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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
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.
Farid Bamdad
Nuclear Technology | Volume 55 | Number 3 | December 1981 | Pages 578-582
Technical Paper | Fission Reactor | doi.org/10.13182/NT81-A32801
Articles are hosted by Taylor and Francis Online.
Analyses of depressurization rates other than full Automatic Depressurization System (ADS) blowdown are performed to study the effect on the core cooling capability and to minimize thermal stress on the reactor vessel. Four different arbitrary conditions are demonstrated in order to verify the possibility of defining a range over which the slow depressurization can be performed without uncovering the core. The first two cases demonstrate the sensitivity to the depressurization starting time by manual blowdown at 25% capacity at 5 and 8 min into the transient. Two other cases are chosen to show the possible effects of the rate of depressurization. This is done by blowing down at 50 and 75% steam relief capacity at 5 min after the initiation of the transient. For all these cases it is assumed that an additional 25% flow discharge exists due to a stuck open relief valve. The last case demonstrated that early full ADS blowdown might flash water mixed with steam through the relief valves. This is due to the sudden expansion in the reactor vessel inventory upon pressure relief and high water level at the time of depressurization. This, however, is of paramount importance in the integrity and design operating conditions of the ADS valves and steam piping system.