Home / Publications / Journals / Nuclear Technology / Volume 170 / Number 3
Volume 170
Number 3
Resolution of Proliferation Issues for a Sodium Fast Reactor Blanket
Nuclear Technology / Volume 170 / Number 3 / June 2010 / Pages 371-382
Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT10-1
Formal Considerations in Establishing Risk-Consistent Acceptance Criteria for Reactor Safety
Nuclear Technology / Volume 170 / Number 3 / June 2010 / Pages 383-396
Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT10-A10325
Validation Status of the ASTEC Integral Code for Severe Accident Simulation
Nuclear Technology / Volume 170 / Number 3 / June 2010 / Pages 397-415
Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT10-A10326
GNEP Hydrided Metal Alloy Fuel-Based Recycling Reactor
Nuclear Technology / Volume 170 / Number 3 / June 2010 / Pages 416-421
Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT10-A10327
Placing Acetic Acid Removal into the UREX+ Process
Nuclear Technology / Volume 170 / Number 3 / June 2010 / Pages 422-429
Technical Paper / Reprocessing / dx.doi.org/10.13182/NT10-A10328
PRAGAMAN: A Computer Code for Simulation of Electrotransport During Molten Salt Electrorefining
Nuclear Technology / Volume 170 / Number 3 / June 2010 / Pages 430-443
Technical Paper / Reprocessing / dx.doi.org/10.13182/NT10-A10329
Analysis of the Waterside Corrosion Kinetics of Zircaloy-4 Fuel Cladding in French PWRs
Nuclear Technology / Volume 170 / Number 3 / June 2010 / Pages 444-459
Technical Paper / Materials for Nuclear Systems / dx.doi.org/10.13182/NT10-A10330
Validation of the Monte Carlo Model of the Greek Research Reactor Core
Nuclear Technology / Volume 170 / Number 3 / June 2010 / Pages 460-464
Technical Note / Fission Reactors / dx.doi.org/10.13182/NT10-A10331
