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Volume 136

Number 3

Measurement and Analysis of Capture Reaction Rate of 237Np in Various Thermal Neutron Fields by Critical Assembly and Heavy Water Thermal Neutron Facility of Kyoto University

Tomohiko Iwasaki, Toshimitu Horiuchi, Daisuke Fujiwara, Hironobu Unesaki, Seiji Shiroya, Masatoshi Hayashi, Hiroshi Nakamura, Takanori Kitada, Nobuo Shinohara

Nuclear Science and Engineering / Volume 136 / Number 3 / November 2000 / Pages 321-339

Technical Paper / dx.doi.org/10.13182/NSE00-A2162

Neutron Cross-Section Evaluations for 238U up to 150 MeV

A. V. Ignatyuk, V. P. Lunev, Yu. N. Shubin, E. V. Gai, N. N. Titarenko, A. Ventura, W. Gudowski

Nuclear Science and Engineering / Volume 136 / Number 3 / November 2000 / Pages 340-356

Technical Paper / dx.doi.org/10.13182/NSE00-A2163

Photofission Cross Sections for 237Np in the Energy Interval from 5.27 to 10.83 MeV

L. P. Geraldo, R. Semmler, O. L. Gonçalez, J. Mesa, J. D. T. Arruda-Neto, F. Garcia, O. Rodriguez

Nuclear Science and Engineering / Volume 136 / Number 3 / November 2000 / Pages 357-362

Technical Paper / dx.doi.org/10.13182/NSE00-A2164

Numerical and Experimental Study of Large Steam-Air Bubbles Injected in a Water Pool

Markus Meier, George Yadigaroglu, Michele Andreani

Nuclear Science and Engineering / Volume 136 / Number 3 / November 2000 / Pages 363-375

Technical Paper / dx.doi.org/10.13182/NSE00-A2165

Modeling of Steam-Clad Interactions Under Severe Accident Conditions in Nuclear Power Light Water Reactors

M. A. Shinaishin, M. A. Abolfadl, A. S. Khedr, M. M. Kamel

Nuclear Science and Engineering / Volume 136 / Number 3 / November 2000 / Pages 376-387

Technical Paper / dx.doi.org/10.13182/NSE00-A2166

The Third Basis Function Relevant to an Approximate Model of Neutral Particle Transport in Ducts

Roberto D. M. Garcia, Shizuca Ono, Wilson J. Vieira

Nuclear Science and Engineering / Volume 136 / Number 3 / November 2000 / Pages 388-398

Technical Paper / dx.doi.org/10.13182/NSE00-1

Adaptive Importance Sampling with a Rapidly Varying Importance Function

Thomas E. Booth

Nuclear Science and Engineering / Volume 136 / Number 3 / November 2000 / Pages 399-408

Technical Note / dx.doi.org/10.13182/NSE00-A2168

Semianalytical Procedures for Obtaining Low-Order Non-Equally-Probable Step-Function Representations in Multigroup Monte Carlo

Li Mao, J. C. Nimal

Nuclear Science and Engineering / Volume 136 / Number 3 / November 2000 / Pages 409-414

Technical Note / dx.doi.org/10.13182/NSE00-A2169

Experimental Determination of the 236U(nth, f) Cross Section

Cyriel Wagemans, Olivier Serot, Peter Geltenbort, Oliver Zimmer

Nuclear Science and Engineering / Volume 136 / Number 3 / November 2000 / Pages 415-418

Technical Note / dx.doi.org/10.13182/NSE00-A2170