American Nuclear Society
Home

Home / Publications / Journals / Nuclear Science and Engineering / Volume 139 / Number 1

Volume 139

Number 1

Development of Methods for Calculation of Deuteron-Lithium and Neutron-Lithium Cross Sections for Energies up to 50 MeV

A. Yu. Konobeyev, Yu. A. Korovin, P. E. Pereslavtsev, Ulrich Fischer, Ulrich von Möllendorff

Nuclear Science and Engineering / Volume 139 / Number 1 / September 2001 / Pages 1-23

Technical Paper / dx.doi.org/10.13182/NSE00-31

Threshold Reaction Cross Sections of Nickel Isotopes, Averaged Over a 235U Fission Neutron Spectrum

M. A. Arribére, S. Ribeiro Guevara, P. M. Suárez, A. J. Kestelman

Nuclear Science and Engineering / Volume 139 / Number 1 / September 2001 / Pages 24-32

Technical Paper

Nonnegative Anisotropic Group Cross Sections: A Hybrid Monte Carlo-Discrete Elements-Discrete Ordinates Approach

J. Mark DelGrande, Kirk A. Mathews

Nuclear Science and Engineering / Volume 139 / Number 1 / September 2001 / Pages 33-46

Technical Paper

A Transport Condensed History Algorithm for Electron Monte Carlo Simulations

Danny R. Tolar, Jr., Edward W. Larsen

Nuclear Science and Engineering / Volume 139 / Number 1 / September 2001 / Pages 47-65

Technical Paper

Neutron Transport in Spatially Random Media: Eigenvalue Problems

M. M. R. Williams, Edward W. Larsen

Nuclear Science and Engineering / Volume 139 / Number 1 / September 2001 / Pages 66-77

Technical Paper

A Spatial Kinetics Method Ensuring Neutronic Balance with Thermal-Hydraulic Feedback and Its Application to a Main Steam Line Break

Yoshiro Asahi, Keisuke Okumura, Yasuo Ose

Nuclear Science and Engineering / Volume 139 / Number 1 / September 2001 / Pages 78-95

Technical Paper

Genetic Algorithms for Estimating Effective Parameters in a Lumped Reactor Model for Reactivity Predictions

Marzio Marseguerra, Enrico Zio

Nuclear Science and Engineering / Volume 139 / Number 1 / September 2001 / Pages 96-104

Technical Paper

An Alternate Formulation of the Nodal Expansion Method

Keqiang Ruan, Xiaogang Xue, Xuedong Fu

Nuclear Science and Engineering / Volume 139 / Number 1 / September 2001 / Pages 105-110

Technical Note

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