ANS / Publications / Journals / Nuclear Science and Engineering

Implications of Alternative Strategies for Transition to Sustainable Fuel Cycles

Antonino Romano, Thomas Boscher, Pavel Hejzlar, Mujid S. Kazimi, Neil E. Todreas

Nuclear Science and Engineering / Volume 154 / Number 1 / September 2006 / Pages 1-27

Technical Paper / dx.doi.org/10.13182/NSE06-A2615

Mixed and Hybrid Finite Element Method for the Transport Equation

J. Cartier, G. Samba

Nuclear Science and Engineering / Volume 154 / Number 1 / September 2006 / Pages 28-47

Technical Paper / dx.doi.org/10.13182/NSE06-A2616

Power Iteration Method for the Several Largest Eigenvalues and Eigenfunctions

Thomas E. Booth

Nuclear Science and Engineering / Volume 154 / Number 1 / September 2006 / Pages 48-62

Technical Paper / dx.doi.org/10.13182/NSE05-05

Development of a Criticality Evaluation Method Involving the Granular Flow of the Nuclear Fuel in a Rotating Drum

Mikio Sakai, Kazuya Shibata, Seiichi Koshizuka

Nuclear Science and Engineering / Volume 154 / Number 1 / September 2006 / Pages 63-73

Technical Paper / dx.doi.org/10.13182/NSE06-A2618

Development of Sweepout Model in APR1400 During an LBLOCA

Byoung-Uhn Bae, Yong-Soo Kim, Goon-Cherl Park

Nuclear Science and Engineering / Volume 154 / Number 1 / September 2006 / Pages 74-93

Technical Paper / dx.doi.org/10.13182/NSE06-A2619

Critical Heat Flux of Subcooled Water Flow Boiling for High L/d Region

Koichi Hata, Masahiro Shiotsu, Nobuaki Noda

Nuclear Science and Engineering / Volume 154 / Number 1 / September 2006 / Pages 94-109

Technical Note / dx.doi.org/10.13182/NSE06-A2620

A Method for Fast Determination of the Parameter in Nuclear Reactors

I. M. Cohen, M. Arrondo, M. A. Arribére, M. C. Fornaciari Iljadica

Nuclear Science and Engineering / Volume 154 / Number 1 / September 2006 / Pages 110-117

Technical Note / dx.doi.org/10.13182/NSE06-A2621

Analysis of Sample Irradiation Experiments in Phénix for JEFF-3.0 Nuclear Data Validation

J. Tommasi, E. Dupont, P. Marimbeau

Nuclear Science and Engineering / Volume 154 / Number 2 / October 2006 / Pages 119-133

Technical Paper / dx.doi.org/10.13182/NSE154-119

The Search for Superconvergence in Spherical Harmonics Approximations

Alain Hébert

Nuclear Science and Engineering / Volume 154 / Number 2 / October 2006 / Pages 134-173

Technical Paper / dx.doi.org/10.13182/NSE06-A2623

Temporal Accuracy of the Nonequilibrium Radiation Diffusion Equations Applied to Two-Dimensional Multimaterial Simulations

Vincent A. Mousseau, Dana A. Knoll

Nuclear Science and Engineering / Volume 154 / Number 2 / October 2006 / Pages 174-189

Technical Paper / dx.doi.org/10.13182/NSE06-A2624

Continuous-Energy Multidimensional S_N Transport for Problem-Dependent Resonance Self-Shielding Calculations

Zhaopeng Zhong, Thomas J. Downar, Yunlin Xu, Mark L. Williams, Mark D. DeHart

Nuclear Science and Engineering / Volume 154 / Number 2 / October 2006 / Pages 190-201

Technical Paper / dx.doi.org/10.13182/NSE06-3

Proton Source Efficiency for Heterogeneous Distribution of Actinides in the Core of an Accelerator-Driven System

Per Seltborg, Jan Wallenius

Nuclear Science and Engineering / Volume 154 / Number 2 / October 2006 / Pages 202-214

Technical Paper / dx.doi.org/10.13182/NSE06-A2626

Compton Current Generated by Nuclear Radiation: A Coupled Neutron-Gamma-Electron Transport Model

Gundra Kondayya, Aditi Ray

Nuclear Science and Engineering / Volume 154 / Number 2 / October 2006 / Pages 215-222

Technical Paper / dx.doi.org/10.13182/NSE06-A2627

Oxygen Control Technique in Molten Lead and Lead-Bismuth Eutectic Systems

Jinsuo Zhang, Ning Li, Yitung Chen

Nuclear Science and Engineering / Volume 154 / Number 2 / October 2006 / Pages 223-232

Technical Paper / dx.doi.org/10.13182/NSE06-A2628

Lead- and Bismuth-Borate Fly-Ash Glasses as Gamma-Ray-Shielding Materials

Kulwant Singh, Ashutosh Goel, Shaweta Mohan, Annu Arora, Gopi Sharma

Nuclear Science and Engineering / Volume 154 / Number 2 / October 2006 / Pages 233-240

Technical Paper / dx.doi.org/10.13182/NSE06-A2629

A Data Identification Method for the Improvement of a Cross-Section Model

Aldo Dall'Osso

Nuclear Science and Engineering / Volume 154 / Number 2 / October 2006 / Pages 241-246

Technical Paper / dx.doi.org/10.13182/NSE06-A2630

A General Method of Conserving Mass in Complex Geometry Simulations on Mesh Grids and Its Implementation in BOT3P5.0

Roberto Orsi

Nuclear Science and Engineering / Volume 154 / Number 2 / October 2006 / Pages 247-259

Computer Code Abstract / dx.doi.org/10.13182/NSE06-A2631

Neutron Capture and Total Cross-Section Measurements and Resonance Parameters of Gadolinium

G. Leinweber, D. P. Barry, M. J. Trbovich, J. A. Burke, N. J. Drindak, H. D. Knox, R. V. Ballad, R. C. Block, Y. Danon, L. I. Severnyak

Nuclear Science and Engineering / Volume 154 / Number 3 / November 2006 / Pages 261-279

Technical Paper / dx.doi.org/10.13182/NSE05-64

Modeling and Neutron-Induced Fission Cross Sections for Americium

D. Rochman, M. Herman, P. Oblozinský, M. Sin

Nuclear Science and Engineering / Volume 154 / Number 3 / November 2006 / Pages 280-293

Technical Paper / dx.doi.org/10.13182/NSE06-A2633

Neutron Capture and Transmission Measurements and Resonance Parameter Analysis of Niobium

N. J. Drindak, J. A. Burke, G. Leinweber, J. A. Helm, J. G. Hoole, R. C. Block, Y. Danon, R. E. Slovacek, B. E. Moretti, C. J. Werner, M. E. Overberg, S. A. Kolda, M. J. Trbovich, D. P. Barry

Nuclear Science and Engineering / Volume 154 / Number 3 / November 2006 / Pages 294-301

Technical Paper / dx.doi.org/10.13182/NSE06-A2634

A Study of Nonlinear Oscillation and Limit Cycles in Boiling Water Reactors - I: The Global Mode

Yousef M. Farawila, Douglas W. Pruitt

Nuclear Science and Engineering / Volume 154 / Number 3 / November 2006 / Pages 302-315

Technical Paper / dx.doi.org/10.13182/NSE06-A2635

A Study of Nonlinear Oscillation and Limit Cycles in Boiling Water Reactors - II: The Regional Mode

Yousef M. Farawila, Douglas W. Pruitt

Nuclear Science and Engineering / Volume 154 / Number 3 / November 2006 / Pages 316-327

Technical Paper / dx.doi.org/10.13182/NSE06-A2636

Homogenization Method for the Two-Dimensional Low-Order Quasi-Diffusion Equations for Reactor Core Calculations

Hikaru Hiruta, Dmitriy Y. Anistratov

Nuclear Science and Engineering / Volume 154 / Number 3 / November 2006 / Pages 328-352

Technical Paper / dx.doi.org/10.13182/NSE06-A2637

Design of a Model Predictive Power Controller for an SP-100 Space Reactor

Man Gyun Na, Belle R. Upadhyaya, Xiaojia Xu, In Joon Hwang

Nuclear Science and Engineering / Volume 154 / Number 3 / November 2006 / Pages 353-366

Technical Paper / dx.doi.org/10.13182/NSE06-A2638

Neutron Slowing Down in a Detector with Absorption

Sara A. Pozzi, Imre Pázsit

Nuclear Science and Engineering / Volume 154 / Number 3 / November 2006 / Pages 367-373

Technical Paper / dx.doi.org/10.13182/NSE06-A2639

Analysis of the Nuclear Level-Density Parameters of Some Large Deformed Odd-A and Odd-Odd Nuclei in the Region of Rare Earth Elements

Seref Okuducu, Erhan Eser, Savas Sönmezoglu

Nuclear Science and Engineering / Volume 154 / Number 3 / November 2006 / Pages 374-381

Technical Paper / dx.doi.org/10.13182/NSE06-A2640