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Volume 138

Number 1

A Parametric Study of the DUPIC Fuel Cycle to Reflect Pressurized Water Reactor Fuel Management Strategy

Daniel Rozon, Wei Shen

Nuclear Science and Engineering / Volume 138 / Number 1 / May 2001 / Pages 1-25

Technical Paper / dx.doi.org/10.13182/NSE138-1-25

Split-Cell Exponential Characteristic Transport Method for Unstructured Tetrahedral Meshes

Charles R. Brennan, Rodney L. Miller, Kirk A. Mathews

Nuclear Science and Engineering / Volume 138 / Number 1 / May 2001 / Pages 26-44

Technical Paper / dx.doi.org/10.13182/NSE01-A2200

Multidimensional Deterministic Nuclear Data Sensitivity and Uncertainty Code System: Method and Application

Ivan Kodeli

Nuclear Science and Engineering / Volume 138 / Number 1 / May 2001 / Pages 45-66

Technical Paper / dx.doi.org/10.13182/NSE00-43

Boiling Water Reactor Loading Pattern Optimization Using Simple Linear Perturbation and Modified Tabu Search Methods

Suetsugu Jagawa, Takashi Yoshii, Akihiro Fukao

Nuclear Science and Engineering / Volume 138 / Number 1 / May 2001 / Pages 67-77

Technical Paper / dx.doi.org/10.13182/NSE00-44

Transient Criticality in Fissile Solutions—Compressibility Effects

C. C. Pain, C. R. E. de Oliveira, A. J. H. Goddard, A. P. Umpleby

Nuclear Science and Engineering / Volume 138 / Number 1 / May 2001 / Pages 78-95

Technical Paper / dx.doi.org/10.13182/NSE138-78

An Approximate Monte Carlo Adaptive Importance Sampling Method

Thomas E. Booth

Nuclear Science and Engineering / Volume 138 / Number 1 / May 2001 / Pages 96-103

Technical Paper / dx.doi.org/10.13182/NSE01-A2204