ANS / Publications / Journals / Nuclear Science and Engineering

Higher Order Prompt-Jump Approximation in Reactor Kinetics

Tomasz Błeński, Adam Gadomski, Janusz Mika

Nuclear Science and Engineering / Volume 66 / Number 3 / June 1978 / Pages 277-283

Technical Paper / dx.doi.org/10.13182/NSE78-A27212

Analysis of the Eigenvalue Equations in k, λ, γ, and α Applied to Some Fast- and Thermal-Neutron Systems

Guillermo Velarde, Carolina Ahnert, José M. Aragonés

Nuclear Science and Engineering / Volume 66 / Number 3 / June 1978 / Pages 284-294

Technical Paper / dx.doi.org/10.13182/NSE78-A27213

Polynomial Solutions to the Tensorial Differential Equations for Monoenergetic Neutrons in Slab and Sphere Geometries

P. Landini, G. Spiga, F. Premuda

Nuclear Science and Engineering / Volume 66 / Number 3 / June 1978 / Pages 295-306

Technical Paper / dx.doi.org/10.13182/NSE78-A27214

Application of Sensitivity and Uncertainty Methodology to Fast Reactor Integral Experiment Analysis

C. R. Weisbin, E. M. Oblow, J. H. Marable, R. W. Peelle, J. L. Lucius

Nuclear Science and Engineering / Volume 66 / Number 3 / June 1978 / Pages 307-333

Technical Paper / dx.doi.org/10.13182/NSE78-3

Calculation of Nuclear Level Densities for ⁵⁶Fe, ⁵⁹Co, ⁶⁰Ni, ⁶¹Cu, ⁶²Ni, ⁶³Cu, and ⁶⁵Cu

G. P. Ford

Nuclear Science and Engineering / Volume 66 / Number 3 / June 1978 / Pages 334-348

Technical Paper / dx.doi.org/10.13182/NSE78-A27216

Precise Measurement of the Capture Width of the 6.67-eV Neutron Resonance of Uranium-238

P. Staveloz, F. Poortmans, L. Mewissen, E. Cornelis

Nuclear Science and Engineering / Volume 66 / Number 3 / June 1978 / Pages 349-353

Technical Paper / dx.doi.org/10.13182/NSE78-A27217

Measurement and Calculation of Californium-252 Fission Neutron-Induced Gamma Fields in Iron

S. H. Jiang, H. Werle

Nuclear Science and Engineering / Volume 66 / Number 3 / June 1978 / Pages 354-362

Technical Paper / dx.doi.org/10.13182/NSE78-A27218

Neutron Capture Cross-Section Ratios of ²⁴⁰Pu, ²⁴²Pu, ²³⁸U, and ¹⁹⁷Au in the Energy Range from 10 to 90 keV

K. Wisshak, F. Käppeler

Nuclear Science and Engineering / Volume 66 / Number 3 / June 1978 / Pages 363-377

Technical Paper / dx.doi.org/10.13182/NSE78-A27219

Characteristics and Stability Analyses of Transient One-Dimensional Two-Phase Flow Equations and Their Finite Difference Approximations

Robert W. Lyczkowski, Dimitri Gidaspow, Charles W. Solbrig, E. D. Hughes

Nuclear Science and Engineering / Volume 66 / Number 3 / June 1978 / Pages 378-396

Technical Paper / dx.doi.org/10.13182/NSE78-4

Effects of Internal Circulation Velocity and Noncondensable Gas on Vapor Condensation from a Rising Bubble

M. N. Özişik, T. S. Kress

Nuclear Science and Engineering / Volume 66 / Number 3 / June 1978 / Pages 397-405

Technical Paper / dx.doi.org/10.13182/NSE78-A27221

Self-Diffusion Processes in Nuclear Carbonitrides UC_xN_{1 − x} and (U, Pu)C_0.8N_0.2

H. Matsui, M. H. Bradbury, Hj. Matzke

Nuclear Science and Engineering / Volume 66 / Number 3 / June 1978 / Pages 406-414

Technical Paper / dx.doi.org/10.13182/NSE78-A27222

Fast Power Excursions in Pebble-Bed Reactors—Methods and Results

K. Friedrich, E. Inführ, U. Weicht

Nuclear Science and Engineering / Volume 66 / Number 3 / June 1978 / Pages 415-421

Technical Note / dx.doi.org/10.13182/NSE78-A27223

A General Correlation for Independent Fission Product Yield Uncertainties

B. I. Spinrad, C. H. Wu

Nuclear Science and Engineering / Volume 66 / Number 3 / June 1978 / Pages 421-424

Technical Note / dx.doi.org/10.13182/NSE78-A27224

Evaluation of the Neutron Flux-Depression Factor via the Integral Transform Method

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

Nuclear Science and Engineering / Volume 66 / Number 3 / June 1978 / Pages 424-428

Technical Note / dx.doi.org/10.13182/NSE78-A27225

Transport of Neutron and Secondary Gamma Radiations Through a Liquid Air Sphere Surrounding a 14-MeV Neutron Source

G. S. Sidhu, W. E. Farley, L. F. Hansen, T. Komoto, B. Pohl, C. Wong

Nuclear Science and Engineering / Volume 66 / Number 3 / June 1978 / Pages 428-433

Technical Note / dx.doi.org/10.13182/NSE78-A27226

Measurements of the Neutron-Induced Fission Cross Sections of ²⁴⁰Pu, ²⁴²Pu, and ²⁴⁴Pu Relative to ²³⁵U from 0.1 to 30 MeV

J. W. Behrens, R. S. Newbury, J. W. Magana

Nuclear Science and Engineering / Volume 66 / Number 3 / June 1978 / Pages 433-441

Technical Note / dx.doi.org/10.13182/NSE78-A27227

⁶Li + ⁶Li ⇒ 3⁴He Cross Sections and Thermonuclear Fusion Parameters

E. Norbeck

Nuclear Science and Engineering / Volume 66 / Number 3 / June 1978 / Pages 441-444

Technical Note / dx.doi.org/10.13182/NSE78-A27228