ANS / Publications / Journals / Nuclear Science and Engineering

Experimental Determination of the Ratio of ²³⁸U Capture to ²³⁵U Fission in LEU-HTR Pebble-Bed Configurations

O. Köberl, R. Seiler, R. Chawla

Nuclear Science and Engineering / Volume 146 / Number 1 / January 2004 / Pages 1-12

Technical Paper / dx.doi.org/10.13182/NSE04-A2391

Impact of Nuclear Data Uncertainties on Transmutation of Actinides in Accelerator-Driven Assemblies

G. Aliberti, G. Palmiotti, M. Salvatores, C. G. Stenberg

Nuclear Science and Engineering / Volume 146 / Number 1 / January 2004 / Pages 13-50

Technical Paper / dx.doi.org/10.13182/NSE02-94

Using the Schwinger Variational Functional for the Solution of Inverse Transport Problems

Jeffrey A. Favorite

Nuclear Science and Engineering / Volume 146 / Number 1 / January 2004 / Pages 51-70

Technical Paper / dx.doi.org/10.13182/NSE02-96

Calculating Nuclear Power Plant Vulnerability Using Integrated Geometry and Event/Fault-Tree Models

Douglas E. Peplow, C. David Sulfredge, Robert L. Sanders, Robert H. Morris, Todd A. Hann

Nuclear Science and Engineering / Volume 146 / Number 1 / January 2004 / Pages 71-87

Technical Paper / dx.doi.org/10.13182/NSE04-A2394

An Order Coding Genetic Algorithm to Optimize Fuel Reloads in a Nuclear Boiling Water Reactor

Juan José Ortiz, Ignacio Requena

Nuclear Science and Engineering / Volume 146 / Number 1 / January 2004 / Pages 88-98

Technical Paper / dx.doi.org/10.13182/NSE04-A2395

Slowing-Down Dynamics of Fast Particles in Plasmas via the Fokker-Planck Equation

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

Nuclear Science and Engineering / Volume 146 / Number 1 / January 2004 / Pages 99-105

Technical Paper / dx.doi.org/10.13182/NSE04-A2396

Calculation and Analysis of n + ^{112,114-120,122,124,nat}Sn Reactions

Yinlu Han

Nuclear Science and Engineering / Volume 146 / Number 1 / January 2004 / Pages 106-119

Technical Paper / dx.doi.org/10.13182/NSE04-A2397

Variational Variance Reduction for Monte Carlo Eigenvalue and Eigenfunction Problems

Jeffery D. Densmore, Edward W. Larsen

Nuclear Science and Engineering / Volume 146 / Number 2 / February 2004 / Pages 121-140

Technical Paper / dx.doi.org/10.13182/NSE04-A2398

An Integral Form of the Variational Nodal Method

M. A. Smith, G. Palmiotti, E. E. Lewis, N. Tsoulfanidis

Nuclear Science and Engineering / Volume 146 / Number 2 / February 2004 / Pages 141-151

Technical Paper / dx.doi.org/10.13182/NSE146-141

Conditions for a Minimum Critical Mass in a Nuclear Reactor and Considerations on Goertzel's Theorem in Transport Theory

M. M. R. Williams

Nuclear Science and Engineering / Volume 146 / Number 2 / February 2004 / Pages 152-175

Technical Paper / dx.doi.org/10.13182/NSE04-A2400

A Hybrid Nodal Diffusion/SP₃ Method Using One-Node Coarse-Mesh Finite Difference Formulation

Chang-Ho Lee, Thomas J. Downar

Nuclear Science and Engineering / Volume 146 / Number 2 / February 2004 / Pages 176-187

Technical Paper / dx.doi.org/10.13182/NSE04-A2401

Benchmarking MCNP and WIMS/RFSP Against Measurement Data - I: Deuterium Critical Assembly

Hangbok Choi, Gyuhong Roh

Nuclear Science and Engineering / Volume 146 / Number 2 / February 2004 / Pages 188-199

Technical Paper / dx.doi.org/10.13182/NSE04-A2402

Measurement of Differential Thick-Target Neutron Yields of C, Al, Ta, W(p,xn) Reactions for 50-MeV Protons

T. Aoki, M. Baba, S. Yonai, N. Kawata, M. Hagiwara, T. Miura, T. Nakamura

Nuclear Science and Engineering / Volume 146 / Number 2 / February 2004 / Pages 200-208

Technical Paper / dx.doi.org/10.13182/NSE04-A2403

Neutron Capture Cross-Section Measurement of ⁹⁹Tc by Linac Time-of-Flight Method and the Resonance Analysis

Katsuhei Kobayashi, Samyol Lee, Shuji Yamamoto, Toshihiko Kawano

Nuclear Science and Engineering / Volume 146 / Number 2 / February 2004 / Pages 209-220

Technical Paper / dx.doi.org/10.13182/NSE04-A2404

Calculation of the Complete Sets of Nuclear Data for n + ^92,94,96Mo below 20 MeV

Chonghai Cai

Nuclear Science and Engineering / Volume 146 / Number 2 / February 2004 / Pages 221-236

Technical Paper / dx.doi.org/10.13182/NSE04-A2405

Investigation of the Outgoing Tritons Angular Distribution in the ⁹Be(n,t₁)⁷Li* Reaction at 14.9 MeV by the Line Shape Analysis of the 0.4776-MeV Gamma Transition

Hongyu Zhou, Ping Wang, Hai Song, Fucai Wu, Fuguo Deng, Ming Hua, Yiming Yan, A. A. Pasternak

Nuclear Science and Engineering / Volume 146 / Number 2 / February 2004 / Pages 237-244

Technical Paper / dx.doi.org/10.13182/NSE04-A2406

Accurate Relations Between the Neutron Current Densities and the Neutron Fluxes

Yigal Ronen

Nuclear Science and Engineering / Volume 146 / Number 2 / February 2004 / Pages 245-247

Technical Note / dx.doi.org/10.13182/NSE04-A2407

BOT3P - Bologna Transport Analysis Pre-Post-Processors Version 3.0

Roberto Orsi

Nuclear Science and Engineering / Volume 146 / Number 2 / February 2004 / Pages 248-255

Technical Note / dx.doi.org/10.13182/NSE04-A2408

Development of One-Group and Two-Group Interfacial Area Transport Equation

M. Ishii, S. Kim

Nuclear Science and Engineering / Volume 146 / Number 3 / March 2004 / Pages 257-273

Technical Paper / dx.doi.org/10.13182/NSE01-69

Adequacy of Power-to-Mass Scaling in Simulating PWR Incident Transient for Reduced-Height, Reduced-Pressure and Full-Height, Full-Pressure Integral System Test Facilities

Tay-Jian Liu, Chien-Hsiung Lee

Nuclear Science and Engineering / Volume 146 / Number 3 / March 2004 / Pages 274-290

Technical Paper / dx.doi.org/10.13182/NSE04-A2410

Long-Lived Fission Product Transmutation Studies

W. S. Yang, Y. Kim, R. N. Hill, T. A. Taiwo, H. S. Khalil

Nuclear Science and Engineering / Volume 146 / Number 3 / March 2004 / Pages 291-318

Technical Paper / dx.doi.org/10.13182/NSE04-A2411

A Nodal and Finite Difference Hybrid Method for Pin-by-Pin Heterogeneous Three-Dimensional Light Water Reactor Diffusion Calculations

Deokjung Lee, Thomas J. Downar, Yonghee Kim

Nuclear Science and Engineering / Volume 146 / Number 3 / March 2004 / Pages 319-339

Technical Paper / dx.doi.org/10.13182/NSE04-A2412

Sensitivity- and Uncertainty-Based Criticality Safety Validation Techniques

B. L. Broadhead, B. T. Rearden, C. M. Hopper, J. J. Wagschal, C. V. Parks

Nuclear Science and Engineering / Volume 146 / Number 3 / March 2004 / Pages 340-366

Technical Paper / dx.doi.org/10.13182/NSE03-2

Perturbation Theory Eigenvalue Sensitivity Analysis with Monte Carlo Techniques

B. T. Rearden

Nuclear Science and Engineering / Volume 146 / Number 3 / March 2004 / Pages 367-382

Technical Paper / dx.doi.org/10.13182/NSE03-03