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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
ANS designates Armour Research Foundation Reactor as Nuclear Historic Landmark
The American Nuclear Society presented the Illinois Institute of Technology with a plaque last week to officially designate the Armour Research Foundation Reactor a Nuclear Historic Landmark, following the Society’s decision to confer the status onto the reactor in September 2024.
Sadayuki Izutsu, Yoshiro Kudo, Junichi Onuma, Tomohiko Iwasaki, Sakae Muto, Akio Toba
Nuclear Technology | Volume 89 | Number 1 | January 1990 | Pages 92-102
Technical Paper | Nuclear Safety | doi.org/10.13182/NT90-A34361
Articles are hosted by Taylor and Francis Online.
Rod drop accidents (RDAs) were calculated for a typical 1100-MW(electric) boiling water reactor (BWR) using the three-dimensional core dynamics simulation code ARIES. Calculated cases are for cold start-up and hot standby cores. In both cold start-up and hot standby core RDAs, the moderator density reactivity feedback has an important effect on suppressing fuel enthalpy increase. Hot standby core RDAs, in particular, show remarkable effects of the moderator density reactivity feedback on reducing the power peak and succeeding fuel enthalpy rise. Sensitivity analyses of the effects of initial power level, core inlet subcooling, rod drop speed, dropping rod worth, etc., have been carried out under both cold start-up and hot standby core conditions for a typical 1100-MW(electric) BWR. In the hot standby core RDAs, the parameters affecting neutronic conditions (such as Doppler feedback) and moderator density proved to be very sensitive. In the cold start-up core RDAs, the parameters affecting moderator density are not so sensitive, but the parameters affecting Doppler feedback or neutronic conditions proved to be more sensitive than in the hot standby core RDAs.
