Volume 193
Number 1 | Number 2 | Number 3
Number 1
Validation of a Three-Dimensional Model of EBR-II and Assessment of RELAP5-3D Based on SHRT-17 Test
Nuclear Technology / Volume 193 / Number 1 / January 2016 / Pages 1-14
Technical Paper / Special Issue on the RELAP5-3D Computer Code / dx.doi.org/10.13182/NT14-152
Nuclear Technology / Volume 193 / Number 1 / January 2016 / Pages 15-35
Technical Paper / Special Issue on the RELAP5-3D Computer Code / dx.doi.org/10.13182/NT14-146
Comparison of MYRRHA RELAP5 MOD 3.3 and RELAP5-3D Models on Steady State and PLOF Transient
Nuclear Technology / Volume 193 / Number 1 / January 2016 / Pages 36-46
Technical Paper / Special Issue on the RELAP5-3D Computer Code / dx.doi.org/10.13182/NT14-139
Thirty Years’ Experience in RELAP5 Applications at GRNSPG & NINE
Nuclear Technology / Volume 193 / Number 1 / January 2016 / Pages 47-87
Technical Paper / Special Issue on the RELAP5-3D Computer Code / dx.doi.org/10.13182/NT14-144
Nuclear Technology / Volume 193 / Number 1 / January 2016 / Pages 88-95
Technical Paper / Special Issue on the RELAP5-3D Computer Code / dx.doi.org/10.13182/NT14-147
Content, Completeness, and Consistency of Analytical Models for Regulatory Consideration
Nuclear Technology / Volume 193 / Number 1 / January 2016 / Pages 96-112
Technical Paper / Special Issue on the RELAP5-3D Computer Code / dx.doi.org/10.13182/NT14-143
The BEPU Evaluation Model with RELAP5-3D for the Licensing of the Atucha-II NPP
Nuclear Technology / Volume 193 / Number 1 / January 2016 / Pages 113-160
Technical Paper / Special Issue on the RELAP5-3D Computer Code / dx.doi.org/10.13182/NT14-145
BWR Station Blackout: A RISMC Analysis Using RAVEN and RELAP5-3D
Nuclear Technology / Volume 193 / Number 1 / January 2016 / Pages 161-174
Technical Paper / Special Issue on the RELAP5-3D Computer Code / dx.doi.org/10.13182/NT14-142
Nuclear Technology / Volume 193 / Number 1 / January 2016 / Pages 175-182
Technical Paper / Special Issue on the RELAP5-3D Computer Code / dx.doi.org/10.13182/NT14-138
Development of an Integrated Code System Using R5EXEC and RELAP5-3D
Nuclear Technology / Volume 193 / Number 1 / January 2016 / Pages 183-199
Technical Paper / Special Issue on the RELAP5-3D Computer Code / dx.doi.org/10.13182/NT15-5
RelapManager: A Safety Analysis Automation Framework and Software for RELAP5-3D
Nuclear Technology / Volume 193 / Number 1 / January 2016 / Pages 200-212
Technical Paper / Special Issue on the RELAP5-3D Computer Code / dx.doi.org/10.13182/NT14-140
Nuclear Technology / Volume 193 / Number 1 / January 2016 / Pages 213-217
Technical Note / Special Issue on the RELAP5-3D Computer Code / dx.doi.org/10.13182/NT14-141
Number 2
Economic Analysis of Complex Nuclear Fuel Cycles with NE-COST
Nuclear Technology / Volume 193 / Number 2 / February 2016 / Pages 219-233
Technical Paper / dx.doi.org/10.13182/NT14-113
A Steady-State Thermal-Hydraulic Analysis Method for Prismatic High-Temperature Gas-Cooled Reactors
Nuclear Technology / Volume 193 / Number 2 / February 2016 / Pages 234-246
Technical Paper / dx.doi.org/10.13182/NT15-14
RPV Depressurization Strategy Analysis for Chinshan Nuclear Power Plant by Using MAAP5
Nuclear Technology / Volume 193 / Number 2 / February 2016 / Pages 247-258
Technical Paper / dx.doi.org/10.13182/NT14-118
Modernization and Capability Investigation of the MATRIX Electromagnetic Pump Analysis Code
Nuclear Technology / Volume 193 / Number 2 / February 2016 / Pages 259-275
Technical Paper / dx.doi.org/10.13182/NT14-120
Loose Parts Localization Delay Calculation Method Based on CWT and Hilbert Envelope
Nuclear Technology / Volume 193 / Number 2 / February 2016 / Pages 276-286
Technical Paper / dx.doi.org/10.13182/NT15-12
Lattice Parameter Behavior with Different Nd and O Concentrations in (U1−yNdy)O2±x Solid Solution
Nuclear Technology / Volume 193 / Number 2 / February 2016 / Pages 287-296
Technical Paper / dx.doi.org/10.13182/NT14-136
Chemical Durability of Gamma-Irradiated Glass Fibrous Insulation
Nuclear Technology / Volume 193 / Number 2 / February 2016 / Pages 297-305
Technical Paper / dx.doi.org/10.13182/NT15-22
Nuclear Technology / Volume 193 / Number 2 / February 2016 / Pages 306-317
Technical Paper / dx.doi.org/10.13182/NT15-27
Nuclear Technology / Volume 193 / Number 2 / February 2016 / Pages 318-329
Technical Paper / dx.doi.org/10.13182/NT15-23
Material Irradiation Technology Using Capsules at HANARO
Nuclear Technology / Volume 193 / Number 2 / February 2016 / Pages 330-339
Technical Note / dx.doi.org/10.13182/NT15-19
Number 3
Nuclear Technology / Volume 193 / Number 3 / March 2016 / Pages 341-363
Technical Paper / dx.doi.org/10.13182/NT15-47
A Core Design Study for a Small Modular Boiling Water Reactor with Long-Life Core
Nuclear Technology / Volume 193 / Number 3 / March 2016 / Pages 364-374
Technical Paper / dx.doi.org/10.13182/NT15-58
Nuclear Technology / Volume 193 / Number 3 / March 2016 / Pages 375-390
Technical Paper / dx.doi.org/10.13182/NT15-56
Nuclear Technology / Volume 193 / Number 3 / March 2016 / Pages 391-403
Technical Paper / dx.doi.org/10.13182/NT15-43
The Molten Salt Reactor Point-Kinetic Component of Neutron Noise in Two-Group Diffusion Theory
Nuclear Technology / Volume 193 / Number 3 / March 2016 / Pages 404-415
Technical Paper / dx.doi.org/10.13182/NT15-71
VEGAS: A Fuel Cycle Simulation and Preconditioner Tool with Restricted Material Balances
Nuclear Technology / Volume 193 / Number 3 / March 2016 / Pages 416-429
Technical Paper / dx.doi.org/10.13182/NT15-6
The Immobilization of Triuranium Octoxide by Gadolinium Zirconate
Nuclear Technology / Volume 193 / Number 3 / March 2016 / Pages 430-433
Technical Paper / dx.doi.org/10.13182/NT15-31
Nuclear Technology / Volume 193 / Number 3 / March 2016 / Pages 434-443
Technical Paper / dx.doi.org/10.13182/NT15-32
Numerical Solution of Stochastic Point-Kinetics Neutron Equation with Fuzzy Parameters
Nuclear Technology / Volume 193 / Number 3 / March 2016 / Pages 444-456
Technical Note / dx.doi.org/10.13182/NT15-63
