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Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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Colin Judge: Testing structural materials in Idaho’s newest hot cell facility
Idaho National Laboratory’s newest facility—the Sample Preparation Laboratory (SPL)—sits across the road from the Hot Fuel Examination Facility (HFEF), which started operating in 1975. SPL will host the first new hot cells at INL’s Materials and Fuels Complex (MFC) in 50 years, giving INL researchers and partners new flexibility to test the structural properties of irradiated materials fresh from the Advanced Test Reactor (ATR) or from a partner’s facility.
Materials meant to withstand extreme conditions in fission or fusion power plants must be tested under similar conditions and pushed past their breaking points so performance and limitations can be understood and improved. Once irradiated, materials samples can be cut down to size in SPL and packaged for testing in other facilities at INL or other national laboratories, commercial labs, or universities. But they can also be subjected to extreme thermal or corrosive conditions and mechanical testing right in SPL, explains Colin Judge, who, as INL’s division director for nuclear materials performance, oversees SPL and other facilities at the MFC.
SPL won’t go “hot” until January 2026, but Judge spoke with NN staff writer Susan Gallier about its capabilities as his team was moving instruments into the new facility.
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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
