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
Jun 2026
Jan 2026
2026
Latest Journal Issues
Nuclear Science and Engineering
July 2026
Nuclear Technology
June 2026
Fusion Science and Technology
May 2026
Latest News
Spent fuel recycling and conditioning topic of U.S.-Japan meeting
Officials with the Department of Energy’s Office of Environmental Management discussed spent nuclear fuel recycling and conditioning with counterparts from Japan during the 13th U.S.-Japan Technical Meeting of the Civil Nuclear Energy Research and Development Working Group, held recently in Santa Fe, N.M.
Jean Johner
Fusion Science and Technology | Volume 59 | Number 2 | February 2011 | Pages 308-349
Technical Paper | doi.org/10.13182/FST11-A11650
Articles are hosted by Taylor and Francis Online.
The HELIOS zero-dimensional code (Version 1.0) is described in detail in the case of deuterium-tritium (D-T) plasmas.The part of the code described solves in a self-consistent way the thermal equilibrium equation of a D-T thermonuclear plasma coupled to the conservation equation of the helium ash with a He*/E = const. constraint.Prominent features of the modeling are the following: description of any type of last closed magnetic surface (LCMS) by means of four portions of conics; exact closed form expressions for the poloidal surface, plasma volume, plasma surface, and LCMS length; exact surface and volume integration (for arbitrary aspect ratio) in the approximation of magnetic surfaces similar to the LCMS; parabolic type density profile and two-parameters temperature profile, both with pedestals and finite values at the separatrix; line radiation of light impurities calculated from tabulated radiative power loss functions; scalings for the pedestal temperature, L-H transition, and confinement time; modeling for the divertor thermal load; self-consistent radial build modeling for the plateau duration calculation; and detailed power plant thermal balance.Applications to ITER and DEMO operation and to inductive reactor design are given.