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Division Spotlight
Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
Meeting Spotlight
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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
DOE issues RFI for a spent fuel consolidated interim storage facility
The Department of Energy’s Office of Nuclear Energy has issued a request for information opportunity for the design and construction of a federal consolidated interim storage facility (CISF) for spent nuclear fuel. The DOE is planning on establishing a federal CISF to manage SNF until a permanent repository is available. In May, the DOE received initial approval, known as “Critical Decision-0,” for such a facility.
The deadline for submissions is September 5.
Bing Hong, Yunqing Bai, Gang Xu, Xiaoliang Zou
Nuclear Technology | Volume 204 | Number 1 | October 2018 | Pages 66-73
Technical Paper | doi.org/10.1080/00295450.2018.1464820
Articles are hosted by Taylor and Francis Online.
Lithium is an attractive coolant for space nuclear reactors due to its good thermal properties and low density. The main objective of this study is to investigate the effect of coolant 6Li concentration on the neutronic parameters of the lithium-cooled space reactor, with the aim to provide an appropriate reference for the purification of lithium coolant and the safety of the lithium-cooled space reactor. The neutronic calculations based on the lithium-cooled reactor are performed using the SuperMC code with the ENDF/B-VII cross-section database. The effects of coolant 6Li concentration were studied over the range of 0 to 8.5 at. % as well as the corresponding effects on the depletion, helium production, neutron spectrum, and temperature reactivity coefficient. The results show that the 6Li concentration of 0.01 at. % in the lithium coolant is appropriate in the lithium-cooled reactor. In this case, the neutronic parameters including the depletion, helium production, and neutron spectrum showed no obvious change compared to that of the pure 7Li, and the coolant reactivity coefficient has a negative effect on reactivity.