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Radiation Protection & Shielding
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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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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
Norway’s Halden reactor takes first step toward decommissioning
The government of Norway has granted the transfer of the Halden research reactor from the Institute for Energy Technology (IFE) to the state agency Norwegian Nuclear Decommissioning (NND). The 25-MWt Halden boiling water reactor operated from 1958 to 2018 and was used in the research of nuclear fuel, reactor internals, plant procedures and monitoring, and human factors.
A. Kumar, Y. Ikeda, C. Konno
Fusion Science and Technology | Volume 19 | Number 3 | May 1991 | Pages 1979-1988
Neutronic | Proceedings of the Ninth Topical Meeting on the Technology of Fusion Energy (Oak Brook, Illinois, October 7-11, 1990) | doi.org/10.13182/FST91-A29632
Articles are hosted by Taylor and Francis Online.
The experimental measurement of nuclear heat deposition rates in a simulated D-T fusion neutron environment has assumed importance due to untested nature of large body of kerma factor libraries. An experimental effort was recently initiated to develop and apply calorimetric technique to measure heat deposition in various materials subjected to D-T neutron fields, in the framework of JAERI/USDOE collaborative program on fusion neutronics. Thermistors and platinum RTD's were employed as thermal sensors within calorimeters made of single materials (or probes). The first experiments were conducted during June 1989 and the tested materials included: Fe, Al, C, Cu. Each of these calorimeters was placed inside a vacuum chamber and the mean distance from the target was ∼8 cm. The calorimeters were subjected to spaced neutron pulses of 3 to 10 min duration. The measured heat deposition rates ranged from 7 to 30 µW/g for a normalized source strength of 1012 n/s-iron and graphite providing the lowest and the highest rates respectively. These single probe experiments were analyzed using 3D code MCNP. The single probe experiments were carried out again in december 1989. This allowed to verify the reproducibility. This time, the average target-probe distance was shortened to ∼5 cm which led to 2 to 3 times higher rates. Tungsten was also included. Ratio of computed (C) to measured (E) rates varied from 0.79 to 1.77 for RMCCS evaluation of MCNP. Four evaluations, available with MCNP, throw up large deviations; For example, C/E for iron for an experiment ranges from 0.40 to 0.94. In addition to single probe experiments, two novel experiments were conducted with multiple probes in separate host media of iron and graphite. C/E varied from 0.51 to 2.36.