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Volume 153

Number 2

Probabilistic Techniques for Diagnosis of Multiple Component Degradations

Steven E. Aumeier, Bulent Alpay, John C. Lee, A. Ziya Akcasu

Nuclear Science and Engineering / Volume 153 / Number 2 / June 2006 / Pages 101-123

Technical Paper

Estimation of Effective Parameters in a Lumped Nuclear Reactor Model Using Multiobjective Genetic Algorithms

Marzio Marseguerra, Enrico Zio, Raffaele Canetta

Nuclear Science and Engineering / Volume 153 / Number 2 / June 2006 / Pages 124-136

Technical Paper

MCDET: A Probabilistic Dynamics Method Combining Monte Carlo Simulation with the Discrete Dynamic Event Tree Approach

Martina Kloos, Jörg Peschke

Nuclear Science and Engineering / Volume 153 / Number 2 / June 2006 / Pages 137-156

Technical Paper

A Fuzzy Logic-Based Model for the Classification of Faults in the Pump Seals of the Primary Heat Transport System of a CANDU 6 Reactor

Marzio Marseguerra, Enrico Zio, Piero Baraldi, Irina Crenguta Popescu, Paul Ulmeanu

Nuclear Science and Engineering / Volume 153 / Number 2 / June 2006 / Pages 157-171

Technical Paper

Time Series Analysis of Monte Carlo Fission Sources - II: Confidence Interval Estimation

Taro Ueki, Brian R. Nease

Nuclear Science and Engineering / Volume 153 / Number 2 / June 2006 / Pages 184-191

Technical Paper / dx.doi.org/10.13182/NSE05-15

Calculations of Proton-Induced Neutron Production Cross Sections on 232Th up to 1.6 GeV

B. Sarer, M. Günay, A. Aydin, E. Tel, A. Arasoglu

Nuclear Science and Engineering / Volume 153 / Number 2 / June 2006 / Pages 192-199

Technical Note

 
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