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Volume 50

Number 3

Numerical Methods of High Order Accuracy for One-Dimensional Diffusion Equation

J. P. Hennart

Nuclear Science and Engineering / Volume 50 / Number 3 / March 1973 / Pages 185-199

Technical Paper / dx.doi.org/10.13182/NSE73-A28971

The Neutron Diffusion Coefficient as a Second-Order Tensor—Theory and Calculations

V. C. Boffi, T. Trombetti

Nuclear Science and Engineering / Volume 50 / Number 3 / March 1973 / Pages 200-207

Technical Paper / dx.doi.org/10.13182/NSE73-A28972

Delayed Neutron Data for Fast Reactor Analysis

J. E. Cahalan, K. O. Ott

Nuclear Science and Engineering / Volume 50 / Number 3 / March 1973 / Pages 208-215

Technical Paper / dx.doi.org/10.13182/NSE73-A28973

On the Applicability of Sjöstrand’s Area Method for Reactivity Measurement by the Pulsed-Neutron Technique

Jan B. Dragt

Nuclear Science and Engineering / Volume 50 / Number 3 / March 1973 / Pages 216-219

Technical Paper / dx.doi.org/10.13182/NSE73-A28974

A Bilinear Formulation for Spatial Cross-Section Averaging

Masaoki Komata, Richard B. Nicholson, Earl M. Page

Nuclear Science and Engineering / Volume 50 / Number 3 / March 1973 / Pages 220-228

Technical Paper / dx.doi.org/10.13182/NSE73-A28975

A Study of Several Methods for Analysis of Critical Assembly Heterogeneity

R. G. Palmer, J. P. Plummer, R. B. Nicholson

Nuclear Science and Engineering / Volume 50 / Number 3 / March 1973 / Pages 229-242

Technical Paper / dx.doi.org/10.13182/NSE73-A28976

The Total Neutron Cross Sections of Uranium-238 from 0.8 to 30 MeV

S. H. Hayes, P. Stoler, J. M. Clement, C. A. Goulding

Nuclear Science and Engineering / Volume 50 / Number 3 / March 1973 / Pages 243-247

Technical Paper / dx.doi.org/10.13182/NSE73-A28977

Measurement of Bremsstrahlung Spectra Produced in Iron and Tungsten Targets by 15-MeV Electrons with Activation Detectors

Hideo Hirayama, Takashi Nakamura

Nuclear Science and Engineering / Volume 50 / Number 3 / March 1973 / Pages 248-256

Technical Paper / dx.doi.org/10.13182/NSE73-A28978

The Californium-252 Fission Neutron Spectrum from 0.5 to 13 MeV

L. Green, J. A. Mitchell, N. M. Steen

Nuclear Science and Engineering / Volume 50 / Number 3 / March 1973 / Pages 257-272

Technical Paper / dx.doi.org/10.13182/NSE73-A28979

A Study of Fission-Fragment-Induced Nucleation of Bubbles in Superheated Water

L. W. Deitrich, T. J. Connolly

Nuclear Science and Engineering / Volume 50 / Number 3 / March 1973 / Pages 273-282

Technical Paper / dx.doi.org/10.13182/NSE73-A28980

Thermal Contact Conductance in Reactor Fuel Elements

Gary Jacobs, Neil Todreas

Nuclear Science and Engineering / Volume 50 / Number 3 / March 1973 / Pages 283-290

Technical Note / dx.doi.org/10.13182/NSE73-A28981

Errors in Perturbation Calculations

C. W. J. McCallien

Nuclear Science and Engineering / Volume 50 / Number 3 / March 1973 / Pages 290-293

Technical Note / dx.doi.org/10.13182/NSE73-A28982

Second-Order Boltzmann Equation from Invariant Imbedding Theory

Zbigniew Weiss

Nuclear Science and Engineering / Volume 50 / Number 3 / March 1973 / Pages 294-297

Technical Note / dx.doi.org/10.13182/NSE73-A28983

Computational Experimentation on the Finite Element Method in Bare Slab Criticality Calculations

Juhani Pitkäranta, Pekka Silvennoinen

Nuclear Science and Engineering / Volume 50 / Number 3 / March 1973 / Pages 297-300

Technical Note / dx.doi.org/10.13182/NSE73-A28984

Variational Estimates of the Detector Response Change in a Fixed Source System Due to Cross-Section Perturbations

T. J. Hoffman

Nuclear Science and Engineering / Volume 50 / Number 3 / March 1973 / Pages 300-302

Technical Note / dx.doi.org/10.13182/NSE73-A28985

In-Core Neutron Flux Distribution Measurement by a Circulating Fluid Activation Method

Masaaki Fujii

Nuclear Science and Engineering / Volume 50 / Number 3 / March 1973 / Pages 302-306

Technical Note / dx.doi.org/10.13182/NSE73-A28986