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Volume 111

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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

Table of Contents

Nuclear Science and Engineering / Volume 111 / Number 1

May 1992

Canada Deuterium Uranium Reactor Design Optimization Using Three-Dimensional Generalized Perturbation Theory

D. Rozon, M. Beaudet

Nuclear Science and Engineering / Volume 111 / Number 1 / Pages 1-20

May 1992

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Reconstruction of Pin Power and Burnup Characteristics from Nodal Calculations in Hexagonal-Z Geometry

W. S. Yang, P. J. Finck, H. Khalil

Nuclear Science and Engineering / Volume 111 / Number 1 / Pages 21-33

May 1992

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A Spectral Nodal Method for One-Group X,Y-Geometry Discrete Ordinates Problems

Ricardo C. De Barros, Edward W. Larsen

Nuclear Science and Engineering / Volume 111 / Number 1 / Pages 34-45

May 1992

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A Massively Parallel Discrete Ordinates Response Matrix Method for Neutron Transport

U. R. Hanebutte, E. E. Lewis

Nuclear Science and Engineering / Volume 111 / Number 1 / Pages 46-56

May 1992

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An Iterative Algorithm for Solving the Multidimensional Neutron Diffusion Nodal Method Equations on Parallel Computers

Bernadette L. Kirk, Yousry Y. Azmy

Nuclear Science and Engineering / Volume 111 / Number 1 / Pages 57-65

May 1992

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Estimation of Neutron Flux and Xenon Distributions via Observer-Based Control Theory

Young Ho Park, Nam Zin Cho

Nuclear Science and Engineering / Volume 111 / Number 1 / Pages 66-81

May 1992

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Ex-Vessel Releases of Radionuclides During Molten Core/Concrete Interactions in Severe Light Water Reactor Accidents

Min Lee, Jan Sea Wu

Nuclear Science and Engineering / Volume 111 / Number 1 / Pages 82-101

May 1992

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Time-Dependent Monte Carlo Calculations of the Oak Ridge Electron Linear Accelerator Target Neutron Spectrum

S. N. Cramer, F. G. Perey

Nuclear Science and Engineering / Volume 111 / Number 1 / Pages 102-111

May 1992

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Table of Contents

Nuclear Science and Engineering / Volume 111 / Number 2

June 1992

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