Home / Publications / Journals / Nuclear Technology / Volume 145 / Number 3
Design of Recycle Pressurized Water Reactor with Heavy Water Moderation
Nuclear Technology / Volume 145 / Number 3 / March 2004 / Pages 239-246
Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT04-A3473
ABWR-II Core Design with Spectral Shift Rods for Operation with All Control Rods Withdrawn
Nuclear Technology / Volume 145 / Number 3 / March 2004 / Pages 247-256
Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT04-A3474
Technology Development Issues for High-Conversion BWRs Using Island-Type MOX Fuel
Nuclear Technology / Volume 145 / Number 3 / March 2004 / Pages 257-265
Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT04-A3475
Utilization/Disposition of Reactor-Grade Plutonium in High-Temperature Gas-Cooled Reactors
Nuclear Technology / Volume 145 / Number 3 / March 2004 / Pages 266-274
Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT04-A3476
Prognostics and Condition-Based Maintenance: A New Approach to Precursive Metrics
Nuclear Technology / Volume 145 / Number 3 / March 2004 / Pages 275-286
Technical Paper / Nuclear Plant Operations and Control / dx.doi.org/10.13182/NT04-A3477
System Analysis for Decay Heat Removal in Lead-Bismuth-Cooled Natural-Circulation Reactors
Nuclear Technology / Volume 145 / Number 3 / March 2004 / Pages 287-297
Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT04-A3478
An Experimental Study of Sweepout and Entrainment in the Advanced Reactor Downcomer
Nuclear Technology / Volume 145 / Number 3 / March 2004 / Pages 298-310
Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT04-A3479
Gas Core Reactor with Magnetohydrodynamic Power System and Cascading Power Cycle
Nuclear Technology / Volume 145 / Number 3 / March 2004 / Pages 311-318
Technical Note / Fission Reactors / dx.doi.org/10.13182/NT04-A3480
A Proposed Method for the Determination of Leakage Rate for a Reactor Containment Vessel
Nuclear Technology / Volume 145 / Number 3 / March 2004 / Pages 319-323
Technical Note / Nuclear Plant Operations and Control / dx.doi.org/10.13182/NT04-A3481