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Glass strategy: Hanford’s enhanced waste glass program
The mission of the Department of Energy’s Office of River Protection (ORP) is to complete the safe cleanup of waste resulting from decades of nuclear weapons development. One of the most technologically challenging responsibilities is the safe disposition of approximately 56 million gallons of radioactive waste historically stored in 177 tanks at the Hanford Site in Washington state.
ORP has a clear incentive to reduce the overall mission duration and cost. One pathway is to develop and deploy innovative technical solutions that can advance baseline flow sheets toward higher efficiency operations while reducing identified risks without compromising safety. Vitrification is the baseline process that will convert both high-level and low-level radioactive waste at Hanford into a stable glass waste form for long-term storage and disposal.
Although vitrification is a mature technology, there are key areas where technology can further reduce operational risks, advance baseline processes to maximize waste throughput, and provide the underpinning to enhance operational flexibility; all steps in reducing mission duration and cost.
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RETRAN Overview
Lance J. Agee
Nuclear Technology | Volume 70 | Number 1 | July 1985 | Pages 7-16
Overview | Third International Retran Meeting / Heat Transfer and Fluid Flow | doi.org/10.13182/NT85-A33658
RETRAN Applications in Pressurized Thermal Shock Analysis of Turkey Point Units 3 and 4
Jorge Arpa, Alan S. Fatemi, S. K. Mathavan
Nuclear Technology | Volume 70 | Number 1 | July 1985 | Pages 17-25
Technical Paper | Third International Retran Meeting / Heat Transfer and Fluid Flow | doi.org/10.13182/NT85-A33659
RETRAN Analysis of the Hanford N Reactor for a Loss of Feedwater
Bruce E. Schmitt
Nuclear Technology | Volume 70 | Number 1 | July 1985 | Pages 26-29
Technical Paper | Third International Retran Meeting / Heat Transfer and Fluid Flow | doi.org/10.13182/NT85-A33660
Semi-Implicit Solution Methods for the RETRAN Model Equations
E. D. Hughes, K. R. Katsma, M. P. Paulsen
Nuclear Technology | Volume 70 | Number 1 | July 1985 | Pages 30-41
Technical Paper | Third International Retran Meeting / Heat Transfer and Fluid Flow | doi.org/10.13182/NT85-A33661
Engineering Analysis Activities in Support of Susquehanna Unit 1 Startup Testing and Cycle 1 Operations
G. D. Miller, J. G. Refling, A. J. Roscioli, S. A. Somma, C. A. Kukielka, L. M. Olson
Nuclear Technology | Volume 70 | Number 1 | July 1985 | Pages 42-52
Technical Paper | Third International Retran Meeting / Heat Transfer and Fluid Flow | doi.org/10.13182/NT85-A33662
RETRAN Analysis of Boiling Water Reactor Accidents
Ernest V. Moore, S. F. Deng, K. K. Chitkara, B. B. Chu
Nuclear Technology | Volume 70 | Number 1 | July 1985 | Pages 53-63
Technical Paper | Third International Retran Meeting / Heat Transfer and Fluid Flow | doi.org/10.13182/NT85-A33663
Analysis of Hatch-2 Dual Recirculation Pump Trip Startup Test
Adel Alapour, Robert A. Hommerson
Nuclear Technology | Volume 70 | Number 1 | July 1985 | Pages 64-73
Technical Paper | Third International Retran Meeting / Heat Transfer and Fluid Flow | doi.org/10.13182/NT85-A33664
An Investigation of Decreasing Reactor Coolant Inventory as a Mechanism to Reduce Power During a Boiling Water Reactor Anticipated Transient Without Scram
Craig E. Peterson, V. K. (Bindi) Chexal, William H. Layman, Richard D. Hentzen, Garry C. Gose
Nuclear Technology | Volume 70 | Number 1 | July 1985 | Pages 74-83
Technical Paper | Third International Retran Meeting / Heat Transfer and Fluid Flow | doi.org/10.13182/NT85-A33665
RETRAN-02 Analysis of Loss-of-Fluid Test Experiments L9-3 and L9-4
Richard F. Farman, Charles E. Hendrix, Jason Chao
Nuclear Technology | Volume 70 | Number 1 | July 1985 | Pages 84-93
Technical Paper | Third International Retran Meeting / Heat Transfer and Fluid Flow | doi.org/10.13182/NT85-A33666
RETRAN Analysis of the San Onofre Unit 2 Turbine Trip from 100% Power
Yine-Ping Ting
Nuclear Technology | Volume 70 | Number 1 | July 1985 | Pages 94-103
Technical Paper | Third International Retran Meeting / Heat Transfer and Fluid Flow | doi.org/10.13182/NT85-A33667
Analysis of a Hot-Leg Small Break Loss-of-Coolant Accident in a Three-Loop Westinghouse Pressurized Water Reactor Plant
Craig E. Peterson, V. K. (Bindi) Chexal, Talmage B. Clements
Nuclear Technology | Volume 70 | Number 1 | July 1985 | Pages 104-110
Technical Paper | Third International Retran Meeting / Heat Transfer and Fluid Flow | doi.org/10.13182/NT85-A33668
Comparison of RETRAN and RELAP5 Models to Oyster Creek Loss of Feedwater Transient
M. A. Alammar
Nuclear Technology | Volume 70 | Number 1 | July 1985 | Pages 111-119
Technical Paper | Third International Retran Meeting / Heat Transfer and Fluid Flow | doi.org/10.13182/NT85-A33669
RETRAN-02 Comparison of Natural Circulation Flow Rates at Babcock & Wilcox 177-FA Plants
Norman T. Simms
Nuclear Technology | Volume 70 | Number 1 | July 1985 | Pages 120-123
Technical Paper | Third International Retran Meeting / Heat Transfer and Fluid Flow | doi.org/10.13182/NT85-A33670
Analytical Investigation of Postaccident Containment Atmospheric Stratification
Vincent P. Manno, Michael W. Golay
Nuclear Technology | Volume 70 | Number 1 | July 1985 | Pages 124-132
Technical Paper | Third International Retran Meeting / Nuclear Safety | doi.org/10.13182/NT85-A33671
Leaching of Plutonium from a Radioactive Waste Glass by Eight Groundwaters from the Western United States
Terry F. Rees, Jess M. Cleveland, Kenneth L. Nash
Nuclear Technology | Volume 70 | Number 1 | July 1985 | Pages 133-140
Technical Paper | Third International Retran Meeting / Radioactive Waste Management | doi.org/10.13182/NT85-A33672
Investigations on the Improvement of the Iodine Filtration Concept of Boiling Water Reactors
H. Deuber
Nuclear Technology | Volume 70 | Number 2 | August 1985 | Pages 149-152
Technical Paper | Fission Reactor | doi.org/10.13182/NT85-A33637
Investigations on the Testing of Iodine Filters by Different Methods
H. Deuber, K. Gerlach
Nuclear Technology | Volume 70 | Number 2 | August 1985 | Pages 153-157
Technical Paper | Fission Reactor | doi.org/10.13182/NT85-A33638
The Filtered Venting System Under Construction at Barsebäck
Åke H. Persson
Nuclear Technology | Volume 70 | Number 2 | August 1985 | Pages 158-160
Technical Paper | Fission Reactor | doi.org/10.13182/NT85-A33639
Investigations on the Aging of Activated Carbons in the Exhaust Air of a Pressurized Water Reactor
H. Deuber, K. Gerlach, R. Kaempffer
Nuclear Technology | Volume 70 | Number 2 | August 1985 | Pages 161-166
Technical Paper | Fission Reactor | doi.org/10.13182/NT85-A33640
Installation of Automatic Control at Experimental Breeder Reactor II
Howard A. Larson, William F. Booty, Donald R. Chick, Lynn J. Christensen, Robert J. Forrester, J. W. Sielinsky
Nuclear Technology | Volume 70 | Number 2 | August 1985 | Pages 167-179
Technical Paper | Fission Reactor | doi.org/10.13182/NT85-A33641
Control Rod Worth and Related Nuclear Characteristics of an Axially Heterogeneous Liquid-Metal Fast Breeder Reactor Core
Katsuyuki Kawashima, Kotaro Inoue, Kunikazu Kaneto, Tatsutoshi Inagaki
Nuclear Technology | Volume 70 | Number 2 | August 1985 | Pages 180-188
Technical Paper | Fission Reactor | doi.org/10.13182/NT85-A33642
Recirculation Pump Discharge Line Break Tests at ROSA-III for a Boiling Water Reactor
Mitsuhiro Suzuki, Kanji Tasaka, Yoshinari Anoda, Hiroshige Kumamaru, Hideo Nakamura, Masayoshi Shiba
Nuclear Technology | Volume 70 | Number 2 | August 1985 | Pages 189-203
Technical Paper | Nuclear Safety | doi.org/10.13182/NT85-A33643
Reducing the Consequences of Reactor Accidents with a Green Belt
V. K. Gupta, Ramesh K. Kapoor
Nuclear Technology | Volume 70 | Number 2 | August 1985 | Pages 204-214
Technical Paper | Nuclear Safety | doi.org/10.13182/NT85-A33644
Fabrication and Mechanical Properties of Oxide Dispersion Strengthening Ferritic Alloy Canning Tubes for Fast Reactor Fuel Pins
J.-J. Huet, L. Coheur, A. De Bremaecker, L. De Wilde, J. Gedopt, W. Hendrix, W. Vandermeulen
Nuclear Technology | Volume 70 | Number 2 | August 1985 | Pages 215-219
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT85-A33645
Experimental Investigation of Coolability Degradation by Fission Gas Release into Flowing Sodium in a Fuel Pin Bundle
Kazuo Haga, Yoshihiro Kikuchi
Nuclear Technology | Volume 70 | Number 2 | August 1985 | Pages 220-234
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT85-A33646
Thermal Conductivity of Simulated Radioactive Waste Glass
Seichi Sato, Hirotaka Furuya, Yuji Nishino, Masayasu Sugisaki
Nuclear Technology | Volume 70 | Number 2 | August 1985 | Pages 235-242
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT85-A33647
The Leaching Behavior of a Glass Waste Form —Part II: The Leaching Mechanisms
Tsunetaka Banba, Takashi Murakami
Nuclear Technology | Volume 70 | Number 2 | August 1985 | Pages 243-248
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT85-A33648
Electrolytic Decontamination of Surface-Contaminated Metal by Alternating Electrolysis Using Square-Wave Current in a Neutral Salt Electrolyte
Tatsuo Izumida, Koji Kato, Fumio Kawamura, Hideo Yusa
Nuclear Technology | Volume 70 | Number 2 | August 1985 | Pages 249-253
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT85-A33649
A Consolidation Process for Spent Burnable Poison Rod Assemblies
Yoshimasa Yamamoto, Yukihiko Komatsu, Minoru Harada
Nuclear Technology | Volume 70 | Number 2 | August 1985 | Pages 254-260
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT85-A33650
A Laboratory Study on Radionuclide Migration in Single Natural Granitic Fissures
Trygve E. Eriksen
Nuclear Technology | Volume 70 | Number 2 | August 1985 | Pages 261-267
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT85-A33651
Postirradiation Dimensional Stability and Fission Product Behavior of Deliberately Defected UO2 Fuel at 200 and 400°C
Ian J. Hastings, David R. McCracken, Elio Mizzan, Roger D. Barrand, John R. Kelm, Ken E. Nash, J. Novak
Nuclear Technology | Volume 70 | Number 2 | August 1985 | Pages 268-273
Technical Paper | Material | doi.org/10.13182/NT85-A33652
Initial Radiations from Tactical Nuclear Weapons
William E. Loewe
Nuclear Technology | Volume 70 | Number 2 | August 1985 | Pages 274-284
Technical Paper | Radiation Biology and Environment | doi.org/10.13182/NT85-A33653
The Effect of Re-Solution Models on Fission Gas Disposition in Irradiated UO2 Fuel
A. R. Wazzan, A. Villalobos, D. Okrent
Nuclear Technology | Volume 70 | Number 2 | August 1985 | Pages 285-289
Technical Note | Fission Reactor | doi.org/10.13182/NT85-A33654
Measurement of the Iodine Partition Coefficient
Max Furrer, Robin C. Cripps, Reinhard Gubler
Nuclear Technology | Volume 70 | Number 2 | August 1985 | Pages 290-293
Technical Note | Nuclear Safety | doi.org/10.13182/NT85-A33655
Authors
Hiroshi Fukui, Kaichiro Mishima, Seiji Shiroya, Masatoshi Hayashi, Keiji Kanda, Yasuhide Senda, Yasuhide Senda, Seiji Shiroya, Masatoshi Hayashi, Keiji Kanda, N. Abe, M. Kato, H. Nagasaka, Jiro Wakabayashi, Shin-ichi Tashima, Akio Gofuku, Alex Galperin, Meir Segev, Anatoly Goldfeld, Yonathan Karni, Y. F. Chang, P. C. Watson, M. D. Langan, P. Sermer, Robert P. Wichner, Roger D. Spence, John F. Geldard, Leigh Phillips, Adolph L. Beyerlein, Karl Richter, Jean Gueugnon, Gerard Kramer, Carlo Sari, Paul Werner, Roberto Caponetti, John R. Krsul, Robert A. Washburn, Bernard L. Cohen
Nuclear Technology | Volume 70 | Number 3 | September 1985 | Pages 295-300
Department | doi.org/10.13182/NT85-A15957
Effect of Reducing Fuel Enrichment on the Void Reactivity — Part I: Experimental Study
Hiroshi Fukui, Kaichiro Mishima, Seiji Shiroya, Masatoshi Hayashi, Keiji Kanda, Yasuhide Senda
Nuclear Technology | Volume 70 | Number 3 | September 1985 | Pages 301-317
Technical Paper | Fission Reactor | doi.org/10.13182/NT85-A15958
Effect of Reducing Fuel Enrichment on the Void Reactivity — Part II: Analytical Study
Yasuhide Senda, Seiji Shiroya, Masatoshi Hayashi, Keiji Kanda
Nuclear Technology | Volume 70 | Number 3 | September 1985 | Pages 318-334
Technical Paper | Fission Reactor | doi.org/10.13182/NT85-A15959
Analysis of Upper Plenum Level Oscillatory Phenomena by TRAC-BD1
N. Abe, M. Kato, H. Nagasaka
Nuclear Technology | Volume 70 | Number 3 | September 1985 | Pages 335-342
Technical Paper | Fission Reactor | doi.org/10.13182/NT85-A15960
Two Identification Techniques for Disturbance Diagnosis in Nuclear Power Plants
Jiro Wakabayashi, Shin-Ichi Tashima, Akio Gofuku
Nuclear Technology | Volume 70 | Number 3 | September 1985 | Pages 343-353
Technical Paper | Fission Reactor | doi.org/10.13182/NT85-A15961
BGUCORE — A Computational System for Neutronic Analysis of a Pressurized Water Reactor Core
Alex Galperin, Meir Segev, Anatoly Goldfeld, Yonathan Karni
Nuclear Technology | Volume 70 | Number 3 | September 1985 | Pages 354-363
Technical Paper | Fission Reactor | doi.org/10.13182/NT85-A15962
Bruce Nuclear Generating Station B Rapid Cooldown Test and Validation of Simulation Model
Y. F. Chang, P. C. Watson, M. D. Langan, P. Sermer
Nuclear Technology | Volume 70 | Number 3 | September 1985 | Pages 364-375
Technical Paper | Nuclear Safety | doi.org/10.13182/NT85-A15963
A Chemical Equilibrium Estimate of the Aerosols Produced in an Overheated Light Water Reactor Core
Robert P. Wichner, Roger D. Spence
Nuclear Technology | Volume 70 | Number 3 | September 1985 | Pages 376-393
Technical Paper | Nuclear Safety | doi.org/10.13182/NT85-A15964
Correlation Functions for the Distribution Coefficients of U(IV) and Pu(III) Ions Between Aqueous Nitric Acid and 30% TBP in an Aliphatic Diluent
John F. Geldard, Leigh Phillips, Adolph L. Beyerlein
Nuclear Technology | Volume 70 | Number 3 | September 1985 | Pages 394-400
Technical Paper | Chemical Processing | doi.org/10.13182/NT85-A15965
Direct Pressing: A New Method of Fabricating MX Fuel Pellets
Karl Richter, Jean Gueugnon, Gerard Kramer, Carlo Sari, Paul Werner
Nuclear Technology | Volume 70 | Number 3 | September 1985 | Pages 401-407
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT85-A15966
Sodium Cleaning Procedures for PEC Prototype Mechanisms
Roberto Caponetti
Nuclear Technology | Volume 70 | Number 3 | September 1985 | Pages 408-423
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT85-A15967
Removal of Radioactive Sodium from Experimental Breeder Reactor-II Components and Conversion to a Disposable Solid Waste: Alcohol Recovery
John R. Krsul, Robert A. Washburn
Nuclear Technology | Volume 70 | Number 3 | September 1985 | Pages 424-432
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT85-A15968
Critique of the National Academy of Sciences Study of the Isolation System for Geologic Disposal of Radioactive Waste
Bernard L. Cohen
Nuclear Technology | Volume 70 | Number 3 | September 1985 | Pages 433-440
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT85-A15969
