Volume 36
Number 1
Neutron Diffusion Lengths of Graphite-Absorber Mixtures Between 200 and 2000°K
Nuclear Science and Engineering / Volume 36 / Number 1 / April 1969 / Pages 1-14
Technical Paper / dx.doi.org/10.13182/NSE69-A18852
Nuclear Science and Engineering / Volume 36 / Number 1 / April 1969 / Pages 15-27
Technical Paper / dx.doi.org/10.13182/NSE69-A18853
A Space-Dependent Reactor-Noise Formulation Utilizing Modal Expansions
Nuclear Science and Engineering / Volume 36 / Number 1 / April 1969 / Pages 28-38
Technical Paper / dx.doi.org/10.13182/NSE69-A18854
The Bimodal Decay of Two Pulsed-Neutron-Coupled Cores of an Organic-Moderated and -Reflected System
Nuclear Science and Engineering / Volume 36 / Number 1 / April 1969 / Pages 39-46
Technical Paper / dx.doi.org/10.13182/NSE69-A18855
Resonance Integral and Doppler Coefficients in Nonuniform Cylindrical Reactor Fuel Rods
Nuclear Science and Engineering / Volume 36 / Number 1 / April 1969 / Pages 47-58
Technical Paper / dx.doi.org/10.13182/NSE69-A18856
Resonance Moderation of Neutrons in Weakly Absorbing Mixtures
Nuclear Science and Engineering / Volume 36 / Number 1 / April 1969 / Pages 59-66
Technical Paper / dx.doi.org/10.13182/NSE69-A18857
Application of Statistical Theory and Multilevel Formalism to Doppler Effect Analysis—I
Nuclear Science and Engineering / Volume 36 / Number 1 / April 1969 / Pages 67-81
Technical Paper / dx.doi.org/10.13182/NSE69-A18858
Application of Statistical Theory and Multilevel Formalism to Doppler Effect Analysis—II
Nuclear Science and Engineering / Volume 36 / Number 1 / April 1969 / Pages 82-96
Technical Paper / dx.doi.org/10.13182/NSE69-A18859
Comparison of Modal and Iterative Approaches to Space and Space-Time Nonlinear Problems
Nuclear Science and Engineering / Volume 36 / Number 1 / April 1969 / Pages 97-104
Technical Paper / dx.doi.org/10.13182/NSE69-A18860
Multiple Scattering in Double Differential Measurements as a Function of Neutron Path Length
Nuclear Science and Engineering / Volume 36 / Number 1 / April 1969 / Pages 105-107
Technical Note / dx.doi.org/10.13182/NSE69-A18861
Iteration and Intermediate Resonance Neutron Absorption in Multinuclide Systems
Nuclear Science and Engineering / Volume 36 / Number 1 / April 1969 / Pages 107-109
Technical Note / dx.doi.org/10.13182/NSE69-A18862
Implications of Recent Fission-Averaged Cross-Section Measurements
Nuclear Science and Engineering / Volume 36 / Number 1 / April 1969 / Pages 109-113
Technical Note / dx.doi.org/10.13182/NSE69-A18863
On the Step-Response Method of Determining the Zero-Power Reactor Transfer Function
Nuclear Science and Engineering / Volume 36 / Number 1 / April 1969 / Pages 113-114
Technical Note / dx.doi.org/10.13182/NSE69-A18864
Nuclear Science and Engineering / Volume 36 / Number 1 / April 1969 / Pages 115-116
Technical Note / dx.doi.org/10.13182/NSE69-A18865
Nuclear Science and Engineering / Volume 36 / Number 1 / April 1969 / Pages 116-122
Technical Note / dx.doi.org/10.13182/NSE69-A18866
A Method for Calculating Space-Dependent Reactor Source Transfer Functions with Feedback
Nuclear Science and Engineering / Volume 36 / Number 1 / April 1969 / Pages 122-125
Technical Note / dx.doi.org/10.13182/NSE69-A18867
Reactivity Rate-Constrained Time-Optimal Neutron Kinetics
Nuclear Science and Engineering / Volume 36 / Number 1 / April 1969 / Pages 125-128
Technical Note / dx.doi.org/10.13182/NSE69-A18868
