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The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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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Fusion Science and Technology
Latest News
Christmas Night
Twas the night before Christmas when all through the houseNo electrons were flowing through even my mouse.
All devices were plugged in by the chimney with careWith the hope that St. Nikola Tesla would share.
Owen N. Jarvis, Edward W. Clipsham, Malcolm A. Hone, Brian J. Laundy, Mario Pillon, Massimo Rapisarda, Guy J. Sadler, Pieter van Belle, Karl A. Verschuur
Fusion Science and Technology | Volume 20 | Number 3 | November 1991 | Pages 265-284
Technical Paper | Experiment Device | doi.org/10.13182/FST91-A29668
Articles are hosted by Taylor and Francis Online.
The time dependence of the 2.5-MeV neutron emission from the Joint European Torus (JET) is reliably measured using fission chambers. The absolute calibration of these chambers is required to an accuracy of 10% or better for a range of intensities that may cover six or more decades. At JET, this calibration is now achieved by use of activation techniques, the most convenient of which involves fissionable materials (thorium and uranium) and delayed neutron counting. Because delayed neutron counting is unfamiliar in the fusion community, particular care is taken to obtain confirmation of the results based on this method by comparison with measurements made using the conventional activation procedure (involving indium, nickel, and zinc as target materials). As the activation measurements can be influenced appreciably by the weak emission of 14-MeV neutrons, this contribution is measured separately using high threshold energy activation reactions (in copper and silicon). Neutron transport calculations are employed to relate the measured local fluences of both 2,5- and 14-MeV neutrons to the total yields from the plasma. Absolute calibration accuracies of 6 and 8% are claimed for 2,5- and 14-MeV neutron yields, respectively; the accuracy of the 14-MeV to 2,5-MeV yield ratios is 6%.