Volume 2
Number 3
The Neutron Velocity Spectrum in a Heavy Moderator1
Nuclear Science and Engineering / Volume 2 / Number 3 / May 1957 / Pages 227-245
Technical Paper / dx.doi.org/10.13182/NSE57-A25393
Measuring the Ratio of Thermal to Resonance Neutron Densities Using Thick Indium Foils1
Nuclear Science and Engineering / Volume 2 / Number 3 / May 1957 / Pages 246-252
Technical Paper / dx.doi.org/10.13182/NSE57-A25394
Criticality and Flux Calculations for Hydrogenous Assemblies
Nuclear Science and Engineering / Volume 2 / Number 3 / May 1957 / Pages 253-287
Technical Paper / dx.doi.org/10.13182/NSE57-A25395
Nuclear Science and Engineering / Volume 2 / Number 3 / May 1957 / Pages 288-302
Technical Paper / dx.doi.org/10.13182/NSE57-A25396
The Use of Fluidized Beds for the Continuous Drying and Calcination of Dissolved Nitrate Salts
Nuclear Science and Engineering / Volume 2 / Number 3 / May 1957 / Pages 303-319
Technical Paper / dx.doi.org/10.13182/NSE57-A25397
Fast Neutron Damaging in Nuclear Reactors. III. The Radiation Damage Dosage1
Nuclear Science and Engineering / Volume 2 / Number 3 / May 1957 / Pages 320-333
Technical Paper / dx.doi.org/10.13182/NSE57-A25398
Nuclear Science and Engineering / Volume 2 / Number 3 / May 1957 / Pages 334-351
Technical Paper / dx.doi.org/10.13182/NSE57-A25399
Method of Studying Multi-Region Reactors with an Analog Computer
Nuclear Science and Engineering / Volume 2 / Number 3 / May 1957 / Pages 352-362
Technical Paper / dx.doi.org/10.13182/NSE57-A25400
Delayed-Neutron Monitors for the Detection of Sheath Failures in Reactor Fuel Rods
Nuclear Science and Engineering / Volume 2 / Number 3 / May 1957 / Pages 363-372
Technical Paper / dx.doi.org/10.13182/NSE57-A25401
The Thermal Spectrum of an Intermediate Assembly
Nuclear Science and Engineering / Volume 2 / Number 3 / May 1957 / Pages 373-381
Technical Paper / dx.doi.org/10.13182/NSE57-A25402
Reactors, Hazard vs Power Level
Nuclear Science and Engineering / Volume 2 / Number 3 / May 1957 / Pages 382-393
Technical Paper / dx.doi.org/10.13182/NSE57-A25403
Nuclear Science and Engineering / Volume 2 / Number 3 / May 1957 / Pages 394-404
Technical Paper / dx.doi.org/10.13182/NSE57-A25404
