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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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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
WIPP improves utility shaft safety, begins infrastructure project
Harrison Western Shaft Sinkers (HWSS), the company drilling a new utility shaft at the Department of Energy’s Waste Isolation Pilot Plant in New Mexico, has retained a safety culture expert following a near-miss accident in the shaft late last year. The safety expert will conduct monthly facilitated discussions with crews working on the shaft to reinforce expectations for identifying concerns regarding unsafe circumstances, according to a recent report by the Defense Nuclear Facilities Safety Board (DNFSB).
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.