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Volume 84

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Nuclear Science and Engineering / Volume 84 / Number 4

August 1983

Boundary Perturbation Theory for Inhomogeneous Transport Equations

F. Rahnema, G. C. Pomraning

Nuclear Science and Engineering / Volume 84 / Number 4 / Pages 313-319

August 1983

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The Radioactive Decay of 44gSc and 44mSc

Guanjun Yuan, Shiping Chen, Benhua Han, Ling Zhou, Peikun Weng

Nuclear Science and Engineering / Volume 84 / Number 4 / Pages 320-323

August 1983

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Lumped Fission Product Neutron Cross Sections Based on ENDF/B-V for Fast Reactor Analysis

J. R. Liaw, H. Henryson II

Nuclear Science and Engineering / Volume 84 / Number 4 / Pages 324-336

August 1983

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Neutron Streaming Through a Slit and Duct in Concrete Shields and Comparison with a Monte Carlo Analysis

Hiroyuki Hashikura, Hideshi Fukumoto, Yoshiaki Oka, Masatsugu Akiyama, Shigehiro An

Nuclear Science and Engineering / Volume 84 / Number 4 / Pages 337-344

August 1983

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Acoustic Mismatch Theory for Heat Flow Across Fuel-Cladding Interfaces in Fast Reactors

G. Dharmadurai

Nuclear Science and Engineering / Volume 84 / Number 4 / Pages 345-349

August 1983

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Two-Dimensional Numerical Modeling of Nonisothermal Flows for Unsteady Thermal-Hydraulic Analysis

P. L. Viollet, J. P. Benque, J. Goussebaile

Nuclear Science and Engineering / Volume 84 / Number 4 / Pages 350-372

August 1983

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Pattern Recognition Techniques Applied to Acoustic Detection of Liquid-Metal Fast Breeder Reactor Cooling Defects

M. Brunet, B. Dubuisson

Nuclear Science and Engineering / Volume 84 / Number 4 / Pages 373-379

August 1983

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Relation Between Koebke's Equivalence Theory and Benoist's Cell Homogenization Procedure

S. V. G. Menon, D. C. Sahni

Nuclear Science and Engineering / Volume 84 / Number 4 / Pages 380-383

August 1983

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An Interpolation Method for the Transport Theory and Its Application in Fusion Neutronics Analysis

Jungchung Jung

Nuclear Science and Engineering / Volume 84 / Number 4 / Pages 383-388

August 1983

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On Zero Variance Monte Carlo Path-Stretching Schemes

Iván Lux

Nuclear Science and Engineering / Volume 84 / Number 4 / Pages 388-390

August 1983

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A Fast Nodal Neutron Diffusion Method for Cartesian Geometry

Mihály Makai, Claude Maeder

Nuclear Science and Engineering / Volume 84 / Number 4 / Pages 390-395

August 1983

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Gamma-Ray Production Due to Neutron Interactions with Copper for Neutron Energies Between 0.7 and 10.5 MeV

G. G. Slaughter, J. K. Dickens

Nuclear Science and Engineering / Volume 84 / Number 4 / Pages 395-406

August 1983

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Fast Breeder Reactors

Neil Todreas, Michael Driscoll

Nuclear Science and Engineering / Volume 84 / Number 4 / Page 407

August 1983

Table of Contents

Nuclear Science and Engineering / Volume 84 / Number 1

May 1983

Measurement of the 242mAm Neutron Fission Cross Section

J. W. T. Dabbs, C. E. Bemis, Jr., S. Raman, R. J. Dougan, R. W. Hoff

Nuclear Science and Engineering / Volume 84 / Number 1 / Pages 1-11

May 1983

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Neutron-Induced Gamma-Ray Production in 57Fe for Incident Neutron Energies Between 0.16 and 21 MeV

Z. W. Bell, J. K. Dickens, D. C. Larson, J. H. Todd

Nuclear Science and Engineering / Volume 84 / Number 1 / Pages 12-32

May 1983

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The Solution of the Multigroup Neutron Transport Equation Using Spherical Harmonics

J. K. Fletcher

Nuclear Science and Engineering / Volume 84 / Number 1 / Pages 33-46

May 1983

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Thermal Performance Modeling of Sphere-Pac Mixed Carbide Fast Reactor Fuel

M. J. Ades, K. L. Peddicord, S. D. Montgomery

Nuclear Science and Engineering / Volume 84 / Number 1 / Pages 47-58

May 1983

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Real-Time Nonlinear Estimation of Fuel-Clad Gap Conductance

J. Louis Tylee

Nuclear Science and Engineering / Volume 84 / Number 1 / Pages 58-61

May 1983

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