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Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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2025 ANS Annual Conference
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Chicago, IL|Chicago Marriott 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
Webinar: MC&A and safety in advanced reactors in focus
Towell
Russell
Prasad
The American Nuclear Society’s Nuclear Nonproliferation Policy Division recently hosted a webinar on updating material control and accounting (MC&A) and security regulations for the evolving field of advanced reactors.
Moderator Shikha Prasad (CEO, Srijan LLC) was joined by two presenters, John Russell and Lester Towell, who looked at how regulations that were historically developed for traditional light water reactors will apply to the next generation of nuclear technology and what changes need to be made.
Chang Joon Jeong, Ho Chun Suk
Nuclear Technology | Volume 154 | Number 2 | May 2006 | Pages 215-223
Technical Paper | Reactor Safety | doi.org/10.13182/NT06-A3729
Articles are hosted by Taylor and Francis Online.
The power pulse characteristics following a large loss-of-coolant accident have been analyzed for a Canada deuterium uranium (CANDU)-6 reactor core fueled with a CANDU flexible fueling recovered uranium fuel. The coupled simulations for the reactor physics and channel thermal-hydraulics phenomena are done using the RFSP and CATHENA codes. The 55% pump suction, 35% reactor inlet header, and 100% reactor outlet header breaks were selected. From the analysis results, it is known that the shutoff rods have enough reactivity for a reactor shutdown and to maintain it at a subcriticality state. Even with the highest power pulse, which occurred in a 100% reactor outlet header break, the fuel temperature was maintained below the fuel melting temperature. The summation of the initial stored energy and the transient pulse energy of the hottest fuel pin has a minimum 17% margin for the fuel breakup.
