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Volume 141

Number 2

Alternative Implementations of the Monte Carlo Power Method

R. N. Blomquist, E. M. Gelbard

Nuclear Science and Engineering / Volume 141 / Number 2 / June 2002 / Pages 85-100

Technical Paper

Intergenerational Correlation in Monte Carlo k-Eigenvalue Calculation

Taro Ueki

Nuclear Science and Engineering / Volume 141 / Number 2 / June 2002 / Pages 101-110

Technical Paper

A Mixed-Oxide Assembly Design for Rapid Disposition of Weapons Plutonium in Pressurized Water Reactors

Gustavo Alonso, Marvin L. Adams

Nuclear Science and Engineering / Volume 141 / Number 2 / June 2002 / Pages 111-128

Technical Paper

Gamma-Ray Spectroscopy Measurements of Decay Heat in Spent Nuclear Fuel

P. Jansson, A. Håkansson, A. Bäcklin, S. Jacobsson

Nuclear Science and Engineering / Volume 141 / Number 2 / June 2002 / Pages 129-139

Technical Paper

Measurements of High-Energy Neutrons Penetrated Through Concrete Shields Using Self-TOF, NE213, and Activation Detectors

M. Sasaki, E. Kim, T. Nunomiya, T. Nakamura, N. Nakao, T. Shibata, Y. Uwamino, S. Ito, A. Fukumura

Nuclear Science and Engineering / Volume 141 / Number 2 / June 2002 / Pages 140-153

Technical Paper

Calculation and Analysis of Double-Differential Cross Sections for n + 209Bi Reaction

Yinlu Han, Zhengjun Zhang

Nuclear Science and Engineering / Volume 141 / Number 2 / June 2002 / Pages 154-164

Technical Paper

Experimental Study of Energy Distribution in Double Photon Compton Scattering

R. Dewan, M. B. Saddi, B. S. Sandhu, B. Singh, B. S. Ghumman

Nuclear Science and Engineering / Volume 141 / Number 2 / June 2002 / Pages 165-170

Technical Paper

The 234U(nth,f) Cross Section Revisited

Cyriel Wagemans, Jan Wagemans, Olivier Serot

Nuclear Science and Engineering / Volume 141 / Number 2 / June 2002 / Pages 171-173

Technical Note

 
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