Volume 58
Number 2
- Table of Contents
- Deposition of Energy in U, UC, and UO2 Fuels
- Comments on ‘Finite-Element Methods for Reactor Analysis,’
- Comments on “Spectrum of Delayed Neutrons from the Thermal-Neutron Fission of Uranium-235”
- Comment on “Influence of Deep Minima on Multigroup Cross-Section Generation”
- Response to “Comment on ‘Influence of Deep Minima on Multigroup Cross-Section Generation’”
The Technological Requirements for Power by Fusion
Nuclear Science and Engineering / Volume 58 / Number 2 / October 1975 / Pages 107-165
Critical Review / dx.doi.org/10.13182/NSE75-A28219
High-Order Response Matrix Equations in Two-Dimensional Geometry
Nuclear Science and Engineering / Volume 58 / Number 2 / October 1975 / Pages 166-181
Technical Paper / dx.doi.org/10.13182/NSE75-1
A Leakage Iterative Method for Solving the Three-Dimensional Neutron Diffusion Equation
Nuclear Science and Engineering / Volume 58 / Number 2 / October 1975 / Pages 182-192
Technical Paper / dx.doi.org/10.13182/NSE75-A28221
A Numerical Method for Solving Integral Equations of Neutron Transport—II
Nuclear Science and Engineering / Volume 58 / Number 2 / October 1975 / Pages 193-202
Technical Paper / dx.doi.org/10.13182/NSE75-A28222
A Two-Dimensional Finite Element Method for Integral Neutron Transport Calculations
Nuclear Science and Engineering / Volume 58 / Number 2 / October 1975 / Pages 203-212
Technical Paper / dx.doi.org/10.13182/NSE75-A28223
The Resonance Integral of Coated Particles
Nuclear Science and Engineering / Volume 58 / Number 2 / October 1975 / Pages 213-225
Technical Paper / dx.doi.org/10.13182/NSE75-A28224
Nuclear Science and Engineering / Volume 58 / Number 2 / October 1975 / Pages 226-238
Technical Paper / dx.doi.org/10.13182/NSE75-A28225
Nuclear Science and Engineering / Volume 58 / Number 2 / October 1975 / Pages 239-251
Technical Paper / dx.doi.org/10.13182/NSE75-A28226
First-Flight Escape Probability for a Three-Region Spherical Body
Nuclear Science and Engineering / Volume 58 / Number 2 / October 1975 / Pages 252-253
Technical Note / dx.doi.org/10.13182/NSE58-252TN
On the Critical Reactor Problem for a Reflected Slab
Nuclear Science and Engineering / Volume 58 / Number 2 / October 1975 / Pages 253-255
Technical Note / dx.doi.org/10.13182/NSE75-A28228
The Ratio of the Uranium-238 to Uranium-235 Fission Cross Sections from 5.3 to 10.3 MeV
Nuclear Science and Engineering / Volume 58 / Number 2 / October 1975 / Pages 255-257
Technical Note / dx.doi.org/10.13182/NSE75-A28229
