ANS / Publications / Journals / Nuclear Science and Engineering

An Early-Time Analysis of Space-Dependent Nuclear Reactor Transients

S. L. Paveri-Fontana, P. L. Chambré

Nuclear Science and Engineering / Volume 61 / Number 4 / December 1976 / Pages 451-465

Technical Paper / dx.doi.org/10.13182/NSE76-A14482

Reactor-Fuel-Independent Reactivity Determinations

S. Pearlstein

Nuclear Science and Engineering / Volume 61 / Number 4 / December 1976 / Pages 466-470

Technical Paper / dx.doi.org/10.13182/NSE76-A14483

Measurement of the Ratio of Fission to Capture Neutron Cross Sections in Uranium-235 in the 200-eV to 15-keV Energy Range

H. Bluhm, C. S. Yen

Nuclear Science and Engineering / Volume 61 / Number 4 / December 1976 / Pages 471-476

Technical Paper / dx.doi.org/10.13182/NSE76-A14484

Fission Cross Section of Neptunium-237 from 3 eV to 2 MeV

S. Plattard, J. Blons, D. Paya

Nuclear Science and Engineering / Volume 61 / Number 4 / December 1976 / Pages 477-495

Technical Paper / dx.doi.org/10.13182/NSE76-A14485

The ENDF/B-IV Representation of the Uranium-238, Total Neutron Cross Section in the Resolved Resonance Energy Region

G. de Saussure, D. K. Olsen, R. B. Perez

Nuclear Science and Engineering / Volume 61 / Number 4 / December 1976 / Pages 496-506

Technical Paper / dx.doi.org/10.13182/NSE76-A14486

Measurement of the Angular Neutron Energy Spectra Originating from a 14-MeV Neutron Source in Liquid Air

K. Clausen, B. Bröcker, P. Schneider-Kühnle, M. Weinert

Nuclear Science and Engineering / Volume 61 / Number 4 / December 1976 / Pages 507-520

Technical Paper / dx.doi.org/10.13182/NSE76-A14487

Differential Elastic and Inelastic Scattering of 9- to 15-MeV Neutrons from Carbon

D. W. Glasgow, F. O. Purser, H. Hogue, J. C. Clement, K. Stelzer, G. Mack, J. R. Boyce, D. H. Epperson, S. G. Buccino, P. W. Lisowski, S. G. Glendinning, E. G. Bilpuch, H. W. Newson, C. R. Gould

Nuclear Science and Engineering / Volume 61 / Number 4 / December 1976 / Pages 521-533

Technical Paper / dx.doi.org/10.13182/NSE76-A14488

Spherical Harmonics Approximations of Neutron Transport

A. Demény, K. M. Dede, K. Erdei

Nuclear Science and Engineering / Volume 61 / Number 4 / December 1976 / Pages 534-535

Technical Note / dx.doi.org/10.13182/NSE76-A14489

A Numerical Method for Solving the Integral Equation of Neutron Transport: III

Robert W. Tsai, Sudarshan K. Loyalka

Nuclear Science and Engineering / Volume 61 / Number 4 / December 1976 / Pages 536-540

Technical Note / dx.doi.org/10.13182/NSE76-A14490

Measurement of Cross Sections for the ⁷Li(n, n′γ)⁷Li Reaction from 0.57 to 4 MeV

Donald L. Smith

Nuclear Science and Engineering / Volume 61 / Number 4 / December 1976 / Pages 540-543

Technical Note / dx.doi.org/10.13182/NSE76-A14491

Rational Approximations for Cross-Section Space-Shielding in Doubly Heterogeneous Systems

M. G. Stamatelatos

Nuclear Science and Engineering / Volume 61 / Number 4 / December 1976 / Pages 543-549

Technical Note / dx.doi.org/10.13182/NSE76-A14492

Basic Collapse Criteria for Boiling Reactor-Fuel-Steel Mixtures

Paul B. Abramson

Nuclear Science and Engineering / Volume 61 / Number 4 / December 1976 / Pages 549-552

Technical Note / dx.doi.org/10.13182/NSE76-A14493