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Aerospace Nuclear Science & Technology
Organized to promote the advancement of knowledge in the use of nuclear science and technologies in the aerospace application. Specialized nuclear-based technologies and applications are needed to advance the state-of-the-art in aerospace design, engineering and operations to explore planetary bodies in our solar system and beyond, plus enhance the safety of air travel, especially high speed air travel. Areas of interest will include but are not limited to the creation of nuclear-based power and propulsion systems, multifunctional materials to protect humans and electronic components from atmospheric, space, and nuclear power system radiation, human factor strategies for the safety and reliable operation of nuclear power and propulsion plants by non-specialized personnel and more.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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Norway’s Halden reactor takes first step toward decommissioning
The government of Norway has granted the transfer of the Halden research reactor from the Institute for Energy Technology (IFE) to the state agency Norwegian Nuclear Decommissioning (NND). The 25-MWt Halden boiling water reactor operated from 1958 to 2018 and was used in the research of nuclear fuel, reactor internals, plant procedures and monitoring, and human factors.
Per Knudsen, Carsten Bagger, Hans Carlsen, Ib Misfeldt, Mogens Mogensen
Nuclear Technology | Volume 72 | Number 3 | March 1986 | Pages 258-267
Technical Paper | Radiation Protection and Health Physics Practices and Experience in Operating Reactors Internationally / Fission Reactor | doi.org/10.13182/NT86-A33765
Articles are hosted by Taylor and Francis Online.
Data are presented on fission gas release for UO2-Zr fuel pins that were subjected to slow power increases late in life. These tests were performed with fuel pins that had been previously irradiated to average burnups of 27000 to 35000 MWd/ton U (peak pellet 43 700 MWd/ton U). The subsequent power increases were to 301 to 444 W/cm (peak pellet), and the hold time was 24 h, with one test at 72 h. Emphasis was given to extensive axially and radially local measurements, rather than to integral pin data. Cross-sectional releases increased with transient powers above 350 W/cm; at 415 W/cm they seemed to saturate at 40 to 45 % within 24 h. Radially local releases started at calculated local temperatures at ∼700°C, reaching a constant level of 90 to 95% above 1100°C. Local swelling appeared to begin at ∼650 to 700°C, with maximum swelling levels at 10%. From the observed transient release data, an effective diffusion coefficient could be calculated that was more than three orders of magnitude higher than commonly accepted values.