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Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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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.
Paul B. Abramson
Nuclear Science and Engineering | Volume 62 | Number 2 | February 1977 | Pages 195-214
Technical Paper | doi.org/10.13182/NSE77-A26957
Articles are hosted by Taylor and Francis Online.
Subroutine POOL was developed for the study of hypothetical core disruptive accidents in nuclear reactors and, as such, is set up for use as a subroutine in the FX-2 Dynamic Neutronics Code. This combination permits scoping studies of the total neutronic/hydrodynamic interactions and is capable of performing phenomenological investigations of hypothetical problems ranging from the high ramp disassembly calculations, performed in the past by the Lagrangian code VENUS, to the study of recriticality in boiling pools of fuel and steel. POOL specifically includes, in at least parametric fashion, the following phenomena: 1. intra- and inter-element heat transfer by diffusion, convection, and radiation for both fuel and steel inside the pool and at the boundaries 2. local vapor generation and concurrent local pressurization 3. hydrodynamic behavior using the inviscid Navier-Stokes equations in a Eulerian formulation. Sample results are shown for boil-up of an initially quiescent dense pool of fuel and steel. Subroutine POOL was modified by removing the free surface portion of the calculation and the associated expansion of the Eulerian Grid. The combined code, known as FX2-P00L, was used to perform prompt burst calculations for two comparison cases for a lOOO-MW(th) demolike reactor. Good agreement is shown between FX2-POOL and VENUS II for these two hypothetical situations, indicating that the hydrodynamic and thermodynamic assumptions made in POOL are accurate enough for prompt burst analysis and compare well with the VENUS models.