Volume 56
Number 3
An In-Pile Study of Thermal Interactions Between . High-Energy Molten UO2 Fuel and Liquid Sodium
Nuclear Science and Engineering / Volume 56 / Number 3 / March 1975 / Pages 229-240
Technical Paper / dx.doi.org/10.13182/NSE75-A26737
Measured and Calculated Rates of Decay Heat in Irradiated 235U, 233U, 239Pu, and 232Th
Nuclear Science and Engineering / Volume 56 / Number 3 / March 1975 / Pages 241-262
Technical Paper / dx.doi.org/10.13182/NSE75-A26738
Point Isotropic Gamma-Ray Buildup Factors in Concrete
Nuclear Science and Engineering / Volume 56 / Number 3 / March 1975 / Pages 263-270
Technical Paper / dx.doi.org/10.13182/NSE75-A26739
Neutron Importance and Fission Density in Uranium-235-Enriched Uranium and Plutonium Metal Spheres
Nuclear Science and Engineering / Volume 56 / Number 3 / March 1975 / Pages 271-290
Technical Paper / dx.doi.org/10.13182/NSE75-3
Response Matrices in Space-Time Reactor Dynamics
Nuclear Science and Engineering / Volume 56 / Number 3 / March 1975 / Pages 291-300
Technical Paper / dx.doi.org/10.13182/NSE75-2
Laser-Induced Thermonuclear Micro-Explosions Using Fissionable Triggers
Nuclear Science and Engineering / Volume 56 / Number 3 / March 1975 / Pages 301-303
Technical Note / dx.doi.org/10.13182/NSE75-A26742
The EBR-I Incident: A Reexamination
Nuclear Science and Engineering / Volume 56 / Number 3 / March 1975 / Pages 303-307
Technical Note / dx.doi.org/10.13182/NSE75-A26743
An Assessment of ENDF/B-III Data for Uranium-238 Based on Integral Spectrum Measurements
Nuclear Science and Engineering / Volume 56 / Number 3 / March 1975 / Pages 307-309
Technical Note / dx.doi.org/10.13182/NSE75-A26744
Nuclear Science and Engineering / Volume 56 / Number 3 / March 1975 / Pages 310-317
Technical Note / dx.doi.org/10.13182/NSE75-A26745
A Numerical Method for Solving Integral Equations of Neutron Transport
Nuclear Science and Engineering / Volume 56 / Number 3 / March 1975 / Pages 317-319
Technical Note / dx.doi.org/10.13182/NSE75-2
