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Volume 142

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Number 1

Neutron Capture and Transmission Measurements and Resonance Parameter Analysis of Samarium

G. Leinweber, J. A. Burke, H. D. Knox, N. J. Drindak, D. W. Mesh, W. T. Haines, R. V. Ballad, R. C. Block, R. E. Slovacek, C. J. Werner, M. J. Trbovich, D. P. Barry, T. Sato

Nuclear Science and Engineering / Volume 142 / Number 1 / September 2002 / Pages 1-21

Technical Paper / dx.doi.org/10.13182/NSE02-A2283

Radiological Hazard of Spallation Products in Accelerator-Driven System

M. Saito, A. Stankovskii, V. Artisyuk, Yu. Korovin, A. Shmelev, Yu. Titarenko

Nuclear Science and Engineering / Volume 142 / Number 1 / September 2002 / Pages 22-36

Technical Paper / dx.doi.org/10.13182/NSE02-A2284

Organization for Economic Cooperation and Development/Nuclear Energy Agency International Benchmark on the VENUS-2 MOX Core Measurements

Byung-Chan Na, Enrico Sartori

Nuclear Science and Engineering / Volume 142 / Number 1 / September 2002 / Pages 37-47

Technical Note / dx.doi.org/10.13182/NSE02-A2285

Computational Experience with the Reich-Moore Resolved-Resonance Equations in the AMPX Cross-Section Processing System

M. E. Dunn

Nuclear Science and Engineering / Volume 142 / Number 1 / September 2002 / Pages 48-56

Technical Note / dx.doi.org/10.13182/NSE02-A2286

Spatial Adaptivity Applied to the Variational Nodal Pn Equations

Hui Zhang, E. E. Lewis

Nuclear Science and Engineering / Volume 142 / Number 1 / September 2002 / Pages 57-63

Technical Note / dx.doi.org/10.13182/NSE02-A2287

Convergence Analysis of Additive Angular Dependent Rebalance Acceleration for the Discrete Ordinates Transport Calculations

Chang Je Park, Nam Zin Cho

Nuclear Science and Engineering / Volume 142 / Number 1 / September 2002 / Pages 64-74

Technical Note / dx.doi.org/10.13182/NSE02-A2288

Single-Ray Streaming Behavior for Discontinuous Finite Element Spatial Discretizations

R. P. Smedley-Stevenson

Nuclear Science and Engineering / Volume 142 / Number 1 / September 2002 / Pages 75-84

Technical Note / dx.doi.org/10.13182/NSE02-A2289

Adaptive Mesh Refinement for the Time-Dependent Nodal Integral Method

Allen J. Toreja, Rizwan-uddin

Nuclear Science and Engineering / Volume 142 / Number 1 / September 2002 / Pages 85-95

Technical Note / dx.doi.org/10.13182/NSE02-A2290

Assessment of Reactivity Effects due to Localized Perturbations in BWR Lattices

R. van Geemert, F. Jatuff, P. Grimm, R. Chawla

Nuclear Science and Engineering / Volume 142 / Number 1 / September 2002 / Pages 96-106

Technical Note / dx.doi.org/10.13182/NSE02-A2291

Boiling Water Reactor Fuel Assembly Axial Design Optimization Using Tabu Search

C. Martín-del-Campo, J. L. François, L. B. Morales

Nuclear Science and Engineering / Volume 142 / Number 1 / September 2002 / Pages 107-115

Technical Note / dx.doi.org/10.13182/NSE02-A2292

Number 2

Optimization of Boiling Water Reactor Loading Pattern Using Two-Stage Genetic Algorithm

Yoko Kobayashi, Eitaro Aiyoshi

Nuclear Science and Engineering / Volume 142 / Number 2 / October 2002 / Pages 119-139

Technical Paper / dx.doi.org/10.13182/NSE02-A2293

Dead-Time Effects on Counting Statistics in Subcritical Nuclear Systems

Felix C. Difilippo

Nuclear Science and Engineering / Volume 142 / Number 2 / October 2002 / Pages 140-149

Technical Paper / dx.doi.org/10.13182/NSE02-A2294

Effects of Backscattering on One-Dimensional Electron Beam Transport

F. Andersson, H. Smith, D. Anderson, M. Lisak, P. Helander

Nuclear Science and Engineering / Volume 142 / Number 2 / October 2002 / Pages 150-157

Technical Paper / dx.doi.org/10.13182/NSE02-A2295

Photon Leakage from Spherical and Hemispherical Samples with a Central 14-MeV Neutron Source

A. I. Saukov, B. I. Sukhanov, A. M. Ryabinin, V. D. Lyutov, V. M. Shmakov, A. P. Vasiliev

Nuclear Science and Engineering / Volume 142 / Number 2 / October 2002 / Pages 158-164

Technical Paper / dx.doi.org/10.13182/NSE02-A2296

Matrix Diffusion of Radionuclides from a Finite Porous Rock Matrix to a Fracture: Importance of Back-Diffusion with a Constant Inlet Boundary Condition

Jin Beak Park, Yong Soo Hwang, Chul Hyung Kang

Nuclear Science and Engineering / Volume 142 / Number 2 / October 2002 / Pages 165-176

Technical Paper / dx.doi.org/10.13182/NSE02-A2297

Neutron and Proton Cross-Section Evaluations for 232Th up to 150 MeV

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

Nuclear Science and Engineering / Volume 142 / Number 2 / October 2002 / Pages 177-194

Technical Paper / dx.doi.org/10.13182/NSE02-A2298

Analysis for Cross Sections of (p,xn) Reactions on 208Pb at Intermediate Energies by Using Quantum Molecular Dynamics

Sheng Fan, Zhuaxia Li, Zhixiang Zhao

Nuclear Science and Engineering / Volume 142 / Number 2 / October 2002 / Pages 195-202

Technical Paper / dx.doi.org/10.13182/NSE02-A2299

Differential Cross-Section Measurement for the 10B(n,)7Li Reaction

Guohui Zhang, Guoyou Tang, Jinxiang Chen, Songbai Zhang, Zhaomin Shi, Jing Yuan, Zemin Chen, Yu. M. Gledenov, M. Sedysheva, G. Khuukhenkhuu

Nuclear Science and Engineering / Volume 142 / Number 2 / October 2002 / Pages 203-206

Technical Paper / dx.doi.org/10.13182/NSE02-A2300

UNF Code for Fast Neutron Reaction Data Calculations

Jingshang Zhang

Nuclear Science and Engineering / Volume 142 / Number 2 / October 2002 / Pages 207-219

Technical Paper / dx.doi.org/10.13182/NSE02-02

A Numerical Model for Evaluating the Impact of Noble Metal Chemical Addition in Boiling Water Reactors

Tsung-Kuang Yeh

Nuclear Science and Engineering / Volume 142 / Number 2 / October 2002 / Pages 220-229

Technical Paper / dx.doi.org/10.13182/NSE01-72

PCCSAC: A Three-Dimensional Code for AC600 Passive Containment Cooling System Analysis

Jiyang Yu, Baoshan Jia

Nuclear Science and Engineering / Volume 142 / Number 2 / October 2002 / Pages 230-236

Technical Paper / dx.doi.org/10.13182/NSE02-A2303

Observations of Confined Spray-Driven Air Vortices

Douglas W. Stamps

Nuclear Science and Engineering / Volume 142 / Number 2 / October 2002 / Pages 237-243

Technical Note / dx.doi.org/10.13182/NSE02-A2304

Number 3

Computing Moment-Based Probability Tables for Self-Shielding Calculations in Lattice Codes

Alain Hébert, Mireille Coste

Nuclear Science and Engineering / Volume 142 / Number 3 / November 2002 / Pages 245-257

Technical Paper / dx.doi.org/10.13182/NSE01-56

Simulation of Mixed-Oxide and Low-Enriched Uranium Fuel Burnup in a Pressurized Water Reactor and Validation Against Destructive Analysis Results

B. D. Murphy, R. T. Primm III

Nuclear Science and Engineering / Volume 142 / Number 3 / November 2002 / Pages 258-269

Technical Paper / dx.doi.org/10.13182/NSE02-A2306

Finite Element Solution of the Self-Adjoint Angular Flux Equation for Coupled Electron-Photon Transport

Jennifer L. Liscum-Powell, Anil B. Prinja, Jim E. Morel, Leonard J. Lorence, Jr.

Nuclear Science and Engineering / Volume 142 / Number 3 / November 2002 / Pages 270-291

Technical Paper / dx.doi.org/10.13182/NSE142-270

Comparative Measures of Radionuclide Containment in the Crystalline Geophere

V. Cvetkovic, S. Painter, J. O. Selroos

Nuclear Science and Engineering / Volume 142 / Number 3 / November 2002 / Pages 292-304

Technical Paper / dx.doi.org/10.13182/NSE02-A2308

Mechanisms of Positive Temperature Reactivity Coefficients of Dilute Plutonium Solutions

Toshihiro Yamamoto, Yoshinori Miyoshi

Nuclear Science and Engineering / Volume 142 / Number 3 / November 2002 / Pages 305-314

Technical Paper / dx.doi.org/10.13182/NSE02-A2309

A Spent-Fuel Combination Method for Minimizing Composition Variability of DUPIC Fuel

Man Gyun Na, Won Il Ko, Hangbok Choi

Nuclear Science and Engineering / Volume 142 / Number 3 / November 2002 / Pages 315-326

Technical Paper / dx.doi.org/10.13182/NSE02-A2310

An Alternative Implementation of the Differential Operator (Taylor Series) Perturbation Method for Monte Carlo Criticality Problems

Jeffrey A. Favorite

Nuclear Science and Engineering / Volume 142 / Number 3 / November 2002 / Pages 327-341

Technical Paper / dx.doi.org/10.13182/NSE02-A2311

Photon Interaction Studies with Some Glasses and Building Materials

Harvinder Singh, Kulwant Singh, Gopi Sharma, R. Nathuram, H. S. Sahota

Nuclear Science and Engineering / Volume 142 / Number 3 / November 2002 / Pages 342-348

Technical Paper / dx.doi.org/10.13182/NSE02-A2312

BOT3P: Bologna Transport Analysis Pre-Post-Processors Version 1.0

Roberto Orsi

Nuclear Science and Engineering / Volume 142 / Number 3 / November 2002 / Pages 349-354

Technical Note / dx.doi.org/10.13182/NSE02-A2313