Home / Publications / Journals / Nuclear Science and Engineering / Volume 76

Volume 76

Number 1

Table of Contents
SAFE(J. M. Kontoleon)
Comments on “The Determination of Time Constants of Reactor Pressure and Temperature Sensors: The Dynamic Data System Method”(James A. Mullens)
Response to “Comments on ‘The Determination of Time Constants of Reactor Pressure and Temperature Sensors: The Dynamic Data System Method'"(S. M. Wu)
Uranium Enrichment(Manson Benedict)
A Methodology for Calculating the Expected Number of Failures of a System Undergoing a Phased Mission(D. F. Montague, J. B. Fussell)

Comparison of the Order of Approximation in Several Spatial Difference Schemes for the Discrete-Ordinates Transport Equation in One-Dimensional Plane Geometry

Suresh M. Lee, R. Vaidyanathan

Nuclear Science and Engineering / Volume 76 / Number 1 / October 1980 / Pages 1-9

Technical Paper / dx.doi.org/10.13182/NSE80-A19287

Generalized Quasi-Static Method for Nuclear Reactor Space-Time Kinetics

J. Devooght, E. Mund

Nuclear Science and Engineering / Volume 76 / Number 1 / October 1980 / Pages 10-17

Technical Paper / dx.doi.org/10.13182/NSE80-A19288

Transport of Thermal Neutrons in D₂O in the Temperature Range 5 to 60°C Based on a New Scattering Kernel

R. M. Bansal, S. P. Tewari, L. S. Kothari

Nuclear Science and Engineering / Volume 76 / Number 1 / October 1980 / Pages 18-29

Technical Paper / dx.doi.org/10.13182/NSE80-A19289

Measurement of Cross Sections for the ⁶³Cu(n, α)⁶⁰Co Reaction from Threshold to 10 MeV

G. Winkler, Donald L. Smith, James W. Meadows

Nuclear Science and Engineering / Volume 76 / Number 1 / October 1980 / Pages 30-42

Technical Paper / dx.doi.org/10.13182/NSE80-A19290

Cross-Section Measurement for the ⁵²Cr(n,p)⁵²V Reaction Near Threshold

Donald L. Smith, James W. Meadows

Nuclear Science and Engineering / Volume 76 / Number 1 / October 1980 / Pages 43-48

Technical Paper / dx.doi.org/10.13182/NSE80-A19291

The Foil Thickness Correction in Measurements and the Discrepancy

J. W. Boldeman, J. Fréhaut

Nuclear Science and Engineering / Volume 76 / Number 1 / October 1980 / Pages 49-52

Technical Paper / dx.doi.org/10.13182/NSE80-A19292

A Multiregion Calculation in the Theory of Neutron Diffusion

R. D. M. Garcia, C. E. Siewert

Nuclear Science and Engineering / Volume 76 / Number 1 / October 1980 / Pages 53-56

Technical Note / dx.doi.org/10.13182/NSE80-A19293

Near-Equilibrium Measurements of Delayed Neutron Spectra from Fast Fission of Plutonium-240

Patrick J. Grant, Gene L. Woodruff

Nuclear Science and Engineering / Volume 76 / Number 1 / October 1980 / Pages 56-61

Technical Note / dx.doi.org/10.13182/NSE80-A19294

Activation Cross Sections for ⁶⁶Zn(n,p)⁶⁶Cu

Donald L. Smith, James W. Meadows

Nuclear Science and Engineering / Volume 76 / Number 1 / October 1980 / Pages 61-66

Technical Note / dx.doi.org/10.13182/NSE80-A19295

Gamma-Ray Buildup Factors for Concrete Slab Shields Under Slant Incidence Conditions

E. M. Fournie, A. B. Chilton

Nuclear Science and Engineering / Volume 76 / Number 1 / October 1980 / Pages 66-69

Technical Note / dx.doi.org/10.13182/NSE80-2

Measurements of Structural Material Capture to Uranium-235 Fission Rate Ratios in an Intermediate Spectrum Assembly

P. Azzoni, V. Benzi, A. Salomoni, P. L. Chiodi, C. Giuliani, R. Marvasi, S. Guardini, S. Tassan

Nuclear Science and Engineering / Volume 76 / Number 1 / October 1980 / Pages 70-77

Technical Note / dx.doi.org/10.13182/NSE80-A19297

Number 2

Table of Contents

Investigation of Blowdown Problems with the Computer Code DRIX-2D

H. Mösinger

Nuclear Science and Engineering / Volume 76 / Number 2 / November 1980 / Pages 89-102

Technical Paper / dx.doi.org/10.13182/NSE80-A19443

The Effect of Dispersion and Spheroidization Treatment of δ-ZrH₂ on Creep and Corrosion Resistance of Zircaloy

Michiko Hamasaki, Shi-Chien Lin, Yii-Der Chuang

Nuclear Science and Engineering / Volume 76 / Number 2 / November 1980 / Pages 103-118

Technical Paper / dx.doi.org/10.13182/NSE80-A19444

Experiments and Analyses of Neutron and Gamma-Ray Streaming in the Cavity-Duct System of a Fast Neutron Source Reactor

Yoshiaki Oka, Ichiroh Yanagisawa, Shigehiro An, Shun-ichi Miyasaka, Tomonori Hyodo

Nuclear Science and Engineering / Volume 76 / Number 2 / November 1980 / Pages 119-136

Technical Paper / dx.doi.org/10.13182/NSE80-A19445

Parameter Determination and Application to Nuclear Model Calculations of Neutron-Induced Reactions on Yttrium and Zirconium Isotopes

E. D. Arthur

Nuclear Science and Engineering / Volume 76 / Number 2 / November 1980 / Pages 137-147

Technical Paper / dx.doi.org/10.13182/NSE80-A19446

The Neutron Capture and Fission Cross Section of Americium-241 in the Energy Range from 10 to 250 keV

K. Wisshak, F. Käppeler

Nuclear Science and Engineering / Volume 76 / Number 2 / November 1980 / Pages 148-162

Technical Paper / dx.doi.org/10.13182/NSE80-A19447

Delayed Neutron Signal Characterization in a Fast Reactor

Kenny C. Gross, Robert V. Strain

Nuclear Science and Engineering / Volume 76 / Number 2 / November 1980 / Pages 163-174

Technical Paper / dx.doi.org/10.13182/NSE80-A19448

Plane Asymmetric Cell Lattices with Superimposed Small Buckling

T. Duracz

Nuclear Science and Engineering / Volume 76 / Number 2 / November 1980 / Pages 175-180

Technical Paper / dx.doi.org/10.13182/NSE80-A19449

Treatment of Resonance Absorption in an Infinite Homogeneous Mixture Using Fourier Transforms

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

Nuclear Science and Engineering / Volume 76 / Number 2 / November 1980 / Pages 181-197

Technical Paper / dx.doi.org/10.13182/NSE80-A19450

Application of Biasing Techniques to the Contributon Monte Carlo Method

A. Dubi, S. A. W. Gerstl

Nuclear Science and Engineering / Volume 76 / Number 2 / November 1980 / Pages 198-217

Technical Paper / dx.doi.org/10.13182/NSE80-A19451

A Nodal Green's Function Method for Multidimensional Neutron Diffusion Calculations

R. D. Lawrence, J. J. Dorning

Nuclear Science and Engineering / Volume 76 / Number 2 / November 1980 / Pages 218-231

Technical Paper / dx.doi.org/10.13182/NSE80-A19452

The Determination of Coupled-Core-Reactor Kinetic Parameters Through Frequency Response

Yoshihiro Yamane, Kazuma Tanaka, Kojiro Nishina, Hajime Tamagawa, Seiji Shiroya

Nuclear Science and Engineering / Volume 76 / Number 2 / November 1980 / Pages 232-245

Technical Paper / dx.doi.org/10.13182/NSE80-A19453

An Analysis of Why Single Pressure Two-Fluid Two-Phase Unequal Velocity Model Equations Are Not Globally Hyperbolic

Robert W. Lyczkowski

Nuclear Science and Engineering / Volume 76 / Number 2 / November 1980 / Pages 246-249

Technical Note / dx.doi.org/10.13182/NSE80-A19454

A Method of Solution of the Transport Equation in Toroidal Geometry

J. K. Fletcher

Nuclear Science and Engineering / Volume 76 / Number 2 / November 1980 / Pages 249-255

Technical Note / dx.doi.org/10.13182/NSE80-A19455

An Improved Single-Parameter Escape Probability Function

D. Kwiat

Nuclear Science and Engineering / Volume 76 / Number 2 / November 1980 / Pages 255-257

Technical Note / dx.doi.org/10.13182/NSE76-255

Number 3

Table of Contents
Futher Comments on “Helium Production in Stainless Steel”(S. Ganesan)
Response to “Futher Comments on ‘Helium Production in Stainless Steel’”(B. Goel)
Advanced Mathematical Methods for Scientists and Engineers(Paul F. Zweifel)

Effective Diffusion Coefficients for Low Density Cylindrical Channels

J. L. Rowlands, C. R. Eaton

Nuclear Science and Engineering / Volume 76 / Number 3 / December 1980 / Pages 263-281

Technical Paper / dx.doi.org/10.13182/NSE80-A21317

Fundamental Mode Decay Constants for Small Two- and Three-Dimensional Pulsed Neutron Moderator Assemblies

Vinod Kumar, D. C. Sahni

Nuclear Science and Engineering / Volume 76 / Number 3 / December 1980 / Pages 282-294

Technical Paper / dx.doi.org/10.13182/NSE80-A21318

A Comparison of Maximum Likelihood and Other Estimators of Eigenvalues from Several Correlated Monte Carlo Samples

M. Beer

Nuclear Science and Engineering / Volume 76 / Number 3 / December 1980 / Pages 295-301

Technical Paper / dx.doi.org/10.13182/NSE80-A21319

A Point Detector Scoring Method Compatible with Monte Carlo Transport Calculations of Specularly Reflected Particles

Hiromasa Iida, Yasushi Seki

Nuclear Science and Engineering / Volume 76 / Number 3 / December 1980 / Pages 302-307

Technical Paper / dx.doi.org/10.13182/NSE80-A21320

A Recursive Monte Carlo Method for Estimating Importance Function Distributions in Deep-Penetration Problems

M. Goldstein, E. Greenspan

Nuclear Science and Engineering / Volume 76 / Number 3 / December 1980 / Pages 308-322

Technical Paper / dx.doi.org/10.13182/NSE80-A21321

A Simple Formula for Calculation of Prompt Neutron Yield from Spontaneous Fission of Transuranics

H. L. Pai, D. G. Andrews

Nuclear Science and Engineering / Volume 76 / Number 3 / December 1980 / Pages 323-330

Technical Paper / dx.doi.org/10.13182/NSE80-A21322

Cross-Section Measurement for the Reaction ¹⁰³Rh(n,n')^103mRh

A. Paulsen, R. Widera, R. Vaninbroukx, H. Liskien

Nuclear Science and Engineering / Volume 76 / Number 3 / December 1980 / Pages 331-335

Technical Paper / dx.doi.org/10.13182/NSE80-A21323

Neutron Streaming in Pebble Beds

J. Lieberoth, A. Stojadinović

Nuclear Science and Engineering / Volume 76 / Number 3 / December 1980 / Pages 336-344

Technical Paper / dx.doi.org/10.13182/NSE80-A21324

On the Solution of Linear Diffusion Problems in Media with Moving Boundaries

S. Bogado Leite, M. N. Özişik, K. Verghese

Nuclear Science and Engineering / Volume 76 / Number 3 / December 1980 / Pages 345-350

Technical Note / dx.doi.org/10.13182/NSE80-A21325

An Evaluation of Different Methods for Space-Dependent Resonance Shielding of Cross Sections in Fast Reactors

J. V. Muralidhar Rao, S. M. Lee, M. L. Sharma

Nuclear Science and Engineering / Volume 76 / Number 3 / December 1980 / Pages 351-356

Technical Note / dx.doi.org/10.13182/NSE80-A21326

Note on the Prompt-Fission-Neutron Spectra of Uranium-233 and -235 and Plutonium-239 and -240 Relative to That of Californium-252

A. Smith, P. Guenther, G. Winkler, R. McKnight

Nuclear Science and Engineering / Volume 76 / Number 3 / December 1980 / Pages 357-361

Technical Note / dx.doi.org/10.13182/NSE80-A21327

Sodium Flow Blockage in Liquid-Metal Fast Breeder Reactors: Sweepout of a Planar Blockage

Douglas K. Warinner, S. C. Saxena

Nuclear Science and Engineering / Volume 76 / Number 3 / December 1980 / Pages 361-366

Technical Note / dx.doi.org/10.13182/NSE80-A21328

Initial-Value Methods for a Simplified Subchannel Model of Thermal-Hydraulic Behavior

Paul Nelson, Charles H. Neil

Nuclear Science and Engineering / Volume 76 / Number 3 / December 1980 / Pages 366-370

Technical Note / dx.doi.org/10.13182/NSE80-A21329