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Volume 111 / Number 4

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Nuclear Science and Engineering / Volume 111 / Number 4

August 1992

Analytical Method for Processing Neutron Multigroup Transfer Cross Sections

R. Ofek, M. Segev

Nuclear Science and Engineering / Volume 111 / Number 4 / Pages 319-344

August 1992

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Contributorn Slowing-Down Theory

Mark L. Williams, Harish Manohara

Nuclear Science and Engineering / Volume 111 / Number 4 / Pages 345-367

August 1992

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Product Yields of 235U, 238U, 237Np, and 239Pu by Photofission Reactions with 20-, 30-, and 60-MeV Bremsstrahlung

Takeshi Kase, Akira Yamadera, Takashi Nakamura, Seiichi Shibata, Ichiro Fujiwara

Nuclear Science and Engineering / Volume 111 / Number 4 / Pages 368-378

August 1992

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Fission Fragment Transport Effects on Heat Transfer in Fissioning Gases

Yoichi Watanabe, Jacob Appelbaum

Nuclear Science and Engineering / Volume 111 / Number 4 / Pages 379-390

August 1992

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Measurement of Neutron Activation Cross Sections of Energy up to 40 MeV Using Semimonoenergetic p-Be Neutrons

Yoshitomo Uwamino, Hiroshi Sugita, Yuhri Kondo, Takashi Nakamura

Nuclear Science and Engineering / Volume 111 / Number 4 / Pages 391-403

August 1992

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Evaluation of the Unresolved Resonance Range of 238U 4-+n, Part II: Differential Data Tests

F. H. Fröhner

Nuclear Science and Engineering / Volume 111 / Number 4 / Pages 404-414

August 1992

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High-Resolution Fission Cross-Section Measurements of 235U and 239Pu

L. W. Weston, J. H. Todd

Nuclear Science and Engineering / Volume 111 / Number 4 / Pages 415-421

August 1992

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Six-Group Decomposition of Composite Delayed Neutron Spectra from 235U Fission

M. F. Villani, G. P. Couchell, M. H. Haghighi, D. J. Pullen, W. A. Schier

Nuclear Science and Engineering / Volume 111 / Number 4 / Pages 422-432

August 1992

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Improved Techniques of Analog and Digital Dynamic Compensation for Delayed Self-Powered Neutron Detectors

Dietrich Hoppe, Rainer Maletti

Nuclear Science and Engineering / Volume 111 / Number 4 / Pages 433-436

August 1992

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