American Nuclear Society
Home

Home / Publications / Journals / Nuclear Technology / Volume 157 / Number 3

Volume 157

Number 3

The PROMETRA Program: Fuel Cladding Mechanical Behavior Under High Strain Rate

B. Cazalis, J. Desquines, C. Poussard, M. Petit, Y. Monerie, C. Bernaudat, P. Yvon, X. Averty

Nuclear Technology / Volume 157 / Number 3 / March 2007 / Pages 215-229

Technical Paper / Reactivity-Initiated Accident (RIA)

Summary and Interpretation of the CABRI REP-Na Program

J. Papin, B. Cazalis, J. M. Frizonnet, J. Desquines, F. Lemoine, V. Georgenthum, F. Lamare, M. Petit

Nuclear Technology / Volume 157 / Number 3 / March 2007 / Pages 230-250

Technical Paper / Reactivity-Initiated Accident (RIA)

Boiling Water Reactor Fuel Lattice Enrichment Distribution Optimization Using Tabu Search and Fuzzy Logic

Cecilia Martin-del-Campo, Juan Luis François, Alejandra M. Barragan, Miguel A. Palomera

Nuclear Technology / Volume 157 / Number 3 / March 2007 / Pages 251-260

Technical Paper / Fuel Cycle and Management

Azimuthal Film-Boiling Heat Transfer from a Downward-Facing Hemisphere

Mong J. Yu, Chan S. Kim, Kune Y. Suh

Nuclear Technology / Volume 157 / Number 3 / March 2007 / Pages 261-276

Technical Paper / Thermal Hydraulics

Studies of an Accelerator-Driven Transuranium Burner with Hafnium-Based Inert Matrix Fuel

Kamil Tucek, Mikael Jolkkonen, Janne Wallenius, Waclaw Gudowski

Nuclear Technology / Volume 157 / Number 3 / March 2007 / Pages 277-298

Technical Paper / Accelerators

Performance of Advanced Self-Shielding Models in DRAGON for the Estimation of CANDU-6 Safety Parameters

Ramamoorthy Karthikeyan, Alain Hébert

Nuclear Technology / Volume 157 / Number 3 / March 2007 / Pages 299-316

Technical Note / Fission Reactors

 
Questions or comments about the site? Contact the ANS Webmaster.
advertisement