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2026 Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
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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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Nuclear power’s new rule book: Managing uncertainty in efficiency, safety, and independence
The U.S. nuclear industry is standing at its most volatile regulatory moment yet—one that will shape the trajectory and the safety of the industry for decades to come. Recent judicial, legislative, and executive actions are rewriting the rules governing the licensing and regulation of nuclear power reactors. Although these changes are intended to promote and accelerate the deployment of new nuclear energy technologies, the collision of multiple legal shifts—occurring simultaneously and intersecting with profound technological uncertainties—is overwhelming the Nuclear Regulatory Commission and threatening to destabilize investor and industry expectations.
Aamir Husain, Calvin E. Breckenridge, David Storey
Nuclear Technology | Volume 109 | Number 2 | February 1995 | Pages 265-274
Technical Paper | Reactor Operation | doi.org/10.13182/NT95-A35059
Articles are hosted by Taylor and Francis Online.
An in situ pipe gamma spectrometry technique was applied to determine the activity within piping during various stages of CANDU reactor decontaminations. Measurements were performed in general radiation fields up to ∼500 mR/h and required both the detector and the pipe being scanned to be appropriately shielded from other neighboring piping. Measured counts were interpreted using a pipe source efficiency calibration with due regard to its distance dependence. Cobalt-60 was the dominant radionuclide on the piping before the decontamination. Deposition of I24Sb occurred on out-core piping surfaces during the decontamination. The spectrometry measurements were supplemented with contact radiation field measurements, which were performed using survey detectors housed within specially designed pipe shields. Radiation fields estimated from measured radionuclide activities were compared with the measured radiation fields. On average, the ratio of measured to estimated fields was ∼72%. Reasons for this discrepancy are discussed.