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Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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
INL’s new innovation incubator could link start-ups with an industry sponsor
Idaho National Laboratory is looking for a sponsor to invest $5 million–$10 million in a privately funded innovation incubator to support seed-stage start-ups working in nuclear energy, integrated energy systems, cybersecurity, or advanced materials. For their investment, the sponsor gets access to what INL calls “a turnkey source of cutting-edge American innovation.” Not only are technologies supported by the program “substantially de-risked” by going through technical review and development at a national laboratory, but the arrangement “adds credibility, goodwill, and visibility to the private sector sponsor’s investments,” according to INL.
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.