Volume 39
Number 2
Slug-Flow Nusselt Numbers for In-Line Flow Through Unbaffled Rod Bundles
Nuclear Science and Engineering / Volume 39 / Number 2 / February 1970 / Pages 143-150
Technical Paper / dx.doi.org/10.13182/NSE70-A21194
A Variational Approach for the Determination of Neutron Flux Spectra from Detector Activation
Nuclear Science and Engineering / Volume 39 / Number 2 / February 1970 / Pages 151-162
Technical Paper / dx.doi.org/10.13182/NSE70-A21195
Delayed Neutrons from Low Energy Photofission
Nuclear Science and Engineering / Volume 39 / Number 2 / February 1970 / Pages 163-169
Technical Paper / dx.doi.org/10.13182/NSE70-A21196
Neutron Wave Analysis in Finite Media
Nuclear Science and Engineering / Volume 39 / Number 2 / February 1970 / Pages 170-181
Technical Paper / dx.doi.org/10.13182/NSE70-A21197
Neutron Pulse Propagation in a Multiplying Medium
Nuclear Science and Engineering / Volume 39 / Number 2 / February 1970 / Pages 182-192
Technical Paper / dx.doi.org/10.13182/NSE70-A21198
A Study of the Pulsed Neutron Problem in Ice in the Temperature Range 273 to 21°K
Nuclear Science and Engineering / Volume 39 / Number 2 / February 1970 / Pages 193-206
Technical Paper / dx.doi.org/10.13182/NSE70-A21199
Nuclear Science and Engineering / Volume 39 / Number 2 / February 1970 / Pages 207-214
Technical Paper / dx.doi.org/10.13182/NSE70-A21200
Analysis of a Radially Loaded Thermal Reactor
Nuclear Science and Engineering / Volume 39 / Number 2 / February 1970 / Pages 215-225
Technical Paper / dx.doi.org/10.13182/NSE70-A21201
Application of Variational Synthesis to the Optimal Control of Spatially Dependent Reactor Models
Nuclear Science and Engineering / Volume 39 / Number 2 / February 1970 / Pages 226-230
Technical Paper / dx.doi.org/10.13182/NSE70-A21202
Digital Control of the Halden Boiling Water Reactor by a Concept Based on Modern Control Theory
Nuclear Science and Engineering / Volume 39 / Number 2 / February 1970 / Pages 231-240
Technical Paper / dx.doi.org/10.13182/NSE70-A21203
On the Use of Point Kinetics for the Analysis of Rod-Ejection Accidents
Nuclear Science and Engineering / Volume 39 / Number 2 / February 1970 / Pages 241-256
Technical Paper / dx.doi.org/10.13182/NSE70-A21204
The Beta-Decay Half-Life of 241Pu
Nuclear Science and Engineering / Volume 39 / Number 2 / February 1970 / Pages 257-258
Technical Note / dx.doi.org/10.13182/NSE70-A21205
Self-Absorption of Monoenergetic Electrons in Cobalt Foils
Nuclear Science and Engineering / Volume 39 / Number 2 / February 1970 / Pages 258-259
Technical Note / dx.doi.org/10.13182/NSE70-A21206
Nuclear Science and Engineering / Volume 39 / Number 2 / February 1970 / Pages 259-263
Technical Note / dx.doi.org/10.13182/NSE70-A21207
Integral Tests of ENDF/B and GAM Neutron Cross-Section Data in a Clean Fast Assembly
Nuclear Science and Engineering / Volume 39 / Number 2 / February 1970 / Pages 263-272
Technical Note / dx.doi.org/10.13182/NSE70-A21208
Polywater as the Mechanism for the pH-Reactivity Effect in Pressurized Water Reactors
Nuclear Science and Engineering / Volume 39 / Number 2 / February 1970 / Pages 272-273
Technical Note / dx.doi.org/10.13182/NSE70-A21209
Transient Solutions of the Neutron Slowing Down Equation
Nuclear Science and Engineering / Volume 39 / Number 2 / February 1970 / Pages 273-277
Technical Note / dx.doi.org/10.13182/NSE70-A21210
Nuclear Science and Engineering / Volume 39 / Number 2 / February 1970 / Pages 278-283
Technical Note / dx.doi.org/10.13182/NSE70-A21211
On the Validity of Some Approximate Zero-Power Describing Functions
Nuclear Science and Engineering / Volume 39 / Number 2 / February 1970 / Pages 283-285
Technical Note / dx.doi.org/10.13182/NSE70-A21212
