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Volume 46

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Number 1

Table of Contents
Synthesis Solutions of the Multigroup Boltzmann Equation for Slabs(W. Schwetje)
TRIFIDO(F. Difilippo, N. Pieroni)
ANCON A Point-Kinetics Program with Nonlinear Feedback(John C. Vigil)
Comment on the Elastic Slowing Down of Neutrons in Fast Systems(R.Paviotti Corcuera)
Reply to Comment on the Elastic Slowing Down of Neutrons in Fast Systems(M. Segev)

A Three-Dimensional Stochastic Gamma-Ray Transport Method for Shielding Calculations

Arsalan Razani, H. E. Hungerford

Nuclear Science and Engineering / Volume 46 / Number 1 / October 1971 / Pages 1-11

Technical Paper / dx.doi.org/10.13182/NSE71-A22330

Monte Carlo Calculation of the Effect of Subterranean Perturbations on Reflected X Rays

W. A. Coleman

Nuclear Science and Engineering / Volume 46 / Number 1 / October 1971 / Pages 12-21

Technical Paper / dx.doi.org/10.13182/NSE71-A22331

Integral Reaction Rate Determinations—Part I. Tailored Reactor Spectrum Preparation and Measurement

E. Linn Draper, Jr.

Nuclear Science and Engineering / Volume 46 / Number 1 / October 1971 / Pages 22-30

Technical Paper / dx.doi.org/10.13182/NSE71-A22332

Integral Reaction Rate Determinations—Part II: Fission Rate Measurements

E. Linn Draper, Jr.

Nuclear Science and Engineering / Volume 46 / Number 1 / October 1971 / Pages 31-41

Technical Paper / dx.doi.org/10.13182/NSE71-A22333

Predictions of the Energy Dependence of the Average Yield of Neutrons Per Fission of Isotopes of Thorium, Uranium, and Plutonium

Robert J. Howerton

Nuclear Science and Engineering / Volume 46 / Number 1 / October 1971 / Pages 42-52

Technical Paper / dx.doi.org/10.13182/NSE71-A22334

Spectra of Fast Neutrons from Water Pulsed with 14-MeV Neutrons

Marion L. Stelts, John D. Anderson, Luisa F. Hansen, Ernest F. Plechaty, Calvin Wong

Nuclear Science and Engineering / Volume 46 / Number 1 / October 1971 / Pages 53-60

Technical Paper / dx.doi.org/10.13182/NSE71-A22335

Neutron Flux in Cells of Finite, Square Lattices

T. Auerbach

Nuclear Science and Engineering / Volume 46 / Number 1 / October 1971 / Pages 61-75

Technical Paper / dx.doi.org/10.13182/NSE71-A22336

Criticality Measurements on Uranium Metal Spheres Immersed in Uranium Solution

D. C. Hunt, Robert E. Rothe

Nuclear Science and Engineering / Volume 46 / Number 1 / October 1971 / Pages 76-87

Technical Paper / dx.doi.org/10.13182/NSE71-A22337

Optimal Control Rod Programming of Light Water Reactors in Equilibrium Fuel Cycle

Hiroshi Motoda

Nuclear Science and Engineering / Volume 46 / Number 1 / October 1971 / Pages 88-111

Technical Paper / dx.doi.org/10.13182/NSE71-A22338

Application of Linear Programming to Refueling Optimization for Light Water Moderated Power Reactors

Atsuyuki Suzuki, Ryohei Kiyose

Nuclear Science and Engineering / Volume 46 / Number 1 / October 1971 / Pages 112-130

Technical Paper / dx.doi.org/10.13182/NSE71-A22339

Measurement of the Effect of Twisted Tapes on the Forced-Convection Heat Transfer and Burnout in Heat Exchangers

R. Brevi, M. Cumo, A. Palmieri, D. Pitimada

Nuclear Science and Engineering / Volume 46 / Number 1 / October 1971 / Pages 131-139

Technical Paper / dx.doi.org/10.13182/NSE71-A22340

Optimal Strategies in Reactor System Economics

Paul Nelson, Jr., Gale Young

Nuclear Science and Engineering / Volume 46 / Number 1 / October 1971 / Pages 140-147

Technical Note / dx.doi.org/10.13182/NSE71-A22341

New Method for Measurement of the Effective Fraction of Delayed Neutrons from Fission

J. T. Mihalczo

Nuclear Science and Engineering / Volume 46 / Number 1 / October 1971 / Pages 147-148

Technical Note / dx.doi.org/10.13182/NSE71-A22342

Measurements of the Total Neutron Cross Section of Praseodymium Between 1 and 18 MeV

M. Enayetullah, N. Ameen, N. Islam, M. Hussain, S. Husain, E. Islam

Nuclear Science and Engineering / Volume 46 / Number 1 / October 1971 / Pages 148-150

Technical Note / dx.doi.org/10.13182/NSE71-A22343

Synthesis of Fast Reactor Neutron Energy Spectra

P. A. Ombrellaro, M. A. Snider

Nuclear Science and Engineering / Volume 46 / Number 1 / October 1971 / Pages 150-159

Technical Note / dx.doi.org/10.13182/NSE71-A22344

Number 2

Table of Contents
Water Coolant Technology of Power Reactors(G. M. Allison)
Approximate Treatment of the Effect of Anisotrpy on Elastic Neutron Moderation(W.M Stacey, Jr.)

Regional-Dependent Reactor Kinetics

David S. Gooden, T. F. Parkinson

Nuclear Science and Engineering / Volume 46 / Number 2 / November 1971 / Pages 169-178

Technical Paper / dx.doi.org/10.13182/NSE71-A22351

Noise and Transient Kinetics Experiments and Calculations for Loosely Coupled Cores

R. A. Rydin, J. A. Burke, W. E. Moore, K. W. Seemann

Nuclear Science and Engineering / Volume 46 / Number 2 / November 1971 / Pages 179-196

Technical Paper / dx.doi.org/10.13182/NSE71-A22352

Optimum Bounds for Space-Time Reactor Problems Using Linear Programming

David B. Reister

Nuclear Science and Engineering / Volume 46 / Number 2 / November 1971 / Pages 197-202

Technical Paper / dx.doi.org/10.13182/NSE71-A22353

Effect of Transverse Dimensions on the Diffusion Length of Neutrons in Crystalline Moderator Assemblies

Feroz Ahmed, L. S. Kothari, Ashok Kumar

Nuclear Science and Engineering / Volume 46 / Number 2 / November 1971 / Pages 203-213

Technical Paper / dx.doi.org/10.13182/NSE71-A22354

Pulsed-Neutron Diffusion Parameters in Mixtures of Heavy and Light Water and Ice

George N. Salaita, Andrew Robeson

Nuclear Science and Engineering / Volume 46 / Number 2 / November 1971 / Pages 214-222

Technical Paper / dx.doi.org/10.13182/NSE71-A22355

The Temperature Dependence of Neutron Inelastic Scattering from Water

L. J. Esch, M. L. Yeater, W. E. Moore, K. W. Seemann

Nuclear Science and Engineering / Volume 46 / Number 2 / November 1971 / Pages 223-235

Technical Paper / dx.doi.org/10.13182/NSE71-A22356

Measured Neutron Spectra in a Number of Uranium- and Plutonium-Fueled Reactor Assemblies

T. J. Yule, E. F. Bennett

Nuclear Science and Engineering / Volume 46 / Number 2 / November 1971 / Pages 236-243

Technical Paper / dx.doi.org/10.13182/NSE71-A22357

Measurements of Thermal-Neutron Spectra in Plutonium Nitrate Solutions

J. M. Neill, J. C. Young, C. A. Preskitt, G. D. Trimble, R. C. Lloyd, C. L. Brown

Nuclear Science and Engineering / Volume 46 / Number 2 / November 1971 / Pages 244-254

Technical Paper / dx.doi.org/10.13182/NSE71-A22358

Statistical Model Calculations of Iron-56 Neutron Cross Sections

S. D. Bloom, J. M. Green, H. W. Hubbard, S. A. Moszkowski

Nuclear Science and Engineering / Volume 46 / Number 2 / November 1971 / Pages 255-265

Technical Paper / dx.doi.org/10.13182/NSE71-A22359

Parametric Fit of the Neutron Cross Section of Holmium

Thomas E. Stephenson, Alberto M. Ferrer

Nuclear Science and Engineering / Volume 46 / Number 2 / November 1971 / Pages 266-273

Technical Paper / dx.doi.org/10.13182/NSE71-A22360

Application of Linear Programming to In-Core Fuel Management Optimization in Light Water Reactors

T. O. Sauar

Nuclear Science and Engineering / Volume 46 / Number 2 / November 1971 / Pages 274-283

Technical Paper / dx.doi.org/10.13182/NSE71-A22361

Turbulent-Flow Heat Transfer for In-Line Flow Through Unbaffled Rod Bundles: Molecular Conduction Only

O. E. Dwyer, H. C. Berry

Nuclear Science and Engineering / Volume 46 / Number 2 / November 1971 / Pages 284-303

Technical Paper / dx.doi.org/10.13182/NSE71-A22362

Advances in the Generalized Perturbation Theory

G. P. Cecchini, M. Salvatores

Nuclear Science and Engineering / Volume 46 / Number 2 / November 1971 / Pages 304-309

Technical Note / dx.doi.org/10.13182/NSE46-304

New Difference Schemes for the Neutron Transport Equation

William H. Reed

Nuclear Science and Engineering / Volume 46 / Number 2 / November 1971 / Pages 309-314

Technical Note / dx.doi.org/10.13182/NSE46-309

Neutron Absorption Cross Sections for Zirconium-94 and Zirconium-96

R. H. Fulmer, D. P. Stricos, T. F. Ruane

Nuclear Science and Engineering / Volume 46 / Number 2 / November 1971 / Pages 314-317

Technical Note / dx.doi.org/10.13182/NSE71-A22365

Positive Difference Schemes in Neutron Spectral Codes

Teresa Kulikowska

Nuclear Science and Engineering / Volume 46 / Number 2 / November 1971 / Pages 317-320

Technical Note / dx.doi.org/10.13182/NSE71-A22366

Number 3

Table of Contents
MECC-3, A Monte Carlo Intranuclear-Cascade Code for Medium-Energy (<3500 MeV) Particle-Nucleus Collisions(H. W. Bertini, A. H. Culkowski, M. P. Guthrie, O. W. Hermann)
VIXEN(Donald J. Dudziak, Johnny M. Romero)
Dynamics of Nuclear Reactors(Allan F. Henry)
Monte Carlo Principles and Neutron Transport Problems(Robert R. Coveyou)
Nuclear Theory, Volume 1: Nuclear Models(K. T. Hecht)
Radiation Heat Transfer(C. L. Tien)
Nuclear Heal Transport(O. E. Dwyer, J. M. Hendrie)
New Method for Measurement of the Effective Fraction of Delayed Neutrons from Fission(J. T. Mihalczo)

Plasma Energy Deposition from Nuclear Elastic Scattering

Joseph J. Devaney, Myron L. Stein

Nuclear Science and Engineering / Volume 46 / Number 3 / December 1971 / Pages 323-333

Technical Paper / dx.doi.org/10.13182/NSE71-A22370

The Effect of the Ground on the Steady-State and Time-Dependent Transport of Neutrons and Secondary Gamma Rays in the Atmosphere

E.A. Straker

Nuclear Science and Engineering / Volume 46 / Number 3 / December 1971 / Pages 334-355

Technical Paper / dx.doi.org/10.13182/NSE71-A22371

Fast Neutron Total and Scattering Cross Sections of Uranium-238

P. Lambropoulos

Nuclear Science and Engineering / Volume 46 / Number 3 / December 1971 / Pages 356-365

Technical Paper / dx.doi.org/10.13182/NSE71-A22372

A New Solution of the Point Kinetics Equations

J. A. W. da Nóbrega

Nuclear Science and Engineering / Volume 46 / Number 3 / December 1971 / Pages 366-375

Technical Paper / dx.doi.org/10.13182/NSE71-A22373

Evaluation of Neutron Spectral Effects in a Plutonium-Fueled Lattice by Foil Activation

F. V. Orestano, F. Pistella

Nuclear Science and Engineering / Volume 46 / Number 3 / December 1971 / Pages 376-384

Technical Paper / dx.doi.org/10.13182/NSE71-A22374

Application of Nonlinear Programming to the Optimal Control of Point Model Nuclear Reactors

G. F. Malan, B. V. Koen

Nuclear Science and Engineering / Volume 46 / Number 3 / December 1971 / Pages 385-393

Technical Paper / dx.doi.org/10.13182/NSE71-A22375

Heated Laminar Gas Flow in Annuli with Temperature-Dependent Transport Properties

R. W. Shumway, D. M. McEligot

Nuclear Science and Engineering / Volume 46 / Number 3 / December 1971 / Pages 394-407

Technical Paper / dx.doi.org/10.13182/NSE71-A22376

Dynamic Effects in Radiation Diagnosis of Fluctuating Voids

A. A. Harms, C. F. Forrest

Nuclear Science and Engineering / Volume 46 / Number 3 / December 1971 / Pages 408-413

Technical Paper / dx.doi.org/10.13182/NSE71-A22377

Fission Temperatures as a Function of the Average Number of Neutrons from Fission

R. J. Howerton, R. J. Doyas

Nuclear Science and Engineering / Volume 46 / Number 3 / December 1971 / Pages 414-416

Technical Note / dx.doi.org/10.13182/NSE71-A22378

Neutron Diffusion from a Fast Point Source in Aqueous Absorbing Solutions

Dong H. Nguyen, Marshall T. Slayton, John A. Frew

Nuclear Science and Engineering / Volume 46 / Number 3 / December 1971 / Pages 416-421

Technical Note / dx.doi.org/10.13182/NSE71-A22379

Evaluation of Space-Energy Factorization for Two-Dimensional Diffusion Theory Problems in the Liquid Metal Fast Breeder Reactor

Weston M. Stacey, Jr.

Nuclear Science and Engineering / Volume 46 / Number 3 / December 1971 / Pages 421-425

Technical Note / dx.doi.org/10.13182/NSE71-A22380

Roots and Coefficients from the Integral Solution of the Reactor Kinetic Equations Applicable to Uranium-235 Fueled, Heavy Water Moderated Reactors

Joseph S. Crudele, Richard A. Danofsky

Nuclear Science and Engineering / Volume 46 / Number 3 / December 1971 / Pages 425-427

Technical Note / dx.doi.org/10.13182/NSE71-A22381

Calculated Thermal (n, α) Cross Section for Nickel-59

G. J. Kirouac

Nuclear Science and Engineering / Volume 46 / Number 3 / December 1971 / Pages 427-428

Technical Note / dx.doi.org/10.13182/NSE71-A22382

On a Possible Resolution of the Nitrogen Nonelastic Neutron Cross-Section Discrepancy Below 9 MeV

F. G. Perey, W. E. Kinney

Nuclear Science and Engineering / Volume 46 / Number 3 / December 1971 / Pages 428-431

Technical Note / dx.doi.org/10.13182/NSE71-A22383

Critical Heat Fluxes of Full Flux Shapes from Partial Flux Shapes

R. H. Wilson, G. O. Geissler

Nuclear Science and Engineering / Volume 46 / Number 3 / December 1971 / Pages 431-436

Technical Note / dx.doi.org/10.13182/NSE71-A22384