Reactivity Worth of the Central Fuel Element in the Bulk Shielding Reactor-I
Nuclear Science and Engineering / Volume 9 / Number 3 / March 1961 / Pages 291-298
Technical Paper / dx.doi.org/10.13182/NSE61-A25879
Niobium-20 w/o Uranium, High-Temperature Metallic Fuel of the Future
Nuclear Science and Engineering / Volume 9 / Number 3 / March 1961 / Pages 299-304
Technical Paper / dx.doi.org/10.13182/NSE61-A25880
Time-Dependent Thermal-Neutron Energy Spectra in a Monatomic Heavy Gas
Nuclear Science and Engineering / Volume 9 / Number 3 / March 1961 / Pages 305-313
Technical Paper / dx.doi.org/10.13182/NSE61-A25881
On the Design and Management of Fast Reactor Blankets
Nuclear Science and Engineering / Volume 9 / Number 3 / March 1961 / Pages 314-322
Technical Paper / dx.doi.org/10.13182/NSE61-A25882
Formal Heat Transfer Solutions
Nuclear Science and Engineering / Volume 9 / Number 3 / March 1961 / Pages 323-331
Technical Paper / dx.doi.org/10.13182/NSE61-A25883
Effect of Specific Power on Fuel Reactivity and Costs in Thorium-Fueled Reactors
Nuclear Science and Engineering / Volume 9 / Number 3 / March 1961 / Pages 332-340
Technical Paper / dx.doi.org/10.13182/NSE61-A25884
The Resonance Fission Integrals of U235, Pu239, and Pu241
Nuclear Science and Engineering / Volume 9 / Number 3 / March 1961 / Pages 341-345
Technical Paper / dx.doi.org/10.13182/NSE61-A25885
Circulating Fused-Salt Fuel Irradiation Test Loop
Nuclear Science and Engineering / Volume 9 / Number 3 / March 1961 / Pages 346-356
Technical Paper / dx.doi.org/10.13182/NSE61-A25886
Nuclear Science and Engineering / Volume 9 / Number 3 / March 1961 / Pages 357-361
Technical Paper / dx.doi.org/10.13182/NSE61-A25887
The Solution of the Reactor Kinetics Equations for Large and Small Excursions
Nuclear Science and Engineering / Volume 9 / Number 3 / March 1961 / Pages 362-366
Technical Paper / dx.doi.org/10.13182/NSE61-A25888
The Effect of Diffusion upon the Initial Phases of the Thermalization of Neutrons
Nuclear Science and Engineering / Volume 9 / Number 3 / March 1961 / Pages 367-369
Technical Paper / dx.doi.org/10.13182/NSE61-A25889
New Analytical Formula for Dancoff Correction for Cylindrical Fuel Lattices
Nuclear Science and Engineering / Volume 9 / Number 3 / March 1961 / Pages 370-376
Technical Paper / dx.doi.org/10.13182/NSE61-A25890
Minimum Critical Dimensions for Water Solutions
Nuclear Science and Engineering / Volume 9 / Number 3 / March 1961 / Pages 377-390
Technical Paper / dx.doi.org/10.13182/NSE61-A25891
Nuclear Science and Engineering / Volume 9 / Number 3 / March 1961 / Pages 391-398
Technical Paper / dx.doi.org/10.13182/NSE61-A25892
Nuclear Science and Engineering / Volume 9 / Number 3 / March 1961 / Pages 399-407
Technical Paper / dx.doi.org/10.13182/NSE61-A25893