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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.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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
G7 pledges support for nuclear at Italy meeting
The Group of Seven (G7) recommitted its support for nuclear energy in the countries that opt to use it at a Ministerial Meeting on Climate in Italy last month.
In a statement following the April meeting, the group committed to support multilateral efforts to strengthen the resilience of nuclear supply chains, referencing the goal set by 25 countries during last year’s COP28 climate conference in Dubai to triple global nuclear generating capacity by 2050.
R. Leonard Myatt, Nicolai N. Martovetsky, Charlotte Barbier, Kevin D. Freudenberg
Fusion Science and Technology | Volume 64 | Number 2 | August 2013 | Pages 161-167
ITER | Proceedings of the Twentieth Topical Meeting on the Technology of Fusion Energy (TOFE-2012) (Part 1), Nashville, Tennessee, August 27-31, 2012 | doi.org/10.13182/FST13-A18072
Articles are hosted by Taylor and Francis Online.
The ITER central solenoid (CS) is wound from cable-in-conduit-conductor (CICC) and cooled by supercritical Helium (He) delivered to ~120 inner diameter (ID) turns through integrally welded "inlets." The flow to each inlet splits and passes through two pancakes, exiting at outlets. While both the He supply and return points (outlets) require penetrating the conduit wall, the inlets reside in the highest stress field, and thus become the more critical structural element.The CS Conceptual Design Review (CRD) reference He inlet design has a long, narrow slot in the inside diameter (ID) turn wall with pencil-tip shaped ends. This shape is optimized in order to minimize the hoop stress concentration. The slot length is chosen to expose each of the six superconducting (SC) sub-cables to the He cooling supply. Implementing this design at 120 inlet sites requires substantial machining and welding operations where even virgin conduit has minimal structural margin.A design space exploration produces numerous inlet options. One configuration emerges as the new reference configuration: the oblong, heavy-wall boss. It addresses all of the critical issues: bi-axial stress field, pressure drop and sub-cable flow uniformity, manufacturing costs (complexities and risks) and in-service robustness (least invasive, greatest margin).Finite element (FE) simulations are presented which highlight the results of the optimization and evaluation process.