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Volume 153

Number 1

Evaluation and Propagation of the 239Pu Fission Cross-Section Uncertainties Using a Monte Carlo Technique

T. Kawano, K. M. Hanson, S. Frankle, P. Talou, M. B. Chadwick, R. C. Little

Nuclear Science and Engineering / Volume 153 / Number 1 / May 2006 / Pages 1-7

Technical Paper

Neutron Transmission and Capture Measurements and Resonance Parameter Analysis of Neodymium from 1 to 500 eV

D. P. Barry, M. J. Trbovich, Y. Danon, R. C. Block, R. E. Slovacek, G. Leinweber, J. A. Burke, N. J. Drindak

Nuclear Science and Engineering / Volume 153 / Number 1 / May 2006 / Pages 8-25

Technical Paper

Calculation of the Prompt Neutron Lifetime in the NBSR

Albert L. Hanson, Hans Ludewig, David J. Diamond

Nuclear Science and Engineering / Volume 153 / Number 1 / May 2006 / Pages 26-32

Technical Paper / dx.doi.org/10.13182/NSE06-4

Photonuclear Physics in Radiation Transport - III: Actinide Cross Sections and Spectra

M.-L. Giacri-Mauborgne, D. Ridikas, M. B. Chadwick, P. G. Young, W. B. Wilson

Nuclear Science and Engineering / Volume 153 / Number 1 / May 2006 / Pages 33-40

Technical Paper

Differential and Angle-Integrated Cross-Section Measurement for the 6Li(n,t)4He Reaction at En = 1.05, 1.54, and 2.25 MeV

Guohui Zhang, Rongtai Cao, Jinxiang Chen, Guoyou Tang, Yu. M. Gledenov, M. Sedysheva, G. Khuukhenkhuu

Nuclear Science and Engineering / Volume 153 / Number 1 / May 2006 / Pages 41-45

Technical Paper

Collision Probabilities in r--z Geometry

R. D. M. Garcia

Nuclear Science and Engineering / Volume 153 / Number 1 / May 2006 / Pages 46-59

Technical Paper

The Statistics of the Number of Neutron Collisions Prior to Absorption

Sara A. Pozzi, Imre Pázsit

Nuclear Science and Engineering / Volume 153 / Number 1 / May 2006 / Pages 60-68

Technical Paper

Space-Time Correction for Reactivity Determination in Source-Driven Subcritical Systems

Viktoriya V. Kulik, John C. Lee

Nuclear Science and Engineering / Volume 153 / Number 1 / May 2006 / Pages 69-89

Technical Paper

The Smallest Thermal Nuclear Reactor

Y. Ronen, E. Fridman, E. Shwageraus

Nuclear Science and Engineering / Volume 153 / Number 1 / May 2006 / Pages 90-92

Technical Paper

MEND: A Program for Calculating the Complete Set of Nuclear Data of Medium-Heavy Nuclei in a Medium-Low Energy Region

Chong-Hai Cai

Nuclear Science and Engineering / Volume 153 / Number 1 / May 2006 / Pages 93-97

Computer Code Abstract / dx.doi.org/10.13182/NSE05-06CCA

 
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