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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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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A new ANSI/ANS standard for liquid metal fire protection published
ANSI/ANS-54.8-2025, Liquid Metal Fire Protection in LMR Plants, received approval from the American National Standards Institute on September 2 and is now available for purchase.
The 2025 edition is a reinvigoration of the withdrawn ANS-54.8-1988 of the same title. The Advanced Reactor Codes and Standards Collaborative (ARCSC) identified the need for a current version of the standard via an industry survey.
Typical liquid metal reactor designs use liquid sodium as the coolant for both the primary and intermediate heat-transport systems. In addition, liquid sodium and NaK (a mixture of sodium and potassium that is liquid at room temperature) are often used in auxiliary heat-removal systems. Since these liquid metals can react readily with oxygen, water, and other compounds, special precautions must be taken in the design, construction, testing, and maintenance of the sodium/NaK systems to ensure that the potential for leakage is very small.
W. W. Godsin
Nuclear Science and Engineering | Volume 8 | Number 4 | October 1960 | Pages 340-345
Technical Paper | doi.org/10.13182/NSE60-A28864
Articles are hosted by Taylor and Francis Online.
An irradiation capsule for high-temperature fuel irradiations has been developed to permit constant temperature control over a range of about ±35% of design power. Control is achieved by the variation in thermal conductivity of a binary gas mixture in a control annulus located between the test specimen and the capsule coolant. For the binary mixture, helium, which is a high-thermal conductivity gas, and a gas of lower conductivity, such as neon, nitrogen, or argon, may be used. The control method is unaffected by time or radiation damage. In-pile operation of capsules using this method of control has demonstrated that the desired temperature may be controlled to within ±25°F automatically, and probably more closely if manually controlled. The automatic control system also protects the capsule from temperature overshoot during a fast reactor recovery following a scram.