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Conference Spotlight
2025 ANS Winter Conference & Expo
November 8–12, 2025
Washington, DC|Washington Hilton
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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Japan gets new U for enrichment as global power and fuel plans grow
President Trump is in Japan today, with a visit with new Prime Minister Sanae Takaichi on the agenda. Takaichi, who took office just last week as Japan’s first female prime minister, has already spoken in favor of nuclear energy and of accelerating the restart of Japan’s long-shuttered power reactors, as Reuters and others have reported. Much of the uranium to power those reactors will be enriched at Japan’s lone enrichment facility—part of Japan Nuclear Fuel Ltd.’s Rokkasho fuel complex—which accepted its first delivery of fresh uranium hexafluoride (UF₆) in 11 years earlier this month.
Mark A. Chaiko, Michael J. Murphy
Nuclear Technology | Volume 94 | Number 1 | April 1991 | Pages 44-55
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT91-A16220
Articles are hosted by Taylor and Francis Online.
The Compartment Transient Temperature Analysis Program (COTTAP) was developed by the Pennsylvania Power & Light Company for postaccident boiling water reactor (BWR) secondary containment thermal analysis. The code makes use of previously developed implicit temporal integration methods and sparse matrix inversion techniques to allow modeling of an entire BWR secondary containment. Investigations were made with a model consisting of 121 compartments and 767 heat-conducting slabs. The simulation presented involves the numerical integration of 20 101 ordinary differential equations over a 30-h simulation period. Two hours of CPU time were required to carry out the calculation on an IBM 3090 computer. The COTTAP code considers natural convection and radiation heat transfer between compartment air and walls through a detailed finite difference solution of the slab conduction equations. Heat addition from hot piping and operating equipment, and cooling effects associated with ventilation flows and compartment heat removal units are also included. Additional capabilities of COTTAP include modeling of compartment heatup resulting from steamline breaks and simulation of natural circulation cooling in compartments with flow paths at differing elevations.