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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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Considerations for Realistic Emergency Core Cooling System Evaluation Methodology for Light Water Reactors
U. S. Rohatgi, Pradip Saha, V. K. Chexal
Nuclear Technology | Volume 76 | Number 1 | January 1987 | Pages 11-26
Technical Paper | Fission Reactor | doi.org/10.13182/NT87-A33893
An On-Line Pressurizer Surveillance System Design to Prevent Small-Break Loss-of-Coolant Accidents Through Power-Operated Relief Valves Using a Microcomputer
Jong Ho Lee, Soon Heung Chang
Nuclear Technology | Volume 76 | Number 1 | January 1987 | Pages 27-40
Technical Paper | Nuclear Safety | doi.org/10.13182/NT87-A33894
Determination of Appendix K Conservatisms for Westinghouse Pressurized Water Reactors Using TRAC-PD2/MOD1
U. S. Rohatgi, Christine Yuelys-Miksis, Pradip Saha
Nuclear Technology | Volume 76 | Number 1 | January 1987 | Pages 41-50
Technical Paper | Nuclear Safety | doi.org/10.13182/NT87-A33895
X-Ray Photoelectron Spectroscopy and Electron Probe X-Ray Microanalysis Investigation and Chemical Speciation of Aerosol Samples Formed in Light Water Reactor Core-Melting Experiments
Harald Moers, Hanns Klewe-Nebenius, Hans J. Ache
Nuclear Technology | Volume 76 | Number 1 | January 1987 | Pages 51-59
Technical Paper | Nuclear Safety | doi.org/10.13182/NT87-A33896
The Applications of Nuclear Technology in Reactor Siting
Pao-Shan Weng, Hseuh-Hsing Cheng, Chuan-Chung Hsu, Kuan-Han Sun
Nuclear Technology | Volume 76 | Number 1 | January 1987 | Pages 60-67
Technical Paper | Nuclear Safety | doi.org/10.13182/NT87-A33897
In-Core Fuel Cycle Transients
Jeffery David Lewins
Nuclear Technology | Volume 76 | Number 1 | January 1987 | Pages 68-83
Technical Paper | Fuel Cycle | doi.org/10.13182/NT87-A33898
The Leaching Behavior of a Glass Waste Form—Part III: The Mathematical Leaching Model
Tsunetaka Banba, Takashi Murakami, Hideo Kimura
Nuclear Technology | Volume 76 | Number 1 | January 1987 | Pages 84-90
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT87-A33899
RETRAN Overview
Lance J. Agee
Nuclear Technology | Volume 76 | Number 1 | January 1987 | Pages 91-97
Fourth International Retran Meeting | Heat Transfer and Fluid Flow | doi.org/10.13182/NT87-A33900
RETRAN Generic Review—A Retrospection
Thomas L. Temple
Nuclear Technology | Volume 76 | Number 1 | January 1987 | Pages 98-104
Fourth International Retran Meeting | Heat Transfer and Fluid Flow | doi.org/10.13182/NT87-A33901
The Development and Application of System Analysis at Kansas Gas and Electric Company
Terry J. Garrett, Steven W. Sorrell
Nuclear Technology | Volume 76 | Number 1 | January 1987 | Pages 105-112
Fourth International Retran Meeting | Heat Transfer and Fluid Flow | doi.org/10.13182/NT87-A33902
Reducing Scram Frequency by Modifying Reactor Setpoints for a Westinghouse Four-Loop Plant
Jason Chao, William H. Layman, Gary Vine
Nuclear Technology | Volume 76 | Number 1 | January 1987 | Pages 113-125
Fourth International Retran Meeting | Heat Transfer and Fluid Flow | doi.org/10.13182/NT87-A33903
Nodalization Study of the Westinghouse Model E Steam Generator Secondary Side
Robert O. Montgomery, Kenneth L. Peddicord, Roger L. Boyer, Charles R. Albury
Nuclear Technology | Volume 76 | Number 1 | January 1987 | Pages 126-136
Fourth International Retran Meeting | Heat Transfer and Fluid Flow | doi.org/10.13182/NT87-A33904
RETRAN Modeling of the Westinghouse Model D Steam Generator
Lance G. Riniker, Kevin B. Ramsden
Nuclear Technology | Volume 76 | Number 1 | January 1987 | Pages 137-142
Fourth International Retran Meeting | Heat Transfer and Fluid Flow | doi.org/10.13182/NT87-A33905
RETRAN Analysis of Susquehanna Steam Electric Station Unit 2 Moisture Separator Drain Tank Level Transient Response
Laurence M. Olson
Nuclear Technology | Volume 76 | Number 1 | January 1987 | Pages 143-165
Fourth International Retran Meeting | Heat Transfer and Fluid Flow | doi.org/10.13182/NT87-A33906
A Comparison of RETRAN-02 and TRAC-PF1 Simulations of a Loss of Off-Site Power Cooldown to Residual Heat Removal Entry Conditions at Calvert Cliffs Nuclear Power Plant
Trevor L. Cook, Steven M. Mirsky
Nuclear Technology | Volume 76 | Number 1 | January 1987 | Pages 166-171
Fourth International Retran Meeting | Heat Transfer and Fluid Flow | doi.org/10.13182/NT87-A33907
Safety Analyses Using RETRAN-02 with Relaxed Trip Setpoints on Combustion Engineering Reactors
Bruce Ching, Chong Chiu, Jason Chao, William H. Layman, Gary Vine
Nuclear Technology | Volume 76 | Number 1 | January 1987 | Pages 172-184
Fourth International Retran Meeting | Heat Transfer and Fluid Flow | doi.org/10.13182/NT87-A33908
Passive Emergency Cooling Systems for Boiling Water Reactors (PECOS-BWR)
Charles W. Forsberg
Nuclear Technology | Volume 76 | Number 1 | January 1987 | Pages 185-192
Technical Note | Fission Reactor | doi.org/10.13182/NT87-A33909
Determination of Isotopic Ratios from Fuel Burnup
John C. Lee, Sin Tao Hsue
Nuclear Technology | Volume 76 | Number 2 | February 1987 | Pages 203-208
Technical Paper | Fuel Cycle | doi.org/10.13182/NT87-A33874
ELOCA-A: A Code for Radial and Axial Behavior of CANDU Fuel Elements at High Temperatures
Mukesh Tayal, Ed Mischkot, Harve E. Sills, A. W. L. Segel
Nuclear Technology | Volume 76 | Number 2 | February 1987 | Pages 209-220
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT87-A33875
Properties of Bentonite Clay as Buffer Material in High-Level Waste Geological Disposal. Part I: Chemical Species Contained in Bentonite
Masanori Takahashi, Masayuki Muroi, Atsuyuki Inoue, Masahiro Aoki, Makoto Takizawa, Kenkichi Ishigure, Norihiko Fujita
Nuclear Technology | Volume 76 | Number 2 | February 1987 | Pages 221-228
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT87-A33876
An Experimental Correlation of Cross-Flow Pressure Drop for Triangular Array Wire-Wrapped Rod Assemblies
Kune Yull Suh, Neil E. Todreas
Nuclear Technology | Volume 76 | Number 2 | February 1987 | Pages 229-240
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT87-A33877
In Vivo Measurement of Organ Mercury by Prompt Gamma Activation Analysis Using a Mobile Nuclear Reactor
Pao-Shu Chang, Yau-Hui ho, Chien Chung, Liq-Ji Yuan, Pao-Shan Weng
Nuclear Technology | Volume 76 | Number 2 | February 1987 | Pages 241-247
Technical Paper | Analyse | doi.org/10.13182/NT87-A33878
Simulation of the Transient Response of Ionization Chambers to Bias Voltage Perturbations
Tunc Aldemir, Steven A. Arndt, Don. W. Miller
Nuclear Technology | Volume 76 | Number 2 | February 1987 | Pages 248-259
Technical Paper | Technique | doi.org/10.13182/NT87-A33879
The Formation of Surface Layers and Reaction Products in the Leaching of Defense Borosilicate Nuclear Waste Glass
Alan B. Harker, John F. Flintoff
Nuclear Technology | Volume 76 | Number 2 | February 1987 | Pages 263-275
Performance of Borosilicate Glass High-Level Waste Forms in Disposal Systems | Radioactive Waste Management | doi.org/10.13182/NT87-A33880
A Guillotine Tube Rupture Modeling Technique Using RETRAN-02
Peter J. Jensen, James F. Lang, Jason Chao
Nuclear Technology | Volume 76 | Number 2 | February 1987 | Pages 279-289
Fourth International Retran Meeting | Heat Transfer and Fluid Flow | doi.org/10.13182/NT87-A33881
A Parametric Study of an Anticipated Transient Without Scram in a Westinghouse Four-Loop Plant
Peter J. Jensen, Kent D. Richert, Jason Chao
Nuclear Technology | Volume 76 | Number 2 | February 1987 | Pages 290-302
Fourth International Retran Meeting | Heat Transfer and Fluid Flow | doi.org/10.13182/NT87-A33882
Moderator Feedback Effects in Two-Dimensional Nodal Methods for Pressurized Water Reactor Analysis
Thomas J. Downar
Nuclear Technology | Volume 76 | Number 2 | February 1987 | Pages 303-307
Technical Note | Fission Reactor | doi.org/10.13182/NT87-A33883
Finite Element Analysis of Boiling Water Reactor Fuel Channel Bulge and Bow
David P. Chan, David L. Larkin
Nuclear Technology | Volume 76 | Number 3 | March 1987 | Pages 319-324
Technical Paper | Fission Reactor | doi.org/10.13182/NT87-A33917
An Analysis of Initiating and Transition Phases for an Unprotected Loss-of-Flow Accident in an Axially Heterogeneous Fast Breeder Reactor Core
Kazuo Azekura, Kikuo Umegaki, Kotaro Inoue, Sang K. Rhow, James E. McElroy, Dennis M. Switick
Nuclear Technology | Volume 76 | Number 3 | March 1987 | Pages 325-336
Technical Paper | Fission Reactor | doi.org/10.13182/NT87-A33918
Liquid-Metal Fast Breeder Reactor Intermediate Heat Exchanger Transient Modeling for Faster Than Real-Time Analysis
Constantine P. Tzanos
Nuclear Technology | Volume 76 | Number 3 | March 1987 | Pages 337-351
Technical Paper | Fission Reactor | doi.org/10.13182/NT87-A33919
Development of a Postscram Analyzer for Boiling Water Reactors
Bill K.-H. Sun, Robert Colley, David G. Cain, John W. Hallam
Nuclear Technology | Volume 76 | Number 3 | March 1987 | Pages 352-359
Technical Paper | Fission Reactor | doi.org/10.13182/NT87-A33920
Experimental Studies of the Air Coolability of TRIGA Reactors Following a Loss-of-Coolant Accident
Mohamed S. El-Genk, Sung-Ho Kim, Galal M. Zaki, Jeffrey S. Philbin, James F. Schulze, Fabian C. Foushée
Nuclear Technology | Volume 76 | Number 3 | March 1987 | Pages 360-369
Technical Paper | Nuclear Safety | doi.org/10.13182/NT87-A33921
A Probabilistic Analysis Method to Evaluate the Effect of Human Factors on Plant Safety
Hiroshi Ujita
Nuclear Technology | Volume 76 | Number 3 | March 1987 | Pages 370-376
Technical Paper | Nuclear Safety | doi.org/10.13182/NT87-A33922
A Comparison of Measured Radionuclide Release Rates from Three Mile Island Unit-2 Core Debris for Different Oxygen Chemical Potentials
V. F. Baston, K. J. Hofstetter, Robert F. Ryan
Nuclear Technology | Volume 76 | Number 3 | March 1987 | Pages 377-389
Technical Paper | Nuclear Safety | doi.org/10.13182/NT87-A33923
CANDU Pressurized Heavy Water Reactor Thorium-233U Oxide Fuel Evaluation Based on Optimal Fuel Management
Hugues W. Bonin
Nuclear Technology | Volume 76 | Number 3 | March 1987 | Pages 390-399
Technical Paper | Fuel Cycle | doi.org/10.13182/NT87-A33924
Gamma Radiation Effects on Time-Dependent Iodine Partitioning
Paul W. Marshall, Jeffrey B. Lutz, James L. Kelly
Nuclear Technology | Volume 76 | Number 3 | March 1987 | Pages 400-407
Technical Paper | Chemical Processing | doi.org/10.13182/NT87-A33925
Radiography Experiments at Argonne National Laboratory
Wade J. Richards, Howard A. Larson
Nuclear Technology | Volume 76 | Number 3 | March 1987 | Pages 408-419
Technical Paper | Material | doi.org/10.13182/NT87-A33926
Total Control Worth by Inspection
Charles R. Marotta
Nuclear Technology | Volume 76 | Number 3 | March 1987 | Pages 420-422
Technical Note | Fission Reactor | doi.org/10.13182/NT87-A33927
