ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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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
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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!
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Survey says . . . Emotional intelligence important in nuclear industry
The American Nuclear Society’s Diversity and Inclusion in ANS (DIA) Committee hosted a workshop social at the 2024 Winter Conference & Expo in November that brought dozens of attendees together for an engaging—and educational—twist on the game show Family Feud.
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.