Progress in Multidimensional Neutron Transport Computation
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
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
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
Nuclear Science and Engineering / Volume 64 / Number 2 / October 1977 / Pages 317-331
Technical Paper / dx.doi.org/10.13182/NSE77-A27373
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
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
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
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
Nuclear Science and Engineering / Volume 64 / Number 2 / October 1977 / Pages 379-383
Technical Paper / dx.doi.org/10.13182/NSE77-A27378
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
Nuclear Science and Engineering / Volume 64 / Number 2 / October 1977 / Pages 405-417
Technical Paper / dx.doi.org/10.13182/NSE77-A27380
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
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
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
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
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
Nuclear Science and Engineering / Volume 64 / Number 2 / October 1977 / Pages 508-516
Technical Paper / dx.doi.org/10.13182/NSE77-A27386
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
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
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
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
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
Nuclear Science and Engineering / Volume 64 / Number 2 / October 1977 / Pages 582-592
Technical Paper / dx.doi.org/10.13182/NSE77-A27392
Nuclear Science and Engineering / Volume 64 / Number 2 / October 1977 / Pages 593-604
Technical Paper / dx.doi.org/10.13182/NSE77-5
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
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
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
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
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
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
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
Nuclear Science and Engineering / Volume 64 / Number 2 / October 1977 / Pages 694-708
Technical Paper / dx.doi.org/10.13182/NSE77-A27401