ANS / Publications / Journals / Nuclear Science and Engineering

A New Approximation for the Neutron Albedo

Ronald C. Brockhoff, J. Kenneth Shultis

Nuclear Science and Engineering / Volume 155 / Number 1 / January 2007 / Pages 1-17

Technical Paper / dx.doi.org/10.13182/NSE07-A2641

Sensitivity and Uncertainty Analysis for Eigenvalue-Difference Responses

Mark L. Williams

Nuclear Science and Engineering / Volume 155 / Number 1 / January 2007 / Pages 18-36

Technical Paper / dx.doi.org/10.13182/NSE06-11

Multigroup Adjoint Transport Solution Using the Method of Cyclic Characteristics

M. Assawaroongruengchot, G. Marleau

Nuclear Science and Engineering / Volume 155 / Number 1 / January 2007 / Pages 37-52

Technical Paper / dx.doi.org/10.13182/NSE07-A2643

Plutonium Denaturing by ²³⁸Pu

G. Kessler

Nuclear Science and Engineering / Volume 155 / Number 1 / January 2007 / Pages 53-73

Technical Paper / dx.doi.org/10.13182/NSE07-A2644

Neutron Scattering from an Asymmetric Rotor: ¹⁹⁷Au

Alan B. Smith

Nuclear Science and Engineering / Volume 155 / Number 1 / January 2007 / Pages 74-83

Technical Paper / dx.doi.org/10.13182/NSE07-A2645

Improved Evaluations of Neutron-Induced Reactions on Americium Isotopes

P. Talou, T. Kawano, P. G. Young, M. B. Chadwick, R. E. MacFarlane

Nuclear Science and Engineering / Volume 155 / Number 1 / January 2007 / Pages 84-95

Technical Paper / dx.doi.org/10.13182/NSE07-A2646

Radial and Azimuthal ²³⁵U Fission and ²³⁸U Capture Distributions in BWR UO₂ Pins: CASMO-4 and MCNP4C Versus Activation Foil Measurements

K. Macku, F. Jatuff, M. Murphy, M. Plaschy, P. Grimm, O. P. Joneja, R. Chawla

Nuclear Science and Engineering / Volume 155 / Number 1 / January 2007 / Pages 96-101

Technical Paper / dx.doi.org/10.13182/NSE07-A2647

Studies on Effective Atomic Numbers and Electron Densities in Some Commonly Used Solvents

Ashok Kumar, Sukhpal Singh, Gurmel S. Mudahar, Kulwant Singh Thind

Nuclear Science and Engineering / Volume 155 / Number 1 / January 2007 / Pages 102-108

Technical Paper / dx.doi.org/10.13182/NSE07-A2648

Polynomial Chaos Functions and Neutron Diffusion

M. M. R. Williams

Nuclear Science and Engineering / Volume 155 / Number 1 / January 2007 / Pages 109-118

Technical Note / dx.doi.org/10.13182/NSE05-73TN

A New Approach to Spatio-Temporal Calculation of Nuclear Reactor Cores Using Neural Computing

Mehrdad Boroushaki, Mohammad B. Ghofrani, Caro Lucas

Nuclear Science and Engineering / Volume 155 / Number 1 / January 2007 / Pages 119-130

Technical Note / dx.doi.org/10.13182/NSE07-A2650

Monte Carlo Modeling of Delayed Neutrons from Photofission

Enrico Padovani, Maura Monville, Sara A. Pozzi

Nuclear Science and Engineering / Volume 155 / Number 1 / January 2007 / Pages 131-142

Technical Note / dx.doi.org/10.13182/NSE07-A2651

CEARCPG: A Monte Carlo Simulation Code for Normal and Coincidence Prompt-Gamma-Ray Neutron Activation Analysis

Xiaogang Han, Robin P. Gardner, W. A. Metwally

Nuclear Science and Engineering / Volume 155 / Number 1 / January 2007 / Pages 143-153

Computer Code Abstract / dx.doi.org/10.13182/NSE07-A2652

A Hybrid Monte Carlo-Deterministic Method for Global Particle Transport Calculations

Troy L. Becker, Allan B. Wollaber, Edward W. Larsen

Nuclear Science and Engineering / Volume 155 / Number 2 / February 2007 / Pages 155-167

Technical Paper / Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications / dx.doi.org/10.13182/NSE07-A2653

A Lumped Linear-Discontinuous Spatial Discretization Scheme for Triangular-Mesh S_n Calculations in r-z Geometry

Jim E. Morel, Alejandro Gonzalez-Aller, James S. Warsa

Nuclear Science and Engineering / Volume 155 / Number 2 / February 2007 / Pages 168-178

Technical Paper / Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications / dx.doi.org/10.13182/NSE07-A2654

An Efficient Exponential Directional Iterative Differencing Scheme for Three-Dimensional S_n Computations in XYZ Geometry

Glenn E. Sjoden

Nuclear Science and Engineering / Volume 155 / Number 2 / February 2007 / Pages 179-189

Technical Paper / Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications / dx.doi.org/10.13182/NSE07-A2655

A Two-Dimensional Discontinuous Heterogeneous Finite Element Method for Neutron Transport Calculations

Emiliano Masiello, Richard Sanchez

Nuclear Science and Engineering / Volume 155 / Number 2 / February 2007 / Pages 190-207

Technical Paper / Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications / dx.doi.org/10.13182/NSE07-A2656

A Nonlinear Space-Angle Multigrid Acceleration for the Method of Characteristics in Unstructured Meshes

Gabriele Grassi

Nuclear Science and Engineering / Volume 155 / Number 2 / February 2007 / Pages 208-222

Technical Paper / Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications / dx.doi.org/10.13182/NSE07-A2657

An Integral Multidomain DP_N Operator as Acceleration Tool for the Method of Characteristics in Unstructured Meshes

Simone Santandrea

Nuclear Science and Engineering / Volume 155 / Number 2 / February 2007 / Pages 223-235

Technical Paper / Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications / dx.doi.org/10.13182/NSE155-223

Solving Three-Dimensional Large-Scale Neutron Transport Problems Using Hybrid Shared-Distributed Parallelism and Characteristics Method

Mohamed Dahmani, Robert Roy

Nuclear Science and Engineering / Volume 155 / Number 2 / February 2007 / Pages 236-249

Technical Paper / Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications / dx.doi.org/10.13182/NSE155-236

MINOS: A Simplified P_n Solver for Core Calculation

Anne-Marie Baudron, Jean-Jacques Lautard

Nuclear Science and Engineering / Volume 155 / Number 2 / February 2007 / Pages 250-263

Technical Paper / Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications / dx.doi.org/10.13182/NSE07-A2660

Component Mode Synthesis Methods for 3-D Heterogeneous Core Calculations Applied to the Mixed-Dual Finite Element Solver MINOS

Pierre Guérin, Anne-Marie Baudron, Jean-Jacques Lautard, Serge Van Criekingen

Nuclear Science and Engineering / Volume 155 / Number 2 / February 2007 / Pages 264-275

Technical Paper / Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications / dx.doi.org/10.13182/NSE07-A2661

Neutron Transport Models of AEGIS: An Advanced Next-Generation Neutronics Design System

Naoki Sugimura, Akio Yamamoto, Tadashi Ushio, Masaaki Mori, Masato Tabuchi, Tomohiro Endo

Nuclear Science and Engineering / Volume 155 / Number 2 / February 2007 / Pages 276-289

Technical Paper / Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications / dx.doi.org/10.13182/NSE155-276

A Quasilinear Implicit Riemann Solver for the Time-Dependent P_n Equations

Ryan G. McClarren, James Paul Holloway, Thomas A. Brunner, Thomas A. Mehlhorn

Nuclear Science and Engineering / Volume 155 / Number 2 / February 2007 / Pages 290-299

Technical Paper / Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications / dx.doi.org/10.13182/NSE07-A2663

The Boundary Source Method with Arbitrary Order Anisotropic Scattering

Gert Van den Eynde, Robert Beauwens, Ernest Mund

Nuclear Science and Engineering / Volume 155 / Number 2 / February 2007 / Pages 300-309

Technical Paper / Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications / dx.doi.org/10.13182/NSE07-A2664

A Review of Legacy and Advanced Self-Shielding Models for Lattice Calculations

Alain Hébert

Nuclear Science and Engineering / Volume 155 / Number 2 / February 2007 / Pages 310-320

Technical Paper / Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications / dx.doi.org/10.13182/NSE06-50

Variational Estimates of Neutron-Induced Gamma Line Leakages and Ratios for Internal Interface Perturbations

Jeffrey A. Favorite

Nuclear Science and Engineering / Volume 155 / Number 2 / February 2007 / Pages 321-329

Technical Paper / Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications / dx.doi.org/10.13182/NSE07-A2666

Description of the LANCER02 Lattice Physics Code for Single-Assembly and Multibundle Analysis

Dave Knott, Erin Wehlage

Nuclear Science and Engineering / Volume 155 / Number 3 / March 2007 / Pages 331-354

Technical Paper / Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications / dx.doi.org/10.13182/NSE155-331

An Analysis of the Extended-Transport Correction with Application to Electron Beam Transport

Clifton R. Drumm, Wesley C. Fan, Leonard Lorence, Jennifer Liscum-Powell

Nuclear Science and Engineering / Volume 155 / Number 3 / March 2007 / Pages 355-366

Technical Paper / Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications / dx.doi.org/10.13182/NSE07-A2668

Development of a Scatter Search Optimization Algorithm for Boiling Water Reactor Fuel Lattice Design

Juan-Luis François, Cecilia Martín-del-Campo, Luis B. Morales, Miguel-Angel Palomera

Nuclear Science and Engineering / Volume 155 / Number 3 / March 2007 / Pages 367-377

Technical Paper / Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications / dx.doi.org/10.13182/NSE07-A2669

Coupled Bundle-Core Design Using Fuel Rod Optimization for Boiling Water Reactors

Matthew A. Jessee, David J. Kropaczek

Nuclear Science and Engineering / Volume 155 / Number 3 / March 2007 / Pages 378-385

Technical Paper / Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications / dx.doi.org/10.13182/NSE07-A2670

Optimized Adaptive Fuzzy Controller of the Water Level of a Pressurized Water Reactor Steam Generator

M. Marseguerra, E. Zio, F. Cadini

Nuclear Science and Engineering / Volume 155 / Number 3 / March 2007 / Pages 386-394

Technical Paper / Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications / dx.doi.org/10.13182/NSE07-A2671

High-Fidelity Light Water Reactor Analysis with the Numerical Nuclear Reactor

David P. Weber, Tanju Sofu, Won Sik Yang, Thomas J. Downar, Justin W. Thomas, Zhaopeng Zhong, Jin Young Cho, Kang Seog Kim, Tae Hyun Chun, Han Gyu Joo, Chang Hyo Kim

Nuclear Science and Engineering / Volume 155 / Number 3 / March 2007 / Pages 395-408

Technical Paper / Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications / dx.doi.org/10.13182/NSE07-A2672

Use of 3D-VAR and Kalman Filter Approaches for Neutronic State and Parameter Estimation in Nuclear Reactors

Sébastien Massart, Samuel Buis, Patrick Erhard, Guillaume Gacon

Nuclear Science and Engineering / Volume 155 / Number 3 / March 2007 / Pages 409-424

Technical Paper / Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications / dx.doi.org/10.13182/NSE07-A2673

Theory of Neutron Noise in a Temporally Fluctuating Multiplying Medium

Lénárd Pál, Imre Pázsit

Nuclear Science and Engineering / Volume 155 / Number 3 / March 2007 / Pages 425-440

Technical Paper / Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications / dx.doi.org/10.13182/NSE07-A2674

Atomic Mix Synthetic Acceleration of Dose Computations in Binary Statistical Media

Anil K. Prinja, Erin D. Fichtl

Nuclear Science and Engineering / Volume 155 / Number 3 / March 2007 / Pages 441-448

Technical Paper / Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications / dx.doi.org/10.13182/NSE07-A2675

Investigation of the Impact of Simple Carbon Interstitial Formations on Thermal Neutron Scattering in Graphite

Ayman I. Hawari, Iyad I. Al-Qasir, Abderrafi M. Ougouag

Nuclear Science and Engineering / Volume 155 / Number 3 / March 2007 / Pages 449-462

Technical Paper / Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications / dx.doi.org/10.13182/NSE07-A2676

Effect of Mass and Activity Heterogeneities on the Activity Measurement of Large Packages of Radioactive Waste

Bernard Rottner

Nuclear Science and Engineering / Volume 155 / Number 3 / March 2007 / Pages 463-474

Technical Paper / Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications / dx.doi.org/10.13182/NSE07-A2677

Interactions Between Fluid-Dynamics and Neutronic Phenomena in the Physics of Molten-Salt Systems

S. Dulla, P. Ravetto

Nuclear Science and Engineering / Volume 155 / Number 3 / March 2007 / Pages 475-488

Technical Paper / Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications / dx.doi.org/10.13182/NSE07-A2678

Turbulent Heat Flux and Temperature Variance Dissipation Rate in Natural Convection in Lead-Bismuth

I. Otic, G. Grötzbach

Nuclear Science and Engineering / Volume 155 / Number 3 / March 2007 / Pages 489-496

Technical Paper / Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications / dx.doi.org/10.13182/NSE07-A2679

Some Measure Theoretic Issues in Probabilistic Dynamics

Tunc Aldemir

Nuclear Science and Engineering / Volume 155 / Number 3 / March 2007 / Pages 497-507

Technical Note / Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications / dx.doi.org/10.13182/NSE07-A2680