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.
Explore membership for yourself or for your organization.
Conference Spotlight
2026 ANS Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
Latest Magazine Issues
Mar 2026
Jan 2026
Latest Journal Issues
Nuclear Science and Engineering
March 2026
Nuclear Technology
February 2026
Fusion Science and Technology
April 2026
Latest News
ANS, UCOR sign MOU for workforce development program
The American Nuclear Society and United Cleanup Oak Ridge have signed a memorandum of understanding that establishes a framework for collaboration to advance ANS workforce training and certification programs serving the nuclear industry.
According to the document, UCOR will provide “operational insights and subject matter expertise to inform ANS’s professional development and credentialing offerings, including the Certified Nuclear Professional [CNP] program.” The collaboration will strengthen UCOR’s workforce development efforts while advancing ANS’s mission to sustain and expand the national nuclear workforce pipeline and capabilities.
G. Jansen, D. D. Stepnewski
Nuclear Technology | Volume 17 | Number 1 | January 1973 | Pages 85-95
Technical Note | Fuel | doi.org/10.13182/NT73-A31259
Articles are hosted by Taylor and Francis Online.
The hypothetical accident approach to analysis of fast reactors has been applied to the meltdown of an entire core and its interaction with containment floor materials of construction. The objective has been to show that penetration can be limited by the use of low melting point fluxing materials and thermal insulation at the pool boundaries. The growth of a hemispherical molten pool composed of fuel dissolved in molten basalt is predicted by a model that includes fuel solubility, internal convection in the pool, and transient conduction into the surrounding solid. Core sizes ranging from 3000 to 20 000 kg were investigated. Tentative conclusions are: A molten pool formed by reactor fuel debris can be shown to reach a manageable limiting size rather than penetrating to an indefinite distance in an uncontrolled manner. The use of sacrificial materials in which fuel is soluble reduces pool temperatures by diluting fission product decay heat generators and increasing heat transfer surface. During the first 100 to 200 h after meltdown the storage of heat in the molten pool can reduce the fission product heat that appears in the overlying sodium pool by 50 to 75%, The use of refractory insulation can reduce the pool size and still maintain temperatures beyond the refractory boundaries at values compatible with ordinary containment structural materials.