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 Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
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
Dec 2025
Jul 2025
Latest Journal Issues
Nuclear Science and Engineering
January 2026
Nuclear Technology
December 2025
Fusion Science and Technology
November 2025
Latest News
Bechtel-led SIMCO awarded three-year WIPP contract extension
The Department of Energy has issued a three-year contract extension to Salado Isolation Mining Contractors (SIMCO), a single-purpose entity comprising Bechtel National and Los Alamos Technical Associates as a teaming contractor, for the continued management and operations of the Waste Isolation Pilot Plant, the DOE’s geologic repository for defense-generated transuranic waste in southeastern New Mexico.
H.C. No, M. S. Kazimi
Nuclear Science and Engineering | Volume 97 | Number 4 | December 1987 | Pages 327-343
Technical Paper | doi.org/10.13182/NSE87-A23516
Articles are hosted by Taylor and Francis Online.
This work involves the development of physical models for the constitutive relations of a two-fluid, three-dimensional sodium boiling code, THERMIT-6S. Based on a simplified flow regime, namely, concurrent annular flow, constitutive relations for two-phase flow of sodium are derived. The wall heat transfer coefficient is based on momentum-heat transfer analogy and a logarithmic law for liquid film velocity distribution. Mass and energy exchanges are modeled by generalization of the turbulent flux concept. Interfacial drag coefficients are derived for annular flows with entrainment. Code assessment is performed by simulating the W-7b’ test for a low-flow, high-power accident in the liquid-metal fast breeder reactor. While the numerical results for predryout are in good agreement with the data, those for postdryout reveal the need for improvement of the physical models. The benefits of nonhomogeneous, nonequilibrium representation of sodium boiling are studied.