Volume 49

Number 1

Table of Contents
ESP: A General Reactor Analysis Monte Carlo Code(S. N. Cramer R. S. Carlsmith G. W. Morrison,LG. W. Perry J. L. Lucius)
HETC: A High Energy Transport Code(T. W. Armstrong, K. C. Chandler)
Comments on Variation Flux Synthesis Methods for Multigroup Diffusion Theory(A. J. Buslik)
Reply to “Comments on Variation Flux Synthesis Methods for Multigroup Diffusion Theory”(W. M. Stacey, Jr.)

Discrete Ordinate Neutron Transport Equation Equivalent to P_L Approximation

Jungchung Jung, Hiroshi Chijiwa, Keisuke Kobayashi,Hiroshi Nishihara

Nuclear Science and Engineering / Volume 49 / Number 1 / September 1972 / Pages 1-9

Technical Paper / dx.doi.org/10.13182/NSE49-01-01

Spherical Harmonic Solutions of the Neutron Transport Equation from Discrete Ordinate Codes

Wm. H. Reed

Nuclear Science and Engineering / Volume 49 / Number 1 / September 1972 / Pages 10-19

Technical Paper / dx.doi.org/10.13182/NSE72-A22523

Effect of Singularities on Approximation in S_N Methods

Jacek Arkuszewski, Teresa Kulikowska, Janusz Mika

Nuclear Science and Engineering / Volume 49 / Number 1 / September 1972 / Pages 20-26

Technical Paper / dx.doi.org/10.13182/NSE72-4

A Timing Comparison Study for Some High Order Finite Element Approximation Procedures and a Low Order Finite Difference Approximation Procedure for the Numerical Solution of the Multigroup Neutron Diffusion Equation

Hans G. Kaper, Gary K. Leaf, Arthur J. Lindeman

Nuclear Science and Engineering / Volume 49 / Number 1 / September 1972 / Pages 27-48

Technical Paper / dx.doi.org/10.13182/NSE72-A22525

Spherical Harmonics Treatment of Epithermal Neutron Spectra in Reactor Lattices

M. V. Mataušek

Nuclear Science and Engineering / Volume 49 / Number 1 / September 1972 / Pages 49-58

Technical Paper / dx.doi.org/10.13182/NSE72-A22526

In-Core Fuel Management Optimization by Heuristic Learning Technique

Tsutomu Hoshino*

Nuclear Science and Engineering / Volume 49 / Number 1 / September 1972 / Pages 59-71

Technical Paper / dx.doi.org/10.13182/NSE72-A22527

The Yield Stress Radiation Damage Function of Iron

G. R. Odette, T. O. Ziebold

Nuclear Science and Engineering / Volume 49 / Number 1 / September 1972 / Pages 72-81

Technical Paper / dx.doi.org/10.13182/NSE72-A22528

Monte Carlo Calculations of High-Energy Nucleon-Meson Cascades and Comparison with Experiment

T. W. Armstrong, R. G. Alsmiller, Jr., K. C. Chandler, B. L. Bishop

Nuclear Science and Engineering / Volume 49 / Number 1 / September 1972 / Pages 82-92

Technical Paper / dx.doi.org/10.13182/NSE72-A22529

A Numerical Calculation of the Redistribution of an Interstitial Solute in a Thermal Gradient

G. P. Marino

Nuclear Science and Engineering / Volume 49 / Number 1 / September 1972 / Pages 93-98

Technical Paper / dx.doi.org/10.13182/NSE72-A22530

Linear Stability of Fast and Thermal Reactor Models Using Space-Time Kinetics

Kenneth Alvin Solomon and William E. Kastenberg

Nuclear Science and Engineering / Volume 49 / Number 1 / September 1972 / Pages 99-103

Technical Note / dx.doi.org/10.13182/NSE72-A22531

Experimentally Measured Dose Albedos of Intermediate Energy Bremsstrahlung

Thomas R. Crites

Nuclear Science and Engineering / Volume 49 / Number 1 / September 1972 / Pages 103-106

Technical Note / dx.doi.org/10.13182/NSE72-A22532

Hot Spot Expectation in Nuclear Reactor Core Thermal Design

A. Amendola

Nuclear Science and Engineering / Volume 49 / Number 1 / September 1972 / Pages 106-108

Technical Note / dx.doi.org/10.13182/NSE72-A22533