ANS / Publications / Journals / Nuclear Science and Engineering

Accuracy of Coarse Group Calculations in Fast Reactors

D. Antonakas, R. Corcuera, P. Govaerts

Nuclear Science and Engineering / Volume 48 / Number 1 / May 1972 / Pages 1-9

Technical Paper / dx.doi.org/10.13182/NSE72-A22451

A Generalized Model for the Elastic and Inelastic Slowing Down of Fast Neutrons

B. Rocca-Volmerange

Nuclear Science and Engineering / Volume 48 / Number 1 / May 1972 / Pages 10-15

Technical Paper / dx.doi.org/10.13182/NSE72-A22452

Synthesis of Three-Dimensional Transport Problems Using Two-Dimensional Trial Functions

M. Natelson

Nuclear Science and Engineering / Volume 48 / Number 1 / May 1972 / Pages 16-27

Technical Paper / dx.doi.org/10.13182/NSE72-A22453

Explosive Disassembly of Fast Reactors

John C. Lee, Thomas H. Pigford

Nuclear Science and Engineering / Volume 48 / Number 1 / May 1972 / Pages 28-44

Technical Paper / dx.doi.org/10.13182/NSE72-A22454

Measurement and Analysis of Neutron Spectra in a Fast Subcritical Assembly Containing Uranium-235, Uranium-238, and Beryllium Oxide

J. C. Young, J. M. Neill, P. d’Oultremont, E.L. Slaggie, C. A. Preskitt

Nuclear Science and Engineering / Volume 48 / Number 1 / May 1972 / Pages 45-50

Technical Paper / dx.doi.org/10.13182/NSE72-A22455

The Spectral Distribution of Neutrons and Neutron Reaction Cross Sections in an Unreflected Uranium-235 Critical Assembly and the Fission Neutron Spectrum

W. N. McElroy, R. J. Armani, E. Tochilin

Nuclear Science and Engineering / Volume 48 / Number 1 / May 1972 / Pages 51-71

Technical Paper / dx.doi.org/10.13182/NSE72-A22456

On the Energy Loss of Fission Fragments in Composite Systems

M. Hakim, N. H. Shafrir

Nuclear Science and Engineering / Volume 48 / Number 1 / May 1972 / Pages 72-77

Technical Paper / dx.doi.org/10.13182/NSE72-A22457

The Neutron Induced Gamma-Ray Reactions in Calcium in the Energy Range 4.85≤ E_n ≤8.05 MeV

J. K. Dickens

Nuclear Science and Engineering / Volume 48 / Number 1 / May 1972 / Pages 78-86

Technical Paper / dx.doi.org/10.13182/NSE72-A22458

Periodicity in Annular Diffuser Flow

F. R. Fricke

Nuclear Science and Engineering / Volume 48 / Number 1 / May 1972 / Pages 87-102

Technical Paper / dx.doi.org/10.13182/NSE72-A22459

Theoretical Heat Transfer Predictions for Finite Nuclear Fuel Rod Assemblies

T. Ginsberg, D. M. France

Nuclear Science and Engineering / Volume 48 / Number 1 / May 1972 / Pages 103-114

Technical Paper / dx.doi.org/10.13182/NSE72-A22460

Extension of Linearly Anisotropic Asymptotic Neutron Diffusion Theory to Reflected Systems

B. L. Koponen, R. J. Doyas

Nuclear Science and Engineering / Volume 48 / Number 1 / May 1972 / Pages 115-118

Technical Paper / dx.doi.org/10.13182/NSE72-A22461

On the Scattering Matrix Construction for the Discrete Energy Representation of Thermal-Neutron Spectra

M. V. Mataušek

Nuclear Science and Engineering / Volume 48 / Number 1 / May 1972 / Pages 119-120

Technical Paper / dx.doi.org/10.13182/NSE72-A22462

Linearization of Sparrow and Koopman’s Method for Heat Transfer with Variable Conductivity

Marc Dixmier

Nuclear Science and Engineering / Volume 48 / Number 1 / May 1972 / Pages 121-122

Technical Paper / dx.doi.org/10.13182/NSE72-A22463