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Volume 64

Number 2

Progress in Multidimensional Neutron Transport Computation

E. E. Lewis

Nuclear Science and Engineering / Volume 64 / Number 2 / October 1977 / Pages 279-293

Technical Paper / dx.doi.org/10.13182/NSE77-A27370

Neutron Transport Methods in Neutrino Transport Calculations

S. A. Bludman, I. Lichtenshtadt, A. Ron, N. Sack, J. J. Wagschal

Nuclear Science and Engineering / Volume 64 / Number 2 / October 1977 / Pages 294-298

Technical Paper / dx.doi.org/10.13182/NSE77-A27371

Compatible Product Angular Quadrature for Neutron Transport in x-y Geometry

I. K. Abu-Shumays

Nuclear Science and Engineering / Volume 64 / Number 2 / October 1977 / Pages 299-316

Technical Paper / dx.doi.org/10.13182/NSE64-299

The Generation of Time-Dependent Neutron Transport Solutions in Infinite Media

B. D. Ganapol, P. W. McKenty, K. L. Peddicord

Nuclear Science and Engineering / Volume 64 / Number 2 / October 1977 / Pages 317-331

Technical Paper / dx.doi.org/10.13182/NSE77-A27373

Application of Space-Angle Synthesis to Two-Dimensional Neutral-Particle Transport Problems of Weapon Physics

Richard M. Roberds, Charles J. Bridgman

Nuclear Science and Engineering / Volume 64 / Number 2 / October 1977 / Pages 332-343

Technical Paper / dx.doi.org/10.13182/NSE77-A27374

Diffusion Synthetic Acceleration Methods for the Diamond-Differenced Discrete-Ordinates Equations

R. E. Alcouffe

Nuclear Science and Engineering / Volume 64 / Number 2 / October 1977 / Pages 344-355

Technical Paper / dx.doi.org/10.13182/NSE77-1

The Direct-Coupled-Ray Method for Design-Oriented Three-Dimensional Transport Analysis

James A. Bucholz, Claude G. Poncelet

Nuclear Science and Engineering / Volume 64 / Number 2 / October 1977 / Pages 356-372

Technical Paper / dx.doi.org/10.13182/NSE77-A27376

Ray Tracing in Axisymmetric Toroidal Coordinates

S. L. Gralnick, H. E. Dalhed

Nuclear Science and Engineering / Volume 64 / Number 2 / October 1977 / Pages 373-378

Technical Paper / dx.doi.org/10.13182/NSE77-A27377

Charged Particle Energy Deposition in an Inertially Confined Thermonuclear Plasma

Michael J. Antal, Clarence E. Lee

Nuclear Science and Engineering / Volume 64 / Number 2 / October 1977 / Pages 379-383

Technical Paper / dx.doi.org/10.13182/NSE77-A27378

Approximate Solutions of the Two-Dimensional Integral Transport Equation by Collision Probability Methods

Richard Sanchez

Nuclear Science and Engineering / Volume 64 / Number 2 / October 1977 / Pages 384-404

Technical Paper / dx.doi.org/10.13182/NSE64-384

Nodal Coupling by Response Matrix Principles

A. Ancona, M. Becker, M. D. Beg, D. R. Harris, A. DaC. Menezes, D. M. VerPlanck, E. Pilat

Nuclear Science and Engineering / Volume 64 / Number 2 / October 1977 / Pages 405-417

Technical Paper / dx.doi.org/10.13182/NSE77-A27380

Mathematical and Computational Techniques Employed in the Deterministic Approach to Liquid-Metal Fast Breeder Reactor Safety

Alan E. Waltar, Andrew Padilla, Jr.

Nuclear Science and Engineering / Volume 64 / Number 2 / October 1977 / Pages 418-451

Technical Paper / dx.doi.org/10.13182/NSE77-A27381

Probabilistic Fast Reactor Accident Analysis

Karl O. Ott

Nuclear Science and Engineering / Volume 64 / Number 2 / October 1977 / Pages 452-464

Technical Paper / dx.doi.org/10.13182/NSE77-A27382

A Numerical Model of Reactor Fuel and Coolant Motions Following Pin Failure

P. A. Pizzica, P. B. Abramson

Nuclear Science and Engineering / Volume 64 / Number 2 / October 1977 / Pages 465-479

Technical Paper / dx.doi.org/10.13182/NSE77-A27383

Simulation of Transients in Liquid-Metal Fast Breeder Reactor Systems

A. K. Agrawal, J. G. Guppy, I. K. Madni, V. Quan, W. L. Weaver III, J. W. Yang

Nuclear Science and Engineering / Volume 64 / Number 2 / October 1977 / Pages 480-491

Technical Paper / dx.doi.org/10.13182/NSE77-A27384

Smoothing and Extrapolation Techniques for Reactor Kinetics

R. D. Lawrence, J. J. Dorning

Nuclear Science and Engineering / Volume 64 / Number 2 / October 1977 / Pages 492-507

Technical Paper / dx.doi.org/10.13182/NSE77-A27385

High-Order Schemes for Neutron Kinetics Calculations, Based on a Local Polynomial Approximation

S. Langenbuch, W. Maurer, W. Werner

Nuclear Science and Engineering / Volume 64 / Number 2 / October 1977 / Pages 508-516

Technical Paper / dx.doi.org/10.13182/NSE77-A27386

Conservation of the Adjoint Neutron Spectrum by Use of Bilinear-Weighted Cross Sections and Its Effect on Fast Reactor Calculations

D. C. Wade, R. G. Bucher

Nuclear Science and Engineering / Volume 64 / Number 2 / October 1977 / Pages 517-538

Technical Paper / dx.doi.org/10.13182/NSE77-A27387

Method for Generating Neutronic Data Bases for Transient Reactor Calculations

M. R. Buckner, P. B. Parks

Nuclear Science and Engineering / Volume 64 / Number 2 / October 1977 / Pages 539-551

Technical Paper / dx.doi.org/10.13182/NSE77-A27388

Current Trends in Methods for Neutron Diffusion Calculations

C. H. Adams

Nuclear Science and Engineering / Volume 64 / Number 2 / October 1977 / Pages 552-562

Technical Paper / dx.doi.org/10.13182/NSE77-A27389

A Finite Element Depletion Diffusion Calculation Method with Space-Dependent Cross Sections

Alain Kavenoky, Jean-Jacques Lautard

Nuclear Science and Engineering / Volume 64 / Number 2 / October 1977 / Pages 563-575

Technical Paper / dx.doi.org/10.13182/NSE77-A27390

The Energy-Dependent Finite Element Method for Two-Dimensional Diffusion Problems

Hideko Komoriya, Wallace F. Walters

Nuclear Science and Engineering / Volume 64 / Number 2 / October 1977 / Pages 576-581

Technical Paper / dx.doi.org/10.13182/NSE77-A27391

Two Nodal Methods for Solving Time-Dependent Group Diffusion Equations

R. A. Shober, R. N. Sims, A. F. Henry

Nuclear Science and Engineering / Volume 64 / Number 2 / October 1977 / Pages 582-592

Technical Paper / dx.doi.org/10.13182/NSE77-A27392

Optimized Iteration Strategies and Data Management Considerations for Fast Reactor Finite Difference Diffusion Theory Codes

D. R. Ferguson, K. L. Derstine

Nuclear Science and Engineering / Volume 64 / Number 2 / October 1977 / Pages 593-604

Technical Paper / dx.doi.org/10.13182/NSE77-5

Theory, Capabilities, and Use of the Three-Dimensional Reactor Operation and Control Simulator (ROCS)

T. G. Ober, J. C. Stork, I. C. Rickard, J. K. Gasper

Nuclear Science and Engineering / Volume 64 / Number 2 / October 1977 / Pages 605-623

Technical Paper / dx.doi.org/10.13182/NSE77-A27394

Calculations of Void Streaming in the Argonne Gas-Cooled Fast Reactor Critical Experiments

E. M. Gelbard, D. C. Wade, R. W. Schaefer, R. E. Phillips

Nuclear Science and Engineering / Volume 64 / Number 2 / October 1977 / Pages 624-637

Technical Paper / dx.doi.org/10.13182/NSE77-A27395

Convergence Results and Asymptotic Error Estimates for Galerkin-Type Spectral Synthesis

Paul Nelson, Harold D. Meyer

Nuclear Science and Engineering / Volume 64 / Number 2 / October 1977 / Pages 638-643

Technical Paper / dx.doi.org/10.13182/NSE77-A27396

Methods for Identification of Dynamic Systems

B. Frogner, B. Friedlander, H. S. Rao

Nuclear Science and Engineering / Volume 64 / Number 2 / October 1977 / Pages 644-656

Technical Paper / dx.doi.org/10.13182/NSE77-A27397

Spatial Reactor Control Methods

Jorma Karppinen

Nuclear Science and Engineering / Volume 64 / Number 2 / October 1977 / Pages 657-672

Technical Paper / dx.doi.org/10.13182/NSE77-A27398

Identification of Nuclear Plant Parameters Using Experimental Data and High-Order Dynamic Models

S. I. Chang, T. W. Kerlin

Nuclear Science and Engineering / Volume 64 / Number 2 / October 1977 / Pages 673-683

Technical Paper / dx.doi.org/10.13182/NSE77-A27399

Reactor Fuel Reliability Constraints on Power Shape Control

Floyd Gelhaus, John Hallam, Tor Sauar

Nuclear Science and Engineering / Volume 64 / Number 2 / October 1977 / Pages 684-693

Technical Paper / dx.doi.org/10.13182/NSE77-A27400

Optimal Pin Enrichment Distributions in Boiling Water Reactor Fuel Bundles

E. Y. Lim, A. Leonard

Nuclear Science and Engineering / Volume 64 / Number 2 / October 1977 / Pages 694-708

Technical Paper / dx.doi.org/10.13182/NSE77-A27401