Volume 24
Number 4
- Table of Contents
- Radiochemical Methods of Analysis
- Energetics in Metallurgical Phenomena—Volume 1
- Refractory Transition Metal Compounds; High-Temperature Cermets
- Effects of Radiation on Semiconductors
- Note on the Use of Generalized Functions and the Poincaré-Bertrand Formula in Neutron Transport Theory
- Comment to the Preceding Letter by Kaper
- Further Comments on the Use of Generalized Functions in Neutron Transport Theory
Heat Transport by Radiation in Solids
Nuclear Science and Engineering / Volume 24 / Number 4 / April 1966 / Pages 317-321
Technical Paper / dx.doi.org/10.13182/NSE66-A16399
Fission-Fragment Transport Effects as Related to Fission-Electric-Cell Efficiencies
Nuclear Science and Engineering / Volume 24 / Number 4 / April 1966 / Pages 322-331
Technical Paper / dx.doi.org/10.13182/NSE66-A16400
Melting Point Determination of Uranium Monophosphide
Nuclear Science and Engineering / Volume 24 / Number 4 / April 1966 / Pages 332-335
Technical Paper / dx.doi.org/10.13182/NSE66-A16401
Nuclear Science and Engineering / Volume 24 / Number 4 / April 1966 / Pages 336-343
Technical Paper / dx.doi.org/10.13182/NSE66-A16402
Nuclear Science and Engineering / Volume 24 / Number 4 / April 1966 / Pages 344-348
Technical Paper / dx.doi.org/10.13182/NSE66-A16403
Multigroup Calculations of the Fast Spectrum and Fast Fission Effect
Nuclear Science and Engineering / Volume 24 / Number 4 / April 1966 / Pages 349-355
Technical Paper / dx.doi.org/10.13182/NSE66-A16404
Effect of Delayed Neutrons on the Stability of a Nuclear Power Reactor
Nuclear Science and Engineering / Volume 24 / Number 4 / April 1966 / Pages 356-361
Technical Paper / dx.doi.org/10.13182/NSE66-A16405
Boundary Conditions in Gap Geometry
Nuclear Science and Engineering / Volume 24 / Number 4 / April 1966 / Pages 362-374
Technical Paper / dx.doi.org/10.13182/NSE66-A16406
A Rigorous Expression for Shape of a Doppler-Broadened Resonance
Nuclear Science and Engineering / Volume 24 / Number 4 / April 1966 / Pages 375-380
Technical Paper / dx.doi.org/10.13182/NSE66-A16407
Use of Discrete-Ordinates Methods for Solution of Photon Transport Problems
Nuclear Science and Engineering / Volume 24 / Number 4 / April 1966 / Pages 381-388
Technical Paper / dx.doi.org/10.13182/NSE66-A16408
The Effect of Randomness on Group Cross Sections
Nuclear Science and Engineering / Volume 24 / Number 4 / April 1966 / Pages 389-393
Technical Paper / dx.doi.org/10.13182/NSE66-A16409
Scattering of Neutrons by Polyethylene
Nuclear Science and Engineering / Volume 24 / Number 4 / April 1966 / Pages 394-409
Technical Paper / dx.doi.org/10.13182/NSE66-A16410
On the Maximum Absorption Theorem
Nuclear Science and Engineering / Volume 24 / Number 4 / April 1966 / Pages 410-412
Techincal Note / dx.doi.org/10.13182/NSE66-A16411
Neutron Fluctuations in a Multiplying Medium
Nuclear Science and Engineering / Volume 24 / Number 4 / April 1966 / Pages 412-414
Techincal Note / dx.doi.org/10.13182/NSE66-A16412
Subcritical Determination of Relative Natural-Neutron-Source Strengths
Nuclear Science and Engineering / Volume 24 / Number 4 / April 1966 / Pages 414-417
Techincal Note / dx.doi.org/10.13182/NSE66-A16413
Variation of the Transport Mean Free Path in Graphite with Temperature
Nuclear Science and Engineering / Volume 24 / Number 4 / April 1966 / Pages 417-418
Techincal Note / dx.doi.org/10.13182/NSE66-A16414
