Volume 75
Number 1 | Number 2 | Number 3
Number 1
Barycentric-Coordinates Technique for Identification of Simultaneous Fuel Failures with Gas Tagging
Nuclear Science and Engineering / Volume 75 / Number 1 / July 1980 / Pages 1-11
Technical Paper / dx.doi.org/10.13182/NSE80-A20313
Efficient Neutron Production Using Low-Energy Electron Beams
Nuclear Science and Engineering / Volume 75 / Number 1 / July 1980 / Pages 12-15
Technical Paper / dx.doi.org/10.13182/NSE80-A20314
Gamma-Ray Buildup Factors for Stratified Lead and Water Shields
Nuclear Science and Engineering / Volume 75 / Number 1 / July 1980 / Pages 16-29
Technical Paper / dx.doi.org/10.13182/NSE80-1
Uncertainty in the Breeding Ratio of a Large Liquid-Metal Fast Breeder Reactor: Theory and Results
Nuclear Science and Engineering / Volume 75 / Number 1 / July 1980 / Pages 30-55
Technical Paper / dx.doi.org/10.13182/NSE80-A20316
Prompt Neutron Multiplicity Distribution in the Spontaneous Fission of Curium-242
Nuclear Science and Engineering / Volume 75 / Number 1 / July 1980 / Pages 56-59
Technical Paper / dx.doi.org/10.13182/NSE80-A20317
A New Approach to the Adjustment of Group Cross Sections Fitting Integral Measurements. Part II
Nuclear Science and Engineering / Volume 75 / Number 1 / July 1980 / Pages 60-68
Technical Paper / dx.doi.org/10.13182/NSE80-A20318
Fast-Neutron Cross Sections of Elemental Bismuth
Nuclear Science and Engineering / Volume 75 / Number 1 / July 1980 / Pages 69-75
Technical Paper / dx.doi.org/10.13182/NSE80-A20319
A Two-Dimensional Constrained Finite Element Method for Nonuniform Lattice Problems
Nuclear Science and Engineering / Volume 75 / Number 1 / July 1980 / Pages 76-87
Technical Paper / dx.doi.org/10.13182/NSE80-A20320
Sensitivity Theory for General Systems of Nonlinear Equations
Nuclear Science and Engineering / Volume 75 / Number 1 / July 1980 / Pages 88-110
Technical Paper / dx.doi.org/10.13182/NSE75-88
Validation Results for the SDX Cell Homogenization Code for Pin Geometry
Nuclear Science and Engineering / Volume 75 / Number 1 / July 1980 / Pages 111-125
Technical Note / dx.doi.org/10.13182/NSE80-A20322
Number 2
- Table of Contents
- ACCEPT
- Comments on the Bayesian Method for Estimating Reactor Core Melt Frequency
- Reply to “Comments on the Bayesian Method for Estimating Reactor Core Melt Frequency”
- Studies in Heat Transfer: A Festschrift for E. R. G. Eckert
- Eigenvalues of the Neutron Transport Equation with Anisotropic Scattering
An Approximate Theory for the Neutron Slowing Down and Propagation in the Field of Gravity
Nuclear Science and Engineering / Volume 75 / Number 2 / August 1980 / Pages 133-139
Technical Paper / dx.doi.org/10.13182/NSE80-A21302
Nuclear Science and Engineering / Volume 75 / Number 2 / August 1980 / Pages 140-150
Technical Paper / dx.doi.org/10.13182/NSE80-A21303
Measurement and Analysis of the 23Na(n,xγ) Reaction Cross Section for 0.2 ≤ En ≤20 MeV
Nuclear Science and Engineering / Volume 75 / Number 2 / August 1980 / Pages 151-158
Technical Paper / dx.doi.org/10.13182/NSE80-A21304
Photointerference Corrections in Neutron Dosimetry for Reactor Pressure Vessel Lifetime Studies
Nuclear Science and Engineering / Volume 75 / Number 2 / August 1980 / Pages 159-166
Technical Paper / dx.doi.org/10.13182/NSE80-A21305
The Behavior of Contained Radioactive Suspensions
Nuclear Science and Engineering / Volume 75 / Number 2 / August 1980 / Pages 167-180
Technical Paper / dx.doi.org/10.13182/NSE80-A21306
Improved Interpolation Schemes in Anisotropic Source Flux Iteration Techniques
Nuclear Science and Engineering / Volume 75 / Number 2 / August 1980 / Pages 181-184
Technical Note / dx.doi.org/10.13182/NSE80-A21307
Effect of Photoneutrons on Thermalization Experiments in Deuterium
Nuclear Science and Engineering / Volume 75 / Number 2 / August 1980 / Pages 184-190
Technical Note / dx.doi.org/10.13182/NSE80-A21308
Variation of Neutron-Density Noise During Core Life in a Pressurized Water Reactor
Nuclear Science and Engineering / Volume 75 / Number 2 / August 1980 / Pages 190-191
Technical Note / dx.doi.org/10.13182/NSE80-A21309
An Algorithm for Failure Location in a Complex Network
Nuclear Science and Engineering / Volume 75 / Number 2 / August 1980 / Pages 191-199
Technical Note / dx.doi.org/10.13182/NSE80-A21310
Number 3
A New Methodology to Quantify Risk Perception
Nuclear Science and Engineering / Volume 75 / Number 3 / September 1980 / Pages 211-224
Technical Paper / dx.doi.org/10.13182/NSE80-A19054
Linearized Transient Analysis of Nuclear Steam Generators
Nuclear Science and Engineering / Volume 75 / Number 3 / September 1980 / Pages 225-242
Technical Paper / dx.doi.org/10.13182/NSE80-A19055
Nuclear Science and Engineering / Volume 75 / Number 3 / September 1980 / Pages 243-257
Technical Paper / dx.doi.org/10.13182/NSE80-A19056
Nuclear Science and Engineering / Volume 75 / Number 3 / September 1980 / Pages 258-264
Technical Paper / dx.doi.org/10.13182/NSE80-A19057
Optimization of Once-Through Uranium Cycle for Pressurized Light Water Reactors
Nuclear Science and Engineering / Volume 75 / Number 3 / September 1980 / Pages 265-274
Technical Paper / dx.doi.org/10.13182/NSE80-A19058
Calculation and Measurement of Fission and Delayed Neutron Yields in U3O8 and UO2
Nuclear Science and Engineering / Volume 75 / Number 3 / September 1980 / Pages 275-277
Technical Note / dx.doi.org/10.13182/NSE80-A19059
