Number 1
Nuclear Technology | Volume 147 | Number 1 | July 2004 | Pages 1-7
Technical Paper | Thoria-Urania NERI | doi.org/10.13182/NT04-A3510
Core Designs and Economic Analyses of Homogeneous Thoria-Urania Fuel in Light Water Reactors
Nuclear Technology | Volume 147 | Number 1 | July 2004 | Pages 8-19
Technical Paper | Thoria-Urania NERI | doi.org/10.13182/NT03-29
Microheterogeneous Thoria-Urania Fuels for Pressurized Water Reactors
Nuclear Technology | Volume 147 | Number 1 | July 2004 | Pages 20-36
Technical Paper | Thoria-Urania NERI | doi.org/10.13182/NT04-A3512
Nuclear Technology | Volume 147 | Number 1 | July 2004 | Pages 37-52
Technical Paper | Thoria-Urania NERI | doi.org/10.13182/NT03-30
Use of Thorium for Transmutation of Plutonium and Minor Actinides in PWRs
Nuclear Technology | Volume 147 | Number 1 | July 2004 | Pages 53-68
Technical Paper | Thoria-Urania NERI | doi.org/10.13182/NT04-A3514
Weapons-Grade Plutonium-Thorium PWR Assembly Design and Core Safety Analysis
Nuclear Technology | Volume 147 | Number 1 | July 2004 | Pages 69-83
Technical Paper | Thoria-Urania NERI | doi.org/10.13182/NT147-69
Thorium-Based Transmuter Fuels for Light Water Reactors
Nuclear Technology | Volume 147 | Number 1 | July 2004 | Pages 84-101
Technical Paper | Thoria-Urania NERI | doi.org/10.13182/NT04-A3516
Costs for Manufacturing Thorium-Uranium Dioxide Fuels for Light Water Reactors
Nuclear Technology | Volume 147 | Number 1 | July 2004 | Pages 102-112
Technical Paper | Thoria-Urania NERI | doi.org/10.13182/NT04-A3517
Fabrication and Thermal Conductivity of (Th,U)O2 Pellets
Nuclear Technology | Volume 147 | Number 1 | July 2004 | Pages 113-119
Technical Paper | Thoria-Urania NERI | doi.org/10.13182/NT04-A3518
The Behavior of ThO2-Based Fuel Rods During Normal Operation and Transient Events in LWRs
Nuclear Technology | Volume 147 | Number 1 | July 2004 | Pages 120-139
Technical Paper | Thoria-Urania NERI | doi.org/10.13182/NT04-A3519
Irradiation Behavior of Thoria-Urania Fuel in a PWR
Nuclear Technology | Volume 147 | Number 1 | July 2004 | Pages 140-148
Technical Paper | Thoria-Urania NERI | doi.org/10.13182/NT04-A3520
Xenon Diffusivity in Thoria-Urania Fuel
Nuclear Technology | Volume 147 | Number 1 | July 2004 | Pages 149-156
Technical Paper | Thoria-Urania NERI | doi.org/10.13182/NT04-A3521
Aqueous Dissolution of Urania-Thoria Nuclear Fuel
Nuclear Technology | Volume 147 | Number 1 | July 2004 | Pages 157-170
Technical Paper | Thoria-Urania NERI | doi.org/10.13182/NT04-A3522
Number 2
Nuclear Technology | Volume 147 | Number 2 | August 2004 | Pages 171-180
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT04-A3523
Computational Fluid Dynamics for the Analysis of Light Water Reactor Flows
Nuclear Technology | Volume 147 | Number 2 | August 2004 | Pages 181-190
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT04-A3524
Validation of Heat Transfer Models in Narrow Gap for RELAP/SCDAPSIM/MOD3.2
Nuclear Technology | Volume 147 | Number 2 | August 2004 | Pages 191-201
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT04-A3525
Hydrogen Generation in Reflooding Experiments with LWR-Type Rod Bundles (QUENCH Program)
Nuclear Technology | Volume 147 | Number 2 | August 2004 | Pages 202-215
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT04-A3526
Identification of Loss-of-Coolant Accidents in LWRs by Inverse Models
Nuclear Technology | Volume 147 | Number 2 | August 2004 | Pages 216-226
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT04-A3527
Software Safety Analysis of Digital Protection System Requirements Using a Qualitative Formal Method
Nuclear Technology | Volume 147 | Number 2 | August 2004 | Pages 227-239
Technical Paper | Nuclear Plant Operations and Control | doi.org/10.13182/NT04-A3528
Design and Validation of Optimized Feedforward with Robust Feedback Control of a Nuclear Reactor
Nuclear Technology | Volume 147 | Number 2 | August 2004 | Pages 240-257
Technical Paper | Nuclear Plant Operations and Control | doi.org/10.13182/NT04-A3529
Water Sorption and Gamma Radiolysis Studies for Uranium Oxides
Nuclear Technology | Volume 147 | Number 2 | August 2004 | Pages 258-268
Technical Paper | Nuclear Plant Operations and Control | doi.org/10.13182/NT04-A3530
Nuclear Technology | Volume 147 | Number 2 | August 2004 | Pages 269-283
Technical Paper | Nuclear Plant Operations and Control | doi.org/10.13182/NT04-A3531
Nuclear Technology | Volume 147 | Number 2 | August 2004 | Pages 284-290
Technical Paper | Reprocessing | doi.org/10.13182/NT04-A3532
Eddy Current Measurements of Corrosion and Metal Loss in Zircaloy Cladding with Ferromagnetic Crud
Nuclear Technology | Volume 147 | Number 2 | August 2004 | Pages 291-300
Technical Paper | Materials for Nuclear Systems | doi.org/10.13182/NT04-A3533
Number 3
Medium-Power Lead-Alloy Reactors: Missions for This Reactor Technology
Nuclear Technology | Volume 147 | Number 3 | September 2004 | Pages 305-320
Technical Paper | Medium-Power Lead-Alloy Reactors | doi.org/10.13182/NT04-A3534
Design Strategy and Constraints for Medium-Power Lead-Alloy–Cooled Actinide Burners
Nuclear Technology | Volume 147 | Number 3 | September 2004 | Pages 321-343
Technical Paper | Medium-Power Lead-Alloy Reactors | doi.org/10.13182/NT147-321
Nuclear Technology | Volume 147 | Number 3 | September 2004 | Pages 344-367
Technical Paper | Medium-Power Lead-Alloy Reactors | doi.org/10.13182/NT04-A3536
Fertile-Free Fast Lead-Cooled Incinerators for Efficient Actinide Burning
Nuclear Technology | Volume 147 | Number 3 | September 2004 | Pages 368-387
Technical Paper | Medium-Power Lead-Alloy Reactors | doi.org/10.13182/NT04-1
Medium-Power Lead-Alloy Fast Reactor Balance-of-Plant Options
Nuclear Technology | Volume 147 | Number 3 | September 2004 | Pages 388-405
Technical Paper | Medium-Power Lead-Alloy Reactors | doi.org/10.13182/NT147-388
Studies of Polonium Removal from Molten Lead-Bismuth for Lead-Alloy-Cooled Reactor Applications
Nuclear Technology | Volume 147 | Number 3 | September 2004 | Pages 406-417
Technical Paper | Medium-Power Lead-Alloy Reactors | doi.org/10.13182/NT04-A3539
Nuclear Technology | Volume 147 | Number 3 | September 2004 | Pages 418-435
Technical Paper | Medium-Power Lead-Alloy Reactors | doi.org/10.13182/NT04-A3540
Corrosion Studies in Support of Medium-Power Lead-Alloy-Cooled Reactor
Nuclear Technology | Volume 147 | Number 3 | September 2004 | Pages 436-456
Technical Paper | Medium-Power Lead-Alloy Reactors | doi.org/10.13182/NT04-A3541
A Qualitative Reactivity and Isotopic Assessment of Fuels for Lead-Alloy-Cooled Fast Reactors
Nuclear Technology | Volume 147 | Number 3 | September 2004 | Pages 457-469
Technical Paper | Medium-Power Lead-Alloy Reactors | doi.org/10.13182/NT04-A3542