ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
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!
Latest Magazine Issues
Apr 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
May 2025
Nuclear Technology
April 2025
Fusion Science and Technology
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.
Selim Sancaktar, T. van de Venne
Nuclear Technology | Volume 91 | Number 1 | July 1990 | Pages 112-117
Technical Paper | Safety of Next Generation Power Reactor / Nuclear Safety | doi.org/10.13182/NT90-A34447
Articles are hosted by Taylor and Francis Online.
Insights obtained from various probabilistic risk analysis (PRA) studies performed by the Westinghouse Electric Corporation and associates on new pressurized water reactor (PWR) designs are briefly discussed and compared. The discussion is limited to internal initiating events since external event analysis requires site-specific data. The plant core melt frequency resulting from these initiating events is used as the measure to identify dominant accident sequences. The initiating events, failures of frontline safety systems and their support systems, operator actions, and consequential failures are used to measure the response of each design to various safety issues discussed. A conventional PWR plant is used as the base to compare the features of the different designs and the insights obtained from the PRA studies. The cases discussed include (a) a conventional PWR plant design (Westinghouse), (b) a Progetto Unificato Nucleare design (Westinghouse and Ansaldo), (c) a Sizewell-B design (Westinghouse and National Nuclear Corporation), and (d) an advanced PWR design (Westinghouse and Mitsubishi Heavy Industries). In studies (b), (c), and (d), PRAs are performed in the early design stages to evaluate the effect of primary safety and support systems on the plant core melt frequency. The results of the PRA evaluations are used, together with other considerations, to make appropriate design modifications. The experience obtained from studies (b), (c), and (d) leads to the conclusion that PRAs are effective in supporting early plant design efforts for engineered safety systems. Probabilistic risk analysis models provide an additional decision-making tool to evaluate the importance and effect of various design alternatives.
