American Nuclear Society
Home

Home / Publications / Journals / Nuclear Science and Engineering / Volume 96 / Number 3

Volume 96

Number 3

A Critique of Three Methodologies for Estimating the Probability of Containment Failure Due to Steam Explosions

Marshall Berman

Nuclear Science and Engineering / Volume 96 / Number 3 / July 1987 / Pages 173-191

Technical Paper / dx.doi.org/10.13182/NSE87-A16380

A Rigorous Pole Representation of Multilevel Cross Sections and Its Practical Applications

R. N. Hwang

Nuclear Science and Engineering / Volume 96 / Number 3 / July 1987 / Pages 192-209

Technical Paper / dx.doi.org/10.13182/NSE87-A16381

Calculation of Capture Cross Sections and Gamma-Ray Spectra Following the Interaction of Neutrons with 181Ta and 197Au

Nobuhiro Yamamuro, Kazuyuki Udagawa, Toshihiro Natsume

Nuclear Science and Engineering / Volume 96 / Number 3 / July 1987 / Pages 210-220

Technical Paper / dx.doi.org/10.13182/NSE87-A16382

On the Generalized Neutron Noise Formulation with Application to a Coupled Core Reactor

Shyn-Jen Lee

Nuclear Science and Engineering / Volume 96 / Number 3 / July 1987 / Pages 221-233

Technical Paper / dx.doi.org/10.13182/NSE87-A16383

Neutron Transport Theory in a Ring Reactor

M. M. R. Williams

Nuclear Science and Engineering / Volume 96 / Number 3 / July 1987 / Pages 234-240

Technical Note / dx.doi.org/10.13182/NSE87-A16384

A Comparison of Gamma-Ray Buildup Factors for Low-Z Material and for Low Energies Using Discrete Ordinates and Point Monte Carlo Methods

Yoshiko Harima, Hideo Hirayama, Toshio Ishikawa, Yukio Sakamoto, Shun-ich Tanaka

Nuclear Science and Engineering / Volume 96 / Number 3 / July 1987 / Pages 241-252

Technical Note / dx.doi.org/10.13182/NSE87-A16385

Effect of a Mixing Vane in a Three-Subchannel Simulated Fuel Rod Bundle Using a Gamma Camera

Alireza Sedaghat, Robert Macduff, Frank Castellana

Nuclear Science and Engineering / Volume 96 / Number 3 / July 1987 / Pages 253-259

Technical Note / dx.doi.org/10.13182/NSE87-A16386