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Home / Publications / Journals / Nuclear Science and Engineering / Volume 146 / Number 3

Volume 146

Number 3

Table of Contents

Development of One-Group and Two-Group Interfacial Area Transport Equation

M. Ishii, S. Kim

Nuclear Science and Engineering / Volume 146 / Number 3 / March 2004 / Pages 257-273

Technical Paper / dx.doi.org/10.13182/NSE01-69

Adequacy of Power-to-Mass Scaling in Simulating PWR Incident Transient for Reduced-Height, Reduced-Pressure and Full-Height, Full-Pressure Integral System Test Facilities

Tay-Jian Liu, Chien-Hsiung Lee

Nuclear Science and Engineering / Volume 146 / Number 3 / March 2004 / Pages 274-290

Technical Paper / dx.doi.org/10.13182/NSE04-A2410

Long-Lived Fission Product Transmutation Studies

W. S. Yang, Y. Kim, R. N. Hill, T. A. Taiwo, H. S. Khalil

Nuclear Science and Engineering / Volume 146 / Number 3 / March 2004 / Pages 291-318

Technical Paper / dx.doi.org/10.13182/NSE04-A2411

A Nodal and Finite Difference Hybrid Method for Pin-by-Pin Heterogeneous Three-Dimensional Light Water Reactor Diffusion Calculations

Deokjung Lee, Thomas J. Downar, Yonghee Kim

Nuclear Science and Engineering / Volume 146 / Number 3 / March 2004 / Pages 319-339

Technical Paper / dx.doi.org/10.13182/NSE04-A2412

Sensitivity- and Uncertainty-Based Criticality Safety Validation Techniques

B. L. Broadhead, B. T. Rearden, C. M. Hopper, J. J. Wagschal, C. V. Parks

Nuclear Science and Engineering / Volume 146 / Number 3 / March 2004 / Pages 340-366

Technical Paper / dx.doi.org/10.13182/NSE03-2

Perturbation Theory Eigenvalue Sensitivity Analysis with Monte Carlo Techniques

B. T. Rearden

Nuclear Science and Engineering / Volume 146 / Number 3 / March 2004 / Pages 367-382

Technical Paper / dx.doi.org/10.13182/NSE03-03

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