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
2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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
Oct 2025
Jul 2025
Latest Journal Issues
Nuclear Science and Engineering
November 2025
Nuclear Technology
October 2025
Fusion Science and Technology
Latest News
OECD NEA meeting focuses on irradiation experiments
Members of the OECD Nuclear Energy Agency’s Second Framework for Irradiation Experiments (FIDES-II) joint undertaking gathered from September 29 to October 3 in Ketchum, Idaho, for the technical advisory group and governing board meetings hosted by Idaho National Laboratory. The FIDES-II Framework aims to ensure and foster competences in experimental nuclear fuel and structural materials in-reactor experiments through a diverse set of Joint Experimental Programs (JEEPs).
P. Bhaskar Rao, Om Pal Singh
Nuclear Technology | Volume 75 | Number 2 | November 1986 | Pages 193-195
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT86-A33861
Articles are hosted by Taylor and Francis Online.
An extension of previous work, the study examines the implications of the approximation that the fuel vapor and liquid temperatures remain equal during the transient. Modified mathematical formulations for calculating the transient fuel vapor temperatures separately are provided as well as the results of calculations of the dynamics of fuel vapor pressure buildup during transient heating in voided liquid-metal fast breeder reactor cooling channels by dispensing with the above approximation. The results with and without the approximation are compared with each other. The study indicates that, although the fuel vapor temperatures lag the liquid-fuel temperatures, the fuel vapor pressure buildup is relatively less sensitive to this lag. The use of the above approximation results in an overprediction of the transient vapor pressure by <10%.