ANS / Publications / Journals / Nuclear Science and Engineering

Neutron-Induced Fission in a DT-Plutonium Plasma. Part I: Fission Fragment Slowing Down

S. T. Perkins

Nuclear Science and Engineering / Volume 69 / Number 2 / February 1979 / Pages 137-146

Technical Paper / dx.doi.org/10.13182/NSE79-A20605

Neutron-Induced Fission in a DT-Plutonium Plasma. Part II: Enhancement of Neutron Production and Fusion Rate

S. T. Perkins

Nuclear Science and Engineering / Volume 69 / Number 2 / February 1979 / Pages 147-155

Technical Paper / dx.doi.org/10.13182/NSE79-A20606

The F_N Method in Neutron-Transport Theory. Part I: Theory and Applications

C. E. Siewert, P. Benoist

Nuclear Science and Engineering / Volume 69 / Number 2 / February 1979 / Pages 156-160

Technical Paper / dx.doi.org/10.13182/NSE79-1

The F_N Method in Neutron-Transport Theory. Part II: Applications and Numerical Results

P. Grandjean, C. E. Siewert

Nuclear Science and Engineering / Volume 69 / Number 2 / February 1979 / Pages 161-168

Technical Paper / dx.doi.org/10.13182/NSE79-A20608

Spectral Fine-Structure Effects on Material and Doppler Reactivity Worths

E. Greenspan, Y. Karni

Nuclear Science and Engineering / Volume 69 / Number 2 / February 1979 / Pages 169-190

Technical Paper / dx.doi.org/10.13182/NSE79-A20609

Neutron Scattering Cross Sections of Uranium-238

L. E. Beghian, G. H. R. Kegel, T. V. Marcella, B. K. Barnes, G. P. Couchell, J. J. Egan, A. Mittler, D. J. Pullen, W. A. Schier

Nuclear Science and Engineering / Volume 69 / Number 2 / February 1979 / Pages 191-201

Technical Paper / dx.doi.org/10.13182/NSE79-A20610

Measurement and Resonance Analysis of Neutron Transmission Through Uranium-238

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

Nuclear Science and Engineering / Volume 69 / Number 2 / February 1979 / Pages 202-222

Technical Paper / dx.doi.org/10.13182/NSE79-A20611

Differential Neutron Scattering Cross Sections of Lithium-6 and Lithium-7 for Neutrons of 4 to 7.5 MeV Energy

H. D. Knox, R. M. White, R. O. Lane

Nuclear Science and Engineering / Volume 69 / Number 2 / February 1979 / Pages 223-230

Technical Paper / dx.doi.org/10.13182/NSE79-A20612

Critical Experiments on Light Water Lattices of UO₂ and Gd₂O₃ Rods

Tohru Haga, Sadao Hanazawa, Toshio Kimura

Nuclear Science and Engineering / Volume 69 / Number 2 / February 1979 / Pages 231-244

Technical Paper / dx.doi.org/10.13182/NSE79-A20613

Criticality of a Slab Reactor with Finite Reflectors

Trine-Yie Dawn

Nuclear Science and Engineering / Volume 69 / Number 2 / February 1979 / Pages 245-250

Technical Paper / dx.doi.org/10.13182/NSE79-A20614

A Model for the Prediction of Shutdown Margin for Boiling Water Reactors

Warren F. Witzig, Ross T. Thomas

Nuclear Science and Engineering / Volume 69 / Number 2 / February 1979 / Pages 251-263

Technical Paper / dx.doi.org/10.13182/NSE79-A20615

Fast Integral Modeling of Hypothetical Core Disruptive Accidents in Liquid-Metal Fast Breeder Reactors

C. J. Mueller, J. K. Vaurio

Nuclear Science and Engineering / Volume 69 / Number 2 / February 1979 / Pages 264-278

Technical Paper / dx.doi.org/10.13182/NSE79-A20616

Network Computations Using a Transient Two-Phase Velocity Difference Model

Robert W. Lyczkowski, Delwin C. Mecham, Charles W. Solbrig

Nuclear Science and Engineering / Volume 69 / Number 2 / February 1979 / Pages 279-289

Technical Paper / dx.doi.org/10.13182/NSE79-A20617

Laminar, Transition, and Turbulent Parallel Flow Pressure Drop Across Wire-Wrap-Spaced Rod Bundles

F. C. Engel, R. A. Markley, A. A. Bishop

Nuclear Science and Engineering / Volume 69 / Number 2 / February 1979 / Pages 290-296

Technical Paper / dx.doi.org/10.13182/NSE79-A20618

Multichannel Model for Relocation of Molten Fuel Cladding in Unprotected Loss-of-Flow Accidents in Liquid-Metal Fast Breeder Reactors

M. Ishii, W. L. Chen, M. A. Grolmes

Nuclear Science and Engineering / Volume 69 / Number 2 / February 1979 / Pages 297-318

Technical Paper / dx.doi.org/10.13182/NSE79-2

Pressure Pulses Generated by Gas Released from a Breached Fuel Element

Ting-Shu Wu

Nuclear Science and Engineering / Volume 69 / Number 2 / February 1979 / Pages 319-325

Technical Paper / dx.doi.org/10.13182/NSE79-A20620

Introduction of the Quasi-Static Synthesis Method for Solution of Space-Time Reactor Kinetics Problems

Bruce I. Hauss, William E. Kastenberg

Nuclear Science and Engineering / Volume 69 / Number 2 / February 1979 / Pages 326-333

Technical Note / dx.doi.org/10.13182/NSE79-A20621

Measurement and Calculation of Average Activation Cross Sections in the Spontaneous Fission Neutron Field of ²⁵²Cf

W. Mannhart, W. G. Alberts

Nuclear Science and Engineering / Volume 69 / Number 2 / February 1979 / Pages 333-338

Technical Note / dx.doi.org/10.13182/NSE79-A20622