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Volume 62

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Number 1

Table of Contents
Experimental Reactor Physics(Glenn F. Knoll)
Fusion Energy Conversion(J. Rand McNally, Jr.)
Safeguards Against Nuclear Proliferation(Melvin L. Tobias)
Transport Eigenvalues(Jeffery Lewins)
The Reactivity Dependence of Neutron Energy Spectra(Y. Ronen, D. Shalitin, D. Shvarts, J. J. Wags chat, Y. Yeivìn)

Reactivity and Power Shape Control

Constantine P. Tzanos

Nuclear Science and Engineering / Volume 62 / Number 1 / January 1977 / Pages 1-8

Technical Paper / dx.doi.org/10.13182/NSE77-A26934

Suboptimal Control of Nuclear Reactors with Distributed Parameters Using Singular Perturbation Theory

K. Asatani, M. Shiotani, Y. Hattori

Nuclear Science and Engineering / Volume 62 / Number 1 / January 1977 / Pages 9-19

Technical Paper / dx.doi.org/10.13182/NSE77-A26935

Fault Trees for Diagnosis of System Fault Conditions

Howard E. Lambert, George Yadigaroglu

Nuclear Science and Engineering / Volume 62 / Number 1 / January 1977 / Pages 20-34

Technical Paper / dx.doi.org/10.13182/NSE77-A26936

The Sensitivity of Decay Power to Uncertainties in Fission Product Yields

B. I. Spinrad

Nuclear Science and Engineering / Volume 62 / Number 1 / January 1977 / Pages 35-44

Technical Paper / dx.doi.org/10.13182/NSE77-A26937

An Approximate Calculational Method for Nuclear Heating

Gene L. Woodruff, David C. Quimby

Nuclear Science and Engineering / Volume 62 / Number 1 / January 1977 / Pages 45-54

Technical Paper / dx.doi.org/10.13182/NSE77-A26938

Singularities in the Finite Element Approximation of Two-Dimensional Diffusion Problems

J. P. Hennart, E. H. Mund

Nuclear Science and Engineering / Volume 62 / Number 1 / January 1977 / Pages 55-68

Technical Paper / dx.doi.org/10.13182/NSE77-A26939

Improved Formulations of the Response Matrix Doubling Equations

W. L. Filippone

Nuclear Science and Engineering / Volume 62 / Number 1 / January 1977 / Pages 69-91

Technical Paper / dx.doi.org/10.13182/NSE77-A26940

The Concept of Spatial Channel Theory Applied to Reactor Shielding Analysis

M. L. Williams, W. W. Engle, Jr.

Nuclear Science and Engineering / Volume 62 / Number 1 / January 1977 / Pages 92-104

Technical Paper / dx.doi.org/10.13182/NSE77-A26941

Integral Measurements of the Effective Delayed Neutron Fractions in the Fast Critical Assembly SNEAK

E. A. Fischer

Nuclear Science and Engineering / Volume 62 / Number 1 / January 1977 / Pages 105-116

Technical Paper / dx.doi.org/10.13182/NSE77-4

Methods of Adjustment and Error Evaluation of Neutron Capture Cross Sections; Application to Fission Product Nuclides

J. B. Dragt, J. W. M. Dekker, H. Gruppelaar, A. J. Janssen

Nuclear Science and Engineering / Volume 62 / Number 1 / January 1977 / Pages 117-129

Technical Paper / dx.doi.org/10.13182/NSE77-3

Source Enhancement Measurement to Determine vσ_ƒ of Uranium-238 for Californium-252 Spontaneous Fission Neutrons

B. W. Lee, S. H. Levine

Nuclear Science and Engineering / Volume 62 / Number 1 / January 1977 / Pages 130-136

Technical Paper / dx.doi.org/10.13182/NSE77-A26944

Cross-Section Sensitivity and Uncertainty Analysis with Application to a Fusion Reactor

S. A. W. Gerstl, Donald J. Dudziak, D. W. Muir

Nuclear Science and Engineering / Volume 62 / Number 1 / January 1977 / Pages 137-156

Technical Paper / dx.doi.org/10.13182/NSE77-A26945

Grain Boundary Grooving of Pure Iron in Nitrogen-Contaminated Liquid Lithium

L. B. Whitefield, D. L. Olson, W. L. Bradley

Nuclear Science and Engineering / Volume 62 / Number 1 / January 1977 / Pages 157-162

Technical Paper / dx.doi.org/10.13182/NSE77-A26946

Dimensionality Reduction of Reactor Noise Signatures

R. C. Gonzalez, L. C. Howington

Nuclear Science and Engineering / Volume 62 / Number 1 / January 1977 / Pages 163-167

Technical Note / dx.doi.org/10.13182/NSE77-A26947

Effects of Neutron Capture Transformations on the Decay Power of Fission Products

Kanji Tasaka

Nuclear Science and Engineering / Volume 62 / Number 1 / January 1977 / Pages 167-174

Technical Note / dx.doi.org/10.13182/NSE77-A26948

The 292.4-eV Neutron Resonance Parameters of Zirconium-91

R. L. Macklin, J. A. Harvey, J. Halperin, N. W. Hill

Nuclear Science and Engineering / Volume 62 / Number 1 / January 1977 / Pages 174-176

Technical Note / dx.doi.org/10.13182/NSE77-A26949

Number 2

Table of Contents
Experimental Development of Design Criteria to Limit Liquid Cross-Flow-Induced Vibration in Nuclear Reactor Heat Exchange Equipment(D. J. Gorman)
Nuclear Reactor Analysis(Noel Corngold)
Annual Review of Energy, Volume 1(H. G. MacPherson)
The Nuclear Fuel Cycle—A Survey of the Public Health, Environmental, and National Security Effects of Nuclear Power(Melvin L. Tobias)
Stress Transients in Solids(J. E. Akin)

Measurement of Sub-Coulomb-Barrier Charged Particles Emitted from Aluminum and Titanium Bombarded by 15-MeV Neutrons

S. M. Grimes, R. C. Haight, J. D. Anderson

Nuclear Science and Engineering / Volume 62 / Number 2 / February 1977 / Pages 187-194

Technical Paper / dx.doi.org/10.13182/NSE77-A26956

FX2-POOL—A Two-Dimensional Coupled Hydrodynamic Thermodynamic and Neutronic Computer Model for Hypothetical Core Disruptive Accident Analysis

Paul B. Abramson

Nuclear Science and Engineering / Volume 62 / Number 2 / February 1977 / Pages 195-214

Technical Paper / dx.doi.org/10.13182/NSE77-A26957

Diagnostic Analyses of a Nuclear Power Plant Using Multivariate Autoregressive Processes

Kohyu Fukunishi

Nuclear Science and Engineering / Volume 62 / Number 2 / February 1977 / Pages 215-225

Technical Paper / dx.doi.org/10.13182/NSE77-A26958

The Effect of Core Burnup on the Dynamic Behavior of Fast Reactors

D. Ilberg, D. Saphier, S. Yiftah

Nuclear Science and Engineering / Volume 62 / Number 2 / February 1977 / Pages 226-242

Technical Paper / dx.doi.org/10.13182/NSE77-A26959

Derivation of Consistent Measures for the Doubling of Fast Breeder Reactor Fuel

Karl O. Ott, Robert C. Borg

Nuclear Science and Engineering / Volume 62 / Number 2 / February 1977 / Pages 243-261

Technical Paper / dx.doi.org/10.13182/NSE77-A26960

Measured Fast-Neutron Penetration Spectra for Water—Comparison with Calculations

William H. Miller, Walter Meyer, Darrol H. Timmons

Nuclear Science and Engineering / Volume 62 / Number 2 / February 1977 / Pages 262-269

Technical Paper / dx.doi.org/10.13182/NSE77-A26961

The Representation of Water Properties by Mathematical Splines

C. S. Caldwell, D. A. Spragg

Nuclear Science and Engineering / Volume 62 / Number 2 / February 1977 / Pages 270-277

Technical Paper / dx.doi.org/10.13182/NSE77-A26962

Orders-of-Scattering Analysis of Particle Transport in Finite Slabs

Stanley Woolf, John C. Garth, William L. Filippone

Nuclear Science and Engineering / Volume 62 / Number 2 / February 1977 / Pages 278-295

Technical Paper / dx.doi.org/10.13182/NSE77-A26963

Perturbation Theory for Ratios in Linear and Nonlinear Problems

Martin Becker

Nuclear Science and Engineering / Volume 62 / Number 2 / February 1977 / Pages 296-301

Technical Paper / dx.doi.org/10.13182/NSE77-A26964

Estimation of Specific Heat of Superheated Water

John H. Lienhard

Nuclear Science and Engineering / Volume 62 / Number 2 / February 1977 / Pages 302-304

Technical Note / dx.doi.org/10.13182/NSE77-A26965

Burnup Calculations with Time-Dependent Generalized Perturbation Theory

J. M. Kallfelz, G. B. Bruna, G. Palmiotti, M. Salvatores

Nuclear Science and Engineering / Volume 62 / Number 2 / February 1977 / Pages 304-309

Technical Note / dx.doi.org/10.13182/NSE77-A26966

Benchmark Testing Using ENDF/B-III and -IV

R. D. McKnight

Nuclear Science and Engineering / Volume 62 / Number 2 / February 1977 / Pages 309-330

Technical Note / dx.doi.org/10.13182/NSE77-A26967

An Improved P-L Solution to the Reflected Critical-Reactor Problem in Slab Geometry

K. Neshat, C. E. Siewert, Y. Ishiguro

Nuclear Science and Engineering / Volume 62 / Number 2 / February 1977 / Pages 330-332

Technical Note / dx.doi.org/10.13182/NSE77-A26968

Asymptotic Solutions in Neutron Transport Theory

V. C. Boffi, V. G. Molinari, G. Spiga

Nuclear Science and Engineering / Volume 62 / Number 2 / February 1977 / Pages 332-339

Technical Note / dx.doi.org/10.13182/NSE77-A26969

New Developments in Generalized Perturbation Methods in the Nuclide Field

A. Gandini, M. Salvatores, L. Tondinelli

Nuclear Science and Engineering / Volume 62 / Number 2 / February 1977 / Pages 339-345

Technical Note / dx.doi.org/10.13182/NSE77-A26970

Number 3

Table of Contents
SPAR1(O. J. Wallace)

Exact Statistical Analysis of Nonlinear Dynamic Nuclear-Power Reactor Models by the Fokker-Planck Method—Part I: Reactor with Direct Power Feedback

W. L. Dutré, A. F. Debosscher

Nuclear Science and Engineering / Volume 62 / Number 3 / March 1977 / Pages 355-363

Technical Paper / dx.doi.org/10.13182/NSE77-A26977

An Optimal Choice of the Initial Flux for Iterative Solutions of the Inhomogeneous Transport Equation

D. Shalitin, J. J. Wagschal, Y. Yeivin

Nuclear Science and Engineering / Volume 62 / Number 3 / March 1977 / Pages 364-370

Technical Paper / dx.doi.org/10.13182/NSE77-A26978

Finite Element Solutions of the Neutron Transport Equation with Applications to Strong Heterogeneities

William R. Martin, James J. Duderstadt

Nuclear Science and Engineering / Volume 62 / Number 3 / March 1977 / Pages 371-390

Technical Paper / dx.doi.org/10.13182/NSE77-A26979

Ray-Effect Mitigation Methods for Two-Dimensional Neutron Transport Theory

W. F. Miller, Jr., Wm. H. Reed

Nuclear Science and Engineering / Volume 62 / Number 3 / March 1977 / Pages 391-411

Technical Paper / dx.doi.org/10.13182/NSE62-391

Continuous Neutron Slowing Down Theory Applied to Resonances

Meir Segev

Nuclear Science and Engineering / Volume 62 / Number 3 / March 1977 / Pages 412-423

Technical Paper / dx.doi.org/10.13182/NSE77-A26981

Surface Density and Density Analog Models for Criticality in Arrays of Fissile Materials

J. T. Thomas

Nuclear Science and Engineering / Volume 62 / Number 3 / March 1977 / Pages 424-437

Technical Paper / dx.doi.org/10.13182/NSE77-A26982

Revisited

R. J. Howerton

Nuclear Science and Engineering / Volume 62 / Number 3 / March 1977 / Pages 438-454

Technical Paper / dx.doi.org/10.13182/NSE77-A26983

²³⁸U(n, f) Measurements Below 100 keV

R. E. Slovacek, D. S. Cramer, E. B. Bean, J. R. Valentine, R. W. Hockenbury, R. C. Block

Nuclear Science and Engineering / Volume 62 / Number 3 / March 1977 / Pages 455-462

Technical Paper / dx.doi.org/10.13182/NSE77-A26984

Epithermal Neutron Capture in Uranium-238

H. I. Liou, R. E. Chrien

Nuclear Science and Engineering / Volume 62 / Number 3 / March 1977 / Pages 463-478

Technical Paper / dx.doi.org/10.13182/NSE77-A26985

Precise Measurement and Analysis of Neutron Transmission Through Uranium-238

D. K. Olsen, G. de Saussure, R. B. Perez, E. G. Silver, F. C. Difilippo, R. W. Ingle, H. Weaver

Nuclear Science and Engineering / Volume 62 / Number 3 / March 1977 / Pages 479-501

Technical Paper / dx.doi.org/10.13182/NSE77-A26986

Space- and Angle-Dependent Steady-State Thermal-Neutron Spectra Inside Finite Prisms of Graphite

Suresh Garg, Feroz Ahmed, L. S. Kothari

Nuclear Science and Engineering / Volume 62 / Number 3 / March 1977 / Pages 502-510

Technical Paper / dx.doi.org/10.13182/NSE77-A26987

The Half-Life of Cobalt-56

M. E. Anderson

Nuclear Science and Engineering / Volume 62 / Number 3 / March 1977 / Pages 511-514

Technical Paper / dx.doi.org/10.13182/NSE77-A26988

Cross Sections for Gamma-Ray Production by Fast Neutrons for 22 Elements Between Z = 3 and Z = 82

J. K. Dickens, G. L. Morgan, G. T. Chapman, T. A. Love, E. Newman, F. G. Perey

Nuclear Science and Engineering / Volume 62 / Number 3 / March 1977 / Pages 515-531

Technical Paper / dx.doi.org/10.13182/NSE77-A26989

Analysis of Neutron Scattering and Gamma-Ray Production Integral Experiments on Nitrogen for Neutron Energies from 1 to 15 MeV

S. N. Cramer, E. M. Oblow

Nuclear Science and Engineering / Volume 62 / Number 3 / March 1977 / Pages 532-549

Technical Paper / dx.doi.org/10.13182/NSE77-A26990

Measurements and Calculations of the Electron Recoil Spectra from Gamma Rays Emitted by Nitrogen for a 14-MeV Neutron Source

L. F. Hansen, T. Komoto, E. F. Plechaty, B. A. Pohl, G. S. Sidhu, C. Wong

Nuclear Science and Engineering / Volume 62 / Number 3 / March 1977 / Pages 550-558

Technical Paper / dx.doi.org/10.13182/NSE77-A26991

Reactivity Worths of Annular Control Rods in a Pressure-Tube-Type Heavy Water Lattice

Makoto Ueda, Mitsuo Matsumoto, Tohru Haga

Nuclear Science and Engineering / Volume 62 / Number 3 / March 1977 / Pages 559-570

Technical Note / dx.doi.org/10.13182/NSE77-A26992

An Assessment of ENDF/B-IV Data for Uranium-238

Ansar Parvez, Martin Becker

Nuclear Science and Engineering / Volume 62 / Number 3 / March 1977 / Pages 571-574

Technical Note / dx.doi.org/10.13182/NSE77-A26993

Canonical Decoupling and Control of Multiple-Core Nuclear Reactors

S. Tzafestas, N. Chrysochoides

Nuclear Science and Engineering / Volume 62 / Number 3 / March 1977 / Pages 574-579

Technical Note / dx.doi.org/10.13182/NSE77-A26994

A Note on Turbulent-Laminar Transition for Flow in Triangular Rod Bundles

J. W. Yang

Nuclear Science and Engineering / Volume 62 / Number 3 / March 1977 / Pages 579-582

Technical Note / dx.doi.org/10.13182/NSE77-A26995

Number 4

Table of Contents
Nuclear Structure, Vol. II: Nuclear Deformations(L. W. Nordheim)
Of Acceptable Risk: Science and the Determination of Safety(Roy Reider)
Environmental Aspects of Nuclear Power(Bernard L. Cohen)
Random Processes in Nuclear Reactors(Joseph A. Thie)
A Rational Finite Element Basis(J. P. Hennart)
FLASH6(J. J. Beyer, W. D. Peterson, D. A. Prelewicz, G. W. Swartele)

Neutronics of a Dense-Plasma Focus— An Investigation of a Fusion Plasma

P. Cloth, H. Conrads

Nuclear Science and Engineering / Volume 62 / Number 4 / April 1977 / Pages 591-600

Technical Paper / dx.doi.org/10.13182/NSE77-A15203

The Influence of Design Variations on Controlled Thermonuclear Reactor Blanket Neutronic Performance Using Variational Techniques

Edward T. Cheng, Robert W. Conn

Nuclear Science and Engineering / Volume 62 / Number 4 / April 1977 / Pages 601-616

Technical Paper / dx.doi.org/10.13182/NSE77-A15204

Monte Carlo Shielding Calculations Using Event-Value Path-Length Biasing

J. S. Tang, T. J. Hoffman, P. N. Stevens

Nuclear Science and Engineering / Volume 62 / Number 4 / April 1977 / Pages 617-626

Technical Paper / dx.doi.org/10.13182/NSE77-A15205

Delayed Neutron Yield Calculations for the Neutron-Induced Fission of Uranium-235 as a Function of the Incident Neutron Energy

D. R. Alexander, M. S. Krick

Nuclear Science and Engineering / Volume 62 / Number 4 / April 1977 / Pages 627-635

Technical Paper / dx.doi.org/10.13182/NSE77-A15206

Measured Near-Equilibrium Delayed Neutron Spectra Produced by Fast-Neutron-Induced Fission of ²³²Th, ²³³U, ²³⁵U, ²³⁸U, and ²³⁹Pu

George W. Eccleston, Gene L. Woodruff

Nuclear Science and Engineering / Volume 62 / Number 4 / April 1977 / Pages 636-651

Technical Paper / dx.doi.org/10.13182/NSE77-A15207

Equilibrium Delayed Neutron Spectra from Fast Fission of Uranium-235, Uranium-238, and Plutonium-239

Albert E. Evans, M. S. Krick

Nuclear Science and Engineering / Volume 62 / Number 4 / April 1977 / Pages 652-659

Technical Paper / dx.doi.org/10.13182/NSE77-A15208

Evaluated Delayed Neutron Spectra and Their Importance in Reactor Calculations

D. Saphier, D. Ilberg, S. Shalev, S. Yiftah

Nuclear Science and Engineering / Volume 62 / Number 4 / April 1977 / Pages 660-694

Technical Paper / dx.doi.org/10.13182/NSE77-A15209

An Experimental Study of the Prompt Fission Neutron Spectrum Induced by 0.5-MeV Neutrons Incident on Uranium-235

P. I. Johansson, B. Holmqvist

Nuclear Science and Engineering / Volume 62 / Number 4 / April 1977 / Pages 695-708

Technical Paper / dx.doi.org/10.13182/NSE77-A15210

An Improved Response Matrix Method for Calculating Neutron Flux Distributions

Toshikazu Takeda, Kazuo Azekura, Tadahiro Ohnishi

Nuclear Science and Engineering / Volume 62 / Number 4 / April 1977 / Pages 709-715

Technical Paper / dx.doi.org/10.13182/NSE77-A15211

Gamma-Ray Production Cross Sections for Copper from 0.67 to 19.6 MeV

V. C. Rogers, D. R. Dixon, C. G. Hoot, D. Costello, V. J. Orphan

Nuclear Science and Engineering / Volume 62 / Number 4 / April 1977 / Pages 716-725

Technical Paper / dx.doi.org/10.13182/NSE77-A15212

Effect of Fixed and Soluble Neutron Absorbers on the Criticality of Uranium-Plutonium Systems

R. C. Lloyd, E. D. Clayton

Nuclear Science and Engineering / Volume 62 / Number 4 / April 1977 / Pages 726-735

Technical Paper / dx.doi.org/10.13182/NSE77-A15213

Taylor Coefficients for Eisenhauer-Simmons Gamma-Ray Buildup Factors in Ordinary Concrete

K. Shure, O. J. Wallace

Nuclear Science and Engineering / Volume 62 / Number 4 / April 1977 / Pages 736-738

Technical Note / dx.doi.org/10.13182/NSE77-A15214

A Low-Order Approximation for Highly Anisotropic Multigroup Transport Cross Sections

Wayne J. Mikols, J. Kenneth Shultis

Nuclear Science and Engineering / Volume 62 / Number 4 / April 1977 / Pages 738-743

Technical Note / dx.doi.org/10.13182/NSE77-A15215

Neutron Spectrum in a Heavy Gas

Raymond L. Murray, Reed S. C. Rogers, Saber Musazay

Nuclear Science and Engineering / Volume 62 / Number 4 / April 1977 / Pages 743-745

Technical Note / dx.doi.org/10.13182/NSE77-A15216

Neutron Diffusion in Finite Blocks of Beryllium

A. N. Verma, Feroz Ahmed, L. S. Kothari

Nuclear Science and Engineering / Volume 62 / Number 4 / April 1977 / Pages 745-750

Technical Note / dx.doi.org/10.13182/NSE77-A15217

A Coarse-Mesh Method for Multidimensional, Mixed-Lattice Diffusion Calculations

H. L. Dodds, Jr., H. C. Honeck, D. E. Hostetler

Nuclear Science and Engineering / Volume 62 / Number 4 / April 1977 / Pages 751-756

Technical Note / dx.doi.org/10.13182/NSE77-A15218

Some Properties of the Width Fluctuation Factor

H. Gruppelaar, G. Reffo

Nuclear Science and Engineering / Volume 62 / Number 4 / April 1977 / Pages 756-763

Technical Note / dx.doi.org/10.13182/NSE77-A15219

Nuclear Reactor Control Using Walsh Function Variational Synthesis

S. Tzafestas, N. Chrysochoides

Nuclear Science and Engineering / Volume 62 / Number 4 / April 1977 / Pages 763-770

Technical Note / dx.doi.org/10.13182/NSE77-A15220