Home / Publications / Journals / Nuclear Science and Engineering / Volume 53 / Number 4

Volume 53

Number 4

Table of Contents
Scattering Theory(Paul F. Zweifel)
The Invariant Imbedding Theory of Nuclear Transport(G. C. Pomraning)
Environmental Radioactivity(Karl Z. Morgan)
Measurement of the ⁵⁹Ni(n,α) Cross Section for Thermal Neutrons(H. M. Eiland, G. J. Kirouac)

Solution of Standard Diamond Difference Equations for Discrete-Ordinate Neutron Transport Equations Equivalent to the P_L Approximation in x-y Geometry

Jungchung Jung, Nobuo Ohtani, Keisuke Kobayashi, Hiroshi Nishihara

Nuclear Science and Engineering / Volume 53 / Number 4 / April 1974 / Pages 355-369

Technical Paper / dx.doi.org/10.13182/NSE74-A23369

Relative and Absolute Measurements of the Fast-Neutron Fission Cross Section of Uranium-235

W. P. Poenitz

Nuclear Science and Engineering / Volume 53 / Number 4 / April 1974 / Pages 370-392

Technical Paper / dx.doi.org/10.13182/NSE74-A23370

The Use of Californium-252 as a Randomly Pulsed Neutron Source for Prompt-Neutron Decay Measurements

J. T. Mihalczo

Nuclear Science and Engineering / Volume 53 / Number 4 / April 1974 / Pages 393-414

Technical Paper / dx.doi.org/10.13182/NSE74-5

A Study of the 2.8-keV Neutron Resonance of Sodium and an Analysis of the Total Neutron Cross Section up to 50 keV

Janet Seltzer, W. K. Firk

Nuclear Science and Engineering / Volume 53 / Number 4 / April 1974 / Pages 415-419

Technical Paper / dx.doi.org/10.13182/NSE74-A23372

Fine Neutron-Spectrum Effects on Spatial Calculations for Fast-Reactor Design

R. Corcuera, A. Khairallah

Nuclear Science and Engineering / Volume 53 / Number 4 / April 1974 / Pages 420-435

Technical Paper / dx.doi.org/10.13182/NSE74-A23373

A Method of Computing Fission-Product Decay Heat in a Reactor with Time-Dependent Flux

F. W. Barclay, K. W. Dormuth

Nuclear Science and Engineering / Volume 53 / Number 4 / April 1974 / Pages 436-439

Technical Paper / dx.doi.org/10.13182/NSE74-A23374

SINOD—A Nonlinear Lumped-Parameter Model for Steady-State, Transient, and Stability Analysis of Two-Phase Flow in Natural Circulation Boiling-Water Loops

M. R. Mataušek

Nuclear Science and Engineering / Volume 53 / Number 4 / April 1974 / Pages 440-457

Technical Paper / dx.doi.org/10.13182/NSE74-A23375

Radiation-Induced Boiling in Superheated Water and Organic Liquids

C. R. Bell, N. P. Oberle, W. Rohsenow, N. Todreas, C. Tso

Nuclear Science and Engineering / Volume 53 / Number 4 / April 1974 / Pages 458-465

Technical Paper / dx.doi.org/10.13182/NSE74-A23376

Equations of Motion of a Liquid-Submerged Sonic Gas Jet Relative to Fission-Gas-Jet Impingement in Subassemblies of the Liquid Metal Fast Breeder Reactor

T. C. Chawla

Nuclear Science and Engineering / Volume 53 / Number 4 / April 1974 / Pages 466-474

Technical Paper / dx.doi.org/10.13182/NSE74-A23377

Reciprocity Relations in Response Matrix Theory

Sten-Örjan Lindahl

Nuclear Science and Engineering / Volume 53 / Number 4 / April 1974 / Pages 475-478

Technical Note / dx.doi.org/10.13182/NSE74-A23378

The Effect of Local Flux Distortions on the Doppler Effect of Small Fissile Samples

P. H. Kier, M. Salvatores

Nuclear Science and Engineering / Volume 53 / Number 4 / April 1974 / Pages 479-482

Technical Note / dx.doi.org/10.13182/NSE74-A23379

Relationships Between Experimental and Theoretical Parameters in Unresolved Resonance Theory

M. Gyulassy, S. T. Perkins

Nuclear Science and Engineering / Volume 53 / Number 4 / April 1974 / Pages 482-486

Technical Note / dx.doi.org/10.13182/NSE74-A23380

An Assessment of Proposed (n, γn<’) Data Based on Measured and Calculated Neutron Spectra in Uranium Depleted in Uranium-235

Martin Becker, Narinder N. Kaushal

Nuclear Science and Engineering / Volume 53 / Number 4 / April 1974 / Pages 487-488

Technical Note / dx.doi.org/10.13182/NSE74-A23381