ANS / Publications / Journals / Nuclear Science and Engineering

Analysis of Reactivity Coefficients of Hydride-Fueled PWR Cores

Francesco Ganda, Ehud Greenspan

Nuclear Science and Engineering / Volume 164 / Number 1 / January 2010 / Pages 1-32

Technical Paper / dx.doi.org/10.13182/NSE08-64

Fourier Convergence Analysis of the Rebalance Methods for Discrete Ordinates Transport Equations in Eigenvalue Problems

Ser Gi Hong, Kang-Seog Kim, Jae Seung Song

Nuclear Science and Engineering / Volume 164 / Number 1 / January 2010 / Pages 33-52

Technical Paper / dx.doi.org/10.13182/NSE09-18

Power Distribution Analysis for the ORNL High Flux Isotope Reactor Critical Experiment 3

David Chandler, R. T. Primm III, G. Ivan Maldonado

Nuclear Science and Engineering / Volume 164 / Number 1 / January 2010 / Pages 53-68

Technical Paper / dx.doi.org/10.13182/NSE09-03

Neutron Detection-Based Void Monitoring in Boiling Water Reactors

John Loberg, Michael Österlund, Jan Blomgren, Klaes-Håkan Bejmer

Nuclear Science and Engineering / Volume 164 / Number 1 / January 2010 / Pages 69-79

Technical Paper / dx.doi.org/10.13182/NSE09-17

Calculation of the Integral Kinetic Model Transient Parameters by the Monte Carlo Method for Space-Dependent Kinetic Analysis

Hiroki Takezawa, Toru Obara

Nuclear Science and Engineering / Volume 164 / Number 1 / January 2010 / Pages 80-86

Technical Note / dx.doi.org/10.13182/NSE08-91

Daubechies' Wavelet Method for Angular Solution of the Neutron Transport Equation

Youqi Zheng, Hongchun Wu, Liangzhi Cao, Nam Zin Cho

Nuclear Science and Engineering / Volume 164 / Number 2 / February 2010 / Pages 87-104

Technical Paper / dx.doi.org/10.13182/NSE09-21

The Inner-Element Subgrid Scale Finite Element Method for the Boltzmann Transport Equation

Andrew G. Buchan, Adam S. Candy, Simon R. Merton, Christopher C. Pain, Justin I. Hadi, Matthew D. Eaton, Anthony J. H. Goddard, Richard P. Smedley-Stevenson, Gregory J. Pearce

Nuclear Science and Engineering / Volume 164 / Number 2 / February 2010 / Pages 105-121

Technical Paper / dx.doi.org/10.13182/NSE08-82

Polynomial Regression Approaches Using Derivative Information for Uncertainty Quantification

Oleg Roderick, Mihai Anitescu, Paul Fischer

Nuclear Science and Engineering / Volume 164 / Number 2 / February 2010 / Pages 122-139

Technical Paper / dx.doi.org/10.13182/NSE08-79

Computing the Matrix Exponential in Burnup Calculations

Maria Pusa, Jaakko Leppänen

Nuclear Science and Engineering / Volume 164 / Number 2 / February 2010 / Pages 140-150

Technical Paper / dx.doi.org/10.13182/NSE09-14

Determination of Operator Action Times During a Loss-of-Feedwater Event Using Extreme Value Statistics

A. C. Morreale, D. R. Novog

Nuclear Science and Engineering / Volume 164 / Number 2 / February 2010 / Pages 151-161

Technical Paper / dx.doi.org/10.13182/NSE08-16

Reactivity Effects of Differences Between JEFF-3.1 and ENDF/B-VI.8 in Analysis of Six MASURCA Cores of the R-Z Program

Michael A. Pope, Jean Tommasi

Nuclear Science and Engineering / Volume 164 / Number 2 / February 2010 / Pages 162-184

Technical Paper / dx.doi.org/10.13182/NSE09-22

Double-Differential Cross Sections of the Particle Emission in Neutron-Induced Reactions on ²⁰⁹Bi

Yinlu Han, Ping Liu, Chonghai Cai

Nuclear Science and Engineering / Volume 164 / Number 2 / February 2010 / Pages 185-203

Technical Paper / dx.doi.org/10.13182/NSE09-20

Discontinuous Least-Squares Spatial Discretization Schemes for the One-Dimensional Slab-Geometry Sn Equations

Lei Zhu, Jim E. Morel

Nuclear Science and Engineering / Volume 164 / Number 3 / March 2010 / Pages 205-220

Technical Paper / dx.doi.org/10.13182/NSE08-67

A Three-Dimensional Block-Oriented Hybrid Discrete Ordinates and Characteristics Method

Ce Yi, Alireza Haghighat

Nuclear Science and Engineering / Volume 164 / Number 3 / March 2010 / Pages 221-247

Technical Paper / dx.doi.org/10.13182/NSE09-110

Fourier Analysis of Inexact Parallel Block-Jacobi Splitting with Transport Synthetic Acceleration

Massimiliano Rosa, James S. Warsa, Jae H. Chang

Nuclear Science and Engineering / Volume 164 / Number 3 / March 2010 / Pages 248-263

Technical Paper / dx.doi.org/10.13182/NSE09-26

Finite Element Analysis of Transient Heat Transfer in and Around a Deep Geological Repository for a Spent Nuclear Fuel Disposal Canister and the Heat Generation of the Spent Nuclear Fuel

Young Joo Kwon

Nuclear Science and Engineering / Volume 164 / Number 3 / March 2010 / Pages 264-286

Technical Paper / dx.doi.org/10.13182/NSE09-11

Resonance Parameters and Uncertainties Derived from Epithermal Neutron Capture and Transmission Measurements of Natural Molybdenum

G. Leinweber, D. P. Barry, J. A. Burke, N. J. Drindak, Y. Danon, R. C. Block, N. C. Francis, B. E. Moretti

Nuclear Science and Engineering / Volume 164 / Number 3 / March 2010 / Pages 287-303

Technical Paper / dx.doi.org/10.13182/NSE08-76

Recalculation and Reevaluation of the Complete Sets of Neutron Data for ⁶³Cu and ⁶⁵Cu Below 20 MeV

Chonghai Cai, Kai Xu, Haixia An, Haicheng Wu

Nuclear Science and Engineering / Volume 164 / Number 3 / March 2010 / Pages 304-317

Technical Note / dx.doi.org/10.13182/NSE08-62TN