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Division Spotlight
Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
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.
Yoshiyuki Kataoka, Michio Murase, Tadashi Fujii, Kenji Tominaga
Nuclear Technology | Volume 111 | Number 2 | August 1995 | Pages 241-250
Technical Paper | Nuclear Criticality Safety Special / Fission Reactor | doi.org/10.13182/NT95-A35133
Articles are hosted by Taylor and Francis Online.
An external water wall type containment cooling system is one of the passive containment cooling systems that use no active components and are intended for system simplification in the next generation power reactors. The core decay heat during a postulated loss-of-coolant accident is accumulated in the suppression pool (SP) and transferred to the outer pool, which is a cooling pool located outside and adjacent to the SP, by only natural phenomena such as natural convection, heat conduction, and evaporation. The temperature profiles and the convection heat transfer coefficients in the pools were measured using a 5-m height apparatus. The formation of a thermal stratification boundary at the vent outlets, which restricts the effective heat transfer area between pools, was clarified, and a correlation for natural convection heat transfer coefficients was obtained. Condensation heat transfer coefficients on the containment vessel wall and evaporation heat transfer coefficients on the SP surface under a noncondensable gas presence, which strongly affected the heat removal from the wet well, were evaluated based on the test results, and the correlations were obtained. The heat removal evaluation models, which analyze the trends of the temperatures and pressure, were developed and verified with system tests. As for the improvement of heat removal capability, two methods were proposed. One is a baffle plate to mitigate thermal stratification in the SP and enlarge the effective heat transfer area between pools. The second method is a divided wet well to avoid noncondensable gas effects. The thermal-hydraulic behavior in the SP with a baffle plate was clarified by three-dimensional analysis, and the effectiveness of these methods was experimentally confirmed.