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Volume 136

Number 1 | Number 2 | Number 3

Number 1

The Screened Rutherford Pencil Beam Problem with Heterogeneities

G. C. Pomraning

Nuclear Science and Engineering / Volume 136 / Number 1 / September 2000 / Pages 1-14

Technical Paper

Higher-Order Boundary Condition Perturbation Theory for the Diffusion Approximation

Michael Scott McKinley, Farzad Rahnema

Nuclear Science and Engineering / Volume 136 / Number 1 / September 2000 / Pages 15-33

Technical Paper

Some Aspects of Neutron Transport in Spatially Random Media

M. M. R. Williams

Nuclear Science and Engineering / Volume 136 / Number 1 / September 2000 / Pages 34-58

Technical Paper

Adjoint Sensitivity Analysis of the RELAP5/MOD3.2 Two-Fluid Thermal-Hydraulic Code System - I: Theory

D. G. Cacuci, M. Ionescu-Bujor

Nuclear Science and Engineering / Volume 136 / Number 1 / September 2000 / Pages 59-84

Technical Paper

Adjoint Sensitivity Analysis of the RELAP5/MOD3.2 Two-Fluid Thermal-Hydraulic Code System - II: Applications

M. Ionescu-Bujor, D. G. Cacuci

Nuclear Science and Engineering / Volume 136 / Number 1 / September 2000 / Pages 85-121

Technical Paper

A Synthetic Acceleration for a Two-Dimensional Characteristic Method in Unstructured Meshes

Richard Sanchez, Abdelhuahed Chetaine

Nuclear Science and Engineering / Volume 136 / Number 1 / September 2000 / Pages 122-139

Technical Paper

The Transport of Neutral Hydrogen Atoms in a Hydrogen Plasma

R. D. M. Garcia, C. E. Siewert

Nuclear Science and Engineering / Volume 136 / Number 1 / September 2000 / Pages 140-149

Technical Paper

Number 2

Development of Nonfertile and Evolutionary Mixed-Oxide Nuclear Fuels for Use in Existing Water Reactors

Stacey Eaton, Carl Beard, Kevin Ramsey, John Buksa, Ken Chidester

Nuclear Science and Engineering / Volume 136 / Number 2 / October 2000 / Pages 151-177

Technical Paper

Split-Cell, Linear Characteristic Transport Method for Unstructured Tetrahedral Meshes

Kirk A. Mathews, Rodney L. Miller, Charles R. Brennan

Nuclear Science and Engineering / Volume 136 / Number 2 / October 2000 / Pages 178-201

Technical Paper

Acceleration of Multidimensional Discrete Ordinates Methods Via Adjacent-Cell Preconditioners

Y. Y. Azmy

Nuclear Science and Engineering / Volume 136 / Number 2 / October 2000 / Pages 202-226

Technical Paper

Load-Following Voltage Controller Design for a Static Space Nuclear Power System

Alexander G. Parlos, Fetiye O. Onbasioglu, John D. Metzger

Nuclear Science and Engineering / Volume 136 / Number 2 / October 2000 / Pages 227-246

Technical Paper

Application of Temperature Parallel Simulated Annealing to Loading Pattern Optimizations of Pressurized Water Reactors

Akio Yamamoto, Hiroshi Hashimoto

Nuclear Science and Engineering / Volume 136 / Number 2 / October 2000 / Pages 247-257

Technical Paper

Cross-Section Measurement for the 17O(n, p)17N Reaction by 14-MeV Neutrons

Y. Kasugai, Y. Ikeda, H. Sakane

Nuclear Science and Engineering / Volume 136 / Number 2 / October 2000 / Pages 258-264

Technical Paper

Calculations for the Excitation Functions of Reactions Induced in 63Cu by Neutrons in the 1- to 20-MeV Energy Range

K. Gul

Nuclear Science and Engineering / Volume 136 / Number 2 / October 2000 / Pages 265-271

Technical Paper

Definition of Subcriticality Using the Importance Function for the Production of Fission Neutrons

Keisuke Kobayashi, Kenji Nishihara

Nuclear Science and Engineering / Volume 136 / Number 2 / October 2000 / Pages 272-281

Technical Paper

Uniform Gauss-Weight Quadratures for Discrete Ordinate Transport Calculations

John F. Carew, Kai Hu, Gabriel Zamonsky

Nuclear Science and Engineering / Volume 136 / Number 2 / October 2000 / Pages 282-293

Technical Paper

Hybrid Skyshine Calculations for Complex Neutron and Gamma-Ray Sources

J. Kenneth Shultis

Nuclear Science and Engineering / Volume 136 / Number 2 / October 2000 / Pages 294-304

Technical Note

A Quantitative Analysis of the Feynman- and Rossi-Alpha Formulas with Multiple Emission Sources

Z. F. Kuang, I. Pázsit

Nuclear Science and Engineering / Volume 136 / Number 2 / October 2000 / Pages 305-319

Technical Note

Number 3

Measurement and Analysis of Capture Reaction Rate of 237Np in Various Thermal Neutron Fields by Critical Assembly and Heavy Water Thermal Neutron Facility of Kyoto University

Tomohiko Iwasaki, Toshimitu Horiuchi, Daisuke Fujiwara, Hironobu Unesaki, Seiji Shiroya, Masatoshi Hayashi, Hiroshi Nakamura, Takanori Kitada, Nobuo Shinohara

Nuclear Science and Engineering / Volume 136 / Number 3 / November 2000 / Pages 321-339

Technical Paper

Neutron Cross-Section Evaluations for 238U up to 150 MeV

A. V. Ignatyuk, V. P. Lunev, Yu. N. Shubin, E. V. Gai, N. N. Titarenko, A. Ventura, W. Gudowski

Nuclear Science and Engineering / Volume 136 / Number 3 / November 2000 / Pages 340-356

Technical Paper

Photofission Cross Sections for 237Np in the Energy Interval from 5.27 to 10.83 MeV

L. P. Geraldo, R. Semmler, O. L. Gonçalez, J. Mesa, J. D. T. Arruda-Neto, F. Garcia, O. Rodriguez

Nuclear Science and Engineering / Volume 136 / Number 3 / November 2000 / Pages 357-362

Technical Paper

Numerical and Experimental Study of Large Steam-Air Bubbles Injected in a Water Pool

Markus Meier, George Yadigaroglu, Michele Andreani

Nuclear Science and Engineering / Volume 136 / Number 3 / November 2000 / Pages 363-375

Technical Paper

Modeling of Steam-Clad Interactions Under Severe Accident Conditions in Nuclear Power Light Water Reactors

M. A. Shinaishin, M. A. Abolfadl, A. S. Khedr, M. M. Kamel

Nuclear Science and Engineering / Volume 136 / Number 3 / November 2000 / Pages 376-387

Technical Paper

The Third Basis Function Relevant to an Approximate Model of Neutral Particle Transport in Ducts

Roberto D. M. Garcia, Shizuca Ono, Wilson J. Vieira

Nuclear Science and Engineering / Volume 136 / Number 3 / November 2000 / Pages 388-398

Technical Paper / dx.doi.org/10.13182/NSE00-1

Adaptive Importance Sampling with a Rapidly Varying Importance Function

Thomas E. Booth

Nuclear Science and Engineering / Volume 136 / Number 3 / November 2000 / Pages 399-408

Technical Note

Semianalytical Procedures for Obtaining Low-Order Non-Equally-Probable Step-Function Representations in Multigroup Monte Carlo

Li Mao, J. C. Nimal

Nuclear Science and Engineering / Volume 136 / Number 3 / November 2000 / Pages 409-414

Technical Note

Experimental Determination of the 236U(nth, f) Cross Section

Cyriel Wagemans, Olivier Serot, Peter Geltenbort, Oliver Zimmer

Nuclear Science and Engineering / Volume 136 / Number 3 / November 2000 / Pages 415-418

Technical Note

 
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