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Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
Materials in Nuclear Energy Systems (MiNES 2023)
December 10–14, 2023
New Orleans, LA|New Orleans Marriott
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From the pages of Nuclear News: Industry update November 2023
Here is a recap of industry happenings from the recent past:
Centrus-Oklo partnership expands
Oklo, a California-based developer of next-generation fission reactors, has expanded its partnership with Centrus Energy, a Maryland-based supplier of nuclear fuel and services. The two companies have been cooperating since 2021 on the development of Centrus’s American Centrifuge Plant in Piketon, Ohio, to produce high-assay low-enriched uranium (HALEU) fuel. According to the companies’ new memorandum of understanding, Centrus will manufacture certain components for Oklo’s Aurora “powerhouse” reactor, a fast neutron reactor designed to generate up to 15 MW of power and operate for at least 10 years without refueling. The Aurora is also designed to produce usable heat. Centrus also has agreed to purchase electricity generated by the Aurora reactors, while Oklo has agreed to purchase HALEU fuel from the Piketon facility. The facility is expected to begin fuel production before the end of the year.
Antti Räty, Tommi Kekki, Merja Tanhua-Tyrkkö, Tiina Lavonen, Emmi Myllykylä
Nuclear Technology | Volume 203 | Number 2 | August 2018 | Pages 205-220
Technical Paper | doi.org/10.1080/00295450.2018.1445402
Articles are hosted by Taylor and Francis Online.
The objective of the study has been to verify the calculated residual activity in the decommissioning waste of the TRIGA Mark II–type research reactor FiR 1 in Finland. Knowledge of the radioactive inventory of irradiated materials is important in the planning of decommissioning activities and is essential for predicting the radiological impact to personnel and the environment. Measurements are performed for low active material samples from outer parts of the reactor. Methods include gamma spectrometric measurements, composition measurements with mass spectrometry, oxidation measurements of especially 14C in graphite, and full combustion measurements of lithium-enriched shielding materials. Results are compared to estimates calculated with a combined Monte Carlo model of the reactor and a point-depletion code modeling the irradiation history. Decommissioning waste consists mainly of ordinary concrete, aluminum, steel, and graphite parts. Only preliminary measurements of low active samples are reported so far, but the same methods will be used later for characterizing and classifying dismantling waste. Some discussion of characterization requirements and future sampling is also included.