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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
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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February 2024
Latest News
Lightbridge announces first U-Zr fuel rod samples extruded at INL
Lightbridge Corporation announced today that it has reached “a critical milestone” in the development of its extruded solid fuel technology. Coupon samples using an alloy of zirconium and depleted uranium—not the high-assay low-enriched uranium (HALEU) that Lightbridge plans to use to manufacture its fuel for the commercial market—were extruded at Idaho National Laboratory’s Materials and Fuels Complex.
Keitaro Kondo, Isao Murata, Axel Klix, Klaus Seidel, Hartwig Freiesleben
Nuclear Technology | Volume 168 | Number 3 | December 2009 | Pages 591-595
Nuclear Data | Special Issue on the 11th International Conference on Radiation Shielding and the 15th Topical Meeting of the Radiation Protection and Shielding Division (PART 3) / Radiation Measurements and Instrumentation | doi.org/10.13182/NT09-A9274
Articles are hosted by Taylor and Francis Online.
For the International Thermonuclear Experimental Reactor (ITER), the European Union intends to introduce a test blanket module using liquid lithium lead. In the present study, a preliminary experiment was conducted using a LiAl/Pb assembly, which has a neutronics performance similar to lithium lead. The neutron spectrum at the inside of the assembly was measured with an NE-213 detector. We found that the spectra calculated with MCNP5 and JENDL-3.3 underestimate the 14-MeV peak by no less than 30%, while ENDF/B-VII.0 and JEFF-3.1 gave good agreement. The neutron nuclear data of lead stored in JENDL-3.3 may have some problems.