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Volume 186
Number 3
Assessment of MICROX-2 Code with New ENDF/B-VII Release 0 Master Libraries
Nuclear Technology / Volume 186 / Number 3 / June 2014 / Pages 305-316
Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT12-137
Heterogeneous Cores for Implementation of Thorium-Based Fuels in Heavy Water Reactors
Nuclear Technology / Volume 186 / Number 3 / June 2014 / Pages 317-339
Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT13-85
A Study of the Containment Venting Strategy for the Fukushima Daiichi Accident
Nuclear Technology / Volume 186 / Number 3 / June 2014 / Pages 340-352
Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT12-145
Fuel Management of PWR Cores with Silicon Carbide Cladding
Nuclear Technology / Volume 186 / Number 3 / June 2014 / Pages 353-377
Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT12-131
Uranium Startup Fast Reactors with Metal Fuel Using Once-Through Fuel Cycle
Nuclear Technology / Volume 186 / Number 3 / June 2014 / Pages 378-389
Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT13-21
Nuclear Technology / Volume 186 / Number 3 / June 2014 / Pages 390-402
Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT13-90
Quantitative NDA Measurements of Multiactinide Oxide Fuels
Nuclear Technology / Volume 186 / Number 3 / June 2014 / Pages 403-414
Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT13-18
Predicting Concrete Roadway Contribution to Gamma-Ray Background in Radiation Portal Monitor Systems
Nuclear Technology / Volume 186 / Number 3 / June 2014 / Pages 415-426
Technical Paper / Radiation Transport and Protection / dx.doi.org/10.13182/NT13-98
