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.
Explore membership for yourself or for your organization.
Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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
Sep 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
September 2025
Nuclear Technology
Fusion Science and Technology
August 2025
Latest News
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The 2025 edition is a reinvigoration of the withdrawn ANS-54.8-1988 of the same title.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.
P. K. Kuroda, M. P. Menon
Nuclear Science and Engineering | Volume 10 | Number 1 | May 1961 | Pages 70-74
Technical Paper | doi.org/10.13182/NSE61-A25932
Articles are hosted by Taylor and Francis Online.
The occurrence of a number of fission products in pitchblende and in nonirradiated natural and depleted U salts with 10-4 dis/sec/g-U, was recently reported by Kuroda and co-workers. The following nuclides were detected: Sr89, 90, 91, 92, Mo99, I131, 132, 133, 134, 135, and Ba140. These fission products are formed predominantly by the spontaneous fission of U238, and it is possible to obtain the general shape of the mass-yield curve for the spontaneous fission of U238 from the equilibrium activities of the fission products found in nonirradiated U salts. The spontaneous fission half-life of U238 can also be calculated from these data. Radiochemical procedures have been developed for the determination of each fission product, in which a quantity ranging from 0.1 to 1 disintegration/sec of the fission product activity is isolated from kilogram quantities of U salts, purified, and then counted. Where the half-life of the fission product was several months, U minerals instead of U salts, were used. Removal of the bulk of the U by a liquid extraction method was found to be necessary and/or advantageous in most cases, although it was possible to precipitate certain fission products directly from a concentrated solution of the U salts. A new procedure is currently under investigation for the isolation and quantitative determination of the isotopes of Ce by a liquid-liquid extraction method. Ce(IV) can be extracted from a 10 M HNO3 solution by a 1 to 4 mixture of TBP and CCl4 with high extraction efficiency, and further purified by a combination of oxidation-reduction and liquid-liquid extraction procedures.
