ANS / Publications / Journals / Nuclear Science and Engineering

Neutronic Analysis of Critical Configurations in Geologic Repositories - II: Highly Enriched Uranium

J. Vujic, E. Greenspan

Nuclear Science and Engineering / Volume 129 / Number 1 / May 1998 / Pages 1-14

Technical Paper / dx.doi.org/10.13182/NSE98-A1960

Dynamic Analysis of an Accelerator-Driven Fluid-Fueled Subcritical Radioactive Waste Burning System

M. L. Woosley, Jr., R. A. Rydin

Nuclear Science and Engineering / Volume 129 / Number 1 / May 1998 / Pages 15-50

Technical Paper / dx.doi.org/10.13182/NSE98-A1961

One-Dimensional Beam Transport - Revisited

D. Anderson, T. Fülöp, M. Lisak, F. Wising

Nuclear Science and Engineering / Volume 129 / Number 1 / May 1998 / Pages 51-60

Technical Paper / dx.doi.org/10.13182/NSE98-A1962

Pressurized Water Reactor Loading Pattern Design Using the Simple Tabu Search

Chaung Lin, Jiing-Iuan Yang, Kuan-Jan Lin, Zheng-De Wang

Nuclear Science and Engineering / Volume 129 / Number 1 / May 1998 / Pages 61-71

Technical Paper / dx.doi.org/10.13182/NSE98-A1963

Entrainment Rate of Droplets in the Ripple-Annular Regime for Small Vertical Ducts

M. A. Lopez de Bertodano, A. Assad, Stephen Beus

Nuclear Science and Engineering / Volume 129 / Number 1 / May 1998 / Pages 72-80

Technical Paper / dx.doi.org/10.13182/NSE98-A1964

Measurements of Tritium and ¹⁴C Production Cross Sections for 14.7-MeV Neutrons on ¹⁷O and ¹⁸O

Yuriy M. Verzilov, Yujiro Ikeda, Fujio Maekawa, Yukio Oyama, Donald L. Smith

Nuclear Science and Engineering / Volume 129 / Number 1 / May 1998 / Pages 81-87

Technical Note / dx.doi.org/10.13182/NSE98-A1965

A Hierarchical Domain Decomposition Boundary Element Method Applied to the Multiregion Problems of Neutron Diffusion Equations

M. Dhandhang Purwadi, M. Tsuji, M. Narita, M. Itagaki

Nuclear Science and Engineering / Volume 129 / Number 1 / May 1998 / Pages 88-96

Technical Note / dx.doi.org/10.13182/NSE98-A1966

Pressurized Water Reactor Core Maneuvering Utilizing Optimal Control Theory

Jianqing Ye, Paul J. Turinsky

Nuclear Science and Engineering / Volume 129 / Number 2 / June 1998 / Pages 97-123

Technical Paper / dx.doi.org/10.13182/NSE98-A1967

A Time-Dependent Collision Probability Method for One-Dimensional Space-Time Nuclear Reactor Kinetics

Paul M. Keller, John C. Lee

Nuclear Science and Engineering / Volume 129 / Number 2 / June 1998 / Pages 124-148

Technical Paper / dx.doi.org/10.13182/NSE98-A1968

Neutron-Induced Fission Cross-Section Ratios for ²³⁹Pu, ²⁴⁰Pu, ²⁴²Pu, and ²⁴⁴Pu Relative to ²³⁵U from 0.5 to 400 MeV

Parrish Staples, Kevin Morley

Nuclear Science and Engineering / Volume 129 / Number 2 / June 1998 / Pages 149-163

Technical Paper / dx.doi.org/10.13182/NSE98-A1969

Excitation Functions of Some (n, p) and (n, ) Reactions from Threshold to 16 MeV

R. Dóczi, V. Semkova, A. Fenyvesi, N. Yamamuro, Cs. M. Buczkó, J. Csikai

Nuclear Science and Engineering / Volume 129 / Number 2 / June 1998 / Pages 164-174

Technical Paper / dx.doi.org/10.13182/NSE98-A1970

A Measurement of the ²⁷Al(d, n) Spectrum for Use in Neutron Detector Calibration

T. N. Massey, S. Al-Quraishi, C. E. Brient, J. F. Guillemette, S. M. Grimes, D. Jacobs, J. E. O'Donnell, J. Oldendick, R. Wheeler

Nuclear Science and Engineering / Volume 129 / Number 2 / June 1998 / Pages 175-179

Technical Paper / dx.doi.org/10.13182/NSE98-A1971

Spallation Neutron Production Measurements

M. S. Zucker, N. Tsoupas, P. E. Vanier, U. von Wimmersperg, S. F. Mughabghab, E. Schmidt

Nuclear Science and Engineering / Volume 129 / Number 2 / June 1998 / Pages 180-186

Technical Paper / dx.doi.org/10.13182/NSE129-180

Criticality Characteristics of Mixtures of Plutonium, Silicon Dioxide, Nevada Tuff, and Water

Rene Sanchez, William Myers, David Hayes, Robert Kimpland, Peter Jaegers, Richard Paternoster, Stephen Rojas, Richard Anderson, William Stratton

Nuclear Science and Engineering / Volume 129 / Number 2 / June 1998 / Pages 187-194

Technical Paper / dx.doi.org/10.13182/NSE98-A1973

Boron-10 Depletion in Pressurized Water Reactors

G. John, E. Neymotin

Nuclear Science and Engineering / Volume 129 / Number 2 / June 1998 / Pages 195-198

Technical Paper / dx.doi.org/10.13182/NSE98-A1974

Simultaneous Monte Carlo Zero-Variance Estimates of Several Correlated Means

Thomas E. Booth

Nuclear Science and Engineering / Volume 129 / Number 2 / June 1998 / Pages 199-202

Technical Paper / dx.doi.org/10.13182/NSE98-A1975

Experimental Analysis of Coherent Neutron Flux Fluctuations Observed in a Pressurized Water Reactor

Tomoaki Suzudo, Erdinç Türkcan, Hans Verhoef

Nuclear Science and Engineering / Volume 129 / Number 2 / June 1998 / Pages 203-208

Technical Note / dx.doi.org/10.13182/NSE98-A1976

Measurements of Neutron Spallation Cross Sections of ¹²C and ²⁰⁹Bi in the 20- to 150-MeV Energy Range

E. Kim, T. Nakamura, A. Konno, Y. Uwamino, N. Nakanishi, M. Imamura, N. Nakao, S. Shibata, S. Tanaka

Nuclear Science and Engineering / Volume 129 / Number 3 / July 1998 / Pages 209-223

Technical Paper / dx.doi.org/10.13182/NSE98-A1977

Analysis of the Transport of Radionuclide Chains in a Stochastic Geological Medium by a Biased Monte Carlo Simulation

O. F. Smidts, J. Devooght

Nuclear Science and Engineering / Volume 129 / Number 3 / July 1998 / Pages 224-245

Technical Paper / dx.doi.org/10.13182/NSE98-A1978

Numerical and Experimental Study of an Accidental Depressurization in an Enclosure Containing High-Pressure Liquid

P. Drai, B. Porterie, P. Monier, J. C. Loraud

Nuclear Science and Engineering / Volume 129 / Number 3 / July 1998 / Pages 246-260

Technical Paper / dx.doi.org/10.13182/NSE98-A1979

Application of Modal Neutron Kinetics to Boiling Water Reactor Oscillation Problems

Yousef M. Farawila

Nuclear Science and Engineering / Volume 129 / Number 3 / July 1998 / Pages 261-272

Technical Paper / dx.doi.org/10.13182/NSE98-A1980

Role of Neutron Sources, Xenon, and Decay Heat Dynamics in Autonomous Reactor Shutdown and Recriticality

H. van Dam

Nuclear Science and Engineering / Volume 129 / Number 3 / July 1998 / Pages 273-282

Technical Paper / dx.doi.org/10.13182/NSE98-A1981

Adaptive Control for Axial Power Distribution in Nuclear Reactors

Man Gyun Na, Belle R. Upadhyaya, Jung In Choi

Nuclear Science and Engineering / Volume 129 / Number 3 / July 1998 / Pages 283-293

Technical Paper / dx.doi.org/10.13182/NSE98-A1982

Mechanistic Modeling of Critical Flow of Initially Subcooled Liquid Containing Dissolved Noncondensables Through Cracks and Slits Based on the Homogeneous Equilibrium Mixture Method

H. Geng, S. M. Ghiaasiaan

Nuclear Science and Engineering / Volume 129 / Number 3 / July 1998 / Pages 294-304

Technical Paper / dx.doi.org/10.13182/NSE98-A1983

Implicit Coupling of Fluid-Dynamic Systems: Application to Multidimensional Countercurrent Two-Phase Flow of Water and Steam

Udo Graf

Nuclear Science and Engineering / Volume 129 / Number 3 / July 1998 / Pages 305-310

Technical Paper / dx.doi.org/10.13182/NSE98-A1984

Performance of Scientific Computing Platforms with MCNP4B

H. E. McLaughlin, J. S. Hendricks

Nuclear Science and Engineering / Volume 129 / Number 3 / July 1998 / Pages 311-319

Technical Paper / dx.doi.org/10.13182/NSE98-A1985