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Human Factors, Instrumentation & Controls
Improving task performance, system reliability, system and personnel safety, efficiency, and effectiveness are the division's main objectives. Its major areas of interest include task design, procedures, training, instrument and control layout and placement, stress control, anthropometrics, psychological input, and motivation.
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2027 ANS Winter Conference and Expo
October 31–November 4, 2027
Washington, DC|The Westin Washington, DC Downtown
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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
Supreme Court rules against Texas in interim storage case
The Supreme Court voted 6–3 against Texas and a group of landowners today in a case involving the Nuclear Regulatory Commission’s licensing of a consolidated interim storage facility for spent nuclear fuel, reversing a decision by the 5th Circuit Court of Appeals to grant the state and landowners Fasken Land and Minerals (Fasken) standing to challenge the license.
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.
