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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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Dragonfly, a Pu-fueled drone heading to Titan, gets key NASA approval
Curiosity landed on Mars sporting a radioisotope thermoelectric generator (RTG) in 2012, and a second NASA rover, Perseverance, landed in 2021. Both are still rolling across the red planet in the name of science. Another exploratory craft with a similar plutonium-238–fueled RTG but a very different mission—to fly between multiple test sites on Titan, Saturn’s largest moon—recently got one step closer to deployment.
On April 25, NASA and the Johns Hopkins University Applied Physics Laboratory (APL) announced that the Dragonfly mission to Saturn’s icy moon passed its critical design review. “Passing this mission milestone means that Dragonfly’s mission design, fabrication, integration, and test plans are all approved, and the mission can now turn its attention to the construction of the spacecraft itself,” according to NASA.
J. Bourges, C. Madic, G. Koehly, T. H. Nguyen, D. Baltes, C. Landesman, A. Simon
Nuclear Technology | Volume 113 | Number 2 | February 1996 | Pages 204-220
Technical Paper | Radioisotopes and Isotope | doi.org/10.13182/NT96-A35189
Articles are hosted by Taylor and Francis Online.
In 1985, the Commissariat à I’Energie Atomique (CEA), France, decided to set up an industrial unit at the Saclay Nuclear Research Center to produce fission 99Mo and to supply this isotope to the ORIS Company, France, for medical applications. The CEA’s role in this project was to develop a brand-new process for 99Mo production and to assume responsibility for the design and construction of the industrial plant. Production was based on 74 TBq (2 kCi) of 99Mo per week, under particularly severe constraints to protect the environment and the workers. The production unit, run in a semiautomatic mode, was built at Saclay in 1987 and cold tested from 1987 to 1989. The unit was never upgraded to active experiments because of the sudden drop in the price of 99Mo on the world market, which made the French project uneconomic. The focus here is mainly on the research conducted at the time to define and to validate the entire fission molybdenum chemical process. The process flowchart incorporates two original features. First, in the head-end of the process, the irradiated targets are dissolved in a sulfuric acid medium, entailing the maintenance of radioiodine and radiotellurium, for safety reasons, in the form of I‾(AgI) and Te(0), respectively, allowing their easy removal as solids from the dissolution liquors and their subsequent storage for radioactive decay. Second, in the core of the process, the molybdenum is purified by extraction with tri-n-butylacetohydroxamic acid, an extractant with exceptional affinity and selectivity for Mo(VI). The 99Mo(VI) extraction cycles employ the extraction chromatographic mode.