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Volume 85

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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

Number 2

Table of Contents
The Necessity for Nuclear Power(Myron S. McCay)
Born Secret-The H-Bomb, The Progressive Case and National(Conrad V. Chester)
Status of USA Nuclear Reactor Pressure Vessel Surveillance for Radiation Effects (ASTM STP 784)(R. D. Cheverton)
Comments on the R-Parameter Formalism for Neutron-Induced Gamma-Ray Production(S. T. Perkins)
Comments on the R-Parameter Formalism for Neutron-Induced Gamma-Ray Production(S. T. Perkins)
Response to “Comments on the R-Parameter Formalism for Neutron-Induced Gamma-Ray Production”(D. Hermsdorf, D. Seeliger)

Validated Deep-Penetration, Air-Over-Ground, Neutron/Gamma-Ray Transport

W. E. Loewe, W. A. Turin, C. W. Pollock, A. C. Springer, B. L. Richardson

Nuclear Science and Engineering / Volume 85 / Number 2 / October 1983 / Pages 87-115

Technical Paper / dx.doi.org/10.13182/NSE83-A27418

Flux-Limited Diffusion and Fokker-Planck Equations

G. C. Pomraning

Nuclear Science and Engineering / Volume 85 / Number 2 / October 1983 / Pages 116-126

Technical Paper / dx.doi.org/10.13182/NSE83-A27419

A Proposed Technique for Producing High-Purity Monoenergetic Neutron Beams Between 100 eV and 2.5 keV for Nuclear Research

A. J. Mill

Nuclear Science and Engineering / Volume 85 / Number 2 / October 1983 / Pages 127-132

Technical Paper / dx.doi.org/10.13182/NSE83-A27420

Basic Principles for Developing Equations for Heterogeneous Reactors—A Modification of the Homogenization Method

N. I. Laletin

Nuclear Science and Engineering / Volume 85 / Number 2 / October 1983 / Pages 133-138

Technical Paper / dx.doi.org/10.13182/NSE83-A27421

Aggregate Delayed Neutron Intensities and Spectra Using Augmented ENDF/B-V Precursor Data

T. R. England, W. B. Wilson, R. E. Schenter, F. M. Mann

Nuclear Science and Engineering / Volume 85 / Number 2 / October 1983 / Pages 139-155

Technical Paper / dx.doi.org/10.13182/NSE83-A27422

Malfunction Isolation in Linear Stochastic Systems: Application to Nuclear Power Plants

Yakov Ben-Haim

Nuclear Science and Engineering / Volume 85 / Number 2 / October 1983 / Pages 156-166

Technical Paper / dx.doi.org/10.13182/NSE83-A27423

On The Neutron Noise Diagnostics of Pressurized Water Reactor Control Rod Vibrations. I. Periodic Vibrations

I. Pázsit and O. Glöckler

Nuclear Science and Engineering / Volume 85 / Number 2 / October 1983 / Pages 167-177

Technical Paper / dx.doi.org/10.13182/NSE83-A27424

Asymmetric Effects on Vibrations of a Cylinder in Turbulent Parallel Flows

Y. T. Fung

Nuclear Science and Engineering / Volume 85 / Number 2 / October 1983 / Pages 178-187

Technical Paper / dx.doi.org/10.13182/NSE83-A27425

Boundary Perturbation Theory for Nonanalytic Perturbations

G. C. Pomraning

Nuclear Science and Engineering / Volume 85 / Number 2 / October 1983 / Pages 188-191

Technical Note / dx.doi.org/10.13182/NSE83-A27426

A Simplified Perturbation Model for Calculation of Few-Group Cross Sections and Reaction Rates

Anthony N. Sinclair, John C. Lee

Nuclear Science and Engineering / Volume 85 / Number 2 / October 1983 / Pages 191-196

Technical Note / dx.doi.org/10.13182/NSE83-A27427

Number 3

Table of Contents
Computer Code Abstract: MAXWEL(B. L. Lathrop, B. R. Wienke)

Transient Two-Phase Two-Component Water-Steam-Air Flow

N. I. Kolev

Nuclear Science and Engineering / Volume 85 / Number 3 / November 1983 / Pages 209-220

Technical Paper / dx.doi.org/10.13182/NSE83-A17313

The Transport of Radioactive Corrosion Products in High-Temperature Water—III. The Interaction of Dissolved Cobalt with Heated Surfaces

D. H. Lister, S. A. Kushneriuk, R. H. Campbell

Nuclear Science and Engineering / Volume 85 / Number 3 / November 1983 / Pages 221-232

Technical Paper / dx.doi.org/10.13182/NSE83-A17314

On the Theory of Transport of Fluids in Fractured Media for the Safety Analysis of a Nuclear Waste Repository

Nimai C. Mukhopadhyay

Nuclear Science and Engineering / Volume 85 / Number 3 / November 1983 / Pages 233-244

Technical Paper / dx.doi.org/10.13182/NSE83-A17315

Calibration of Self-Powered Neutron Detectors

M. F. Sulcoski, H. D. Warren

Nuclear Science and Engineering / Volume 85 / Number 3 / November 1983 / Pages 245-250

Technical Paper / dx.doi.org/10.13182/NSE83-A17316

Neutron Capture and Fission Cross Section of ²⁴³Am in the Energy Range from 5 to 250 keV

K. Wisshak, F. Käppeler

Nuclear Science and Engineering / Volume 85 / Number 3 / November 1983 / Pages 251-260

Technical Paper / dx.doi.org/10.13182/NSE83-A17317

The Total Neutron Cross Sections of ²⁴⁹Bk and ²⁴⁹Cf Below 100 eV

Richard W. Benjamin, John A. Harvey, Nathaniel W. Hill, Madhu S. Pandey, Robert F. Carlton

Nuclear Science and Engineering / Volume 85 / Number 3 / November 1983 / Pages 261-270

Technical Paper / dx.doi.org/10.13182/NSE83-A17318

The Fission Cross Section of ²³⁷Np Relative to ²³⁵U from 0.1 to 9.4 MeV

J. W. Meadows

Nuclear Science and Engineering / Volume 85 / Number 3 / November 1983 / Pages 271-279

Technical Paper / dx.doi.org/10.13182/NSE83-A17319

Measurements of Fast Neutron Number Albedos for Double-Layered Slabs

Kazuo Shin, Hiroyuki Nakano, Tomonori Hyodo

Nuclear Science and Engineering / Volume 85 / Number 3 / November 1983 / Pages 280-288

Technical Paper / dx.doi.org/10.13182/NSE83-A17320

The Finite Element Response Matrix Method

Horacio Nakata, William R. Martin

Nuclear Science and Engineering / Volume 85 / Number 3 / November 1983 / Pages 289-305

Technical Paper / dx.doi.org/10.13182/NSE83-A17321

Multigroup Transfer Matrices for Charged-Particle and Neutron-Induced Reactions—Part III: Energy Conservation and Local Deposition

S. T. Perkins, R. J. Howerton

Nuclear Science and Engineering / Volume 85 / Number 3 / November 1983 / Pages 306-313

Technical Paper / dx.doi.org/10.13182/NSE83-A17322

Measurement of the Subthreshold Neutron-Induced Fission Cross Section of ²⁴⁰Pu Relative to ²³⁵U from 5 to 300 keV

J. W. Behrens

Nuclear Science and Engineering / Volume 85 / Number 3 / November 1983 / Pages 314-318

Technical Note / dx.doi.org/10.13182/NSE83-A17323

Number 4

Table of Contents
Nuclear Power Materials and Applications(P. F. Pasqua)
Generalized Perturbation Formula Versus Classic Perturbation Formula(J. V. Muralidhar Rao)
Reply to “Generalized Perturbation Formula Versus Classic Perturbation Formula”(G. C. Pomraning)

Neutron Signal Multiplet Analysis for the Mass Determination of Spontaneous Fission Isotopes

R. Dierckx and W. Hage

Nuclear Science and Engineering / Volume 85 / Number 4 / December 1983 / Pages 325-338

Technical Paper / dx.doi.org/10.13182/NSE83-3

Evaluation of the Yields from the Radiolysis of Water in Boiling Water Reactors by Neutron and Gamma Radiation

Eishi Ibe, Shunsuke Uchida

Nuclear Science and Engineering / Volume 85 / Number 4 / December 1983 / Pages 339-349

Technical Paper / dx.doi.org/10.13182/NSE83-A18381

Neutron Capture Cross Sections and Resonances of Iodine-127 and Iodine-129

R. L. Macklin

Nuclear Science and Engineering / Volume 85 / Number 4 / December 1983 / Pages 350-361

Technical Paper / dx.doi.org/10.13182/NSE83-A18382

Neutron Noise Transmission Characteristics of Multiplying Media and Neutron Noise Source Localization in Liquid-Metal Fast Breeder Reactors by Using the Neutron Wave Propagation Technique

T. M. John, Om Pal Singh

Nuclear Science and Engineering / Volume 85 / Number 4 / December 1983 / Pages 362-370

Technical Paper / dx.doi.org/10.13182/NSE83-A18383

Comparison of Measured and Calculated Radiation Transport in Air-Over-Ground Geometry to 1.6 km from a Fission Source

A. H. Kazi, C. R. Heimbach, R. C. Harrison

Nuclear Science and Engineering / Volume 85 / Number 4 / December 1983 / Pages 371-386

Technical Paper / dx.doi.org/10.13182/NSE83-A18384

Mixing of Molten Core Material and Water

S. G. Bankoff, S. H. Han

Nuclear Science and Engineering / Volume 85 / Number 4 / December 1983 / Pages 387-395

Technical Paper / dx.doi.org/10.13182/NSE83-A18385

Real-Time Simulation of the Transient Behavior of Local and Global Pressurized Water Reactor Core and Plant Parameters

A. Hoeld, O. Lupas

Nuclear Science and Engineering / Volume 85 / Number 4 / December 1983 / Pages 396-417

Technical Paper / dx.doi.org/10.13182/NSE83-A18386

Significant Differences in Reported Gamma-Ray Buildup Factors

A. Natarajan, K. V. Subbaiah, D. V. Gopinath

Nuclear Science and Engineering / Volume 85 / Number 4 / December 1983 / Pages 418-422

Technical Note / dx.doi.org/10.13182/NSE83-A18387

Exploitation of Bragg Cutoff Phenomenon for Improved Albedo in Beryllium-Reflected Minimum Critical Mass Systems

P. K. Job, M. Srinivasan

Nuclear Science and Engineering / Volume 85 / Number 4 / December 1983 / Pages 422-425

Technical Note / dx.doi.org/10.13182/NSE83-A18388

A Simple Semi-Empirical Formula for the Incoherent Scattering Cross Sections for Gamma Rays in the 300- to 1250-keV Energy Region

T. K. Umesh, C. Ranganathaiah, B. Sanjeevaiah

Nuclear Science and Engineering / Volume 85 / Number 4 / December 1983 / Pages 426-427

Technical Note / dx.doi.org/10.13182/NSE83-A18389

An Evaluation of Two Aggregates for Use in a Concrete Reactor Shield

F. U. Ahmed, M. A. Rahman, S. R. Husain, M. M. Rahman

Nuclear Science and Engineering / Volume 85 / Number 4 / December 1983 / Pages 427-430

Technical Note / dx.doi.org/10.13182/NSE83-A18390