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Home / Publications / Journals / Nuclear Science and Engineering / Volume 107 / Number 1

Volume 107

Number 1

Reaction Cross Sections on Carbon for Neutron Energies from 11.5 to 19 MeV

B. Antolković, G. Dietze, H. Klein

Nuclear Science and Engineering / Volume 107 / Number 1 / January 1991 / Pages 1-21

Technical Paper / dx.doi.org/10.13182/NSE91-A23777

Determination of Neutron-Induced Alpha-Particle Cross Sections on Carbon Using the Response of a Liquid Scintillation Detector

H. J. Brede, G. Dietze, H. Klein, H. Schölermann

Nuclear Science and Engineering / Volume 107 / Number 1 / January 1991 / Pages 22-34

Technical Paper / dx.doi.org/10.13182/NSE91-A23778

252Cf-Source-Driven Noise Measurements of Subcriticality for a Slab Tank of Aqueous Pu-U Nitrate

J. T. Mihalczo, E. D. Blakeman, G. E. Ragan, R. C. Kryter, H. Seino, R. C. Robinson

Nuclear Science and Engineering / Volume 107 / Number 1 / January 1991 / Pages 35-57

Technical Paper / dx.doi.org/10.13182/NSE91-A23779

Comparison of Vectorization Methods Used in a Monte Carlo Code

Masayuki Nakagawa, Takamasa Mori, Makoto Sasaki

Nuclear Science and Engineering / Volume 107 / Number 1 / January 1991 / Pages 58-66

Technical Paper / dx.doi.org/10.13182/NSE91-A23780

Study of Slab Transmission and Reflection

C. M. Eisenhauer

Nuclear Science and Engineering / Volume 107 / Number 1 / January 1991 / Pages 67-81

Technical Paper / dx.doi.org/10.13182/NSE91-A23781

Physics of the Conceptual Design of Intense Steady Neutron Sources

Felix C. Difilippo

Nuclear Science and Engineering / Volume 107 / Number 1 / January 1991 / Pages 82-98

Technical Note / dx.doi.org/10.13182/NSE91-A23782

 

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