Volume 70
Number 1 | Number 2 | Number 3
Number 1
- Table of Contents
- A Semi-Analytic Solution to the Transport Equation in Spherical Geometry
- 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
- Higher Order Time-Dependent Generalized Perturbation Theory
- Thermal Effluent Disposal from Power Generation
Optimal Choice of Parameters for Exponential Biasing in Monte Carlo
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
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
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
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
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
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
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
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
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
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
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
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
Nuclear Science and Engineering / Volume 70 / Number 1 / April 1979 / Pages 106-110
Technical Note / dx.doi.org/10.13182/NSE79-A18934
Number 2
Nuclear Science and Engineering / Volume 70 / Number 2 / May 1979 / Pages 119-126
Technical Paper / dx.doi.org/10.13182/NSE79-A19644
Application of Acoustic Agglomerators for Emergency Use in Liquid-Metal Fast Breeder Reactor Plants
Nuclear Science and Engineering / Volume 70 / Number 2 / May 1979 / Pages 127-134
Technical Paper / dx.doi.org/10.13182/NSE79-A19645
Expert Opinion and Statistical Evidence: An Application to Reactor Core Melt Frequency
Nuclear Science and Engineering / Volume 70 / Number 2 / May 1979 / Pages 135-149
Technical Paper / dx.doi.org/10.13182/NSE79-A19646
The Transmission of Neutrons Through Iron-56 at 24.37 keV
Nuclear Science and Engineering / Volume 70 / Number 2 / May 1979 / Pages 150-154
Technical Paper / dx.doi.org/10.13182/NSE79-A19647
Neutron Resonance Parameters for Neptunium-237
Nuclear Science and Engineering / Volume 70 / Number 2 / May 1979 / Pages 155-162
Technical Paper / dx.doi.org/10.13182/NSE79-A19648
Cross Sections for the 14N(n,p0), (n,α0), and (n,α1) Reactions from 0.5 to 15 MeV
Nuclear Science and Engineering / Volume 70 / Number 2 / May 1979 / Pages 163-176
Technical Paper / dx.doi.org/10.13182/NSE79-A19649
Fission Yields for Thermal-Neutron Fission of Plutonium-241
Nuclear Science and Engineering / Volume 70 / Number 2 / May 1979 / Pages 177-183
Technical Paper / dx.doi.org/10.13182/NSE79-A19650
Calculated Time-Dependent Delayed Neutron Group Yields for Thermal-Neutron Fission of Uranium-235
Nuclear Science and Engineering / Volume 70 / Number 2 / May 1979 / Pages 184-191
Technical Paper / dx.doi.org/10.13182/NSE79-A19651
Electron Transport in One-Dimensional Finite Systems
Nuclear Science and Engineering / Volume 70 / Number 2 / May 1979 / Pages 192-200
Technical Paper / dx.doi.org/10.13182/NSE79-A19652
Use of Temperature Variance to Detect Sodium Boiling
Nuclear Science and Engineering / Volume 70 / Number 2 / May 1979 / Pages 201-204
Technical Note / dx.doi.org/10.13182/NSE79-A19653
Nuclear Science and Engineering / Volume 70 / Number 2 / May 1979 / Pages 204-207
Technical Note / dx.doi.org/10.13182/NSE79-A19654
On the Polynomial Form of Gamma-Ray Buildup Factor Functions
Nuclear Science and Engineering / Volume 70 / Number 2 / May 1979 / Pages 207-209
Technical Note / dx.doi.org/10.13182/NSE79-A19655
Optimum Biasing of Integral Equations in Monte Carlo Calculations
Nuclear Science and Engineering / Volume 70 / Number 2 / May 1979 / Pages 210-212
Technical Note / dx.doi.org/10.13182/NSE79-A19656
Number 3
Nuclear Science and Engineering / Volume 70 / Number 3 / June 1979 / Pages 225-242
Technical Paper / dx.doi.org/10.13182/NSE79-A20145
Prediction of Statistical Error and Optimization of Biased Monte Carlo Transport Calculations
Nuclear Science and Engineering / Volume 70 / Number 3 / June 1979 / Pages 243-261
Technical Paper / dx.doi.org/10.13182/NSE79-A20146
Lattice Eigenvalue as a Function of Buckling: Correction to First-Order Perturbation Theory
Nuclear Science and Engineering / Volume 70 / Number 3 / June 1979 / Pages 262-273
Technical Paper / dx.doi.org/10.13182/NSE79-A20147
Tritium Production in a Sphere of 6LiD Irradiated by 14-MeV Neutrons
Nuclear Science and Engineering / Volume 70 / Number 3 / June 1979 / Pages 274-280
Technical Paper / dx.doi.org/10.13182/NSE79-A20148
Neutron Interaction with Carbon-12 in the Few-MeV Region
Nuclear Science and Engineering / Volume 70 / Number 3 / June 1979 / Pages 281-293
Technical Paper / dx.doi.org/10.13182/NSE79-A20149
Neutron Inelastic Scattering in Silicon-28 to 4.15 MeV
Nuclear Science and Engineering / Volume 70 / Number 3 / June 1979 / Pages 294-297
Technical Paper / dx.doi.org/10.13182/NSE79-A20150
Emission Probability of the 312-keV Gamma Ray from the Decay of Protactinium-233
Nuclear Science and Engineering / Volume 70 / Number 3 / June 1979 / Pages 298-306
Technical Paper / dx.doi.org/10.13182/NSE79-A20151
Self-Shielded Fission Rates for Uranium-235
Nuclear Science and Engineering / Volume 70 / Number 3 / June 1979 / Pages 307-308
Technical Note / dx.doi.org/10.13182/NSE79-A20152
Neutron Multiplication Studies in Beryllium for Fusion Reactor Blankets
Nuclear Science and Engineering / Volume 70 / Number 3 / June 1979 / Pages 309-313
Technical Note / dx.doi.org/10.13182/NSE79-A20153
Reactor Fuel Burnup Calculations in the LASER Code
Nuclear Science and Engineering / Volume 70 / Number 3 / June 1979 / Pages 313-315
Technical Note / dx.doi.org/10.13182/NSE79-A20154
Availability Maximization of Supervised Protective Systems for Nuclear Reactors
Nuclear Science and Engineering / Volume 70 / Number 3 / June 1979 / Pages 315-317
Technical Note / dx.doi.org/10.13182/NSE79-A20155
