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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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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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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Latest News
NRC updating GEIS rule for new nuclear technology
The Nuclear Regulatory Agency is issuing a proposed generic environmental impact statement (GEIS) for use in reviewing applications for new nuclear reactors.
In an April 17 memo, NRC secretary Carrie Safford wrote that the commission approved NRC staff’s recommendation to publish in the Federal Register a proposed rule amending 10 CFR Part 51, “Environmental Protection Regulations for Domestic Licensing and Related Regulatory Functions.”
A. I. Vedeneev et al.
Fusion Science and Technology | Volume 48 | Number 1 | July-August 2005 | Pages 43-46
Technical Paper | Tritium Science and Technology - Tritium Processing, Transportation, and Storage | doi.org/10.13182/FST05-A876
Articles are hosted by Taylor and Francis Online.
First experimental results of a tritium pellet injector steady-state operation is presented. The tritium injector TPI-1 was developed at the PELIN Laboratory and put in operation in Russian Federal Nuclear Center. It is a part of an experimental closed circuit for simulation of ITER fuel cycle. Results of several continuous extrusions of solid rod made of various hydrogen isotopes are presented. Transverse dimensions of an extruded ice rod with rectangular cross-section were ~ 3 × 4mm. The greatest extrusion velocity came to 15 mm/s for hydrogen and 9 mm/s for D-T mixture; tritium content in fuel mixture did not exceed 11%; pellet velocity ran up to 500 m/s at repetitive mode. An optimal mode of D-T ice extrusion was determined.