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Volume 152

Number 1 | Number 2 | Number 3

Number 1

Determination of the 232Th(n,) Cross Section from 4 to 140 keV at GELINA

A. Borella, K. Volev, A. Brusegan, P. Schillebeeckx, F. Corvi, N. Koyumdjieva, N. Janeva, A. A. Lukyanov

Nuclear Science and Engineering / Volume 152 / Number 1 / January 2006 / Pages 1-14

Technical Paper

Comparison of Ramsauer and Optical Model Neutron Angular Distributions

D. P. McNabb, J. D. Anderson, R. W. Bauer, F. S. Dietrich, S. M. Grimes, C. A. Hagmann

Nuclear Science and Engineering / Volume 152 / Number 1 / January 2006 / Pages 15-22

Technical Paper

Investigation of the Ramsauer Model for the Prediction of Neutron Cross Sections Below 120 MeV

R. S. Gowda, S. Ganesan

Nuclear Science and Engineering / Volume 152 / Number 1 / January 2006 / Pages 23-28

Technical Paper

Generalization of the Variational Nodal Method to Spherical Harmonics Approximations in R-Z Geometry

Hui Zhang, E. E. Lewis

Nuclear Science and Engineering / Volume 152 / Number 1 / January 2006 / Pages 29-36

Technical Paper

Development of Probabilistic Design Method for Fast Reactor Fuel Rod

T. Ozawa, T. Abe

Nuclear Science and Engineering / Volume 152 / Number 1 / January 2006 / Pages 37-47

Technical Paper

A New Automatic Biasing Technique for Transport Monte Carlo Methods

Jean-Marc Depinay, Michel Caillaud, Remi Sentis

Nuclear Science and Engineering / Volume 152 / Number 1 / January 2006 / Pages 48-55

Technical Paper

Implications of Monte Carlo Statistical Errors in Criticality Safety Assessments

Ronald E. Pevey

Nuclear Science and Engineering / Volume 152 / Number 1 / January 2006 / Pages 56-64

Technical Paper

Results and Analysis of the Spherical 237Np Critical Experiment Surrounded by Highly Enriched Uranium Hemispherical Shells

David Loaiza, Rene Sanchez, David Hayes, Charlene Cappiello

Nuclear Science and Engineering / Volume 152 / Number 1 / January 2006 / Pages 65-75

Technical Paper

A Device for Nondestructive Experimental Determination of the Power Distribution in a Nuclear Fuel Assembly

P. Jansson, S. Jacobsson Svärd, A. Håkansson, A. Bäcklin

Nuclear Science and Engineering / Volume 152 / Number 1 / January 2006 / Pages 76-86

Technical Paper

GAMMA Multidimensional Multicomponent Mixture Analysis to Predict Air Ingress Phenomena in an HTGR

Hong Sik Lim, Hee Cheon No

Nuclear Science and Engineering / Volume 152 / Number 1 / January 2006 / Pages 87-97

Technical Paper

Electromagnetic Excitation Rates for Nuclear Isomers in a Hot Dense Plasma

T. C. Luu, J. L. Friar, A. C. Hayes

Nuclear Science and Engineering / Volume 152 / Number 1 / January 2006 / Pages 98-105

Technical Paper

Identification of an Unknown Material in a Radiation Shield Using the Schwinger Inverse Method

Jeffrey A. Favorite, Keith C. Bledsoe

Nuclear Science and Engineering / Volume 152 / Number 1 / January 2006 / Pages 106-117

Technical Note

Improvement of Low-Pressure Subcooled Boiling Models in RELAP/MOD3.2 Code for Predicting Flow Instability

E. M. Dilla, J. Y. Tu, G. H. Yeoh

Nuclear Science and Engineering / Volume 152 / Number 1 / January 2006 / Pages 118-124

Technical Note

Number 2

Experimental Determination of the Decay Constants and Abundances of Delayed Neutrons by Means of Reactor Noise Analysis

Ricardo Diniz, Adimir dos Santos

Nuclear Science and Engineering / Volume 152 / Number 2 / February 2006 / Pages 125-141

Technical Paper / dx.doi.org/10.13182/NSE04-69

Calculating the Effective Delayed Neutron Fraction with Monte Carlo

Robin Klein Meulekamp, Steven C. van der Marck

Nuclear Science and Engineering / Volume 152 / Number 2 / February 2006 / Pages 142-148

Technical Paper / dx.doi.org/10.13182/NSE03-107

Mixed-Hybrid Transport Discretization Using Even and Odd PN Expansions

S. Van Criekingen, E. E. Lewis, R. Beauwens

Nuclear Science and Engineering / Volume 152 / Number 2 / February 2006 / Pages 149-163

Technical Paper / dx.doi.org/10.13182/NSE06-1

A Diffusion Synthetic Acceleration Method for Block Adaptive Mesh Refinement

Robert C. Ward, Randal S. Baker, Jim E. Morel

Nuclear Science and Engineering / Volume 152 / Number 2 / February 2006 / Pages 164-179

Technical Paper

Variational Estimates of Internal Interface Perturbations and a New Variational Functional for Inhomogeneous Transport Problems

Jeffrey A. Favorite

Nuclear Science and Engineering / Volume 152 / Number 2 / February 2006 / Pages 180-196

Technical Paper

Particle Swarm Optimization in Reactor Core Design

Roberto P. Domingos, Roberto Schirru, Cláudio M. N. A. Pereira

Nuclear Science and Engineering / Volume 152 / Number 2 / February 2006 / Pages 197-203

Technical Paper

A Physics Study of a 600-MW(thermal) Gas-Cooled Fast Reactor

Hangbok Choi, Gérald Rimpault, Jean C. Bosq

Nuclear Science and Engineering / Volume 152 / Number 2 / February 2006 / Pages 204-218

Technical Paper

Analysis of a BWR Turbine Trip Experiment by Entire Plant Simulation with Spatial Kinetics

Yoshiro Asahi, Tomoaki Suzudo, Nobuyuki Ishikawa, Toru Nakatsuka

Nuclear Science and Engineering / Volume 152 / Number 2 / February 2006 / Pages 219-235

Technical Paper

Excitation Behavior of Rare Gases in Low-Energy Plasma

Hiroaki Ogawa, Kiyoshi Kiuchi

Nuclear Science and Engineering / Volume 152 / Number 2 / February 2006 / Pages 236-241

Technical Paper

Number 3

Analog Monte Carlo Methods for Simulating Isotopic Inventories in Complex Systems

Paul Wilson, Phiphat Phruksarojanakun

Nuclear Science and Engineering / Volume 152 / Number 3 / March 2006 / Pages 243-255

Technical Paper

Effect of Transverse Neutron Leakage on the Attenuation of the Displacements per Atom in the Reactor Pressure Vessel

John F. Carew, Kai Hu

Nuclear Science and Engineering / Volume 152 / Number 3 / March 2006 / Pages 256-273

Technical Paper

Stochastic Approximation for Monte Carlo Calculation of Steady-State Conditions in Thermal Reactors

Jan Dufek, Waclaw Gudowski

Nuclear Science and Engineering / Volume 152 / Number 3 / March 2006 / Pages 274-283

Technical Paper / dx.doi.org/10.13182/NSE06-2

Thermal Neutron Diffusion in an Array of Plates

B. D. Ganapol

Nuclear Science and Engineering / Volume 152 / Number 3 / March 2006 / Pages 284-291

Technical Paper

Analysis of Single Rod Drop Transient in BWR Considering Detailed Intrabundle Void Distribution

Akitoshi Hotta, Hiroshi Shirai, Shinya Mizokami

Nuclear Science and Engineering / Volume 152 / Number 3 / March 2006 / Pages 292-305

Technical Paper

Use of 240Pu Waste as a Burnable Absorber in Light Water Reactors

Edward P. Naessens, Jr., Kenneth S. Allen, Brian E. Moretti

Nuclear Science and Engineering / Volume 152 / Number 3 / March 2006 / Pages 306-313

Technical Paper

Measurement of 16N Gamma Rays with Argon-Filled Three-Electrode Ionization Chamber as Reactor Power Level Indicator

Muhammad Munir, Nasir Ahmad

Nuclear Science and Engineering / Volume 152 / Number 3 / March 2006 / Pages 314-319

Technical Paper

Determination of Intermediate Energy Neutron Cross Sections Using the Ramsauer Model

M. Azam, R. S. Gowda, S. Ganesan

Nuclear Science and Engineering / Volume 152 / Number 3 / March 2006 / Pages 320-324

Technical Paper

Calculation and Evaluation of Neutron-Induced Reactions on 58Ni Below 150 MeV

Xiaolong Huang

Nuclear Science and Engineering / Volume 152 / Number 3 / March 2006 / Pages 325-333

Technical Note

A Rule for Determining Fissile Isotopes

Yigal Ronen

Nuclear Science and Engineering / Volume 152 / Number 3 / March 2006 / Pages 334-335

Technical Note

 
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