The Integral 9Be (n,2n) Cross Section
Nuclear Science and Engineering / Volume 25 / Number 1 / May 1966 / Pages 1-7
Technical Paper / dx.doi.org/10.13182/NSE66-A17494
Effective Thermal-Neutron Cross Sections for Materials with Grain Structure
Nuclear Science and Engineering / Volume 25 / Number 1 / May 1966 / Pages 8-11
Technical Paper / dx.doi.org/10.13182/NSE66-A17495
Burnup Cross Sections and Resonance Integrals of Dysprosium
Nuclear Science and Engineering / Volume 25 / Number 1 / May 1966 / Pages 12-20
Technical Paper / dx.doi.org/10.13182/NSE66-A17496
Neutron Spectra in Light or Heavy Water Within a Container Located Inside a Uranium Tube
Nuclear Science and Engineering / Volume 25 / Number 1 / May 1966 / Pages 21-30
Technical Paper / dx.doi.org/10.13182/NSE66-A17497
Parameters of Neutron Resonances in 184W
Nuclear Science and Engineering / Volume 25 / Number 1 / May 1966 / Pages 31-36
Technical Paper / dx.doi.org/10.13182/NSE66-A17498
Doppler Effect Measurements in Plutonium-Fueled Fast Power Breeder Reactor Spectra
Nuclear Science and Engineering / Volume 25 / Number 1 / May 1966 / Pages 37-46
Technical Paper / dx.doi.org/10.13182/NSE66-A17499
A Nonlinear Study of Reactors with a Linear Feedback
Nuclear Science and Engineering / Volume 25 / Number 1 / May 1966 / Pages 47-57
Technical Paper / dx.doi.org/10.13182/NSE66-A17500
The Stabilized March Technique Applied to the Diffusion Equation
Nuclear Science and Engineering / Volume 25 / Number 1 / May 1966 / Pages 58-65
Technical Paper / dx.doi.org/10.13182/NSE66-A17501
Dose Attenuation in Two-Legged Concrete Ducts for Various Gamma-Ray Energies
Nuclear Science and Engineering / Volume 25 / Number 1 / May 1966 / Pages 66-74
Technical Paper / dx.doi.org/10.13182/NSE66-A17502
Transport Effects in the P3 Treatment of Cylindrical Rods in a Square Lattice
Nuclear Science and Engineering / Volume 25 / Number 1 / May 1966 / Pages 75-84
Technical Paper / dx.doi.org/10.13182/NSE66-A17503
Dose Buildup Factors of Plane Parallel Barriers for 60Co Plane Monodirectional Source
Nuclear Science and Engineering / Volume 25 / Number 1 / May 1966 / Pages 85-92
Technical Paper / dx.doi.org/10.13182/NSE66-A17504
Yields of 133I in the Fission of 233U and 239Pu Relative to that for 235U
Nuclear Science and Engineering / Volume 25 / Number 1 / May 1966 / Pages 93-94
Technical Note / dx.doi.org/10.13182/NSE66-A17505
Rigorous Solution of the Initial Value Problem of the Time-Dependent Reactor Transport
Nuclear Science and Engineering / Volume 25 / Number 1 / May 1966 / Pages 94-95
Technical Note / dx.doi.org/10.13182/NSE66-A17506
Nuclear Science and Engineering / Volume 25 / Number 1 / May 1966 / Pages 95-96
Technical Note / dx.doi.org/10.13182/NSE66-A17507