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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
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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Reviewers needed for NRC research proposals
The deadline is fast approaching for submitting an application to become a technical reviewer for the Nuclear Regulatory Commission’s fiscal year 2025 research grant proposals.
Steven T. Polkinghorne, Gregg L. Sharp, Richard T. McCracken
Nuclear Technology | Volume 145 | Number 1 | January 2004 | Pages 44-56
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT04-A3459
Articles are hosted by Taylor and Francis Online.
The Advanced Test Reactor (ATR) is a 250-MW irradiation facility used to test reactor fuels and other materials, and also to produce radioisotopes. The ATR core is divided into five regions, or lobes, that normally operate at different power levels. To support future irradiation programs, it is desired that the maximum lobe power be increased 10% (from 60 to 66 MW). A modification to ATR's emergency core cooling system is proposed to ensure that adequate safety margins would be maintained during a loss-of-coolant accident (LOCA). The modification being considered is the addition of an accumulator injection system. The RELAP5 thermal-hydraulic code and the SINDA thermal analyzer were used to simulate the two most challenging design-basis LOCAs identified in the ATR Safety Analysis Report. Calculations were performed both with and without accumulator injection. The results indicate that a 10% increase in maximum lobe power is achievable. Minimum thermal margins increased more than 40% when accumulator injection was simulated.