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Home / Publications / Journals / Nuclear Science and Engineering / Volume 103 / Number 4

Volume 103

Number 4

The Optimum Fuel and Power Distribution for a Pressurized Water Reactor Burnup Cycle

J. A. Stillman, Y. A. Chao, T. J. Downar

Nuclear Science and Engineering / Volume 103 / Number 4 / December 1989 / Pages 321-333

Technical Paper / dx.doi.org/10.13182/NSE89-A23685

SIMULATE-3 Pin Power Reconstruction: Methodology and Benchmarking

K. R. Rempe, K. S. Smith, A. F. Henry

Nuclear Science and Engineering / Volume 103 / Number 4 / December 1989 / Pages 334-342

Technical Paper / dx.doi.org/10.13182/NSE89-A23686

A Nodal Expansion Method with Spatially Coupled Effects Incorporated into the Transverse Leakage Approximation

Moon H. Chang, Kap S. Moon, Jae M. Noh, Si H. Kim

Nuclear Science and Engineering / Volume 103 / Number 4 / December 1989 / Pages 343-350

Technical Paper / dx.doi.org/10.13182/NSE89-A23687

Neutronic Analysis Code for Fuel Assembly Using a Vectorized Monte Carlo Method

Yuuichi Morimoto, Hiromi Maruyama, Kazuya Ishii, Motoo Aoyama

Nuclear Science and Engineering / Volume 103 / Number 4 / December 1989 / Pages 351-358

Technical Paper / dx.doi.org/10.13182/NSE89-A23688

Environment-Insensitive Equivalent Diffusion Theory Group Constants for Pressurized Water Reactor Radial Reflector Regions

E. Z. Müller

Nuclear Science and Engineering / Volume 103 / Number 4 / December 1989 / Pages 359-376

Technical Paper / dx.doi.org/10.13182/NSE89-A23689

Three-Dimensional Nodal Diffusion and Transport Theory Methods for Hexagonal-z Geometry

M. R. Wagner

Nuclear Science and Engineering / Volume 103 / Number 4 / December 1989 / Pages 377-391

Technical Paper / dx.doi.org/10.13182/NSE89-A23690

ILLICO: A Nodal Neutron Diffusion Method for Modern Computer Architectures

Hrabri L. Rajic, Abderrafi M. Ougouag

Nuclear Science and Engineering / Volume 103 / Number 4 / December 1989 / Pages 392-408

Technical Paper / dx.doi.org/10.13182/NSE89-A23691

A Spatial Kinetics Computational Method for Large Fast Reactors

J. K. Fletcher

Nuclear Science and Engineering / Volume 103 / Number 4 / December 1989 / Pages 409-414

Technical Paper / dx.doi.org/10.13182/NSE89-A23692

Theory and Performance of the Fast-Running Multidimensional Pressurized Water Reactor Kinetics Code, SPNOVA-K

Y. A. Chao, P. Huang

Nuclear Science and Engineering / Volume 103 / Number 4 / December 1989 / Pages 415-419

Technical Paper / dx.doi.org/10.13182/NSE89-A23693

Verification of the SIMULATE-3 Pin Power Distribution Calculation

A. S. DiGiovine, J. P. Gorski, M. A. Tremblay

Nuclear Science and Engineering / Volume 103 / Number 4 / December 1989 / Pages 420-426

Technical Note / dx.doi.org/10.13182/NSE89-A23694

 

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