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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
2022 ANS Winter Meeting and Technology Expo
November 13–17, 2022
Phoenix, AZ|Arizona Grand 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
October 2022
Nuclear Technology
Fusion Science and Technology
Latest News
Maintaining RIPB in commercial LWRs
The new standard ANSI/ANS-30.3-2022, Light Water Reactor Risk-Informed, Performance-Based Design, has just been issued by the American Nuclear Society. Approved by the American National Standards Institute (ANSI) on July 21, 2022, the standard provides requirements for the incorporation of risk-informed, performance-based (RIPB) principles and methods into the nuclear safety design of commercial light water reactors. The process described in this standard establishes a minimum set of process requirements the designer must follow in order to meet the intent of this standard and appropriately combine deterministic, probabilistic, and performance-based methods during design development.
P. Chellapandi, S. C. Chetal, Baldev Raj
Nuclear Technology | Volume 172 | Number 1 | October 2010 | Pages 1-15
Technical Paper | Fission Reactors | dx.doi.org/10.13182/NT10-A10878
Articles are hosted by Taylor and Francis Online.
The FUSTIN dedicated computer code has been developed to predict the transient response of pool-type fast reactor components in a core disruptive accident. FUSTIN accurately simulates several complex phenomena, such as large distortions in the fluids, large displacements of the structure, fast transient fluid-structure interaction, etc., involved in determining the transient pressures, vessel displacements, and strains. FUSTIN has been validated by solving a few international benchmark problems. Further, for experimental validation of FUSTIN, dedicated tests were conducted to (a) characterize a low-density explosive that can appropriately simulate the nuclear energy release rate and (b) generate data, particularly deformations in the vessels representing the scaled-down model of the main vessel of a typical pool-type fast reactor. In the tests, the nuclear energy release rate was simulated by a low-density chemical explosive, which has been thoroughly characterized. The validation exercise demonstrates the excellent prediction capability of FUSTIN. The paper presents the mathematical formulations, solution strategy, and validation aspects of FUSTIN.
