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Conference Spotlight
2026 ANS Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
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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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Christmas Light
’Twas the night before Christmas when all through the house
No electrons were flowing through even my mouse.
All devices were plugged by the chimney with care
With the hope that St. Nikola Tesla would share.
Hideo Nagasaka, Takashi Sato, Hirohide Oikawa, Ryoichi Hamazaki, Kenji Arai, Takao Kageyama, Hiroyuki Yoshida, Hiroshi Machiba
Nuclear Technology | Volume 92 | Number 2 | November 1990 | Pages 260-268
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT90-A34477
Articles are hosted by Taylor and Francis Online.
The TOSBWR-900P, a natural-circulation boiling water reactor design with 300-MW(electric) power emphasizing passive safety, is studied. The TOSBWR-900P has steam drums above the pressure vessel that minimize the lower drywell volume associated with a top-mounted gravity-driven control rod device. The flow to the core is controlled by the valves on the downcomer pipes. The emergency core cooling system consists of high- and low-pressure accumulators, a gravity-driven core cooling system, and an automatic depressurization system, which guard against core uncovery in case of a design-basis accident. Long-term decay heat removal is achieved passively by a drywell water wall. The gravity-driven drywell spray water can completely flood the reactor pressure vessel during a severe core damage accident.