Tritium Generation in the Coolant-Moderator of Pressurized Water Reactors
Nuclear Science and Engineering / Volume 49 / Number 3 / November 1972 / Pages 247-254
Technical Paper / dx.doi.org/10.13182/NSE72-A22539
Optimum Binary Signals for Reactor Frequency Response Measurements
Nuclear Science and Engineering / Volume 49 / Number 3 / November 1972 / Pages 255-262
Technical Paper / dx.doi.org/10.13182/NSE72-A22540
Nuclear Science and Engineering / Volume 49 / Number 3 / November 1972 / Pages 263-273
Technical Paper / dx.doi.org/10.13182/NSE72-A22541
Critical Experiments for the Brookhaven Pulsed Fast Reactor Study
Nuclear Science and Engineering / Volume 49 / Number 3 / November 1972 / Pages 274-300
Technical Paper / dx.doi.org/10.13182/NSE72-A22542
The Angular Distribution of Thermal Neutrons at the Surfaces of Black and Grey Cylinders
Nuclear Science and Engineering / Volume 49 / Number 3 / November 1972 / Pages 301-309
Technical Paper / dx.doi.org/10.13182/NSE72-A22543
The Ratio of the Uranium-238 to Uranium-235 Fission Cross Sections from 1 to 5 MeV
Nuclear Science and Engineering / Volume 49 / Number 3 / November 1972 / Pages 310-316
Technical Paper / dx.doi.org/10.13182/NSE72-A22544
Neutron Capture Cross Sections in the keV Region for 154Sm, 160Gd, 164Dy, and 165Ho
Nuclear Science and Engineering / Volume 49 / Number 3 / November 1972 / Pages 317-329
Technical Paper / dx.doi.org/10.13182/NSE72-A22545
Measurement and Analysis of Fast Neutron Spectra in Uranium Depleted in the Uranium-235 Isotope
Nuclear Science and Engineering / Volume 49 / Number 3 / November 1972 / Pages 330-348
Technical Paper / dx.doi.org/10.13182/NSE72-A22546
Nuclear Science and Engineering / Volume 49 / Number 3 / November 1972 / Pages 349-357
Technical Paper / dx.doi.org/10.13182/NSE72-A22547
Nuclear Science and Engineering / Volume 49 / Number 3 / November 1972 / Pages 358-369
Technical Paper / dx.doi.org/10.13182/NSE72-A22548
The Integral Transform Method for the Average Neutron Transport Properties of a Lattice
Nuclear Science and Engineering / Volume 49 / Number 3 / November 1972 / Pages 370-376
Technical Note / dx.doi.org/10.13182/NSE72-A22549
Analytical Treatment of Neutron Age in Perpendicular Direction in Slab Lattices
Nuclear Science and Engineering / Volume 49 / Number 3 / November 1972 / Pages 376-384
Technical Note / dx.doi.org/10.13182/NSE72-A22550
The Treatment of Boundary Value Problems in Optically Thick Media by Means of Lie Series
Nuclear Science and Engineering / Volume 49 / Number 3 / November 1972 / Pages 384-387
Technical Note / dx.doi.org/10.13182/NSE72-A22551
Calculations of Cadmium Cutoff Energies
Nuclear Science and Engineering / Volume 49 / Number 3 / November 1972 / Pages 387-389
Technical Note / dx.doi.org/10.13182/NSE72-A22552
Note on the Fast Neutron Cross Sections of Palladium
Nuclear Science and Engineering / Volume 49 / Number 3 / November 1972 / Pages 389-392
Technical Note / dx.doi.org/10.13182/NSE72-A22553
Total Neutron Cross Section of Mylar at Low Energies
Nuclear Science and Engineering / Volume 49 / Number 3 / November 1972 / Pages 392-393
Technical Note / dx.doi.org/10.13182/NSE72-A22554
Specification and Testing of Nuclear Data Required for Monte Carlo Transport Calculations
Nuclear Science and Engineering / Volume 49 / Number 3 / November 1972 / Pages 394-395
Technical Note / dx.doi.org/10.13182/NSE72-A22555
Nuclear Science and Engineering / Volume 49 / Number 3 / November 1972 / Pages 395-398
Technical Note / dx.doi.org/10.13182/NSE72-A22556
Laminar- and Slug-Flow Heat Transfer Characteristics of Fuel Rods Adjacent to Fuel Subassembly Walls
Nuclear Science and Engineering / Volume 49 / Number 3 / November 1972 / Pages 398-404
Technical Note / dx.doi.org/10.13182/NSE72-A22557