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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
Meeting Spotlight
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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
June 2025
Nuclear Technology
Fusion Science and Technology
Latest News
First concrete marks start of safety-related construction for Hermes test reactor
Kairos Power announced this morning that safety-related nuclear construction has begun at the Oak Ridge, Tenn., site where the company is building its Hermes low-power test reactor. Hermes, a scaled demonstration of Kairos Power’s fluoride salt–cooled, high-temperature reactor technology, became the first non–light water reactor to receive a construction permit from the Nuclear Regulatory Commission in December 2023. The company broke ground at the site in July 2024.
Ernie Kee, John Hasenbein, Alex Zolan, Phil Grissom, Seyed Reihani, Zahra Mohaghegh, Fatma Yilmaz, Bruce Letellier, Vera Moiseytseva, Rodolfo Vaghetto, David Imbaratto, Tatsuya Sakurahara
Nuclear Technology | Volume 196 | Number 2 | November 2016 | Pages 270-291
Technical Paper | doi.org/10.13182/NT16-34
Articles are hosted by Taylor and Francis Online.
An approach is described that would use test data to evaluate the risk associated with the concerns raised in Generic Safety Issue 191 (GSI-191). The relationship to the elements of quantitative risk-informed regulation for addressing the concerns raised in GSI-191 in pressurized water reactor (PWR) plant licensing is described. Use of experimental data from a deterministic sump performance test to establish scenario success for tested debris loads is summarized and compared to the licensing requirements in the regulations. Generation and transport of debris to the emergency core cooling system sump from a loss-of-coolant accident is described, and data are shown for a particular PWR. Application of the analysis results to a license amendment for an operating PWR is summarized.
