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The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
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Orlando, FL|Renaissance Orlando at SeaWorld
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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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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.
Ji Bok Lee, Byong Whie Lee, Byung Chul Lee
Nuclear Science and Engineering | Volume 121 | Number 2 | October 1995 | Pages 334-344
Technical Paper | doi.org/10.13182/NSE95-A28569
Articles are hosted by Taylor and Francis Online.
A radiation streaming analysis for the radial and tangential beam tubes of a 250-kW TRIGA reactor was performed using the MCNP-MCNP coupling method. The measurements of the neutron flux and dose rate in the beam tubes were also conducted using gold-aluminum foils and thermoluminescent dosimeters. When compared with the experimental results, the calculated thermal neutron flux reproduces the measurement well, i.e., within 2 to 90%. The calculated nonthermal neutron and gamma-ray dose rates show about the same distribution along the beam tube as the measurements. For the neutron dose rate, there is a big discrepancy between the calculation and the measurement for the radial beam tube but good agreement for the tangential tube. The calculational method using MCNP-MCNP coupling, which is used here, may well be applicable to analyzing the particle streaming phenomena in the beam tube of a research reactor. The beam characteristics of the radial and tangential tubes were investigated based on MCNP calculations. The thermal neutron fluxes are about the same in both beam tubes, but the ratios of the thermal-to-nonthermal neutron flux and the thermal neutron-to-gamma-ray flux in the tangential beam tube increase from only 12% and 18% higher at the nose to 2.4 times and 2.8 times higher at 130 cm from the nose, respectively, compared with those for the radial tube. Thus, the tangential beam tube gives a better neutron beam quality, i.e., the same thermal neutron flux and lower nonthermal neutron and gamma-ray fluxes at the tangential beam tube exit as compared with the radial one.