ANS / Publications / Journals / Nuclear Science and Engineering

Numerical Calculation of Two-Phase Flows

John R. Travis, Francis H. Harlow, Anthony A. Amsden

Nuclear Science and Engineering / Volume 61 / Number 1 / September 1976 / Pages 1-10

Technical Paper / dx.doi.org/10.13182/NSE76-A28455

Models for Calculating the Effects of Isotopic Exchange, Radioactive Decay, and Recycle in Removing Iodine from Gas and Liquid Streams

Wallace Davis, Jr.

Nuclear Science and Engineering / Volume 61 / Number 1 / September 1976 / Pages 11-20

Technical Paper / dx.doi.org/10.13182/NSE76-A28456

Radiation-Damage Calculations: Primary Knock-On Atom Spectra, Displacement Rates, and Gas Production Rates

T. A. Gabriel, J. D. Amburgey, N. M. Greene

Nuclear Science and Engineering / Volume 61 / Number 1 / September 1976 / Pages 21-32

Technical Paper / dx.doi.org/10.13182/NSE76-A28457

Neutron Spectrum from a Uranium-235 Sphere Bombarded by 14-MeV Neutrons

C. E. Ragan III, G. F. Auchampaugh, A. Hemmendinger, M. G. Silbert

Nuclear Science and Engineering / Volume 61 / Number 1 / September 1976 / Pages 33-39

Technical Paper / dx.doi.org/10.13182/NSE76-A28458

Cross Sections for the Production of 8- to 20-MeV Photons

G. Longo, F. Saporetti

Nuclear Science and Engineering / Volume 61 / Number 1 / September 1976 / Pages 40-52

Technical Paper / dx.doi.org/10.13182/NSE76-A28459

Reaction Rates in a Uranium Pile Surrounding a 14-MeV Neutron Source: Calculations of the Weale Experiment

R. C. Haight, J. D. Lee, J. A. Maniscalco

Nuclear Science and Engineering / Volume 61 / Number 1 / September 1976 / Pages 53-59

Technical Paper / dx.doi.org/10.13182/NSE76-A28460

The Kinetics of a Coupled Two-Core Nuclear Reactor

Felix C. Difilippo, Ricardo M. Waldman

Nuclear Science and Engineering / Volume 61 / Number 1 / September 1976 / Pages 60-71

Technical Paper / dx.doi.org/10.13182/NSE76-A28461

Neutron Transport in Two Dissimilar Media with Anisotropic Scattering

A. R. Burkart, Y. Ishiguro, C. E. Siewert

Nuclear Science and Engineering / Volume 61 / Number 1 / September 1976 / Pages 72-77

Technical Paper / dx.doi.org/10.13182/NSE76-A28462

Thermal-Neutron Transport Processes in H₂O-D₂O Mixtures in the Temperature Range 253 to 21 K: The Possible Use of These Moderators as Cold-Neutron Sources

G. S. Gangwani, S. P. Tewari, L. S. Kothari

Nuclear Science and Engineering / Volume 61 / Number 1 / September 1976 / Pages 78-89

Technical Paper / dx.doi.org/10.13182/NSE76-A28463

The Application of Neutron Transport Codes to the Transport of Neutrals in Plasmas

J. H. Marable, E. M. Oblow

Nuclear Science and Engineering / Volume 61 / Number 1 / September 1976 / Pages 90-97

Technical Paper / dx.doi.org/10.13182/NSE76-A28464

Analysis of the Coarse-Mesh Rebalancing Effect on Chebyshev Polynomial Iterations

S. Nakamura

Nuclear Science and Engineering / Volume 61 / Number 1 / September 1976 / Pages 98-106

Technical Paper / dx.doi.org/10.13182/NSE76-A28465

Mass Transfer in the Contamination of Isothermal Steel Surfaces

D. H. Lister

Nuclear Science and Engineering / Volume 61 / Number 1 / September 1976 / Pages 107-112

Technical Note / dx.doi.org/10.13182/NSE76-A28466

A Low Reynolds Number Bundle-Size Effect for Wire-Wrapped Liquid-Metal Fast Breeder Reactor Assemblies

Ehsan U. Khan

Nuclear Science and Engineering / Volume 61 / Number 1 / September 1976 / Pages 112-115

Technical Note / dx.doi.org/10.13182/NSE76-A28467

The Energy Dependence of the Neutron Absorption and Fission Cross Sections of U ranium-235 and Plutonium-239 Below 1 eV and the Wescott g Factors

R. Gwin

Nuclear Science and Engineering / Volume 61 / Number 1 / September 1976 / Pages 116-117

Technical Note / dx.doi.org/10.13182/NSE76-A28468

A Two-Dimensional Time-Dependent Neutron Transport Calculation Using One-Dimensional Equations

Michael Boring, W. H. Roach

Nuclear Science and Engineering / Volume 61 / Number 1 / September 1976 / Pages 117-118

Technical Note / dx.doi.org/10.13182/NSE76-A28469

A Coarse-Mesh Correction of the Finite Difference Method for Neutron Diffusion Calculations

Yasuyoshi Kato, Toshikazu Takeda, Seiichi Takeda

Nuclear Science and Engineering / Volume 61 / Number 2 / October 1976 / Pages 127-141

Technical Paper / dx.doi.org/10.13182/NSE76-A27347

Exact Solutions of the Neutron Slowing Down Equation

Trine-Yie Dawn, Chio-Min Yang

Nuclear Science and Engineering / Volume 61 / Number 2 / October 1976 / Pages 142-158

Technical Paper / dx.doi.org/10.13182/NSE76-A27348

A Discrete Energy Formulation of Neutron Transport Theory Applied to Solving the Discrete Ordinates Equations

J. Ching, E. M. Oblow, H. Goldstein

Nuclear Science and Engineering / Volume 61 / Number 2 / October 1976 / Pages 159-169

Technical Paper / dx.doi.org/10.13182/NSE76-A27349

Perturbation Theory and Importance Functions in Integral Transport Formulations

E. Greenspan

Nuclear Science and Engineering / Volume 61 / Number 2 / October 1976 / Pages 170-180

Technical Paper / dx.doi.org/10.13182/NSE76-A27350

The Representation of Light-Water Reflectors by Boundary Conditions

P.C. Kalambokas, A. F. Henry

Nuclear Science and Engineering / Volume 61 / Number 2 / October 1976 / Pages 181-194

Technical Paper / dx.doi.org/10.13182/NSE76-A27351

External Bremsstrahlung Generated by Yttrium-91 and Thallium-204 Beta Rays

K. V. N. Sarma, K. Narasimha Murty, V. V. V. Subrahmanyam

Nuclear Science and Engineering / Volume 61 / Number 2 / October 1976 / Pages 195-200

Technical Paper / dx.doi.org/10.13182/NSE76-A27352

Calculations of the Neutron Emission Spectra from Materials Bombarded with 14-MeV Neutrons

L. F. Hansen, S. M. Grimes, R. J. Howerton, J D. Anderson

Nuclear Science and Engineering / Volume 61 / Number 2 / October 1976 / Pages 201-211

Technical Paper / dx.doi.org/10.13182/NSE76-A27353

The Transmutation of Strontium-90 and Cesium-137 in a High-Flux Fast Reactor with a Thermalized Central Region

M. Taube

Nuclear Science and Engineering / Volume 61 / Number 2 / October 1976 / Pages 212-221

Technical Paper / dx.doi.org/10.13182/NSE76-A27354

Postaccident Heat Removal—Part I: Heat Transfer Within an Internally Heated, Nonboiling Liquid Layer

Louis Baker, Jr., Richard E. Faw, Francis A. Kulacki

Nuclear Science and Engineering / Volume 61 / Number 2 / October 1976 / Pages 222-230

Technical Paper / dx.doi.org/10.13182/NSE76-A27355

Postaccident Heat Removal—Part II: Heat Transfer from an Internally Heated Liquid to a Melting Solid

Richard E. Faw, Louis Baker, Jr.

Nuclear Science and Engineering / Volume 61 / Number 2 / October 1976 / Pages 231-238

Technical Paper / dx.doi.org/10.13182/NSE76-A27356

Solution of the Fuel Burnup Control Problem with a Controlling Neutron Equation and Walsh Functions

Ryuji Koga

Nuclear Science and Engineering / Volume 61 / Number 2 / October 1976 / Pages 239-249

Technical Paper / dx.doi.org/10.13182/NSE76-A27357

On the Dynamics of Transition Region Flow Boiling

W. C. Peterson, M. G. Zaalouk, S. İ. Güçeri

Nuclear Science and Engineering / Volume 61 / Number 2 / October 1976 / Pages 250-257

Technical Paper / dx.doi.org/10.13182/NSE76-A27358

A Groupwise Rebalancing Technique for Integral Transport Problems

Hsiang-Shou Cheng

Nuclear Science and Engineering / Volume 61 / Number 2 / October 1976 / Pages 258-261

Technical Note / dx.doi.org/10.13182/NSE76-A27359

Two-Dimensional Calculation of a Pulse Propagation Experiment

J. M. A. Christens, P. B. Parks, N. J. Diaz

Nuclear Science and Engineering / Volume 61 / Number 2 / October 1976 / Pages 261-267

Technical Note / dx.doi.org/10.13182/NSE76-A27360

Cross Section for the ⁹Be(n, t₁)⁷Li Reaction Between 13.3 and 15 MeV

F. S. Dietrich, L. F. Hansen, R. P. Koopman

Nuclear Science and Engineering / Volume 61 / Number 2 / October 1976 / Pages 267-268

Technical Note / dx.doi.org/10.13182/NSE76-A27361

Geometrical Efficiency Equation for Proton Recoil Telescopes

G. E. Hansen, R. K. Smith, G. G. Simons

Nuclear Science and Engineering / Volume 61 / Number 2 / October 1976 / Pages 269-276

Technical Note / dx.doi.org/10.13182/NSE76-A27362

Nonlinear Dynamics of a Pressurized Water Reactor Core

R. J. Onega, K. E. Karcher

Nuclear Science and Engineering / Volume 61 / Number 2 / October 1976 / Pages 276-282

Technical Note / dx.doi.org/10.13182/NSE76-A27363

Laminar-Flow Pressure Drop in Symmetrical Finite Rod Bundles

John P. Zarling

Nuclear Science and Engineering / Volume 61 / Number 2 / October 1976 / Pages 282-285

Technical Note / dx.doi.org/10.13182/NSE76-A27364

Two-Phase Pressure Drop Across Abrupt Area Changes in Oscillatory Flow

J. Weisman, T. Ake, R. Knott

Nuclear Science and Engineering / Volume 61 / Number 3 / November 1976 / Pages 297-309

Technical Paper / dx.doi.org/10.13182/NSE76-A26916

Transient Freezing of a Flowing Ceramic Fuel in a Steel Channel

Michael Epstein, Michael A. Grolmes, Robert E. Henry, Hans K. Fauske

Nuclear Science and Engineering / Volume 61 / Number 3 / November 1976 / Pages 310-323

Technical Paper / dx.doi.org/10.13182/NSE76-A26917

Experimental Development of Design Criteria to Limit Liquid Cross-Flow-Induced Vibration in Nuclear Reactor Heat Exchange Equipment

D. J. Gorman

Nuclear Science and Engineering / Volume 61 / Number 3 / November 1976 / Pages 324-336

Technical Paper / dx.doi.org/10.13182/NSE76-A26918

Cross Sections for the Al(n, xn) and Al(n, xγ) Reactions Between 1 and 20 MeV

G. L. Morgan, F. G. Perey

Nuclear Science and Engineering / Volume 61 / Number 3 / November 1976 / Pages 337-345

Technical Paper / dx.doi.org/10.13182/NSE76-A26919

Neutron Capture Cross Section of Cobalt-59 in the Energy Range 2.5 to 1000 keV

R. R. Spencer, R. L. Macklin

Nuclear Science and Engineering / Volume 61 / Number 3 / November 1976 / Pages 346-355

Technical Paper / dx.doi.org/10.13182/NSE76-A26920

Neutron Absorption Cross Section of Americium-241

L. W. Weston, J. H. Todd

Nuclear Science and Engineering / Volume 61 / Number 3 / November 1976 / Pages 356-365

Technical Paper / dx.doi.org/10.13182/NSE76-A26921

Light Charged Particles and Fission Elements from Californium-252 Fission

Charles A. Bolig, Jr., R. R. Roy

Nuclear Science and Engineering / Volume 61 / Number 3 / November 1976 / Pages 366-369

Technical Paper / dx.doi.org/10.13182/NSE76-A26922

Critical Experiments with Low-Moderated Homogeneous Mixtures of Plutonium and Uranium Oxides Containing 8, 15, and 30 wt% Plutonium

S. R. Bierman, E. D. Clayton

Nuclear Science and Engineering / Volume 61 / Number 3 / November 1976 / Pages 370-376

Technical Paper / dx.doi.org/10.13182/NSE76-A26923

A Simple Approximate Treatment of Neutron Inelastic Scattering in a Fast Reactor Assembly

Yasunori Yamamura

Nuclear Science and Engineering / Volume 61 / Number 3 / November 1976 / Pages 377-387

Technical Paper / dx.doi.org/10.13182/NSE76-A26924

Synthesis of an Elementary Function for the Spatially Dependent Neutron Slowing Down Distribution in Hydrogen

Harvey J. Amster, K. Cheuk Chan

Nuclear Science and Engineering / Volume 61 / Number 3 / November 1976 / Pages 388-398

Technical Paper / dx.doi.org/10.13182/NSE76-A26925

Stability Analysis of Spatially Dependent Nonlinear Reactor Systems Using a Semigroup Approach

Ronald J. Onega, Lech Mync, John A. Burns

Nuclear Science and Engineering / Volume 61 / Number 3 / November 1976 / Pages 399-407

Technical Paper / dx.doi.org/10.13182/NSE76-A26926

A Method of Characteristics and Other Improvements in Solution Methods for the Transport Equation

Bengt G. Carlson

Nuclear Science and Engineering / Volume 61 / Number 3 / November 1976 / Pages 408-425

Technical Paper / dx.doi.org/10.13182/NSE76-A26927

Observation of a Difference in Yields of Delayed Neutron Emitters from U₃O₈ and UO₂

H. R. Lukens, R. L. Bramblett

Nuclear Science and Engineering / Volume 61 / Number 3 / November 1976 / Pages 426-428

Technical Note / dx.doi.org/10.13182/NSE76-A26928

Critical Experiments and the 2200 m/sec Neutron Parameters

R. Gwin

Nuclear Science and Engineering / Volume 61 / Number 3 / November 1976 / Pages 428-431

Technical Note / dx.doi.org/10.13182/NSE76-A26929

Acceleration of the Convergence of the Integral Transform Method

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

Nuclear Science and Engineering / Volume 61 / Number 3 / November 1976 / Pages 431-434

Technical Note / dx.doi.org/10.13182/NSE76-A26930

Generalized Exact Spatially Dependent Neutron Slowing Down Distribution Near Source Lethargy

K. Cheuk Chan, Harvey J. Amster

Nuclear Science and Engineering / Volume 61 / Number 3 / November 1976 / Pages 434-437

Technical Note / dx.doi.org/10.13182/NSE76-A26931

Control Algorithms in a Coarse-Mesh Rebalance Framework

M. V. Gregory, H. C. Honeck

Nuclear Science and Engineering / Volume 61 / Number 3 / November 1976 / Pages 437-445

Technical Note / dx.doi.org/10.13182/NSE76-A26932

An Early-Time Analysis of Space-Dependent Nuclear Reactor Transients

S. L. Paveri-Fontana, P. L. Chambré

Nuclear Science and Engineering / Volume 61 / Number 4 / December 1976 / Pages 451-465

Technical Paper / dx.doi.org/10.13182/NSE76-A14482

Reactor-Fuel-Independent Reactivity Determinations

S. Pearlstein

Nuclear Science and Engineering / Volume 61 / Number 4 / December 1976 / Pages 466-470

Technical Paper / dx.doi.org/10.13182/NSE76-A14483

Measurement of the Ratio of Fission to Capture Neutron Cross Sections in Uranium-235 in the 200-eV to 15-keV Energy Range

H. Bluhm, C. S. Yen

Nuclear Science and Engineering / Volume 61 / Number 4 / December 1976 / Pages 471-476

Technical Paper / dx.doi.org/10.13182/NSE76-A14484

Fission Cross Section of Neptunium-237 from 3 eV to 2 MeV

S. Plattard, J. Blons, D. Paya

Nuclear Science and Engineering / Volume 61 / Number 4 / December 1976 / Pages 477-495

Technical Paper / dx.doi.org/10.13182/NSE76-A14485

The ENDF/B-IV Representation of the Uranium-238, Total Neutron Cross Section in the Resolved Resonance Energy Region

G. de Saussure, D. K. Olsen, R. B. Perez

Nuclear Science and Engineering / Volume 61 / Number 4 / December 1976 / Pages 496-506

Technical Paper / dx.doi.org/10.13182/NSE76-A14486

Measurement of the Angular Neutron Energy Spectra Originating from a 14-MeV Neutron Source in Liquid Air

K. Clausen, B. Bröcker, P. Schneider-Kühnle, M. Weinert

Nuclear Science and Engineering / Volume 61 / Number 4 / December 1976 / Pages 507-520

Technical Paper / dx.doi.org/10.13182/NSE76-A14487

Differential Elastic and Inelastic Scattering of 9- to 15-MeV Neutrons from Carbon

D. W. Glasgow, F. O. Purser, H. Hogue, J. C. Clement, K. Stelzer, G. Mack, J. R. Boyce, D. H. Epperson, S. G. Buccino, P. W. Lisowski, S. G. Glendinning, E. G. Bilpuch, H. W. Newson, C. R. Gould

Nuclear Science and Engineering / Volume 61 / Number 4 / December 1976 / Pages 521-533

Technical Paper / dx.doi.org/10.13182/NSE76-A14488

Spherical Harmonics Approximations of Neutron Transport

A. Demény, K. M. Dede, K. Erdei

Nuclear Science and Engineering / Volume 61 / Number 4 / December 1976 / Pages 534-535

Technical Note / dx.doi.org/10.13182/NSE76-A14489

A Numerical Method for Solving the Integral Equation of Neutron Transport: III

Robert W. Tsai, Sudarshan K. Loyalka

Nuclear Science and Engineering / Volume 61 / Number 4 / December 1976 / Pages 536-540

Technical Note / dx.doi.org/10.13182/NSE76-A14490

Measurement of Cross Sections for the ⁷Li(n, n′γ)⁷Li Reaction from 0.57 to 4 MeV

Donald L. Smith

Nuclear Science and Engineering / Volume 61 / Number 4 / December 1976 / Pages 540-543

Technical Note / dx.doi.org/10.13182/NSE76-A14491

Rational Approximations for Cross-Section Space-Shielding in Doubly Heterogeneous Systems

M. G. Stamatelatos

Nuclear Science and Engineering / Volume 61 / Number 4 / December 1976 / Pages 543-549

Technical Note / dx.doi.org/10.13182/NSE76-A14492

Basic Collapse Criteria for Boiling Reactor-Fuel-Steel Mixtures

Paul B. Abramson

Nuclear Science and Engineering / Volume 61 / Number 4 / December 1976 / Pages 549-552

Technical Note / dx.doi.org/10.13182/NSE76-A14493