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Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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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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Latest News
NRC v. Texas: Supreme Court weighs challenge to NRC authority in spent fuel storage case
The State of Texas has not one but two ongoing federal court challenges to the Nuclear Regulatory Commission that could, if successful, turn decades of NRC regulations, precedent, and case law on its head.
T. R. Herold
Nuclear Technology | Volume 14 | Number 3 | June 1972 | Pages 269-278
Technical Paper | Radioisotope | doi.org/10.13182/NT72-A31116
Articles are hosted by Taylor and Francis Online.
A new electronic method has been developed that requires about 10 min to assay 252Cf sources between 1 μg and 50 mg. The assay is made by placing the 252Cf source in the center of a polyethylene moderator and measuring the resulting thermalized neutrons with fission counters in the moderator. All measurements are referenced to a 252Cf calibrated with a manganese sulfate bath by the National Bureau of Standards. Sources smaller than 1 μg and larger than 50 mg could be similarly assayed with appropriate modifications to the moderator. The new method is routinely compared with the manganese bath method to determine the precision and sensitivity of the measurements so that the new method can be used as a secondary standard. Measurements of 252Cf content agree with manganese sulfate bath determinations to within ±0.6%. The present design is tailored for a fission neutron spectrum but could be used with proper calibration in assaying between 106 and 1011 n/sec from sources having different spectra.