Nuclear Science and Engineering / Volume 40 / Number 3 / June 1970 / Pages 365-374
Technical Paper / dx.doi.org/10.13182/NSE70-A20187
A Measurement of the Fission Cross Sections of 239Pu and 233U Relative to 235U
Nuclear Science and Engineering / Volume 40 / Number 3 / June 1970 / Pages 375-382
Technical Paper / dx.doi.org/10.13182/NSE70-A20188
Nuclear Science and Engineering / Volume 40 / Number 3 / June 1970 / Pages 383-388
Technical Paper / dx.doi.org/10.13182/NSE70-A20189
Total Neutron Cross Section of 242Pu
Nuclear Science and Engineering / Volume 40 / Number 3 / June 1970 / Pages 389-395
Technical Paper / dx.doi.org/10.13182/NSE70-A20190
Nuclear Science and Engineering / Volume 40 / Number 3 / June 1970 / Pages 396-406
Technical Paper / dx.doi.org/10.13182/NSE70-A20191
Critical Parameters of a Uranium Solution Slab-Cylinder System
Nuclear Science and Engineering / Volume 40 / Number 3 / June 1970 / Pages 407-413
Technical Paper / dx.doi.org/10.13182/NSE70-A20192
Analysis of Central Reactivity Worths in Fast Critical Assemblies
Nuclear Science and Engineering / Volume 40 / Number 3 / June 1970 / Pages 414-423
Technical Paper / dx.doi.org/10.13182/NSE70-A20193
An Approximate Solution to the Asymptotic Slowing Down Equations of Fast Neutrons
Nuclear Science and Engineering / Volume 40 / Number 3 / June 1970 / Pages 424-437
Technical Paper / dx.doi.org/10.13182/NSE70-A20194
Some Monte Carlo Techniques for the Calculation of Doppler Coefficients
Nuclear Science and Engineering / Volume 40 / Number 3 / June 1970 / Pages 438-448
Technical Paper / dx.doi.org/10.13182/NSE70-A20195
Verification of Space-Time Reactor-Kinetics Analysis by Experiments
Nuclear Science and Engineering / Volume 40 / Number 3 / June 1970 / Pages 449-459
Technical Paper / dx.doi.org/10.13182/NSE70-A20196
Space- and Time-Dependent Neutron Slowing Down
Nuclear Science and Engineering / Volume 40 / Number 3 / June 1970 / Pages 460-471
Technical Paper / dx.doi.org/10.13182/NSE70-A20197
Effect of Neutron Anisotropy on the Depletion of a Cylindrical Burnable Poison Pin
Nuclear Science and Engineering / Volume 40 / Number 3 / June 1970 / Pages 472-477
Technical Paper / dx.doi.org/10.13182/NSE70-A20198
Use of Gauss-Laguerre Numerical Integration for Point Kernel Shielding Calculations
Nuclear Science and Engineering / Volume 40 / Number 3 / June 1970 / Pages 478-483
Technical Note / dx.doi.org/10.13182/NSE70-A20199
Nuclear Science and Engineering / Volume 40 / Number 3 / June 1970 / Pages 483-485
Technical Note / dx.doi.org/10.13182/NSE70-A20200
Prompt Gamma Rays from Thermal Neutron Fission of Uranium-235
Nuclear Science and Engineering / Volume 40 / Number 3 / June 1970 / Pages 485-486
Technical Note / dx.doi.org/10.13182/NSE70-A20201
Photon Cross Sections of Uranium and Plutonium
Nuclear Science and Engineering / Volume 40 / Number 3 / June 1970 / Pages 487-488
Technical Note / dx.doi.org/10.13182/NSE70-A20202
Nuclear Science and Engineering / Volume 40 / Number 3 / June 1970 / Pages 488-491
Technical Note / dx.doi.org/10.13182/NSE70-A20203
Several Particular Solutions of the One-Speed Transport Equation
Nuclear Science and Engineering / Volume 40 / Number 3 / June 1970 / Pages 491-494
Technical Note / dx.doi.org/10.13182/NSE70-A20204
Prompt-Jump Correction of Inverse Kinetics Rod-Drop Measurements
Nuclear Science and Engineering / Volume 40 / Number 3 / June 1970 / Pages 494-498
Technical Note / dx.doi.org/10.13182/NSE70-A20205
Approximate Calculation of Prompt-Critical Excursions
Nuclear Science and Engineering / Volume 40 / Number 3 / June 1970 / Pages 498-500
Technical Note / dx.doi.org/10.13182/NSE70-A20206