ANS / Publications / Journals / Nuclear Science and Engineering

Boundary Projection Acceleration: A New Approach to Synthetic Acceleration of Transport Calculations

Marvin L. Adams, William R. Martin

Nuclear Science and Engineering / Volume 100 / Number 3 / November 1988 / Pages 177-189

Technical Paper / dx.doi.org/10.13182/NSE100-177

Comparison of Three Approximations to the Linear-Linear Nodal Transport Method in Weighted Diamond-Difference Form

Y. Y. Azmy

Nuclear Science and Engineering / Volume 100 / Number 3 / November 1988 / Pages 190-200

Technical Paper / dx.doi.org/10.13182/NSE88-5

SMART Scattering Matrices for Single Collision Electron Monte Carlo Calculations

W. L. Filippone, S. Woolf

Nuclear Science and Engineering / Volume 100 / Number 3 / November 1988 / Pages 201-208

Technical Paper / dx.doi.org/10.13182/NSE88-A29032

The S_N/Monte Carlo Response Matrix Hybrid Method

W. L. Filippone, R. E. Alcouffe

Nuclear Science and Engineering / Volume 100 / Number 3 / November 1988 / Pages 209-217

Technical Paper / dx.doi.org/10.13182/NSE88-A29033

Mixed and Mixed-Hybrid Elements for the Diffusion Equation

F. Coulomb, C. Fedon-Magnaud

Nuclear Science and Engineering / Volume 100 / Number 3 / November 1988 / Pages 218-225

Technical Paper / dx.doi.org/10.13182/NSE88-A29034

Parallel Multigrid Algorithms Implemented on Memory-Coupled Multiprocessors

H. Finnemann, J. Volkert

Nuclear Science and Engineering / Volume 100 / Number 3 / November 1988 / Pages 226-236

Technical Paper / dx.doi.org/10.13182/NSE88-A29035

On the Application of Runge-Kutta Methods to Transport Calculations

Paul Nelson, James Jeffery

Nuclear Science and Engineering / Volume 100 / Number 3 / November 1988 / Pages 237-247

Technical Paper / dx.doi.org/10.13182/NSE88-A29036

The Intelligent Random Number Technique in MCNP

Thomas E. Booth

Nuclear Science and Engineering / Volume 100 / Number 3 / November 1988 / Pages 248-254

Technical Paper / dx.doi.org/10.13182/NSE88-A29037

Neutronics Methods for Thermal Radiative Transfer

Edward W. Larsen

Nuclear Science and Engineering / Volume 100 / Number 3 / November 1988 / Pages 255-259

Technical Paper / dx.doi.org/10.13182/NSE88-A29038

Two-Dimensional Calculation of Neutron Flux and Power Distribution in the Fuel Assembly of a Light Water Reactor

Zhao Chunlei, Xie Zhongsheng, Yin Banghua

Nuclear Science and Engineering / Volume 100 / Number 3 / November 1988 / Pages 260-268

Technical Paper / dx.doi.org/10.13182/NSE88-A29039

Control Rod Heterogeneity Effects in Liquid-Metal Fast Breeder Reactors: Method Developments and Experimental Validation

M. Carta, G. Granget, G.Palmiotti, M. Salvatores ,R. Soule

Nuclear Science and Engineering / Volume 100 / Number 3 / November 1988 / Pages 269-276

Technical Paper / dx.doi.org/10.13182/NSE88-A29040

Core Design Aspects of SNR-2

Udo K. Wehmann

Nuclear Science and Engineering / Volume 100 / Number 3 / November 1988 / Pages 277-282

Technical Paper / dx.doi.org/10.13182/NSE88-A29041

Status of Axial Heterogeneous Liquid-Metal Fast Breeder Reactor Core Design Studies and Research and Development

Hiroshi Nakagawa , Tatsutoshi Inagaki, Hirotaka Yoshimi , Keisho Shirakata, Yoshio Watari, Masao Suzuki, Kotaro Inoue, Takanobu Kamei

Nuclear Science and Engineering / Volume 100 / Number 3 / November 1988 / Pages 283-295

Technical Paper / dx.doi.org/10.13182/NSE88-A29042

Physics Methods for Calculating Light Water Reactor Increased Performances

Cl. Vandenberg , A. Charlier

Nuclear Science and Engineering / Volume 100 / Number 3 / November 1988 / Pages 296-304

Technical Paper / dx.doi.org/10.13182/NSE88-A29043

Validation of the Pressurized Water Reactor Core Analysis System SEANAP-86 with Measurements in Tests and Operation

C.Ahnert, J. M. Aragonés , A. Crespo, A. Labay, J. R. León, A. I. Alvarez

Nuclear Science and Engineering / Volume 100 / Number 3 / November 1988 / Pages 305-313

Technical Paper / dx.doi.org/10.13182/NSE88-A29044

Validation of Neutronic Codes for Distorted Core Configurations with the SNEAK-12 Critical Assemblies

Georg Henneges

Nuclear Science and Engineering / Volume 100 / Number 3 / November 1988 / Pages 314-323

Technical Paper / dx.doi.org/10.13182/NSE88-A29045

Testing and Applications of the QPANDA Nodal Model

K. S. Smith, K. R. Rempe

Nuclear Science and Engineering / Volume 100 / Number 3 / November 1988 / Pages 324-331

Technical Paper / dx.doi.org/10.13182/NSE88-A29046

ILLICO-HO: A Self-Consistent Higher Order Coarse-Mesh Nodal Method

Abderrafi M. Ougouag , Hrabri L. Rajic

Nuclear Science and Engineering / Volume 100 / Number 3 / November 1988 / Pages 332-341

Technical Paper / dx.doi.org/10.13182/NSE100-332

CASMO-3: New Features, Benchmarking, and Advanced Applications

Malte Edenius, Ake Ahlin

Nuclear Science and Engineering / Volume 100 / Number 3 / November 1988 / Pages 342-351

Technical Paper / dx.doi.org/10.13182/NSE88-A29048

APOLLO II: A User-Oriented, Portable, Modular Code for Multigroup Transport Assembly Calculations

Richard Sanchez, Jacques Mondot, arko Stankovski, Antoine Cossic, Igor Zmijarevic

Nuclear Science and Engineering / Volume 100 / Number 3 / November 1988 / Pages 352-362

Technical Paper / dx.doi.org/10.13182/NSE88-3

The DIT Nuclear Fuel Assembly Physics Design Code

Alf Jonsson

Nuclear Science and Engineering / Volume 100 / Number 3 / November 1988 / Pages 363-374

Technical Paper / dx.doi.org/10.13182/NSE88-A29050