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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
BREAKING NEWS: Trump issues executive orders to overhaul nuclear industry
The Trump administration issued four executive orders today aimed at boosting domestic nuclear deployment ahead of significant growth in projected energy demand in the coming decades.
During a live signing in the Oval Office, President Donald Trump called nuclear “a hot industry,” adding, “It’s a brilliant industry. [But] you’ve got to do it right. It’s become very safe and environmental.”
K. Schleisiek, J. Aberle, Ch. Homann, I. Schmuck, W. Maschek, A. Rahn, O. Romer, L. Schmidt, L. Borms, A. Verwimp
Nuclear Science and Engineering | Volume 128 | Number 2 | February 1998 | Pages 93-143
Technical Paper | doi.org/10.13182/NSE98-A1949
Articles are hosted by Taylor and Francis Online.
The aim of the Mol-7C experiments has been to investigate local cooling disturbances in mixed-oxide fuel assemblies of liquid-metal-cooled reactors. The tests were carried out in the BR2 reactor at Mol, Belgium, within the framework of a joint program of Forschungszentrum Karlsruhe and Studiecentrum voor Kernenergie/Centre d'Etude de l'Energie Nucléaire Mol, with the partial support of the Joint Research Centre, Ispra. The test sections consisted of bundles of up to 30 fuel pins with burnups of between 0.1 and 10 at.%. The cooling disturbances were simulated by porous local blockages that were dimensioned such that local coolant boiling temperatures were attained inside the blockage as initial fault conditions. In all the tests, this disturbance led to loss of coolability and severe fuel pin damage; however, its extent and timescales differed significantly, with the burnup of the fuel pins being identified as the dominating parameter. At low burnup, the damage was limited to the blockage zone, and irradiation could be continued at full power. At high burnup, a stepwise further progression of the damage from the blockage into the bundle occurred. The main conclusion from the experiments is that local faults of the Mol-7C type and size in irradiated subassemblies are not self-limiting and require active protection measures, i.e., detection and shutdown. Delayed neutron (DN) detection was determined to be an efficient method to detect this kind of fault: In all the tests, immediately after the start of the damage, DN signals were recorded that were much higher than needed for reliable fault detection. This means that if a similar fault were to occur in a reactor core, detection by DN and shutdown would be possible before a dangerous situation would develop.