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Division Spotlight
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.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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
ANS designates Armour Research Foundation Reactor as Nuclear Historic Landmark
The American Nuclear Society presented the Illinois Institute of Technology with a plaque last week to officially designate the Armour Research Foundation Reactor a Nuclear Historic Landmark, following the Society’s decision to confer the status onto the reactor in September 2024.
Amir N. Nahavandi
Nuclear Science and Engineering | Volume 14 | Number 3 | November 1962 | Pages 272-286
doi.org/10.13182/NSE62-A26217
Articles are hosted by Taylor and Francis Online.
A digital computer analysis of the loss-of-coolant accident in the primary system of a multicircuit core nuclear power plant in the event of a complete severance of a pressure or jumper tube is presented. The time-dependent mass, momentum, and energy balance differential equations are expressed in finite difference form and solved numerically on an IBM-7090 digital computer together with the equations of state, system boundary conditions, and constraints. The system mass flow rate, pressure, and enthalpy distribution are calculated together with the other important system properties as functions of time during the transient operation following the break. The application of the analysis to the Carolinas-Virginia Tube Reactor indicates that the loss-of-coolant accident could lead to flow starvation in the reactor core and steam formation in the primary pump with subsequent core damage if no corrective action were taken. The flow starvation and steam formation problems are solved by the operation of a high pressure, high capacity emergency injection pump with fast starting characteristics.