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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 Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
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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
Palisades to receive $3B in federal, state funding to fuel plant restart
With a $1.52 billion loan from the Department of Energy and $1.3 billion in grants to rural electric cooperatives near the plant, the ambitious plans to restart Michigan’s Palisades nuclear plant next fall are moving ahead.
Makoto Sobajima
Nuclear Science and Engineering | Volume 60 | Number 1 | May 1976 | Pages 10-18
Technical Paper | doi.org/10.13182/NSE76-A26852
Articles are hosted by Taylor and Francis Online.
It was found that the results of the RELAP-3 code, which is one of the typical analytical codes for analysis of the loss-of-coolant accident (LOCA) of light water reactors, do not agree well with the results from the ROSA-I experiments under certain break conditions. It was determined that the discharge coefficient used in the code as a parameter can be correlated with the quality of the discharged fluid and that the calculated liquid mass transient does not always agree with the experimental one when a constant bubble escape velocity is assumed. These difficulties come from the possibility of shortcomings of the model dealing with the LOCA phenomena. An attempt was made to improve these aspects of the code by incorporating the correlation of the discharge coefficient with the quality and with Wilson's experimental interpretation of the bubble velocity and certain assumptions in its application. The results obtained by the modified code are in good agreement with both those from the ROSA-I experiment and experiments at Hitachi Ltd.