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.
Explore membership for yourself or for your organization.
Conference Spotlight
2026 Nuclear Energy Conference & Expo (NECX)
August 24–27, 2026
Dallas, TX|Hilton Anatole
Latest Magazine Issues
Jul 2026
Jan 2026
2026
Latest Journal Issues
Nuclear Science and Engineering
September 2026
Nuclear Technology
August 2026
Fusion Science and Technology
Latest News
NRC accepts Ginna SLR application as Constellation seeks 20-year extension
The Nuclear Regulatory Commission has accepted Constellation’s subsequent license renewal application to extend operations at the Ginna nuclear power plant by another 20 years.
If approved, the Ontario, N.Y., facility’s operating license would be extended through September 18, 2049. The plant was first issued a 40-year license in 1969, followed by a 20-year renewal in 2004 that extended the license into 2029.
Samuel H. Levine
Nuclear Technology | Volume 53 | Number 3 | June 1981 | Pages 303-325
Technical Paper | Nuclear Fuel Cycle Education Module / Education | doi.org/10.13182/NT81-A32641
Articles are hosted by Taylor and Francis Online.
This educational module utilizes techniques used to calculate the core reactivity, power distribution, and isotopic inventory for the first and subsequent cores of a nuclear power plant to maintain adequate safety margins and operating lifetime for each core. Some reloading schemes studied minimize energy costs. The module is written more for classroom presentation and self-study by students than for the practicing nuclear engineer; however, the first two sections cover in-core fuel management in a way that should be helpful to a utility manager having the purview of core analysis. The major emphasis is on light water reactors, but in-core fuel management for the high temperature gas-cooled reactor and the liquid-metal fast breeder reactor is included. The module involves detailed information on the systematic application of nucleonic codes, e.g., cross-section generating codes and nodal and diffusion theory multigroup codes, to calculate the depletion and reloading of nuclear power reactors. It is not intended to be a reactor physics text, but detailed derivations of formulas, e.g., the B1 approximation in LEOPARD, FLARE recursion formula, used in the relevant nucleonic codes, are given in greater detail than normally found in a text to eliminate the “black box” use of computer codes.