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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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Proving DRACO will deliver
The United States is now closer than it has been in over five decades to launching the first nuclear thermal rocket into space, thanks to DRACO—the Demonstration Rocket for Agile Cislunar Orbit.
K. Ilieva, S. Belousov, T. Apostolov
Nuclear Science and Engineering | Volume 131 | Number 2 | February 1999 | Pages 282-285
Technical Paper | doi.org/10.13182/NSE99-A2035
Articles are hosted by Taylor and Francis Online.
The verification of calculated neutron fluence onto the VVER-440/230 pressure vessel is a very timely task, especially considering that some of these reactors have been operating for the major part of the reactor design lifetime. Since the induced activity from the neutron irradiation onto the elements is a simple response of neutron flux, the neutron fluence verification usually is done using the measured activity of radionuclides produced during reactor operation.Calculational and experimental results are presented for 54Mn-induced activity of scraps from the inner wall of the Unit 1 reactor pressure vessel after the 18th cycle and from detectors irradiated behind the vessel during the 18th cycle of Unit 1 at Kozloduy Nuclear Power Plant as well as activity attenuation through the VVER-440/230 pressure vessel.Neutron cross-section libraries generated on the basis of ENDF/B-IV and ENDF/B-VI have been used in the calculations. The comparative analysis of evaluated activities and the attenuation coefficient demonstrates that the neutron fluence calculations by the libraries based on ENDF/B-VI are more reliable than ones based on ENDF/B-IV.The extreme rarity of data for the activity of scraps from the VVER-440 reactor vessel and its combination with the data for the detectors irradiated behind the vessel makes them especially attractive for verification of calculational methods of neutron fluence onto the VVER-440 vessel with dummy cassette loading.