Effects of the Contamination by Light Water on Lattices of Natural Uranium Rods in Heavy Water
Nuclear Science and Engineering / Volume 7 / Number 2 / February 1960 / Pages 93-96
Technical Paper / dx.doi.org/10.13182/NSE60-A29076
Thermal Stresses in Nuclear Reactor Vessel Nozzles
Nuclear Science and Engineering / Volume 7 / Number 2 / February 1960 / Pages 97-103
Technical Paper / dx.doi.org/10.13182/NSE60-A29077
Accuracy of the Sn Code in Cell Calculations
Nuclear Science and Engineering / Volume 7 / Number 2 / February 1960 / Pages 104-110
Technical Paper / dx.doi.org/10.13182/NSE60-A29078
Irradiation of Uranium Monocarbide
Nuclear Science and Engineering / Volume 7 / Number 2 / February 1960 / Pages 111-121
Technical Paper / dx.doi.org/10.13182/NSE60-A29079
The Use of the Generation Time in Reactor Kinetics
Nuclear Science and Engineering / Volume 7 / Number 2 / February 1960 / Pages 122-126
Technical Paper / dx.doi.org/10.13182/NSE60-A29080
Convergence of the Sn Method for Thermal Systems
Nuclear Science and Engineering / Volume 7 / Number 2 / February 1960 / Pages 127-132
Technical Paper / dx.doi.org/10.13182/NSE60-A29081
Feasibility of Radioactive Waste Disposal in Shallow Sedimentary Formations
Nuclear Science and Engineering / Volume 7 / Number 2 / February 1960 / Pages 133-143
Technical Paper / dx.doi.org/10.13182/NSE60-A29082
Greuling-Goertzel Calculations in Heavy Water
Nuclear Science and Engineering / Volume 7 / Number 2 / February 1960 / Pages 144-146
Technical Paper / dx.doi.org/10.13182/NSE60-A29083
A Wide-Range Neutron Detector and Monitoring Instrument
Nuclear Science and Engineering / Volume 7 / Number 2 / February 1960 / Pages 147-155
Technical Paper / dx.doi.org/10.13182/NSE60-A29084
Statistical Analysis of Hot Channel Factors
Nuclear Science and Engineering / Volume 7 / Number 2 / February 1960 / Pages 156-161
Technical Paper / dx.doi.org/10.13182/NSE60-A29085
Collision Probabilities and Resonance Integrals for Lattices
Nuclear Science and Engineering / Volume 7 / Number 2 / February 1960 / Pages 162-171
Technical Paper / dx.doi.org/10.13182/NSE60-A29086
Nuclear Science and Engineering / Volume 7 / Number 2 / February 1960 / Pages 172-183
Technical Paper / dx.doi.org/10.13182/NSE60-A29087
The Absorption Cross Section of Copper for Thermal Neutrons
Nuclear Science and Engineering / Volume 7 / Number 2 / February 1960 / Pages 184-186
Technical Paper / dx.doi.org/10.13182/NSE60-A29088
Total Neutron Cross Sections of U233 and U235 from 0.02 to 0.08 ev
Nuclear Science and Engineering / Volume 7 / Number 2 / February 1960 / Pages 187-192
Technical Paper / dx.doi.org/10.13182/NSE60-A29089
Total Cross Sections of Ti, V, Y, Ta, and W
Nuclear Science and Engineering / Volume 7 / Number 2 / February 1960 / Pages 193-197
Technical Paper / dx.doi.org/10.13182/NSE60-A29090