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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.
Meeting Spotlight
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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Latest News
Candidates for leadership provide statements: ANS Board of Directors
With the annual ANS election right around the corner, American Nuclear Society members will be going to the polls to vote for a vice president/president-elect, treasurer, and members-at-large for the Board of Directors. In January, Nuclear News published statements from candidates for vice president/president-elect and treasurer. This month, we are featuring statements from each nominee for the Board of Directors.
J. A. Redfield, J. H. Murphy
Nuclear Technology | Volume 6 | Number 2 | February 1969 | Pages 127-136
Technical Paper and Note | doi.org/10.13182/NT69-A28243
Articles are hosted by Taylor and Francis Online.
A loss-of-coolant analysis method, FLASH, has been tested experimentally and improved. The more versatile FLASH-2 computer program that evolved produces results that agree with classical theory in the case of decompression of pipes and with experiment in the case of blowdown of water-filled tanks. Such agreement increases confidence in FLASH-2 as a rational basis for predicting the consequences of a loss-of-coolant accident.
