Number 1 | Number 2 | Number 3 | Number 4
An Overview of Superphénix Commissioning Tests
Nuclear Science and Engineering / Volume 106 / Number 1 / September 1990 / Pages 1-10
Technical Paper / dx.doi.org/10.13182/NSE90-A23751
Superphénix Core-L.oading Strategy Using the Checkerboard Pattern
Nuclear Science and Engineering / Volume 106 / Number 1 / September 1990 / Pages 11-17
Technical Paper / dx.doi.org/10.13182/NSE90-A23752
Measurement and Predictions of Control Rod Worth
Nuclear Science and Engineering / Volume 106 / Number 1 / September 1990 / Pages 18-29
Technical Paper / dx.doi.org/10.13182/NSE90-02
Superphénix Reactivity and Feedback Coefficients
Nuclear Science and Engineering / Volume 106 / Number 1 / September 1990 / Pages 30-36
Technical Paper / dx.doi.org/10.13182/NSE90-A23754
Power and Neutron Flux Distributions in the Core and Shielding
Nuclear Science and Engineering / Volume 106 / Number 1 / September 1990 / Pages 37-46
Technical Paper / dx.doi.org/10.13182/NSE90-A23755
Measurement of Core Thermal-Hydraulic Characteristics
Nuclear Science and Engineering / Volume 106 / Number 1 / September 1990 / Pages 47-54
Technical Paper / dx.doi.org/10.13182/NSE90-A23756
Assessment of Thermal-Hydraulic Characteristics of the Primary Circuit
Nuclear Science and Engineering / Volume 106 / Number 1 / September 1990 / Pages 55-63
Technical Paper / dx.doi.org/10.13182/NSE90-A23757
Analysis of Specific Control Rod Experiments Involving Highly Distorted Flux Distributions
Nuclear Science and Engineering / Volume 106 / Number 1 / September 1990 / Pages 64-68
Technical Paper / dx.doi.org/10.13182/NSE90-A23758
An Analysis of the Dynamic Behavior of the Core
Nuclear Science and Engineering / Volume 106 / Number 1 / September 1990 / Pages 69-74
Technical Paper / dx.doi.org/10.13182/NSE90-A23759
Coolant Mixing Phenomena Influencing Measurements of Core Coolant Temperature Rises
Nuclear Science and Engineering / Volume 106 / Number 1 / September 1990 / Pages 75-80
Technical Paper / dx.doi.org/10.13182/NSE90-A23760
Neutron Monitoring and the Inherent Source of Superphénix
Nuclear Science and Engineering / Volume 106 / Number 1 / September 1990 / Pages 81-87
Technical Paper / dx.doi.org/10.13182/NSE90-A23761
Comparison of Failed Fuel Detection Mock-Up with Superphénix Measurements
Nuclear Science and Engineering / Volume 106 / Number 1 / September 1990 / Pages 88-93
Technical Paper / dx.doi.org/10.13182/NSE90-A23762
Measurement of Decay Heat and Comparison with Predictions
Nuclear Science and Engineering / Volume 106 / Number 1 / September 1990 / Pages 94-97
Technical Paper / dx.doi.org/10.13182/NSE90-A23763
Nuclear Science and Engineering / Volume 106 / Number 2 / October 1990 / Pages 99-113
Technical Paper / dx.doi.org/10.13182/NSE90-A27464
The Tokamak as a Neutron Source
Nuclear Science and Engineering / Volume 106 / Number 2 / October 1990 / Pages 114-137
Technical Paper / dx.doi.org/10.13182/NSE90-A27465
High-Performance Beam-Plasma Neutron Sources for Fusion Materials Development
Nuclear Science and Engineering / Volume 106 / Number 2 / October 1990 / Pages 138-155
Technical Paper / dx.doi.org/10.13182/NSE90-A27466
Neutron Production from a Novel Approach to Inertial Fusion
Nuclear Science and Engineering / Volume 106 / Number 2 / October 1990 / Pages 156-159
Technical Paper / dx.doi.org/10.13182/NSE90-A27467
Nuclear Science and Engineering / Volume 106 / Number 2 / October 1990 / Pages 160-182
Technical Paper / dx.doi.org/10.13182/NSE90-A27468
Proposal for a High-lntensity 14-MeV Cutoff Neutron Source Based on the 1H(t,n)1He Source Reaction
Nuclear Science and Engineering / Volume 106 / Number 2 / October 1990 / Pages 183-191
Technical Paper / dx.doi.org/10.13182/NSE90-07
Nuclear Science and Engineering / Volume 106 / Number 2 / October 1990 / Pages 192-207
Technical Paper / dx.doi.org/10.13182/NSE90-A27470
The Los Alamos National Laboratory Spallation Neutron Sources
Nuclear Science and Engineering / Volume 106 / Number 2 / October 1990 / Pages 208-218
Technical Paper / dx.doi.org/10.13182/NSE90-A27471
Nuclear Science and Engineering / Volume 106 / Number 2 / October 1990 / Pages 219-227
Technical Paper / dx.doi.org/10.13182/NSE90-A27472
Rotating Target 14-MeV Neutron Generators
Nuclear Science and Engineering / Volume 106 / Number 2 / October 1990 / Pages 228-233
Technical Paper / dx.doi.org/10.13182/NSE90-A27473
Mirror-Based Neutron Sources for Fusion Technology Studies
Nuclear Science and Engineering / Volume 106 / Number 3 / November 1990 / Pages 235-242
Technical Paper / dx.doi.org/10.13182/NSE90-A29052
KORONA, An Intense Sealed-Tube 14-MeV Neutron Generator
Nuclear Science and Engineering / Volume 106 / Number 3 / November 1990 / Pages 243-248
Technical Paper / dx.doi.org/10.13182/NSE90-A29053
Status of OKTAVIAN I and Proposal for OKTAVIAN II
Nuclear Science and Engineering / Volume 106 / Number 3 / November 1990 / Pages 249-265
Technical Paper / dx.doi.org/10.13182/NSE90-A29054
The Multipurpose 14-MeV Neutron Source at Bratislava
Nuclear Science and Engineering / Volume 106 / Number 3 / November 1990 / Pages 266-278
Technical Paper / dx.doi.org/10.13182/NSE90-A29055
Sources of Variable Energy Monoenergetic Neutrons for Fusion-Related Applications
Nuclear Science and Engineering / Volume 106 / Number 3 / November 1990 / Pages 279-295
Technical Paper / dx.doi.org/10.13182/NSE90-A29056
A Rotating Gas Cell for High-lntensity Monoenergetic Neutron Production
Nuclear Science and Engineering / Volume 106 / Number 3 / November 1990 / Pages 296-298
Technical Paper / dx.doi.org/10.13182/NSE90-A29057
Dense Plasma Focus as a Neutron Source for Fusion Research
Nuclear Science and Engineering / Volume 106 / Number 3 / November 1990 / Pages 299-307
Technical Paper / dx.doi.org/10.13182/NSE90-A29058
Neutron Production from the Deuteron Breakup Reaction on Deuterium
Nuclear Science and Engineering / Volume 106 / Number 3 / November 1990 / Pages 308-317
Technical Paper / dx.doi.org/10.13182/NSE90-A29059
Summary of Monoenergetic Neutron Beam Sources for Energies >14 MeV
Nuclear Science and Engineering / Volume 106 / Number 3 / November 1990 / Pages 318-331
Technical Paper / dx.doi.org/10.13182/NSE90-A29060
Calibrated Fission and Fusion Neutron Fields at the Kyoto University Reactor
Nuclear Science and Engineering / Volume 106 / Number 3 / November 1990 / Pages 332-344
Technical Paper / dx.doi.org/10.13182/NSE90-A29061
Evaluation of 252Cf Prompt Fission Neutron Data from 0 to 20 MeV by Watt Spectrum Fit
Nuclear Science and Engineering / Volume 106 / Number 3 / November 1990 / Pages 345-352
Technical Paper / dx.doi.org/10.13182/NSE89-177
The 252Cf(sf) Neutron Spectrum in the 5- to 20-MeV Energy Range
Nuclear Science and Engineering / Volume 106 / Number 3 / November 1990 / Pages 353-366
Technical Paper / dx.doi.org/10.13182/NSE90-A29063
Nuclear Science and Engineering / Volume 106 / Number 3 / November 1990 / Pages 367-376
Technical Paper / dx.doi.org/10.13182/NSE90-A29064
Nuclear Science and Engineering / Volume 106 / Number 3 / November 1990 / Pages 377-398
Technical Paper / dx.doi.org/10.13182/NSE90-A29065
Analog and Digital Dynamic Compensation Techniques for Delayed Self-Powered Neutron Detectors
Nuclear Science and Engineering / Volume 106 / Number 4 / December 1990 / Pages 399-408
Technical Paper / dx.doi.org/10.13182/NSE90-A23765
Accurate Determination of (n,2n) Cross Sections for Heavy Nuclei from Neutron Production Spectra
Nuclear Science and Engineering / Volume 106 / Number 4 / December 1990 / Pages 409-414
Technical Paper / dx.doi.org/10.13182/NSE90-A23766
R Matrix Analysis of the 241 Pu Neutron Cross Sections in the Thermal to 300-eV Energy Range
Nuclear Science and Engineering / Volume 106 / Number 4 / December 1990 / Pages 415-433
Technical Paper / dx.doi.org/10.13182/NSE90-A23767
R Matrix Analysis of 239Pu Neutron Cross Sections in the Energy Range Up to 1000 eV
Nuclear Science and Engineering / Volume 106 / Number 4 / December 1990 / Pages 434-451
Technical Paper / dx.doi.org/10.13182/NSE90-A23768
Attenuation of External Bremsstrahlung in Metallic Absorbers
Nuclear Science and Engineering / Volume 106 / Number 4 / December 1990 / Pages 452-456
Technical Paper / dx.doi.org/10.13182/NSE90-A23769
Scattering Model Approximations for Neutron Thermalization Problems
Nuclear Science and Engineering / Volume 106 / Number 4 / December 1990 / Pages 457-470
Technical Paper / dx.doi.org/10.13182/NSE90-A23770
The SKN Method I: A High-Order Transport Approximation to Neutron Transport Problems
Nuclear Science and Engineering / Volume 106 / Number 4 / December 1990 / Pages 471-479
Technical Paper / dx.doi.org/10.13182/NSE90-A23771
The The SKN Method II: Heterogeneous Problems
Nuclear Science and Engineering / Volume 106 / Number 4 / December 1990 / Pages 480-488
Technical Paper / dx.doi.org/10.13182/NSE90-A23772
Analysis of In-Core Detector Signals from N Reactor at Shutdown Conditions
Nuclear Science and Engineering / Volume 106 / Number 4 / December 1990 / Pages 489-493
Technical Note / dx.doi.org/10.13182/NSE90-A23773
Nuclear Science and Engineering / Volume 106 / Number 4 / December 1990 / Pages 494-500
Technical Note / dx.doi.org/10.13182/NSE90-A23774