ANS / Publications / Journals / Nuclear Science and Engineering

Approximate Solution and Application of the Survival Probability Diffusion Equation

Scott D. Ramsey, Gregory J. Hutchens

Nuclear Science and Engineering / Volume 170 / Number 1 / January 2012 / Pages 1-15

Technical Paper / dx.doi.org/10.13182/NSE10-26

Proliferation-Resistant Fuel for CANDU Reactors

Yigal Ronen, M. Aboudy, D. Regev

Nuclear Science and Engineering / Volume 170 / Number 1 / January 2012 / Pages 16-26

Technical Paper / dx.doi.org/10.13182/NSE10-51

Chaotic Data Encryption for Long-Distance Monitoring of Nuclear Reactors

Günyaz Ablay, Can Emre Koksal, Tunc Aldemir

Nuclear Science and Engineering / Volume 170 / Number 1 / January 2012 / Pages 27-43

Technical Paper / dx.doi.org/10.13182/NSE10-21

Measurement of ²³²Th(n,)²³³Th, ⁹⁸Mo(n,)⁹⁹Mo, ¹⁸⁶W(n,)¹⁸⁷W, ¹¹⁵In(n,)^116m1In, and ⁹²Mo(n,p)^92mNb Cross Sections in the Energy Range of 1.6 to 3.7 MeV

Megha Bhike, B. J. Roy, A. Saxena, R. K. Choudhury, S. Ganesan

Nuclear Science and Engineering / Volume 170 / Number 1 / January 2012 / Pages 44-53

Technical Paper / dx.doi.org/10.13182/NSE10-63

Peelle's Pertinent Puzzle: A Fake Due to Improper Analysis

Denise Neudecker, Rudolf Frühwirth, Helmut Leeb

Nuclear Science and Engineering / Volume 170 / Number 1 / January 2012 / Pages 54-60

Technical Paper / dx.doi.org/10.13182/NSE11-20

Studies on Production of Neutrons in the Spallation Reactions Using the Monte Carlo Code MCNPX

Heba Louis, Esmaat Amin, Moustafa Aziz, Ibrahim Bashter

Nuclear Science and Engineering / Volume 170 / Number 1 / January 2012 / Pages 61-65

Technical Paper / dx.doi.org/10.13182/NSE11-11

Correcting the Cusping Problem in Three-Dimensional Transients Through NEM Modification

Zelmo Rodrigues de Lima, Aquilino Senra Martinez, Fernando Carvalho da Silva, Antonio Carlos Marques Alvim

Nuclear Science and Engineering / Volume 170 / Number 1 / January 2012 / Pages 66-74

Technical Note / dx.doi.org/10.13182/NSE10-67TN

On the Method ASCM for the Solution of the External Source Problem in a Slightly Subcritical Reactor

Sherly Ray, R. S. Modak

Nuclear Science and Engineering / Volume 170 / Number 1 / January 2012 / Pages 75-86

Technical Note / dx.doi.org/10.13182/NSE10-87TN

Cross-Section Uncertainty Propagation in the Multigroup Slowing-Down Equations Using Probability Table Formalism

Cheikh M. Diop, Mireille Coste-Delclaux, Sébastien Lahaye

Nuclear Science and Engineering / Volume 170 / Number 1 / January 2012 / Pages 87-97

Technical Note / dx.doi.org/10.13182/NSE10-94TN

Highly Efficient, Exact Quadratures for Three-Dimensional Discrete Ordinates Transport Calculations

Cory D. Ahrens

Nuclear Science and Engineering / Volume 170 / Number 1 / January 2012 / Pages 98-101

Technical Note / dx.doi.org/10.13182/NSE10-69TN

An Efficient Multiproblem Strategy for Accurate Solutions of Linear Particle Transport Problems in Spherical Geometry

Paolo Picca, Roberto Furfaro, Barry D. Ganapol

Nuclear Science and Engineering / Volume 170 / Number 2 / February 2012 / Pages 103-124

Technical Paper / dx.doi.org/10.13182/NSE11-05

Parallel Fission Bank Algorithms in Monte Carlo Criticality Calculations

Paul K. Romano, Benoit Forget

Nuclear Science and Engineering / Volume 170 / Number 2 / February 2012 / Pages 125-135

Technical Paper / dx.doi.org/10.13182/NSE10-98

A Probabilistic Physics-of-Failure Approach to Prediction of Steam Generator Tube Rupture Frequency

Kaushik Chatterjee, Mohammad Modarres

Nuclear Science and Engineering / Volume 170 / Number 2 / February 2012 / Pages 136-150

Technical Paper / dx.doi.org/10.13182/NSE11-27

Analysis of the Core Power Response During a PWR Rod Ejection Transient Using the PARCS Nodal Code and the DeCART MOC Code

Mathieu Hursin, Thomas J. Downar, Brendan Kochunas

Nuclear Science and Engineering / Volume 170 / Number 2 / February 2012 / Pages 151-167

Technical Paper / dx.doi.org/10.13182/NSE10-75

Gradient-Enhanced Universal Kriging for Uncertainty Propagation

Brian A. Lockwood, Mihai Anitescu

Nuclear Science and Engineering / Volume 170 / Number 2 / February 2012 / Pages 168-195

Technical Paper / dx.doi.org/10.13182/NSE10-86

A Technique for Accounting for Multigroup Cross-Section Interdependence in Sensitivity Calculations

Kirill Fedorovich Raskach

Nuclear Science and Engineering / Volume 170 / Number 2 / February 2012 / Pages 196-206

Technical Paper / dx.doi.org/10.13182/NSE11-09

Novel Investigation of Iron Cross Sections via Spherical Shell Transmission Measurements and Particle Transport Calculations for Material Embrittlement Studies

Michael T. Wenner, Alireza Haghighat, James M. Adams, Allan D. Carlson, Steven M. Grimes, Thomas N. Massey

Nuclear Science and Engineering / Volume 170 / Number 3 / March 2012 / Pages 207-233

Technical Paper / dx.doi.org/10.13182/NSE09-30

Kernel Density Estimation Method for Monte Carlo Global Flux Tallies

Kaushik Banerjee, William R. Martin

Nuclear Science and Engineering / Volume 170 / Number 3 / March 2012 / Pages 234-250

Technical Paper / dx.doi.org/10.13182/NSE10-77

An Innovative Method to Measure the Gamma-Ray Emission Probabilities in the Decay of ²³⁸Np and ²³³Pa

P. Leconte, J.-P. Hudelot, M. Antony, J. Di-Salvo, D. Bernard

Nuclear Science and Engineering / Volume 170 / Number 3 / March 2012 / Pages 251-264

Technical Paper / dx.doi.org/10.13182/NSE11-14

Evaluation and Adjustment of the Neutron-Induced Reactions of ^63,65Cu

D. Rochman, A. J. Koning

Nuclear Science and Engineering / Volume 170 / Number 3 / March 2012 / Pages 265-279

Technical Paper / dx.doi.org/10.13182/NSE11-37

Computational Schemes for Online Flux Mapping System in a Large-Sized Pressurized Heavy Water Reactor

Surendra Mishra , R. S. Modak, S. Ganesan

Nuclear Science and Engineering / Volume 170 / Number 3 / March 2012 / Pages 280-289

Technical Paper / dx.doi.org/10.13182/NSE10-84

Core Temperature Monitoring System for Prototype Fast Breeder Reactor

M. Sakthivel, K. Madhusoodanan

Nuclear Science and Engineering / Volume 170 / Number 3 / March 2012 / Pages 290-293

Technical Paper / dx.doi.org/10.13182/NSE11-07