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Division Spotlight
Decommissioning & Environmental Sciences
The mission of the Decommissioning and Environmental Sciences (DES) Division is to promote the development and use of those skills and technologies associated with the use of nuclear energy and the optimal management and stewardship of the environment, sustainable development, decommissioning, remediation, reutilization, and long-term surveillance and maintenance of nuclear-related installations, and sites. The target audience for this effort is the membership of the Division, the Society, and the public at large.
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
TerraPower begins U.K. regulatory approval process
Seattle-based TerraPower signaled its interest this week in building its Natrium small modular reactor in the United Kingdom, the company announced.
TerraPower sent a letter to the U.K.’s Department for Energy Security and Net Zero, formally establishing its intention to enter the U.K. generic design assessment (GDA) process. This is TerraPower’s first step in deployment of its Natrium technology—a 345-MW sodium fast reactor coupled with a molten salt energy storage unit—on the international stage.
R. C. Sanders, G. E. Mueller
Nuclear Technology | Volume 42 | Number 3 | March 1979 | Pages 289-296
Technical Paper | Reactor Siting | doi.org/10.13182/NT79-A32182
Articles are hosted by Taylor and Francis Online.
The maximum credible accident for which a nuclear reactor must be analyzed is a loss-of-coolant accident (LOCA) due to a major rupture in the primary system. Such an accident has been analyzed for a conceptual design of a consolidated nuclear steam system (CNSS) using the thermal-hydraulic computer code RELAP4/MOD5. The results of the analysis show that the maximum fuel cladding temperature during the accident is ∼344°C (652°F), which is sufficiently low to preclude any damage to the reactor core. Based on the results of this analysis, it appears that a LOCA in a CNSS may be less severe than in typical loop-type pressurized water and boiling water reactors. This result is expected because of the smaller piping connected to the CNSS reactor vessel
