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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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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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
Fabrication milestone for INL’s MARVEL microreactor
A team from Idaho National Laboratory and the Department of Energy’s Office of Nuclear Energy (DOE-NE) recently visited Carolina Fabricators Inc. (CFI), in West Columbia, S.C., to launch the fabrication process for the primary coolant system of the MARVEL microreactor. Battelle Energy Alliance (BEA), which manages INL, awarded the CFI contract in January.
Peter J. Jensen, James F. Lang, Jason Chao
Nuclear Technology | Volume 76 | Number 2 | February 1987 | Pages 279-289
Fourth International Retran Meeting | Heat Transfer and Fluid Flow | doi.org/10.13182/NT87-A33881
Articles are hosted by Taylor and Francis Online.
A method allowing individual representation of a ruptured steam generator tube without including it explicitly in the RETRAN-02 nodalization was investigated. The resulting methodology allows accurate representation of flow through a single ruptured tube without incurring prohibitive computing costs. The study considered a wide variety of fluid conditions at the rupture ranging from subcooled liquid to two-phase fluid and from choked to unchoked rupture flow. Although only one tube rupture geometry was considered, this study provides the groundwork from which methods specific to other geometries can be easily developed. Portions of this method were compared with RELAP5 calculations and good agreement was shown. This methodology was incorporated in a RETRAN-03 analysis of a steam generator tube rupture event in a Westinghouse two-loop plant. This included a case with a tube rupture accompanied by loss of off-site power as well as a case incorporating procedures for operator actions during a tube rupture event. The results indicate both the impact and the necessity of appropriate operator actions in such an event. The RETRAN-03 computer code was found to perform satisfactorily when this tube rupture modeling technique was incorporated. Faster than “realtime” computational speed was demonstrated on a Cyber 176 computer when using a fairly detailed RETRAN plant model (54 volumes, 82 junctions).