Temperature Dynamic Analysis of Fuel Elements for Boiling Water Reactors
Nuclear Science and Engineering / Volume 54 / Number 1 / May 1974 / Pages 1-9
Technical Paper / dx.doi.org/10.13182/NSE74-A23387
Some Aspects of Fuel-Pin-Failure Propagation in Sodium-Cooled Fast Reactors
Nuclear Science and Engineering / Volume 54 / Number 1 / May 1974 / Pages 10-17
Technical Paper / dx.doi.org/10.13182/NSE74-A23388
The Thermal-Neutron Scattering Cross Sections of Uranium-233 and Thorium-232
Nuclear Science and Engineering / Volume 54 / Number 1 / May 1974 / Pages 18-27
Technical Paper / dx.doi.org/10.13182/NSE74-A23389
Age of Californium-252 Fission Neutrons to Indium Resonance Energy in Water
Nuclear Science and Engineering / Volume 54 / Number 1 / May 1974 / Pages 28-34
Technical Paper / dx.doi.org/10.13182/NSE74-A23390
Nuclear Science and Engineering / Volume 54 / Number 1 / May 1974 / Pages 35-46
Technical Paper / dx.doi.org/10.13182/NSE74-A23391
Simulation Studies of a Practical Reactor Control System Providing Time-Optimal Shutdown
Nuclear Science and Engineering / Volume 54 / Number 1 / May 1974 / Pages 47-54
Technical Paper / dx.doi.org/10.13182/NSE74-A23392
An Examination of Some Approximations for Heterogeneous Reactors
Nuclear Science and Engineering / Volume 54 / Number 1 / May 1974 / Pages 55-71
Technical Paper / dx.doi.org/10.13182/NSE74-A23393
Effects of Highly Anisotropic Scattering on Monoenergetic Neutron Transport at Deep Penetrations
Nuclear Science and Engineering / Volume 54 / Number 1 / May 1974 / Pages 72-84
Technical Paper / dx.doi.org/10.13182/NSE74-A23394
Legendre Polynomial Expansion of the Klein-Nishina Differential Cross Section
Nuclear Science and Engineering / Volume 54 / Number 1 / May 1974 / Pages 85-93
Technical Paper / dx.doi.org/10.13182/NSE74-A23395
Benchmark Values for the Slab and Sphere Criticality Problem in One-Group Neutron Transport Theory
Nuclear Science and Engineering / Volume 54 / Number 1 / May 1974 / Pages 94-99
Technical Note / dx.doi.org/10.13182/NSE54-94