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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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
Atomic Canyon partners with INL on AI benchmarks
As interest and investment grows around AI applications in nuclear power plants, there remains a gap in standardized benchmarks that can quantitatively compare and measure the quality and reliability of new products.
Nuclear-tailored AI developer Atomic Canyon is moving to fill that gap by entering into a new strategic partnership with Idaho National Laboratory to develop and release the “first comprehensive benchmark suite for evaluating retrieval-augmented generation (RAG) and large language models (LLMs) in nuclear applications.”
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.