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Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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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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The 2025 ANS election results are in!
Spring marks the passing of the torch for American Nuclear Society leadership. During this election cycle, ANS members voted for the newest vice president/president-elect, treasurer, and six board of director positions (four U.S., one non-U.S., one student). New professional division leadership was also decided on in this election, which opened February 25 and closed April 15. About 21 percent of eligible members of the Society voted—a similar turnout to last year.
D. Castelliti, T. Hamidouche
Nuclear Technology | Volume 193 | Number 1 | January 2016 | Pages 36-46
Technical Paper | Special Issue on the RELAP5-3D Computer Code | doi.org/10.13182/NT14-139
Articles are hosted by Taylor and Francis Online.
The MYRRHA (Multi-purpose hYbrid Research Reactor for High-tech Applications) project aims at the construction of a pool-type subcritical accelerator-driven system that could also operate as a critical reactor. The primary system, enclosed in the primary vessel, is filled with lead-bismuth eutectic (LBE). The secondary cooling fluid is two-phase water operating at relatively low pressure (16 bars). Four aerocondensers act as heat sinks.
The code version used for the development of the MYRRHA models is RELAP5 MOD 3.3; this version has been properly modified to allow the use of LBE as a fluid.
Since the RELAP5-3D code is already equipped with LBE as working fluid, RELAP5-3D has recently been acquired by SCK•CEN in anticipation of the licensing process.
The first important action taken consisted of comparing the two codes by running the existing MYRRHA model input deck, developed for RELAP5 MOD 3.3, on RELAP5-3D.
From the steady-state comparative analysis, it appears clear how the two code versions are using different physical models since the steady-state predictions show several differences. Several code issues have been found, mainly about LBE physical properties, initial noncondensable gas computation at LBE free surface level, and LBE heat transfer coefficient correlations.
For what concerns the transient analysis, the protected loss-of-flow (PLOF) accident has been taken as reference. Also, in PLOF conditions the mass flow rates and temperature distributions are affected by physical properties and heat transfer model differences.