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The busyness of the nuclear fuel supply chain
Ken Petersenpresident@ans.org
With all that is happening in the industry these days, the nuclear fuel supply chain is still a hot topic. The Russian assault in Ukraine continues to upend the “where” and “how” of attaining nuclear fuel—and it has also motivated U.S. legislators to act.
Two years into the Russian war with Ukraine, things are different. The Inflation Reduction Act was passed in 2022, authorizing $700 million in funding to support production of high-assay low-enriched uranium in the United States. Meanwhile, the Department of Energy this January issued a $500 million request for proposals to stimulate new HALEU production. The Emergency National Security Supplemental Appropriations Act of 2024 includes $2.7 billion in funding for new uranium enrichment production. This funding was diverted from the Civil Nuclear Credits program and will only be released if there is a ban on importing Russian uranium into the United States—which could happen by the time this column is published, as legislation that bans Russian uranium has passed the House as of this writing and is headed for the Senate. Also being considered is legislation that would sanction Russian uranium. Alternatively, the Biden-Harris administration may choose to ban Russian uranium without legislation in order to obtain access to the $2.7 billion in funding.
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NUFREQ/SLIP: An Improved Digital Computer Model for Predicting Nuclear Thermally Induced Flow Instabilities
Samir M. Sami, C. H. Le
Nuclear Technology | Volume 77 | Number 1 | April 1987 | Pages 7-17
Technical Paper | Fission Reactor | doi.org/10.13182/NT87-A33947
Fission Product Tellurium Release Behavior Under Severe Light Water Reactor Accident Conditions
Jack L. Collins, Morris F. Osborne, R. A. Lorenz
Nuclear Technology | Volume 77 | Number 1 | April 1987 | Pages 18-31
Technical Paper | Fission Reactor | doi.org/10.13182/NT87-A33948
SAFER03 and TRAC-BD1 Analyses of a ROSA-III Large-Break Experiment on a Boiling Water Reactor
Seihiro Itoya, Masami Kato, Nobuaki Abe, Hideo Nagasaka
Nuclear Technology | Volume 77 | Number 1 | April 1987 | Pages 32-45
Technical Paper | Nuclear Safety | doi.org/10.13182/NT87-A33949
Removal of Suspended Alumina Particles from Heavy Water by Electroadsorption on Fibrous Carbon Electrodes
Haim Tobias, Efraim Taragan, Yoram Oren, Abraham Soffer
Nuclear Technology | Volume 77 | Number 1 | April 1987 | Pages 46-49
Technical Paper | Chemical Processing | doi.org/10.13182/NT87-A33950
Cracking and Relocation of Mixed-Oxide Fast-Reactor Fuel
Timothy S. Roth, A. Biancheria
Nuclear Technology | Volume 77 | Number 1 | April 1987 | Pages 50-59
Technical Paper | Material | doi.org/10.13182/NT87-A33951
Exposure Buildup Factors of High-Energy Gamma Rays for Water, Concrete, Iron, and Lead
Hideo Hirayama
Nuclear Technology | Volume 77 | Number 1 | April 1987 | Pages 60-67
Technical Paper | Radioisotopes and Isotope Separation | doi.org/10.13182/NT87-A33952
Coal Analysis with Gamma Rays from Capture of 252Cf Neutrons—Experimental Equipment Designs and Results
Dick Duffey, Peter F. Wiggins
Nuclear Technology | Volume 77 | Number 1 | April 1987 | Pages 68-81
Technical Paper | Radioisotopes and Isotope Separation | doi.org/10.13182/NT87-A33953
A Test of Some Condensation Models in the Presence of a Noncondensable Gas Against the ECOTRA Experiment
Philippe J. Vernier, Philippe Solignac
Nuclear Technology | Volume 77 | Number 1 | April 1987 | Pages 82-91
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT87-A33954
A Miniature Spark Counter for Public Communication and Education
Cheng-Hsin Mao, Pao-Shan Weng
Nuclear Technology | Volume 77 | Number 1 | April 1987 | Pages 92-96
Technical Paper | Analyse | doi.org/10.13182/NT87-A33955
A Monte Carlo Model for On-Line Neutron Capture Prompt Gamma-Ray Analysis of Coal in Transmission Geometry
Y. L. Yuan, R. P. Gardner, K. Verghese
Nuclear Technology | Volume 77 | Number 1 | April 1987 | Pages 97-109
Technical Paper | Analyse | doi.org/10.13182/NT87-A33956
Fission Gas Bubbles in Uranium-Aluminide Fuels
Gerard L. Hofman
Nuclear Technology | Volume 77 | Number 1 | April 1987 | Pages 110-115
Technical Note | Nuclear Fuel | doi.org/10.13182/NT87-A33957
Transport of Pollutants: Summary Review of Physical Dispersion Models
George Yadigaroglu, Hector A. Munera
Nuclear Technology | Volume 77 | Number 2 | May 1987 | Pages 125-149
Critical Review | Nuclear Safety | doi.org/10.13182/NT87-A33979
The Importance of Fission Production/Aerosol Interactions in Reactor Accident Calculations
Roger D. Spence, Anthony L. Wright
Nuclear Technology | Volume 77 | Number 2 | May 1987 | Pages 150-160
Technical Paper | Nuclear Safety | doi.org/10.13182/NT87-A33980
The Absorption of Gaseous Iodine by Water Droplets
Michael F. Albert, Jack S. Watson, Robert P. Wichner
Nuclear Technology | Volume 77 | Number 2 | May 1987 | Pages 161-174
Technical Paper | Nuclear Safety | doi.org/10.13182/NT87-A33981
Development of Thermal Plutonium Recycling
Horst Roepenack, Fritz U. Schlemmer, Gerhard J. Schlosser
Nuclear Technology | Volume 77 | Number 2 | May 1987 | Pages 175-186
Technical Paper | Fuel Cycle | doi.org/10.13182/NT87-A33982
Droplet Diameters and Axial Mixing in Pulse Columns in the Comparison of the Aqueous to Organic Continuous Mode of Operation
Hiromichi Fumoto, Erich Zimmer, Erich R. Merz, Atsuyuki Suzuki, Ryohei Kiyose
Nuclear Technology | Volume 77 | Number 2 | May 1987 | Pages 187-193
Technical Paper | Chemical Processing | doi.org/10.13182/NT87-A33983
Modeling Nuclear Decontamination Processes
Alexander P. Murray
Nuclear Technology | Volume 77 | Number 2 | May 1987 | Pages 194-209
Technical Paper | Chemical Processing | doi.org/10.13182/NT87-A33984
Development and Operation of a Unique Conversion/Solidification Process for Highly Radioactive and Fissile Uranium
C. Phillip McGinnis, Emory D. Collins, Reginald Hall, J. Keith Johnson, Alan M. Krichinsky, Bradley D. Patton, Joel T. Shor, Raymond J. Vedder
Nuclear Technology | Volume 77 | Number 2 | May 1987 | Pages 210-219
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT77-210
Boron-10 Concentration Measurements Using the Solid-State Nuclear Track Detector CR-39 and Automatic Image Analysis
Thomas E. Blue, T. Courtney Roberts, Rolf F. Barth, Joseph W. Talnagi, Fazlul Alam
Nuclear Technology | Volume 77 | Number 2 | May 1987 | Pages 220-226
Technical Paper | Radioisotopes and Isotope Separation | doi.org/10.13182/NT87-A33986
Monte Carlo Departure from Nucleate Boiling Ratio Limit Development Using Few-Channel Thermal-Hydraulics Code Models
Ross C. Anderson, Kerry L. Basehore
Nuclear Technology | Volume 77 | Number 2 | May 1987 | Pages 227-230
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT87-A33987
A New Approach for Predicting Steam Volume Fraction in Transient Flow Boiling
Samir M. Sami, M. Kraitem
Nuclear Technology | Volume 77 | Number 3 | June 1987 | Pages 237-246
Technical Paper | Fission Reactor | doi.org/10.13182/NT87-A33963
Development of a Compact Digital Reactivity Meter and a Reactor Physics Data Processor
Yoichiro Shimazu, Yuzo Nakano, Yoshihisa Tahara, Tadayoshi Okayama
Nuclear Technology | Volume 77 | Number 3 | June 1987 | Pages 247-254
Technical Paper | Fission Reactor | doi.org/10.13182/NT87-A33964
Reactivity Analysis Model Based on Finite Difference Method for Three-Dimensional Fast Breeder Reactor Core Deformation
Kazuo Azekura
Nuclear Technology | Volume 77 | Number 3 | June 1987 | Pages 255-262
Technical Paper | Fission Reactor | doi.org/10.13182/NT87-A33965
Liquid-Metal Fast Breeder Reactor Core Transient Modeling for Faster Than Real-Time Analysis
Constantine P. Tzanos
Nuclear Technology | Volume 77 | Number 3 | June 1987 | Pages 263-278
Technical Paper | Fission Reactor | doi.org/10.13182/NT87-A33966
Measurements and Evaluations of Neutron Dose and Spectra at the Reactor Top of the Liquid-Metal Fast Breeder Type Reactor, JOYO
Toshiso Kosako, Junpei Matsumoto, Akira Sekiguchi+, Nobuo Ohtani, Soju Suzuki, Shinso Takeda, Osamu Sato
Nuclear Technology | Volume 77 | Number 3 | June 1987 | Pages 279-294
Technical Paper | Nuclear Safety | doi.org/10.13182/NT87-A33967
Conversion of Deuterium Gas to Heavy Water by Catalytic Isotopic Exchange Using Wetproof Catalyst
Robert J. Quaiattini, Michael P. McGauley, Deborah L. Burns, Paul R. Tichler
Nuclear Technology | Volume 77 | Number 3 | June 1987 | Pages 295-298
Technical Paper | Chemical Processing | doi.org/10.13182/NT87-A33968
A Semiempirical Equation for Estimating Thorium Nitrate Extraction by DHPSO from Nitric Acid Solution
Jiin-Shiung Horng, Wen-Shou Chuang, Ying-Chu Hoh
Nuclear Technology | Volume 77 | Number 3 | June 1987 | Pages 299-302
Technical Paper | Chemical Processing | doi.org/10.13182/NT87-A33969
Release of Iodine from Defective Fuel Elements Following Reactor Shut-down
Brent J. Lewis, Dugald B. Duncan, Colin R. Phillips
Nuclear Technology | Volume 77 | Number 3 | June 1987 | Pages 303-312
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT87-A33970
Water Corrosion and Release Mechanism of Cement Matrix Incorporating Simulated Medium-Level Waste
Edmondo Zamorani
Nuclear Technology | Volume 77 | Number 3 | June 1987 | Pages 313-319
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT87-A33971
The Relationship Between Gap Inventories of Stable Xenon, 137Cs, and 129I in Used CANDU Fuel
Simcha Stroes-Gascoyne, Lawrence H. Johnson, Dennis M. Sellinger
Nuclear Technology | Volume 77 | Number 3 | June 1987 | Pages 320-330
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT87-A33972
On the Development of Turbulent Flow in Wall Subchannels of a Rod Bundle
Klaus Rehme
Nuclear Technology | Volume 77 | Number 3 | June 1987 | Pages 331-342
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT87-A33973
A Historical Perspective on Seismic Risk Assessment and Bayesian Updating
Manuel González-Cuesta, David Okrent
Nuclear Technology | Volume 77 | Number 3 | June 1987 | Pages 343-348
Technical Note | Nuclear Safety | doi.org/10.13182/NT87-A33974
Energy Dissipation in Nuclear Ceramic Materials
Gerhard Karsten
Nuclear Technology | Volume 77 | Number 3 | June 1987 | Pages 349-353
Technical Note | Material | doi.org/10.13182/NT87-A33975
