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Volume 116

Number 2

Table of Contents

A Fission-Source Acceleration Technique for Time-Dependent Even-Parity S_n Calculations

J. E. Morel, J. M. McGhee

Nuclear Science and Engineering / Volume 116 / Number 2 / February 1994 / Pages 73-85

Technical Paper / dx.doi.org/10.13182/NSE94-A21484

Effective Diffusion Homogenization of Cross Sections for Pressurized Water Reactor Core Calculations

Nuclear Science and Engineering / Volume 116 / Number 2 / February 1994 / Pages 86-95

Technical Paper / dx.doi.org/10.13182/NSE94-A21485

A Probabilistic Method for Evaluating Reactivity Feedbacks and Its Application to Experimental Breeder Reactor II

R. W. Schaefer

Nuclear Science and Engineering / Volume 116 / Number 2 / February 1994 / Pages 96-112

Technical Paper / dx.doi.org/10.13182/NSE94-A21486

A Monte Carlo Variance Reduction Approach for Non-Boltzmann Tallies

Thomas E. Booth

Nuclear Science and Engineering / Volume 116 / Number 2 / February 1994 / Pages 113-124

Technical Paper / dx.doi.org/10.13182/NSE94-A21487

Excitation Functions of Neutron Threshold Reactions on Some Isotopes of Germanium, Arsenic, and Selenium in the 6.3- to 14.7-MeV Energy Range

I. Birn, S. M. Qaim

Nuclear Science and Engineering / Volume 116 / Number 2 / February 1994 / Pages 125-137

Technical Paper / dx.doi.org/10.13182/NSE94-A21488

Measurements of the Modified Conversion Ratio by Gamma-Ray Spectrometry of Fuel Rods for Water-Moderated UO₂ Cores

Ken Nakajima, Masanori Akai, Takenori Suzaki

Nuclear Science and Engineering / Volume 116 / Number 2 / February 1994 / Pages 138-146

Technical Paper / dx.doi.org/10.13182/NSE94-A21489

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