ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2023)
February 6–9, 2023
Amelia Island, FL|Omni Amelia Island Resort
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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Nuclear Science and Engineering
Fusion Science and Technology
A review of workforce trends in the nuclear community
The nuclear community is undergoing a moment of unprecedented interest and growth not seen in decades. The passage of the bipartisan Infrastructure Investment and Jobs Act and the Inflation Reduction Act are providing a multitude of new funding opportunities for the nuclear community, and not just the current fleet. A mix of technologies and reactor types are being evaluated and deployed, with Vogtle Units 3 and 4 coming on line later this year, the Advanced Reactor Demonstration Projects of X-energy and TerraPower, and NuScale’s work with Utah Associated Municipal Power Systems to build a first-of-a-kind small modular reactor, making this is an exciting time to join the nuclear workforce.
L. Savoldi, R. Bonifetto, A. Brighenti, V. Corato, L. Muzzi, S. Turtu’, R. Zanino, A. Zappatore
Fusion Science and Technology | Volume 72 | Number 3 | October 2017 | Pages 439-448
Technical Paper | doi.org/10.1080/15361055.2017.1333866
Articles are hosted by Taylor and Francis Online.
The design of a suitable quench protection system is fundamental for the safe operation of superconducting magnets and in turn requires the accurate simulation of the quench transient. The quench propagation in a toroidal field (TF) coil for the future European fusion reactor (EU DEMO) is analyzed here considering the latest, layer-wound winding pack (WP) design proposed by ENEA. The thermal-hydraulic model of a TF coil implemented in the 4C code is updated by including the external cryogenic circuits of the WP and of the casing cooling channels and proposing a preliminary layout of the quench lines. Three different locations are considered for the quench initiation: maximum temperature margin in the WP, and minimum and maximum temperature margin on the same turn of the innermost layer. The evolution of the main electrical and thermal-hydraulic parameters is simulated, such as voltage along each layer, quench front propagation both along and across the layers, hot spot temperature, pressurization of the coil and coolant mass flow rate at the coil boundaries, so that the 4C code provides a reliable (in view of its validation) and detailed virtual monitor of what happens inside the coil during the quench transient. In all cases considered, the ENEA design is predicted to satisfy the present (i.e., ITER) design criteria concerning the maximum allowed hot spot temperature.