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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
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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Nuclear Science and Engineering
February 2025
Nuclear Technology
January 2025
Fusion Science and Technology
Latest News
Marzano sworn in as NRC commissioner
Marzano
Matthew Marzano became the newest member of the Nuclear Regulatory Commission when he was officially sworn into office by chair Christopher Hanson this week.
The nuclear engineer and former reactor operator was confirmed last month in a 50–45 vote in the U.S. Senate. Last July, President Biden nominated Marzano to serve on the commission, which is tasked with formulating policies, developing regulations, issuing orders, and resolving legal matters.
Marzano’s term expires June 30, 2028.
Masahiro Matsumura
Nuclear Technology | Volume 83 | Number 2 | November 1988 | Pages 134-161
Technical Paper | Fission Reactor | doi.org/10.13182/NT88-A34156
Articles are hosted by Taylor and Francis Online.
The performance of pressurized water reactor (PWR) power plants is evaluated through analysis of power generation records, and directions are given in which measures might be effectively sought for further improvement of plant performance and productivity. The boundary between what has already been achieved in the performance of such plants and what remains to be done in development and demonstration is clearly identified. To supplement the traditionally adopted “capacity factor” (average power/nominal capacity) for assessing the improvements gained in the performance of uprated fuels and reactor cores, additional new yardsticks are proposed to represent the productivity of nuclear fuel and the reactor core. For evaluating the performance of fuel, the proposed variable is based on the correlation between specific power and annual core average burnup, i.e., thermal power and annual heat generation per unit mass of fuel. Similarly for the reactor core, the variable is based on the correlation between thermal power and heat generation per unit core volume and per unit area of core cross section. The advantages of adopting the proposed variables are discussed. Operating experience with PWR plants indicates that the relatively short service life of nuclear fuel, compared with the core structure and other reactor components, has permitted reliable, effective service of uprated fuel in high-performance plants to be demonstrated over periods extending beyond the service life of individual fuels. This is not the case, however, with the core structure and other reactor components: Most existing plants have been in service for less than half of the expected service life of these components, therefore data available today are insufficient for evaluation of their long-term performance. An analysis is presented on possible repercussions to be expected from the current trend in development, which tends toward higher core power rating, and it is pointed out that certain plant components will possibly come to be exposed to increasingly severe thermal conditions, which calls for further efforts in development and demonstration to ensure their continued reliability in service.