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Division Spotlight
Isotopes & Radiation
Members are devoted to applying nuclear science and engineering technologies involving isotopes, radiation applications, and associated equipment in scientific research, development, and industrial processes. Their interests lie primarily in education, industrial uses, biology, medicine, and health physics. Division committees include Analytical Applications of Isotopes and Radiation, Biology and Medicine, Radiation Applications, Radiation Sources and Detection, and Thermal Power Sources.
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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Latest News
NRC issues subsequent license renewal to Monticello plant
The Nuclear Regulatory Commission has renewed for a second time the operating license for Unit 1 of Minnesota’s Monticello nuclear power plant.
Yuri Orechwa
Nuclear Technology | Volume 170 | Number 3 | June 2010 | Pages 383-396
Technical Paper | Reactor Safety | doi.org/10.13182/NT10-A10325
Articles are hosted by Taylor and Francis Online.
Traditionally, the safety of a nuclear reactor system has been assessed through a set of mechanistic calculations of bounding accident sequences using conservative models. Extensive experience in the operation and analysis of nuclear reactor systems has led to two complementary approaches: best-estimate mechanistic calculations with a quantitative estimate of the uncertainty for assessing conformance with acceptance criteria based on technical limits and probabilistic risk analysis of the event sequences due to the probability of failure of safety systems. Both assess the safety of the reactor system; however, the emphasis, especially in the estimation of probabilities, is different in the two approaches. Yet both address the same concern: the safety of the reactor system. We discuss the formal relations that are necessary for a risk-consistent analysis of the safety of the nuclear reactor systems with respect to the two current approaches.