Number 1 | Number 2 | Number 3
A Stylized Three-Dimensional Pressurized Water Reactor Benchmark Problem with UO2 and MOX Fuel
Nuclear Technology / Volume 184 / Number 1 / October 2013 / Pages 1-28
Technical Paper / Reactor Physics / Pressurized Water Reactors / dx.doi.org/10.13182/NT11-124
Nuclear Technology / Volume 184 / Number 1 / October 2013 / Pages 29-41
Technical Paper / Neutron Transport and Shielding / dx.doi.org/10.13182/NT13-A19866
Nuclear Technology / Volume 184 / Number 1 / October 2013 / Pages 42-53
Technical Paper / Fuel Design/Defects/Examination / Fuel Performance/Bu/Isotopes / dx.doi.org/10.13182/NT13-A19867
Rod-Inserted Sintering of Annular Pellets for Dual-Cooled Annular Fuel
Nuclear Technology / Volume 184 / Number 1 / October 2013 / Pages 54-62
Technical Paper / Fuel Design/Defects/Examination / Fuel Performance/Bu/Isotopes / dx.doi.org/10.13182/NT13-A19868
Nuclear Technology / Volume 184 / Number 1 / October 2013 / Pages 63-77
Technical Paper / Fuel Design/Defects/Examination / Materials for Nuclear Fuels / dx.doi.org/10.13182/NT13-A19869
Evolution of Charged Aerosols: Role of Charge on Coagulation
Nuclear Technology / Volume 184 / Number 1 / October 2013 / Pages 78-95
Technical Paper / Source Term Assessment / dx.doi.org/10.13182/NT184-78
Nuclear Technology / Volume 184 / Number 1 / October 2013 / Pages 96-106
Technical Paper / Source Term Assessment / Techniques for Measurements of Nuclear Data / Nondestructive Examination/Testing Methods / dx.doi.org/10.13182/NT13-A19871
Nuclear Technology / Volume 184 / Number 1 / October 2013 / Pages 107-120
Technical Paper / Pyrometallurgical Reprocessing / dx.doi.org/10.13182/NT13-A19872
Resource Requirements and Proliferation Risks Associated with Small Modular Reactors
Nuclear Technology / Volume 184 / Number 1 / October 2013 / Pages 121-129
Technical Paper / Proliferation Issues/Nuclear Safeguards / dx.doi.org/10.13182/NT13-A19873
Nuclear Technology / Volume 184 / Number 2 / November 2013 / Pages 131-147
Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT13-A22310
Nuclear Technology / Volume 184 / Number 2 / November 2013 / Pages 148-155
Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT13-A22311
Parametric Core Analysis and Economic Feasibility of a Thorium Heavy Water Breeder Reactor
Nuclear Technology / Volume 184 / Number 2 / November 2013 / Pages 156-168
Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT13-22
The Energy Multiplier Module: Advancing the Nuclear Fuel Cycle Through Technology Innovations
Nuclear Technology / Volume 184 / Number 2 / November 2013 / Pages 169-180
Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT13-A22313
Nuclear Technology / Volume 184 / Number 2 / November 2013 / Pages 181-197
Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT184-181
Design, Construction, and Demonstration of the Colorado School of Mines Neutron Imaging Facility
Nuclear Technology / Volume 184 / Number 2 / November 2013 / Pages 198-209
Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT13-A22315
Nuclear Technology / Volume 184 / Number 2 / November 2013 / Pages 210-216
Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT13-A22316
Experimental Validation of the DARWIN2.3 Package for Fuel Cycle Applications
Nuclear Technology / Volume 184 / Number 2 / November 2013 / Pages 217-232
Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT12-121
Optimized Design of a PGNAA System for Cement Analysis Using Monte Carlo Simulations
Nuclear Technology / Volume 184 / Number 2 / November 2013 / Pages 233-238
Technical Paper / Radiation Transport and Protection / dx.doi.org/10.13182/NT13-A22318
A Notable Comparison of Computational Geometries in MCNP6 Calculations
Nuclear Technology / Volume 184 / Number 2 / November 2013 / Pages 239-248
Technical Paper / Radiation Transport and Protection / dx.doi.org/10.13182/NT13-A22319
The Issue of Accelerator Beam Trips for Efficient ADS Operation
Nuclear Technology / Volume 184 / Number 2 / November 2013 / Pages 249-260
Technical Paper / Accelerators / dx.doi.org/10.13182/NT12-75
BWR-HD: An Optimized Boiling Water Reactor with High Power Density
Nuclear Technology / Volume 184 / Number 3 / December 2013 / Pages 261-273
Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT13-A24984
Safety Analysis of BWR-HD: An Optimized Boiling Water Reactor with High Power Density
Nuclear Technology / Volume 184 / Number 3 / December 2013 / Pages 274-286
Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT13-A24985
Stability Analysis of BWR-HD: An Optimized Boiling Water Reactor with High Power Density
Nuclear Technology / Volume 184 / Number 3 / December 2013 / Pages 287-296
Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT13-A24986
Nuclear Technology / Volume 184 / Number 3 / December 2013 / Pages 297-309
Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT13-A24987
Operating Manipulator Arm by Robot Suit HAL for Remote In-Cell Equipment Maintenance
Nuclear Technology / Volume 184 / Number 3 / December 2013 / Pages 310-319
Technical Paper / Robotic and Remote Systems / Human Factors / dx.doi.org/10.13182/NT13-A24988
Nuclear Technology / Volume 184 / Number 3 / December 2013 / Pages 320-332
Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT13-A24989
Uncertainty and Sensitivity Study in the Frame of TRACE Validation for Reflood Experiment
Nuclear Technology / Volume 184 / Number 3 / December 2013 / Pages 333-350
Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT184-333
Nuclear Technology / Volume 184 / Number 3 / December 2013 / Pages 351-363
Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT13-A24991