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Volume 70

Number 1

Table of Contents
A Semi-Analytic Solution to the Transport Equation in Spherical Geometry(A. Dubi, Y. S. Horowitz)
Effects of Energy Losses of Arbitrary Magnitude on Fuel Quality, Vapor Density, and Bubble Diameter in an Idealized Expansion of Mixtures of UO₂ and Sodium(Hugo W. Bertini, Janice S. White)
Higher Order Time-Dependent Generalized Perturbation Theory(A. Gandini)
Thermal Effluent Disposal from Power Generation(Richard F. Cole)

Optimal Choice of Parameters for Exponential Biasing in Monte Carlo

A. Dubi, Donald J. Dudziak

Nuclear Science and Engineering / Volume 70 / Number 1 / April 1979 / Pages 1-13

Technical Paper / dx.doi.org/10.13182/NSE79-A18922

Bounded Flux-at-a-Point Estimators for Multigroup Monte Carlo Computer Codes

S. K. Fraley, T. J. Hoffman

Nuclear Science and Engineering / Volume 70 / Number 1 / April 1979 / Pages 14-19

Technical Paper / dx.doi.org/10.13182/NSE79-A18923

Development of Depletion Perturbation Theory for Coupled Neutron/Nuclide Fields

M. L. Williams

Nuclear Science and Engineering / Volume 70 / Number 1 / April 1979 / Pages 20-36

Technical Paper / dx.doi.org/10.13182/NSE79-3

PURNIMA—A PuO₂-Fueled Zero-Energy Fast Reactor at Trombay

P. K. Iyengar, T. K. Basu, K. Chandramoleshwar, S. Das, P. K. Job, S. K. Kapil, V. R. Nargundkar, C. S. Pasupathy, M. Srinivasan, K. Subba Rao

Nuclear Science and Engineering / Volume 70 / Number 1 / April 1979 / Pages 37-52

Technical Paper / dx.doi.org/10.13182/NSE79-A18925

Neutron Capture Cross Sections of Rhodium, Thulium, Iridium, and Gold Between 0.5 and 3.0 MeV

S. Joly, J. Voignier, G. Grenier, D. M. Drake, L. Nilsson

Nuclear Science and Engineering / Volume 70 / Number 1 / April 1979 / Pages 53-59

Technical Paper / dx.doi.org/10.13182/NSE79-A18926

Diagnostic Neutron Spectra from Deuterons on Several Materials

H. W. Lefevre, J. C. Davis, J. D. Anderson

Nuclear Science and Engineering / Volume 70 / Number 1 / April 1979 / Pages 60-65

Technical Paper / dx.doi.org/10.13182/NSE79-A18927

Transitor Damage Characterization by Neutron Displacement Cross Section in Silicon: Experimental

V. V. Verbinski, C. Cassapakis, R. L. Pease, H. L. Scott

Nuclear Science and Engineering / Volume 70 / Number 1 / April 1979 / Pages 66-72

Technical Paper / dx.doi.org/10.13182/NSE79-A18928

Diffusion Coefficients of Sodium Vapors in Argon and Helium

T. Kumada, R. Ishiguro, Y. Kimachi

Nuclear Science and Engineering / Volume 70 / Number 1 / April 1979 / Pages 73-81

Technical Paper / dx.doi.org/10.13182/NSE79-A18929

An Atomic Model for Neutral and Singly Ionized Uranium

Edward L. Maceda, George H. Miley

Nuclear Science and Engineering / Volume 70 / Number 1 / April 1979 / Pages 82-95

Technical Paper / dx.doi.org/10.13182/NSE79-A18930

Three Basic Neutron-Transport Problems in Spherical Geometry

C. E. Siewert, P. Grandjean

Nuclear Science and Engineering / Volume 70 / Number 1 / April 1979 / Pages 96-98

Technical Note / dx.doi.org/10.13182/NSE70-96

The Total Neutron Cross Section of Boron-10 Between 90 and 420 keV

H. Beer, R. R. Spencer

Nuclear Science and Engineering / Volume 70 / Number 1 / April 1979 / Pages 98-101

Technical Note / dx.doi.org/10.13182/NSE79-A18932

Fission Yields for Fast-Neutron Fission of Uranium-238

J. E. Gindler, L. E. Glendenin, J. W. Meadows, Jr., K. F. Flynn

Nuclear Science and Engineering / Volume 70 / Number 1 / April 1979 / Pages 101-106

Technical Note / dx.doi.org/10.13182/NSE79-A18933

Identifiability of Dynamics of a Boiling Water Reactor Using Autoregressive Modeling

Masaharu Kitamura, Kunihiko Matsubara, Ritsuo Oguma

Nuclear Science and Engineering / Volume 70 / Number 1 / April 1979 / Pages 106-110

Technical Note / dx.doi.org/10.13182/NSE79-A18934