ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Division Spotlight
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.
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!
Latest Magazine Issues
Aug 2024
Jan 2024
Latest Journal Issues
Nuclear Science and Engineering
October 2024
Nuclear Technology
Fusion Science and Technology
August 2024
Latest News
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.
P. L. Viollet, J. P. Benque, J. Goussebaile
Nuclear Science and Engineering | Volume 84 | Number 4 | August 1983 | Pages 350-372
Technical Paper | doi.org/10.13182/NSE83-A15456
Articles are hosted by Taylor and Francis Online.
Finite difference numerical methods are available for the computation of unsteady non-isothermal flows with possibly strong buoyancy effects or head loss terms. The algorithm uses either velocity-pressure or velocity-stream-function formulations. The treatment of advective terms involves the method of characteristics. Arbitrary non-orthogonal curvilinear grids may be used, and turbulence is modeled by means of a k-ϵ eddy viscosity model. Two examples of application to liquid-metal fast breeder reactor thermal analysis are: 1. hot plenum flow in a pool-type vessel during flow and thermal transients, 2. unsteady flow in a pipe resulting from an inlet temperature change with a very low flow rate. For both cases, comparisons with experimental studies and applications to real reactors are shown.