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Home / Publications / Journals / Nuclear Science and Engineering / Volume 85 / Number 1

Volume 85

Number 1

Table of Contents
Management of Plutonium Contaminated Waste(Don E. Ferguson)
Reply to ‘On the Use of First-Order Perturbation Theory in Interface Shift Problems,’(G. C. POMRANING, F. RAHNEMA)
Measurement of the 242mAm Neutron Fission Cross Section(J. W. T. DABBS et al.)
The Use of Neutronic Fluctuations to Locate a Vibrating Control Rod in a Pressurized Water Reactor Model(S. J. LEE, R. W. ALBRECHT)

A Simplified Finite Element Model for Fully Developed Axial Turbulent Flow in Rod Bundles

M. Abdelghany, M. C. Roco, R. Eichhorn

Nuclear Science and Engineering / Volume 85 / Number 1 / September 1983 / Pages 1-16

Technical Paper / dx.doi.org/10.13182/NSE83-A17146

Observation of Ionic Sodium Uranate Precursors in a Laser Simulation of the Conditions Inside the Bubble Formed in an HCDA of an LMFBR

William A. Zanotelli, Stephen M. Craven, Garry D. Miller, William E. Moddeman, Frank Novak, David M. Hercules

Nuclear Science and Engineering / Volume 85 / Number 1 / September 1983 / Pages 17-25

Technical Paper / dx.doi.org/10.13182/NSE83-A17147

Application of the Image Method to Thermal Neutron Leakage Problems

D. Ingman, E. Taviv

Nuclear Science and Engineering / Volume 85 / Number 1 / September 1983 / Pages 26-35

Technical Paper / dx.doi.org/10.13182/NSE83-A17148

Use of Boundary-Fitted Coordinate Transformation in Neutron Diffusion Calculations for Arbitrary Two-Dimensional Geometries

Sadao Uchikawa

Nuclear Science and Engineering / Volume 85 / Number 1 / September 1983 / Pages 36-44

Technical Paper / dx.doi.org/10.13182/NSE83-A17149

An Approximation of Gamma-Ray Buildup Factors for Two-Layer Shields

Y. Harima

Nuclear Science and Engineering / Volume 85 / Number 1 / September 1983 / Pages 45-51

Technical Note / dx.doi.org/10.13182/NSE83-A17150

Decay Heat and Decay Rate of Actinides in Highly Neutron-Irradiated Uranium Initially of High ²³⁵U Content

K. Shure

Nuclear Science and Engineering / Volume 85 / Number 1 / September 1983 / Pages 51-55

Technical Note / dx.doi.org/10.13182/NSE83-A17151

A Semianalytic Solution of the Monoenergetic Transport Equation in Cylindrical Geometry and the Derivation of Fluxes from Singular Sources

J. K. Fletcher

Nuclear Science and Engineering / Volume 85 / Number 1 / September 1983 / Pages 55-61

Technical Note / dx.doi.org/10.13182/NSE83-A17152

First-Flight Neutron Collision Probabilities in an Annular Region Containing Fuel Rods

Erkang Li

Nuclear Science and Engineering / Volume 85 / Number 1 / September 1983 / Pages 61-70

Technical Note / dx.doi.org/10.13182/NSE83-A17153

Calculational Model Based on Influence Function Method for Power Distribution and Control Rod Worth in Fast Reactors

Toshio Sanda, Kazuo Azekura

Nuclear Science and Engineering / Volume 85 / Number 1 / September 1983 / Pages 70-79

Technical Note / dx.doi.org/10.13182/NSE83-A17154

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