226-241

Technical Paper / dx.doi.org/10.13182/NSE10-22

Using Core Symmetry in Monte Carlo Dominance Ratio Calculations

Sergey S. Gorodkov

Nuclear Science and Engineering / Volume 168 / Number 3 / July 2011 / Pages 242-247

Technical Paper

Stochastic Invariant Imbedding Theory for a Distributed Internal Source

S. B. Degweker, Imre Pázsit

Nuclear Science and Engineering / Volume 168 / Number 3 / July 2011 / Pages 248-264

Technical Paper

Deterministic and Stochastic Evaluation of Criticality Excursion Power Bursts

Scott D. Ramsey, Gregory J. Hutchens

Nuclear Science and Engineering / Volume 168 / Number 3 / July 2011 / Pages 265-277

Technical Paper / dx.doi.org/10.13182/NSE10-11

Simplified Simulation of Fast Neutron Scattering for an Explosives Detection Application

A. L. Lehnert, K. J. Kearfott

Nuclear Science and Engineering / Volume 168 / Number 3 / July 2011 / Pages 278-286

Technical Paper / dx.doi.org/10.13182/NSE10-13

An Experimental Study on Radon Adsorption Ability and Microstructure of Activated Carbon

Qingbo Wang, Jingyuan Qu, Wenkai Zhu, Baichang Zhou, Jinxing Cheng

Nuclear Science and Engineering / Volume 168 / Number 3 / July 2011 / Pages 287-292

Technical Note

 
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