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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
Meeting Spotlight
2024 ANS Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
Standards Program
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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New laws offer nuclear industry incentives for existing power plant uprates
This year, the U.S. nuclear industry received a much-needed economic boost that could help preserve operating nuclear power plants and incentivize upgrades that extend their lifespan and power output.
Signed into law in 2022, the Inflation Reduction Act offers production tax credits (PTCs) for existing nuclear power plants and either PTCs or investment tax credits (ITCs) for new carbon-free generation. These credits could make power uprates—increasing the maximum power level at which a commercial plant may operate—a much more appealing option for utilities.
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.