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Division Spotlight
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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2021 Student Conference
April 8–10, 2021
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Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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January 2021
Latest News
Fukiushima Daiichi: 10 years on
The Fukushima Daiichi site before the accident. All images are provided courtesy of TEPCO unless noted otherwise.
It was a rather normal day back on March 11, 2011, at the Fukushima Daiichi nuclear plant before 2:45 p.m. That was the time when the Great Tohoku Earthquake struck, followed by a massive tsunami that caused three reactor meltdowns and forever changed the nuclear power industry in Japan and worldwide. Now, 10 years later, much has been learned and done to improve nuclear safety, and despite many challenges, significant progress is being made to decontaminate and defuel the extensively damaged Fukushima Daiichi reactor site. This is a summary of what happened, progress to date, current situation, and the outlook for the future there.
Y. Keheyan et al.
Fusion Science and Technology | Volume 48 | Number 1 | July-August 2005 | Pages 230-233
Technical Paper | Tritium Science and Technology - Decontamination and Waste | dx.doi.org/10.13182/FST05-A919
Articles are hosted by Taylor and Francis Online.
The sorptive behaviour of radioactive waste on Armenian zeolites, natural, irradiated, chemically treated and heated at high temperatures was studied and their capacity for the separation and enrichment of radionuclides was evaluated.The influence of temperature, acidity, basicity, specific activity, electron and gamma irradiation on sorption have been studied. The chemical analysis of exchanged samples was carried out and the cation exchange capacity was determined. Absorption properties of mono-cationic forms of different clinoptilolite samples were studied depending on type of guest cation and contact time.By means of model experiments the laboratory plant for absorption of metal cations from solutions in dynamic regime was designed and developed. This plant was used for experiments of radioactive waste removal from the Armenian nuclear reactor.
