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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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Latest News
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
Armando B. Antoniazzi, Clive S. Morton, Kevin P. Chen, Baojun Liu
Fusion Science and Technology | Volume 54 | Number 2 | August 2008 | Pages 635-638
Technical Paper | Process Applications | doi.org/10.13182/FST08-A1895
Articles are hosted by Taylor and Francis Online.
A tritium exposure apparatus has been designed and built for the purposes of generating a high-pressure tritium atmosphere at 523 K. The loading system consists of a uranium tritide storage bed, an intermediate tritium transfer chamber filled with 5A molecular sieve, and the sample exposure chamber. The loading system resides in a sealed glovebox with a nitrogen atmosphere that is continually purged through a Glovebox Clean-up System. The tritium used in each loading experiment is approximately 6000 Ci (22 TBq). The process entails transferring the tritium inventory from the uranium storage bed to the cryogenically cooled (77 K) molecular sieve chamber. The molecular sieve at liquid nitrogen temperature is capable of adsorbing tritium to densities of 290 Ci/gram at one atmosphere. At 523 K a maximum tritium pressure of 21 MPa is achieved. The loading apparatus is used to develop high-density radioactive isotope fuel for self-powered microelectronic and micromechanical devices. This paper presents the design specifics of the tritium exposure apparatus, the steps taken in generating the high-temperature, high-pressure tritium atmosphere and the performance characteristics of the apparatus. Additionally, the handling practices and equipment utilized to conduct the tests safely are presented.