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The U.S. Department of Defense has awarded NorthStar Group Services subsidiary NorthStar Maritime Dismantlement Services a firm-fixed-price contract worth $536,749,731 for the dismantling, recycling, and disposal of the historic USS Enterprise (now also known as the ex-Enterprise), the world’s first nuclear-powered aircraft carrier. The work will be performed in Mobile, Ala., and is expected to be completed by November 2029.
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Introduction to the Annular Fuel Special Issue
Mujid S. Kazimi
Nuclear Technology | Volume 160 | Number 1 | October 2007 | Page 1
Technical Paper | Annular Fuel | doi.org/10.13182/NT160-1-1
Annular Fuel for High-Power-Density Pressurized Water Reactors: Motivation and Overview
Pavel Hejzlar, Mujid S. Kazimi
Nuclear Technology | Volume 160 | Number 1 | October 2007 | Pages 2-15
Technical Paper | Annular Fuel | doi.org/10.13182/NT160-2-15
Thermal-Hydraulic Design of High-Power-Density Annular Fuel in PWRs
Dandong Feng, Pavel Hejzlar, Mujid S. Kazimi
Nuclear Technology | Volume 160 | Number 1 | October 2007 | Pages 16-44
Technical Paper | Annular Fuel | doi.org/10.13182/NT07-A3882
Safety Analysis of High-Power-Density Annular Fuel for PWRs
Dandong Feng, Paolo Morra, Ramu Sundaram, Won-Jae Lee, Pradip Saha, Pavel Hejzlar, Mujid S. Kazimi
Nuclear Technology | Volume 160 | Number 1 | October 2007 | Pages 45-62
Technical Paper | Annular Fuel | doi.org/10.13182/NT07-A3883
High-Performance Annular Fuel Reactor Physics and Fuel Management
Zhiwen Xu, Yasuyuki Otsuka, Pavel Hejzlar, Mujid S. Kazimi, Michael J. Driscoll
Nuclear Technology | Volume 160 | Number 1 | October 2007 | Pages 63-79
Technical Paper | Annular Fuel | doi.org/10.13182/NT07-A3884
Fertile-Free Annular Fuel for Plutonium Recycling
Eugene Shwageraus, Pavel Hejzlar, Mujid S. Kazimi
Nuclear Technology | Volume 160 | Number 1 | October 2007 | Pages 80-99
Technical Paper | Annular Fuel | doi.org/10.13182/NT07-A3885
High-Power-Density Annular Fuel: Manufacturing Viability
Edward Lahoda, Herbert Feinroth, Marcelo Salvatore, Diego O. Russo, Holly Hamilton
Nuclear Technology | Volume 160 | Number 1 | October 2007 | Pages 100-111
Technical Paper | Annular Fuel | doi.org/10.13182/NT07-A3886
High-Power-Density Annular Fuel for Pressurized Water Reactors: Manufacturing Costs and Economic Benefits
Edward Lahoda, Jason Mazzoccoli, Julien Beccherle
Nuclear Technology | Volume 160 | Number 1 | October 2007 | Pages 112-134
Technical Paper | Annular Fuel | doi.org/10.13182/NT07-A3887
Thermomechanical Performance of High-Power-Density Annular Fuel
Yi Yuan, M. S. Kazimi, P. Hejzlar
Nuclear Technology | Volume 160 | Number 1 | October 2007 | Pages 135-149
Technical Paper | Annular Fuel | doi.org/10.13182/NT07-A3888
Irradiation Testing of High-Power-Density Vibropacked Annular Fuel
Gordon Kohse, David Carpenter, Yi Yuan, Pavel Hejzlar, Mujid Kazimi
Nuclear Technology | Volume 160 | Number 1 | October 2007 | Pages 150-168
Technical Paper | Annular Fuel | doi.org/10.13182/NT07-A3889
Study on Leak Rate of Gas Medium in Leak-Before-Break Technique - I: Experimental Studies
Zhengming Zhang, Shuyan He
Nuclear Technology | Volume 160 | Number 2 | November 2007 | Pages 170-177
Technical Paper | Fission Reactors | doi.org/10.13182/NT07-A3890
Study on Leak Rate of Gas Medium in Leak-Before-Break Technique - II: Theoretical Studies
Nuclear Technology | Volume 160 | Number 2 | November 2007 | Pages 178-186
Technical Paper | Fission Reactors | doi.org/10.13182/NT07-A3891
Direct Simulation, Monte Carlo, Multicomponent, Aerosol Dynamics: Coagulation, Deposition, and Source Reinforcement
Geethpriya Palaniswaamy, Sudarshan K. Loyalka
Nuclear Technology | Volume 160 | Number 2 | November 2007 | Pages 187-204
Technical Paper | Reactor Safety | doi.org/10.13182/NT160-187
Boron Transport Model with Physical Diffusion for RELAP5
Jordi Freixa, Francesc Reventós, Carme Pretel, Lluís Batet
Nuclear Technology | Volume 160 | Number 2 | November 2007 | Pages 205-215
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT07-A3893
Feasibility Study of a Passive DHR System with Heat Transfer Enhancement Mechanism in a Lead-Cooled Fast Reactor
Jae-Hyuk Eoh, Seyun Kim, Sang-Ji Kim, Seong-O Kim
Nuclear Technology | Volume 160 | Number 2 | November 2007 | Pages 216-232
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT07-A3894
The Synergetic Effects of Nuclear-Assisted Gas Turbine Power Cycles
Yong Hoon Jeong, Mujid S. Kazimi
Nuclear Technology | Volume 160 | Number 2 | November 2007 | Pages 233-243
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT07-A3895
Radiochemical Analysis in Fuel Integrity Evaluation
Chien C. Lin, J. H. Chao
Nuclear Technology | Volume 160 | Number 2 | November 2007 | Pages 244-250
Technical Paper | Radioisotopes | doi.org/10.13182/NT07-A3896
Molecular Dynamics Simulations of Graphite at High Temperatures
Brian D. Hehr, Ayman I. Hawari, Victor H. Gillette
Nuclear Technology | Volume 160 | Number 2 | November 2007 | Pages 251-256
Technical Paper | Materials for Nuclear Systems | doi.org/10.13182/NT07-A3897
Feasibility of Designing the Encapsulated Nuclear Heat Source Reactor with Negative Void Reactivity Feedback
Tsuyoshi Okawa, Ehud Greenspan
Nuclear Technology | Volume 160 | Number 3 | December 2007 | Pages 257-278
Technical Paper | Fission Reactors | doi.org/10.13182/NT07-A3898
On the Fuel and Coolant Interaction Behavior of Partially Oxidized Corium
J. H. Song, J. H. Kim, S. W. Hong, B. T. Min, S. H. Hong
Nuclear Technology | Volume 160 | Number 3 | December 2007 | Pages 279-293
Technical Paper | Reactor Safety | doi.org/10.13182/NT07-A3899
Validation of RCS Bleed-and-Feed Strategy for the SAMG of the Kuosheng Nuclear Power Plant
I Ming Huang, Yuh Ming Ferng, Shih Jen Wang
Nuclear Technology | Volume 160 | Number 3 | December 2007 | Pages 294-307
Technical Paper | Reactor Safety | doi.org/10.13182/NT07-A3900
Initial Size Distribution of Sodium Combustion Aerosol
V. Subramanian, R. Baskaran
Nuclear Technology | Volume 160 | Number 3 | December 2007 | Pages 308-313
Technical Paper | Reactor Safety | doi.org/10.13182/NT07-A3901
Simulation of the Internal Flows of an Inlet Diffuser Assembly for the CANDU-6 Moderator Analysis
Churl Yoon, Joo Hwan Park
Nuclear Technology | Volume 160 | Number 3 | December 2007 | Pages 314-324
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT07-A3902
Use of Fuel Assembly/Backfill Gas Effective Thermal Conductivities to Predict Basket and Fuel Cladding Temperatures Within a Rail Package During Normal Transport
Miles Greiner, Kishore Kumar Gangadharan, Mithun Gudipati
Nuclear Technology | Volume 160 | Number 3 | December 2007 | Pages 325-336
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT07-A3903
Influence of Alpha Radiolysis of Water on UO2 Matrix Alteration: Chemical/Transport Model
A. Poulesquen, C. Jégou
Nuclear Technology | Volume 160 | Number 3 | December 2007 | Pages 337-345
Technical Paper | Materials for Nuclear Systems | doi.org/10.13182/NT07-A3904
Experimental and Numerical Study on the Flow Distribution and the Pressure Drop of a Tubular Fuel
Jong-Hark Park, Hee-Taek Chae, Cheol Park, Heonil Kim
Nuclear Technology | Volume 160 | Number 3 | December 2007 | Pages 346-351
Technical Note | Thermal Hydraulics | doi.org/10.13182/NT07-A3905
Calculated Reduction of the Residual Adsorbent Mass Requiring Long-Term Storage in Radioactive Waste Processing by Magnetic Separation
James H. P. Watson, Patrick Foss-Smith, Ray Lidzey
Nuclear Technology | Volume 160 | Number 3 | December 2007 | Pages 352-360
Technical Note | Radioactive Waste Management and Disposal | doi.org/10.13182/NT07-A3906
Physical Property Modeling of Concentrated Cesium Eluate Solutions - Part I: Derivation of Models
A. S. Choi, R. A. Pierce, T. B. Edwards, T. B. Calloway
Nuclear Technology | Volume 160 | Number 3 | December 2007 | Pages 361-373
Technical Note | Radioisotopes | doi.org/10.13182/NT07-A3907
