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
Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
Takao Hayashi
Nuclear Technology | Volume 78 | Number 3 | September 1987 | Pages 216-226
Technical Paper | Fission Reactor | doi.org/10.13182/NT87-A15987
Articles are hosted by Taylor and Francis Online.
The heat transport capability of the steam generator (SG) in a high-temperature gas-cooled reactor (HTGR) is compared with SGs in other reactor types, for example, in gas-cooled reactors, pressurized water reactors, and liquid-metal fast breeder reactors (LMFBRs). The comparison is done in the form of q = Q/A (kW/m2), where Q is the reactor thermal output (in kilowatts) and A is the total heat transfer area (in square metres) of the SG. It is found that the HTGR SG has unexpectedly excellent characteristics, in spite of the low expectations of the gas-heating SG. In the area of heat transport capability, the HTGR SG is by no means inferior to (and may be superior to) light water reactors and LMFBRs. The reasons for this are explained and analyzed. The q value directly affects the design of the SG and the reactor, thus having a great impact on the cost of the plant. The greater q value of the HTGR SG lends optimistic views on the economics, at least on the HTGR SG design.