ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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!
Latest Magazine Issues
Apr 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
June 2025
Nuclear Technology
Fusion Science and Technology
May 2025
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.
Sang Woon Shin, Hee Cheon No
Nuclear Technology | Volume 73 | Number 3 | June 1986 | Pages 378-383
Technical Paper | Material | doi.org/10.13182/NT86-A16079
Articles are hosted by Taylor and Francis Online.
To investigate the denting phenomenon, the rates of corrosion occurring in simulated tube/support plate crevices were examined by using seven model boilers at 1.11 MPa. The model boilers were operated with all-volatile treatment (morpholine + hydrazine) with 15- and 100-ppm chloride concentrations constituting 10% FeCl2, 30% NaCl, and 60% CaCl2. It was found that corrosion rates increased with heat flux. A model was proposed to explain this observation, based on mechanisms that acid chloride is concentrated in the tube/support plate crevices. The model is expressed by the following equation for empty heated crevices: Good agreement was obtained by comparing the results predicted by the model with Brown’s data and the present data for empty heated crevices, and with Pathania’s data obtained at high heat flux. Based on the above equation, a model was developed to describe chloride concentration within the crevices versus heat flux for given condenser leakage rates in nuclear steam generators. Results predicted by the model show that a small increase in condenser leakage rates gives a considerable increase in chloride concentration within the crevices.