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Division Spotlight
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
Meeting Spotlight
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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
Norway’s Halden reactor takes first step toward decommissioning
The government of Norway has granted the transfer of the Halden research reactor from the Institute for Energy Technology (IFE) to the state agency Norwegian Nuclear Decommissioning (NND). The 25-MWt Halden boiling water reactor operated from 1958 to 2018 and was used in the research of nuclear fuel, reactor internals, plant procedures and monitoring, and human factors.
Yu-Huai Shih, Shih-Jen Wang, Kai-Cheng Chuang, Tzu-En Huang
Nuclear Technology | Volume 186 | Number 3 | June 2014 | Pages 340-352
Technical Paper | Reactor Safety | doi.org/10.13182/NT12-145
Articles are hosted by Taylor and Francis Online.
The Fukushima Daiichi accident occurred on March 11, 2011. A seismic event and tsunami induced an extended station blackout plus loss of the ultimate heat sink. Three units progressed into a core melt severe accident. The accident occurred in the emergency operation procedure (EOP) domain. However, this situation was already beyond the scope of an EOP. The operator followed the EOP faithfully, and a core melt situation still occurred. An interesting topic is whether it is possible to avoid this type of accident. The purpose of this study is to survey the Fukushima accident progression with respect to the effect of the containment venting strategy for the Chinshan Nuclear Power Plant EOPs. Under the emergency situation, only a small reactor pressure vessel (RPV) injection system was available. This type of accident may be avoided by an early shift from the EOP to the severe accident guideline (SAG), switching from high-pressure injection to low-pressure injection while the reactor core isolation cooling system is available, gradually lowering the RPV pressure, and maximizing the injection flow rate. The plant responses and accident physical phenomena were simulated using MAAP5. The results show that the consequences of an uncovered core and core melt can be avoided by adopting the proper RPV depressurization and containment venting strategy.