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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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Seconds Matter: Rethinking Nuclear Facility Security for the Modern Threat Landscape
In today’s rapidly evolving threat environment, nuclear facilities must prioritize speed and precision in their security responses—because in critical moments, every second counts. An early warning system serves as a vital layer of defense, enabling real-time detection of potential intrusions or anomalies before they escalate into full-blown incidents. By providing immediate alerts and actionable intelligence, these systems empower security personnel to respond decisively, minimizing risk to infrastructure, personnel, and the public. The ability to anticipate and intercept threats at the earliest possible stage not only enhances operational resilience but also reinforces public trust in the safety of nuclear operations. Investing in such proactive technologies is no longer optional—it’s essential for modern nuclear security.
R. G. Alsmiller, Jr., J. Barish
Nuclear Technology | Volume 33 | Number 3 | May 1977 | Pages 318-321
Technical Note | Material | doi.org/10.13182/NT77-A31794
Articles are hosted by Taylor and Francis Online.
Calculated results are presented of the variation with position in the experimental volume of a Li(D,n) neutron radiation damage facility of the damage energy and helium and hydrogen production in copper and in niobium when this volume is partially filled with experimental samples. At a given position in the experimental volume for either copper or niobium, the ratio of the damaged energy with no absorber to the damaged energy with a 50-mm-thick iron absorber or a 100-mm-thick carbon absorber is never >3 and in most positions is <2. The neutron nonelastic cross-section data at the higher energies (>15 to 20 MeV) needed to carry out the transport calculations were obtained from the intranuclear-cascade model of nuclear reactions.