American Nuclear Society
Home

Home / Publications / Journals / Nuclear Science and Engineering / Volume 156

Volume 156

Number 1 | Number 2 | Number 3

Number 1

Fuel Cycle Options for the Production and Utilization of Denatured Plutonium

C. H. M. Broeders, G. Kessler

Nuclear Science and Engineering / Volume 156 / Number 1 / May 2007 / Pages 1-23

Technical Paper / dx.doi.org/10.13182/NSE07-A2681

Numerical Modeling of Evaporating Thin Liquid Film Instability on a Heated Cylindrical Rod with Parallel and Cross Vapor Flow

Seungwon Shin, S. I. Abdel-Khalik

Nuclear Science and Engineering / Volume 156 / Number 1 / May 2007 / Pages 24-39

Technical Paper / dx.doi.org/10.13182/NSE07-A2682

Two-Dimensional Modeling of the Direct ECC Bypass in the APR1400 Downcomer

H. K. Cho, B. J. Yun, C.-H. Song, G. C. Park

Nuclear Science and Engineering / Volume 156 / Number 1 / May 2007 / Pages 40-54

Technical Paper / dx.doi.org/10.13182/NSE07-A2683

Strategies in Stochastic Transport

A. Ziya Akcasu, Noel Corngold

Nuclear Science and Engineering / Volume 156 / Number 1 / May 2007 / Pages 55-67

Technical Paper / dx.doi.org/10.13182/NSE07-A2684

The Description of Particle Transport Problems with Helical Symmetry

Edward W. Larsen

Nuclear Science and Engineering / Volume 156 / Number 1 / May 2007 / Pages 68-73

Technical Paper / dx.doi.org/10.13182/NSE07-A2685

Fourier Convergence Analysis of Two-Dimensional/One-Dimensional Coupling Methods for the Three-Dimensional Neutron Diffusion Eigenvalue Problems

Hyun Chul Lee, Jae Man Noh, Hyung Kook Joo, Deokjung Lee, Thomas J. Downar

Nuclear Science and Engineering / Volume 156 / Number 1 / May 2007 / Pages 74-85

Technical Paper / dx.doi.org/10.13182/NSE06-32

Investigations of 238U Captures to Total Fissions in a Westinghouse SVEA-96+ Assembly

U. C. Bergmann, P. Grimm, F. Jatuff, M. F. Murphy, R. Chawla

Nuclear Science and Engineering / Volume 156 / Number 1 / May 2007 / Pages 86-95

Technical Paper / dx.doi.org/10.13182/NSE07-A2687

Process Development for Bulk Separation of Trivalent Actinides and Lanthanides from Radioactive High-Level Liquid Waste

Smitha Manohar, J. N. Sharma, B. V. Shah, P. K. Wattal

Nuclear Science and Engineering / Volume 156 / Number 1 / May 2007 / Pages 96-102

Technical Paper / dx.doi.org/10.13182/NSE07-A2688

The 10B(n,0)/10B(n,1) Branching Ratio

F.-J. Hambsch, I. Ruskov

Nuclear Science and Engineering / Volume 156 / Number 1 / May 2007 / Pages 103-114

Technical Paper / dx.doi.org/10.13182/NSE07-A2689

Differential Cross-Section Measurement for the 64Zn(n, )61Ni Reaction at 5.03 and 5.95 MeV

Guohui Zhang, Rongtai Cao, Jinxiang Chen, Guoyou Tang, Yu. M. Gledenov, M. Sedysheva, G. Khuukhenkhuu

Nuclear Science and Engineering / Volume 156 / Number 1 / May 2007 / Pages 115-119

Technical Paper / dx.doi.org/10.13182/NSE07-A2690

Number 2

An Improved Algebraic Collapsing Acceleration with General Boundary Conditions for the Characteristics Method

R. Le Tellier, A. Hébert

Nuclear Science and Engineering / Volume 156 / Number 2 / June 2007 / Pages 121-138

Technical Paper / dx.doi.org/10.13182/NSE07-A2691

A Discretization Scheme for the Three-Dimensional Angular Fokker-Planck Operator

Jim E. Morel, Anil Prinja, John M. McGhee, Todd A. Wareing, Brian C. Franke

Nuclear Science and Engineering / Volume 156 / Number 2 / June 2007 / Pages 154-163

Technical Paper / dx.doi.org/10.13182/NSE07-A2693

Nonanalog Implementations of Monte Carlo Isotopic Inventory Analysis

Phiphat Phruksarojanakun, Paul P. H. Wilson

Nuclear Science and Engineering / Volume 156 / Number 2 / June 2007 / Pages 164-179

Technical Paper / dx.doi.org/10.13182/NSE07-A2694

An Optimum Approach to Monte Carlo Burnup

W. Haeck, B. Verboomen

Nuclear Science and Engineering / Volume 156 / Number 2 / June 2007 / Pages 180-196

Technical Paper / dx.doi.org/10.13182/NSE07-A2695

Cross Sections for Neutron-Induced Fission of 235U, 238U, 209Bi, and natPb in the Energy Range from 33 to 200 MeV Measured Relative to n-p Scattering

R. Nolte, M. S. Allie, F. D. Brooks, A. Buffler, V. Dangendorf, J. P. Meulders, H. Schuhmacher, F. D. Smit, M. Weierganz

Nuclear Science and Engineering / Volume 156 / Number 2 / June 2007 / Pages 197-210

Technical Paper / dx.doi.org/10.13182/NSE06-14

High Resolution Measurement of the 234U(n,f) Cross Section in the Neutron Energy Range from 0.5 eV to 100 keV

J. Heyse, C. Wagemans, L. De Smet, O. Serot, J. Wagemans, J. Van Gils

Nuclear Science and Engineering / Volume 156 / Number 2 / June 2007 / Pages 211-218

Technical Paper / dx.doi.org/10.13182/NSE07-A2697

Isotope Separation Using Condensation Repression of the Laser Excited Gaseous CHCl3 Molecules Colliding with a Cold Wall

Jaewoo Kim, Jeff W. Eerkens, William H. Miller

Nuclear Science and Engineering / Volume 156 / Number 2 / June 2007 / Pages 219-228

Technical Paper / dx.doi.org/10.13182/NSE07-A2698

Variation of Mass Attenuation Coefficient, Effective Atomic Number, and Electron Density with Incident Photon Energy of Some Organic Acids

Tejbir Singh, Paramjeet Kaur, Parjit S. Singh

Nuclear Science and Engineering / Volume 156 / Number 2 / June 2007 / Pages 229-243

Technical Paper / dx.doi.org/10.13182/NSE07-A2699

Incineration of Light Water Reactor Waste in High-Temperature Gas Reactors: Axial Fuel Management and Efficiency of Americium and Curium Transmutation

Alberto Talamo, Waclaw Gudowski

Nuclear Science and Engineering / Volume 156 / Number 2 / June 2007 / Pages 244-266

Technical Note / dx.doi.org/10.13182/NSE07-A2700

Isotopic and Energy Groupwise Dependence of Fuel Temperature Coefficient of Reactivity in Natural Uranium-Fueled Pressurized Heavy Water Reactors

Kannan Umasankari, S. Ganesan

Nuclear Science and Engineering / Volume 156 / Number 2 / June 2007 / Pages 267-279

Technical Note / dx.doi.org/10.13182/NSE07-A2701

Number 3

NEPTUNE: A New Software Platform for Advanced Nuclear Thermal Hydraulics

Antoine Guelfi, Dominique Bestion, Marc Boucker, Pascal Boudier, Philippe Fillion, Marc Grandotto, Jean-Marc Hérard, Eric Hervieu, Pierre Péturaud

Nuclear Science and Engineering / Volume 156 / Number 3 / July 2007 / Pages 281-324

Technical Paper / dx.doi.org/10.13182/NSE05-98

Spatial Finite-Element Lumping Techniques for the Quadrilateral Mesh Sn Equations in X-Y Geometry

Jim E. Morel, James S. Warsa

Nuclear Science and Engineering / Volume 156 / Number 3 / July 2007 / Pages 325-342

Technical Paper / dx.doi.org/10.13182/NSE06-13

Analytical Calculation of the Average Dancoff Factor for Prismatic High-Temperature Reactors

Alberto Talamo

Nuclear Science and Engineering / Volume 156 / Number 3 / July 2007 / Pages 343-356

Technical Paper / dx.doi.org/10.13182/NSE07-A2704

New Nuclear Data Libraries for Lead and Bismuth and Their Impact on Accelerator-Driven Systems Design

A. J. Koning, M. C. Duijvestijn, S. C. van der Marck, R. Klein Meulekamp, A. Hogenbirk

Nuclear Science and Engineering / Volume 156 / Number 3 / July 2007 / Pages 357-390

Technical Paper / dx.doi.org/10.13182/NSE156-357

Evaluation of the 238U Neutron Cross Section in the Unresolved Resonance Range

Arnaud Courcelle, Hervé Derrien, Luiz C. Leal, Nancy M. Larson

Nuclear Science and Engineering / Volume 156 / Number 3 / July 2007 / Pages 391-402

Technical Paper / dx.doi.org/10.13182/NSE07-A2706

Unbiased Monte Carlo Estimation of the Reciprocal of an Integral

Thomas E. Booth

Nuclear Science and Engineering / Volume 156 / Number 3 / July 2007 / Pages 403-407

Technical Paper / dx.doi.org/10.13182/NSE07-A2707

The Common Properties of the "Fertile" Isotopes

Y. Ronen

Nuclear Science and Engineering / Volume 156 / Number 3 / July 2007 / Pages 408-409

Technical Note / dx.doi.org/10.13182/NSE07-A2708