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Volume 141

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

Randal S. Baker

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

May 2002

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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 / Pages 13-31

May 2002

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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 / Pages 32-45

May 2002

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Adjoint and Generalized Adjoint Flux Calculations Using the Collision Probability Technique

T. Courau, G. Marleau

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

May 2002

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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 / Pages 55-65

May 2002

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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 / Pages 66-77

May 2002

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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 / Pages 78-84

May 2002

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Alternative Implementations of the Monte Carlo Power Method

R. N. Blomquist, E. M. Gelbard

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

June 2002

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Intergenerational Correlation in Monte Carlo k-Eigenvalue Calculation

Taro Ueki

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

June 2002

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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 / Pages 111-128

June 2002

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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 / Pages 129-139

June 2002

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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 / Pages 140-153

June 2002

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

Yinlu Han, Zhengjun Zhang

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

June 2002

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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 / Pages 165-170

June 2002

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The 234U(nth,f) Cross Section Revisited

Cyriel Wagemans, Jan Wagemans, Olivier Serot

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

June 2002

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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 / Pages 175-189

July 2002

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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 / Pages 190-217

July 2002

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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 / Pages 218-235

July 2002

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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 / Pages 236-251

July 2002

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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 / Pages 252-271

July 2002

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