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Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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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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ANS announces 2025 Presidential Citations
One of the privileges of being president of the American Nuclear Society is awarding Presidential Citations to individuals who have demonstrated outstanding effort in some manner for the benefit of ANS or the nuclear community at large. Citations are conferred twice each year, at the Annual and Winter Meetings.
ANS President Lisa Marshall has named this season’s recipients, who will receive recognition at the upcoming Annual Conference in Chicago during the Special Session on Tuesday, June 17.
Lalit Singh, Hitesh Rajput
Nuclear Technology | Volume 195 | Number 3 | September 2016 | Pages 301-309
Technical Paper | doi.org/10.13182/NT15-151
Articles are hosted by Taylor and Francis Online.
Verification of safety is a key activity in designing safety critical systems. The objective of safety verification is to avoid unacceptable risk of damage to public health or property or physical injury by any means. To ensure the goals of safety, these systems must reach a safe state for the occurrence of any failure. There is a need to verify the design of such systems to identify and overcome the probable risks, if any. This paper presents a case for safety verification of the main steam system of a nuclear reactor. The technique shown is based on Petri nets, to model and analyze the safety critical computer-based systems for safety verification. The paper further argues that the proposed technique is beneficial in improving faulty design.