American Nuclear Society
Home

Home / Store / Journals / Electronic Articles / Nuclear Science and Engineering / Volume 154

Volume 154

Viewing 1 to 20 of 29

Table of Contents

Nuclear Science and Engineering / Volume 154 / Number 1

September 2006

Table of Contents

Nuclear Science and Engineering / Volume 154 / Number 2

October 2006

Table of Contents

Nuclear Science and Engineering / Volume 154 / Number 3

November 2006

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 / Pages 1-27

September 2006

Format:

Price:$30.00

Mixed and Hybrid Finite Element Method for the Transport Equation

J. Cartier, G. Samba

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

September 2006

Format:

Price:$30.00

Power Iteration Method for the Several Largest Eigenvalues and Eigenfunctions

Thomas E. Booth

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

September 2006

Format:

Price:$30.00

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 / Pages 63-73

September 2006

Format:

Price:$30.00

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 / Pages 74-93

September 2006

Format:

Price:$30.00

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 / Pages 94-109

September 2006

Format:

Price:$30.00

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 / Pages 110-117

September 2006

Format:

Price:$30.00

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 / Pages 119-133

October 2006

Format:

Price:$30.00

The Search for Superconvergence in Spherical Harmonics Approximations

Alain Hébert

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

October 2006

Format:

Price:$30.00

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 / Pages 174-189

October 2006

Format:

Price:$30.00

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 / Pages 190-201

October 2006

Format:

Price:$30.00

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 / Pages 202-214

October 2006

Format:

Price:$30.00

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 / Pages 215-222

October 2006

Format:

Price:$30.00

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 / Pages 223-232

October 2006

Format:

Price:$30.00

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 / Pages 233-240

October 2006

Format:

Price:$30.00

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

Aldo Dall'Osso

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

October 2006

Format:

Price:$30.00

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 / Pages 247-259

October 2006

Format:

Price:$30.00
Page of 2
«Previous Page|Next Page»
 
 
 
Questions or comments about the site? Contact the ANS Webmaster.
advertisement