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Volume 141

Number 1 | Number 2 | Number 3

Number 1

A Block Adaptive Mesh Refinement Algorithm for the Neutral Particle Transport Equation

Randal S. Baker

Nuclear Science and Engineering / Volume 141 / Number 1 / May 2002 / Pages 1-12

Technical Paper

The Effect of Random Geometry on the Criticality of a Multiplying System III: Three Dimensional Systems and Spherical Absorbers

M. M. R. Williams

Nuclear Science and Engineering / Volume 141 / Number 1 / May 2002 / Pages 13-31

Technical Paper

Neutronics Investigations for the Lower Part of a Westinghouse SVEA-96+ Assembly

M. F. Murphy, A. Lüthi, R. Seiler, P. Grimm, O. Joneja, A. Meister, R. van Geemert, F. Jatuff, R. Brogli, R. Jacot-Guillarmod, T. Williams, S. Helmersson, R. Chawla

Nuclear Science and Engineering / Volume 141 / Number 1 / May 2002 / Pages 32-45

Technical Paper

Adjoint and Generalized Adjoint Flux Calculations Using the Collision Probability Technique

T. Courau, G. Marleau

Nuclear Science and Engineering / Volume 141 / Number 1 / May 2002 / Pages 46-54

Technical Paper

Secondary Light Charged Particle Emission from the Interaction of 25- to 65-MeV Neutrons on Silicon

S. Benck, I. Slypen, J.-P. Meulders, V. Corcalciuc

Nuclear Science and Engineering / Volume 141 / Number 1 / May 2002 / Pages 55-65

Technical Paper

Development of Fast-Running Simulation Methodology Using Neural Networks for Load Follow Operation

Seung-Hwan Seong, Heui-Youn Park, Dong-Hoon Kim, Yong-Suk Suh, Seop Hur, In-Soo Koo, Un-Chul Lee, Jin-Wook Jang, Yong-Chul Shin

Nuclear Science and Engineering / Volume 141 / Number 1 / May 2002 / Pages 66-77

Technical Paper

APMN: A Program for Automatically Searching Optimal Optical Potential Parameters in the E 300 MeV Energy Region

Qing-Biao Shen

Nuclear Science and Engineering / Volume 141 / Number 1 / May 2002 / Pages 78-84

Computer Code Abstract

Number 2

Alternative Implementations of the Monte Carlo Power Method

R. N. Blomquist, E. M. Gelbard

Nuclear Science and Engineering / Volume 141 / Number 2 / June 2002 / Pages 85-100

Technical Paper

Intergenerational Correlation in Monte Carlo k-Eigenvalue Calculation

Taro Ueki

Nuclear Science and Engineering / Volume 141 / Number 2 / June 2002 / Pages 101-110

Technical Paper

A Mixed-Oxide Assembly Design for Rapid Disposition of Weapons Plutonium in Pressurized Water Reactors

Gustavo Alonso, Marvin L. Adams

Nuclear Science and Engineering / Volume 141 / Number 2 / June 2002 / Pages 111-128

Technical Paper

Gamma-Ray Spectroscopy Measurements of Decay Heat in Spent Nuclear Fuel

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

Nuclear Science and Engineering / Volume 141 / Number 2 / June 2002 / Pages 129-139

Technical Paper

Measurements of High-Energy Neutrons Penetrated Through Concrete Shields Using Self-TOF, NE213, and Activation Detectors

M. Sasaki, E. Kim, T. Nunomiya, T. Nakamura, N. Nakao, T. Shibata, Y. Uwamino, S. Ito, A. Fukumura

Nuclear Science and Engineering / Volume 141 / Number 2 / June 2002 / Pages 140-153

Technical Paper

Calculation and Analysis of Double-Differential Cross Sections for n + 209Bi Reaction

Yinlu Han, Zhengjun Zhang

Nuclear Science and Engineering / Volume 141 / Number 2 / June 2002 / Pages 154-164

Technical Paper

Experimental Study of Energy Distribution in Double Photon Compton Scattering

R. Dewan, M. B. Saddi, B. S. Sandhu, B. Singh, B. S. Ghumman

Nuclear Science and Engineering / Volume 141 / Number 2 / June 2002 / Pages 165-170

Technical Paper

The 234U(nth,f) Cross Section Revisited

Cyriel Wagemans, Jan Wagemans, Olivier Serot

Nuclear Science and Engineering / Volume 141 / Number 2 / June 2002 / Pages 171-173

Technical Note

Number 3

Neutron Spectrum Effects on Burnup, Reactivity, and Isotopics in UO2/H2O Lattices

Zhiwen Xu, Michael J. Driscoll, Mujid S. Kazimi

Nuclear Science and Engineering / Volume 141 / Number 3 / July 2002 / Pages 175-189

Technical Paper

Object-Oriented Three-Dimensional Fine-Mesh Transport Calculation on Parallel/Distributed Environments for Advanced Reactor Core Analyses

Masahiro Tatsumi, Akio Yamamoto

Nuclear Science and Engineering / Volume 141 / Number 3 / July 2002 / Pages 190-217

Technical Paper

A Variational Nodal Expansion Method for the Solution of Multigroup Neutron Diffusion Equations with Heterogeneous Nodes

Makoto Tsuiki, Sverre Hval

Nuclear Science and Engineering / Volume 141 / Number 3 / July 2002 / Pages 218-235

Technical Paper

Fully Consistent Diffusion Synthetic Acceleration of Linear Discontinuous SN Transport Discretizations on Unstructured Tetrahedral Meshes

James S. Warsa, Todd A. Wareing, Jim E. Morel

Nuclear Science and Engineering / Volume 141 / Number 3 / July 2002 / Pages 236-251

Technical Paper

The Evaluation of Radiation Transport Forward-Adjoint Flux Integrals Using Monte Carlo Correlated Coupling Methods

S. N. Cramer

Nuclear Science and Engineering / Volume 141 / Number 3 / July 2002 / Pages 252-271

Technical Paper

Cluster-Event Biasing in Monte Carlo Applications to Systems Reliability

Michael Khazen, Arie Dubi

Nuclear Science and Engineering / Volume 141 / Number 3 / July 2002 / Pages 272-287

Technical Paper

 
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