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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
Oklo completes end-to-end demonstration of advanced fuel recycling
Oklo Inc. has announced that it has completed the first end-to-end demonstration of its advanced fuel recycling process as part of an ongoing $5 million project in collaboration with Argonne and Idaho National Laboratories. Oklo’s goal: scaling up its fuel recycling capabilities to deploy a commercial-scale recycling facility that would increase advanced reactor fuel supplies and enhance fuel cost effectiveness for its planned sodium fast reactors.
Anna A. Afanasieva, Evgeniy V. Burlakov, Alexander V. Krayushkin, Andre V. Kubarev
Nuclear Technology | Volume 103 | Number 1 | July 1993 | Pages 1-9
Technical Paper | Fission Reactor | doi.org/10.13182/NT93-A34825
Articles are hosted by Taylor and Francis Online.
When the causes of the accident at Chernobyl Unit 4 on April 26, 1986, were studied, particular attention was given to the positive void reactivity coefficient and the dynamic characteristics of the shutdown system. The role of these factors in the development of the accident is discussed. The physical nature of the void reactivity coefficient is considered. Safety measures added to the remaining RBMK-type reactors are described. These measures include installation of 80 stationary neutron absorbers in the core to decrease the void reactivity coefficient as well as modification of the absorber rods. The results of reactor parameter measurements after these measures were implemented are presented. The calculation methods are outlined, and the changes in the neutron physics characteristics after the Chernobyl accident are described. The measures taken to improve the safety of RBMK reactors preclude the possibility of another accident of the Chernobyl type. Possible further improvements in the operation of an RBMK reactor are discussed.