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Volume 154

Number 2

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 SN 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