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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.
Meeting Spotlight
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
Standards Program
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
TerraPower begins U.K. regulatory approval process
Seattle-based TerraPower signaled its interest this week in building its Natrium small modular reactor in the United Kingdom, the company announced.
TerraPower sent a letter to the U.K.’s Department for Energy Security and Net Zero, formally establishing its intention to enter the U.K. generic design assessment (GDA) process. This is TerraPower’s first step in deployment of its Natrium technology—a 345-MW sodium fast reactor coupled with a molten salt energy storage unit—on the international stage.
P. Barthelemy, R. Berger, R. Boucher, L. Hayet
Nuclear Technology | Volume 26 | Number 2 | June 1975 | Pages 201-214
Technical Paper | Radioisotope | doi.org/10.13182/NT75-A24419
Articles are hosted by Taylor and Francis Online.
In 1971 the French Atomic Energy Commission (CEA) established itself as a candidate for 252Cf commercial encapsulation services. A production facility, designed and built at the Fontenay-aux-Roses Centre for Nuclear Studies, allows handling of up to 10 mg of 252Cf. This unit started operation in Sep. 1973. The main features of the californium facility are: (a) remote manipulation by means of two electrical robots, (b) TIG welding of capsules and assemblies using two machines, with variable positioning of the electrode along the three axis that allows the soldering of pieces as large as 50 mm in diameter and 2 m in length, (c) capsule decontamination by an electrolytic pickling technique, and (d) neutron source emission counting by means of a uranium fission chamber giving relative measurements versus a 252Cf standard with an accuracy of 3%. All sealed sources developed at the CEA are made of 252Cf2O3-Pd cermets encapsulated in stainless steel, Zircaloy, or nickel and are qualified as special form nuclear material. Present applications of 252Cf sealed sources in France are directed toward physical research and nuclear reactor design, nuclear reactor startup and nuclear materials assay, neutron activation analysis development for in situ determinations in the earth science and mineral exploration, and for process control in metallurgy. Furthermore, the CEA is involved in a government-sponsored program on a 252Cf source projector for neutron therapy. For the afterloading interstitial technique, the CEA has designed miniaturized sources made of a 252Cf2O3-Pd cermet containing 0.32 μg of 252Cf sealed in a platinum capsule 0.70 mm in diameter and 4 mm long.