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
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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
Apr 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
June 2025
Nuclear Technology
Fusion Science and Technology
May 2025
Latest News
Ariz. governor vetoes “fast track” bill for nuclear
Gov. Katie Hobbs put the brakes on legislation that would have eliminated some of Arizona’s regulations and oversight of small modular reactors, technology that is largely under consideration by data centers and heavy industrial power users.
B. W. LeTourneau, M. E. Gavin, S. J. Green
Nuclear Science and Engineering | Volume 54 | Number 2 | June 1974 | Pages 214-232
Technical Note | doi.org/10.13182/NSE74-A23411
Articles are hosted by Taylor and Francis Online.
Critical heat flux and pressure drop tests were run with vertical upflow of water parallel to 20-rod bundles of rods at 1200 to 2000 psia and mass velocities from 0.15 × 106 to 3.0 × 106 lb/(h ft2). The heated rods were 0.75-in. o.d. × 94-in. heated length, spaced by warts in a 5 × 4 array on a 0.765-in. equilateral-triangular pitch in a rhombic shroud box. Tests were run both with all rods uniformly heated and with a linear-transverse heat-flux distribution, with and without protrusions to minimize the effect of large peripheral channels.