Volume 1
Number 2
Calculation of Neutron Radiative Capture Cross Sections
Nuclear Science and Engineering / Volume 1 / Number 2 / May 1956 / Pages 103-107
Technical Paper / dx.doi.org/10.13182/NSE56-A17514
An Effective Capture Cross Section of Np239 for Thermal Reactor Neutrons
Nuclear Science and Engineering / Volume 1 / Number 2 / May 1956 / Pages 108-111
Technical Paper / dx.doi.org/10.13182/NSE56-A17515
An Unreflected U-235 Critical Assembly
Nuclear Science and Engineering / Volume 1 / Number 2 / May 1956 / Pages 112-125
Technical Paper / dx.doi.org/10.13182/NSE56-1
ZPR-III, Argonne's Fast Critical Facility
Nuclear Science and Engineering / Volume 1 / Number 2 / May 1956 / Pages 126-134
Technical Paper / dx.doi.org/10.13182/NSE56-A17517
Small Liquid Metal Fueled Reactor Systems
Nuclear Science and Engineering / Volume 1 / Number 2 / May 1956 / Pages 135-155
Technical Paper / dx.doi.org/10.13182/NSE56-A17518
The Attenuation of Neutrons by Air Ducts in Shields
Nuclear Science and Engineering / Volume 1 / Number 2 / May 1956 / Pages 156-166
Technical Paper / dx.doi.org/10.13182/NSE56-A17519
A Preliminary Study of Superheating Boiling Reactors
Nuclear Science and Engineering / Volume 1 / Number 2 / May 1956 / Pages 167-173
Technical Paper / dx.doi.org/10.13182/NSE56-A17520
Delayed Neutron Yields in Pu, U-233, U-238, and Th Relative to Yield in U-235
Nuclear Science and Engineering / Volume 1 / Number 2 / May 1956 / Pages 174-184
Technical Paper / dx.doi.org/10.13182/NSE56-A17521
Cyclotron Target for the Irradiation of Chemical Compounds
Nuclear Science and Engineering / Volume 1 / Number 2 / May 1956 / Pages 185-190
Technical Paper / dx.doi.org/10.13182/NSE56-A17522
