ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
Meeting Spotlight
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott 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
NRC v. Texas: Supreme Court weighs challenge to NRC authority in spent fuel storage case
The State of Texas has not one but two ongoing federal court challenges to the Nuclear Regulatory Commission that could, if successful, turn decades of NRC regulations, precedent, and case law on its head.
M. Coquerelle, J. Gabolde, R. Lesser, P. Werner
Nuclear Technology | Volume 16 | Number 1 | October 1972 | Pages 110-119
Technical Paper | Reactor Materials Performance / Material | doi.org/10.13182/NT72-A31180
Articles are hosted by Taylor and Francis Online.
The European Institute for Transuranium Elements has performed a series of mixed-oxide irradiation experiments in the Dounreay Fast Reactor. The main parameters varied were the O/M ratio of the fuel, radial fuel distribution, and fuel form. Three low burnup experiments with nine pins were terminated in 1969. Eight of the corresponding nine high burnup pins were removed from the reactor subsequently, after several intermediate nondestructive examinations. One pin is further irradiated. Three of the eight pins failed. The Inconel-625 claddings of the sound pins did not change their o.d. at a total neutron dose of 7.3 × 1022 n/cm2. The three pins of the DS-2 experiment, in which fuels with different O/M ratios have been irradiated to a burnup of 7.3 at.%, were examined destructively. A low initial O/M (1.94) led to a negligible attack of the cladding at a maximum temperature of 650°C, whereas fuel of stoichiometric composition corroded severely. No influence of the different O/M on the swelling was detected. The reduction of the O/M ratio to low values seems to increase the risk of central fuel melting.