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
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
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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Nuclear Science and Engineering
February 2025
Nuclear Technology
January 2025
Fusion Science and Technology
Latest News
When your test capsule is the test: ORNL’s 3D-printed rabbit
Oak Ridge National Laboratory has, for the first time, designed, printed, and irradiated a specimen capsule—or rabbit capsule—for use in its High Flux Isotope Reactor (HFIR), the Department of Energy announced on January 15.
Alex Galperin
Nuclear Science and Engineering | Volume 86 | Number 1 | January 1984 | Pages 112-115
Technical Note | doi.org/10.13182/NSE84-A17976
Articles are hosted by Taylor and Francis Online.
An alternative method of thorium utilization in light water reactors (LWRs) is proposed. The main idea of the proposed concept is to apply a different fuel management scheme for the neutron-producing part of the core, the uranium seed, and for the neutron-absorbing part of the core, the thorium blanket. An example of the specific design based on this concept was analyzed, and preliminary evaluation indicated the potential of significant savings in uranium consumption. The fuel cycle of the proposed concept includes reprocessing and re-fabrication of uranium fuel only, without separation of plutonium and 233U isotopes. Such a fuel cycle offers higher proliferation resistance compared with the LWR recycle mode of operation or the light water breeder reactor fuel cycle. Finally, the feasibility of the reactor design based on the proposed concept may be established after detailed thermal-hydraulic analysis and study of the irradiation behavior of the thorium-based fuel.