ANS / Publications / Journals / Nuclear Science and Engineering

Development of Methods for Calculation of Deuteron-Lithium and Neutron-Lithium Cross Sections for Energies up to 50 MeV

A. Yu. Konobeyev, Yu. A. Korovin, P. E. Pereslavtsev, Ulrich Fischer, Ulrich von Möllendorff

Nuclear Science and Engineering / Volume 139 / Number 1 / September 2001 / Pages 1-23

Technical Paper / dx.doi.org/10.13182/NSE00-31

Threshold Reaction Cross Sections of Nickel Isotopes, Averaged Over a ²³⁵U Fission Neutron Spectrum

M. A. Arribére, S. Ribeiro Guevara, P. M. Suárez, A. J. Kestelman

Nuclear Science and Engineering / Volume 139 / Number 1 / September 2001 / Pages 24-32

Technical Paper / dx.doi.org/10.13182/NSE01-A2219

Nonnegative Anisotropic Group Cross Sections: A Hybrid Monte Carlo-Discrete Elements-Discrete Ordinates Approach

J. Mark DelGrande, Kirk A. Mathews

Nuclear Science and Engineering / Volume 139 / Number 1 / September 2001 / Pages 33-46

Technical Paper / dx.doi.org/10.13182/NSE00-69

A Transport Condensed History Algorithm for Electron Monte Carlo Simulations

Danny R. Tolar, Jr., Edward W. Larsen

Nuclear Science and Engineering / Volume 139 / Number 1 / September 2001 / Pages 47-65

Technical Paper / dx.doi.org/10.13182/NSE01-A2221

Neutron Transport in Spatially Random Media: Eigenvalue Problems

M. M. R. Williams, Edward W. Larsen

Nuclear Science and Engineering / Volume 139 / Number 1 / September 2001 / Pages 66-77

Technical Paper / dx.doi.org/10.13182/NSE01-A2222

A Spatial Kinetics Method Ensuring Neutronic Balance with Thermal-Hydraulic Feedback and Its Application to a Main Steam Line Break

Yoshiro Asahi, Keisuke Okumura, Yasuo Ose

Nuclear Science and Engineering / Volume 139 / Number 1 / September 2001 / Pages 78-95

Technical Paper / dx.doi.org/10.13182/NSE01-A2223

Genetic Algorithms for Estimating Effective Parameters in a Lumped Reactor Model for Reactivity Predictions

Marzio Marseguerra, Enrico Zio

Nuclear Science and Engineering / Volume 139 / Number 1 / September 2001 / Pages 96-104

Technical Paper / dx.doi.org/10.13182/NSE01-A2224

An Alternate Formulation of the Nodal Expansion Method

Keqiang Ruan, Xiaogang Xue, Xuedong Fu

Nuclear Science and Engineering / Volume 139 / Number 1 / September 2001 / Pages 105-110

Technical Note / dx.doi.org/10.13182/NSE01-A2225

High-Resolution Transmission Measurements of ²³³U Using a Cooled Sample at the Temperature T = 11 K

K. H. Guber, R. R. Spencer, L. C. Leal, P. E. Koehler, J. A. Harvey, R. O. Sayer, H. Derrien, T. E. Valentine, D. E. Pierce, V. M. Cauley, T. A. Lewis

Nuclear Science and Engineering / Volume 139 / Number 2 / October 2001 / Pages 111-117

Technical Paper / dx.doi.org/10.13182/NSE01-A2226

Conceptual Design of a Fluidized Bed Nuclear Reactor

J. L. Kloosterman, V. V. Golovko, H. van Dam, T. H. J. J. van der Hagen

Nuclear Science and Engineering / Volume 139 / Number 2 / October 2001 / Pages 118-137

Technical Paper / dx.doi.org/10.13182/NSE01-A2227

Conceptual Neutronic Design of a Lead-Bismuth-Cooled Actinide Burning Reactor

Pavel Hejzlar, Michael J. Driscoll, Mujid S. Kazimi

Nuclear Science and Engineering / Volume 139 / Number 2 / October 2001 / Pages 138-155

Technical Paper / dx.doi.org/10.13182/NSE01-A2228

The Analytic Function Expansion Nodal Method Refined with Transverse Gradient Basis Functions and Interface Flux Moments

Sweng Woong Woo, Nam Zin Cho, Jae Man Noh

Nuclear Science and Engineering / Volume 139 / Number 2 / October 2001 / Pages 156-173

Technical Paper / dx.doi.org/10.13182/NSE01-A2229

Numerical Optimization of Computing Algorithms of the Variational Nodal Method Based on Transformation of Variables

W. S. Yang, G. Palmiotti, E. E. Lewis

Nuclear Science and Engineering / Volume 139 / Number 2 / October 2001 / Pages 174-185

Technical Paper / dx.doi.org/10.13182/NSE01-A2230

Analytic Radiation Transport Systems and Monte Carlo Benchmarks

S. N. Cramer

Nuclear Science and Engineering / Volume 139 / Number 2 / October 2001 / Pages 186-208

Technical Paper / dx.doi.org/10.13182/NSE01-A2231

Measurement of Neutron and Gamma-Ray Absorbed Doses Under Criticality Accident Conditions at TRACY Using Tissue-Equivalent Dosimeters

Hiroki Sono, Hiroshi Yanagisawa, Akio Ohno, Takuji Kojima, Noboru Soramasu

Nuclear Science and Engineering / Volume 139 / Number 2 / October 2001 / Pages 209-220

Technical Paper / dx.doi.org/10.13182/NSE01-A2232

An Improved Model for Assessing the Effectiveness of Hydrogen Water Chemistry in Boiling Water Reactors

Tsung-Kuang Yeh, Fang Chu

Nuclear Science and Engineering / Volume 139 / Number 2 / October 2001 / Pages 221-233

Technical Paper / dx.doi.org/10.13182/NSE00-77

FORMOSA-P Three-Dimensional/Two-Dimensional Geometry Collapse Methodology

Paul M. Keller, Paul J. Turinsky

Nuclear Science and Engineering / Volume 139 / Number 3 / November 2001 / Pages 235-247

Technical Paper / dx.doi.org/10.13182/NSE01-A2234

A Time-Dependent, Three-Dimensional Neutron Transport Methodology

Sedat Goluoglu, H. L. Dodds

Nuclear Science and Engineering / Volume 139 / Number 3 / November 2001 / Pages 248-261

Technical Paper / dx.doi.org/10.13182/NSE01-A2235

LWR-PROTEUS Verification of Reaction Rate Distributions in Modern 10 × 10 Boiling Water Reactor Fuel

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

Nuclear Science and Engineering / Volume 139 / Number 3 / November 2001 / Pages 262-272

Technical Paper / dx.doi.org/10.13182/NSE01-A2236

Measurement of Neutron-Induced Fission Cross Sections of ²²⁹Th and ²³¹Pa Using Linac-Driven Lead Slowing-Down Spectrometer

Katsuhei Kobayashi, Shuji Yamamoto, Samyol Lee, Hyun-Je Cho, Hajimu Yamana, Hirotake Moriyama, Yoshiaki Fujita, Toshiaki Mitsugashira

Nuclear Science and Engineering / Volume 139 / Number 3 / November 2001 / Pages 273-281

Technical Paper / dx.doi.org/10.13182/NSE01-A2237

Neutron Radiative Capture Cross Section of ²³²Th in the Energy Range from 0.06 to 2 MeV

D. Karamanis, M. Petit, S. Andriamonje, G. Barreau, M. Bercion, A. Billebaud, B. Blank, S. Czajkowski, R. Del Moral, J. Giovinazzo, V. Lacoste, C. Marchand, L. Perrot, M. Pravikoff, J. C. Thomas

Nuclear Science and Engineering / Volume 139 / Number 3 / November 2001 / Pages 282-292

Technical Paper / dx.doi.org/10.13182/NSE01-A2238

An Efficient Formulation of the Modified Nodal Integral Method and Application to the Two-Dimensional Burgers' Equation

Bradley L. Wescott, Rizwan-uddin

Nuclear Science and Engineering / Volume 139 / Number 3 / November 2001 / Pages 293-305

Technical Paper / dx.doi.org/10.13182/NSE01-A2239

CANDLE: The New Burnup Strategy

Hiroshi Sekimoto, Kouichi Ryu, Yoshikane Yoshimura

Nuclear Science and Engineering / Volume 139 / Number 3 / November 2001 / Pages 306-317

Technical Note / dx.doi.org/10.13182/NSE01-01

Study of Properties of the Neutron Production Target Induced from 150-MeV Incident Proton Energy for the China ADS

S. Fan, Y. Ye, Z. Zhao, H. Yu, Z. Luo

Nuclear Science and Engineering / Volume 139 / Number 3 / November 2001 / Pages 318-326

Technical Note / dx.doi.org/10.13182/NSE01-A2241