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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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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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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College students help develop waste-measuring device at Hanford
A partnership between Washington River Protection Solutions (WRPS) and Washington State University has resulted in the development of a device to measure radioactive and chemical tank waste at the Hanford Site. WRPS is the contractor at Hanford for the Department of Energy’s Office of Environmental Management.
Kazuo Haga, Yoshihiro Kikuchi
Nuclear Technology | Volume 70 | Number 2 | August 1985 | Pages 220-234
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT85-A33646
Articles are hosted by Taylor and Francis Online.
A series of experiments was performed to assess the thermal effect of a burst-type fission gas release from fuel pins. Simulated fission product gas was injected continuously and transiently from the central pin of a 37-pin bundle. The opposite pin surface impinged on by the released gas showed an extreme temperature rise under high coolant-flow conditions. Comparison of measured temperature change data with analytical results by a simple computer code revealed that the ratios of the heat transfer coefficient after gas injection to those of sodium single-phase flow were in the range of 0.05 to 0.15, irrespective of the magnitude of the gas plenum pressure and the nozzle diameter. The estimated pin-surface temperature increased by gas release in actual reactor operating conditions was less than the saturation temperature of sodium. The measured pressure pulse at the transient gas release was <0.2 times the initial gas plenum pressure.