Evaluating the Collective Radiation Dose to Workers from the U.S. Once-Through Nuclear Fuel Cycle

2014 ◽  
Vol 185 (2) ◽  
pp. 192-207 ◽  
Author(s):  
Steven L. Krahn ◽  
Allen G. Croff ◽  
Bethany L. Smith ◽  
James H. Clarke ◽  
Andrew G. Sowder ◽  
...  
Keyword(s):  
Radiation Dose ◽  
Nuclear Fuel ◽  
Fuel Cycle ◽  
Nuclear Fuel Cycle ◽  
The U.S

Overview of the U.S. Department of Energy Advanced Waste Forms Development

2018 ◽  
Author(s):  
Kimberly Gray ◽  
John Vienna ◽  
Patricia Paviet
Keyword(s):  
Nuclear Fuel ◽  
Fuel Cycle ◽  
Nuclear Fuel Cycle ◽  
The United States ◽  
Department Of Energy ◽  
High Level Waste ◽  
Fuel Cycles ◽  
Waste Forms ◽  
The U.S

In order to maintain the U.S. domestic nuclear capability, its scientific technical leadership, and to keep our options open for closing the nuclear fuel cycle, the Department of Energy, Office of Nuclear Energy (DOE-NE) invests in various R&D programs to identify and resolve technical challenges related to the sustainability of the nuclear fuel cycle. Sustainable fuel cycles are those that improve uranium resource utilization, maximize energy generation, minimize waste generation, improve safety and limit proliferation risk. DOE-NE chartered a Study on the evaluation and screening of nuclear fuel cycle options, to provide information about the potential benefits and challenges of nuclear fuel cycle options and to identify a relatively small number of promising fuel cycle options with the potential for achieving substantial improvements compared to the current nuclear fuel cycle in the United States. The identification of these promising fuel cycles helps in focusing and strengthening the U.S. R&D investment needed to support the set of promising fuel cycle system options and nuclear material management approaches. DOE-NE is developing and evaluating advanced technologies for the immobilization of waste issued from aqueous and electrochemical recycling activities including off-gas treatment and advanced fuel fabrication. The long-term scope of waste form development and performance activities includes not only the development, demonstration, and technical maturation of advanced waste management concepts but also the development and parameterization of defensible models to predict the long-term performance of waste forms in geologic disposal. Along with the finding of the Evaluation and Screening Study will be presented the major research efforts that are underway for the development and demonstration of waste forms and processes including glass ceramic for high-level waste raffinate, alloy waste forms and glass ceramics composites for HLW from the electrochemical processing of fast reactor fuels, and high durability waste forms for radioiodine.

scholarly journals Integration of the Back-end of the Nuclear Fuel Cycle: An Overview

MRS Advances ◽  
2020 ◽  
Vol 5 (5-6) ◽  
pp. 253-264
Author(s):  
François Diaz-Maurin ◽  
Rodney C. Ewing
Keyword(s):  
Nuclear Fuel ◽  
Fuel Cycle ◽  
Nuclear Fuel Cycle ◽  
The United States ◽  
Nuclear Waste Management ◽  
Policy Choices ◽  
Interim Storage ◽  
The Impact ◽  
Fully Coupled ◽  
The U.S

ABSTRACTRecent efforts have been made toward the integration of the back-end of the nuclear fuel cycle in the United States. The back-end integration seeks to address several management challenges: 1) current storage practices are not optimized for transport and disposal; 2) the impact of interim storage on the disposal strategy needs to be evaluated; and 3) the back-end is affected by—and affects—nuclear fuel cycle and energy policy choices. The back-end integration accounts for the various processes of nuclear waste management—onsite storage, consolidated storage, transport and geological disposal. Ideally, these processes should be fully coupled so that benefits and impacts can be assessed at the level of the full fuel cycle. The paper summarizes the causes and consequences of the absence of integration at the back-end of the nuclear fuel cycle in the U.S., critically reviews ongoing integration efforts, and suggests a framework that would support the back-end integration.

Aluminosilicate-Phosphate Model of Polyphase Matrices for Immobilization of Sr-Cs-fractions of Nuclear Fuel Cycle HLW

2013 ◽  
Vol 7 (3) ◽  
pp. 209-219 ◽  
Author(s):  
R. Bogdanov ◽  
R. Kuznetsov ◽  
V. Epimahov ◽  
A. Titov ◽  
E. Prudnikov
Keyword(s):  
Nuclear Fuel ◽  
Fuel Cycle ◽  
Nuclear Fuel Cycle

A family of uranyl oxide hydrate phases with bivalent cations [MII(H2O)4][(UO2)3O3(OH)2]·H2O (MII – Mn, Co, Ni, Zn): synthesis, characterization and chemical stability in aqueous solutions

2021 ◽  
Author(s):  
Nikolay G. Chernorukov ◽  
Oxana V. Nipruk ◽  
Kseniya A. Klinshova ◽  
Olga N. Tumaeva ◽  
Dmitry V. Sokolov
Keyword(s):  
Aqueous Solutions ◽  
Nuclear Fuel ◽  
Chemical Stability ◽  
Fuel Cycle ◽  
Nuclear Fuel Cycle ◽  
Oxide Hydrate ◽  
Uranium Compounds ◽  
Bivalent Cations

A series of new uranium compounds [MII(H2O)3][(UO2)3O3(OH)2]·2H2O (MII – Mn, Co, Ni, Zn) were synthesized for binding radionuclides in the environment and nuclear fuel cycle.

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