American Nuclear Society
Home

Home / Publications / Journals / Nuclear Science and Engineering / Volume 144

Volume 144

Number 1 | Number 2 | Number 3

Number 1

Analysis of Ray-Effect Mitigation Techniques

J. E. Morel, T. A. Wareing, R. B. Lowrie, D. K. Parsons

Nuclear Science and Engineering / Volume 144 / Number 1 / May 2003 / Pages 1-22

Technical Paper / dx.doi.org/10.13182/NSE01-48

Analytic Coarse-Mesh Finite-Difference Method Generalized for Heterogeneous Multidimensional Two-Group Diffusion Calculations

Nuria García-Herranz, Oscar Cabellos, José M. Aragonés, Carol Ahnert

Nuclear Science and Engineering / Volume 144 / Number 1 / May 2003 / Pages 23-35

Technical Paper / dx.doi.org/10.13182/NSE03-A2340

A Finite Subelement Generalization of the Variational Nodal Method

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

Nuclear Science and Engineering / Volume 144 / Number 1 / May 2003 / Pages 36-46

Technical Paper / dx.doi.org/10.13182/NSE144-36

The Reactivity Temperature Coefficient Analysis in Light Water Moderated UO2 and UO2-PuO2 Lattices

L. Erradi, A. Santamarina, O. Litaize

Nuclear Science and Engineering / Volume 144 / Number 1 / May 2003 / Pages 47-73

Technical Paper / dx.doi.org/10.13182/NSE144-47

Scaling and Parametric Studies of Condensation Oscillation in an In-Containment Refueling Water Storage Tank

Jun Hyung Lee, Hee Cheon No

Nuclear Science and Engineering / Volume 144 / Number 1 / May 2003 / Pages 74-85

Technical Paper / dx.doi.org/10.13182/NSE03-A2343

Scattering of Intermediate-Energy Neutrons from Nuclei and the Ramsauer Hypothesis

Mofazzal Azam, Rajesh S. Gowda

Nuclear Science and Engineering / Volume 144 / Number 1 / May 2003 / Pages 86-93

Technical Paper / dx.doi.org/10.13182/NSE03-A2344

Neutron Capture Cross-Section Measurement of Rhodium in the Energy Region from 0.003 eV to 80 keV by Linac Time-of-Flight Method

Samyol Lee, Shuji Yamamoto, Katsuhei Kobayashi, Guinyun Kim, Jonghwa Chang

Nuclear Science and Engineering / Volume 144 / Number 1 / May 2003 / Pages 94-107

Technical Paper / dx.doi.org/10.13182/NSE03-A2345

Angular Distribution and Cross-Section Measurements for 64Zn(n,)61Ni Reaction at 5.0, 5.7, and 6.5 MeV

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

Nuclear Science and Engineering / Volume 144 / Number 1 / May 2003 / Pages 108-112

Technical Paper / dx.doi.org/10.13182/NSE03-A2346

Number 2

Validation of Minor Actinide Cross Sections by Studying Samples Irradiated for 492 Days at the Dounreay Prototype Fast Reactor - I: Radiochemical Analysis

N. Shinohara, N. Kohno, Y. Nakahara, K. Tsujimoto, T. Sakurai, T. Mukaiyama, S. Raman

Nuclear Science and Engineering / Volume 144 / Number 2 / June 2003 / Pages 115-128

Technical Paper / dx.doi.org/10.13182/NSE03-A2347

Validation of Minor Actinide Cross Sections by Studying Samples Irradiated for 492 Days at the Dounreay Prototype Fast Reactor - II: Burnup Calculations

K. Tsujimoto, N. Kohno, N. Shinohara, T. Sakurai, Y. Nakahara, T. Mukaiyama, S. Raman

Nuclear Science and Engineering / Volume 144 / Number 2 / June 2003 / Pages 129-141

Technical Paper / dx.doi.org/10.13182/NSE03-A2348

Precise Validation of Database (n,) Cross Sections Using a Lead-Slowing-Down Spectrometer and Simulation from 0.1 eV to 30 keV: Methodology and Data for a Few Elements

L. Perrot, A. Billebaud, R. Brissot, A. Giorni, D. Heuer, J.-M. Loiseaux, O. Méplan, J.-B. Viano

Nuclear Science and Engineering / Volume 144 / Number 2 / June 2003 / Pages 142-156

Technical Paper / dx.doi.org/10.13182/NSE03-A2349

Photonuclear Physics in Radiation Transport—I: Cross Sections and Spectra

M. B. Chadwick, P. G. Young, R. E. MacFarlane, M. C. White, R. C. Little

Nuclear Science and Engineering / Volume 144 / Number 2 / June 2003 / Pages 157-173

Technical Paper / dx.doi.org/10.13182/NSE144-157

Photonuclear Physics in Radiation Transport—II: Implementation

M. C. White, R. C. Little, M. B. Chadwick, P. G. Young, R. E. MacFarlane

Nuclear Science and Engineering / Volume 144 / Number 2 / June 2003 / Pages 174-189

Technical Paper / dx.doi.org/10.13182/NSE144-174

Number 3

Criticality and Reactivity Measurement Method for Nuclear Material Control and Accountability

N. N. Ponomarev-Stepnoi, Y. S. Glushkov, V. P. Garin, G. V. Kompaniets, V. I. Nosov, R. G. Sanchez, R. R. Paternoster, S. P. Gary

Nuclear Science and Engineering / Volume 144 / Number 3 / July 2003 / Pages 191-199

Technical Paper / dx.doi.org/10.13182/NSE03-A2352

A Numerical Method for Computing Collision, Escape, and Transmission Probabilities in Three Dimensions

R. D. M. Garcia

Nuclear Science and Engineering / Volume 144 / Number 3 / July 2003 / Pages 200-210

Technical Paper / dx.doi.org/10.13182/NSE03-A2353

Effects of Nuclear Data Library on BFS and ZPPR keff Analysis Results

Gennadi Manturov

Nuclear Science and Engineering / Volume 144 / Number 3 / July 2003 / Pages 211-218

Technical Paper / dx.doi.org/10.13182/NSE03-A2354

The Fragment Distribution of Nb, Au, and Pb from Proton-Induced Reactions with Energies Ranging from 100 MeV to 3 GeV

S. Fan, J. Rong, H. Zhang, Z. Zhao

Nuclear Science and Engineering / Volume 144 / Number 3 / July 2003 / Pages 219-226

Technical Paper / dx.doi.org/10.13182/NSE03-A2355

Characterization of a Source Importance Function in an Accelerator-Driven System

Yonghee Kim, Won Seok Park, Chang Kue Park

Nuclear Science and Engineering / Volume 144 / Number 3 / July 2003 / Pages 227-241

Technical Paper / dx.doi.org/10.13182/NSE03-A2356

An Investigation of Power Stabilization and Space-Dependent Dynamics of a Nuclear Fluidized-Bed Reactor

Christopher C. Pain, Matthew D. Eaton, Jefferson L. M. A. Gomes, Cassiano R. E. de Oliveira, Adrian P. Umpleby, Kemal Ziver, Ron T. Ackroyd, Bryan Miles, Antony J. H. Goddard, H. van Dam, T. H. J. J. van der Hagen, D. Lathouwers

Nuclear Science and Engineering / Volume 144 / Number 3 / July 2003 / Pages 242-257

Technical Note / dx.doi.org/10.13182/NSE03-A2357

Dynamic Adsorption of Noble Gases

Dwight Underhill

Nuclear Science and Engineering / Volume 144 / Number 3 / July 2003 / Pages 258-260

Technical Note / dx.doi.org/10.13182/NSE03-A2358