Number 1 | Number 2 | Number 3
Description of Critical Experiments in Spherical Geometry Containing UO2F2 Solution
Nuclear Technology / Volume 122 / Number 1 / April 1998 / Pages 1-18
Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT98-A2847
Nuclear Technology / Volume 122 / Number 1 / April 1998 / Pages 19-42
Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT98-A2848
Neutronic and Burnup Characteristics of an Actinide-Reduced Plutonium Fuel with Tungsten
Nuclear Technology / Volume 122 / Number 1 / April 1998 / Pages 43-51
Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT98-A2849
Comparison of Pressurized Water Reactor Core Characteristics for 100% Plutonium-Containing Loadings
Nuclear Technology / Volume 122 / Number 1 / April 1998 / Pages 52-63
Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT98-A2850
Nuclear Technology / Volume 122 / Number 1 / April 1998 / Pages 64-71
Technical Paper / Reprocessing / dx.doi.org/10.13182/NT98-A2851
Nuclear Technology / Volume 122 / Number 1 / April 1998 / Pages 72-82
Technical Paper / Reactor Operations and Control / dx.doi.org/10.13182/NT98-A2852
Nuclear Technology / Volume 122 / Number 1 / April 1998 / Pages 83-92
Technical Paper / Reactor Operations and Control / dx.doi.org/10.13182/NT98-A2853
Nuclear Technology / Volume 122 / Number 1 / April 1998 / Pages 93-103
Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT98-A2854
Nuclear Technology / Volume 122 / Number 1 / April 1998 / Pages 104-124
Technical Paper / Radioisotopes / dx.doi.org/10.13182/NT98-A2855
RETRAN-03 Simulation of a Multiple Failure Event at Kori Unit 2
Nuclear Technology / Volume 122 / Number 2 / May 1998 / Pages 125-131
Technical Paper / RETRAN / dx.doi.org/10.13182/NT98-A2856
The RETRAN-3D Code; Pressurized Water Reactor Multidimensional Neutron Kinetics Applications
Nuclear Technology / Volume 122 / Number 2 / May 1998 / Pages 132-145
Technical Paper / RETRAN / dx.doi.org/10.13182/NT98-A2857
RETRAN Benchmarks of LaSalle Units 1 and 2 Startup Tests
Nuclear Technology / Volume 122 / Number 2 / May 1998 / Pages 146-157
Technical Paper / RETRAN / dx.doi.org/10.13182/NT98-A2858
Analysis of WNP-2 Single-Loop Operation Using RETRAN-02
Nuclear Technology / Volume 122 / Number 2 / May 1998 / Pages 158-169
Technical Paper / RETRAN / dx.doi.org/10.13182/NT98-A2859
A Probabilistic Approach for the Evaluation of Reactivity Insertion Accident Effects
Nuclear Technology / Volume 122 / Number 2 / May 1998 / Pages 170-178
Technical Paper / RETRAN / dx.doi.org/10.13182/NT98-A2860
Design and Development of Fast Breeder Reactor Passive Reactivity Control Systems: LEM and LIM
Nuclear Technology / Volume 122 / Number 2 / May 1998 / Pages 179-195
Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT98-A2861
Nuclear Technology / Volume 122 / Number 2 / May 1998 / Pages 196-210
Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT98-A2862
Calculation of Radiation Dose Rates in a Water Layer in Contact with Used CANDU UO2 Fuel
Nuclear Technology / Volume 122 / Number 2 / May 1998 / Pages 211-221
Technical Paper / Radiation / dx.doi.org/10.13182/NT98-A2863
Reduction of Neptunium(VI) by Butyraldehyde Isomers in Nitric Acid Solution
Nuclear Technology / Volume 122 / Number 2 / May 1998 / Pages 222-227
Technical Paper / Enrichment / dx.doi.org/10.13182/NT98-A2864
Nuclear Technology / Volume 122 / Number 2 / May 1998 / Pages 228-249
Technical Paper / Decontamination/Decommissioning / dx.doi.org/10.13182/NT98-A2865
Nuclear Technology / Volume 122 / Number 2 / May 1998 / Pages 250-253
Technical Note / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT98-A2866
Criticality Analysis of the Multiplying Material Inside the Chernobyl Sarcophagus
Nuclear Technology / Volume 122 / Number 3 / June 1998 / Pages 255-264
Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT98-A2867
Nonuniformity Effect on Reactivity of Fuel in Slurry
Nuclear Technology / Volume 122 / Number 3 / June 1998 / Pages 265-275
Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT98-A2868
Fission Gas Release Determination Using an Anti-Compton Shield Detector
Nuclear Technology / Volume 122 / Number 3 / June 1998 / Pages 276-283
Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT98-A2869
Nuclear Technology / Volume 122 / Number 3 / June 1998 / Pages 284-294
Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT98-A2870
Nuclear Technology / Volume 122 / Number 3 / June 1998 / Pages 295-305
Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT98-A2871
A Structured Methodology for Waste Management Facility Accident Analysis
Nuclear Technology / Volume 122 / Number 3 / June 1998 / Pages 306-317
Technical Paper / Criticality of Nuclear Materials / dx.doi.org/10.13182/NT98-A2872
Nuclear Technology / Volume 122 / Number 3 / June 1998 / Pages 318-329
Technical Paper / Reactor Operations and Control / dx.doi.org/10.13182/NT98-A2873
Nuclear Applications of Accelerator-Driven Spallation Targets
Nuclear Technology / Volume 122 / Number 3 / June 1998 / Pages 330-354
Technical Paper / Accelerators / dx.doi.org/10.13182/NT98-A2874