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Division Spotlight
Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
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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2024: The Year in Nuclear—July through September
Another calendar year has passed. Before heading too far into 2025, let’s look back at what happened in 2024 in the nuclear community. In today's post, compiled from Nuclear News and Nuclear Newswire are what we feel are the top nuclear news stories from July through September 2024.
Stay tuned for the top stories from the rest of the past year.
David Meneghetti, Dwight A. Kucera
Nuclear Technology | Volume 91 | Number 2 | August 1990 | Pages 139-145
Technical Paper | Safety of Next Generation Power Reactor / Fission Reactor | doi.org/10.13182/NT90-A34423
Articles are hosted by Taylor and Francis Online.
The linear and Doppler feedback components of the regional contributions of the power reactivity decrement (PRD) and of the temperature coefficient of reactivity for a 900-MW(thermal) homogeneous U10Zr-fueled sodium-cooled reactor are calculated. The PRD components are separated into power- and power-to-flow-dependent parts. The values of PRD and temperature coefficient components are compared with corresponding quantities calculated for the Experimental Breeder Reactor II. The implications of these comparisons on inherent safety characteristics of metal-fueled sodium-cooled reactors are discussed.
