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Division Spotlight
Human Factors, Instrumentation & Controls
Improving task performance, system reliability, system and personnel safety, efficiency, and effectiveness are the division's main objectives. Its major areas of interest include task design, procedures, training, instrument and control layout and placement, stress control, anthropometrics, psychological input, and motivation.
Meeting Spotlight
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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!
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Latest News
Candidates for leadership provide statements: ANS Board of Directors
With the annual ANS election right around the corner, American Nuclear Society members will be going to the polls to vote for a vice president/president-elect, treasurer, and members-at-large for the Board of Directors. In January, Nuclear News published statements from candidates for vice president/president-elect and treasurer. This month, we are featuring statements from each nominee for the Board of Directors.
J. Sejvar
Nuclear Technology | Volume 36 | Number 1 | November 1977 | Pages 48-55
Radiation Environments in Nuclear Reactor Power Plant | Reactor | doi.org/10.13182/NT77-A31957
Articles are hosted by Taylor and Francis Online.
Operating plant radiation level measurements are important in optimizing the operation of nuclear plant systems and in confirming methods and assumptions used by shield designers and must be evaluated to aid in improving future plant designs. In addition, the anticipated long-term radiation fields to which reactor components are subjected are an important consideration in materials selection and/or placement. Radiation level measurements obtained from various pressurized water reactor plants show a wide range of measured dose rates, both in certain areas of the plant (e.g., containment operating deck) and near various components. In some cases, the differences can be explained based on variations in plant layout and shielding configuration, extent of fuel cladding failures, etc., but in many cases, the reported values lack sufficient detail and appropriate explanatory information to correctly interpret the data. The measurements that have been accumulated and correlated thus far are being used to confirm the assumptions and models currently being employed by the shield designers and have led to system and equipment design improvements.