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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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
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.
Yuan-Zhong Liu
Nuclear Technology | Volume 124 | Number 2 | November 1998 | Pages 192-197
Technical Note | Reactor Safety | doi.org/10.13182/NT98-A2919
Articles are hosted by Taylor and Francis Online.
A 10-MW high-temperature gas-cooled test reactor, the High-Temperature Reactor-10 (HTR-10), being built at the Institute of Nuclear Energy Technology of Tsinghua University, is a type of modular high-temperature gas-cooled reactor. The design features of the HTR-10 are studied in terms of five important sources of airborne radioactive materials released to the environment. These sources are activation of the air in the reactor cavity, leakage of the primary coolant, release of radioactively contaminated helium from the regeneration of the helium purification systems, release of radioactively contaminated helium from the gas evacuation subsystem of the fuel load and unload systems, and leakage of the vapor from the water/steam loops. On the basis of the HTR-10 design parameters, the amount of radioactivity released to the environment per year is calculated, and the dose to the public is calculated as it relates to the HTR-10 site.