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Conference Spotlight
2026 ANS 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!
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Latest News
DOE announces awards for three university nuclear education outreach programs
The Department of Energy’s Office of Nuclear Energy has announced more than $590,000 in funding awards to help three universities enhance their outreach in nuclear energy education. The awards, which are part of the DOE Nuclear Energy University Program (NEUP) University Reactor Sharing and Outreach Program, are primarily designed to provide students in K-12, vocational schools, and colleges with access to university research reactors in order to increase awareness of nuclear science, engineering, and technology and to foster early interest in nuclear energy-related careers.
Bahman Zohuri, Stephen Lam, Charles Forsberg
Nuclear Technology | Volume 206 | Number 11 | November 2020 | Pages 1642-1658
Critical Review | doi.org/10.1080/00295450.2019.1681222
Articles are hosted by Taylor and Francis Online.
The fluoride-salt-cooled high-temperature reactor and some proposed fusion reactors use clean fluoride salts as reactor coolants that have melting points above 450°C and generate tritium. Tritium diffuses through most hot metals, thus methods to capture tritium and prevent its release to the environment are required. Molten salt reactors (MSRs) use fluoride or chloride salts with high melting points where the fuel is dissolved in the coolant. MSR systems produce volatile fission products (Xe, Kr, etc.) and some produce significant tritium. We examine the use of heat exchangers with multiple heat pipes for salt-cooled fission and fusion systems that serve four functions: (1) transfer heat from primary coolant to power cycle, secondary loop, or environment; (2) provide the safety function of a secondary loop by isolating the reactor salt coolant from the high-pressure power cycle; (3) stop heat transfer if the reactor coolant approaches its freezing point to prevent blockage of the primary loop; and (4) block tritium escape to the environment with recovery of the tritium. Each of these capabilities in some form has been demonstrated in a heat pipe system, but not all the functions have been demonstrated in a single system because there has been no need for all of these capabilities in a single system. We review the status of heat pipe technology and the limits of heat pipe technology as the starting points for decisions on the development of such heat pipe systems.