Number 1 | Number 2 | Number 3
Assigning Uncertainties to Scientific Data
Nuclear Science and Engineering / Volume 126 / Number 1 / May 1997 / Pages 1-18
Technical Paper / dx.doi.org/10.13182/NSE97-A24453
Space-Dependent Resonance Self-Shielding
Nuclear Science and Engineering / Volume 126 / Number 1 / May 1997 / Pages 19-34
Technical Paper / dx.doi.org/10.13182/NSE97-2
Extension of Analytic Function Expansion Nodal Method to Multigroup Problems in Hexagonal-Z Geometry
Nuclear Science and Engineering / Volume 126 / Number 1 / May 1997 / Pages 35-47
Technical Paper / dx.doi.org/10.13182/NSE97-A24455
Simplified Spherical Harmonics in the Variational Nodal Method
Nuclear Science and Engineering / Volume 126 / Number 1 / May 1997 / Pages 48-58
Technical Paper / dx.doi.org/10.13182/NSE97-A24456
An Assessment of the Continuous Neutron Source Using a Low-Energy Electron Accelerator
Nuclear Science and Engineering / Volume 126 / Number 1 / May 1997 / Pages 59-70
Technical Paper / dx.doi.org/10.13182/NSE97-A24457
Uniform Particle Beam Distributions Produced by Octupole Focusing
Nuclear Science and Engineering / Volume 126 / Number 1 / May 1997 / Pages 71-79
Technical Paper / dx.doi.org/10.13182/NSE97-A24458
Physics Study on Direct Use of Spent Pressurized Water Reactor Fuel in CANDU (DUPIC)
Nuclear Science and Engineering / Volume 126 / Number 1 / May 1997 / Pages 80-93
Technical Paper / dx.doi.org/10.13182/NSE97-A24459
Nuclear Science and Engineering / Volume 126 / Number 1 / May 1997 / Pages 94-100
Technical Paper / dx.doi.org/10.13182/NSE97-A24460
Neutron-Induced Reaction Cross Sections Between 9 and 14 MeV
Nuclear Science and Engineering / Volume 126 / Number 1 / May 1997 / Pages 101-107
Technical Paper / dx.doi.org/10.13182/NSE97-A24461
Air-Water Experiment for Annular Flow Pressure Drop in a Small Pipe
Nuclear Science and Engineering / Volume 126 / Number 1 / May 1997 / Pages 108-114
Technical Paper / dx.doi.org/10.13182/NSE97-A24462
A Control Algorithm Capable of Handling Steam Generator Water Level Swell and Shrinkage
Nuclear Science and Engineering / Volume 126 / Number 1 / May 1997 / Pages 115-118
Technical Paper / dx.doi.org/10.13182/NSE97-A24463
Data for the Chilton-Huddleston Photon-Albedo Approximations
Nuclear Science and Engineering / Volume 126 / Number 1 / May 1997 / Pages 119-126
Technical Note / dx.doi.org/10.13182/NSE97-A24464
Nuclear Science and Engineering / Volume 126 / Number 2 / June 1997 / Pages 131-145
Technical Paper / dx.doi.org/10.13182/NSE97-A24467
Nuclear Science and Engineering / Volume 126 / Number 2 / June 1997 / Pages 146-157
Technical Paper / dx.doi.org/10.13182/NSE97-A24468
High-Probability One-Sided Confidence Intervals in Reliability Models
Nuclear Science and Engineering / Volume 126 / Number 2 / June 1997 / Pages 158-167
Technical Paper / dx.doi.org/10.13182/NSE97-A24469
The 14N(n,n′γ) Cross Section of the 2.313-MeV First Excited State
Nuclear Science and Engineering / Volume 126 / Number 2 / June 1997 / Pages 168-175
Technical Paper / dx.doi.org/10.13182/NSE97-A24470
Nuclear Science and Engineering / Volume 126 / Number 2 / June 1997 / Pages 176-186
Technical Paper / dx.doi.org/10.13182/NSE97-A24471
Nuclear Science and Engineering / Volume 126 / Number 2 / June 1997 / Pages 187-200
Technical Paper / dx.doi.org/10.13182/NSE97-A24472
Nuclear Science and Engineering / Volume 126 / Number 2 / June 1997 / Pages 201-212
Technical Paper / dx.doi.org/10.13182/NSE97-A24473
Nuclear Science and Engineering / Volume 126 / Number 2 / June 1997 / Pages 213-223
Technical Paper / dx.doi.org/10.13182/NSE97-A24474
Effective Atomic Numbers of Low-Z Compounds for Photon Interaction
Nuclear Science and Engineering / Volume 126 / Number 2 / June 1997 / Pages 224-228
Technical Paper / dx.doi.org/10.13182/NSE97-A24475
Critical Flow of Initially Highly Subcooled Water Through a Short Capillary
Nuclear Science and Engineering / Volume 126 / Number 2 / June 1997 / Pages 229-238
Technical Paper / dx.doi.org/10.13182/NSE97-A24476
Nuclear Science and Engineering / Volume 126 / Number 2 / June 1997 / Pages 239-244
Technical Paper / dx.doi.org/10.13182/NSE97-A24477
Nuclear Science and Engineering / Volume 126 / Number 3 / July 1997 / Pages 245-263
Technical Paper / dx.doi.org/10.13182/NSE97-A24479
Nuclear Science and Engineering / Volume 126 / Number 3 / July 1997 / Pages 264-281
Technical Paper / dx.doi.org/10.13182/NSE97-A24480
Variational Estimates for Use with the Improved Quasistatic Method for Reactor Dynamics
Nuclear Science and Engineering / Volume 126 / Number 3 / July 1997 / Pages 282-292
Technical Paper / dx.doi.org/10.13182/NSE97-A24481
The Green's Function Method for Nuclear Engineering Applications
Nuclear Science and Engineering / Volume 126 / Number 3 / July 1997 / Pages 293-313
Technical Paper / dx.doi.org/10.13182/NSE97-A24482
A Measurement-Based Method to Determine the Photofission Contribution to Fission Rate
Nuclear Science and Engineering / Volume 126 / Number 3 / July 1997 / Pages 314-323
Technical Paper / dx.doi.org/10.13182/NSE97-A24483
Delayed Neutron Energy Spectra of 87Br, 88Br, 89Br, 90 Br, 137l, 138l, 139l, and 136Te
Nuclear Science and Engineering / Volume 126 / Number 3 / July 1997 / Pages 324-332
Technical Paper / dx.doi.org/10.13182/NSE97-A24484
Nuclear Science and Engineering / Volume 126 / Number 3 / July 1997 / Pages 333-340
Technical Paper / dx.doi.org/10.13182/NSE97-A24485
Evidence of Source Dominance in the Dynamic Behavior of Accelerator-Driven Systems
Nuclear Science and Engineering / Volume 126 / Number 3 / July 1997 / Pages 341-344
Technical Note / dx.doi.org/10.13182/NSE97-A24486