Home / Publications / Journals / Nuclear Science and Engineering / Volume 63 / Number 4

Volume 63

Number 4

Table of Contents
Neutron Activation Tables(V. Krivan)
Measurement of Sub-Coulomb-Barrier Charged Particles Emitted from Aluminum and Titanium Bombarded by 15-MeV Neutrons(S. M. Grimes, R. C. Haight, J. D. Anderson)

Nonequilibrium Critical Discharge of Saturated and Subcooled Liquid Freon-11

Michael R. Prisco, Robert E. Henry, Michael N. Hutcherson, John L. Linehan

Nuclear Science and Engineering / Volume 63 / Number 4 / August 1977 / Pages 365-375

Technical Paper / dx.doi.org/10.13182/NSE77-A27054

Estimation of Nuclear Decay Heat for Short-Lived Fission Products

Tadashi Yoshida

Nuclear Science and Engineering / Volume 63 / Number 4 / August 1977 / Pages 376-390

Technical Paper / dx.doi.org/10.13182/NSE77-A27055

Neutron Thermalization Spectrum in a Partially Hydrogenated Terphenyl: Evaluation of Scattering Kernels for Organic Reactor Coolant

H. Alan Robitaille, John S. Hewitt

Nuclear Science and Engineering / Volume 63 / Number 4 / August 1977 / Pages 391-400

Technical Paper / dx.doi.org/10.13182/NSE77-A27056

Double-Differential Beryllium Neutron Cross Sections at Incident Neutron Energies of 5.9, 10.1, and 14.2 MeV

D. M. Drake, G. F. Auchampaugh, E. D. Arthur, C. E. Ragan, P. G. Young

Nuclear Science and Engineering / Volume 63 / Number 4 / August 1977 / Pages 401-412

Technical Paper / dx.doi.org/10.13182/NSE77-A27057

Thermal-Neutron Capture and Fission Cross Sections and Resonance Integrals for Curium-243

C. E. Bemis, Jr., J. H. Oliver, R. Eby, J. Halperin

Nuclear Science and Engineering / Volume 63 / Number 4 / August 1977 / Pages 413-417

Technical Paper / dx.doi.org/10.13182/NSE77-A27058

High-Resolution Fast-Neutron Gamma-Ray Production Cross Sections for Iron up to 2100 keV

W. E. Kinney, F. G. Perey

Nuclear Science and Engineering / Volume 63 / Number 4 / August 1977 / Pages 418-429

Technical Paper / dx.doi.org/10.13182/NSE77-A27059

A Reconciliation of Measurements of for Neutron-Induced Fission of Uranium-235

J. W. Boldeman, J. Fréhaut, R. L. Walsh

Nuclear Science and Engineering / Volume 63 / Number 4 / August 1977 / Pages 430-436

Technical Paper / dx.doi.org/10.13182/NSE77-A27060

Coarse-Mesh Flux-Expansion Method for the Analysis of Space-Time Effects in Large Light Water Reactor Cores

S. Langenbuch, W. Maurer, W. Werner

Nuclear Science and Engineering / Volume 63 / Number 4 / August 1977 / Pages 437-456

Technical Paper / dx.doi.org/10.13182/NSE77-A27061

Some Basic Properties of the Response Matrix Equations

Zbigniew Weiss

Nuclear Science and Engineering / Volume 63 / Number 4 / August 1977 / Pages 457-492

Technical Paper / dx.doi.org/10.13182/NSE77-A27062

Measurements of Energy Spectra and Doses in Liquid Air of Neutrons from a Californium-252 Source

K. Clausen, U. Roose, P. Schneider-Kühnle, F. W. Buchholz, L. Schänzler, S. Stüker, G. Tumbrägel, M. Weinert

Nuclear Science and Engineering / Volume 63 / Number 4 / August 1977 / Pages 493-500

Technical Note / dx.doi.org/10.13182/NSE77-A27063

Space- and Angle-Dependent Steady-State Thermal-Neutron Spectra Inside Small Beryllium Assemblies: II

Suresh Garg, Feroz Ahmed, L. S. Kothari

Nuclear Science and Engineering / Volume 63 / Number 4 / August 1977 / Pages 500-504

Technical Note / dx.doi.org/10.13182/NSE77-A27064

Distribution of Fission Yields for Fission Spectrum Neutron-Induced Fission of Uranium-238

D. C. Harris, J. N. Beck, W. L. Raines, J. T. Harvey, K. G. W. Inn, J. L. Meason, H. L. Wright

Nuclear Science and Engineering / Volume 63 / Number 4 / August 1977 / Pages 504-507

Technical Note / dx.doi.org/10.13182/NSE77-A27065

Two-Half-Space Milne Problem in Two-Group Neutron Transport Theory

Yuji Ishiguro, José Rubens Maiorino

Nuclear Science and Engineering / Volume 63 / Number 4 / August 1977 / Pages 507-509

Technical Note / dx.doi.org/10.13182/NSE77-A27066

Upper-Bound Estimation of Bilinear Functionals in Reactor Theory

Yigal Ronen, Ehud Greenspan

Nuclear Science and Engineering / Volume 63 / Number 4 / August 1977 / Pages 509-513

Technical Note / dx.doi.org/10.13182/NSE77-A27067