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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.
Seung Min Baek, Hee Cheon No, In Yong Park
Nuclear Technology | Volume 74 | Number 3 | September 1986 | Pages 260-266
Technical Paper | Fission Reactor | doi.org/10.13182/NT86-A33828
Articles are hosted by Taylor and Francis Online.
A nonequilibrium three-region model is developed for the accurate prediction of the pressure in the pressurizer under both transient and accident conditions. The mathematical model derived from the general conservation equations includes all of the important thermal-hydraulics processes occurring in the pressurizer: bulk flashing and condensation, wall condensation, and interfacial heat and mass transfer, etc. The Stanton number for the interfacial heat transfer coefficient is obtained by fitting the experimental results in terms of the surge rate. The bubble rising and rain-out models are developed to describe bulk flashing and condensation, respectively. To obtain the wall condensation rate, a one-dimensional heat conduction equation is solved by the pivoting method. The mathematical model is numerically solved by the back substitution and successive iteration method for fast convergence and stability. For verification, several numerical tests are done on a mild transient in the Shippingport nuclear power plant, an experimental test done at the Massachusetts Institute of Technology, and the Three Mile Island accident. It is proved that predicted results are in better agreement with experimental tests than those by previous models. Sensitivity analysis is done to see the effect of each model on the behavior of the pressurizer. Discrepancy between results predicted with the three- and the tworegion models becomes apparent in an outsurge after insurge transient. Although the interfacial heat transfer of the pressurizer can be neglected in the case of the high water level, it becomes one of the most dominant processes in the low level. The wall condensation rate becomes important with an increase in pressure due to an insurge transient.