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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 Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
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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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Fusion Science and Technology
August 2024
Latest News
Nuclear new build procurement considerations
It may seem counterintuitive, but the best time to enhance the ability to support operations and maintenance for a new plant is before construction starts. This is one of many lessons learned by the currently operating nuclear fleet. As construction and startup of many nuclear facilities was completed, it quickly became evident that the ability to efficiently support operations and maintenance was limited. Most of the information necessary to establish and manage procurement of spare and replacement items, maintenance, and configuration of the facilities was unavailable and had to be gathered on a case-by-case, “on-demand” basis. Absence of necessary information and the associated challenges resulted in the need for staff augmentation and multiyear-long projects to develop equipment bills of material and maintenance programs and to perform technical evaluations for the huge quantities of spare and replacement items being requested.
J.-L. Duchateau, M. Coatanea, B. Lacroix, S. Nicollet, D. Ciazynski, P. Bayetti
Fusion Science and Technology | Volume 64 | Number 4 | November 2013 | Pages 705-710
Technical Paper | doi.org/10.13182/FST13-A24089
Articles are hosted by Taylor and Francis Online.
The quench of one of the ITER magnet systems is an irreversible transition of the conductor from superconducting to normal resistive state. The normal zone propagates along the cable-in-conduit conductor, dissipating a large power. The detection has to be fast enough (1 to 2 s) to initiate the dumping of the magnetic energy and avoid irreversible damage of the systems.The experience of CEA is based on the operation of the superconducting tokamak Tore Supra for more than 20 years. In support of ITER, CEA was also very involved in quench detection investigations during these past 3 years.The primary quench detection in ITER is based on voltage detection, the most rapid detection. The very magnetically disturbed environment during a plasma scenario makes the voltage detection particularly difficult, inducing large inductive components across the pulsed coils (10 kV) or coil subcomponents. Voltage compensations therefore have to be designed to discriminate the resistive voltage associated with the quench.A secondary detection based on a thermohydraulic signals system also has to be investigated to protect the environment in case of a nondetected quench, especially for the largest ITER system, which is the toroidal field system with a stored energy of 40 GJ.