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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.
Sergey I. Belousov, Krassimira D. Ilieva, Stoyan Y. Antonov
Nuclear Technology | Volume 111 | Number 2 | August 1995 | Pages 270-274
Technical Paper | Nuclear Criticality Safety Special / Material | doi.org/10.13182/NT95-A35136
Articles are hosted by Taylor and Francis Online.
The neutron flux values at the sites important for the pressure vessels of the VVER-1000 and VVER-440 reactors have been calculated by the three-dimensional TORT code and the synthesis method approximation. The synthesis method is widely used now for neutron fluence routine calculations in metal embrittlement surveillance. The three-dimensional neutron flux evaluation by the synthesis method is based on the two-dimensional and one-dimensional solutions of the transport equation. The comparison of the results obtained by both methods confirms the good consistency within 3% for integral neutron flux with energy >0.5 MeV, used for metal damage estimation, according to Russian reactor standards. Further investigations on the calculation validity will be based on comparisons with measurements of the threshold detector activities, monitored in the air shell behind the reactor pressure vessels of the Kozloduy nuclear power plant.
