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Volume 154

Number 1

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

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

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

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

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

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

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

 
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